ML20235L886

Technical Evaluation Rept for Radiological Effluent Release & Environ Operating Repts for 1985 - San Onofre Nuclear Generating Station Unit 1, Informal Rept

ML20235L886
Person / Time
Site:	San Onofre
Issue date:	06/30/1987
From:	Magleby E, Thomas Young EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	NRC
Shared Package
ML13308A986	List: ML20235L886
References
CON-FIN-A-6808 EGG-PHY-7602, TAC-59403, NUDOCS 8707160862
Download: ML20235L886 (167)

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j" TECHNICAL EVALUATION REPORT FOR THE RADIOLOGICAL EFFLUENT RELEASE AND ENVIRONMENTAL OPERATING Engineer /nFE

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' i NOTICE This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United Sates Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legalliability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or proc-ess disclosed in this report, or represents that its use by such third party would not infringe privately owned rights.

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EGG-PHY-7602 TECHNICAL EVALUATION REPORT for the RADIOLOGICAL EFFLUENT RELEASE AND ENVIRONMENTAL OPERATING REPORTS FOR 1985 SOUTHERN CALIFORNIA EDISON COMPANY SAN ON0FRE NUCLEAR GENERATING STATION UNIT 1 NRC DOCKET NO. 50-206 NRC LICENSE NO. DPR-13 T. E. Young, E. H. Magleby, W. Serrano, T. S. Bohn, J. W. Mandler, and F. B. Simpson Published June 1987 EG&G Idaho, Inc.

Idaho Falls, Idaho 83415

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Prepared for the U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Under DOE Contract No. DE-AC07-76ID01570 FIN No. A6808 L_-_-_-_-_____

ABSTRACT A review was performed of reports required by Federal regulations L and the plant-specific radiological effluent technical specifications (RETS) for operations conducted at San Onofre Nuclear Generating Station, Unit i 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 carlier 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 found to be reasonably complete and consistent with the review guidelines. The Offsite Dose Calculation Manual (0DCM). Revision 2 dated 06-15-85 for San Onofre Unit 1 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 gaseous release points. Because-of this exception, it is uncertain if the methodology provides assurance that the NUREG-0472 dose rate limits will not be exceeded.

The Licensee' submitted minor changes to the generic Process Control Program (PCP) which presently.has interim NRC approval. The reported changes were reviewed and it is recommended the interim NRC approval be extended to include the reported changes.

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FOREWORD This report is supplied as part of the " Selected Operating Reactor

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Issues Program (III)" being conducted for the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, by the INEL, Radiological Physics.

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, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe

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privately-owned rights.

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CONTENTS page Abstract..

i Foreword..............................

ii 1.

Introduction..........................

1 2.

Technical Summary.........

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.

10 2.5 Revisions to 00CM, PCP, and Radwaste Treatment Systems...

15 2.6 Analysis of Release, Dose, and Environmental Trends....

16 2.7 Information Contained in Licensee's Reports........

22 3.

Conclusions...........................

26 4.

References...........................

28 Appendix A.

Plant and Site Design Features............. Al Appendix B.

Summary of Radioactive Effluent Releases and Calculated Doses.................... B1 Appendix C.

Radiological Environmental Monitoring Program Results..................... C1 Appendix D.

Evaluation of Changes to the 00CM, PCP, and Radwaste Treatment Systems............... D1 1

Appendix E.

Tables of Licensee's Report Commitments.

.. El Appendix F.

Checklist of RETS-Required Reports...........

F1 i

TABLES l

1 2-1 Summary of Reported Radioactive Effluents / Exposures for 1985..

4 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 17 2-4 Direct Radiation and Gross Beta Activity...........

20 iii

FIGURES Page 2-1 Radioactivity of effluents from San Onofre Nuclear Generating Station, Unit 1 and calculated offsite doses for 1984 and 1985.

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2-2 Levels of radioactivity in the environs of San Onofre Nuclear Generating Station Units, 1,2,3 for 1984 and 1985.......

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1.

INTRODUCTION This Technical Evaluation Report presents a review and summary of l

the reports submitted by the Licensee of San Onofre Nuclear Generating Station Unit 1 in accordance with the plant's Radiological Effluent Technical Specifications (RETS) for operations conducted during 1985.

