ML20235M522

Technical Evaluation Rept for Radiological Effluent Release & Environ Operating Repts for 1985 - Southern California Edison Co,San Onofre Nuclear Generating Station Units 2 & 3, Informal Rept

ML20235M522
Person / Time
Site:	San Onofre
Issue date:	05/31/1987
From:	Magleby E, Thomas Young EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML13304B705	List: ML20235M522
References
CON-FIN-A-6808 EGG-PHY-7603, NUDOCS 8707170222
Download: ML20235M522 (183)

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{{#Wiki_filter:,,.... - s, EGG-PHY-7603 E. May, 1987 I v-INFORMAL REPORT s l aO ? National - TECHNICAL EVALUATION REPORT FOR THE RADIOLOGICAL EFFLUENT RELEASE AND ENVIRONMENTAL OPERATING 1 Engineering 1 REPORTS FOR 1985 - SOUTHERN CALIFORNI A EDISON Laboratoty:' COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 ' Managed : by the U.S. T. E. Young Department E. H. Magieby o/ Energy W. Serrano T. S. Bohn J. W. Mandler F. B. Simpson i f1 .[EGnG,on. 1 Y L.y Prepared for the U. S. NUCLEAR EGulATORY CRHISSIGi . - 5 ' Work per/ormed under. l* DOE Contract No, DE-AC07-761D01570 87071 0222 B70E01 I PDR ADOCK 05000361 P PDR

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EGG-PHY-7603 'l TECHNICAL EVALUATION REPORT for the l RADIOLOGICAL EFFLUENT RELEASE AND ENVIRONMENTAL OPERATING REPORTS FOR *.985 SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNITS 2 AND 3 NRC DOCKET NOS. 50-361 NRC LICENSE NOS. NPF-10 50-362 NPF-15 T. E. Young, E. H. Magleby, W. Serrano, T. S. Bohn, J. W. Mandler, and F. B. Simpson Published May 1987 EG&G Idaho, Inc. Idaho Falls, Idaho 83415 l Prepared for the l U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Under DOE Contract No. DE-AC07-761D01570 FIN No. A6808

ABSTRACT. A review was performed of report.s required by Federal regulations 3 and the plant-specific' radiological. effluent technical specifications (RETS) for operations conducted at San Onofre Nuclear Generating ' Station, Units 2 and 3 during 1985. The periodic. reports reviewed were (a) the. semiannual ' radioactive effluent and solid waste disposal- . reports for 1985, and (b) the annual radiological environmental operating report for 1985. These and earlier reports were also.used to evaluate trends in radioactivity releases,'offsite doses'and radioactivity of environmental samples over the time period 1984 and l 1985. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. The San'Onofre Units 2 and 3 Offsite Dose Calculation Manual (0DCM) consisting of Revision 17 dated 06-15-85 was reviewed. The ODCM uses methods that' are generally in agreement with the guidelines of NUREG-0133 with the exception of considering simultaneous releases from the radioactive j gaseous release points. Because of this exception, it is uncertain if- ) the methodology provides reasonable assurance that the NUREG-0472 dose rate limits will not be exceeded. The Licensee submitted minor changes to their generic Process Control Program (PCP) 'which presently has interim NRC approval. The reported changes were reviewed and it is { recomtr.anded the interim NRC approval be extended to include the f reported changes. I l l. l .j q i

FOREWORD This report is supplied as part of the " Selected Operating Reactor Issues Program (III)" being conducted for the U.S. Nuclear Regulatory - i Commission, Office of Nuclear Reactor Regulation, Planning and Program Analysis Staff, by the INEL, Radiological Physics. o The U.S. Nuclear Regulatory Commission funded the work under the authorization B&R 20 19 10 11 1, FIN A6808. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warrant, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, coparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately-ovned rights. 4

CONTENTS P_aSe .i Abstract.. -i Foreword....... ii l 1. Introduction.......................... 1 2. T e c h n i c al S umma ry........................ 2 2.1 Plant-Specific Background................. .2 2.2 Radioactive Effluent Releases............... 3 2.3 Radiological Dose Impact. -8 2.4 Radiological Environmental Monitoring Program. 15 10 2.5 Revisions to ODCM, PCP, and Radwaste Treatment Systems... 2.6 Analysis of Release, Dose, and Environmental Trends.... 15 2.7 Information Contained in Licensee's' Reports.'....... 22 1 3. Conclusions........................... 26: j 4. References........................... 29 Appendix A. Plant and Site Design Features Al Appendix B. Summary of Radioactive Effluent Releases and Cal cul ated Doses..............-....... : B1 Appendix C. Radiological Environmental Monitoring. l Program Results.....................C1 i .) Appendix D. Evaluation of Changes to the ODCM, PCP, and Radwaste Treatment Systems............... D1 Appendix E. Tables of Licensee's Report Commitments........ E1 Appendix F. Checklist of RETS-Required Reports... F1 TABLES-2-1 Summary of Reported Radioactive Effluents / Exposures for'1985.. 5 2-2 Outline of Radiological Environmental Monitoring Program.... 11 2-3 Liquid and Gaseous Radioactive Effluent Releases, Solid Waste Shipments, and Exposure Data for 1984 and 1985......... 16 2-4 Direct Radiation and Gross Beta Activity.... '........ 20 l iii

FIGURES .Pate 2-1 Radioactivity of effluents from Sen Onofre Nuclear Generating Station Units 2 and 3 and calcule.ted offsite doses for 1984 and 1985......................... 17 2-2 Levels of radioactivity in the environs of San Onofre Nuclear Generating Station Units 1, 2, and 3 for 1984 and 1985..... 21 O i i l J l i 1 iv .i........... , _...........i

I 1. INTRODUCTION This Technical Evaluation Report presents a review and summary of the reports submitted by the Licensee of San Onofre Nuclear Generating { Station Units 2 and 3 in accordance with the plant's Radiological i Effluent Technical Specifications (RETS) for operations conducted { during 1985. The principal review guidelines were the plant's 1 RETSE13 (which follow NRC recommendations contained in NUREG-0472[2]), NRC guidance given in NUREG-0133, " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants,"E33 and NRC memorandum guidance " Criteria for Process Control Program."E43 Special emphasis is placed on any reportcd changes to the Licensee's Process Control Program (PCP), Offsite Dose Calculation Manual (ODCM), and radioactive waste treatment system. This report also includes results of a survey of reported releases j of radioactive materials, calculated doses and dose commitments to 1 persons in unrestricted areas, and radioactivity levels in environmental media. A summary of trends from available data for the years 1984 and 1985 is included. i 1 a l 1 l

I l 2. TECHNICAL

SUMMARY

1 2.1 Plant-Specific Background e The San Onofre Nuclear Generating Station (SONGS) consists of three reactors owned and operated by Southern California Edison Company in Southern California about 5 miles southeast of San Clemente. Plant-specific information pertinent to this review is given below for Units 2 and 3 of the three San Onofre units. Type of Reactors PWR (Combustion Engineering) (both units) l Licensed Thermal Power Unit 2 3410 MWt Unit 3 3390 MWt Maximum Dependable Power Unit 2 1070 MWe Net Unit 3 1080 MWe Net Commercial Operation Unit 2 August 8, 1983 4 Unit 3 April 1, 1984 RETS Implementation (Issued Unit 2 February 16, 1982 with low power license) Unit 3 November 15, 1982 Condenser Cooling Water Once through to Pacific Ocean System (both units) 4 Major Gaseous Discharge Plant Vent Stack, Elev. 206.75 f t. l Point (175 ft. above grade) l Unit 2 Unit 3 Gross Electric Output 1984: 5,577,914 MWh 4,968,689 MWh 1985: 5,480,329 MWh 4,004,575 MWh Average Capacity Factor 1984: 56.35% 50.19% 1985: 55.51% 40.56% l I The circulating water system operates in the once-through mode, with water being taken from and discharged to the Pacific Ocean via intake and discharge conduits. The " site boundary for gaseous effluents" is i essentially a pair of 1967.5 ft.-radius circles centered at Units 2 and 3. l 2

l l Radioactive gaseous effluents are discharged via four vents (three chimneys) for each unit: (1) Containment Purge Vent Stack (160 ft. above grade), (2) Continuous Exhaust Vent Stack (160 ft. above grade) which is ~ l also called the plant vent stack and is the release pcint for the waste gas decay system as well as continuous releases, (3) Main Condenser Exhaust (43 ft. above grade), and (4) Turbine Gland Seal Exhaust (43 ft. I above grade). The containment vent and the exhaust vent release gases out a single chimney which is divided by a septum creating two separate I discharge pathways (i.e., containment vent and continuous exhaust vent). These gaseous effluent releases points are considered as ground level releases. A map of the plant area showing gaseous and liquid effluent release points is shown in Appendix A along with diagrams of the liquid and gaseous radwaste effluent pathways. (The Unit 3 continuous exhaust vent stack is apparently omitted from the figure, A-2.) l 2.2 Radioactive Effluent Releases Reported radioactive effluents during 1985 were low enough for the calculated doses to fall well within 10 CFR 50 Appendix I guidelines. There were no abnormal liquid releases reported by the San Onofre Nuclear Generating Station during 1985, but they did report one abnormal (unplanned) gaseous release that resulted in the release of 306 Ci of Xe-133. A summary of the radioactive effluents, solid waste shipments, effluent dilution, and radiological dose impact data for 1985 provided by the Licensee in the two effluent and waste disposal semiannuai reports is presented in Table 2-1 and in the following paragraphs. Quarterly data for 1984[5,6] and 1985[7,8] are compiled in the tables of Appendix B. 2.2.1 Liquid Effluent Releases i There are three nuclear power units at the San Onofre site. Units 2 I and 3 share a common liquid radwaste treatment system and the liquid radwastes are released to the Unit 2 circulating water outfall pipe which returns Unit 2 main condenser cooling water to the Pacific Ocean between 6000 ft. and 8500 ft. from the reactor. Since the liquid radwaste system of Units 2 and 3 is served by a dilution stream 3

separate from the Unit 1 dilution stream, the liquid releases frem Units 2 and 3 may be made independently of releases from Unit 1. 1 i Liquid radwaste from Units 2 and 3 are released to the Unit 2 outfall i line in both the batch and continuous modes. The Licensee's Technical Specifications require monitoring, with automatic termination of release j if high radioactivity is detected, of the Liquid Radwaste Effluent Line, the Steam Generator Blowdown (Neut calization Sump) Effluent Line, and the Turbine Building Sumps Effluent Line. The Liquid Radwaste Effluent Line is a pathway for batch releases and the other two are pathways for continuous releases. The Offsite Dose Calculation Manual (ODCM) also i requires monitoring of other pathways by which radioactive liquids may be released from the site. (See Appendices A and D.) Several important aspects of the Licensee's 1985 liquid effluent releases are noted as follows: Releases were made in both the batch and continuous mode during 1985. Approximately 11.2 Ci of fission and activation products and 475 Ci of tritium were released. The most abundant radioisotopes among th? fission and activation products were Cs-137 (25.3%), Co-58 (15.3%), Cs-134 (12.7%), and Cr-51 (10.1%). A total of 1,851 GL was reported as the dilution water volume during 1985. There were no abnormal liquid releases reported during 1985. 2.2.2 Gaseous Effluent Releases There are six gaseous effluent monitored release points for Units 2 and 3: Unit 2 continuous exhaust vent stack, Unit 3 continuous exhaust 4

TABLE 2-1.

