| ML20247A665 | |
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|---|---|
| Site: | Hope Creek |
| Issue date: | 06/30/1989 |
| From: | Public Service Enterprise Group |
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| NUDOCS 8909120183 | |
| Download: ML20247A665 (40) | |
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[Table view] Category:TEXT-ENVIRONMENTAL REPORTS [Table view] |
Contents
- 1 Text
- 1.1 SUMMARY
- 1.2 SUMMARY
- 1.3 SUMMARY
- 1.4 SUMMARY
- 2 = e e M E O @ @ @ e 9 9 9 9 9 9 9 e=O 0 0 e
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- 6 8 ese E a e s me w
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HOPE CREEK GENERATING STATION 1989 SEMI-ANNUAL RADIOACTIVE i
EFFLUENT RELEASE REPORT HCGS-7 PS,G DOCKET NO. 50-354 OPERATING LICENSE NO. NPF-57 The Energy People DCO.
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w; HOPE CREEK GENERATING STATION' SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT
.HCGS'RERR .. ,
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DOCKET'NO..50-354
- - OPERATING LICENSE.NO. NPF-57:
O SEPTEMBER 1989 E
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NPF-57 f
l REPORT'NO. HCGS-RERR-7 i, RADIOACTIVE EFFLUENT RELEASE REPORT-JANUARY l - JUNE 30, 1989 l
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HOPE CREEK GENERATING STATIdN.
Public Service Electric and Gas Company n- .
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HOPE CREEK GENERATING STATION RADIOACTIVE EFFLUENT RELEASE REPORT ,
JANUARY - JUNE 1989 )
INTRODUCTION !
This report, HCGS-RERR-7, sammarif.es the releases of radioactive materials in liquid, gasecus and solid form from the Hope Creek Genersting Station (HCGS) for the period January 1, 1989 to June 30, 1989.
The report is prepared in the format of Regulatory Guide 1.21, Appendix B, as required by Specification 6.9.1.7 of the Hope Creek Technical Specifications. Preceding the tables summarizing the gaseous and liquid discharges and solid waste shipaents are our responses to parts A-F of the " Supplemental Information" section of Regulatory Guide 1.21, Appendix B.
As required by Regulatory Guide 1.21, our Technical Specification limits are described in detail within this report along with a summary description of how measurements and
(^N approximations of the total activity discharged were developed.
() To facilitate determination of compliance with 40CFR190 requirements, the following information on electrical output is provided.
HCGS generated 4,006,566 megawatt-hours of electrical energy
( net) during the reporting period.
Results of liquid and gaseous composites analyzed for gross alpha, Sr-89, Sr-90, and Fe-55 for the second quarter of 1989 were not available for inclusion in this report. The results of these composites will be provided in the next Radioactive Effluent Release Report.
The gross alpha, Sr-89, Sr-90, and Fe-55 analyses for the second half of 1988 (refer to RERR-6) have been completed. There was no SR-89, Sr-90, Fe-55 or gross alpha released.
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Part A. PRELIMINARY SUPPLEMENTAL INFORMATION
- 1. 0 - REGULATORY LIMITS .
1.1 Noble Gases Release Limits The dose rate due to radioactive materials' released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
For noble gases: Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin.
In addition, the air dose due to noble gases released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, During any calendar year: Less than or equal to
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10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.
1.2 Iodine, Particulate, and Tritium The dose rate due to radioactive materials released in gaseous effluents from the site to areas at and beyond the site boundary shall be limited to the following:
For Iodine-131, Iodine-133, for tritium, arid for ,
all radionuclides in particulate form with half !
lives greater than 8 days: Less than or equal to 1500 mrems/yr to any organ.
In addition, the dose to a member of the public from iodine-131, from tritium, and from all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from the site to areas at and beyond the site boundary shall be limited to the following:
During any calendar quarter: Less than or equal to 7.5 mrems to any organ and, L During any calendar year: Lers than or equal to
(}
v._,1 15 mtems to any organ. .
h x_,I 1.3 Liquid Effluents Release Limits The concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to'the concentrations specified in 10CFR, Part 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 microcuries per milliliter.
In addition, the dose or dose commitment to a member of the public from radioactive materials in liquid effluents released to unrestricted areas shall be limited:
During any calendar quatter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.
1.4 Total Dose Limit
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(_,) The annual (calendar year) dose or dose commitment to any member of the public, due to releases of radioactivity and radiation, from uranium frael cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ (except the thyroid, which shall be limited to less than or equal to 75 mrems).
2.0 MAXIMUM PERMISSIBLE CONCENTRATIONS (MPP)
Regulatory Guide 1.21 requires that the licensee provide the MPC's used in determining allowable release rates for radioactive releases.
- a. MPC values were not used to determine the maximum release rates for fission gases, iodines, or particulate.
- b. MPC values as stated in 10CFR20, Appendix B, Table II, Column 2 were used for liquids.
- c. MPC value used for dissolved or entrained notle gases was 2E-4 microcuries per milliliter.
s .) 3.0 AVERAGE ENERGY Legulatory Guide 1.21 requires that the licensee provide the average energy of the radionuclides mixture in releases of fission and activation gases, if applicable.
Release limits for the HCGS are not based upon average energy, hence, this section does not apply.
4.0 MEASUREMENTS AND APPROXIMATION OF TOTAL RADIOACTIVITY 4.1 Liquid effluents are monitored in accordance with Table 4.11.1.1.1-1 of the Technical Specifications.
During the period of record, all liquid wastes were routed to the sampling tanks for monitoring prior to release. Technical Specifications require these tanks to be thoroughly mixed before sampling and analysis before any releases are made. Batch releases are defined as releases from equipment drain sample tanks, floor drain sample tanks, detergent drain tanks, and condensate storage tanks. There are no continuous liquid releases for this reporting period.
The preponderant gamma emitting isotopes detected in sampling were Cr-51, Na-24', and 2n-65. Specific
(~T activity from analyses were multiplied by the volume
'_) of effluent discharged to the environment in order to estimate the total liquid activity discharged.
The detection requirements of Table 4.11.1.E.1.-1 of the Technicial Specifications are achieved or exceeded. Isotopes existing at concentra";.ons below the achieved detection limit are treated as not being present.
4.2 Gaseous effluent streams are monitored and sampled in accordance with Table 4.11.2.1.2-1 of the Technical Specifications. The north plant vent (NPV) and south plant vent (SPV) are the final release points for most planned gaseous effluent releases. A small quantity of gaseous effluent will be released via the Filtration, Recirculation, and Ventilation System (FRVS) vent during testing periods. The NPV and SPV are continuously monitored for particulate, iodines, and noble gases; the FRVS is continuously monitored for noble gases. The NPV and SPV have moving i particulate and fixed iodine filters; the FRVS has )
fixed particulate and iodine filters. The filters are changed and analyzed at least weekly when releases are i in progress. The NPV and SPV are sampled monthly for i r^N noble gases and tritium. ~)
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exceeded. Isotopes existing at concentrations below. I the achieved detection limit are treated as not being j present.
Continuous Moce gaseous releases are quantified by routine (monthly) sampling and isotopic analyses of the plant vents. Specific activities for each isotope detected during the routine-sampling are adjusted Luing the radiation monitoring readings to obtain an average concentration for the period. This average concentration is then multiplied by the total vent flow volume for the entire sampling period in order to estimate the normal continuous release of radioactivity through the plant vent.
When monthly noble gas grab samples yielded no detectabics activity, continuous mode releases were quantifia/ >y integrating Radiation Monitoring System readings move background. Noble Gas Isotopic abundances for these integrations were based on the ANSI mix for BWR's. Doses. calculated from this data employed the methods of the Hope Creek ODCM Section
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2.0.
Batch Mode gaseous releases (primary containment purge) are quantified by pre-release sampling and isotopic analyses. Specific activities for each isotope are multiplied by the total purge flow volume in order to estimate the batch release of radioactivity through the plant 'e n t .
4.3 The estimated total error of reported liquid releases is within 25%.
The estimated total error of the reported continuous gaseous releases is within 25% when concentrations exceed detectable levels. This error is due primarily to variability of waste stream flow rates and changes in isotopic distributions of waste streams between sampling periods. The estimated total error of the reported batch gaseous releases is within 25%.
Error estimates for releases where sample activity is below the detectable concentration levels are not included since error estimates at the LLD are net defined.
The estimated total error of reported solid releases ._
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D 5.0 BATCH RELEASES n
Summaries of batch releases of gaseous and liquid effluents are provided in Tables 4A and 4B.
6.0 UNPLANNED RELEASES During this reporting period there were no. unplanned releases.
7.0 MODIFICATION TO PREVIOUS RADIOACTIVE EFFLUENT RELEASE REPORTS
'Our last report (RERR-6) did not include the quarterly gross alpha, Sr-89, Sr-90, and Fe-55 composite data for the fourth quarter of 1989. The composites have since been completed, no.Fe-55, Sr-89, Sr-90 or gross alpha were detected for the fourth quarter. No amendments are needed for-RERR-6.
Pa rt B . GASEOUS EFFLUENTS l
See Summary Tables lA thru 1C.
Part C. LIQUID EFFLUENTS See' Summary Tables'2A and 28.
Pa r t D. SOLID WASTE
~See Summary Tatple'3.
i Part E. RADIOLOGICAL IMPACT ON MAN The calculated individual doses in this section are based on actual locations of nearby residents and farms. The population dose impact is based on historical site specific data i.e., food production, milk production, feed for milch animals, and seafood production.
The doses were calculated using methods described in Regulatory Guide 1.109. Individual doses from batch and continuous releases were calculated using the annual average historic meteorological dispersion coefficients as ;
described in the Offsite Dose Calculation Manual.
Population doses were calculated using the meteorological dispersion coefficients for the six month interval from January through June, 1989.
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i Liquid Pathways Doses to individuals in the population from liquid releases are primarily from the seafood ingestion pathway. The total body dose to an individual was calculated to be 4.04E-01 mrem. The calculated highest organ dose from liquid releases was 9.05E-01 mrem to the liver. The ,
calculated population total body dose was 4.93E+00 person-rem. The calculated average total body dose to the population within fifty miles of the site was 8.26E-04 mrem / person.
Air Pathways The resulting total body and skin doses to an individual
.were calculated to be 4.35E-02 mrem and 9.48E-02 mrem respectively. The highest organ dose due to radiciodines and particulate with half-lives greater than 8 days was 9.36E-06 mrem to the thyroid. The calculated population total body dose was 6.64E-01 person-rem. The calculated hverage total body dose to the population within fifty _j miles of~the site was 1.11C-04 mrem / person. !
Direct Radiation f~
f Direct radiation may be estimated by thermoluminescent dosimetric (TLO) measurements. One method for comparing TLD measurements is by comparison with preoperational data. It shoula te noted tha c the TLDs measure dire: t radiation from both tht Salera and Hope Creek Generating Stations at Artificial Islar.d.
TLD's at onsite location 6 2S-2 and SS-1, which are 0.3 miles and 0.9 miles from the point of origin, averaged 4.9 and 4.0 mrads/ month respectively. The values for stations 2S-2 and SS-1 are within the statistical variation j associated with the preoperational program results.
~
It should be noted that the nearest resident is 3.5 miles away. It can thus be concluded that there was no measurable dose to any offsite location from direct I radiation.
Part F. METEOROLOGICAL DATA Cumulative joint wind frequency distributions by atmospheric stability class at the 300 foot elevation are provided for the first and second quarters of 1989 as Tables 5 and 6. . _
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During the reporting period of January 1, ' 1989 to July 31, 1989 the Hope Creek ODCM was revised. Nevisions to the ODCM were performed in response to the NRC's Technical Evaluation Report.(TER, EGG-PHY-7897) on the Hope Creek ODCM. In'accordance with Hope Crcek Technical Specification 6.14.2 Revision'10 of the'ODCM and an explanation of the revisions is attached.
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. HOPE CREEK GENERATILG'bTATIOh
_d ".1 ~,t, ,. ., . TABLE 1A
' EFFLUENT AhO W STE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1989
- ' GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 1st 2nd -Est. Total Units Quarter Quarter Error%
LA. Fission & Activation Gases
- 1. Total release ci 1.16E+02 5.04E+01
- 2. Average release rate
. for period 'uCi/sec. 1.48E+01 6.41E+00
- 3. Percent of, technical specification limit (T.S. 3.11.2.2(a)) t 1.13E+00 4.92E-01 8.-Iodines-
- 1. Total iodine-131, iodine-133 0.00E+00 0.00E+00
- 2. Average release rate
--- for period uCi/sec. 0.00E+00 0.00E+00
- 3. Percent.or technical
- specification limit g (T.S. 3.11.2.3(a)) % 0.00E+00 0.00E+00 C.-Particulate
- 1. Particulate with half-lives >8 aays Ci 0.00E+t)0 0.00E+00
- 2. Average release rate for period uCi/sec. 0.00E+00 0.00E+00
- 3. Percent of technical specification limit (T.S. 3.11.2.3(a)) % 0.00E+00 0.00E+00
- 4. Gross alpha radioactivity (1) Ci 0.00E+00
~ D. Tritium
- 1. Total release Ci 2.74E+01 1.88E-01
- 2. Average release rate for period uCi/sec. 3.52E+00 2.39E-02
- 3. Percent or technical specification limit (T.S. 3.11.2.3(a)) % 9.76E-03 1.36E-05 i
(1) Alpha analyses for the second quarter are not available for inclusion in this report.
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- / x TABLE IB iEFFLUENT AND WASTE DISPCSAL SEMIANNUAL REPORT'
. : JANUARY'l - JUNE 30, 1989
- - ^" GASEOUS' EFFLUENTS-GROUND LEVEL RELEASES i
CONTINUOUS MODE BATCH MODE lat- 2nd , 1st 2nd Nuclides Released Units Quarter Quarter Quarter- Quarter l1. Fission cases K ryr. con-83m Ci 1.16E+00 5.04E-01
~~
K ryp to r.-85m Ci 1.16E+00 5.04E-01 K ryp ton-87 Ci 4.64E400 2.02E+00 Krypton-88 Ci 4.64E+00 2.02E+00 Krypto'n-89 Ci 3.13E+01 1.36E+01 Xenon-133 Ci 2.32E+00 1.01E+01 Xenon-135 Ci 5.80E+00 2.52E+00 Xenon-135m Ci 5.96E+00 3.02E+00 Xenon-137 -
Ci 3.bOE+01 1.S6E+01 Xenon-138 Ci 2.20E+01 9.58E+00 Total tor period Ci 1.16E+02 5.04E+01
- 2. Iodines Iodine-131 Ci Iodine-133 Ci Iodine-135 Ci Total for period Ci 0.00E+00 0.00E+00
- 3. Particulate (Ha.1.f life >B days)
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Sodium-24 Ci Chromium-51 Ci Mancanese-54 Ci Cobalt-58 Ci Cobalt-60 Ci i Iron-59 Ci Y t t r iun.-8 8 Ci
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Strontium-89 Ci Strontium-90 Ci Zirconium-95 Ci Molybdenum-99 Ci Cesium-137 Ci Cerium-139 Ci Gross Alpha Ci Total For Period C 1, 0.00E+00 0.00E+00
. Tritium j Tritium Ci 2.57E+01 1.88E-Ol 1.60E+00 0.00E+0i
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HOPE CREEK GEhERATING STATION TABLE 1C EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY 1 - JUNE.30, 1989 -
GASEOUS EFFLUENTS-ELEVATED RELEASES-
, There were no elevated releases during this reporting period.
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s_f TABLE 2A l LFFLUENT AND WAdTE vibPUSAL SEM1AhhuAL REPokT JAN?)ARY 1 - JUNb 30, 1989 LIVU10 EFFLUE14TS-duMMAT10N UF ALL RELEAdES.
1st 2nd Units Uuarter Quarter Est. Total i Error, 4 A. F1ssion and activation products
- 1. Total release (not including tritium, gases, alpha) (1) Ci 1.39E-01 1.66E-01 255
- 2. Average diluted concentration during period uCi/ml 2.99E-07 2.20E-07 J. Percent or applicable limit (T.S. 3.11.1.2.(a); 5 1.36E+01 1.36E+01 B. Tritium
- 1. 'lotal release Ci 2.74t+00 6.30E+00 256
- 2. Average diluted concentration 7s auring period uti/mi b. vie-Ub 6.376-ub
- 3. Percent or applicable limit u (N -) '(T.S. 3.11.1.1) 1.95E-01 2.7bE-01 C. Dissolved and entrained noble gases
- 1. Total release C1 J.44E-U4 1.2bE-UJ 256
- 4. Average dilutec concentration during period uCi/mi 7.41E-10 1.67E-09 J. Percent or appilcaole limit t (T.S. 3.11.1.1) 3.71E-04 6.3dt-04 D. Gross alpha radioactivity i
- 1. Total release (2) C1 U.uut+UU l E. Volume at waste release (prior to dilution - batch Release) liters 2.74Etuo 4.6BE+06 2dt F. Volume ot' d11ution water used during entire perlod Jiters 4.64Evue 7.54E+08 2S%
(1) Fe-b5, dr-89, and Sr-90 analyses tor the second quarter are not available for inclusion in this report.
(2) Gross Alpha analyses tor the second quarter are not available for inclusion in this report, n
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~ TABLE 2B EFFLUENT AND KASTE DISPOSAL SEMIANNUAL REPORT JANUARY 1 - JUNE 30, 1989 LIQUID EFFLUENTS CONTINUOUS' MODE BATCH MODE 1st 2nd 1st 2nd Nuclides Released Unit Quarter Quarter Quarter Quarter Antimony-125- Ci 5.82E-05 Cobalt-58 Ci 4.40E-03 1.57E-03 Cobalt-60 Ci 4.61E-03 5.33E-03 Chromium-51 C1 1.87E-02 5.66E-02' Cesium-137 C1 1.80E-07 3.17E-05 Iron-55 Ci 4.93E-03 Iron-59 -
Ci 3.47E-03 4.77E-03 Iodine-131 -
Ci 1.33E-05 Mancanese-54 -
Ci 1.21E-02 1.66E-02 Silver-110m -
Ci 2.41E-05 1.48E-05
__ Sodium-24 -
Ci 8.06E-03 1.76E-(Q Strontium-90 Ci 3.01E-05 Strontium-92 -
' Ci 8.22E-06 1.40E-0T
-Technetium-99m Ci 8.55E-05 1.44E-0T Zinc-65 -
Ci 8.21E-02 8.08E-02 Total ( Abc,ve ) -
Ci 1.39E-01 1.66E-01 Tritium -
Ci 2.74E+00 6.30E+00 Xenon-131m Ci Xenon-133 -
Ci 3.41E-05 1.09E-04 Xenon-135 -
Ci 3.10E-04 1.15E-03 O -
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'Y i HOPE CREEK GENERATING STATION TABLE 3 EFFLUEhT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1989 bOLID WASTE AND IRRADIATED FUEL SHIPf4ENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Not irradiated fuel) 6-month Est. Total
- 1. Type or Waste Units Period Error, t
- a. Spent resins, filters sludges, m3 49.6 evaporator bottoms Ci 4.13E+02 25
- b. Dry compressible waste, m3 24.4 contaminated equipment Ci 3.52E-01 25
- c. Irradiated components, m3 control rods Ci
- d. Others ' Describe) m3
[') Solidified Oil Ci t-
- 2. Estimate of major nuclide composition (For Type A and B waste)
-Resin DAW (Ci) % (Ci) %
Chromium-51 1.38E+01 3.34 2.52E-02 7.15 Mancanese-54 1.72E+01 4.16 3.00E-02 8.52 Iron-55 3.44E+01 8.35 4.31E-02 12.25 Iron-59 3.04E+00 0.74 1.02E-02 2.91 l Cobalt-58 1.15E+00 0.28 7.78E-03 2.21 Cobalt-60 8.13E+00 1.98 3.15E-02 8.96 Nickel-63 6.3dE-ul 0.15 Zinc-65 3.34E+02 80.67 2.14E-01 60.66 Carbon-14 1.41E-04 0.04 Cerium-144 5.05E-01 0.12 6
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'(Continued)
EFFLUENT AND WASTE DISPOSAL' SEMIANNUAL REPORT JANUARY l - JUNE 30, 1989
~ SOLID WASTE AND IRRADIATED FUEL SHIPMENTS
- 3. Solid Waste Disposition Nurnber of Shipments Mode of Transportation Destination 10 Truck Barnwell 1 Truck Richland
- b. ~ IRRADIATED FUEL SHIPMENTS (Disposition)
Nun.ber of Shipments Mode of Transportation Destination O
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. , HOPE CREEK GENERATING STATION tTABLE.'4A' A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT
. JANUARY: 1'-' JUNE 30, 1989
SUMMARY
l SHEET FOR-RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE .
,+
BATCH RELEASES ONLY
- 1. Dates:- January 1, 1989 - March-31,.1989
- 2. ' Type of.. release: Gas
- 3. -Number of releases during.the 1st Quarter: 1
- 4. Total time durationfor all releases of type listed above: 26,310
'5. Maximum duration'.for releases of type listed above: 26,310 minutes'.
6..' Average. duration'for.all releases of type' listed above:
26,310 minutes n
I) 7. Min'imum duration for release of type listed above: 26,310 minutes
- 8. The average stream flow (dilution flow) during the period of
. release: 'N/A
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EFFLUENT AND WASTE. DISPOSAL SEMIANNUAL REPORT JANUARY.1 - JUNE 30, 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED-IN A BATCH MODE-
.q BATCH RELEASES ONLY
- 1. Dates: April'1, . 1989 -~ June 30, 1989 2.- Type of release:- Gas
- 3. Number of . releases during the 2nd Quarter: 0
'1
- 4. Total. time duration for all releases of type listed above: '
.0 minutes-
- 5. Maximum duration-for releases of type listed above:
0 minutes-N' 6.
[d Average duration:for all releases'of type listed above:
0 minutes
- 7. Minimum duration- for release of type listed. above
- 0. minutes 1
- 8. - The average stream flow-(dilution flow) during the period of releases. N/A
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' HOPE CREEK GENERATING' STATION' L1 '
TABLE 4B-O. * ,. ' EFFLUENT AND. HASTE; DISPOSAL SEMIAhNUAL REPORT JANUARY 1 - JUNE 30,: 1989
SUMMARY
' SHEET FOR RADIOACTIVE. EFFLUENTS RELEASED ~
-IN A BATCH MODE '
BATCH: RELEASES ONLY
- 1. LDatest. January'1,.1989 -. March.31,-1989 2.- Type of release: ~ Liquid 3.- Number of releases during the 1st Quarter: 64
- 4. Total ' time duration .for all releases of type listed above:
14,615 minutes;
- 5. Maximum duration for.. releases of type listed above:
924 minutes-6.- Aterage dura' t ion for all releases o'f type listed above:
T s228 minutes k.
. Minimum duration for release of type listed above 17 . 27 minutes
- 8. The average stream flow (dilution flow) during the period of release: .26,'152'gpm l
I ~
s t 1 N---------._.------------------N------ - - - - - - - - - - -
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. HOPE CREEK GENERATING STATION l TABLE 4B
, (Cont'd). ,
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT JANUARY l - JUNE 30, 1989
SUMMARY
SHEET FOR RADIOACTIVE EFFLUENTS RELEASED IN A BATCH MODE BATCH RELEASES ONLY ;
- 1. D4.tes: April 1, 1989 - June 30, 1989 l
- 2. . Type of release: Liquid
- 3. Number of releases during the 2nd Quarter: 99
- 4. Total time duration for all releases of type listed above:
19,025. minutes
- 5. Maximum duration:for releases of type listed above:
'1,0d8 minutes
- 6. . Average duration for all releases of type listed above:
192 minutes 7.- Minimum' duration-for release of' type listed above: 37 minutes
- 8. .The average stream flow (dilution flow) during the period of release: 25,785 gpm I '
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i OFFSITE DOSE CALCULATION MANUAL FOR PUBLIC SERVICE ELECTRIC AND GAS COMPANY j HOPE CREEK GENERATING STATION a.
Q-
-d Revision 10 January 1989 I
Approval: j SORC Chairman: 1.M Date: I!'if9Mtg.# ii-do I 0
. _ _ _ - u- -- - - . - - _
HOPE CREEK GENERATING STATION OFFSITE DOSE CALCULATION MANUAL n.
s_/ TABLE OF CONTENTS INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . I 1.0 LIQUID EFFLUENTS 1.1 Radiation Monitoring Instrumentation and Controls . . . . . . . . . . 2 1.2 Liquid Eftluent Monitor Setpoint Determination . . . . . . . . . . . . . 3 1.2.1 Liquid Effluent Monitors . . . . . . . . 4 1.2.2 Conservative Default Values . . . . . . . 5 1.3 Liquid Effluent Concentration Limits -10 CFR 20 . . . . . . . . . . . . . . . 7 1.4 Liquid Effluent Dose Calculations - 10 CFR 50 . . . . . . . . . . . . 8 1.4.1 Member of the Public Dose -
Liquid Effluents . . . . . . . . . . . . 8
(^N 1.4.2 Simplified Liquid Effluent
(_,) Dose Calculation . . . . . . . . . . . . 10 1.5 Liquid Effluent Dose Projection . . . . . . . . 12 2.0 GASEOUS EFFLUENTS 2.1 Radiation Monitoring Instrumentation and Controls . . . . . . . . . . 13 2.2 Gaseous Effluent Monitor Setpoint Determination . . . . . . . . . . . . . 15 2.2.1 Plant Vent and FRVS Monitors . . . . . . 15 2.2.2 Conservative Default Values . . . . . . . 18 2.3 Gaseous Effluent Instantaneous Dose Rate Calculations - 10 CFR 20 . . . . . . . 19 2.3.1 Site Boundary Dose Rate -
Noble Gases . . . . . . . . . . . . . . . 19 2.3.2 Site Boundary Dose Rate -
Radiciodine and Particulate . . . . . . 21 7s v)
( l
.~ .
t l
.iz l .; }
L 2.4.' Noble Gas Effluent Dose Calculations - 10 CFR 50 . . . . .. . . . . . 24
.I4 2.4.1 UNRESTRICTED AREA Dose -
Noble Gses . . . . . .. . . . . . . . . 24 2.4.2 Simplified Dose Calculation for. Noble Gases . . .. . . . ... . . . 25
.2. 5 Radiciodine and Particulate Dose Calculations - 10 CFR-50 . . . . . . . . . . . . 27
- 2. 5. l' UNRESTRICTED AREA Dose -
Radioiodine and Particulate . - . . . . . 27 2.5.2 Simplified Dose Calculation for Radiciodines and Particulate . . . . . . 29 2.6 Gaseous Effluent Dose Projection . . - . . . . . . 31-3.0 SPECIAL DOSE ANALYSIS 3.1 Doses Due to Activities Inside the SITE BOUNDARY . . .. . . . . . . . . . . . 33 3.2 Doses to-MEMBERS OF THE PUBLIC -
40 CFR 190 .. . . . . . . . . . . . . . . . . . 34 3.2.1 Effluent Dose Calculations . -. . . .. . 35 3.2.2 Direct Exposure Determination . . . . . . 35
' 4.0. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM . . . . 36-4.1 Sampling Program . . . . . .. . . . . . . . . . . 36 4.2 Interlaboratory Comparison Program ... . . . . . 37 TABLES 1-1 Parameters for Liquid Alarm
.Setpoint Determination . . . . . . . . . . . .. 39 1-2 Site Related Ingestion Dose Commitment Factors, Aio . . . . . . . . . . . . 40 1-3 Bioaccumulation Factors (BFi) . . . . . . . . . . 42 2-1 Dose Factors for Noble Gases . . . . . . . . . . 45 2-2 Parameters for Gaseous' Alarm Septoint Determination . . . . . . . . . . . . . 46 2-3 Controlling Locations, Pathways ,
and. Atmospheric Dispersion for Dose Calculations . . . . . . . . . . . .. . . . 47 2-4 Pathway Dose Parameters -
Atmospheric Releases . . . . . . . . . . . . . . 48 s
[: 1
[;
l
/ A-1 Calculation of Effective MPC . . .' . . . . . . . A-4 B-1 Adult Dose Contributions Fish and i:- .
Drinking Water Pathways . . . . . . . . . . .. B-4
, ! C-1 Ef f ective Dose. Factors .
. . . . . . . . . . . . C-5 D-1 Infant Dose Contribution Fraction of Dose . .. D-4 D-2 Fraction of Dose. Contributions by Pathway . . . D-4 APPENDICIES Appendix'A'- Evaluation of Conservative, Default-MPC Value for Liquid Effluents . . . . . . . .. A-1 Appendix B - Technical Basis for Effective Dose Factors - Liquid Radioactive Etfluents . . . . B-1
- Appendix - C '- Technical Basis for Ef f ective Dose Factors - Gaseous Radioactive Effluents . . . . C-1 Appen' dix D - Technical Basis for Effective Dose Parameters - Gaseous Radioactive Effluents... . D-1 Appendix E - Radiological Environmental Monitoring.
' Program - Sample Type, Location and Analysis. . E-1 O
JI
Hope Creek ODCM 1/04/89
-1
' ~
6 -
U '
HOPE' CREEK GENERATING STATION-OFFSITE DOSE CALCULATION MANUAL ~
, INTRODUCTION
.The Hope Creek'Offsite Dose Calculation Manual (ODCM) describes
.the methodology and parameters used'in: 1) the' calculation of
-radioactive. liquid-and gaseous effluent monitoring instrumentation. alarm / trip setpoints; and 2) the calculation of radioactive liquid and g'aseous concentrations, dose. rates and
. cumulative' quarterly and yearly doses.- The methodology stated in
'this manualuis acceptable for use in demonstrating compliance with 10'CFR:20.106, 10 CFR 50, Appendix I and 40 CFR 190.
-More' conservative calculation methods and/or conditions (e.g.,
location anc/or exposure pathways) expected to yield higher
)
computed: doses than appropriate for the maximally exposed person may be assumed in the dose evaluations.
The ODCM will be maintained at the' station for use as a reference guide and training documentaof accepted methodologies and calculations. . Changes will be made to the ODCM calculation methodologies and parameters as is deemed necessary to ensure reasonable conservatism in keeping with the principles of
.10 CFR 50.36a and Appendix I for demonstrating radioactive effluents are ALARA.
NOTE: As used throughout this document, excluding acronyms, words appearing all capitalized denote the application of definitions as used in the Hope Creek Technical Specifications.
O 1 Rev. 10
Hope. Creek ODCM 1/04/89 i.
1.0 Liquid Effluents 1.1 Radiation Monitoring Instrumentation and Controls The liquid effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring normal radioactive material releases in accordance with the Hope Creek Radiological Effluent Technical Specifications are summarized as follows:
- 1) Alarm (and Automatic Termination) - Liquid Radwaste Discharge Line Monitor provides the alarm and automatic termination of liquid (RE4861) radioactive material releases from the liquid waste management system as required by Technical Specification 3.3.7.9.
- 2) Alarm (only) - The Cooling-Tower Blowdown Effluent Monitor (RE8817) provides an Alarm function only for releases into the environment as required bj Technical Specification 3.3.7.9.
Liquid radioactive waste flow diagrams with the-applicable, associated radiation monitoring instrumentation and controls are presented in ]
Figure 1-1.
I k!hI 2 Rev. 10
( .-
Hope Creek ODCM 1/04/89 (m- 1.' 2 Liquid Effluent Monitor Setpoint Determination Per the requirements of Technical Specification 3.3.3.8, alarm setpoints shall be established for the liquid effluent monitoring instrumentation to ensure that the release concentration limits of Specification 3.11.1.1 are met (i.e., the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Column 2, for radionuclides and 2.0E-04 uCi/ml for dissolved or entrained noble gases). The following equation
- must be satisfiec to meet the liquid etfluent restrictions:
C (F + f) f- c< -------------
(1.1) i f
where:
C = the effluent concentration limit of Technical Specification (3.11.1.1) implementing the 10 CFR 20 MPC for the site, in uCi/ml.
c = the setpoint, in uCi/ml, of the radioactivity monitor measuring the radioactivity concentration in the effluent line prior to dilution and subsequent release; the setpoint, represents a value which, if exceeded, would result in concentrations exceeding the limits of 10 CFR 20 in the UNRESTRICTED AREA.
- Adopted from NUREG-0133 i l
3 Rev. 10
Hope Creek ODCM 1/04/89 f = the flow rate at the radiation monitor location, in volume per unit time, but in the same units as F, below F = the dilution water flow rate as measured prior to the release point, in volume per unit time.
[ Note that if no dilution is provided, c 1 C. Also, note that when (F) is large compared to (f), then (F + f) = F.]
1.2.1 Liquid Effluent Monitors The setpoints for the liquid effluent monitors at the Hope Creek Generating Station are determined by the following equation:
MPC e
- CTBD SP 1 -------------
+ bkg (1.2)
RR with:
=C i(1.3)MPCe{(Ci/MPCi) where:SP = alarm setpoint corresponding to the maximum allowable release rate (uCi/ml)MPCe = an effective MPC value for the mixture of radionuclides in the effluent stream (uCi/ml)O' 4 Rev. 10
Hope' Creek?ODCM 1/04/89 y( ). .C1 = the concentration of radionuclides i in-Lthe liquid effluent.(uci/ml)*
- NOTE: The concentration mix ~must include the'most recent composite.of. alpha emmitters,
.Sr-89, Sr-90, Fe-55, and'H-3 as m
per Technical Specification 3.11.1.1.MPCi = the MPC value corresponding to radionuclides i from 10 CFR 20, Appendix B, Table II,' Column 2 (uCi/ml)CTBD = the Cooling-Tower' Blowdown Discharge rate at the time of release (gal / min)RR = the liquid effluent release rate (gal / min) at the monitor location
; -(i.e., at the liquid radwaste monitor or at the CTBD monitor).
bkg = the background of the monitor (uCi/ml) l
-The radioactivity monitor setpoint equation-(1.2) remains valid during. outages when the Cooling-Tower Blowdown discharge is potentially.at its-lowest value. Reduction of .j the waste stream flow (RR) may be necessary ]
during these periods to meet the discharge -criteria. Procedural restrictions prevent 1simultaneous liquid releases.5 Rev. 10 j i1
.._____.__m.. _ _ __ _ _ _ _ _ . _ _ _ _ _ _ _ . . . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _
Hope Creek ODCM 1/04/89 1.2.2 -Conservative Default Values Conservative alarm setpoints may be determined through the use of def ault parameters.Table 1-1 summarizes all current default values in use for Hope Creek.They are based upon the following:a) substitution )f the effective MPC value with a default value of 4.19E-05 uCi/ml for radwaste releases (Refer to Appendix A for justification);b) substitutions of the Cooling-Tower Blowdown discharge rate with the minimum average flow, in gal / min; and, c) substitutions of the effluent release rate with the highest allowed rate, in gal / min.l ,With pre-established alarm setpoints, it is possible to control the radwaste release rate (RR) to ensure the inequality of equation (1.2) is maintained under changing values for MPCe and for differing Cooling-Tower Blowdown discharge.l ll lI!- 6 Rev. 10 4l
Hope Creek.ODCM 1/04/89
+
p pm Liquid Effluent' Concentration Limits -'10 CFR 20
-( ) 1.3 Technical Specification 3.11.l'.1 limits the y concentration of radioactive material in liquid effluents (after dilution-in the Cooling-Tower ,
Blowdown Discharge System) to less.than the concentrations as.specified-in 10 CFR 20,' Appendix B,
. Table II,-Column 2 for radionuclides other than noble.
- gases. Noble gases are limited to a diluted concentration of 2.0E-04 uCi/ml. Release rates are controlled and radiation monitor alarm setpoints are established as addressed above to ensure that these concentration limits'are not exceeded. However, in the event any liquid release results in an alarm-setpoint being exceeded, an evaluation of compliance with'the' concentration limits of Technical Specification 3.11.1.1 may be performed using the
.I) following equation:
[ Ci RR 1 1 (1.4)( MPCi j/ CTBD + RR-where:
= actual concentration of radionuclides i as Ci measured in the undiluted liquid effluent (uCi/ml)
MPCi = the MPC value corresponding to radionuclides i from 10 CFR 20, Appendix B, Table II, Column 2 (uCi/ml)
= 2E-04 uCi/ml for dissolved or entrained noble gases RR = the actual liquid effluent release rate (gal / min)
CTBD = the actual Cooling-Tower Blowdown discharge() at the time of release (gal / min) 7 Rev. 30
Hopa Creek ODCM 1/04/89 1.4 Liquid Erfluent Dose Calculation - 10 CFR 50 1.4.1 MEMBER OF THE PUBLIC Dose - Liquid Effluents Technical Specification 3.11.1.2 limits the dose or dose commitment to MEMBERS OF THE PUBLIC from radioactive materials in liquid effluents from Hope Creek Generating Station to:
- during any calendar quarter:
1 1.5 mrem to total body 15.0 ml:em to any organ
- during any calendar year:
1 3.0 mrem to total body
~< 10.0 mrem to any organ Per the surveillance requirements of Technical O
Specification 4.11.1.2, the following calculation methods may be used for determining the dose or dose commitment due to the liquid radioactive effluents from Hope Creek.8.35E-04 VOL Do = ---------------- *[_(Ci
- Aio) (1.5)
CTBD wheIE:Do
= dose or dose commitment to organ or including total body (mreia) i i
O 8 Rev. 10 ,1 ll
Hope Creek ODCM 1/04/89
.(~~) Aoi = site-related ingestion dose \/ commitment factor to the total l body or any organ o for radionuclides i (mrem /hr per uCi/ml) l Ci = average concentration of '
radionuclides i, in undiluted liquid effluent representative of the volume VOL (uCi/ml)VOL = volume of liquid effluent released (gal)CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min) 8.35E-04 = conversion factor (1.67E-2 hr/ min) and a near tield dilution factor of 0.05 (refer Iy} to Appendix B, Page B-4 for
'l definition).
The site-related ingestion dose / dose commitment factors (Aio) are presented in Table 1-2 and have been derived in accordance with a NUREG-0133 by the equation:Ao i
= 1.14E+05 [(UI
- BIi) + (UF
- BFi)) DFi (1.6) where Aio = composite dose parameter for the total body or critical organ o of an adult for radionuclides i, for the fish and invertebrate ingestion pathways (mrem /hr per uCi/ml) 1.14E5 = conversion factor (pCi/uCi
- ml/kg per hr/yr)
/T UI = adult invertebrate consumption (5 kg/yr)
! V 9 Rev. 10 1.
Hope Creek ODCM 1/04/89 BI i = bioaccumulation factor for radionuclides i in invertebrates from Table 1-3 (pCi/kg per pCi/1)UF = adult fish consumption (21 kg/yr)BFi = bioaccumulation factor for nuclide i in fish from Table 1-4 ~ (pCi/kg per pCi/1)DFi = dose conversion factor for nuclide i for adults in pre-selected organ, o, from Table E-ll of Regulator Guide 1.109 (mrem /pCi)The radionuclides included in the periodic dose assessment per the requirements of {I Technical Specification 3/4.11.1.2 are those as identified by gamma spectral analysis of the liquid waste samples collected and analyzed per the requirements of Technical Specification 3/4.11.1.1, Table 4.11.1.1.1-1. lh Radionuclides requiring radiochemical analysis (e.g., Sr-89 and Sr-90) will be added to the dose analysis at a frequency consistent with the required minimum analysis frequency of Technical Specification Table 4.11.1.1.1-1.W 1.4.2 Simplified Liquid Effluent Dose Calculatio,n ]In lieu of the individual radionuclides dose j assessment as presented in Section 3_4.1, the following simplified dose calculation equation may be used for demonstrating compliance with the dose limits of Technical Specification I3.11.1.2. (Refer to Appendix B for the j iderivation and justification for this l simplified method.) h I10 Rev. 10 1 1
Hopo Creek ODCM l'1/04/89 L~f, .- Total' Body?<" , 1.94E+02-
- VOL
.Dt b = ---------------- *[_Ci (1.7) .CTBD -Maximum Organ 4.28E+02 * .VOL Dmax '" ---------------- *[Ci (1.8)
CTBD where:.Ltb = conservatively evaluated total-body dose.(mrem)- a
'Dmax = conservatively. evaluated maximum-organ dose (mrem)
Ci = average concentration of radionuclides i, in' undiluted liquid
,g- ef fluent represer tative of the k> volume VOL (uCi/ml)
VOL = ' volume of liquid effluent released (gal)'CTBD = average Cooling-Tower Blowdown discharge rate during release period (gal / min) 1.94E+02 = conversion factor (1.67E-2 hr/ min) the conversative total body' dose-conversion factor (Zn-65, total a body -- 2.32E5 mrem /hr per uCi/ml),and the' near field dilution factor of 0.05 (See Appendix B). .-4.28E+02 '= conversion factor (1.67E-2 hr/ min) th9 conservative maximum organ dose )conversion factor (Zn-65, Liver --5.13E5 mrem /hr per uCi/ml), and the ,near field dilution factor of 0.05 )
. s> L (See Appendix B).