The principal review guidelines were the plant's 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,"[3] and NRC memorandum guidance " Criteria for Process Control Program."[43 Special emphasis is placed on any reported changes to the Licensee's Process Control Program (PCP), Offsite Dose Calculation Manual (ODCM), and radioactive waste treatment syster.

This report also includes results of a survey of reported releases of radioactive materials, calculated doses and dose commitments to 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.

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2.

TECHNICAL'

SUMMARY

2.1 Plant-Specific Background 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, California.

Plant-specific information pertinent to this review is given below for Unit 1 of-.the three San Onofre units.

Type of Reactori PWR (Westinghouse).

Licensed Thermal Power 1347 MWt Maximum Dependable Power 436 MWe Net 4

Commercial' Operation

. January 1, 1968-RETS Implementation January 1, 1985

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l Condenser Cooling Water.

Once through to the Pacific Ocean System Major Gaseous Discharge Plant Vent Stack, Elev. = 157 ft.

' Point' Gross Electric Output 1984:

304,200 MWh 1985:

2,618,768 MWh 1

Average Capacity Factor 1984:

7.59%

1985: 65.56%

1 The circulating water system operates in the once-through mode, with water _being taken from and discharged to-the Pacific Ocean via intake and i

discharge conduits.

The " site boundary for gaseous effluents" is l

essentially a pair of 1967.5 ft.- radius circles centered at Units 2 and

3. - A map of the plant area is shown in appendix A.

1 All radioactive gaseous effluents are discharged as ground level I

relases, since Unit i does not conduct elevated releases.

Radioactive liquid effluents are discharged to the Pacific Ocean ~with the Unit 1 main condenser cooling water.

Diagrams of the liquid and gaseous radwaste treatment systems and discharge pathways are shown in Appendix A.

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l 2.2 Radioactive Effluent Releases Reported radioactive effluents during 1985 were low enough that the calculated offsite doses were less than 50% of the technical specification

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reporting levels. There were no abnormal liquid releases reported by Unit 1 of the San Onofre Nuclear Generating Station during 1985, but they did report one abnormal gaseous ' release that resulted in the release of 0.34 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 semiannual 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 There are three nuclear power units at the San Onofre site.

Unit 1 has it's own circulating water outfall pipe which returns Unit 1 main

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condenser cooling water to the Pacific Ocean through a 2600 ft. long conduit.

There are four pathways for discharging potentially radioactive liquids to the circulating water outfall line:

the liquid radwaste effluent line, the steam generator blowdown effluent line, the turbine building sump effluent line (from the reheater pit sump), and the yard.

sump effluent line (see figures in Appendix A).

Releases are made in both the batch and continuous modes.

Batch releases are made from the monitor tanks through the liquid radwaste effluent line.

The Licensee's ODCM indicates that batch releases are also made through the steam generator blowdown effluent line (See discussion in Appendix 0.) Continuous releases are made through the steam generator blowdown effluent line, the turbine building sump effluent line, and the yard sump effluent line.

Each release pathway is continuously monitored for radioactivity during the releases.

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TABLE 2-1.

SUMMARY

OF REPORTED RADI0 ACTIVE EFFLUENTS / EXPOSURES FOR 1985

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1.

ACTIVITY RELEASED Solid Waste and

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Liquid Effluents Gaseous Effluents Irradiated Fuel Shipments A.

Fission and Activa-A.

Particulate A.

Spent Resins, Filter tion Products Sludge, Evaporator Bottoms, etc.

Total:

7.99 Ci Total:

0.000246 Ci Unit 1: 0 Ci Cs-137 2.73 (34.2%)

Rb-88 0.000122 (49.6%)

Common: 0 Ci Co-58 1.86 (23.3%)

Br-82 0.000099 (40.2%)

Cs-134 1.39 (17.4%)

Ce-144 0.00000684 (2.8%)

Co-60 0.89 (11.1%)

Cs-137 0.00000629 (2.6%)

1-131 0.484 (6.0%)

Fe-55 0.337 (4.2%)

B.

Tritium B.

Tritium B.

Dry Compressible Waste, Contaminated Equipment, etc.

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Total:

2380 Ci Total:

28.9 Ci Unit 1:

5.05 Ci Common: 0.501 Ci Dissolved or En-C.

Noble Gases C.

Irradiated Components

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trained Noble Gas

. Control Rods, etc.