SUMMARY

OF REPORTED RADI0 ACTIVE EFFLUENTS / EXPOSURES FOR 1985 I. ACTIVITY RELEASED Solid Waste and Liquid Effluents Gaseous Effluents Irradiated Fuel Shipments i A. Fission and Activa-A. Particulate A. Spent Resins, Filter tion Products Sludge, Evaporator { Bottoms, etc. Total: 11.2 Ci Total: 0.0612 Ci Units 2/3; 471 Ci Cs-137 2.84 (25.3%) Rb-88 0.0475 (77.6%) Common: 0 Ci j Co-58 1.71 (15.3%) Cs-138 0.00852 (13.9%) Cs-134 1.43 (12.7%) Fe-55 0.00190 (3.1%) Cr-51 1.13 (10.1%) Cs-137 0.00123 (2.0%) l Co-60 0.929 (8.3%) 1-131 0.594 (5.3%) Nb-95 0.490 (4.4%) B. Tritium B. Tritium B. Dry Compressible Waste, Contaminated Equipment, etc. Total: 475 Ci Total: 7.98 Ci Units 2/3; 53.8 Ci ) Common: 0.501 Ci i C. Dissolved or En-C. Noble Gases C. Irradiated Components trained Noble Gas Control Rods, etc. Total: 92.0 Ci Total: 25,300 Ci Units 2/3; 0.956 Ci Xe-133 87.5 (95.2%) Xe-133: 23,700 (93.5%) Common: 0 Ci Xe-135: 1,220 (4.8%) D. Gross Alpha D. Iodines D. Other (filter, sludge, sand / rubble, wet trash) Total: None Total: 0.503 Ci Units 2/3; 198.67 Ci 1-131: 0.442 (87.9%) Common: 0.395 Ci 1-133: 0.0502 (10.0%) E. Batch Releases E. Batch Releases E. Disposal Site Not discussed Not discussed Richland, WA F. Abnormal Releases F. Abnormal Releases F. Irradiated Fuel None One: 306 Ci Xe-133 None 5 1

TABLE 2-1.

SUMMARY

OF REPORTED RADIOACTIVE EFFLUENTS / EXPOSURES FOR 1985 (Cont.) II. EFFLUENT DILUTION A. Liquid Effluents Circulation Dilution-Circulation Flow Rate Discharge Volume ~ System (GL/yr)a Mode (GL)a Once-through mode Not reported Batch and Con-1851 to/from Pacific Ocean tinuous Mode B. Gaseous Effluents-(NRC Parameters for Maximum Doses.- Continuous Release)b X/0 (sec/m ) D/0(m-21 Location Release Type 8 III. MAXIMUM INDIVIDUAL DOSES Liquid Effluents Gaseous Effluents Direct Radiation A. Total Body Dose A. Noble Gas Air Dose 0.804 mrad (4.02%jc 0.802 mrem /300 hrs 0.449 mrem (7.48%)c Gamma: ~ 2.22 mrad (5.55%) (At San Onofre State Beta: Beach, Unit 1)- B. Organ Dose B. Organ Doses (I-131, long-lived particulate, and tritium.) 5.06 mrem (25.3%)c 0.405 mrem (1.35%) Critical organ: Critical Organ: (GI-LLI) Child thyroid

a. GL (gigaliter) = 10' liters.

b. NRC staff evaluation for 10 CFR 50, Appendix 1.

(Data were not available to the reviewers.)

c. Percent of 10 CFR 50, Appendix I guideline per year (which is also equal to the Licensee's technical specification reporting level).

6

W". vent stack, Unit 2 containment purge vent stack, Unit 3 containment purge vent stack, Unit 2 main condenser evacuation system exhaust, and Unit 3 condenser evacuation system exhaust. (The turbine gland seal exhausts are 4 not monitored.) A simplified diagram of the waste gas treatment system for Units 2 and 3 is shown in the Figures of' Appendix A. Several important aspects of the' Licensee's 1985 gaseous releases are i as follows: l l Releases were made both in batch and continuous mode, a Total gaseous releases included 25,300 Ci of noble gases,.0.503 e Ci of radiciodines and 0.061.2 Ci of particulate. A total of 7.98 Ci of tritium was released. The most abundant radioisotopes in each gaseous group were Xe-133 for noble gases (93.5%), I-137. for radioiodines (87.9%), and Rb - for particulate (77.6%). 1 There was one abnormal gaseous release reported during 1985, e consisting of 306 Ci of Xe-133. 2.2.3 Solid Radioactive Waste and Irradiated Fuel Shipments i Information on the Licensee's 1985 shipments of solid radwaste offsite is presented in Appendix B and is summarized below for the San Onofre Nuclear Generating Station, Units 2 and 3. Waste shipments from the San 4 Onofre site are from Units 2 and 3, Unit 1, and from common site sources, and in actuality, shipments are from the San Onofre site as a whole. + a. The terms " noble gases" and " fission and activation gases" are used interchangeably in this report to refer to gaseous effluents whose radioactivity;is normally dominated by the activity of noble gases. i 7

1 A total of 35.03 m8 of solid radwaste containing 471.0 Ci of activity consisting of spent resins, filter sindges, evaporator bottoms, etc. was shipped offsite, from Units 2 and 3. l I' e A total of 403.0 m8 of dry compressible waste with an activity of 53.8 Ci was shipped offsite, from Units 2 and 3. ) l of irradiated components, control rods, etc. A total of 1.49 m5 containing 0.956 Ci of activity was shipped during 1985 from Units j l 2 and 3. I i l i of other waste (filters, sludges, rubble, j A total of 105.3 m8 etc.) with an activity of 198.67 Ci was shipped offsite from Units ) 2 and 3. l 1 40 shipments were made by truck to the Richland, WA burial site. These shipments would include waste from Units 2 and 3, Unit 1, I and from common site waste. I l A total of 15.63 m8 of waste with an activity of 0.896 Ci from Units 1, 2 and 3 was shipped offsite, consisting of mainly dry compressible waste and filters, sludges, etc. l The Licensee stated that cement was the solidification agent used i during the first half of 1985. Resins, etc. were shipped in High j Integrity Containers during the second half of the year.. No shipments of irradiated fuel were reported from the San Onofre Nuclear Generating Station during 1985. 2.3 Radiological Dose Impact As seen in Table 2-1, the reported San Onofre Nuclear Generating Station, Units 2 and 3 offsite dose impact during 1985 was, in all cases, well below the reporting levels specified in the RETS with 25.3% of technical specification limits in the worst case. 8 i

A summary of the 1985 maximum dose to individuals beyond the site boundary or in unrestricted areas for liquid and gaseous releases is presented in the following paragraphs. 2.3.1 Liquid Effluent Dose i The following calculated maximum liquid effluent doses were reported by the Licensee: The whole body dose was 0.449 mrem (7.48% of the technical specification reporting level of 6 mrem for two units)a, The critical organ was identified as the adult GI-LLI, with a dose of 5.06 mrem (25.3% of the technical specification reporting level of 20 mrem to any organ except the thyroid for two units)a, j 2.3.2 Gaseous Effluent Dose l 4 The following gaseous effluent doses were reported by the Licensee: The gamma air dose during 1985 was 0.804 mrad (4.02% of the I technical specification reporting level of 20 mrad for two units)a, I The beta air dose during 1985 was 2.22 mrad (5.55% of the e technical specification reporting level of 40 mrad for two units)a, The maximum organ dose due to iodines, particulate and tritium e was 0.405 mrem to the thyroid of a child (1.35% of the technical specification reporting level of 30 mrem for two units)a, 2.3.3 Total Dose 1 l l a. The 10 CFR 50, Appendix dose limits are doubled for the two units addressed in the reports reviewed here. 9

l l I To show compliance with the fuel-cycle-dose limits of 40 CFR 190, the Licensee reported an annual total body dose of 11.2 mrem and an organ dose of 6.62 mrem to the GI-LLI. These values are 44.8% and 26.5%, respectively, of the 40 CFR 190 limits of 25 mrem to the total body and any organ except the thyroid. The annual thyroid dose reported was 8.47 { mrem, or 11.3% of the 40 CFR 90 limit of 75 mrem. These doses appear to be the result of summing the doses due to liquid effluents, direct I radiation, and doses due to gaseous effluents (calculated using historical meteorology). Dose calculations using historical meteorology gave significantly higher doses due to gaseous effluents than corresponding doses (also reported) calculated using concurrent meteorology. Dose l contributions from Units 1, 2, and 3 were included in the 40 CFR 190 i calculations. The Licensee stated that there ara no other nuclear fuel ] cycle sources within 8 km. 2.4 Radiological Environmental Monitoring Program The Licensee's annual radiological environmental monitoring report [9] presents both raw and summarized data obtained from the analyses of a large number of environmental samples collected during 1985. The monitoring program reported is summarized in Table 2-2. More i i detailed information on the program and a tabulation of results are given in Appendix C. Most of the Licensee's analyses results were below the lower limits of detection (LLDs) reported for environmental samples. These LLDs ranged from 5% to 100% of the maximum LLDs specified in the Licensee's HETS. The report also included an LLD of 5 mrem for direct radiation. The only radionuclides detected that were attributable to operation of Units 2 and 3 were Co-58, Co-60, 1-131, and Cs-137. Co-58 and Co-60 were detected at up to 30% above the maximum LLD in marine animal flesh samples taken from near the Unit 2/3 outfall. Corresponding samples contained Cs-137 at levels between the LLD reported and the maximum LLDs specified in the Licensee's RETS. (Somewhat higher Co-58 and Co-60 activities were detected near the Unit 1 outfall, but the highest was less than 20% of the reporting level.) I 10 l

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The Licensee's results from kelp monitoring (not required. by the technical specifications) were inconclusive. Co-60 and Cs-137 were detected above the LLDs in one of seven samples at indicator locations and Cs-137 in one of three samples at the control location. 1-131 was detected in five of seven samples from indicator locations and in two of three samples from the control locations. The average activity at indicator locations was 0.027 pCi/g l compared to 0.038 pCi/g at the control location. l l Particular emphasis in the program was placed on detection of direct radiation, airborne I-131, radioactivity in airborne particulate, and radioactivity in non-migratory marine animals. Highlights of the results are summarized below: Gross beta analyses of 423 airborne samples from 8. indicator locations gave a mean of 0.020 pCi/m, and analyses of 53 samples from one 8 control location gave 0.021 pCi/m. 8 l 1-131 was detected in nine airborne samples out of 423 samples from. indicator locations at a mean of 0.373 pCi/m, compared to <LLD 8 ~ activity at the control location. ( All samples in which I-131 was detected were within the exclusion area boundary.) Gross beta and gamma spectrum analyses of ocean water samples indicated-e negligible plant effect. i Gross beta activities in drinking water samples from indicator e locations were comparable. The Licensee states, "None of the radioactivity in either the monthly or quarterly drinking water samples can be attributed to SONGS since liquid effluents are released solely to the ocean". l l Detectable levels of Co-58, Co-60, and Cs-137 (at less than 0.5% of the I reporting levels) were measured in marine animal flesh samples (primarily in the mollusks, Bay Mussel and Sea Hare) taken near the Unit 2/3 outfall. (Samples of Sea Hare from the area of the Unit 1 outfall contained Co-60 at up to 20% of the reporting level.) 12 )