11 Rev. 10 'l
)
__1___._________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ ______ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
)
Hopo Creek ODCM 1/04/89 1.5 Liquid Effluent Dose Projections Technical Specification 3.11.1.3 requires that the liquid radioactive waste processing system be used to reduce the radioactive material levels in the liquid waste prior to release when the 31-day projected doses exceed:
- 0.06 mrem to the total body, or 0.2 mrem to any organ.
Tne applicable liquid waste processing system for maintaining radioactive material releases ALARA are the drain filters and deminerializers as delineated in Figure 1-1.Dose projections are made at least once per 31-days by the following equations:31d ODtbp =(Dtb / d) (l*9)Dmaxp * (Dmax / d)
- 31d (1.10) where:
Dtbp = the total body dose projection for current 31-day period (mrem)Dtb = the total body dose to date for current calendar quarter as determined by equation (1.5) or (1.7) (mrem)Dmaxp = the maximum organ dose projection for current 31-day period (mrem)Dmax = the maximum organ dose to date for current calendar quarter as determined by equation (1.5) or (1.8) (mrem) o = .the number of days in current calendar quarter at the end of the release 31d = the number of days of concern f 12 Rev. 10
Hope' Creek ODCM- 1/04/89-l
- /
s 2.0 Gaseous Effluents {2.1 Radiation Monitoring Instrumentation and controls The gaseous effluent monitoring instrumentation and controls at Hope Creek for controlling and monitoring ;normal radioactive material releases in accordance with the Radiological Effluent Technical Specifications are summarized as follows:
- 1) Filtration, Recirculation, and Ventilation System -
LThe FRVS.is' maintained in a standby condition.
-Upon reactor building isolation, the FRVS recirculation system recirculates the reactor building air through HEPA and charcoal filters.
Releases are made to the atmosphere via a reactor building vent or the South Plant Vent depending on
.O mode of operation. Noble gas monitoring is provided by RE-4811A.
- 2) -Soutn Plant Vent - The SPV receives discharge from the radwaste evaporator, reactor building purge, auxiliary building radwaste area, condensate demineralized, pipe chase, feedwater heater, and untreated ventilation sources. Effluents are monitored (for noble gas) by the RE-4875B monitor.-
- 3) North Plant Vent - The NPV receives discharges from the gaseous radwaste treatment system (Offgas system) and untreated ventilation air sources.
Effluents are monitored (for noble gases) by the RE-4573B monitor.i lO 13 Rev. 10
Hopo Creek ODCM ~1/04/89 A gaseous' radioactive waste flow diagrams with the applicable, associated radiation monitoring instrumentation and controls are presented in Figures 2-1 and 2-2.F lO O14 ney, lo
Hope Creek ODCM 1/04/89 Gaseous Effluent Monitor Setpoint Determination( 2.2 2.2.1 Plant Vent and FRVS Vent Monitors Per the requirements of Technical Specification 3.3.3.10, alarm setpoints shall be established for the gaseous effluent monitoring instrumentation to ensure that the release rate of noble gases does not exceed the limits of specification 3.11.2.1, which corresponds to a dose rate at the SITE BOUNDARY of 500 mren/ year to the total body or 3000 mrem / year to the skin. Based on a grab sample analysis of the applicable release (i.e., of FRVS, pipe chase, gaseous radwaste treatment system air, etc.),the radiation monitoring alarm setpoints may be established by the following calculation() method. The measured radionuclides concentrations and release rate are used to calculate the fraction of the allowable release rate, as limited by Specification 3.11.2.1, by the equation:FRAC = [4.72E+02
- X/Q
- VF * (Ci
- Ki)] / 500 (2.1)
FRAC = [4.72E+02
- X/Q
- VF * (Ci *
(Li + 1.1 Mi))) / 3000 (2.2) where:FRAC = fraction of the allowable release rate based on the identitied radionuclides concentrations and lthe release flow rate X/Q = annual average meteorological dispersion to the controlling site boundary location (sec/m3) 15 Rev. 10
Hopo Crook ODCM 1/04/89 VF = ventilation sustem flow rate for the applicable release point and monitor (ft3/ min)Ci = concentration of noble gas radionuclides i as determined by radioanalysis of grab sample (uCi/cm3)Ki = total body dose conversion factor for noble gas radionuclides i (mrem /yr per uCi/m3, from Table 2-1)Li = beta skin dose conversion factor for noble gas radionuclides i (mrem /yr per uCi/m3, from Table 2-1)Mi = gamma air dose conversion factor for noble gas radionuclides i .(mrad /yr per uCi/m3, from Table 2-1) 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad) 4.72E+02 = conversion factor (cm3/ft3
- min /sec) total body dose rate limit j 500 =
I (mrem /yr) !3000 = skin dose rate limit (mrem /yr)I iBased on the more limiting FRAC (i.e., higher )1 value) as determined above, the alarm setpoints for the applicable monitors may be calculated by the equation:SP = [AF * }~ C i / FRAC) + bkg (2.3) i lll 16 Rev. 10 ll
Hopo Croon ODCM 1/04/89(,) where:SP = alarm setpoint corresponding to the maximum allowable release rate (uCi/cc)FRAC = highest fraction of the allowable release rate as determined in equation (2.2) bkg = background of the monitor (uCi/cc)AF = administrative allocation factor for the specific monitor (0.2 NPV, 0.2 SPV, 0.1 FRVS)The allocation factor (AP) is an administrative control imposed to ensure that combined relsases from Salem Units 1 and 2 and Hope Creek will not exceed the regulatory limits on release rate from the site (i.e., the release rate limits of
,s Technical Specification 3.11.2.1). Normally, k_)
the combined AF value for Salem Units 1 and 2 is 0.5 (0.25 per uniti, with the remainder 0.5 allocated to Hope Cr3ek. Any increase in AF above 0.5 for the Hope Creek Generating Station will be coordinated with the Salem Generating Station to ensure that the combined allocation factors for all units do not exceed 1.0.
~ /O 1G I
l 17 Rev. 10 lh
F Hop 3 Creek ODCM 1/04/89 2.2.2 Conservative Default Values A conservative alarm setpoint can be established, in lieu of the individual radionuclides evaluation based on the grab sample analysis, to eliminate the potential of periodically having to adjust the setpoint to reflect minor changes ir radionuclides distribution and variations in release flow rate. The alarm setpoint may be conservatively determined by ti'e default values presented in Table 2-2.These values are based upon:
- the maximum ventilation (or purge) flow rate; - a radionuclides distribution adopted from ANSI N237-1976/ANS 18.1 " Source Term h Specifications", Table 5 and; an administrative allocation factor of 0.5 to cont tvatively ensure that any releases from Hope Creek do not exceed the maximum allowable release rate.
For the noble gas radionuclides distribution from ANSI N237-1976/ANS 18.1 (Note Table C-1), the alarm setpoint based on the total body dose rate is more restrictive than the corresponding setpoint based on the skin dose rate. The resulting conservative, default setpoints are presented in Table 2-2.
- Adopted from ANS1 N237-1976/ANS-18.1, Source Term Specifications, Table 6 9
18 Rev. 10 f
gc , - -ljj ' *s Hope Creek ODCM -1/04/89 yv, .(,/f 2.3 Gaseous Effluent' Instantaneous Dose Rate Calculations -10 CFR 20
~
2.3.1 Site Boundary Dose Rate - Noble Gases
. Technical Specification 3.ll.2.la limits the Ldose rate at the-SITE BOUNDARY due to noble. gas releases to < 500 mrem /yr, total body and < 3000.
L' mrem /yr, skin. Radiation monitor alarm j setpoints are established to ensure that these release limits are not exceeded. 'In the event
~
any gaseous releases'from the station results in
-an alarm setpoint being exceeded, an. evaluation of the SITE BOUNDARY dose rate ~resulting from ,the release may be performed using the following equations:
D t b.= X/Q * { (Ki *.01) (2.4)-and Ds " X/O * [.((Li + 1.lMi)
- Qi). (2.5) where:
Dtb = total body dose rate (mrem /yr)Ds = skin dose rate (mrem /yr)X/0 = atmospheric dispersion to the.controlling SITE BOUNDARY location (sec/m3)Qi = average release rate of radionuclides i over the release period under evaluation (uCi/sec) 19 Rev. 10, ,y aL. '- ' '_______l__.__._..__.__._.._.____...___.
F~Hopa Crco*k ODCM 1/04/89 iKi = total body dose conversion factor _for f noble gas radionuclides i (mrem /yr per uCi/m3, from Table 2-1)Li = beta skin doce conversion factor for noble gas radionuclides 1 (mrem /yr per uCi/m3, from Table 2-1)Mi = -gamma air dose conversion factor for noble gas radionuclides 1 (mrad /yr per uCi/m3, from Table 2-1) 1.1 = mrem skin dose per mrad gamma air dose (mrem / mrad)As appropriate, simultaneous releases from Salem Units 1 and 2 and Hope Creek will be considered in evaluating compliance with the release rate limits of Specification 3.11.2.la, following.any releases exceeding the above prescribed alarm setpoints. Monitor indications (readings) may h; be averaged over a time period not to exceed 15 minutes when determining noble gas release rate based on correlation of the monitor readicg and monitor sensitivity. The 15-minute averaging is l lneeded to allow for reasonable monitor response to potentially changing radioactive material concentrations and to exclude potential electronic spikes in monitor readings that may be unrelated to radioactive material releases.As identified, any electronic spiking monitor responses may be excluded from the analysis.O 20 Rev. 10 11
. ,-= -
F 4) ;d e . Hopo Crock.ODCM 1/04/89 p.f(ik_/E NOTE: ' For administrative: purposes, more
- conservative' alarm setpcints than those as prescribed =above may.be imposed.
However, conditionsfexceeding these more limiting alarm setpoints doLnot necessarily indicate radioactive material,e release rates exceeding the dose limits
- of Technical Specification 3.11.2.14.
Provided actual releases do not result in
. radiation monitor indications exceeding alarm setpoint: values based on the above-criteria, no_further' analyses are required for demonstrating compliance with the limits of Specification 3.11.2.la.
T
/- ,
Actual meteorological conditions concurrent with
\ the release' period or the' default, annual average dispersion parameters'as presented in Table 2-4 may be used for evaluating the gaseous effluent: dose rate.
2.3.2' Site Boundary Dose Rate - Radiciodine'and Particulate Technical Specification 3.11.2.lb limits the dose rate to < 1500 mrem /yr to any organ-for I-131, I-133, tritium and particulate with l half-lives greater than 8 days. To demonstrate compliance with this limit, an evaluation is performed at a frequency no greater than that
.i 21 Rev. 10 mm .-_-__m_.__-_.m.mm_mm.____m_____ ___-__.a __-m . _. .: .-_.-_-.m.___-2 _m.2__-__ __-______m________._-___._-___-___m___-__m m._____c ______2__..___-_m._ .---_____2-_._m_______.m .
Hopa Crook ODCM 1/04/89 corresponding to the sampling and analysis time period (e.g, nominally once per 7 days). The following equation may be used for the dose rate evaluation:Do = X/0 *['(Ri
- Qi)
(2.6) where:Do = average organ dose rate over the sampling time period (mrem /yr)X/O = atmospheric dispersion to the controlling SITS BOUNDARY location for the inhalation pathway (sec/m3)Ri = dose parameter for radionuclides i, (mrem /yr per uCi/m3) for the child inhalation pathway from Table 2-4 01 = average release rate over the appropriate sampling period and analysis frequency for radionuclides i -- I-131, I-133, tritium or other radionuclides in particulate form with half-live greater than 8 days (uCi/sec)By substituting 1500 mrem /yr for Do and solving for Q, an allowable release rate for I-131 can be determined. Based on the annual average meteorological dispersion (See Table 2-3) and the most limiting potentia) pathway, age group and organ (inhalation, child, thyroid -- Ri =1.62E+07 mrem /yr per uCi/m3), the allowable release rate for I-131 is 34.7 uCi/sec.Reducing this release rate by a factor of 2 to O22 Rev. 10
Hope Creek ODCM 1/04/89 ii l-
,,_s )- account for potential dose contributions from other radioactive particulate material and other release points (e.g., Salem), the corresponding release rate allocated to Hope Creek is 17.4 uCi/sec. For a 7-day period, which is the
- nominal sampling and. analysis frequency.for 1
I-131, the cumulative release is 10.5 Ci.Therefore, as long as the I-131 release in any 7-day period do not exceed 10.5 Ci, no additional analyses are needed for veritying compliance with the Technical Specification 3.11.2.1.6 limits on allowable release rate.
. es L.)
23 Rey, 10_2 _ _ _ _ _ - . _ _ )
t 'Hopo Crook ODCM- 1/04/89)2.4 Noble Gas Effluent Dose Calculations - 10 C R 50 2.4.1 UNRESTRICTED AREA Dose - Noble Gases Technical Specification 3.11.2.2 requires a periodic assessment of releases of noble gases to evaluate compliance with the quarterly dose limits of i 5 mrad, gamma-air and i 10 mrad, beta-air and the calendar year limits i 10 mrad, gamma-air and i 20 mrad, beta-air. The limits are applicable separately to each generating station and are not combined site limits. The following equations may be used to calculate the gamma-air and beta-air doses:Dg = 3.17E-08
- X/O * {,(Mi
- 01) (2.7) and Db = 3.17E-08
- X/O * [,(Ni
- Oi) (2.8)
{where: l Dg = air dose due to gamma emmissions for noble gas radionuclides (mrad)Db
= air dose due to beta emissions for noble gas radionuclides (mrad) x/0 = atmospheric dispersion to the controlling SITE BOUNDARY location (sec/m3) 1 l
i Qi = cumulative release of noble gas radionuclides i over the period of interest (uCi) i ll l24 Rev. 10
Hope Creek ODCM 1/04/89 Lrm
'r dose factor due to gamma ) =
s mj Mi .
.issions from noble gas radionuclides 1 (mrad /yr per uCi/m3, from Table 2-1)
Ni = air dose factor due to beta emissions from noble gas radionuclides i (nrad/yr per uCi/m3, Table 2-1) 3.17E-08 = conversion factor (yr/sec) 2.4.2 Simplified, Dose Calculation for Noble Gases In ?ieu of the' individual noble gas radionuclides dose assessment as presented above, the following simplified dose calculation equations may be used for verifying compliance with the dose limits of Technical Specification()7_3.11.2.2. (Refer to Appendix C for the derivation and justification of risis simplified method.)3.17E-08 Dg = -----------
*X/O*Meff*[Qi (2.9) 0.50 and 3.17E-08 Db = -----------
- X/Q
- Negg * [.Qi (2.10) 0.50 C
25 Rev. 10
Hop 3 Creek ODCM 1/04/89 1l iwhere:Megg = 8.lE3, effective gamma-air dose l )factor (mrad /yr per uCi/m3)Negg = 8.5E3, ef fective beta-air dose ,I' factor (mrad /yr per uCi/m3)Qi = cumulative release for all noble gas radionuclides (uCi) 0.50 = conservatism factor to account for ,potential variability in the radionuclides distribution Actual meteorological conditions concurrent with the release period or the default, annual average dispersion parameters as presented in Table 2-3, may be used for the evaluation of the gamma-air and beta-air doses.O O26 Rev. 10
Hope Creek ODCM 1/04/89 pm i s ) 2.5 Radiciodine and Particulate Dose Calculations -10 CFR 50 2.5.1 U, UNRESTRICTED AREA Dose - Radioiodine and Particulate In accordance.with requirements of Technical Specification 3.11.2.3, a periodic assessment shall be performed to evaluate compliance with the ' quarterly dose limit of 1 '/.5 mrem and calendar year limit i 15 mrem to any organ. The following equation may be used to evaluate the maximum organ dose due to release of I-131, (I-133, tritium and particulate with half-lives greater than 8 days:7s Dop=3.17E-08*W*SFp*{(Ri aVi) (2.11) ,L) where:Daop = dose or dose commitment via controlling pathway p and age group a (as identified in Table 2-3) to organ o, including the total body (mrem).W = atmospheric dispersion parameter to the control]!ng location (s) as identified in Table 2-3.X/0 = atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3).D/O = atmospheric deposition for vegetation, milk and ground plane exposure pathways (1/m2).p 27 Rev. 10
_ _ , _ _ _ _ ~ _Hopo Crcek ODCM 1/04/89 Ri = dose factor for radionuclides i, (mrem /yr per uCi/m3) or (m2 - mrem /yr per uCi/sec) from Table 2-4 for each age group a and the applicable pathway p as identified in Table 2-3. Values for Ri were derived in accordance with the methods described in NUREG-0133.Qi = cumulative release over the period of interest for radionuclides i -- I-131 or radioactive material in particulate form with half-life greater than 8 days (uCi).SFp = annual seasonal correction factor to account for the fraction of the year that the applicable exposure pathway does not exist.
- 1) For milk and vegetation exposure k pathways:
= A six month fresh vegetation and grazing season (May through October). = 0.5
- 2) For inhalation and ground plane exposure pathways:
= 1.0 For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway. Only the controlling age group and pathway as identified in Table 2-3 need be evaluated for compliance with Technical Specification 3.11.2.3.
O 26 Rev. 10 j I i
' Hope CreekL0DCM 1/04/89 I J' l o
( ~Simplified Dose Calculation for-Radiciodines and}A) 2 . 5 '. 2
. Particulate i In lieu of'the individual =~ radionuclides (I-131, I-133 and particulate) dose assessment as. l presented above, the following simplified _ dose.
calculation equation'may be used for verifying compliance with the dose limits of' Technical' specification 3.ll.2.3'(Refer toLAppendix D for
.the derivation and' justification of this simplified method).
(2.12)Dmax = 3.17E-08
- W *'SFp
- RI-131 * {,01 where:
3%- Dmax
= maximum organ dose (mrem) i RI-131 = I-131 dose parameter for the thyroid for the identified controlling pathway J = 1.05E12, infant thyroid dose parameter [
with the cow-milk pathway controlling (m2 - mrem /,yr per uCi/sec)W = D/0 for radioiodine, 2.87E-10 1/m2 01 = cumulative release over the period of interest for radionuclides i -- I-131 or radioactive material in particulate form with half-life greater than~8 days (uC3) _ i Ig 29 Rev. 10 e_L__________________ -
Hop 3 Creek ODCM 1/04/89 The location of exposure pathways and the maximum organ dose calculation may be based on h'the available pathways in the surrounding environment of Hope Creek as identified by the annual land-use census (Technical Specification 3.12.2). Otherwise, the dose will be evaluated based on the predetermined controlling pathways as identified in Table 2-3.4 ll 30 Rev. 10
Hope Creek ODCM 1/04/89
,\ '2.6 Gaseous Effluent Dose Projection Technical Specification 3.11.2.4 requires that the VENTILATION EXHAUST TREATMENT SYSTEM be used'to reduce radioactive material levels prior to discharg4 when projected doses in 31-days exceed: - 0.2 mrad to air from gamma radiation, or - 0.4 mrad to air from beta radiation, or 0.3 mrem to any organ of a MEMBER OF THE PUBLIC The applicable gaseous processing systems for maintaining radioactive material releases ALARA are the Gaseous Radwaste Treatment System and Exhaust Treatment System as delineated in Figures 2-1 and 2-2.