Total:

31.2 Ci Total:

3,840 Ci Unit 1: O Ci Xe-133 30.4 (97.4%)

Xe-133:

3,570 (93.1%)

Common: 0 Ci Xe-131m 0.419 (1.3%)

Xe-135:

190 (5.0%)

D.

Gross Alpha D.

Iodines D.

Other (filter, sludge, sand / rubble, wet Total:

0.00358 Ci Total:

0.00125 trash)

I-131:

0.00114 (91.6%)

I-133:

0.000104 (8.4%)

Unit 1: 0.995 Ci Common: 0.395 Ci E.

Batch Releases E.

Batch Releases E.

Disposal Site Batch releases, but Batch releases, but not discussed.

not discussed.

Richland, WA

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F.

Abnormal Releases F.

Abnormal Releases F.

Irradiated Fuel None One:

0.34 Ci (Xe-133)

None 4

TABLE 2-1.

SUMMARY

OF REPORTED RADIOACTIVE EFFLUENTS / EXPOSURES FOR 1985 (Cont.)

II.

EFFLUENT DILUTION

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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-633.8 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

Maximum Site Boundary Noble Gas Doses

a. 6.0E-5 9.2E-8 (Nearest state land

a. Stack & turbine vent

b. 3.0E-4 4.7E-7 Boundary - 0.17 mi.

b. Containment purge

c. 3.3E-4 5/1E-7 WNW of Unit One Vent)

c. Gas decay tank releases Maximum Exposed Individual

a. 3.2E-6 1.3E-8 (Nearest residence and

a. Stack & turbine vent

b. 9.1E-6 3.9E-8 garden - 1.0 mi. NNW

b. Containment purge

c. 9.7E-6 4.1E-8 of Unit One Vent)

c. Gas decay tank release III. MAXIMUM INDIVIDUAL DOSES Liquid Effluents Gaseous Effluents Direct Radiation A. Total Body Dose A. Noble Gas Air Dose I

1.36 mrem (45.3%)c Gamma:

0.595 mrad (5.95%)c 0.802 mrem (Pro-Beta:

1.38 mrad (6.90%)c rated on the basis of 300 hrs /yr at San Onofre State Beach, Unit 1)

B. Organ Oose B. Organ Doses (I-131, long-lived particulate, j

and tritium.)

1.90 mrem (19.0%)c 0.0160 mrem (0.107%)

Critical organ:

Critical Organ:

Liver Child thyroid 9 liters.

a. GL (gigaliter) = 10

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

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

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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 7.99 Ci of fission and activation products and 2380 Ci of tritium were released.

l The most abundant radioisotopes among the fission and activiation l

products were:

Cs-137 (34.2%), Co-58 (23.3%), Cs-134 (17.4%), and

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l Co-60 (11.1%).

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I A total of 633.8 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 i

1 All gaseous effluents expected to contain significant amounts of radioactive materials are released to the atmosphere through the monitored plant vent stack.

In addition, the waste gas decay tanks and containment are sampled and analyzed before batch releases are made from these sources.

Several important aspects of the Licensee's 1985 gaseous releases are as follows:

l Releases were reported both in batch and continuous mode during e

1985.

a Total gaseous releases included 3,840 Ci of noble gases,

0.00125 Ci of radiciodines and 0.000246 Ci of particulate.

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.

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f.

l' A total of-28.9'Ci of tritium was released.

The most' abundant radioisotopes in each gaseous group were Xe-133 l

for noble gases (93.1%), I-131 for radiciodines (91.6%), and Rb-88 for particulate (49.6%).

l There was one abnormal gaseous release reported during 1985, e

L consisting of 0.34 Ci of Xe-133.

l 2.2.3 Solid Radioactive Waste and Irradiated Fuel Shipments Information on the Licensee's 1985 shipments of solid radwaste to offsite locations is presented in Appendix B and is summarized below for the San Onofre Nuclear Generating Station, e

A total of 180.3 m8 of solid radwaste containing 6.0 Ci was shipped offsite from Unit 1.

In addition,15.635 m8 of solid radwaste containing 0.896 Ci was shipped offsite that was identified as common radwaste.

No spent resins, filter sludges, evaporator bottoms were shipped offsite from Unit 1 during 1985.

A total of 136.3 ma of dry compressible waste with an activity of 5.05 Ci was shipped offsite from Unit 1.