2.4.1 Direct' Radiation In the discussion of direct radiation the' Licensee stated that,except for the SONGS meteorological tower (which is within the exclusion area) the plant operations'"had negligible impact on this environmental medium." Excluding results from the onsite meteorological tower and the " Transit Dose" and " Transit Storage Location" TLDs, the mean doses were 20.5 mrem /qtr for stations at less than 2 miles, 20.7 mrem /qtr for stations between 2 and 5 miles, 20.2 mrem /qtr for stations et greater than 5 miles, and 22.6 mrem /qtr for the control station (at 37 miles). The NRC conducted a direct radiation monitoring' program' comparable to that performed by the Licensee! (See. Tables'C-1 and C-4 of Appendix C.)' The NRC's corresponding measurements were 10% lower than<the Licensee's at less-than 2 miles, 6% lower at 2-5 miles,14% lower at greater than 5-railes, and 3% higher at the control locations. 2.4.2 Airborne Gross Beta and I-131 Activities Airborne gross beta activity measured at the control location was 5% higher than at the indicator location,.and the variation with time during the year showed the same fluctuations at control and indicator locations. l The Licensee stated: "The impact of SONGS on this environmental medium was insignificant." { Airborne I-131 was detected in nine samples collected onsite, but none was detected in samples taken outside the exclusion area. l 2.4.3 Waterborne and Ingestion The Licensee did not report any significant impact on the environment through water pathways (ocean water, drinking water, shoreline sediment, and ocean bottom sediment). Virtually all of the radioactivity detected in ocean water was attributable to K-40. Gross beta activity in drinking water at the control location was less than at the indicator locations 13 _.1 1

-= and was attributable to K-40 at all locations. All radioactivity detected in shoreline sediments was due to naturally occurring radionuclides. In -l addition to naturally occurring radionuclides, Co-60 was detected in one indicator sample and one control sample of. ocean bottom sediments. The two samples containing Co-60 were collected about one month apart and the Licensee stated that the Co-60 (at 0.090 pCi/g) may be attributable to plant effluents, but did not discuss the fact that the same concentration l was detected at an indicator location and the control location. The Licensee also stated that the impact on the environmental medium was minimal. l Non-migratory marine animals (fish, crustacea and mollusks) were the ) only media sampled that showed a non-neglible impact in' unrestricted areas due to plant operation. The highest measured radionuclude concentration, expressed as percent of reporting level, was in one sample of Sea Hare (a mollusk) collected at the Unit 1 outfall. It contained 1.9 pCi/g of Co-63. (less than 20% of the reporting level). Plant-related radionuclides observed at the Units 2/3 outfall were Co-58 and Co-60 in. Sea Hare and Bay. Mussel, which were detected at less than 2% of the reporting levels, and Cs-137 in one sample of Bay Mussel at 0.3% of the reporting level. 1 ) ~ The Licensee calculated adult whole body and organ doses assuming 21 kg consumption per year and using radionuclides concentrations observed at the Unit 1 and Units 2/3 outfalls. The highest doses calculattd were 0.201 mrem /yr to the whole body and 1.724 mrem /yr to an organ (GI-LLi) due ] to consumption of Sea Hare from the Unit 1 outfall. The highest doses l attributable to radionuclides concentrations detected at the Units 2/3 I outfall were 0.031 mrem /yr to the total body and 0.195 mrem /yr to an organ (GI-LLi) due to consumption of Bay Mussel. The Licensee noted that the I species sampled are not popular for consumption, and stated "the opera' ion c of SONGS had a minor but detectable impact on this environmental medium." 2.4.4 Land Use Census Very detailed results were reported from the annual Land Use Census required by the Licensee's Units 2 and 3 Technical Specification 3.4.12.2 14

and Unit : Technical Specification 3.18.2. The census identified no milk animals within a 5-mile radius of SONGS, but 9 sectors contained meat animals, 2 sectors contained gardens, 7 sectors contained residences and 9 sectors were used for a variety of purposes. Six of the sixteen meteorological sectors are seaward. 2.4.5 Quality Assurance program The Licensee reported results of analyses of air samples and samples of water, milk, urine, and food as a participant in an interlaboratory comparison program. About half of the approximately 120 measurements reported in the program were made on water samples. The Licensee stated "The results of interlaboratory cross-check program showed that 12% of the samples fell outside the control limit range. The errors were randomly distributed among all different sample and different analyses." The control limits shown in the report are at +1.74 times the EPA s.d. 2.5 Revisions to ODCM, PCp, and Radwaste Treatment Systems Changes to the San Onofre Offsite Dose Calculation Manual (ODCM) for Units 2 and 3 are reported to the NRC by the Licensee in the Monthly Operating Reports. The NRC transmitted the changes to INEL for review. Evaluation of the revised ODCM is given in Appendix D. Process Control Program (PCP) changes are reported in the Semiannual Radioactive Effluent Release Reports. The Jan-Jun semiannual report for 1985 included information that interim approval of a revised PCP and use of Nupac Inc. for dewatering was received.[10] The Jul-Dec 1985 report stated that a Temporary Change Notice (TCN), effective July 15, 1985, changed the free standing liquid requirement when dewatering resin to <.5% instead of <1.0%. 2.6 Analysis of Release, Oose, and Environmental Trends Radioactive effluent data and calculated dose impacts for San Onofre Nuclear Generating Station (SONGS), Units 2 and 3 for 1984 and 1985 are 15

se t t y la s u m nt 7 6 c e ei 3 2 mv) i) 4 s r t m 9 0 m 1 4 irii r e 1 4 tC 9 4 ar 0 h c( 4 2 P m 0 0 3 sA 5 7 ( e 1 t 3 s 1 a W e 1 uL m ( d 5 i l3 3 2 n 8 l om 2 8 a 9 oV( g 1 s 2 4 r 0 4 O D 2 5 N A se 4 s 8 on 9 Di 1 l) tS m A R n e . / O ear a a N F ut m m l e( A u f B T A i ) 8 f ti 4 9 E D i C 4 r( 4 7 s E T u R oy U ed S s o) O aB m P G e X s er f. E e lo( a. a. / m t D a 8 2 h N N sl A t ui) 7 1 W 1 6 ncC 0 0 ei( S ut 0 0 T l r N f a r d E f P i) a M E Ad r P a 3 2 m I s ar 6 2 H u t m 0 S o e( 2 2 4 e1 B E s3 T a1 S G - ) 8 2 A el 0 4 W D inC 4 4 ( r L3) d 0 0 i) d I o O l Ad a a 3 4 r ar 7 0 m SD mm 9 8 N m( 0 ,A a 0 0 2 S G E2 s S e AS s 0 0 ET al 0 0 LI Gi 1, 3, EN C RU e( 0 5 T l 4 2 NN, bo EO N UI LT m FA e FT r ES s ) 8 6 m enm 8 0 sa e EG 0 IVN m ogr 9 5 2 I u Dr m TT il O( CA ti t AR iC 5 5 n OE r( 5 7 e I N T 4 4 AG s lu DE f y R t fd R n E o m SA e ) B) 9 e UE ugs d m 9 4 r OL ne ee EC lfi s iul r 4 4 m 5U f d a oom 0 0 6 QN E E d lug ih( G LW c, E DR na S NF E luih) 2 2 O AO S o pl D N Aitl C 3 1 DO EL oa( 1 1 L I L n IQA R ( m, A d. UN E U D e L( Y l u I l s S e s ai V v e T tt I e r I oi D L d V T r N d 3 I t I g a T n 2 C M A U i t t o E O M r N L B I r 4 5 I r 4 5 o D a 8 8 X a 8 8 p A A e 9 9 A e 9 9 e T R Y 1 1 M Y 1 1 R a. ac n f!l

i i 2 0,-- .BO i 18 .72 Activlty g io .e4 14 - .se - 9.33 2 x o \\ a j .,j - 8. 00 en 12 .4e E 58 g 3o. --..40 g .- 6.67 t g 'n o 13 - o .32 5 - 5.33,Ej e an 6 .24 5 - 4.00 vi o i I j 5 Jo e 4 -f.c --.s e - 2.67 g p 2 -- d .08 -1.33 a o / c% .O - 0. 0 $ o 4 1951 1982 1983 1984 1985 o YEAR A A. L1 quid ef fluent a c tivity and whole body dose. 20 15.0 18 13.5 Activity G 1e 12.0 ~ m .a o 1

• ]

14-- - - - - - 10.5 y - 52.5 g u a - 45.0 p$ 12 -- 9.0 [ 8 eo I => 7.e s - 37.5 t c go._ _ _ _ Y f" o to j k Cn .y e e.O g - 30.0 gg i .E =5 e-- 4 - 22.5 v$ 3 'h 4.s N "E 2 4 3.0 - 15.0 w t 00 - 7.5 *52 2-- 1.s o O - 0. 0 E 1981 1982 1983 1984 1985 YEAR B. Liq uid ef f!uent a c tivlty and orgon dose. I I Figure 2-1. Radioactivity of effluents from San Onofre Nuclear Generating Station, Units 2 and 3, and calculated offsite doses for 1984 and 1985. 17 I 1 m.