Dose projection are performed at least once per 31-days qk_/ by tiie following equations:Dgp =(Dg / d)
- 31d (2.17)
Dbp =(Db / d)
- 31d, (2.18)
Dmaxp =(Dmax / d)
- 31d (2.19) where:
D gp = gamma air dose projection for current 31-day period (tarad )Dg a gamma air dose to date for current calendar quarter as determined by equation (2.7) or (2.9) (mrad)Dbp = beta air dose projection for current 31-day period (mrad)Db
= beta air dose to date for current calendar quarter as determined by equation (2.8) or l ,-; (2.10) (mrad) \
l l tl 31 Rev. 10_ r
1 Hopo Creek ODCM 1/04/89 '4 Dmaxp = maximum organ dose projection for current h 31-day period (mrem)Dmax
= maximum organ dose to date for current calendar quarter as determined by equation (2.11) or (2.12) (mrem) d = number of days in current calendar quarter at the end of the release 31d = the number of days of concern O
O 32 Rev. 10
Hopa Creek ODCM 1/04/89
- (_,) 3.0 Special Dose Analysis 3.1 Doses Due to Activities Inside the SITE BOUNDARY In accordance with Technical Specification 6.9.1.7, the Radioactive Effluent Release Report (RERR) submitted within 60-days after January 1st of each year shall include an assessment of radiation doses from radioactive Jiquid and gaseous effluents to MEMBERS OF THE PUBLIC due to their activities inside the SITE BOUNDARY.
There is one location on Artificial Island that is accessible to MEMBERS OF THE PUBLIC for activities unrelated to PSE&G operational and support activities.This location is the Second Sun (visitor's center) f~s located near the contractors gate in the Salem k_,) Generat'ing Station.The calculation methods as presented in Sections 2.4 and 2.5 may be used for determining the maximum potential dose to a MEMBER OF THE PUBLIC based on the parameters from Table 2-3 and 2-hours per visit per year. The defau3t value for the meteorological dispersion data as presented in Table 2-3 may be used if current year meteorology is unavailable at the time of NRC reporting. However, a follow-up evaluation shall be performed when the data becomes available.r' 33 Rev. 10
Hopo Crook ODCM 1/04/B9 3.2 Total Dose to MEMBERS OF THE PUBLIC - 40 CFR 190 The Radioactive Effluent Release Report ( RERR')submitted within 60-days after January 1st of each year shall also include an assessment of the radiation dose to the likely most exposed MEMBER OF THE PUBLIC for reactor releases and other nearby uranium fuel cycle sources (including dose contribution from effluents and direct radiation from on-site sources). For the likely most exposed MEMBER OF THE PUBLIC in the vicinity of Artificial Island, the sources of exposure need only consider the Salem Generating Station and the Hope Creek Generating Station: No other fuel cycle facilities contribute to the MEMBER OF THE PUBLIC dose for the Artificial Island vicinity.The dose contribution from the operation of Hope Creek Generating Station will be estimated based on the h methods as presented in the Hope Creek Offsite Dose Calculation Manual (HCGS ODCM).As appropriate for demonstrating / evaluating compliance with the limits of Technical Specification 3.11.4 (40 CFR 190), the results of the environmental monitoring program may be used for providing data on actual measured levels of radioactive material in the actual pathways of exposure.l li il llk l34 Rev. 10 ll l
l[ Hope Creek ODCM 1/04/89! 3.2.1 Effluent Dose Calculations
/"~\ For purposes of implemkDting the surveillance -' requirements of Technical Specification 3/4.11.4 l and the reporting requirements of 6.9.1.11 (RERR), dose calculations for the Hope Creek Generating Station may be performed using the calculation methods contained within the ODCM; l the conservative controlling pathways and locations of Table 2-4 or the actual pathways and locations as identified by the land use census (Technical Specification 3/4.12.2) may be used. Average annual meteorological dispersion paranwters or meteorological conditions concurrent with the release period under evaluation may be used.
3.2.2 Direct Exposure Dose' Determination Any potentially significant direct exposure()
\~
contribution to off-site individual doses may be svaluated based on the results of the environmental measurements (e.g., TLD, ion chamber measurements) and/or by the use of a radiation transport and shielding calculation method. Only during a typical conditions will there exist any potential for significant on-site sources at Hope Creek that would yield potentially significant off-site doses (i.e., in excess of 1 mrem per year to a MEMBER OF THE PUBLIC), that would require detailed evaluation for demonstrating compliance with 40 CFR 190.However, should a situation exist whereby the direct exposure contribution is potentially significant, on-site measurements, off-site measurements and/or calculational techniques will be used for determination of dose for assessing 40 CFR 190 compliance.{35 Rev. 10
Hopo Crook ODCM 1/04/89 l4.0 Radiological Environmental Monitoring Program 4.1 Sampling Program The operational phase of the Radiological Environmental Monitoring Program (REMP) is conducted in accordance with the requirements of Appendix A Technical Specification 3.12. The objectives of the program are:
- To determine whether any significant increases occur in the concentration of radionuclides in the critical pathways of exposure in the vicinity of Artificial Island; - To determine if the operation of the Hopo Creek Generating Station has resulted la any increase in the inventory of long lived radionuclides in the environment; h - To detect any enanges in the ambient gamma radiation levels; and - To verify that HCGS operations have no detrimental effects on the health and safety of the public or on the environment.
The sampling requirements (type of samples, collection frequency and analysis) and sample locations are presented in Appendix E.O 36 Rev. 10
Hope Creek ODCM 1/04/89
,a Interlaboratory Comparison Program
(_) 4.2 Technical Specification 3.12.3 requires analyses be performed on radioactive material supplied as part of an Interlaboratory Comparison.Participation in an approved Interlaboratory Comparison Program provides a check on the precisness of measurements of radioactive materials in environmental samples. A summary of the Interlaboratory Comparison Program results will be provided in the Annual Radiological Environmental Operating Report pursant to Technical Specification 6.9.1.7.im .(. -1 37 Rev. 10
Hope Creek ODCM 1/04/89 1FIGURE l-1 LIQUID RADWASTE TREATMENT SYSTEM Cooling Tower --Basin y Collector Tanks (2) !
-jp Equipment Equipment Equipment j Surge ' Eg O
Drain Filter O-) Drain Demineralized p Drain Sample Tanks (2)
) p l 1 -iP Tank 9r Condensate Storage -- l Tank Jk n
JE O Floor Floor Floor Floor p Drain Collector g Drain Filter
-IL) Drain ,
Demineralized
-g Drain Sample -g I I Tanks (2) Tanks (2)
- p. Vapor to Chemical Decontamination South Vent
----) Waste Tank ) Solution Evaporator b Sottoms to Solid Waste Detergent Detergent q Drain Tanks (2)
Drain Filter p *
"h RE Logged: RE = Effluent Radiation Monitor RE 3 8817_f 5
To Delawam River (offsi e) 38 Rev. 10
1 9 &e'g, o S'v Q ,b%t R% IMAGE EVALUATION ////g /
;/o//7/\}l' $r TEST TARGET (MT-3) $
1 V<>+ <<%#1'0 MH 2
$c u:m gaa=
l,l I
- kN 1.8 1.25 1.4 1.6 4 150mm >
< 6" >
b[?, m,*%, /$
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. . l 1
b i Hope Crock ODCM 1/04/89 TABLE l-1 PARAMETERS FOR LIQUID ALARM SETPOINT DETERMINATION Actual Default P;rameter Value Value Units Comments MPCe Calculated 4.19E-5 uCi/ml Calculated for each batch to be released
'MPC I-131 3.0E-08 N/A uCi/ml I-131 MPC conservatively used for HC CTBD and liquid radwaste monitor setpoints RCi Measured N/A uCi/ml Taken from gamma cpectral analysis of liquid effluent As N/A uCi/ml Taken from 10 CFR 20, MPCi Determined Appendix B, Table II, Column 2 CTCD As 1.20E4 gpm Cooling tower blowdown Determined discharge RR As 176 gpm or Determined prior to Determined 1300 gpm (CST) release; release rate can be adjusted for Technical Specification compliance SP A) RE4861 Calculated 2.86E-03 uCi/ml Default alarm setpoints; more conservative values RE8817 Calculated 4.19E-05 uCi/ml may be used as deemed appropriate and desirable for ensuring regulatory compliance and for maintaining releases ALARA B) RE4861 Calculated 3.87E-04 uCi/ml These setpoints are for condensate storage tank RE8817 Calculated 4.19E-05 uCi/ml releases 39 Rev. 10
, Hope' Creek ODCM. 1/04/89 TABLE 1-2 SITE REUGED INGESTICN DOSE OC2MI' DENT FACIOR, Ait +
(FISH AND INVEEEEBRA2E 0]NSLMPrION)(MRD Vhr per uCi/ml)Page 1 of 2 NUCLIDE Bone Liver Total Body Thyroid Kidney Lurg GI-LLI H-3 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 2.82E-1 C-14 1.45E+4 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+3 2.90E+5
'NA-24 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.57E-1 4.67E-1 4.57E-1 P-32 4.69E+6 2.91E+5 1.81E+5 --- '-- -
5.27E+5 CR-51 --- -5.58E+0 3.34E+0 1.23E+0 7.40E+0 1.40E+3 MN-54 -7.06E+3 1.35E+3 ---2.10E+3 2.16E+4 MN-56 ---1.78E+2 3.15E+1 ----2.26E+2 -5.67E+3 FE-55 5.11E+4 3.53E+4 8.23E+3 ---1.97E+4 2.03E+4 FE-59 8.06E+4 1.90E+5 7.27E+4 --- ---5.30Er4 6.32E+5 CO-58 -6.03E+2 1.35E+3 --- -- - - - -1.22E+4 C0-57 -1.42E+2 2.46E+2 --- - --3.59E+4-
- CD-60 -
1.73E+3 3.82E&3 - -- ----3.25E+4 NI-63. 4.96E+4 3.44E+3 1.67E+3 - -- .- 7.18E+2 NI-65 2.02E+2 2.62E+1 1.20E+1 --- -- ----6.65E+2 CU-64 - - - 2,14E+2 1.01Et2 -5.40E+2 ---1.83E+4
,r -ZN-65 1.61E+5 '5.13E+5 2.32E+5 3.43E+5 -
3.23E+5
% ZN-69 3.43E+2 6.56E+2 4.56E+1 -
4.26E+2 -9.85E+1
'BR-82 -- -
4.07E+0 -- -. -4.67E40 BR-83 ----7.25E-2 -- -1.045-1
'BR-84 ---- -
9.39E-2 --- -- ---7.37E-7 BR-85 -3.86E-3 --- ---- ---RB-86 -6.25E+2 2.91E+2 - --1.23E+2 RB-88 1.79E+0 9.49E-1 - - - -- - - -2.47E-11 RB-89 -1.19E+0 8.34E-1 -- -6.89E-14 SR-89 4.99E+3 -1.43E+2 - ----8.00E+2 SR-90 1.23E+5 3.01E+4 --- --- ---3.55E+3 SR-91 9.18E+1 3.?)E+0 - -4.37E+2 SR-D2 3.48E+1 -1.5.2+0 -- - -6.90E+2 Y-90 6.06E+0 1.62E-1 - -- ----6.42E+4 Y-91m 5.72E+2 2.22E-3 - - - - --- ---1.68E-1 Y-91 8.88E+1 -2.37E+0 - --- ----4.89E+4 Y-92 5.12E-1 -1.56E-2 --- --- -9.32E+3 Y-93 1.69E+0 -4.66E-2 -- -- ----5.35E+4 ZR-95 1.59E+1 5.llE+0 3.46E+0 ---8.02E+0 ---1.62E+4 ZR-97 8.81E-1 1.78E-3 8.12E-2 2.68E-1 -5.blE+4 NB-95 4.47E+2 2.49E+2- 1.34E+2 -2.46E+2 ----1.51E+6 NB-97 3.75E+0 9.49E-1 3.46E-1 -1.11E+0 ----3.50E+3 MO-99 1.28E+2 2.43E+1 2.89E+2 - -2.96E+2
'IC-99m 1.29E-2 3.65E-2 4.66E-1 -- 5.56E-1 1.79E-2 2.17E+1 TC-101 1.33E-2 1.92E-2 1.88E-1 --- 3.46E-1 9.81E-3 5.77E-14 40 Rev. 10
l Hope Creek ODCM 1/04/89 lTAB m 1-2 SITE REIA7ED ItGCSTION DOSE ODPMI1 MENT FACIOR, Ait l (FISH AND INVERIERATE CONSLMPI' ION) l (MRDVhr per uCi/al)Page 2 of 2 NUCLIDE Bone Liver Total Body Thyroid Kidney M GI-LLI RU-103 1.07E+2 ---4.60E+1 -4.07E+2 -1.2SE+4 RU-lCS 8.89EW 3.51E+0 ---1.15E+2 -5.44E+3 RU-106 1.59E+3 2.01E+2 -3.06E+3 -1.03E+5 RH-103m RH-106 AG-110m 1.56E+3 1.45E+3 8.6CE+2 2.85E+3 -5.91E+5 SB-124 2.77E+2 5.23E+0 1.10E+2 6.71E-1 - --2.15E+2 7.86E+3 SE-125 1.77E+2 1.98E+0 4.21E+1 1.80E-1 1.36E+2 1.95S+3 <TE-125m 2.17E+2 7.86E+1 2.91E+1 6.52E+1 8.82E+2 - - - -8.66E+2 TE-127m 5.48E+2 1.96E+2 6.6BE+1 1.40E+2 2.23E+3 -3.84E+:'TE-127 8.90E+0 3.20E+0 1.33E+0 6.60E+0 3.63E+1 7.03E+2 TE-129m 9.31E+2 3.47E+2 1.47E+2 3.'20E+2 3.39E+3 --4.69E+3 TE-129 2.54E+0 9.55E-1 6.19E-1 1.95E+0 1.07E+1 -1.92E+0 TE-131m 1.40E+2 6.85E+1 5.71E+1 1.08E+2 6.94E+2 - - - -6.80Et3 TE-131 1.59E+0 6.66E-1 5.03E-1 1.31E+0 6.99E+0 -2.26E-1 TE-132 2.04E+2 1.32E+2 1.24E+2 1.46E+2 1.27E+3 ---6.24E+3 'I-130 3.96E+1 1.17E+2 4.61E+1 9.91E+3 1.82E+2 1.01E+2 I-131 2.1C+2 3.12E+2 1.792+2 1.02E+5 5.35E+2 -8.23E+1 I-132 1.06E+1 2.85E+1 9.96E+0 9.96E+2 4.54E+1 -5.35E+0 I-133 7.45E+1 1.30E+2 3.95E+1 1.90E+4 2.26E+2 -1.16E+2 I-134 5.56E+0 1.51E+1 5.40E+0 2.62E+2 2.40E+1 1.32E-2 1-135 2.32E+1 6.08E+1 2.24E+1 4.01E+3 9.75E+1 -- -6.87E+1 CS-134 6.84EF3 1.63E+4 1.33E44 5.27E+3 1.75E+3 2.85E+2 CS-136 7.16E+2 2.83E+3 2.04E+3 1.57E+3 2.16E+2 3.21E+2 CS-137 8.77E+3 1.20E+4 7.85E+3 4.07E+3 1.35E+3 2.32E+2 CS-138 6.07E+0 1.20E+1 5.94E+0 -8.81E+0 B.70E-1 5.11E-5 BA-139 7.85E+0 5.59E-3 2.30E-1 --5.23E-3 3.17E-3 1.39F+1 BA-140 1.61E+3 2.06E+0 1.08E+2 7.02E-1 1.18E+0 3.38E+3 BA-141 3.81E+0 2.88E-3 1.29E-1 -- 2.68E-3 1.63E-3 1.80E-9 BA-142 1.72E+0 1.77E-3 1.08E-1 -1.50E-3 1.00E-3 2.43E-18 LA-140 1.57E+0 7.94E -1 2.10E-1 ---5.83E+4 IA-142 8.06E-2 3.67E-2 9.13E-3 ---- 2.68E+2 CE-141 3.43E+0 2.32E+0 2.63E-1 1.08E+0 8.86E+3 CE-143 6.04E-1 4.46E+2 4.94E-2 --- 1.96E-1 --1.67E+4 CE-144 1.79E+2 7.47E+1 9.59E+0 -4.43E+1 6.04E+4 PR-143 5.79E+0 2.32E+0 2.87E-1 -1.34E+0 2.54E+4 TR-144 1.90E-2 7.87E-3 9.64E-4 --- 4.44E-3 - 2.73E-9 ND-147 3.96Er0 4.58E+0 2.74E-1 2.68E+0 ----2.20E+W-187 9.16E+0 7.66E+0 2.68E+0 - 2.51E+3 NP-239 3.53E-2 3.47E-3 1.91E-3 1.0SE-2 7.llE+2 41 huv. 10
p Hope Creek ODCM 1/04/09 TABLE 1-3 L( ^BIOACCUMULATION FACTORS l' .(pci/kg' pet pCi/ liter)*ELEMENT SALTWATER FISH SALTWATER INVERTEBRATES l- 'H 9.0E-01 9.3E-01 "C- 1.8E+03 1.4E+03 NA- 6.7E-02 1.9E-01
-P -3.0E+03 3.0E+04 l' CR 4.0E+02- 2.0E+03 MN 5.5E+02 4.0E+02 L. FE. '3.0E+03 2.0E+04 Co. 1.0E+02 1.0E+03-NI- 1.0E+02 2.5E+02 'CU 6.7E+02 1.7E+03 ZN 2.0E+03 5.0E+04 BR 1.5E-02 3.lE+00 L RB 8.3E+00 1.7E+01 SR 2.0E+00 2.0E+01 Y 2.5E+01 1.0E+03 ZR 2.0E+02 8.0E+01 NB' 3.0E+04 1.0E+02 L MO -1.0E+01 1.0E+01 TC 1.0E+01 5.0E+01
[ ' RU 3.0E+00 1.0E+03 RH -1.0E+01 2.0E+03, AG 3.3E+03 3.3E+03 l Sb 4.0E+01 5.4E+00-
'TE 1.0E+01 'l.0E+02 l ~I 1.0E+01 5.0E+01 l CS 4.0E+01 2.5E+02 L
BA 1.0E+01 1.0E402 LA 2.5E+01 1.0E+03 L CE 1.0E+01 6.0E+02 PR 2.5E+01 1.0E+03 ND 2.5E+01 1.0E+03 W 3.0E+01 3.0E+01 NP 1.0E+01 1.0E+01 m
- Values in this table are taken from Regulatory Guide 1.109 except i for phosphurus (fish) which is adapted from NUREG/CR-1336 and
. silver and antimony which are taken from UCRL 50564, Rev. 1, October 1972.
l 42 ,Rev. 10 l u_______________ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ l
i Hope Creek ODCM 1/04/B9 fl l FIGURE 2-1 lGASEOUS RADWASTE TREATMENT SYSTEM lMain or Auxiliary Steam SJAE Iq Offgas -Reco:abiner Preheater Recombiner Condenser Condenser Offgas Typical of 2 Recombiner Packages L__ .__ .___J Holdup Pipes I Guard l Cooler Rehester -Condenser Bed il To North - HEPA Filter - Absorber Plant Vent Train (Figure 2-2) ;Ambient Charcoal System ll l 1 l1 l1 1 0 43 Rev. 10 a________
Hope Creek ODCM' 1/04/89 j l.
,. FIGURE.2-2 VENTILATION EXHAUST TREATMENT SYSTEM L
l LRE*
~ Gaseous Radwaste RE Treatment-System 4573B (f rom Figure 2-1) North Plant E Vent lj Untreated Ventilation Air Sources Radwaste Decon.'