In addition, 0.425 m containing 0.501 Ci was shipped offsite that was identified 8

as common dry compressible waste..

No irradiated components, control rods, etc. were shipped offsite during 1985 from Unit 1 or as common waste.

e A total of 44.0 m8 of Other (filters, sludges, sand / rubble, wet trash) waste with an activity of 0.995 Ci was shipped offsite from a

Unit i during 1985.

In addition, 15.21 m containing 0.395 Ci was shipped offsite that was identified common "Other" waste.

7

l Forty truck 1 shipments were made'to Richland, WA during 1985 from the San Onofre site. There was no breakdown as to the number of truckloads shipped from individual reactor units.

'The Licensee did not' ship spent resins, etc. from Unit I during e

1985. EFor Units 2/3 resins, etc. cement was used'for solidification during the first six-months and.High Integrity containers were used for shipments of dewatered waste during the second six-months.

No_ shipments'of. irradiated fuel were reported from the San Onofre Nuclear Generating Station'auring 1985.

2.3 Radiological Dose Impact As seen in Table 2-1,.the reported San Onofre Nuclear Generating

Station'offsite' dose-impact was, in all cases, below the reporting levels specified in the RETS with 45.3% of these technical specification limits in the worst case.

(The Licensee's technical. specification reporting levels are equal to the 10 CFR 50, Appendix I guidelines.)

The Licensee estimated a maximum dose of 0.802 due to direct radiation (See Table 2-1.)

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 The.following liquid effluent doses were reported by the Licensee:

i The maximum whole body dose was 1.36 mrem (45.3% of the 10 CFR 50, Appendix I guideline of 3 mrem).

The critical organ was identified as the liver, with a maximum dose of 1.90 mrem (19.0% of the 10 CFR 50 Appendix I guideline of 10 mrem).

a 8

l 2.3.2 Gaseous Effluent Dose The following gaseous effluent doses were reported by the Licensee:

I The gamma air dose during 1985 was 0.595 mrad (5.95% of the e

technical specification reporting level of 10 mrad).

j The beta air dose during 1985 was 1.38 mrad (6.90% of the e

technical specification reporting level of 20 mrad).

The maximum organ dose due to iodines, particulate and tritium was 0.016 mrem to the thyroid of a child (0.107% of the 10 CFR 50, Appendix I annual limit of 15 mrem).

2.3.3 Total Dose To show compliance with the fuel-cycle-dose limits of 40 CFR 190, the

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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 radiation, and doses due to gaseous effluents (calculated using historical meteorology). Oose calculations using historical meteorology usually gave significantly higher doses due to gaseous effluents than corresponding doses (also reported) calculated using concurrent meteorology. (The ratio of historic-meteorology-doses to concurrent meteorology-doses ranged from 0.1 to 13.4.)

It is not clear why use of concurrent meteorology for calculation of offsite doses due to gaseous effluents usually (in 10 of 12 quarterly calculations) resulted in lower doses than use of historical meteorology, for both noble gases and iodines, etc.

Noble gas batch releases could be scheduled to take advantage of favorable meteorological conditions, but the calculated doses due to iodines, particulate, and tritium were also usually lower (in 6 of 8 cases, when Units 2 and 3 are 9

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_ included) when concurrent meteorology was used, and all releases of iodines and particulate were in the continuous mode.) Dose contributions from Units 1, 2, and 3 were included in the 40 CFR 190 calculations.

The Licensee stated that'there are no other nuclear fuel cycle sources within 8 km.

2.4 Radiological Environmental Monitoring Program l

'The Licensee's annual radiological environmental monitoring reportE93 presents both' raw and summarized data obtained from the l

analyses of a large number of environmental samples collected during 1985.

The monitoring program reported is summarized in Table 2-2.

More 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 RETS.

The report also included an LLO of 5 mrem for direct radiation.

The only radionuclides detected that were attributable to operation of Unit 1 were Co-58, Co-60, I-131, and Cs-137.

Cobalt-58 and Co-60 were detected in Sea J

Hare'(a mollusk) flesh samples from near the' Unit 1 outfall_at up to 1.2%

and 19% of the reporting level, respectively.

Cobalt-60 and Cs-137 were also detected in several other-marine animal flesh samples at less than 1%

j of the reporting levels.

Several marine animal bone and shell samples contained Co-60 at less than 1% of the reporting level of 10 pCi/g.