Soooo 1.so s4ooo 1.3 s Activity e

1. '" U **

~ h 4sooo 1.2 o g o 5 5.25 g g 42o00 1.os 'a a u } .so g - 4.50 g secco O g .r= c) l M = .Q soooo .7s - 3.75 t o li E 24o00 j .so 3 - 3.00 g.h i e f E g ,eooo 0 4s Di - 2.25 m. m - 1.50 w e! A 5 s) 12000-- .so o u sooo .i s - 0.75 U S e i U o o - 0.0 ' l 1981 1982 1983 1984 195s CJ YEAR i C. Geseous effluent a ctivity and gommo oIr dose. l 1.o 1.o .9---- .9 Activity i or9 a n o... E Y 5 g .7 - .7 1 - 2.33 g ~ f u .e- .e 8 - 2. 00 en

• i s

E 5b K - 1. 67 t c. a .5 - c .s N om i 7 6- - 1. 33 E !"- 4 .4 E a: o h l 9 5 -.s 5 - 1. 00 v".8 .s .E 6 s J Tn l ); .2 -4 .2 - 0.67 %t oo .1 ? -x .1 - 0. 33 +> c / ES o-o - 0. 0 E 1981 1982 19ss 1984 198s e YEAR Q-D. Geseous ef flu e nt a c tivity and orgon dose. ~ Figure 2-1. Radioactivity of effluents from San Onofre Nuclear Generating Station, Units 2 and 3, and calculated offsite doses for 1984 and 1985 (cont.) 18 2

summarized in Table. 2-3.. Activities of fission and activation products in' liquid effluents,.of fission and activation gases, and,of radioiodines and particulate in' gaseous effluents are plotted by year in' Figure 2-1. Calculated offsite doses due to liquid and gaseous effluents are also shown in this figure. 2.6.1 Trends of Effluent Releases and Calculated Doses ] Trend; of releases of radioactive materials from San Onofre Units 2 .) and 3.and calculated offsite doses for 1984-and 1985 are discus' sed below: 1 Releases of fission and activation products in liquid effluents during 1985 were 15% below the releases in'1984. I Calculated whole body and organ doses due to liquid effluents e during 1985 were, respectively, 8% and 49% lower.than those for 1984. Releases of fission and activation gases (noble gases).in gaseous effluents during 1985 were 37% below the releases in 1984. 1 The calculated gamma air dose during 1985 was 17% below the dose e for 1984. This appears consistent with the reduction in noble gas releases since the Licensee uses concurrent meteorological data i for calculation of doses due to gaseous effluents. 1 Releases of I-131 and long-lived particulate in gaseous effluents e during 1985 were 18% higher than during 1984. (I-131 8% higher j and particulate 244% higher.) i Calculated organ dose due to I-131, long-lived particulate, and e tritium during 1985 was over twice that reported for 1984. The ( much greater increase of dose than of releases may be due to the Licensee's use of concurrent rather than historical meteorological data in the dose calculations, which would allow releases during l certain atmospheric conditions to make relatively large I contributions to the calculated dose. .19

Releases of tritium in liquid effluent's was about the same in 1985 e as in 1984. Releases of tritium in gaseous effluents during 1985 ^ was only 2% of the 1984 releases. [The 1984 releases occurred mainly in the first quarter (when Unit'2'was shut down~for primary coolant pump seal replacement) and during the fourth quarter (when Unit 2 was shut down for refueling).] Activity releases and the associated calculated doses shown in Figure 2-1 appear consistent except for the whole body and organ-doses due to liquid effluents. Based on the much higher-volume of dilution water reported for 1985 and the approximately equal release of activities, the calculated doses for 1985 should be much lower than for 1984. The only 1985 doses that are much lower (i.e., by'a factor of approximately 10) than the 1984 doses are the organ doses calculated for the third and fourth quarters, so there may be an inconsistency between the calculation of whole body and organ doses for these two quarters. Another anomaly in the releases reported is the release of over 800 times as much liquid waste per quarter (prior to dilution) during the third and fourth quarters of 1985 as during previous quarters of 1984 and 1985. 2.6.2 Trends of Environmental Radioactivity Levels Direct radiation levels and gross beta activities in airborne particulate measured in the environmental monitoring program during 1984E113 and 1985E93 are tabulated in Table 2-4 and plotted in Figure 2-2. TABLE 2-4. DIRECT RADIATION AND GROSS BETA ACTIVITY l Direct Radiation Dose Airborne Gross Beta Levels (mrem /atr) Activity (pCi/m ) 8 Control Indicator Control Indicator I Year Locations Locations Locations Locations 1984 23.8 21.2 0.020 0.020 1985 22.6 20.4 0.021 0.020 20 \\

Jo 27 Control 24 Indicator 3 g Sf 18 e 33 f di ,2 l 4 3 0 1981 1982 1983 1984 1985 YEAR A. Dire c t ( c m ble n t) gomma ra dic tle n. .040 .o36 C en trol t9dicator n

d.o28

]. $.o24 i $2 .020 m .oi s - ~ ~ - ---4 y I ,o,2 I d5 j k 5 9 008 ~~ \\ .o04 ^' o 1981 1982 1983 1C84 1985 YEAR B. Airb o rn e gross beto o ctivlty. Figure 2.2. Levels of radioactivity in the environs of San Onofre fluclear Generating Station, Units 1,2,3, for 1984 and 1945. 21

Direct radiation levels were about 5% lower ir, 1985 than in 1984, and about 10% 10wer at indicator locations than at the control location. The only dose location with relatively unrestricted public access showing an apparently significant plant effect, San Onofre State Beach - Unit 1, had an average quarterly dose of 26.25 mrem in 1985 and 26.8 mrem in 1984 compared to control location doses of 23.8 mrem and 22.6 mrem, respectively. (As implied by the location description, the dose at this location was apparently due to the operation of SONGS Unit 1.) l Airborne gross beta activity levels were essentially the same during 1985 as in 1984. The Licensee discussed these levels for the 1981-1985 1 i period and concluded that there was no increasing trend. ) Iodine-131 was detected in 9 of 476 air samples during 1985 and 2 of 464 samples during 1984, all at onsite locations. 2.7 Information Contained in Licensee's Reports i Information contained in the Licensee's reports was compared with the l Licensee's report commitments (see tables in Appendix E) for the Licensee's Annual Radiological Environmental Operating Report for 1985E93 and the two Effluent and Waste Disposal Semiannual Reports for 1985.[7,8] The completeness of the reports submitted compared to the I report commitments is discussed in the following paragraphs (see tables in Appendix F). 2.7.1 Annual Radiological Environmental Monitoring Report The Licensee described the radiological environmental monitoring progran conducted during 1985 and reported summarized and tabulated results of the program. The repo,'t included results of the radiological environmental monitoring program, results of the Licensee's participation in an interlaboratory comparison program for environmental samples, and a complete report of the results of the land use census. 22

The following deviations from sampling requirements were reported by the Licensee: Two quarterly TLD monitors were lost due to work on the utility poles on which they were mounted. One air sampler was out of service for, about 11 sampling period ( I due to loss of power. About 20 other cases of non-normal down times were reported, but only three of these were for.more than one day. Over 20 cases were reported of low air volumes, mainly due to filter loading. (These cases of filter loading were fairly evenly distributed among the various sampling locations.)' ) Drinking water samples from the San Clemente golf course were e-taken from a single well because the second well was being. repaired. Fleshy vegetables were substituted for unavailable leafy vegetables. Several non-migratory marine animals were sampled at a somewhat later time than scheduled. I One sample of kelp was not obtained because o'f non-availability. ') e I Two ocean bottom sediment samples were taken later than scheduled. w No significant deficiencies were noted in the Licensee's report except j the failure to sample and perform monthly gamma analyses on local l vegetation from two indicator locations (offsite locations with highest D/Q) and one control location, as required by Unit 2_ Technical I Specifications Table 3.12-1. l 23 i s I

The Licensee's report included raw data for all sampling media, the data summary required by the technical specifications,'and extended discussions of-the results of the monitoring, including analyses of trends and comparisons with preoperational data. The LLD's reported in the data summary (Licensee's Appendix B) appear to be those obtainable with the equipment used, since most of the reported LLD's are much lower'than the maximum LLD's specified by the RETS. The Licensee also included a table titled '*4 measurements Exceeding Investigation Levels" which contained a listing of individua1' samples more than 25% above background for external dose or tvice background for radionuclides content (or twice the LLD if no non-zero background value was determined). This table was required by the Unit.1 Technical Specifications, Appendix B, which was in effect until August 5, 1985. Several minor inconsistencies in the report appear' to be' due to clerical or editorial errors (e.g., all samples listed'in the data summary-are identified as " composite" although most are the result of a single collection; Section II.I contains a statement that leafy crops were collected, but Appendix G explains why they were not collected; the " Total Number of Analyses Performed" column in the data summary did not reflect the lost TLDs). There are also apparent inconsistencies which on' closer examination are understandable. Specifically, sample analyses reported in the raw data that gave activity levels below the reported LLD are discussed in Section II of the Licensee's report, but are not included in the data summary (Appendix B). w 2.7.2 Effluent and Waste Disposal Semiannual Reports The Licensee reported a radioactive' effluent release summary for-liquid and gaseous effluents and solid radioactive waste disposal essentially in the format of Regulatory Guide 1.21.[12] The Licensee reported one abnormal gaseous effluent release from the plant during 1985, with a total release of 306 Ci'of Xe-133. 24 f

l i ) I The following items were noted in the Licensee's liquid and gaseous effluent, solid waste shipped offsite, and dose reporting: j l Average decay energy of fission and activation gases was not f discussed. J l ~ 1 Total body doses to the population and average doses to l individuals in the population from gaseous effluents to a j distance of 50 miles were not stated.a j i } I I l i l 1 1 i l a. The Licensee's technical specificat'ons can be interpreted as not requiring this information, since they do not specify that the contents of reports must be as specified in Regulatory Guide 1.21, i Revision 1, June 1974. 25

l l 3. CONCLUSIONS The radioactive effit.ent release reports and the radiological l ~ ~ environmental monitoring reports submitted for. San Onofre Nuclear Generating Station Units 2 and 3 met all of the reporting requirements of l the Licensee's RETS. The only significant deficiency was. failure to report results of sampling and analyses of local vegetation ' required. by the Unit 2 Technical Specifications. The Licensee included very comprehensive discussions of plant effect 'on the environment, comparison of operational data with preoperational data (when available), and historical trends of environmental data. A complete list 1ng of raw data (individual sample measurements) was also included in the environmental monitoring report, f The following conclusions may be drawn from the data reported by the Licensee: Releases of radioactive materials liquid and gaseous effluents ~ (except for H-3) during 1985 were comparable to the releases in 1984 and were consistent with the power produced by Units 2 and 3 in those two years. Power production in 1985 was 10% below the 1984 level, and changes in releases of radioactive materials varied from a decrease of 40% for noble gases to'an increase of 18% for I-131 and long-lived particulate. (8% for I-131 and 244% for long-lived particulate.) The 1985 release of H-3 in liquids was comparable to the release during 1984, but the release in gaseous effluents was only 2% of the 1984 releases, possibly due to less exposure of primary coolant to the atmosphere. Doses calculated from radioactivity released in liquid and gaseous effluents showed an approximately linear relationship to l releases, except for organ doses due to liquid effluents during the second half of 1985. (Some change in calculational method seems to have occurred in the middle of 1985.) 26

I Offsite doses due to radioactive effluents from Units 2 and 3 were e i 1 reported as 25.3% or less of the 10 CFR 50, Appendix I guidelines. j i 1 The Licensee reported whole body, organ other than thyroid, and i e thyroid doses that were, respectively, 44.8%, 26.5%, and 11.3% of the 40 CFR 190 limits. (The difference between the doses due to j radioactive effluents from Units 2 and 3 and the doses reported in relation to the 40 CFR 190 limits is apparently produced both by inclusion in the 40 CFR 190 values of the doses due to Unit 1, and also the fact that concurrent data was used to calculate doses due to 3 gaseous effluent for comparison with 10 CFR 50 limits, but historical data was used for doses to compare with 40 CFR 190 values.) l During 1985 the Licensee conducted an environmental monitoring e I program, participated in an approved interlaboratory comparison program, and performed a land-use census essentially in accordance with the requirements of the plant's RETS. l l1 - Analyses of samples taken in accordance with the Licensee's e radiological environmental monitoring program showed definite evidence i of plant influence on radioactivity levels in the environment only in the case of non-migratory marine animals (primarily the mollucks, Bay Mussel and Sea Hare). (The doses due to eff1 cents from Units 2 and 3, calculated from measured activities in this medium, were due mostly to Co-60 and totaled approximately 0.1 mrem to the whole budy and less than 0.5 mrem to any organ.) Direct radiation (TLD) and airborne gross beta radioactivity levels reported for 1984 and 1985 were essentially the same. During the fourth quarter, the direct radiation level at an onsite location was 4.58 times the control location average, due to parking of a radwaste 1 l vehicle nearby. 1 27 i

The Licensee's revision to'the ODCM for Units 2 and 3 (Revision I l. 17, dated June 15, 1985) uses methods that'are, in general, consistent with the guidelines of NUREG-0133. However, the methodology for determining setpoints for the Units 2 and 3 noble. -) ~ gas. effluent monitors does not consider simultaneous releases from Unit 1. ~Also, the definitions of the release rates for ~ q noble gases, radioiodines, particulate, arsd tritium do not 0 appear-- to include considerations of simultaneous releases from more than one release point (including Unit 1), so it is .j uncertain if the methodology provides reasonable assurance that.

j the NURE3-0472 dose rate limits'will not be exceeded.