Evaporator Reactor' Building R H
. Purge Air:
(Typ. of 3)RE Auxiliary Building 4875B
,Radwaste Area R H South Ventilation Air- Plant (Typ. of 3) Vent
( ) Condensate Demineralized' Room Air Pipe Chase Air' R H C H Feedwater Heater Room Air
. Untreated Ventilation Air Sources (Recirculation) RE _
48;.lA FRVS 1 Reactor H C H C H System Vent Building Air .(Typ. of 6) (Typ. of 2)Legend: R = Roughing Filter C = Charcoal Filter j H = HEPA Filter RE = Effluent Radiation Monitor L\~ * -- This Foot-Treatment Monitor is not an effluent monitor as designatad by the RETS.44 Rev. 10 -;l
=_- _ _ _ _ - _ _ - _ - ._ I
1 Hopa Creek ODCM 1/04/89 TABLE 2-1 DOSE PACTORS FOR NOBLE GASES 9 lJ Total Body Skin Gamma Air Beta Air Dose Factor Dose Factor Dose Factor Dose Factor Ki Li Mi
- Ni (mrem /yr per (mrem /yr per (mrad /yr per (mrad /yr per Rcdionuclide uCi/m3) uCi/m3) uCi/m3) uCi/m3)
Kr-83m 7.56E-02 --------1.93E401 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.56E 04 7.29E+03 1.63E+04 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.11E+Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 Xa-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04 Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 ll l45 Rev. 10 w_-__ _
i Hope Creek.ODCM 1/04/89 i
.i!!. ' TABLE 2-2 t .. 4 r . PARAMETERS POR GASEOUS ALARM SETPOINT DETERMINATION HOPE CREEK f l-I. i Actual Default
! Parameter Value Value Units Comments q X/Q_ ' . Calculated 2.67E-6 sec/m3 From FSAR Table 2.3-31 O.S. mile, N 1 VF (NPV) Measured 41900 ft /3 min Maximum Operation VP.(SPV) Measured 440,180 ft /3 min Maximum Operation VF (FRVS) Measured 9000 ft /3 min Maximum Operation AF.(NPV) Coordinated 0.2 Unitiess Administrative with SGS allocation factor-
~
co ensure releases AF,(SPV)' O.2 Unitless do not exceed release rate limit
-AF (FRVS)- 0.1 Unitiess j
( Ci Measured N/A uCi/cm3 Ki Nuclide N/A (mrem /yr Table 2-1 Specific per uCi/m3)Li Nuclide N/A (mrem /yr Table 2-1 Specific per uCi/m 3)
.Mi- Nuclide N/A (mrad /yr Table 2-1 i Specific per uCi/m3) 8 Sv: NPV Calculated 2.43E-4 uCi/cc Def ault alarm SPV Calculated 2.31E-5 uCi/cc Setpoints; more FRVS Calculated 5.56E-4 uCi/cc conservative values may he used as deemed appropriate for ensuring ALARA and regulatory compliance Sv(0) NPV Calculated 4.8C3 uCi/sec Determined by SPV Calculated 4.8E3 uCi/sec multiplying setpoint FRVS Calculated 2.4E3 uCi/sec (uCi/cc) times vent flow rates (cc/sec)
O 46 Rev. 10
Hope Creek ODCM 1/04/89 TABLE 2-3 CONTROLLING LOCATIONS, PATHWAYS AND ATOMSPHERIC DISPERSION POR DOSE CALCULATIONS
- Controlling X/O D/Q Tech. Spec. Location Pathway (s) Age Group (sec/m3) (1/m2) 3.11.2.la Site Boundary Noble Gases N/A 2.67E-06 N/A (0.5 Mile, N) direct exposure 3.11.2.lb Site Boundary Inhalation Child 2.67E-06 N/A (0.5 Mile, N) 3.11.2.2 Site Boundary Gamma-Air N/A 2.67E-06 N/A (0.5 Mile, N) Beta-Air 3.11.2.3 Residence / Dairy milk and Infant 7.2E-08 2.87E-10 (4.9 Miles, W) ground plane 6.9.1.7 Second Sun direct exposure N/A 8.22E-06 N/A (0.21 Miles, SE) and inhaltion
- The identified controlling locations, pathways and atmospheric dispersion are from the Artificial Island Radiological Monitoring Program and the Hope Creek FSAR.
i ti l l O' i 47 Rev. 10 ll f ;
Hopa Creek ODCM 1/04/89 TABLE 2-4 PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - ADULT
.(aren/yr per uCi/m3)
Nuclide Bone Liver Thyroid Kidney Luno GI-LLI Total Body H-3 -----1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 1.26E+3 C-14 1.82E+4 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 3.41E+3 P-32 1.32E+6 7.71E+4 ----- ----- -----8.64E+4 5.01E+4 Cr-51 ----- -----5.95E+1 2.2BE+1 1.44E+4 3.32E+3 1.00E+2 Mn-54 -----3.96E+4 -----9.84E+3 1.40E+6 7.74E+4 6.3CE+3 Fe-55 2.46E*4 1.70E+4 ----- -----7.21E+4 6.03Et3 3.94E+3.Fe-59 1. 3.8 E4 4 2.78E+4 ----- -----1.02E+6 1.88E+5- 1.06E+4 Co-57 -----6.92E+2 ----- -----3.70E+5 3.14E+4 6.71E+2 Co-58 -----1.58E+3 ----- -----9.28E+5 1.06E+5 2.07E+3 Co-60 -----1.15E+4 ----- -----5.97E+6 2.85E+5 1.48E+4 Ni-63 4.32E+5 3.14E+4 ----- -----1.78E+5 1.34E+4 1.45E+4 Zn-65 3.24E+4 1.03E+5 -----6.90E+4 8.64E+5 5.34E+4 4.66E+4 Rb-86 -----1.35E+5 ----- ----- -----1.66E+4 5.90E+4
-Sr-89 3.04E+5 ----- ----- -----
1.40E+6 3.50E+5 8.72E+3 Sr-90 9.92E+7 ----- ----- -----9.60E+6 7.22E+5 6.10Ev6 Y-91 4.62E+5 ----- ----- -----1.70E+6 3.85E+5 1.24E+4 I 1.07E+5 3.44E+4 5.42E+4 1.77E+6 Zr-95 -----1.50E+5 2.33E+4 Nb-95 1.41E+4 7.82E+3 -----7.74E+3 5.05E+5 1.04E+5 4.21E+3 Ru-103 1.53E+3 ----- -----5.83E+3 5.05E+5 1.10E+5 6.58Ev2 Ru-106 6.91E+4 ----- -----1.34E+5 9.36E+6 9.12E+5 8.72E+3 Ag-110m 1.08E+4 1.00E+4 -----1.97E+4 4.63E+6 3.02E+5 5.94E+3 Sb-124 3.12E+4 5.89E+2 7.55E+1 -----2.48Ev6 4.06E+5 1.24E+4.Sb-125 5.34E+4 5.95E+2 5.40E+1 -----1.74E+6 1.01E+5 1.26E+4 Te-125m 3.42E+3 1.58E+3 1.05E+3 1.24E+4 3.14E+5 7.06E+4 4.67E+2 Te-127m 1.26E+4 5.77E+3 3.29E+3 4.58E+4 9.60E+5 1.50E&5 1.57E+3 Te-129m 9.76E+3 4.67E+3 3.44E+3 3.66E+4 1.16E+6 3.83E+5 1.58E+3 I-131 2.52E+4 3.58E+4 1.19E+7 6.13E+4 -----6.28E+3 2.05E+4 I-133 8.64E+3 1.48E+4 2.15E+6 2.58E+4 -----8.88E+3 4.52E+3 lCs-134 3.73E+5 8.48Et5 ------2.87E+5 9.76E+4 1.04E+4 7.28E+5 Cs-136 3.90E+4 1.46E+5 -----8.56E+4 1.20E+4 1.17E+4 1.10E+5 Cs-137 4.78E+5 6.21E+5 -----2.22E+5 7.52E+4 8.40E+3 4.26E+5 Ba-140 3.90E+4 4.90E+1 -----1.67E+1 1.27E+6 2.18E+5 2.573+3 Ce-141 1.99E+4 1.35E+4 -----6.26E+3 3.62E+5 1.20E+5 1.53E+3 Ce-144 3.43E+6 1.43E+6 -----8.48E+5 7.78E+6 8.16E+5 1.84E+5 Pr-143 9.36E+3 3.75E+3 -----2.16E+3 2.81E+5 2.00E+5 4.64E+2 Nd-147 5.27E+3 6.10E+3 -----3.56E+3 2.21E+5 1.73E+5 3.65E+2 48 Rev. 10
Hopa Crock ODCM 1/04/89 TABLE 2-4 (Con't)PATFWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) INHALATION PATHWAY FACTORS - TEENAGER (arem/yr per uCi/m3)Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body H-3 -----1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 1.27E+3 C-14 2.60E+4 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 4.87E+3 P-32 1.89E+6 1.10E+5 ----- ----- -----9.28E+4 7.16E+4 Cr-51 ----- -----7.50E+1 3.07E+1 2.10E+4 3.00E+3 1.35E+2 Mn-54 ----- 5.llE+4 ----- 1.27E+4 1.98E+6 6.68E+4 8.40E+3 Fe-55 3.34E+4 2.38E+4 ----- -----1.24E+5 6.39E+3 5.54E+3 Fe-59 1.59E+4 3.70E+4 ----- -----1.53E+6 1.78E+5 1.43E+4 Co-57 -----6.92E+2 ----- -----5.36E+5 3.14E+4 9.20E+2 Co-58 -----2.07E+3 ----- -----1.34E+6 9.52E+4 2.78E+3 Co-60 ----- 1.51E+4 ----- ----- 8.72E+6 2.59E+5 1.98E+4 Ni-63 5.80E+5 4.34d+4 ----- ----- 3.07E+5 1.42E+4 1.98E+4 Zn-65 3.E6E+4 1.34E+5 - - - - -8.64E+4 1.24E+6 4.66E+4 6.24E+4 Rb-86 -----1.90E+5 ----- ----- -----1.77E+4 8.40E+4 Sr-89 4.34E+5 ----- ----- -----2.42E+6 3.71E+5 1.25E+4 Sr-90 1.08E+8 ----- ----- ----- 1.65E+7 7.65E+5 6.68E+6 Y-91 6.61E+5 ----- ----- ----- 2.94E+6 4.09E+5 1.77E+4 Zr-95 1.46E+5 4.58E+4 ----- 6.74E+4 2.69E+6 1.49E+5 3.15E+4l k Nb-95 1.86E+4 1.03E+4 ----- 1.00E+4 7.51E+5 9.68E+4 5.66E+3 Ru-103 2.10E+3 ----- ----- 7.43E+3 7.83E+5 1.09E+5 8.96E+2 Ru-106 9.84E+4 ----- ----- 1.90E+5 1.61E+7 9.60E+5 1.24E+4 Ag-110m 1.38E+4 1.31E+4 ----- 2.50E+4 6.75E+6 2.73E+5 7.99E+3 Sb-124 4.30E+4 7.94E+2 9.76E+1 -----3.85E+6 3.96E+5 1.68E+4 Sb-125 7.38E+4 8.08E+2 7.04E+1 ----- 2.74E+6 9.92E+4 1.72E+4 Te-12$m 4.88E+3 2.24E+3 1.40E+3 ----- 5.36E+3 7.50E+4 6.67E+2 lTe-127m 1.80E+4 8.16E+3 4.38E+3 6.54E+4 1.66E+6 1.59E+5 2.18E+3 Te-129m 1.39E+4 6.5BE+3 4.5BE+3 5.19E+4 1.98E+6 4.05E+5 2.25E+3 I-131 3.54E+4 4.91E+4 1.46E+7 8.40E+4 ----- 6.49E+3 2.64E+4 I-133 1.22E+4 2.05E+4 2.92E+6 3.59E+4 -----1.03E+4 6.22E+3 l Cs-134 5.02E+5 1.13E+6 -----3.75E+5 1.46E+5 9.76E+3 5.49E+5 Cs-136 5.15E+4 1.94E+5 ----- 1.10E+5 1.78E+4 1.09E+4 1.37E+5 Cs-137 6.70E+5 8.48E+5 ----- 3.04E+5 1.21E+5 8.48E+3 3.11E+5 Ba-140 5.47E+4 6.70E+1 ----- 2.28E+1 2.03S+6 2.29E+5 3.52E+3 Ce-141 2.84E+4 1.90E+4 ----- 8.88E+3 6.14E+5 1.26E+5 2.17E+3 Ce-144 4.89E+6 2.02E+6 ----- 1.21E+6 1.34E+7 8.64E+5 2.62E+5 Pr-143 1.34E+4 5.31E+3 -----3.09E+3 4.83E+5 2.14E+5 6.62E+2 Nd-147 7.86E+3 8.56E+3 ----- 5.02E+3 3.72E+5 1.82E+5 5.13E+2 49 Rev. 10 lk
Hope Creek ODCM 1,/04/89 TABLE 2-4 (Con't) {PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES ss R(io) INHALATION PATHWAY FACTORS - CHILD (mrem /yr per uCi/m3)Nuclide Bone Liver Thyroid Kidney Lung GI-LL1 Total Body iH-3 -----1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 1.12E+3 C-14 3.59E+4 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 6.73E+3 P-32 2.60E+6 1.14E+5 ----- ----- -----4.22E+4 9.88E+4 Cr-51 ----- -----8.55E+1 2.43E+1 1.70E+4 1.08E+3 1.54E+2 Mn-54 -----4.29E+4 -----1.00E+4 1.58E+6 2.29E+4 9.51E+3 Fe-55 4.74E+4 2.52E+4 ----- -----1.11E+5 2.87E+3 7.77E+3 Fe-59 2.07E+4 3.34E+4 ----- -----1.27E+6 7.07E+4 1.67E+4 Co-57 -----9.03E+2 ----- -----5.07E+5 1.32E+4 1.07E+3 Co-58 -----1.77E+3 ----- -----1.11E+6 3.44E+4 3.16E+3 Co-60 -----1.31E+4 ----- -----7.07E+6 9.62E+4 2.26E+4 Ni-63 8.21E+5 4.63E+4 ----- -----2.75E+5 0.33E+3 2.80E+4 Zn-65 4 26E+4 1.13E+5 -----7.14E+4 9.95E+5 1.63E+4 7.03E+4 Rb-86 -----1.98E+5 ----- ----- -----7.99E+3 1.14E+5 Sr-89 5.99E+5 ----- ----- -----2.16E+6 1.67E+5 1.72E+4 tT-90 1.01E+8 ----- ----- -----1.48E+7 3.43E+5 6.44E+6( )91 9.14Et5 ----- ----- -----2.63E+6 1.84E+5 2.44E+4 Zr-95 1.90E+5 4.18E+4 -----5.96E+4 2.23E+6 6.11E+4 3.70E+4 Nb-95 2.35E+4 9.18E+3 -----8.62E+3 6.14E+5 3.70E+4 6.55E+3 Ru-103 2.79E+3 ----- -----7.03E+3 6.62E+5 4.4BE+4 1.07E+3 Ru-106 1.36E+5 ----- -----1.84E+5 1.43E+7 4.29E+5 1.69E+4 Ag-110m 1.69E+4 1.14E+4 -----2.12E+4 5.48E+6 1.00E+5 9.14E+3 Sb-124 5.74E+4 7.40E+2 1.26E+2 -----3.24E+6 1.64E+5 2.00E+4 Sb-125 9.84E+4 7.59E+2 9.10E+1 -----2.32E+6 4.03E+4 2.07E+4 Te-125m 6.73E+3 2.33E+3 1.'lE+3 4.77E+5 3.38E+4 9.14E+2 Te-127m 2.49E+4 8.55E+3 7.14E+4 6.07E+3 6.36E+4 1.48E+6 3.02E+3 Te-129m 1.92E+4 6.85E+3 6.33E+3 5.03E+4 1.76E+6 1.82E+5 3.04E+3 1-131 4.81E+4 4.81E+4 1.62E+7 7.88E+4 -----2.84E+3 2.73E+4 I-133 1.66E+4 2.03E+4 3.85E+6 3.38E+4 -----5.48E+3 7.70E+3 Cs-134 6.51E+5 1.01E+6 -----3.30E+5 1.21E+5 3.85E+3 2.25E+5 Cs-136 6.51E+4 1.71E+5 -----9.55E+4 1.45E+4 4.18E+3 1.16E+5 Cs-137 9.07E+5 8.25E+5 -----2.82E+5 1.04E+5 3.62E+3 1.28E+5 Ba-140 7.40E+4 6.48E+1 -----2.11E+1 1.74E+6 1.02E+5 4.33E+3 Ce-141 3.92E+4 1.95E+4 -----8.55E+3 5.44E+5 5.66E+4 2.90E+3 Ce-144 6.77E+6 2.12E+6 -----1.17E+6 1.20E+7 3.89E+5 3.61E+5
,Pr-143 1.85E+4 5.55E+3 -----
3.00E+3 4.33E+5 9.73E+4 9.14E+2( i- 1.08E+4 8.73E+3 -----4.81E+3 3.28E+5 8.21E+4 6.dlE+2 L ) 147 l 50 Rev. 10 l
Hopa Creek C DCM. 1/04/89 ll TABLE 2-4 (Con't)PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(lo) INHALATION PATHWAY FACTORS - INFANT (aren/yr per uCi/m3) l
,Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body l H-3 -----
6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 6.47E+2 l C-14 2.65E+4 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 5.31E+3 P-32 2.03E+6 1.12E+5 ----- ----- -----1.61E+4 7.74E+4 Cr-51 ----- -----5.75E+1 1.32E+1 1.28E+4 3.57E+2 8.95E+1 Mn-54 -----2.53E+4 -----4.98E+3 1.00E+6 7.06E+3 4.98E+3 Fa-55 1.97E+4 1.17E+4 ----- -----8.69E+4 1.09E+3 3.33E*3 Fo-59 1.36E+4 2.35E+4 ----- -----1.02E+6 2.48E+4 9.48E+3 Co-57 -----6.51E+2 ----- -----3.79E+5 4.86E+3 6.41E+2 Co-58 -----1.22E+3 ----- -----7.77E+5 1.llE+4 1.82E+3 Co-60 -----8.02E+3 ----- -----4.51E+6 3.19E+4 1.18E+4 Ni-63 3.39E+5 2.04E+4 ----- -----2.09E+5 2.42E+3 1.16E+4 Zn-65 1.93E+4 6.26E+4 -----3.25E+4 6.47E+5 5.14E+4 3.llE+4 Rb-86 -----1.90E+5 ----- ----- -----3.04E+3 8.82E+4 Sr-89 3.98E+5 ----- ----- -----2.03E+6 6.40E+4 1.14E+4 Sr-90 4.09E+7 ----- ----- -----1.12E+7 1.31E+5 2.59E+6 Y-91 5.88E+5 ----- ----- -----2.45E+6 7.03E+4 1.57E+4 Zr-95 1.15E+5 2.79E+4 -----3.llE+4 1.75E+6 2.17E+4 2.03E+4 Nb-95 1.57E+4 6.43E+3 -----4.72E+3 4.79E+5 1.27E+4 3.76E+3 Ru-103 2.02E+3 ----- -----4.24E+3 5.52E+5 1.61E+4 6.79E+2 Ru-106 8.68E+4 ----- -----1.07E+5 1.16E+7 1.64E+5 1.09E+4 Ag-110m 9.98E+3 7.22E+3 -----1.09E+4 3.67E+6 3.30E+4 5.00E+3 Sb-124 3.79E+4 5.56E+2 1.01E+2 -----2.65E+6 5.91E+4 1.20E+4 Sb-125 5.17E+4 4.77E+2 6.23E+1 -----1.64E+6 1.47E+4 1.09E+4 To-125m 4.76E+3 1.99E+3 1.62E+3 -----4.47E+5 1.29E+4 6.58E+2 To-127m 1.67E+4 6.90E+3 4.87E+3 3.75E+4 1.31E+6 2.73E+4 2.07E+3 To-129m 1.41E+4 6.09E+3 5.47E+3 3.18E+4 1.68E+6 6.90E+4 2.23E+3 I-131 3.79E+4 4.44E+4 1.48E+7 5.18E+4 -----1.06E+3 1.96E+4 I-133 1.32E+4 1.92E+4 3.56E+6 2.24E+4 -----2.16E+3 5.60E+3 l Cs-134 3.96E+5 7.03E+5 -----1.90E+5 7.97E+4 1.33E+3 7.45E+4 Cs-136 4.83E+4 1.35E+5 -----5.64E+4 1.18E+4 1.43E+3 5.29E+4 Ca-137 5.49E+5 6.12E+5 -----1.72E+5 7.13E+4 1.33E+3 4.55E+4 Bc-140 5.60E+4 5.60E+1 -----1.34E+1 1.60E+6 3.84E+4 2.90E+3 Co-142 2.772+4 1.67E+4 ----- 5.25E+3 5.17E+' 2.16E+4 1.99E+3 Cc-144 3.19E+6 1.21E+6 -----5.38E+5 9.84E+6 1.48E+5 1.76E+5 Pr-143 1.40E+4 5.24E+3 -----1.97E+3 4.33E+5 3.72E+4 6.99E+2 Nd-147 7.94E+3 8.13E+3 -----3.15E+3 3.22E+5 3.12E+4 5.00E+2 51 Rev. 10