One i

sample of Black Perch bone from the Unit 1 outfall area contained Co-60 at j

4.0% of the reporting level.

The Licensee's results from kelp monitoring (not required by the technical specifications) were inconclusive.

Cobalt-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 i

location.

I-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 compared to 0.038 pCi/g at the control location.

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.Particular emphasis.in the program was placed on detection of direct radiation, airborne I-131, radioactivity in airborne'particualtes, 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.

3 samples from one control location gave 0.021 pCi/m.

3

'I-131 was detected in'nine of 423-airborne samples from indicator e

locations at a-mean of 0.373 pCi/m, compared to no a'tivity 3

c detected 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 l

indicated negligible plant effect.

Gross beta activities in drinking water samples from indicator

~

locations determined by different analyses (monthly, quarterly, solids, filtrate) were from 28% to 72% greater than in l

corresponding control samples.

Since the plant's liquid discharges are to the ocean, this difference was attributed to I

natural causes.

Detectable levels of Co-58, Co-60, and Cs-137 (at up to 1.2% of the reporting level for Co-58, 197,of the reporting level for l

Co-60, and 0.8% of the reporting level for Cs-137) were measured I

in marine animal flesh samples from near the Unit 1 outfall.

(Samples from near-the Units 2/3 outfall contained lower L

concentrations of these radionuclides.)

l l

12

2.4.1 Direct Radiation In the discussion of direct radiation the Licensee stated that except at the SONGS meteorological tower (which is within the exclusion area) the plant operations "had negligible impact on this environmental medium."

(The direct radiation level recorded at the meteorological tower during the fourth quarter was 4.58 times the control location value, due to radiation received from two radwaste vehicles parked nearby.)

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 at 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 f

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 4

<2 miles, 6% lower at 2-5 miles, 14% lower at > 5 miles, and 3% higher at the control locations.

1 2.4.2 Airborne Gross Beta and I-131 Activities Airborne gross heta 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.

j 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.

2.4.3 Waterborne and Ingestion The Licensee did not report any significant plant impact on the environment through water pathways (ocean water, drinking water, shoreline 13

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, but was attributable to naturally occurring K-40 at all locations.

All radioactivity detected in shoreline sediments was due to-naturally occurring radionuclides.

In 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 was detected at an indicator location and the control location. The Licensee also stated that the impact on the environmental medium was minimal.

I 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-60 (less than 20% of the reporting level).

This relatively large concentration of Co-60 by itself might imply a buildup at the Unit 1 outfall. However, the plot furnished by the Licensee of Co-60 in mollusks from 1979 through 1985 shows an erratic trend, with peaks in 1981 and 1985.

The Licensee calculated adult whole body and organ doses assuming I

21 kg consumption per year and using radionuclides concentrations observed at the Unit 1 and Units 2/3 outfalls.

The highest doses calculated 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 attributable to radionuclides concentrations detected at the Units 2/3

)

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 species sampled are not popular for consumption, and stated "the operation of SONGS had a minor but detectable impact on this environmental medium."

14

I l

i 4.4 Land Use Census Very detailed results were reported from the annual Land Use Census required by the Lice'nsee's Units 2'and 3 Technical Specification 3.4.12.2 and Unit 1 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 1

Changes to the San Onofre Offsite Dose Calculation Manual (ODCM) for Unit 1 are reported to the NRC by the Licensee in the Semiannual Radioactive' Effluent Release 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%.

15

d i

2.6' Analysis of Release,' Dose, and Environmental Trends Radioactive effluent data and' calculated dose impacts for San Onofre Nuclear Generating Station (SONGS), Unit 1 for 1984 and 1985 are summarized in Table 2-3 (doses.were not reported for 1984).

Activities of fission and activation products in, liquid effluents, of fission and activation gases, and of-radioiodines and particulate in gaseous l

effluents are platted by year in Figure 2-1.

Calculated offsite doses due

-to liquid and gaseous effluents are also shown in this figure, j

\\

l.

2.6.1 Trends of Effluent Releases and Calculated Doses Unit 1 opera'ted at significant power only during the final month of-l 1984 since it'was in shutdown most of the year.

Offsite doses due'to effluents were not calculated for 1984.

(The calculations were not required by the technical specifications in effect I

during 1984)..Therefore, there are no calculated dose values from 1984 to compare'with the 1985 values.