The Licensee's semiannual. reports included information that a revised PCP had been approved, and that the. amount of liquid allowed in dewatered resins had been reduced. l i l l l 1 i 28 l l

'l 4. REFERENCES 1. " San Onofre Nuclear Generating Station Unit 2 Technical Specifications, Appendix A to License No. NPF-10", NUREG-0741, February 1982 (no amendments), and ) J " San Onofre Nuclear Generating Station Unit 3 Technical i Specifications, Appendix A to License No. NPF-15" NUREG-0952, November 1982 (no amendments). i 2. " Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors," Rev. 3, Draft 7", NUREG-0472, Sept. 1982 (available in the NRC Public Document Room). 3. " Preparation of Radiological Effluent Technical Specifications for 1 Nuclear Pover Plants," NUREG-0133, October 1978 (available in the NRC Public Document Room). ~ 4. Letter C. A. Willis (NRC) to F. B. Simpson (EG&G Idaho) dated January 3, 1983, providing guidance on the review of Process Control Programs. 5. "Samiannual Radioactive Release and Solid Waste Disposal Report," January 1 through June 30, 1984, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, August 24, 1984 (available in the NPC Public Document Room). 6. " Semiannual Radioactive Release and Solid Waste Disposal Report," July 1, 1934 through December 31, 1984, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, February 28, 1985 (available in the NRC Public Document Room). 29

7. " Semiannual Radioactive Effluent Release Report," January 1, 1985 through June 30, 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, August 28, 1985 (available ~ in the NRC Public Document Room). 8. " Semiannual Radioactive Effluent Release Report," July 1,1985 through December 31, 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, February 28,1986 (available in the NRC Public Document Room). 9. " Annual Radiological Environmental Operating Report" for 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, April 30,1986 (available in the NRC Public Document Room).

10. Letter G. W. Knighton (NRC) to K. P. Baskin (SCE) and J. C. Holcomb (SDG&E), dated June 11, 1985.

11. " Annual Radiological Environmental Operating Report" for 1984, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company,1985 (available in the NRC Public Document Room).

12. " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," U.S. Atomic Energy Commission, Regulatory Guide 1.21, Revision 1, June 1974.

e 30

e l j I i l 4 1 ( APPENDIX A ) l Plant and Site Design Features for the l San Onofre Nuclear Generating Station, Units 2 and 3 J l l e l t l l

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F Figure A-1 shows the area surrounding San Onofre Nuclear Generating Station, including the low population zone radius. Figure A-2 shows the exclusion area boundary for gaseous effluents and the physical layout of the plant. The public is not entirely excluded from the area within the i exclusion area boundary. There is free public transit along old U.S. Highway 101 and the San Diego Freeway as well as along a pathway between i the seawall along the southwest side of the plant and the Pacific Ocean. This pathway is intended for passage between public areas northwest and southeast of the plant, and long term occupation by the public is prohibited. Discharge points (diffusers) for main condenser cooling water from J Units 2 and 3 are shown in Figure A-3, and gaseous and liquid radwaste systems and' discharge pathways are shown in Figures A-4 and A-5. 1 1 A3

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N O R R T I O E N T T 3 T AI .E L N ME I I O F A D O NG A NI E P M A R E R R T U I T P H P NN UO P A C )j 3C N A f OR tT I O NS T T UT AI 3 3 3 N N I N D R E O T T T R O I O V A I I I M TT R N N N T U U U AI [( IN K DO C O AM A M R T (2 S T II 4 T I N NE UW /g M7 7 R O T S S S Y U E A ) 6 A R C ( N H P E R O X M D K O E N I TT O S A AI N C A T N I O G DO I A M T R A C 0 L T E I G E T S N U R E A U V H T P X S G E U I N N A N H I I M D O X L IT E I U A B N L l O I K T T I w N T f E N M A A S N E L E T ) E V E I T P T T D S C N G N S N S E G & N E Y I V S A A 2 2 M N D G N T T Y G T I L A I D P I G T I 2 I U N N R N R I I A L U B U A I E N U S V U I N Q D M P O E Y L I S O B O C Y A UI R A C N R P G T B E I T I L D N E I L U F X E A U U S A F 5

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i l i l i APPENDIX B 1 Summary of Radioactive Effluent Releases and Calculated Doses (San Onofre Nuclear Generating Station, Units 2 and 3) l l l l l

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The data summarized here are taken from the Licensee's radioactive effluent release data submitted for 1984 and 1985. + The Licensee's effluent release data are summarized in Tables B-1, B-2, B-5, and B-6, for liquid and gaseous releases. The tables show the quarterly data as well as the combined annual data on activity releases, and also information on abnormal releases. Tables B-3 and B-7 summarize j the shipment of solid radioactive waste for offsite burial. Since l mid-1984 San Onofre has shipped solid waste on a site-wide basis. Therefore, solid waste tables since then reflect solid waste from Units 1, 2, and 3 and are identical with the corresponding tables'in the TER for Unit 1, EGG-PHY-7202. In Tables B-4 and B-8 the maximum-doses reported by the Licensee for individuals are shown for. liquid as well as gaseous releases. e l B3

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i l i l l APPENDIX C Radiological Environmental Monitoring Program Results (San Onofre Nuclear Generating Station, Units 2 and 3) i l l = 1 1 l l i 4 I 1 i ) l 1 l l l

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I TF:s conduct of the Licensee's radiological environmental monitoring program during 1985, as recorted in the Licensee's Annual Radiological Environmental Operating ReportE93 for 1985 is summarized in this appendix. San ONfre i4uclear Generating Station (SONGS) is the site of three pressurized water reactors, Units 1, 2, and 3. Unit I was manufactured by Westinghouse and Units 2 and 3 by Combustion Engineering. The reactors are located on the shore c' the Pacific Ocean about 5 miles south of San Clemente, California. The main condenser cooling water systems operate in the once-through mode, with water taken from and returned to the Pacific Ocean. Discharges from Units 2 and 3 are between 3500 ft. and 8500 ft. from the reactors. (See Figure A-3 ) The Licensee's radiological environmental monitoring program follows i the requirements of the Unit 3 RETS, issued November 1982. The annual environmental operating report includes data required by the Unit 3 RETS as well as some additional data required by Appendix B of the technical specifications for Unit 1, which was in effect until deleted August 5, 1985. The environmental monitoring program is summarized in Table 2-2 of the text of this report. Figures C-1 and C-2 show the sampling locations. Program details and compilations of the results of the program for 1984 and 1985 are shown in Tables C-1, C-2, and C-3. The NRC monitored direct (ambient) radiation in the environs of SONGS during 1985. Locations of the monitors (TLDs) used by the NRC are shown in Table C-4, and the corresponding doses are shown at the various dose locations in Figure C-3. .(The Licensee's monitoring program included I several onsite locations as well as a significant number of other locations within the " exclusion area boundary for gaseous effluents", whereas the NRC's program included only three locations in these areas.) The Licensee's control location was 37 miles NW of the plant and the NRC's l C3 j

l locations were apparently 35 NNW. The NRC's indicator and control location values (in mR/std qtr) were, respectively, 9% below and 3% above those reported by the Licensee (in mrem /qtr). ] I ) The Licensee states, "...it is concluded that the radiological environmental impact of the San Onofre linits 1, 2, and 3 operations . j through 1985 has been minimal, and the resulting dose to man is negligible." This statement seems justified, since dose calculations using the only measurable levels of activity in offsite environmental media (non-migratory marine animals) yielded a whole body dose of less than 0.5 mrem and an organ dose of less than 2.5 mrem for 1985, using conservative assumptions in the calculations. l - I C4 l

B D + A E e R F k ' .l q% h @ $a,. \\' \\*5 .x f 1 '9N T g g/.A- ~g G o@ f' - San Onofre [ State Beach O h e O 2> r d ka Md. 4 som P H W + SCALE o 1 MILE g 0 1000 2000 3000 4000 5000 FEET /' LEGEND RADIOLOGICAL [ ENVIRONMENTAL NONiiORING L .. ; e....,. i ca... g o...... f An 4, s-g on w..., Figure C-1. Locations of radiological environmental o w..., 3 monitoring locations within two miles of the San Onofre Nuclear Generating Station , to..i c,,,. (SONGS). (Taken from Figure A-3 of the y,,,, i SONGS Annual Radiological Environmental Operating Report for 1985, dated April 1986.) C5

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NRC TLD DOSES FOR SAN ONOFRE ARER C rnR p e r 90 days) l N 17 88 CRtf pet @LETold .StiN CLEl1 ENTE 21 as d he '7 ag, 27 0 1 2 i.n se is i I 3, ee nru:s i 5 S4 bbh b:h!.