Hope Creek ODCM 1/04/89 TABLE 2-4 (Con't)(g~) PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FACTOR - ADULT (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide- Bone Liver Thyroid Kidney Lung GI-LLI Total Body l
H-3 ----- 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 7.63E+2 l C-14 3.53E+5 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 7.26E+4 P-32 1.71E+10 1.06E+9 ----- ----- ----- 1.92E+9 6.60E+8 Cr-51 ----- -----1.71E+4 6.30E+3 3.80E+4 '7.20E+6 2.86E+4 Mn-54 -----8.40E+6 -----2.50E+6 -----2.57E+7 1.60E+6 Fe-55 2.51E+7 1.73E+7 ----- -----9.67E+6 9.95E+6 4.04E+6 Fe-59 2.98E+7 7.00E+7 ----- -----1.95E+7 2.33E+8 2.68E+7 Co-57 -----1.28E+6 ----- ----- -----3.25E+7 2.13E+6 Co-58 ----- 4.72E+6 ----- ----- ----- 9.57E+7 1.06E+7 Co-60 -----1.64E+7 ----- ----- -----3.08E+8 3.62E+7 Ni-63 6.73E+9 4.66E+8 ----- ----- -----9.73E+7 2.26E+8 Zn-65 1.37E+9 4.36E+9 -----2.92E+9 ----- 2.75E+9 1.97E+9 Rb-86 -----2.59E+9 ----- ----- ----- 5.11E+8 1.21E+9 gr-89 1.45E+9 ----- ----- ----- -----2.33E+8 4.16E+7 90 4.68E+10 ----- ----- ----- -----1.35E+9 1.15E+10 (7p_91 k-t- 8.60E+3 ----- ----- ----- -----4.73E+6 2.30E+2 Zr-95 9.46E+2 3.03E+2 -----4.76E+2 -----9.62E+5 2.05E+2 Nb-95 8.25E+4 4.59E+4 ----- 4.54E+4 ----- 2.79E+8 2.47Et4 Ru-103 1.02E+3 ----- -----3.89E+3 -----1.19E+5 4.39E+2 Ru-106 2.04E+4 ----- -----3.94E+4 ----- 1.32E+6 2.58E+3 Ag-110m 5.83E+7 5.39E+7 ----- 1.06E+8 -----2.20E+10 3.20E+7 Sb-124 2.57E+7 4.86E+5 6.24E+4 -----2.00E+7 7.31E+08 4.8bE+6 Sb-125 2.04E+7 2.28E+5 2.08E+4 ----- 1.58E+7 2.25E+8 2.18E+6 Te-125m 1.63E+7 5.90E+6 4.90E+6 6.63E+7 ----- 6.50E+7 2.18E+6 Te-127m 4.58E+7 1.64E+7 1.17E+7 1.86E+8 ----- 1.54E+8 5.58E+6 Te-129m 6.04E+7 2.25E+7 2.08E+7 2.52E+8 ----- 3.04E+8 9.57E+6 I-131 2.96E+8 4.24E+8 1.39E+11 7.27E+8 ----- 1.12E+8 2.43E+8 I-133 3.97E+6 6.90E+6 1.01E+9 1.20E+7 ----- 6.20E+6 2.10E+6 Cs-134 5.65E+9 1.34E+10 -----4.35E+9 1.44E+9 2.35E+8 1.10E+10 lCs-136 2.61E+8 1.03E+9 -----5.74E+8 7.87E+7 1.17E+8 7.42E+8 Cs-137 7.38E+9 1.01E+10 -----3.43E+9 1.14E+9 1.95E+8 6.61E+9 Ba-140 2.69E+7 3.38E+4 -----1.15E+4 1.93E+4 5.54E+7 1.76E+6 l I Ce-141 4.84E+3 3.27E+3 ----- 1.52E+3 ----- 1.25E+7 3.71E+2 Ce-144 3.58E+5 1.50E+5 ----- 8.87E+4 -----1.21E+8 1.92E+4
/~';-143 1.59E+2 6.37E+1 -----
3.68E+1 -----6.96E+5 7.88E+0(_ S-147 9.42E+1 1.09E+2 ----- 6.37E+1 -----5.23E+5 6.52E+0 ,i l52 Rev. 10
l l Hope Creek ODCM 1/04/89 ll TABLE 2-4 (Con't) l PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK FATHWAY FACTOR - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Tiyroid l
Kidney Lung GI-LLI Total Body l H-3 ----- 9.94Et2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 9.94E+2 C-14 6.70E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 1.34E+5 P-32 3.15E+10 1.95E+9 ----- ----- -----2.65E+9 1.22E+9 Cr-51 ----- ----- 2.7BE+4 1.10E+4 7.13E+4 8.40E+6 5.00E+4 Mn-54 ----- 1.40E+7 -----4.17E+6 ----- 2.87E+7 2.78E+6 Fe-55 4.45E+7 3.16E+7 ----- -----2.00E+7 1.37E+7 7.36E+6 Fe-59 5.20E+7 1.21E+8 ----- -----3.82E+7 2.87E+8 4.68E+7 Co-57 -----2.25E+6 ----- ----- ----- 4.19E+7 3.76E+6 Co-58 -----7.95E+6 ----- ----- -----1.10E+8 1.83E+7 Co-60 ----- 2.78E+7 ----- ----- -----3.62E+8 6.26E+7 Ni-63 1.18E+10 8.35E+8 ----- ----- -----1.33E+8 4.01E+8 Zn-65 2.11E+9 7.31E+9 -----4.68E+9 -----3.10E+9 3.41E+9 Rb-86 -----4.73E+9 ----- ----- -----7.00E+8 2.22E+9 Sr-89 2.67E+9 ------ ----- ----- -----3.18E+8 7.66E+7 Sr-90 9.92E+7 ----- ----- ----- 9.60E+6 7.22E+5 6.10E Y-91 1.58E+4 ----- ----- ----- -----6.48E+6 4.24E Zr-95 1.65E+3 5.22E+2 ----- 7.67E+2 ----- 1.20E+6 3.59E+2 Nb-95 1.41E+5 7.80Ev4 ----- 7.57Et4 -----3.34E+8 4.30E+4 Ru-103 1.81E+3 ----- -----6.40E+3 ----- 1,52E+5 7.75E+2 Ru-106 3.75E+4 ----- -----7.23E+4 -----1.80E+6 4.73E+3 Ag-110m 9.63E+7 9.11E+7 ----- 1.74E+8 -----2.56E+10 5.54E+7 Sb-124 4.59E+7 8.46E+5 1.04E+5 -----4.01E+7 9.25E+8 1.79E+2 Sb-125 3.65E+7 3.99E+5 3.49E+4 -----3.21E+7 2.84E+8 8.54E+6 Te-125m 3.00E+7 1.08E+7 8.39E+6 ----- -----8.86E+7 4.02F.+6 Te-127m 8.44E+7 2.99E+7 2.01E+7 3.42E+8 -----2.10E+8 1.00E+7 Te-129m 1.llE+8 4.10E+7 3.57E+7 4.62E+8 -----4.15E+8 1.75E+7 I-131 5.38E+8 7.53E+8 2.20E+11 1.30E+9 -----1.49E+8 4.04E+8 l 1-133 7.24E+6 1.23E+7 1.72E+9 2.15E+7 -----9.30E+6 3.75E+6 Cs-134 9.81E+9 2.31E+10 -----7.34E+9 2.80E+9 2.87E+8 1.07E+10 Cs-136 4.45E+8 1.75E+9 -----9.53E+e 1.50E.8 1.41E+8 1.18E.9 Cs-137 1.34E+10 1.78E+10 -----6.06E+9 2.35E+9 2.53E+8 6.20E+9 Ba-140 4.85E+7 5.95E+4 -----2.02E+4 4.00E+4 7.49E+7 3.13E+6 Ce-141 8.87E+3 5.92E+3 -----2.79E+3 ----- 1.69E+7 6.81E+2 Ce-144 6.58E+5 2.72E+5 -----1.63E+5 ----- 1.66E+8 3.54E+4 Pr-143 2.92E+2 1.17E+2 -----6.77E+1 -----9.61E+5 1.45E Nd-147 1.81E+2 1.97E+2 -----1.16E+2 ----- 7.11E+5 1.18 55 Rev. 10
c Hope Creek.ODCM 1/04/89 TABLE 2-4 (Con't)
' PATHWAY DOSE FAC70RS - ATMOSPHERIC RELEASES U R(io) GRASS-COW-MILE PATHWAY FACTOR - CHILD (arem/yr per uCi/m3) for H-3 and C-14 (m2
- mren/yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI Total Body H-3 -----
1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3 1.57E+3
. C-14 1.65E+6 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 3.29E+5 - P-32 7.77E+10 3.64E+9 ----- ----- -----
2.15E+9 3.00E+9
- Cr-51 ----- -----
5.66E+4 1.55E+4 1.03E+5 5.41E+6 1.02E+5 11n-54 -----2.09E+7 -----5.87E+6 -----1.76E+7 5.58E+6 Fe-55 1.12E+8 5.93E+7 ----- -----3.35E+7 1.10E+7 1.84E+7 Fe-59 1.20E+8 1.95E+8 ----- -----5.65E+7 2.03E+8 9.71E+7 Co-57 -----3.84E+6 ----- ----- -----3.14E+7 7.77E+6 Co -----1.21E+7 ----- ----- -----7.08E+7 3.72E+7 Co-60 -----4.32E+7 ----- ----- -----
.2.39E+8 1.27E+8 Ni-63 2.96E+10 1.59E+9 ----- ----- -----
1.07E+8 1.01E+9 Zn-65 4.13E+9 1.10E+10 ----- 6.94E+9 -----1.93E+9 6.85E+9 Rb-86 --~~-8.77E+9 ----- ----- -----5.64E+8 5.39E+9 Sr-89 6.62E+9 ----- ----- ----- -----2.56E+8 1.89E+8 Sr-90 1.12E+11 ----- ----- ----- -----1.51E+9 2.83E+10 Y-91 3.91E+4 ----- ----- ----- -----5.21E+6 1.04E+3 1r-95 3.84E+3 8.45E+2 -----1.21E+3 -----8.81E+5 7.52E+2[\.dib-95 3.18E+5 1.24E+5- -----1.16E+5 -----2.29E+8 8.84E+4 Ru-103 4.29E+3 ----- -----1.08E+4 -----1.11E+5 1.65E+3 Ru-106 9.24E+4 ----- -----1.25E+5 -----1.44E+6 1.15E+4 Ag-110m 2.09E+8 1.41E+8 -----2.63E+8 -----1.68E+1G 1.13E+8 Sb-124 1.09E+8- 1.41E+8 2.40E+5' ----- 6.03E+8 6.79E+8 1.32E+7 Sb-125 8.70E+7 1.41E+6 8.06E+4 ----- 4.85E+7 2.0BE+8 9.84E+6 To-125m 7.38E+7 2,00E+7 2.07E+7 ----- -----7.12E+7 9.84E+6 Te-127m 2.08E+8 5.60E+7 4.97E+7 5.93E+8 -----1.6EE+8 2.47E+7
- Te-129m 2.72E+8 7.61E+7 8.78E+7 8.00E+8 ----- 3.32E+8 4.23E+7 I-131 1.30E+9 1.31E+9 4.34E+11 2.15E+9 -----
1.17E+8 7.46E+8 I-133 1.76E+7 2.18E+7 4.04E+9 3.63E+7 -----8.77E+6 8.23E+6 l j iCs-134 2.26E+10 3.71E+10 -----1.15E*10 4.13E+9 2.00E+8 7.83E+9 i Cs-136 1.00E+9 2.76E+9 -----1.47E+9 2.lCE+8 9.70E+7 1.79E+9 I Cs-137 3.22E+10 3.09E+10 -----1.01E+10 3.62E+9 1.93E+8 4.55E+9 i Be-140 1.17E+8 1.03E+5 -----3.34E+4 6.12E+4 5.94E+7 6.84E+6 j Co-141 2.19E+4 1.09E+4 -----4.78E+3 -----1.36E+7 1.62E+3
' Co-144 1.62E+6 5.09E+5 -----
2.82E+5 -----1.33E+8 8.66E+4 Pr-143 7.23E+2 2.17E+2 -----1.17E+2 ----- 7.80E+5 3.59E+1 Nd-147 4.4bE+2 3.60E+2 ----- 1.98E+2 -----5.71E+5 2.79E+1 l! 54 Rev. 10 ll
- _ _ _ ___ _ m- _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _
Hope Creek ODCM 1/04/89 TABLE 2-4 (Con't)PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GRASS-COW-MILK PATHWAY FAC2OR - INFANT (area /yr per uCi/m31 for H-3 and C-14 (m2
- mren/yr par uCF/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI _
Total Body H-3 ----- 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 2.38E+3 C-14 3.23E+6 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 6.89E+5 P-32 1.60E+11 9.(2E+9 ----- ----- -----2.17E+9 6.21E+9 Cr-51 ----- -----1.05E+5 2.30E+4 2.05E+5 4.71E+6 1.61E+5 Mn-L4 ----- 3.89E+7 ----- 8.63Et6 -----1.43E+7 8.83E+6 Fe-55 1.35E+8 8.72E+7 ----- -----4.27E+7 1.llE+7 2.33E+7 Fe-59 2.25E+8 3.93E+8 ----- -----1.16E+8 1.88E+8 1.55E+8 Co-57 -----8.95E+6 ----- ----- -----3.05E+7 1.46E+7 Co-58 -----2.43E+7 ----- ----- -----6.05E+7 6.06E+7 Co-60 -----8.81E+7 ----- ----- -----2.10E+8 2.08E+8 Ni-63 3.49E+10 2.16E+9 ----- ----- -----1.0?E+8 1.21E+9 Zn-65 5.55E+9 1.90E+10 -----9.23E+9 -----1.61E+10 8.78E+9 Rb-86 -----2.22E+10 ----- ----- -----5.69E+8 1.10E+10 Sr-89 1.26E+10 ----- ----- ----- -----2.59E+8 3.61E+8 Sr-90 1.22E+11 ----- ----- ----- -----1.52E+9 3.10E+10 Y-91 7.33E+4 ----- ----- ----- -----5.26E+6 1.95E+3 Zr-95 6.83E+3 1.66E+3 -----1.79E+3 ------8.28E+5 1. LEE +3 k Nb-95 5.93E+5 2.44E+5 ----- 1.7bE+5 ------ 2.06E+8 1.41E+5 l Ru-103 8.69S+3 ----- -----1.81E+4 -----1.06E+5 2.91E+3 l Ru-106 1.90E+5 ----- -----2.25E+5 -----1.44E+6 2.3BE+4 lAg-110m 3.86E+8 2.82E+8 -----4.03E+8 ----- 1.46E+10 1.86E+B Sb-124 2.09E+8 3.00E+6 5.56E+5 -----1.31E+8 6.46E+8 6.49E+7 S b-125 1.49E+8 1.45E+6 1.87E+5 -----9.38E+7 1.99E+8 3.07E+7 To-125m 1.51E+8 5.04E+7 5.07E+7 ----- -----7.18E+7 2.04E+7 Te-127m 4.21E+8 1.40E+8 1.22E+8 1.04E+9 -----1.70E+8 5.10E+7 To-129m 5.59E+8 1.92E+8 2.15E+8 1.40E+9 -----3.34E+8 6.62E+7 I-131 2.72E+9 3.21E+9 1.05E+12 3.75E+9 -----1.15E+8 1.41E+9 !I-133 3.72E+ 7 5.41E+7 9.84E+9 6.36E+7 -----9.16E+6 1.58E+7 l Cs-134 3.65E+10 6.80E+10 -----1.75E+10 7.18E+9 1.85C+8 6.87E+9 Cs-136 1.96E+9 5.77E+9 -----2.30E+9 4.70E+8 8.76E+7 2.15E+9 Cs-137 5.15E+10 6.02E+10 ----- 1.62E+10 6.55E+9 1.88E+8 4.27E+9 Ba-140 2.41E+0 2.41E+5 -----5.73E+4 1.48E+5 5.92E+7 1.24E+7 Co-141 4.33E+4 2.64E+4 -----8.15E+3 -----1.37E+7 3.llE+3 Ce-144 2.33E+6 9.52E+5 ----- 3.85E+5 -----1.33E+8 1.30E+5 Pr-143 1.49E+3 5.59E+2 -----2.08E+2 -----7.89E+5 7.41E+1 Nd-147 8.82E+2 9.06E+2 ----- 3.49E+2 -----5.74E+5 5.55E+1 155 Rev. 10 ll E__ - )
-1 1 - Hope Creek ODCM- 1/04/89 l 1
4
)
TABLE 2-4 (Con't) i
. PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES , ! R(io) VEGETATION PATHWAY FACTOR - ADULT- ]
(mren/yr per uCi/m3) for H-3 and C-14 !(m2
- mren/yr per uCi/sec) for others I l
N_uclid e ' Bone Liver' Thyroid Kidney- Lung GI-LLI Total 3ody )i H-3 -----2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 2.26E+3 l C-14 8.97E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 1.79E+5 P-32 l.40E&9 8.73E+7 ----- ----- -----1.53E+8 5.42E+7 Cr-51 ----- -----; 2.79E+4 1.03E+4 5.19E+4' l.17E+7 4.66E+4 Mn-54 -----3.llE+8 ----- 9.27E+7- -----9.54E+8. 5.94E+7 Fe-55 2.09E+8- 1. 4 5 E+ 8- ----- -----8.06E+7 8.29E+7 3.37E+7 {Fe-59 1.27E+8 2.99E+8. ----- -----8.35E+7 9.96E+8 1.14E+8 l Co-57 ----- 1.17E+7 ----- ----- ----- 2.97E+8 1.95E+7 Co-58 ----- 3.09E+7 ----- ----- -----6.26E+8 6.92E+7 Co-60 ----- 1.67E+8 ----- ----- -----3.14E+9 3.69E+8 Ni-63 1.04E+10 7.21E+8 ----- ----- -----1.50E+8 3.49E+8 2n-65 3.17E+8 1.01E+9 ----- 6.75E+8 -----6.36E+8 4.56E+8 Rb-86 -----2.19E+8 ----- ----- -----4.32E+7 1.02E+8 Sr 9.96E+9 ----- ----- ----- ----- 1.60E+9 2.86E+8 Sr-90 6.05E+11 ----- ----- ----- -----1.75E+10 1.48E+11 Y-91 5.13E+6 ----- ----- ----- -----2.82E+9 1.37E+5 5.97Ei5
'y-95L 1.19E+6 3.81E+5 ----- -----
1.21E+9 2.58E+5' s~ib-95 1.42E+5 7.91E+4 -----7.81E+4 ----- 4.80E+8 4.25E+4 Ru-103 4.80E+6 ----- ----- 1.83E+7 ----- 5.61E+8 2.07E+6 Ru-106 1.93E+8 ------ ----- 3.72E+8 ----- 1.25E+10 2.44E+7 Ag-110m 1.06E+7 9.76E+6 ----- 1.92E+7 -----3.98E+9 5.80E+6 Sb-124 1.04E+8 1.96E+6 2.52E+5 -----8.08E+7 2.95E+9 4.llE+7 Sb-125 1.36E+8 1.52E+6 1.39E+5 ----- 1.05E+8 1.50E+9 3.25E+7 To-125m. 9.66E+7 3.50E+7 2.90E+7 3.93E+8 -----3.86E+8 1.29E+7 To-127m 3.49E+8 1.25E+8 8.92E+7- 1.42E+9 ----- 1.17E+9 4.26E+7 Te-129m 2.55E+8 9.50E+7 8.75E+7 1.06E+9 -----1.28E+9 4.03E+7
'I-131 8.09E+7 1.16E+8 3.79E+10 1.98E+8 ----- 3.05E+7 6.63E+7 I-133 2.12E+6 3.69E+6 5.42E+8 6.44E+6 ----- 3.31E+6 1.12E+6 l Cs-134 4.66E+9 1.llE+10 ----- 3.59E+9 1.19E+9 1.94E+8 9.07E+9 Cs-136 4.20E+7 1.66E+8 ----- 9.24E+7 1.27E+7 1.89E+7 1.19E+8 i Cs-137 6.36F+9 'B.70E+9 ----- 2.95E+9 9.81E+8 1.68E+8 5.70E+9 Ba-140 1.29E+8 1.62E+5 ----- 5.49E+4 9.25E+4 2.65E+8 8.43E+6 Ce-141 1.96E+5 1.33E+5 ----- 6.17E+4 ----- 5.08E+8 1.51E+4 Ce-144 3.29E+7 1.38E+7 -----
8.16E+6 -----1.llE+10 1.77E+6 Pr-143 6.34E+4 2.54E+4 ----~1.47E+4 ----- 2.7BE+8 3.14E+3 Nd-147- 3.34E+4 3.86E+4 ----- 2.25E+4 ----- 1.85E+8 2.31E+3 56 Rev. 10
=_ _-. _ - - - _ _ _ - - _ _ _ _ _ _ _ - __- - - _ _ _ - _
Hope Creek ODCM 1/04/89 TABLE 2-4 (Con't)PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) VEGETATION PATHWAY FACTOR - TEENAGER (mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per uCi/sec) for others Nuclide Bone Liver Thyroid Kidney Lung GI-LLI _T_otal Body H-3 ----- 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 2.59E+3 C-14 1.45E+6 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 2.91E+5 P-32 1.61E*9 9.96E+7 ----- ----- -----