-Another complicating factor is that all the I-131 released in gaseous effluents from Unit i during the first three quarters of 1984 (83% of the total for the year) was due to processing of Unit 2/3 radwaste at Unit 1.

l Also,-a footnote to the values for continuous releases of I-131 and Co-58 in continuous liquid effluents'during the fourth quarter of 1984 stated:

j "The evaporation pond is released through the Unit 1 outfall.

Activity released from;the evaporation pond originates from Units 2/3".

Because of the lack of data and complications of releases from Units 2/3 through the Unit i system during 1984, no meaningful discussion of I

trends of activities released or calculated offsite doses was possible for

.)

the 1984-1985 period.

16 i

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u.t..

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i Figure 2-1.

Radioactivity of effluents from San Onofre Nuclear Generating i

Station, Unit 1, and calculated offsite doses for 1984 and 1985.

18 i

I

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t ~

1 Figure 2-1.

Radioactivity of effluents from San Onofre Nuclear Generating Station, Unit 1, and calculated offsite doses for 1984 and 1985 (cont.)

~

19 i

l

l-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 1984[113 and 1985[93 are tabulated in Table 2-4 and plotted in Figure 2-2.

I TABLE 2-4.

DIRECT RADIATION AND GROSS BETA ACTIVITY l

l Direct Radiation Dose Airborne Gross Beta J

Level's (mrem /atr)

Activity (pCi/m )

]

3 Control Indicator' Control Indicator Year Locations Locations Locations Locations 1984 23.8 21.2 0.020 0.020 1985 22.6 20.4 0.021 0.020

. 1 Direct radiation levels were about 5% lower in 1985 than in 1984, and about 10% lower 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 Unit 1.)

l Airborne. gross beta activity levels were essentially the same

-during-1985 as in 1984.

The Licensee discussed these levels for the l

1981-1985 period and concluded that there was no increasing trend.

i Iodine-131 was detected in 9 of 476 air samples during 1985 and 2 l

of 464 samples during 1984, all at onsite locations.

l e

20 l

f I

1

\\

Jo-l 27 Control j

g indica tor 21 E

N 1s 33 y

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l 1951 1982 1983 1954 198S YEAR A.

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1981 1982 1983 1954 1985 j

YEAR l

B. Airborne gross beto activity, j

l Figure 2-2.

Levels of radioactivity in the environs of San Onofre Nuclear Generating Station, Units 1,2,3, for 1984 and 1985.

3 l

^

l 21 j

p.-_______.

L L

i 2.7 Information' Contained in Licensee's Reports 1

Information contained in the Licensee's' reports was compared with the Licensee's report commitments (see tables in Appendix E) for the.

Licensee's Annual Radiological Environmental Operating Report for' 1985[93 and the two Effluent and Waste Disposal Semiannual ~ Reports for 1985.[7,8] The completeness of the reports' submitted compared to the 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 i

program conducted during 1985 and reported summarized and tabulated results of the program. The report included results of the radiological' environmental. monitoring program, resultsHof the

~ Licensee's participation in.an interlaboratory comparison ~ program for environmental. samples, a complete report of the environmental samples, and a complete report of the results of the land use census.

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 1 1/2 sampling-period 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.).

22

i l

Orinking water samples from the San Clemente golf course were e

taken from a single well because the second well was being repaired.

Fleshy vegetables (e.g., squash, cucumbers) were substituted for J

unavailable leafy vegetables.

i lSeveral non-migratory marine animals were sampled at a somewhat later time than scheduled.

One sample of kelp was not obtained because of l

non-availability.

Two ocean bottom sediment samples were taken later than scheduled.

Comparison of the contents of the Licensee's environmental monitoring report with the requirements of the Unit 1 technical specifications revealed no significant discrepancies except that comparisons of 1985 monitoring results with preoperational data were made only for air particulate, drinking water, and local crops, since no preoperational data were available for other sampled media.

The Licensee reported 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 LLO'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.

e 23

The Licensee also included a table titled " Measurements Exceeding Investigation Levels" which contained a. listing of individual samples more than 25% above background for external dose or twice background for radionuclides content (or twice the LLD if no 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 editori>> 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).

l l

l 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.