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TABLE C-1. LICENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS Sample Typea Location Lccation Code Description of Location Dist. (mi)b Sectorb Direct Radiation {TLDs) 1 City of Clemente (SDG&E Offices) 5.6-NW 2 Camp San Mateo -3.5 N 3 Camp San Onofre 2.6 NE. 4 Camp Horno -4.5-E 5 . Camp Las Pulgas 8.5 ESE. 6 Old Route 101 - East-Southeast 3.0 ESE 7 Old Route 101 - East-Southeast 0.5 ESE 8 Noncommissioned Officer's Beach Club 1.2 NW 9 Basilone Road /I-5 Freeway Offramp '2.0 NW 10 Bluff 0.8 .NW 11 El C&aina Training Annex 0.2 NNE. 12 South Edge of Switchyard 0.2. NE 13 Site Boundary 0.13 SE 14 (c) Huntington Beach Generating Station 37 NW 15 East-Southeast Site Boundary 0.2 ESE 16 East Site Boundary 0.5 E. 17 Transit Dose 18 Transit Dose 19 San Clemente Highlands 5.0 NNW 20 San Clemente Pier 5.0 NW 21 Concordia Elementary School - San Clemente '3. 5 NW i 22 Coast Guard Station - San Mateo Point 2.7 WNW 23 San Clemcnte General Hospital 8.2 NW 24 San Clemente High School 6.0 NW 25 Convalescent Home - San Clemente 8.0 NW 2G Dana Hills High School 11.0 NW 27 U. S. Post Office - Dana Point 10.5 NW ' 28 Doheny Fire Station - Capistrano Beach 9.5 NW 29 San Juan Capistrano Fire Station 10.8 NW 30 Laguna Beach Fire Station 17.5 NW 31 Aurora Park Mission Viejo 18.6. NNW' l 32 Santa Ana Police Department 32.0 NW 1 33 Camp Talega 5.7 N 34 San Onofre School 1.7 NW .i 35 Range 312 (Camp Pendleton) 4.7 NNE I 36 Range 208C (Camp Pendleton) 4.0 NE. 37 Laguna Niguel Fire Station 13.5 NW .i 38 San Onofre State Beach Park 3.6 SE 39 Basilone Road Trailer Park ~1.4 NNW j 40 SCE Training. Center - Mesa .0.8 NW 41 Old Route 101 - East 0.3 E 42 Horno Canyon 4.6 E 43 Edson Range (Camp Pendleton) 10.6 SE 44 Fallbrook Fire Station 18.0 E I Cl3

I TABLE C-1. LICENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (Cont.) ~ Sample Typed Lccation Location Code Description of Location Dist. (mi)b Sectorb Direct Radiation (TLDs) 45 Interstate 5 Weigh Station 2.0 ESE i 46 San Onofre State Beach Park 1.4 SE 47 Camp Las Flores 8.6 SE 48 Mainside (Camp Pendleton) 15.0 ESE 49 Camp Chappo 12.8 ESE 50 Oceanside Fire Station 15.5 SE 51 Carlsbad Fire Station 18.6 SE 52 Vista Fire Station 21 ESE 53 San Diego County Operations Center 45 SE 54 Escondido Fire Station 32 ESE 55 San Onofre State Beach (Unit 1) 0.2 W 56 San Onofre State Beach (Unit 1) 0.1 W 57 San Onofre State Beach (Unit 2) 0.1 SSW 58 San Onofre State Beach (Unit 3) 0.1 S 59 SONGS Meteorological Tower 0.3 NW 60 Transit Control Storage Area 61 Adjacent to Pressurized Ion Chamber #4 0.6 NNE 62 Adjacent to Pressurized Ion Chamber #5 0.7 NE 63 Adjacent to Pressurized Ion Chamber #6 0.7 ENE 64 Adjacent to Pressurized Ion Chamber #7 0.7 E 65 Adjacent to Pressurized Ion Chamber #8 0.9 ESE 66 Adjacent to Pressurized Ion Chamber,#9 0.8 ESE 67 Adjacent to Pressurized Ion Chamber #2 0.4 NW Airborne 1 City of San Clemente (City Hall) 5.5 NW l 2 Camp San Onofre (Camp Pendleton)C 1.8 NE 3 (c) Huntington Beach Generating Station 37 NW 5 Units 2 and 3 Switchyarde 0.13 ESE e 0.3 NW 6 SONGS Meteorological Tower 9 State Beach Parkc 0.4 ESE 10 Bluff 0.5 WNW 11 MESA EOF 0.5 NNW 12 SONGS Evaporation Pond 0.4 NW Soil 1 Camp San Onofre 2.5 NE 2 Old Route 101 - Southeast 3.0 SE 3 Basilone Road /I-5 Freeway Offramp 2.0 NW 4 (c) Huntington Beach Generating Station 37 NW l 5 East Site Boundary 0.2 NNW i l l C14 l

TABLE C-1. LlCENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (Cont.) Sample Typea Location Location Code Description of Location Dist. (mi)b Sectorb Ocean Water A Station Discharge Outfall - Unit 1 0.5 SW B Outfall - Unit 2 0.7 SW C Outfall - Unit 3 0.7 SW D Newport Beach 30 NW Drinking Water 1 Tri-Cities Municipal Water District Res. 8.7 NW 2 San Clemente Golf Course Well 3.5 NNW 3 (c) Huntington Beach 37 NW Shoreline Sediment 1 San Onofre State Beach 0.6 SE 2 San Onofre Surfing Beach 0.9 NW l 3 San Onofre State Beach 3.5 SE l 4 (c) Newport Beach (North End) 30 NW Non-Migratory Marine Animals A Unit 1 Outfall 0.6 WSW B Units 2 and 3 Outfall 0.7 SSW C (c) Newport Beach 30 NW Local Crops 1 San Mateo Canyon 2.6 NW 2 (c) Southeast of Oceanside 22 SE Kelp A San Onofre Kelp Bed 1.5 S B San Mateo Kelp Bed 3.5 WNW C Barn Kelp Bed 6.6 SSE ) 0 (c) Newport Beach 30 NW Ocean Bottom Sediments A Unit 1 Outfall 0.5 W B Unit 1 Outfall 0.6 W C Unit 2 Outfall 0.8 SSW D Unit 3 Outfall 0.6 W E (c) Newport Beach 30 NW

a. The Licensee uses the same code number for different locations depending on sample type.

Therefore, both sample type and location code are required to identify the location. A "(c)" following the location code indicates a control location. i

b. Distance and Sector are measured from Units 2 and 3 midpoint.

c. Not required by technical specifications.

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? TABLE C-4. NRC's DIRECT RADIATION (TLD) ENVIRONMENTAL MONITORING LOCATIONS j Station _Dist. (Mi.) Dir. (*) Description 1 35.0 346 Featherly Park 2 35.0 346 Featherly Park 3 35.0 346-Featherly Park. 4 11.0 327-S. Coast Hospital-5 14.0 308 Fire Station 6 10.0 307 Dana Pt. Harbor 7 6.3 318 Gas & Electric Office (San Clemente) 8 5.1 322 Civic Ctr. (San Clemente) 9 3.3 311 Concordia School 10 3.3 331 San Mateo Rd. 11 2.6 300 U. S. Coast Guard 12 .5 285 San Onofre Surfing Beach. 13 2.4 320 San Clemente Ranch Head 14 1.7 320 San Onofre Elementary School-15 1.2 333 San-Onofre Mobile Home Park 16 1.9 30 Basilone Rd. 17 1.3 8 Basilone Rd. 18 2.0 39 Camp San Onofre-Fire Station 19 2.9 55 Camp San Onofre 20 4.1 77 Camp Horno 21 4.7 87 Camp Horno 22 3.4 25 San Mateo Rd. 23 3.5 357-Camp San Mateo 24 .4 25 Old Rt. 101 25 .4 81 Old Rt. 101 26 2.1 126 Border Patrol Station 27 8.6 130 'Stuart Mesa Rd. Area 28 8.9 99 Camp Los Pulgas 29 11.0 135 Stuart Mesa Rd. 30 2.0 126 San Onofre State Camping Area 31 3.7 128 San Onofre State Park 32 22.0 140 Oceanside Fire Station 33 26.0 120 Vista County Offices 9 d C33

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APPENDIX D Evaluation of Changes to the ODCM, PCP, and Radwaste Treatment Systems for the San Onofre Nuclear Generating Station Units 2 and 3 e 9

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i D.1' EVALUATION OF CHANGES TO THE ODCM The Southern California Edison Company (SCE), the Licensee for the San Onofre Nuclear Generating Station with Units 1, 2 and 3, prepared an Offsite Dose Calculation Manual (ODCM) for Unit 1 and another ODCM for' ~ Units 2 and 3. Revisions to the ODCM are required bl/ the Licensee's i Technical Specifications to be reported to the NRC in the Semiannual Radioactive Effluent Release Reports for Unit 1 and in the Monthly Operating Reports for Units 2 and.3. The Licensee submitted changes to the ODCMs in the Semiannual Radioactive Effluent Release reports for the first half of 1985(1) for Unit I and in the Monthly Operating Report for August 1985 for Units 2 and 3(2). Additionally, the ODCMs were submitted to the NRC with letter dated September 17, 1985.(3) The letter contained Revision 2 dated 06-15-85 for Unit 1 and ODCM Revision 17 dated 06-15-85 for Units 2 and 3. The NRC mailed the ODCM revisions to the Idaho National Engineering Laboratory (INEL) for review. The INEL reviewed the entire ODCMs, including the revisions, as a whole. The result of the ODCM evaluation for Units 2 and 3 is intended to be a stand-alone document and is given in ~ Supplement 1 to this appendix. D.2 EVALUATION OF CHANGES TO THE PCP Initially, the SCE prepared individual Process Control Programs (PCP) that were unit and processing specific. The individual PCPs were subsequently replaced with a generic PCP which allowed several process methods for the site and the generic PCP was submitted to NRC for review. The NRC reviewed the PCP and notified the licensee of interim approval of the generic PCP with letter dated June 11,1985(4). Changes to the PCP are required by the licensee's technical specifications to be reported to the NRC in the Semiannual Radioactive Effluent Release Reports. Three changes to the generic PCP were reported in the Semiannual Radioactive l Effluent Release Report for the second half of 1985(5). Two of the j changes were editorial and the third changed the free-standing liquid l i D3 = _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _

requirement when dewatering resins to <0.5% instead of <1.0%. The percent' change for free-standing liquid is acceptable since it is within the -limits identified in 10 CFR'61 Part 56(6). Since the reported changes are minor'in extent, a review of the entire document was not made and the NRC interim approval of the generic PCP should be' extended to include these reported changes. D.3 REPORTED CHANGES TO THE RA0 WASTE TREATMENT SYSTEMS The licensee's technical specifications require changes to the radwaste treatment systems to be reported in the Monthly Operating Reports. Monthly Operating Reports are not reviewed by INEL, and if major changes were made to the systems they will not be identified in this' report. i j l l i D4 j

0.4 REFERENCES

1. " Semiannual Radioactive Effluent Release Report," January 1, 1985 through June 30, 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, August 28, 1985. 2. Letter from H. E. Morgan (SCE) to J. B. Martin (NRC),

Subject:

Monthly Operating Reports for August 1985 San Onofre Nuclear l Generating Station, Units 2 and 3, September 16, 1985. 3. Letter from H. E. Morgan (SCE) to J. B. Martin (NRC),

Subject:

San Onofre Nuclear Generating Station, Units 1, 2, and 3, September 17, 1985. 4. Letter from G. W. Knighton (NRC) to K. P. Baskin (SCE),

Subject:

Interim Approval of the Units 1, 2, and 3 Process Control Program, June 11, 1985. 5. " Semiannual Radioactive Release and Solid Waste Disposal Report, July 1,1985 through December 31, 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company. 6. Title 10, Code of Federal Regulations, Part 61.56, " Waste Characteristics". r D5

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t-6 SUPPLE;4ENT 1 to APPENDIX D EVALUATION OF CHANGES TO THE ODCM O ) l I .1 l j i __.____________.___.____w