1.35E+8 6.23E+7 Cr-51 ----- ------3.44E+4 1.36E+4 8.05E+4 1.04E+7 6.20E+4 Mn-54 -----4.52E+8 -----1.35E+8 -----9.27E+8 8.97E+7 Fo-55 3.25E+8 2.31E+8 ----- -----1.46E+8 9.98E+7 5.38E+7 Fo-59 1.81E+8 4.22E+8 ----- ----- 1.j3E+8 9.98E+8 1.63E+9 Co-57 -----1.79E+7 ----- ----- ----- 3.34E+8 3.00E+7 Co-58 ----- 4.38E+7 ----- ----- ----- 6.04E+8 1.01E+8 Co-60 -----2.49E+8 ----- ----- -----3.24E+9 5.60E+8 Ni-63 1.61E+10 1.13E+9 ----- ----- -----1.81E+8 5.45E+8 Zn-65 4.24E+8 1.47E+9 -----9.41E+8 -----6.23E+8 6.86E+8 Rb-86 ----- 2.73E+8 ----- ----- ----- 4.05E+7 1.2BE+8 Sr-89 1.51E+10 ----- ----- ----- -----1.80E+9 4.33E+8 Sr-90 7.51E+11 ----- ----- ----- -----2.llE+10 1.85E+11 Y-91 7.87E+6 ----- ----- ----- -----3.23E+9 2.llE+5 Zr-95 1.74E+6 5.49E+5 -----8.07E+5 -----1.27E+9 3.78E+5 Nb-95 1.92E+5 1.06E+5 -----1.03E+5 -----4.55E+8 5.86E+4 Ru-103 6.87E+6 ----- -----2.42E+7 -----5.74E+8 2.94E+6 Ru-106 3.09E+8 ----- -----5.97E+8 -----1.48E+10 3.90E+~i Ag-110m 1.52E+7 1.44E+7 -----2.74E+7 ----- 4.04E+9 8.74E+6 Sb-124 1.55E+8 2.85E+6 3.51E+5 ----- 1.35E+8 3.llE+9 6.03E+7 Sb-125 2.14E+8 2.34E+6 2.04E+5 ----- 1.88E+8 1.66E+9 5.00E+7 To-125m 1.48E+8 5.34E+7 4.14E+7 ----- ----- 4.37E+8 1.98E+7 Te-127m 5.51E+8 1.96E+8 1.31E+8 2.24E+9 ----- 1.37E+9 6.56Et7 To-129m 3.67E+8 1.36E+8 1.18E+8 1.54E+9 ----- 1.38E+9 5.81E+7 1-131 7.70E+7 1.08E+8 3.14E+10 1.85E+8 ----- 2.13E+7 5.79E+7 I-133 1.97E+6 3.34E+6 4.66E+8 5.86E+6 ----- 2.53E+6 1.02E+6 l Cs-134 7.09E+9 1.67E+10 -----5.30E+9 2.02E+9 2.08Ev8 7.74E+9 Cs-136 4.29E+7 1.69E+8 -----9.19E+7 1.45E+7 1.36E+7 1.13E+8 Cs-137 1.01E+10 1.35E+10 -----4.59E+9 1.78E+9 1.92E+8 4.69E+9 Bn-140 1.38E+8 1.69E+5 -----5.75E+4 1.14E+5 2.13E+8 8.91E+6 Co-141 2.82E+5 1.88E+5 ----- 8.86E+4 -----5.38E+8 2.16E+4 Co-144 5.27E+7 2.18E+7 ----- 1.30E+7 ----- 1.33E+10 2.83E+6 Pr-143 7.12E+4 2. 8 4 r.+ 4 ----- 1.65E+4 ----- 2.34E+8 3.55E+3 Nd-147 3.63E+4 3.94E+4 -----2.32E+4 ----- 1.42E+8 2.36E+3 57 Rev. 10 f
l Hope Creek ODCM 1/04/89 TABLE 2-4 (Con't) J
'I PATHWAY DOSE PACTORS - ATMOSPHERIC RELEASES \--) R(io) VEGETATION PATHWAY FACTOR - CHILD i
(mrem /yr per uCi/m3) for H-3 and C-14 (m2
- mrem /yr per aci/sec) for others Nuclide Bone Liver Thyrc-id Kidney Lung GI-LLI Total Body l
H-3 -----
- 4. ole +3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 4.01E+3 C-14 3.50E+6 7.01E+5 7.0]E+5 7.01E+5 7.01E+5 7.01E+5 7.01E+5 4 P-32 3.37E+9 1.58E+8 ----- ----- -----
9.30E+7 1.30Et8 {Cr-51 ----- -----6.54E+4 1.79E+4 1.19E+5 6.25Ev6 1.18E+5 1 Mn-54 -----6.61E+8 -----1.85E+8 -----5.55E+8 1.76E+8 Fe-55 8.00E+8 4.24E+8 ----- -----2.40E+8 7.86E+7 1.31E+8 Fe-59 4.01E+8 6.49E+8 ----- -----1.88E+8 6.76E+8 3.23E+8 Co-57 -----2.99E+7 ----- ----- -----2.45E+8 6.04E+7 Co-58 -----6.47E+7 ----- - - - - - -----3.77E+8 1.98E+8 Co-60 -----3.78E+8 ----- ----- -----2.10E+9 1.12E+9 Ni-63 3.95E+10 2.llE+9 ----- ----- -----1.42E+8 1.34E+9 Zn-65 8.12E+8 2.16E+9 -----1.36E+9 -----3.80E+8 1.35E+9 Rb-86 -----4.52E+8 ----- ----- -----2.91E+7 2.78E+8 Sr-89 3.59E+10 ----- ----- ----- -----1.39E+9 1.03E+9(~'T- 9 0 1.24E+12 ----- ----- ----- -----1.67E+10 3.15E+11(,,/- 91 1.87E+7 ----- ----- ----- -----2.49E+9 5.01E+5 Zr-95 3.90E+6 8.58E+5 ----- 1.23E+6 -----8.95E+8 7.64E+5 .Nb-95 4.10E+5 1.59E+5 -----1.50E+5 -----2.95E+8 1.14E+5 Ru-103 1.55E+7 ----- ----- 3.89E+7 -----3.99E+8 5.94E+6 Ru-106 7.45E+8 ----- -----1.01E+9 -----1.16E+10 9.30E+7 Ag-110m 3.22E+7 2.17E+7 -----4.05E+7 -----2.58E+9 1.74E+7 Sb-124 3.52E+8 4.57E+6 7.78E+5 -----1.96E+8 2.20E+9 1.23E+8 Sb-125 4.99E+8 3.85E+6 4.62E+5 ----- 2.78E+8 1.19E+9 1.05E+8 Te-125m 3.51E+8 9.50E+7 9.84E+7 ----- -----3.38E+8 4.67E+7 iTe-127m 1.32E+9 3.56E+8 3.16E+8 3.77E+9 -----1.07E+9 1.57E+8 {Te-129m 8.54E+8 2.39E+8 2.75E+8 2.51E+9 ----- 1.04E+9 1.33E+8 !I-131 1.43E+8 1.44E+8 4.76E+10 2.36E+8 -----1.28E+7 8.18E+7 I-133 3.59E+6 4.44E+6 8.25E+8 7.40E+6 -----1.79E+6 1.68E+6 Cs-134 1.60E+10 2.63E+10 -----8.14E+9 2.92E+9 1.42E+8 5.54E+9 iI Cs-136 8.06E+7 2.22E+8 -----1.18E+8 1.76E+7 7.79E+6 1.43E+8 Cs-137 2.29E+10 2.29E+10 -----7.46E+9 2.68E+9 1.43Et8 3.38E+9 Ba-140 2.77E+8 2.43E+5 ----- 7.90E+4 1.45E+5 1.40E+8 1.62E+7 Ce-141 1.23E+5 6.14E+4 -----2.69E+4 -----7.66E+7 9.12E+3 Ce-144 1.27E+8 3.98E+7 -----2.21E+7 ----- 1.04E+10 6.78E+6 !
,-' 1.48E+5 4.46E+4 -----
2.41E+4 -----1.60E+8 7.37E+3 )( ,)r-143
-147 7.16E+4 5.80E+4 -----
3.18E+4 ----- 9.18E+7 4.49E+3 1 58 Rev. 10 lL _ ____ ____ __ !
3 t:- Hope Creek ODCM 1/04/89 !TABLE 2-4 (Con't)PATHWAY DOSE FACTORS - ATMOSPHERIC RELEASES R(io) GROUND PLANE PATHWAY FACTOR (m2
- mrem /yr per uCi/sec)
Nuc3ide Any Organ H-3 -----C-14 -----P-32 -----Cr-51 4.68E 6 Mn-54 1.34E 9 Fe-55 -----Fe-59 2.75E 8 Co-58 3.82E 8 Co-60 2.16E10 Ni-63 -----Zn-65 7.45E 8 Rb-86 8.98E 6 Sr-89 .?.16E 4 Sr-90 -----Y-91 1.08E 6 Zr-95 2.48E 8 Nb-95 1.36E 8 Ru-103 1.09E 8 Ru-106 4.21E 8 Ag-llom 3.47E 9 Te-125m 1.55E 6 Tc-127m 9.17E 4 Te-129m 2.00E 7 I-131 1.72E 7 I-133 2.47E+6 l Cn-134 6.75E 9 Cs-136 1.49E 8 Cs-137 1.04E10 1 Ba-140 2.05E 7 Ce-141 1.36E 7 Ce-144 6.95E 7 Pr-143 -----l Nd-147 8.40E 6 I O.I 59 Rev. 10 li a______ __ _ ._
Hope Creek ODCM 1/04/89 Or
'\ )
APPENDIX A 4 EVALUATION OP DEFAULT MPC VALUES lg FOR LIQUID EFFLUENTS A-1 Rev. 10
Hope Creek ODCM 1/04/89 APPENDIX A Evaluation of Default MPC Value for Liquid Effluents In accordance with the requirements of Technical Specification 3.3.3.10 the radioactive effluent monitors shall be operable with alarm setpoints established to ensure that the concentration of radioactive material at the discharge point does not exceed the MPC value of 10 CFR 20, Appendix B, Table II, Column 2. The determination of allowable radionuclides concentration and corresponding alarm setpoint is a function of the individual radionuclides distribution and corresponding MPC values.In order to limit the need for routinely having to reestablish the alarm setpoints as a function of changing radionuclides distributions, a default alarm setpoint can be established. This default setpoint can be based on an evaluation of the radionuclides distribution from the 1987 release data of the ,_liquid effluents from Hope Creek and the effective MPC value for this distribution.The effective MPC value for a ridionuclide distribution is calculated by the equation:MPCe =Ci/{_(Ci/MPCi) (A.1) where:MPCe
= an effective MPC value for a mixture of radionuclides (uCi/ml)
Ci = concentration of radionuclido i in the mixture MPCi = the 10 CFR 20, Appendix B, Table II, Column 2 MPC value for radionuclides 1 (uCi/ml)O A-2 Rev. 10
Hope Creek ODCM 1/04/89 L=Based on the above equation and the radionuclides distribution in the effluents for Hope Creek from 1987 releases, Results are presented in Table A-1.Considering the average effective MPC values from 1987 releases it is reasonable to select an MPC value of 4.19 uCi/ml as typical ot liquid radwaste discharges. This value will be reviewed and 1adjusted as necessary based on the distribution history of effluents from Hope Creek. Using the value of uCi/ml to calculate the default alarm setpoint, results in a setpoint that:
- 1) Will not require trequent re-adjustment due to minor variations in the nuclide distribution which are typical of routine plant operations, and;
- 2) will provide for a liquid radwaste discharge rate (as evaluated for each batch release) that is compatible with plant operations (Refer to Table 1-1).
O A-3 Rev. 10
Hops Creek ODCM 1/04/89 TABLE A-1 CALCULATION OF EPt'ECTIVE MPC HOPE CREEK 1987 ACTIVITY NUCLIDE MPC RELEASED (Ci)Na-24 3.0E-05 5.7E-01 Cr-51 2.0E-03 4.5E-01 Mn-54 1.0E-04 6.3E-02 Fe-55 8.0E-04 3.0E-02 Mn-56 1.0E-04 1.3E-04 Co-55 9.0E-05 9.5E-02 Fe-59 6.0E-05 5.2E-02 Co-60 3.0F-05 3.8E-02 Cu-64 3.0E-04 9.6E-04 Ni-55 1.0E-04 3.3E-05 zn-65 1.03-04 1.7E-01 2n-69 2.0E-03 3.4E-03 Se-75 3.0E-04 4.0E-04 Sr-89 3.0E-06 3.2E-03 Y-91m 3.0E-03 2.8E-02 Y-91 3.0E-05 2.8E-03 Sr-92 7.0E-05 3.lE-05 Nb-95 1.0E-04 1.3E-03 Zr-95 6.0E-05 1.4E-04 Nb-97 9.02-04 1.9E-03 Zr-97 2.0E-05 2.7E-05 Mo-99 4.0E-05 1.2E-02 g l Tc-99m 6.0E-03 1.3E-02 i Tc-100 3.0E-06 3.7E-05 Ru-106 1.0E-05 1.1E-05 Sb-122 3.0E-05 7.7E-04 Sb-124 2.0E-5 6.5E-03 Sb-125 1.0E-4 1.7E-04 I-131 3.0E-07 1.8E-04 Te-132 3.0E-05 2.6E-04 A-4 Rev. 10 a__-_-__-____________
Hope Creek ODCM 1/04/89_w
,~ '
i )
"s' TABLE A-1 (CONT'D)
CALCULATION OF EFFECTIVE MPC HOPE CREEK 1987 ACTIVITY NUCLIDE MPC RELEASED (Ci)I-133 1.0E-06 2.9E-03 Cs-137 2.0E-05 1.2E-05 Ba-139 3.0E-06 1.3C-05 Ce-141 9.0E-05 1.0E-05 Ce-143 4.0E-05 7.4E-06 Ce-144 1.0E-05 2.3E-03 Np-239 1.0E-04 1.3E-03 Hg-203 2.0E-05 1.9E-04 TOTAL 1.58E+0J
,n N'~']
SUM (Ci/MPCi) 3.77E+04 MPCe (uCi/ml) 4.19E-05 1l(~' i I(_-) 'i IA-5 Rev. 10 L--____
Hope Creek ODCM 1/04/89 9APPENDIX B TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS LIQUID RADIOACTIVE EFFLUENT B-1 Rev. 10
cm - . .i ., a Hope Creek ODCM 1/04/89 O APPENDIX B Technical Basis for Effective Dose Factors -Liquid Effluent Releases L The radioactive liquid effluents from Hope Creek during 1987 were evaluated to determine the dose contribution of the radionuclides distribution. This analysis was performed to evaluate the use of a limited ~ dose analysis for determining environmental doses, providing a simplified method of determining compliance with the dose limits of Technical Specification 3.11.1.2. For the espected-radionuclides distribution of effluents from Hope Creek during .1987, the controlling organ is the liver. The calculated liver doseHis predominately a function of the 2n-65 and Fe-59 releases. The radionuclides, 2n-65 and Fe-59 also contribute the large majority of the calculated total body dose. The results of this evaluation are presented in Table B-1.For purposes of simplifying the details of the dose calculation proce ss, it is conservative to identify a controlling, dose significant radionuclides and limit the calculation process to the use of the dose conversion factor for this nuclide.O Multiplication of the total release (i.e., cumulative activity for all radionuclides) by this dose conversion factor provides for a' dose calculation method that is simplified while also being conservative.For the evaluation of the maximum organ dose, it is conservative to use the Zn-65 dose conversion. factor (5.13E5 mrem /hr per liver). By this approach, the maximum organ dose will be q overestimated since this nuclide has the highest organ dose fraction of all the radionuclides evaluated. For the total body calculation, the 2n-65 dose factor (2.32E5 mrem /hr per uCi/ml, total body) is the highest among the identified dominant i nuclides.For evaluating compliance with the dose limits of Technical Specification 3.11.1.2, the following simplified equations may be used:Total' Body 8.35E-04 VOL ,Db t
= ---------
CTBD Ai,tb "{Ci l iB-2 Rev. 10 l lA
Hope Creek ODCM 1/04/89 Where:Dtb = dose to the total body (mrem)Ai,tb = 2.32E5, total body ingestion dose conversion factor for 2n-65 where A is dose conversion factor, i is isotope which is Zn-65, and TB is the total body (mrem /hr per uCi/ml) l VOL = voleme of liquid effluent released (gal) 1 Ci = total concentration of all radionuclides (uCi/ml)CTBD = average cooling tower blowdown discharge rate during release period (gal / min) 8.35E-04 = conversion factor (1.67E-2 hr/ min) and the near field dilution factor 0.05 Substituting the value for the Zn-65 total body dose conversion factor, the equation simplified tot 1.94E2
- VOL Db t
*[_Ci 1 CTBD Maximum Organ *
- Aio, GI-LLI 8.35E-4 VOL Dmax = -----------------
- y,Ci CTBD Where:
Dmax = maximum organ dose (mrem)Aio, = 5.13ES, liver ingestion dose conversion factor for GI-LLI Zn-65 where A is dose conversion factor, i is isotope which is Zn-65 and O is maximuu organ which is the GI-LLI. (mrem /hr per uCi/ml).Substituting the value for Aio the equation simplifies to:
- VOL 4.28E2 Dmax = --------
*[,Ci CTBD Tritium ir. not included in the limited analysis dose assessment for liquid releases, because the potential dose resulting from normal reactor releases is relatively negligible.
1 B-3 Rev. 10
Hope Creek ODCM 1/04/89 1
,r s l
Near Field Dilution Factor The near field dilution factor stems from NuReg-0133, Section 4.1. For plants with cooling towers, such as Hope Creek, a dilution factor is applicable so that the product of the average blowdown flow (in CFS) and the dilution factor is 1000 cfs or less. The average minimum cooling tower blowdown for Hope Creek is 1.90E4 GPM (from FSAR 11.2). This converts to 42 CFS,'for conservatism a dilution factor of 20 will be used, giving a dilution flow of 880 CF6. This near field dilution factor of 20 is inverted to a multiple of 0.05, multiplied times the liquid effluent dose equations.O (vD B-4 Rev. 10 ;1_ . _ . . _ . _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . . . . . _ _ . _ J
i I lr is..Si - Hope Creek ODCM 1/04/89 1l O1 ll lt APPENDIX C 1TECHNICAL BASIS FOR EFFECTIVE DOSE FACTORS GASEOUS RADIOACTIVE EFFLUENT lO ll-1 9C-1 Rev. 10
\.