The Licensee reported one abnormal gaseous effluent release from the plant during 1985, with a total release of 306 Ci of Xe-133.

l The following items were noted in the Licensee's liquid and gaseous effluent, solid waste shipped offsite, and dose reporting:

l The average energy of fission and activation gases was not e

discussed.

24

. _ - - _ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ _ _ _ - - - _ _ _ _ _ - _ _ _ _ = _ _ _ _ - - _ _ -.

Total body doses to the population and average doses to e

. individuals in the population from gaseous effluents to a distance of 50 miles were not stated.a Unit i did not provide information about liquid and gaseous

~

e a

batch releases,

The licensee did not specifically state that there were no e

abnormal liquid releases during 1985.

Solid waste shipping container volumes were given in cubic feet rather than cubic meters, as is required by their RETS.

The Licensee's technical specifications can be interpreted as not

- a.

requiring this information, since they do not specify that the contents of. reports must be a specified in Regulatory Guide 1.21, Revision 1, June 1974.

e 25

l l

)

l 3.

CONCLUSIONS l

The radioactive effluent release reports and the radiological environmental monitoring reports submitted for San Onofre Nuclear Generating Station Unit 1 met essentially all of the reporting requirements of the Licensee's RETS.

Some environmental monitoring studies were not compared to preoperational studies because of a lack of preoperational measurements. 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 listing of raw data (individual sample measurements) was included in the environmental monitoring report.

The following conclusions may be drawn from the data reported by the Licensee:

Due to the short period of operation of Unit 1 during 1984 there could be no meaningful trend analyses of release of radioactive materials and calculated offsite doses for the years 1984 and 1985.

Offsite doses due to radioactive effluents from Unit 1 were reported as 45.3% or less of the 10 CFR 50, Appendix I I

guidelines.

i 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 radioactive effluents from Unit 1 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 Units 2/3 and also to the fact that concurrent data was used to calculate doses due to gaseous effluent for comparison with 10 CFR 50 limits, but historical data was used for doses to l

compare with 40 CFR 190 values.)

26

)

i

During 1985 the Licensee conducted an environmental monitoring program, participated in an approved interlaboratory comparison program, and performed a land-use census essentially in f

accordance with the requirements of the plant's RETS.

Only in the case of non-migratory marine animals did analyses of samples taken in accordance with the Licensee's radiological environmental monitoring program show definite evidence of plant influence on radioactivity levels in the environment, specifically the case of 1.9 pCi/g of Co-60 in Sea Hare at the Unit 1 outfall.

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 2 radwaste vehicles nearby.

The Licensee's revision to the ODCM for Unit 1 (Revision 2, 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 Unit i noble gas effluent monitors does not consider simultaneous releases from Units 2 and 3.

Therefore, it is uncertain if the methodology provides reasonable assurance that the NUREG-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 from <1.0% to

<0.5%, a conservative change.

27

4.

REFERENCES

1.. " San Onofre Nuclear Generating Station Unit l' Technical Specifications, Appendix A to License.No. DPR-13," through Amendment No. 90.

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 Technical Specifications for Nuclear Power 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.

" Semiannual Radioactive Effluent Release and Solid Waste. Disposal 1

Report,"' January 1, 1984 through June 30, 1984, San Onofre Nuclear i

Generating Station, Units 1, 2, 3, Southern California Edison l

i

' Company, August 24, 1984 (available in the NRC Public Document Room).

{

6.

" Semiannual Radioactive Effluent Release and Solid Waste Disposal Report," July 1, 1984 through December 31, 1984, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison

Company, February 25, 1985 (available in the NRC Public Document Room).

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).

j 28 l

l E_____2__ n _ _____

i i

" Semiannual Radioactive Effluent Release Report," July 1, 1985

'f 8.

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.)

" Annual Radiological Environmental Operating Report" for 1984, San 9.

Onofre Nuclear Generating Station, Units 1, 2,'3, Southern California Edison Company, 1985 (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, giving interim approval to a generic PCP for San Onofre Nuclear Generating Station.

11.'" Annual Radiological Environmental Operating Report" for 1985, San Onofre Nuclear Generating Station, Units 1, 2, 3, Southern California Edison Company, April 39,1986 (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.

l S

l i

29 i

i I

l a

l e

l APPENDIX A Plant and Site Design Features for the San Onofre Nuclear Generating Station, Unit 1 I

i 1

I 1

1 l

l l

u_________________

_)

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 l

the plant. The public is not entirely excluded from the area within 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 exclusion area boundary for gaseous effluents. There is-free public transit along old U.S. Highway 101 and the San Diego Freeway as well as along a pathway between 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.