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INTRODUCTION Purpose of Review The purpose of this document is to report the review and evaluation of the revised Offsite Dose Calculation Manual (0DCM) submitted by the Southern California Edison Company (SCE) for the San Onofre Nuclear Generating Station Units 2 and 3. The ODCM is a supplementary document for implementing the Radiological Effluent Technical Specifications (RETS) in compliance with 10 CFR 50, Appendix I requirements.[1] Scope of Review As specified in NUREG-0472[2] and NUREG-0473,[3] the ODCM is to be developed by the Licensee to document the methodology and approaches used to calculate offsite doses and maintain the operability of the radioactive 1 effluent systems. As a minimum, the ODCM should provide equations and methodology for the following topics: o Alarm and trip setpoints on effluent instrumentation o Liquid effluent concentrations in unrestricted areas o Gaseous effluent dose rates at or beyond the site boundary l I o Liquid and gaseous effluent dose contributions l o Liquid and gaseous effluent dose projections. l In addition, the ODCM should contain flow diagrams, consistent with the systems being used at the station, defining the treatment paths and the components of the radioactive liquid, gaseous, and solid waste management systems. A de.scription and the location of samples in support of the environmental monitoring program are also needed in the ODCM. O D1-3

l plant-Specific Background l The SCE prepared an ODCM for San Onofre Unit I and another ODCM for l Units 2 and 3. The Licensee reported revisions to both ODCMs as required by the Licensee's Technical Specifications in the Semiannual Radioactive Effluent Reports for Unit 1 and in the Monthly Operating Reports for l Units 2 and 3. The revisions were also submitted to the NRC with letter dated September 17,1985.(4) The letter contained ODCM Revision 2 dated 06-15-85 for Unit 1 and ODCM Revision 17 dated 06-15-85 for Units 2 l and 3. The NRC transmitted the ODCM revisions to the Idaho National Engineering Laboratory (INEL) for review. The INEL reviewed the ODCM for Units 2 and 3 and the results and conclusions of the evaluation are presanted in this supplement. REVIEW CRITERIA Review criteria for the ODCM were provided by the NRC in three documents: NUREG-0472, RETS for PWRs[2] NUREG-0473, RETS for BWRs[3] NUREG-0133, Preparation of RETS for Nuclear Power Plants.[5] In the ODCM review, the following NRC guidelines were also used: " General Contents of the Offsite Dose Calculation Manual," Revision 1,[6] and Regulatory Guide 1.109.[73 The ODCM format is left to the Licensee and may be simplified by tables and grid printouts. W D1-4

EVALUATION l The Licensee, to provide reasonable assurance that the maximum ~ permissible concentrations (MPCs) specified in 10 CFR 20[8] will not be exceeded by discharges from the liquid or gaseous release points, has in ~ general followed the methodology of NUREG-0133 to determine the.setpoints for the liquid and gaseous effluent monitors. L There are three nuclear power units at the San Onofre site. Unit I has it's own liquid radwaste discharge system and releases liquid radwaste-to it's own circulating water outfall pipe which' returns Unit I condenser cooling water to the Pacific Ocean. As indicated in Figure 4-1 of the ODCM, Units 2 and 3 share a common liquid'radwaste treatment system and the liquid radwastes are released to the Unit 2 circulating water outfall ' pipe which returns Unit 2 condenser ecoling water to the Pacific Ocean. Since the liquid radwaste system of Units 2 and 3 is served by a dilution stream separate from the Unit I dilution stream, then liquid releases from Units 2 and 3 may be made independent of releases from Unit 3. Liquid radwaste from Units 2 and 3 are released to the Unit 2 outfall line in both the batch and continuous modes. As described in Section 1.1 of the ODCM, batch releases to the Unit 2 outfall line are from the radwaste primary tanks, the radwaste secondary tank, the primary plant makeup tank, the condensate monitor tank, and the neutralization / sump discharge lines. Continuous releases made to the Unit 2 outfall line are from tt.e steam generator blowdown lines, the steam generator blowdown bypass lines and the turbine building sump.s. Figure 4-1 in the ODCM is a simplified diagram of the Units 2 and 3 liquid radwaste treatment system and release pathways. However, Figure 4-1 does not indicate the batch and continuous sources released to the Unit 2 outfall line that are described in Section 1.1 of the ODCM. Figure 1 of this report is a diagram prepared from the information in Section 1.1 showing the liquid radwaste sources released to the Unit 2 outfall line. The Licensee should verify the accuracy of this diagram and should consider including a similar' diagram into the next revision to the ODCM. Each of the' release sources to the outfall line are monitored and the methodology for determining the D1-5

T E R 2 NT P m QI x z% 3 I N TBA M u 2 IN RL U S A T R I U UP T N N 3 O W S MT S N o2 U AO A y A WER D P 9 S E E# Y 5 E NT USNO B 7 S H E L G B A T E R N T P L 3 O W R O E O3 A A O 3 N R T MT TI E R D y N N T E W Ea o2 3 9 X S U SN O 5 5 U ID E 7 7 M G N L 6 P U A B 6 sT G G N S MWS N T h E 2 2 R R 0 i C O S A 2 2 0 l R ND O W y 5, C US W P Y E 8 T N NO OI E L B U 1 G B SNU E RN SE 2 OW AR MT O EF T AAD f LO I ERW i E E N TE O Em a2 P N U SN L I R EB P O G L l ,iI 1, 1II3 y1 It 1I Ii 1 1 t I I I i i L DN A IA i F US r T U Q O IT LA P N P N 2 O EE O O O I T VP N I N T f T A 4 II X 2 A X 3 Z iU TP ZP M T I ILP u C P I L M M T AM AL A U P I G N S G N RU OL R U T UT S IA I 0 U S DF U E 0 E f E 4 N AT W 4 RU N O F 3 E 1 3 8 1 7 3 E I /2 R U t ? e i G IF N P P P O O O OR F P O N N N TO O I N E AT X E Y X X T II g R P AR DN X EY T M SO AO bK T M SRS M S AS M NT RM g P AAK P A DK P N P EI G WMN G WNN G A G N O D N / O = A CCT T N DIR T 0 l E OM = i 0 A P 4 PJE 6 fl C P 4 R 1 S 1 I O 1 l

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l monitor's setpoints is described in Section 1.1 of the ODCM. Administrative factors are included in the methodology to determine'the monitor's setpoints to assure release limits will not be exceeded by simultaneous releases into the Unit 2 circulating water outfall pipe. The Licensee's methodology, described in Section 1.1 of the ODCM, to determine the setpoints for the liquid effluent monitors is in general.in agreement ~ with the guidelines of NUREG-0133 to provide reasonable assurance that the concentration limits of 10 CFR 20 will not be exceeded. The methodology to determine the setpoints for the radioactive gaseous effluent monitors is contained in Section 2.1 of the ODCM. According to the descr'.ption in Section 2.1 there are six monitored release pathways for Units 2 and 3: l Unit 2 vent stack I Unit 3 vent stack Unit 2 containment purge Unit 3 containment purge Unit 2 condenser evacuation system Unit 3 condenser evacuation system A simplified diagram of the waste gas treatment system for Units 2 and 3 is shown in Figure 4-2 of the ODCM. Figure 4-2 should be modified to include the condenser evacuation systems and identify the noble gas monitors. There are a number of noble gas monitors associated with these release pathways as indicated in Figure 2 of this report which was drawn based on the information from Section 2.1. The Licensee should verify the accuracy of Figure 2. The methodology to determine the setpoints for the noble gas monitors for Units 2 and 3 uses the historical annual average l 3 dispersion factor of 4.8E-06 sec/m. Noble gas effluent monitor setpoints are dependent on dose rates which are site limits and not j I individual limits for each reactor on the site. Since simultaneous noble gas release rates are additive, then the methodology to determine the setpoint for each noble gas monitor must consider simultaneous releases D1-7 i

g 8 A 1 98O 8 7 7 7 TR T 3 R 3 STN OI T P N E 3 M E E G S N R A d TI I AU E 5 N TP L 4 6 UN 8 8 E 8 7 O C R 7-TRO 3 T N K T T 3 R A C N 3 L A E D P T N S TA 3 "E 1 = L T F TN G - F 2 I E N5 N E V A6 M S U R8 3 T E - D S E T 7 NK T AC A L D T N G S S N A I R A Y U U PT W3 S S g E O 2 2 T 1 8 SY E E T SA A S R TN 8 8 V 6 7 TW C A F IE 5 N I ED G O N U 8 T U N 7C E R O R 3 V T 2 2 TI N / A C S A O M I O D A R T N R F E 2 ME N G y T I R E I TA U 2 G 8 N P 5 4 N 2 U N 6 .F A 8 8 O E 8 R 7 7 C R 7O ET T-U TR DR R G 2 IW2 F I 2 N J E I gb 2 L T 1 N G - 8 N U 0 A 1 7 8 R 8 7q I R 7 T-E - DT R2 W 2 1 w Z IT

from all noble gas release points at the site including the releases from Unit 1. The methodology in Section 2.1 considers simultaneous releases from all release points at Units 2 and 3 but does not consider simultaneous noble gas releases from L' nit 1. As a minimuni, an adjustment facter should be included to consider simultaneous releases from the three unit vents. The Licensee's method to calculate setpoints for the noble-gas effluent monitors is, in general, in agreement with the guidelines ef NUREG-0133 except for consideration of simultaneous releases from Unit 1. Therefore, it is questionable if the methodology provides reasonable assurance that the dose rate limits of NUREG-0472 will not be exceeded. Radioactivity concentrations in liquid effluents at the point of release are reasonably assured to be within the 10 CFR 20 concentration limits in the determination of MPCeff described in ODCM Section 1.1.1. The methodology for determining the dose rate to an individual due to the release of noble gases is contained in Section 2.2.1. The release rate calculation uses the highest calculated annual average dispersion factor of 4.8E-06 sec/m3 for estimating the dose to an individual at or beyond the unrestricted area boundary. However, it is not clear if the release rate term in Equations 2-11 and 2-12 of Section 2.2.1 includes the noble gas release rates from all release points on the site including Unit 1. Therefore, it is uncertain if the Licensee's method provides reasonable assurance that the NUREG-0472 dose rate limits shall not be exceeded due to siinultaneous releases of all noble gases from the site. The methodology for determining the dose rate to the critical organ of a child via the inhalation pathway due to the release of radioiodines, tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days is contained in Section 2.2.2 of the ODCM. The release rate calculation uses the highest calculated annual average dispersion factor of 4.8E-06 sec/m3 for estimating the dose to an individual at or beyond the unrestricted area boundary. However, it is not clear if the release rate term in Equation 2-13 of Section 2.2.2 includes the release rates for these nuclides from all release points on D1-9

the site including Unit 1. Therefore, it is uncertain if the Licensee's method provides reasonable assurance that the NUREG-0472 dose rate limit of $1500 mrem /yr from the site shall not be exceeded due to simultaneous releases of these nuclides from the site. The methodology to determine the dose commitment to the maximum exposed individual in the adult age group from radioactive materials in liquid effluents is contained in Section 1.2. Since San Onofre is an ocean site, the dose pathways due to liquid effluents are the consumption of saltwater fish and saltwater invertebrates. It should be clearly stated that both pathways are included in the definition for Ait in Section 1.2. The Licensee's methodology for calculating doses due to the release of radioactivity in liquid effluents is in general in agreement with the guidelines of NUREG-0133 and should provide reasonable assurance that the dose limits of 10 CFR 50 will not be exceeded. The methodology to determine the air dose in unrestricted areas due to the quantity of noble gasas released is contained in Section 2.3.1. The air doses are calculated using the maximum annual average atmospheric dispersion factor X/Q for any sector or distance at or beyond the unrestricted area boundary. The methodology identified in Section 2.3.1 of the ODCM to calculate air doses due to the release of noble gases is, in gen m l, in agreement with U1e guidelines presented in NUREG-0133 and L should provide reasonable assurance that the dose limits of 10 CFR 50 will not be exceeded. f The methodology to determine the dose to an individual from I-131, ] I-133, radioactive materials in particulate form with half lives greater than eight days, and tritium is contained in Section 2.3.2. The Licensee identifies the inhalation, the food, and ground plane pathways in each age group for the dose calculation and uses the annual average dispersion parameter for estimating the dose to an individual at the controlling ] location. It is not clear why De identified in Section 2.3.2.2 is the " annual" dose and not just the dose for the reporting period whether the reporting period be quarterly or annual. The methodology described in the D1-10