A Hope Creek ODCM 1/04/89 APPENDIX C Technical Basis for' Effective Dose Factors -Gaseous Radioactive' Effluents Overview 1The evaluation of doses due to releases of radioactive material to the' atmosphere can be simplified by the use of effective dose
. transfer factors instead of using dose factors which are . radionuclides specific. These effective factors, which are based on typical radionuclides distributions of releases, can be applied to the total' radioactivity released to approximate the dose in the environment. Instead of having to perform individual radioluclide dose analysis only a single multiplication (i'.e.,
Keff, Meff, or Neff times the total quantity of radioactive material. released) would be needed. The approach provides a.reasonable estimate-of the actual dose while eliminating the need
.for a detailed calculation technique.
Determination of Effective Dose Factors Effective dose transfer. factors are calculated by the following Keff =(( {Ki
- fi)
Where:Keff = the effective total body factor due to gamma emissions from all noble gases released.Ki = the total body dose factor due to gamma emissions from each noble gas radionuclides i released.fi
= the fractional. abundance of noble gas )
radionuclides i relative to the total noble gas activity.1 (L + 1.1 M) egg = ((Li + 1.1 Mi) *f i)Where: <(L + 1.1M) egg = the effective skin dose factor due to beta and gamma emissions from all noble gases released.C-2 Rev. 10 i
l Hope Creek ODCM 1/04/89 1'(Li + 1.1 Mi) = the skin dose factor due to beta and gamma emissions from each noole gas radionuclides i released. g Megg ={(Mi* f i)Where:Meff = the effective air dose factor due to gamma emissions from all noble gases released.Mi
= the air dose factor due to gamma emissions from each noble gas radionuclides i released. ,
1 Neff = E(Ni
- f i)
Where:Neff = the effective air dose factor due to beta emissions from all noble gases released.Ni = the air dose factor due to beta emissions from each noble gas radionuclides i released.Normally, it would be expected that past radioactive effluent data would be used for the determination of the effective dose factors. However, the noble gas releases from Hope Creek have a short history. So, to provide a reasonable basis for the derivation of the effective noble gas dose factors, the source terms from ANSI N237-1976/ANS-18.1, " Source Term Specifications",Table 5 has been used as representing a typical distribution.The effective dose factors as derived are presented in Table C-1. I!l Application To provide an additional degree of conservatism, a factor of 0.50 is introduced into the dose calculational process when the effective dose transfer factor is used. This conservatism !provides additional assurance that the evaluation of doses by the {use of a single effective f actor will not significantly underestimate any actual doses in the environment.For evaluating compliance with the dose limits of Technical Specification 3.11.2.2, the following simplified equations may be i 1used:3.17E-08 g Dg = -----
- X/Q
- Meff * (( Qi ,
i 0.50 !I and 1 lC-3 Rev. 10
l -lifl
- j. c i 1 4 Hop. ' Creek.ODCM. 1/04/89-l .:
r.
"/ .
3.17E-08 Neff * {Qi Db'. =: -----X/Q 0.50 Lir '
' Where:
Og .= air dose due to. gamma emissions for the cumulative release of all noble gases (mrad)Db
= air dose due to beta emissions for the cumulative release of all noble gases (mrad)
X/O. = atmospheric dispersion to the controlling. site boundary (sec/m3)Meff = 8.lE3,t effective gamma-air dose factor (mrad /yr per uCi/m 3)Neff = 8.5E3, effective beta-air dose factor (mrad /yr' )per uCi/m3) q Qi = cumulative release for all noble gas radionuclides (uCi) 3.17E-08 = conversion factor (yr/sec)() 0.50 = conservatism factor to account for the variability in the: effluent data iCombining the constants, the dose calculational equations i simplify to:Dg = 5.14E
- X/Q * { Qi Db_
= 5.39E-4
- X/Q * {, Qi The effective dose factors are to be used on a limited basis for the purpose of facilitating the timely assessment of radioactive effluent releases, particularly during periods of computer 3 malfunction where a detailed dose assessment may be unavailable. j
-. i .i C-4 Rev. 10
Hope Creek ODCM 1/04/89 Oi Il lI Il APPENDIX D TECHNICAL BASIS FOR EFFECTIVE DOSE PARAMETER GASEOUS RADIOACTIVE EFFLUENT
]
l l1
)
l ll 1l Ji iO i D-1 Rev. 10
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Hope Creek ODCM1/04/89 L,l()TABLE C-1 Effe.ctive Dose Factors Noble Gases - Total Body and Skin LTotal Body. Effective Skin Effective.Keff (L + 1.1 M) eff Radionuclides fi* (mrem /y per uCi/m3) (mrem /y per uCi/m3)Kr83m- 0.01 ------ ------Kr85m 0.01 1.0El 2.8El
.Kr87 0.04 2.4E2 6.6E2 Kr88 0.04 5.9E2 7.6E2> ;
Kr89 0.27 4.5E3 7.9E3 "Xel33 0.02 5.9E0 1.4El Xel35- 0.05 9.0El '2.0E2 Xel35m 0.06 1.9E2 2.6E2 1 Xel37 0.31 4.4E2 '4.3E3 'Xel38- 0.19 1.7E3 -2.7E3 TOTAL 7.8E3 1.7E4 Noble Gases - Air Gamma Air Effective Beta Air Effective Meff Neff Radionuclides fi* (mrad /y per uCi/m3) (mrad /y per uCi/m3)Kr83m 0.01 ----- 3.0E0 Kr85m 0.01 1.2El 2.0E1 Kr87 0.04 2.5E2 4.lE2 Kr88 0.04 6.lE2 -2.0E2' Kr89 0.27 4.7E3 2.9E3 Xe133 0.02 7.0E0 2.lEl Xe135 0.05 9.6El 1.2E2 Xe135m 0.06 2.0E2 4.4E1 l Xel37 0.31 4.7E2 3.9E3 Xe138 0.19 1.8E3 9.0E2 TOTAL 8.lE3 8.5E3
- Based on noble' gas distribution from ANSI N237-1976/ANS-18.1,
" Source Term Specification".
O C-5 Rev. 10- _ _ _ _ - _ _ _ - _ _ - - - _ _ __-__ = - _ - - _ .
t ll Hope Creek ODCM 1/04/89 APPENDIX D Technical Basis'for Effective Dose Parameter Gaseous Radioactive Effluent Releases The pathway dose factors for the controlling infant age group were evaluated to determine the controlling pathway, organ and radionuclides. This analysis was performed to provide a simplified method for determining compliance with Technical Specification 3.11.2.3. For the infant age group, the controlling pathway is the grass - milk - cow (g/m/c) pathway.An inf ant receives a greater radiation dose f rom the g/m/c pathway than any other pathway. Of this g/m/c pathway, the maximum exposed organ including the total body, is the thyroid, and the highest dose contributor is radionuclides I-131. The results of this evaluation are presented in Table D-1.For purposes of simplifying the details of the dose calculation process, it is conservative to identify a controlling, dose significant organ and radionuclides and limit the calculation process to the use of the dose conversion factor for the organ and radionuclides. Multiplication of the total release (i.e.,cumulative activity for all radionuclides) by this dose conversion factor provides for a dose calculation method that is simplified while also being conservative.For the evaluation of the dose commitment via a controlling pathway and age group, it is conservative to use the infant, g/m/c, thyroid, I-131 pathway dose factor (1.67E12m2 mrem /yr per uCi/sec). By this approach, the maximum dose commitment will be overestimated since I-131 has the highest pathway dose factor of all radionuclides evaluated.For evaluating compliance with..the dose limits of Technical Specification 3.11.2.3, the following simplified equation may be i used: )Dmax
= 3.17E-8
- W
- RI-131 * ((Qi Where:
Dmax = maximum organ dose (mrem)W = atmospheric dispersion parameter to the ;controlling location (s) as identified in Table 2-3. l X/O = Atmospheric dispersion for inhalation pathway and H-3 dose contribution via other pathways (sec/m3)D-2 Rev. 10
Hope Creek ODCM 1/04/89 p.T._/' .D/0 = atmospheric disposition for vegetation, milk and-ground plane exposure pathways (m-2).01- = cumulative release over the. period of interest for radioiodines, particulate and tritium (uC1), l 3.17E-8= conversion factor (yr/sec)RI-131 = I-131. dose parameter for the thyroid for the identified controlling pathway
= 1.05t12, infant thyroid dose parameter with the I cow - milk - grass pathway controlling (m2mrem /yr .per uCi/sec)
The ground. plane exposure and inhalation pathways need not be considered when the above' simplified calculational method is used because of'the overall negligible contribution of these pathways to the-total thyroid dose. It is recognized that for some particulate radionuclides (e.g., Co-60 and Cs-137), the ground exposure pathway may represent a higher dose contribution than either the vegetation or milk pathway. However, use of the I-131 thyroid dose parameter for all radionuclides will maximize the J organ dose calculation, 'especially considering that no other
- radionuclides has a higher-dose parameter for any organ via any A, pathway than I-131 for the thyroid via the milk pathway.
The location of exposure pathways and the maximum organ dose y calculation may be based on the available pathways in the surrounding' environment of Hope Creek as identified by the annual land-use census (Technical Specification 3.12.2). 'Otherwise, the dose will be~ evaluated based on the predetermined controlling-pathways as identified in Table 2-3.l--l lb lO D-3 Rev. 10
Hope Creek ODCM 1/04/89 OTABLE D-1 Infant Dose Contributions Fraction of Total Organ and Body Dose PATHWAYS Target Organs Grass - Cow - Milk Ground Plane Total Body 0.02 0.15 Bone 0.23 0.14 Liver 0.09 0.15 Thyroid 0.59 0.15 Kidney 0.02 0.15 Lung 0.01 0.14 h GI-LLI 0.02 0.15 TABLE D-2 Fraction of Dose Contribution by Pathway lPathway f Grass-Cow-Milk 0.92 Ground Plane 0.08 Inhalation O i, D-4 Rev. 10 l
6 Hope Creek ODCM 1/04/89-a ,:.-O 1l lAPPENDIX E l RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -l
; SAMPLE TYPE, LOCATION AND ANALYSIS E-1 Rev. 10 mK-_ -_. .n____ .a-. . . _ _ . - - _ . . .--_-n . - . . _ _ _ _ _
Hope Creek ODCM 1/04/89 APPENDIX E SAMPLE DESIGNATION Samples are identified by a three part code. The first two letters are the power station identification code, in this case "SA". The next three letters are for tha media sampled. l AIO = Air Iodine IDM = Immersion Dose (TLD)APT = Air Particulate MLK = Milk ECH = Hard Shell Blue Crab PWR = Potable Water (Raw)ESF = Edible Fish PWT = Potable Water (Treated)ESS = Sediment RWA = Rain Water (Precipitation)FPB = Beef SWA = Surface Water FPL = Green Leafy Vegetables VGT = Fodder Crops (Various)FPV = Vegetable (Various) WWA = Well Water GAM = Game The last four symbols are a location code based on direction and distance from the site. Of these, the first two represent each of the sixteen angular sectors of 22.5 degrees centered about the reactor site. Sector one is divided evenly by the north axis and other sectors are numbered in a clockwise direction; i.e., 2=NNE, 3=NE, 4=ENG, etc. The next digit is a letter which represents the radial distance from the plant:S = On-site location E = 4-5 miles off-site A = 0-1 miles off-site F = 5-10 miles off-site B = l-2 miles off-site G = 10-20 miles off-site C = 2-3 miles off-site H = >20 miles off-site D = 3-4 miles off-site The last number is the station numerical designation within eah sector and zone; e.g., 1,2,3,... For example, the designation SA-WWA-5D1 would indicate a sample in the SGS program (SA),consisting of well water (WWA), which had been collected in sector number 5, centered at 90' (due east) with respect to the reactor site at a radial distance of 3 to 4 miles off-site, (therefore, radial distance D). The number 1 indicates that this is sampling station #1 in that particular sector.O 11 1E-2 Rev. 10 L_____ _ __ _. l
g Hope Creek ODCM- 1/04/89 L
. )
U. SAMPLING LOCATIONS l LAll sampling. locations and specific information about the individual
. locations are:given in Table E. Maps E-1 and E-2.show the locations- 'of sampling stations with respect to the site.
i TABLE E-1 l STATION ~CODE- STATION LOCATION SAMPLE TYPES 2S2. 0.4 mi. NNE of vent IDM 3S3 700 ft. NNE of vent; fresh water holding WWA tank SS1' 'l.0 mi. .E of. vent; site access. road AIO, APT,IDM 6S2 0.2 mi. ESE of' vent; observation building IDM 7S1 0.l'2 mi. SE of vent; station personnel gate- IDM
-10S1 0.14 mi. SSW of vent; site shoreline IDM ; 11S1. 0.09 mi. SW of vent; site shoreline IDM g
llAl 0.2 mi. W of vent; outfall area ECH,ESF,ESS, SWA
- 15A1 0.3 mi. NW of vent; cooling tower blowdown ESS L ' discharge line
'16Al 0.7 mi. NNW of vent; south storm drain ESS discharge line l
12Cl 2.5 mi. WSW of vent; west bank of Delaware ECH, ESP,ESS, River SWA 4D2 3.7 mi. ENE of vent;.Alloway Creek Neck Road IDM SD1 3.5.mi. E of vent; local farm AIO, APT,IDM, WWA 10D1 3.9 mi. SSW of vent; Taylor's Bridge Spur IDM 11D1 3.5 mi. SW of vent GAM ll 14D1 3.4 mi. WNW of vent; Bay View, Delaware IDM 2El 4.4 mi. NNE of vent; local farm IDM OE-3 Rev. 10
Hope Creek ODCM 1/04/89' {;TABLE E-1 (Cont'd)STATION CODE STATION LOCATION SAMPLE TYPES 3El 4.1 mi. NE of vent; local farm FPB,FPV, GAM, IDM,VGT,WWA ;3E2 5.7 mi. NE of vent; local farm FPV 7El 4.5 mi. SE of vent; 1 mi. W of Man Horse ESP,ESS,SWA Creek 9El 4.2 mi. .' of vent IDM llE2 5.0 mi. SW of vent IDM 12El 4.4 mi. WSW of vent; Thomas Landing IDM 13E1 4.2 mi. W of vent; Diehl House Lab IDM 13E3 4.9 mi. W of vent; local farm VGT 16El 4.1 mi. NNW of vent; Port Penn AIO, APT,IDM 1F1 5.8 mi. N of vent; Fort Elfsborg AIO, APT,IDM 1F2 7.1 mi. N of vent; midpoint of Delaware River SWA 1F3 5.9 mi. N of vent; local farm FPL,FPV 2F2 8.7 mi. NNE of vent; Salem Substation AIO, APT,IDM, RWA l 2F3 8.0 mi. NNE of vent; Salem Water Company PWR, PWT 2F4 6.3 mi. NNE of vent; local farm FPV 2FS 7.4 mi. NNE of vent; Salem High School IDM 2F6 7.3 mi. NNE of vent; Southe.rn Training IDM Center 2F7 5.7 mi. NNE of vent; local farm MLK,VGT 3F2 5.1 mi. NE of vent; Hanco*cks Bridge IDM i Municipal Building 3F3 8.6 mi. NE of vent; Quinton Township School IDM 5F1 6.5 mi. E of vent FPV,IDM OE-4 Rev. 10
c a
^ , >g 9
j ,t;- .[' Hope Creek ODCM 1/04/89 1 4 '
' TABLE E-1 (Cont'd)
STATION
, o CODE STATION' LOCATION SAMPLE TYPES 5F2 7.0 mi. E of vent; local farm VGT k 6F1 6.4 mi. ESE of vent; Stow' Neck Road IDM 7F2: 9.1 mi. SE of vent; .Bayside, New Jersey IDM 10F2 5.8 mi. SSW of vent IDM llF1 6.2 mi. SW of' vent; Taylor's Bridge Delaware IDM llF3 5.3 mi. SW of vent; Townsend, Delaware MLK,VGT 12F1 9.4 mi. WSW of vent; Townsend Elementary IDM-School 13F2 6.5 mi. W of vent; Odessa, Delaware IDM 13F3' 9.3 mi. W of vent; Redding-Middle' School, IDM Middletown, Delaware . l d r'4 9.8 mi. W of vent; Middletown, Delaware IDM
{
.14F1 5.5 mi. WNW of vent; local farm MLK,VGT 14F2 6.6 mi. WNW of. vent; Boyds Corner IDM 14F3 5.4 mi. WNW of vent;. local farm' FPV 15F3 5.4 mi. NW of vent IDM 16F1 6.9 mi. NNW of vent; C&D-Canal ESS,SWA.
16F2 8.1 mi. NNW of. vent; Delaware City Public IDM ll School l1G1 10.3 mi. of N of vent; local farm FPV 1G3- 19 mi. N of vent; Wilmington, Delaware IDM 2G1 12 mi. NNE of vent; Mannington Township, NJ FPV 3G1 17 mi. NE of vent; local farm IDM,MLK,VGT 10G1 12 mi. SSW of vent; Smyrna, Delaware IDM E-5 Rev. 10
7,-- ;i Hope Creek ODCM 1/04/89
\
I TABLE E-1 (Cont'd) l STATION l CODE' STATION LOCATION SAMPLE TYPES l l 16G1 15 mi. NNW of vent; Greater Wilmington IDM Airport j
-3H1 32 mi. NE of vent; National Park, New Jersey IDM j i
3H3 110 mi. NE of vent; Research and Testing AIO, APT,IDM 4 Laboratory. f j 3H5 25 mi. NE of vent; local farm FPL,FPV i il lO I1 li I
)
i lE-6 Rev. 10 I I
\
i Hope Creak ODCM 1/04/89
) SAMPLE COLLECTION AND ANALYSIS ~J' Sample Collection Method Analysis Air Particulate Continuous low volume Gross Beta analysis air sampler. Sample on each weekly collected every week sample. Gamma along with the filter spectrometry shall change. be performed if gross beta exceeds l 10 times the yearly mean of the control station value. As well one sample is analyzed >24 hrs after sampling to allow for radon and thoron daughter decay. Gamma isotopic analysis on quarterly composites.
Air Iodine A TEDA impregr.ated Iodine 131 analysis
<^N charcoal cartridge is are performed on
( ')'~connected to air articulated air sampler each weekly sample.and is collected weekly at filter change.Crab and Fish Two batch samples are Gamma isotopic sealed in a plastic analysis of edible bag or jar and frozen portion on collection semi-annually or when in season.i Sediment A sediment sample is Gamma isotopic analysis i taken semi-annually.semi-annually.Direct 2 TLD's will be Gamma dose quarterly collected from each location quarterly.Milk Sample of fresh milk Gamma isotopic is collected for each analysis and I-131 farm semi-monthly when analysis on each cows are in pasture, sample on collection.monthly at other times.E-7 Rev. 10, - _ _ _ . . k
Pi,[~ il, i, oj,: 1
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- i. . ... F2GURE E-2' c r.
1 (... t CNS8TE SAMPLING LOCAT20NS h1 m -4 3,T% hk{j . .. '""'
, , , , ornt f .
g, 99 89h' .
-it ' e . 0, i pg ! 99 ges ar I L ' $Y ,I. .6 '
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i i_ _ _ - - . b
,i Hope Creek ODCM 1/04/89 l \ >~.: ,' ') SAMPLE COLLECTION AND ANALYSIS (Cont'd) -j x _s' (
Sample Collection Method Analysis Water (Rain,- Sample to be collected Gamma isotopic Pocable, Surface) monthly providing winter monthly H-3 on /icing conditions allow. quarterly surface sample, monthly on ground water sample.I[
<_,\
, 1 jl' tr'^T, L t E-8 Rev. 10 l 1x-- ___ _ _ _ k
FIGURE E-1 OFFSITE SAMPLING LOCATIONS j; , & [ '% .[' t, D.2C1 '3H3 y
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