l i ODCM for calculating the dose to an individual is, in general, in agreement with the guidelines presented in NUREG-0133 and should provide reasonable assurance that the dose limits of 10 CFR 50 will not be ~ exceeded. The methodology to project doses due to liquid and gaseous effluents is contained in Section 3.0. The dose projections are based on the doses I due to releases from the previous twelve months which were determined using methodoingy that is in agreement with the guidelines of NUREG-0133. Therefore, the dose projections are in agreement with the guidelines of q NUREG-0133. 1 i Simplified diagrams for the liquid, gaseous, and solid waste treatment J systems are shown in Figures 4-1, 4-2, and 4-3 of the ODCM. However, maps showing site boundaries and unrestricted areas and effluent release points j are not included in the ODCM. l i The methodology to demonstrate compliance to 40 CFR 190 is contained in Section 2.4. The methodology includes all doses from the site including direct radiation and considers uranium fuel cycle sources within 5 miles of the site, The Radiological Environmental Monitoring program for Units 2 and 3 is described in Section 5.0 of the ODCM. Figure 5-1 identifying the environmental monitoring sample locations referenced in Section 5.0 is not included in the ODCM. Specific parameters of distance and the direction sector from the center of the Units 2 and 3 building complex and additional information have been provided for each and every sample required by the RETS Environmental Monitoring Technical Specification in the ODCM Tables 5-1, 5-2, and 5-3. Additionally, Table 2-15 is a synopsis of the land use surrounding the San Onofre site. D1-11

In summary, the Licensee's ODCM as' revised uses methods that are generally consistent with the methodology and guidance in NUREG-0133. However, because the Licensee does not consider simultaneous releases from the gaseous release points on the site, it is questionable if the setpoints determined for the noble gas effluent monitors and the dose -rates due to gaseous releases provide reasonable ascurance that the NUREG-0472 dose rate limits will not be exceeded. l l l l D1-12

CONCLUSIONS The San Onofre Units 2 and 3 ODCM Revision 17 dated 06-15-85 submitted ~ to the NRC by the Licensee with letter dated September 17, 1985(4) uses methods that are, in general, consistent with the guidelines of ~ NUREG-0133. However, because the Licensee does not consider simultaneous releases from the Unit 1 gaseous release points, it is questionable if the setpoints determined for the Units 2 and 3 noble gas effluent monitors provide reasonable assurance that the NUREG-0472 dose rate limits will not be exceeded. Exceptions to the ODCM are identified below: o The methodology contained in Section 2.1 for determining the \\ setpoints for the Units 2 and 3 noble gas effluent monitors does not consider simultaneous releases from Unit 1. o It is not clear if the definition for the release rate of radionuclides in Section 2.2.1 for determining the dose rate to an individual due to noble gas releases considers simultaneous noble gas releases from all release points at the site including the release points of Unit 1. Therefore, it is uncertain if the ~ methodology provides reasonable assurance that the NUREG-0472 dose rate limits will not be exceeded. o It is not clear if the definition for the release rate of the radionuclides in Section 2.2.2 for determining the dose rate to an individual due to the release of radioiodines, tritium, and materials in particulate form with half lives greater than eight days considers simultaneous releases from all release points at the site including the releases from Unit 1. Therefore, it is uncertain if the methodology provides reasonable assurance that l the NUREG-0472 dose rate limits will not be exceeded. D1-13

i Additional discrepancies and modifications that should be made to the ODCM are identified below: o Figure 4-1 does not indicate the batch and continuous sources released to the Unit 2 outfall line that are described in Section 1.1 of the ODCM. o Typo: The monitor setpoint is referred to as "c" instead of Cm in the first sentence of Section 1.1.1 on page 1-3 o The title of Section 1.1.2.1 appears to be incorrect. Should it be " Steam Generator Blowdown" instead of " Neutralization Sump Discharge Line Monitors?" Also, are the monitors correctly identified? The " Note" in Section 1.1.2.1 has an incorrect syr.bol for the "<" o sign. l o A map should be included in the ODCM showing the site boundaries, the unrestricted area boundaries, and the relative location of the three units including their respective circulating water outfall lines. l o It should be clearly stated that both pathways of saltwater fish and saltwater invertebrates are included in the definition for Ait in Section 1.2. e D1-14 1 _i

o Identified corrections that should be made to Table.1-2 are listed below: Nuclide T. Body Bone Kidney 'GI-Lli Na-24 4.57E-01 Fe-59 6.32E05 Sr-91 3.71E00 9.18E01 Ru-103 1.25E04 .Te-132 2.04E02 1-135 9.75E01 o It is not clear how the Licensee arrived at.the Table 1-2 values ~ for Co-57, Br-84 (Kidney), Nb-95, Nb-95m, Nb-97, Ag-110m,.Sn-113, Sb-124, and Sb-125. i o Equations 2-2, 2-2, 2-4, 2.4a, 2.6, 2.7, 2.6a, and'2.7a have.the following error in the numerator: I The units of Ci/pCi should be replaced with the correct units 3 ~ of m /cc. d i o The purpose for the "$" in the footnote of' Table 2-1 is not clear. o The portion of Figure 4-2 showing the waste gas' decay system ) indicates Unit 2 twice instead of indicating Unit 2.and Unit 3. Also, Figure 4-2 should be modified to include the condenser-evacuation systems and identify.the noble gas monitors. O It is suggested the title of Section 2.2.2 be changed to read "I-131, I-133, Tritium....." instead of "All Radioiodines, Tritium,......." .) i o It is not clear why De identified in Section 2.3.2.2 is the. l " annual" dose instead of the dose for the reporting period whether the reporting perio e quarterly or annual. ..j __ j

I i Figure 5-1 identifying the environmental monitoring sample o locations referenced in Section 5.0 is not included in the ODCM. 1 l e e l S O D1-16

REFERENCES' 1. Title 10, Code of Federal Regulations, Part 50, Appendix'I, " Numerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criterion, 'As Low As Is' Reasonably Achievable,for Radioactive Material in' Light-Water-Cooled Nuclear Power Reactor Effluents". 2. " Radiological Effluent Technical Specifications for Pressurized Water Reactors," Rev. 3, Draft 7", intended for contractor guidance in-reviewing RETS proposals for operating reactors, NUREG-0472, September 1982. 3. " Radiological Effluent Technical Specifications for Boiling Water Reactors," Rev. 3, Draft 7", intended for contractor guidance in reviewing RETS proposals for operating reactors, NUREG-0473, September 1982. 4. Letter from H. E. Morgan (SCE) to J. B. Martin (NRC),

Subject:

1 f San Onofre Nuclear Generating Station, Units 1, 2, and 3, September 17, 1985. i i 5. " Preparation of Radiological Effluent Technical Specifications for ) Nuclear Power Plants, A Guidance Manual for Users of Standard ' Technical Specifications," NUREG-0133, October 1978. 6. " General Contents of the Offsite Dose Calculation Manual," Revision 1 Branch Technical Position, Radiological Assessment Branch, NRC, j 3 February 8, 1979. 1 7. " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix I," Regulatory Guide 1.109, Rev. 1, October 1977. 8. Title 10, Code of Federal Regulations, Part 20, " Standards for Protection Against Radiatior,." D1-17

I i l 4 i l APPENDIX E l Tables of Licensee's Report Commitments (San Onofre Nuclear Generating Station, Units 2 and 3) (Through Technical Specification Amendment No. O dated November 1982) t 1 i 4 4 e i 1

(Blank Page) i t k i l I . l. I 1 \\ E2 l

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l l APPENDIX F Checklist of RETS-Required Reports (San Onofre Nuclear Generating Station, Units 2 and 3) O 6 9 9

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4 ...uca... ous.,o.. co...u.o. ..uo.,~.....,~,.- =c ~~. - g.,cjo..m L"l,",7 BIBLIOGRAPHIC DATA SHEET EGG-PHY-7603 u,,~, i..,c,,o~i o.,........ n TR'hirlTd'f" Evaluation Report for the Radiological Effluent Release and Radiological Environmental Operating Reports for 1985 - San Onofre Nuclear .o naro.'w-uno Generating Station, Units 2 and 3 l May 1987 Y.,,..$.., Young, E. H. Magieby, W. Serrano .. u...o.,,uu. o T. S. Bohn, J. W. Mandler and F. B. Simpson l j ~o~'~ aa May 1987 i ,... o...~o o.s.....,,0~ ~... o...s. c.co. us,, ~ < c, .,.o,.c.,,.m. o..w~,, Radiological Physics Unit ,,,,,o,o,,,,,,,,,, EG&G Idaho, Inc. Idaho Falls, Idaho 83415 A6808 ....o~ w..~c, o....,.. o..... ~ o...s,~ o. o o. u,,,.,,. <. c, ...... o.. uo, Office of Nuclear Reactor Regulation Final V. S. Nuclear Regulatory Commission ,,,,,,ooco....,,,,,,., Washington, D.C. 20555 i o w..u....... ~ a i u i ........c.....-., A review was performed of reports required by Federal regulations and the plant-specific radiological effluent technical specifications (RETS) for operations conducted at San Onofre Nuclear Generating Station, Units 2 and 3 during 1985. The periodic reports reviewed were (a) the semiannual radioactive effluent and solid waste disposal reports for 1985, and (b) the annual radiological environmental operating report for 1985. These and earlier reports were also used to evaluate trends in radioactivity releases, offsite doses and radioactivity of environmental samples over the time period 1984 and 1985. The Licensee's submitted reports were l found to be reasonably complete and consistent with the review guidelines. The San Onofre Units 2 and 3 Offsite Dose Calculation Manual (0DCM) consisting of Revision 17 dated 06-15-85 was reviewed. The ODCM uses methods that are generally in l agreement with the guidelines of NUREG-0133 with the exception of considering simultaneous releases from the radioactive gaseous release points. Because of this exception, it is uncertain if the methodology provides reasonable assurance that the NUREG-0472 dose rate limits will not be exceeded. The Licensee submitted minor changes to their generic Process Control Program (PCP) which presently has interim l NRC approval. The reported changes were reviewed and it is recommended the interim NRC approval be extended to include the reported changes. l .. o c c -. ~,. ~. s,..... o.o.onc....o, .,.n.i~, Unlimited .. a t v.,.. m u,,,c.,,o., Un cl...,assified ..oi~,.....s o,i i~o.o n..: Unclassified i ,,~~...o,..cu .....e, i}}