The discharge point for main condenser cooling water.from Unit 1 is shown in' Figure A-2 (at the end of a 2600 ft. conduit). Gaseous and liquid radwaste systems and discharge pathways are shown in Figures A-3

-i and A-4.

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APPENDIX B l

Summary of Radioactive Effluent Releases and calculated Dose (San Onofre Nuclear Generating Station, Unit 1) e b

e

._-_____________w

h The data summarized here are taken from the Licensee's radioactive effluent release data submitted.for 1984 and 1985.

i l

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 the shipment of solid radioactive waste for offsite burial.

San Onofre ships solid waste only'from the station. Therefore, these tables reflect solid waste from Units 1, 2, and 3 and will be identical with Tables B-3 and B-7 in the TER for Units 2 and 3, EGG-PHY-7603.

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.

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1 APPENDIX C Radiological Environmental Monitoring Program Results (San Onofre Nuclear Generating Station, Unit 1) t O

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The. conduct of.the Licensee's radiological environmental monitoring

' program'during 1984, as reported in the Licensee's Annual Radiological Environmental Operating ReportE93 for 1985 is summarized in this appendix.

San Onofre Nuclear 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 of 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 2/3 and 1 1/2 miles from shore;(See Figure A-3.)

l The Licensee's ' radiological environmental monitoring program follows 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 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 locations were apparently 35 miles NNW. The NRC's indicator and control C3

l l-l location values (in mR/std qtr) were, respectively, 9% below and 3% above those reported by the Licensee (in mrem /qtr.)

The Licensee states, "... it is concluded that the radiological environmental impact of the San Onofre Units 1, 2, and 3 operations 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.

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NRC TLD DOSES FOR SAN ONOFRE ARER C rnR p e r 90 d ays )

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Locations of NRC's direct radiation (TLD) monitors at San Onofre Nuclear Generating Station.

(Figure reproduced from "NRC TLD Direct Radiation Monitoring Network", NUREG-0837, dated May 1986).

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TABLE C-1.

LICENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING' LOCATIONS Sample Typed Location-Location Code Description of Location Dist. (mi)b Sectorb j

Direct Radiation 1

(TLD) 1 City of Clemente (SOG&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

l 5

Camp Las Pulgas 8.5 ESE l

6 Old Route 101 - East-Southeast 3.0 ESE 7

Old Route 101 - East-Southeast 0.5 ESE 8

Noncommissioned Officor's Beach Club 1.2 NW 9

Basilone Road /I-5 Freeway Offramp 2.0 NW 10 Bluff-0.8 NW 11 El Camino Training Annex 0.2 NNE 12 South Edge of Switchyard 0.2 NE i

13 Site Boundary 0.13 SE 14 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 3.6 NW 22 Coast Guard Station - San Mateo Point 2.7 WNW 23 San Clemente General Hospital 8.2 NW 24 San Clemente High School 6.0 NW

)

25 Convalescent Home - San Clemente 8.0 NW q

26 Dana Hills High School 11.0 NW i

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 32 Santa Ana Police Department 32.0 NW 33 Camp Talega 5.7 N

34 San Onofre School 1.7 NW 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 38 San Onofre State Beach Park 3.6 SE 39 Basilone Road Trailer Park 1.4 NNW 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

C13

[

L TABLE C-1.

LICENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (Cont.)

Sample Typea Location l

Location Code Description of Location Dist. (mi)b Sectorb 1

Direct Radiation l

(TLD)

~

45 Interstate 5 Weigh Station 2.0 ESE 46 San Onofre State Beach Park 1.4 SE 47 Camp Las Flores 8.6 SE 48 Mainside (Camp Pendleton) 15.0 ESE 1

'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 2

Camp San Onofre (Camp Pendleton)c 1.8 NE 3

Huntington Beach Generating Station 37 NW 5

Units 2 and 3 Switchyardc 0.13 ESE c

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

Huntington Beach Generating Station 37 NW 5

East Site Boundary 0.2 NNW C14

[.

I TABLE C-1.

LICENSEE'S RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS (Cont.)

)

1 Sample Typea Location i

Location Code I

TLD Description of Location Dist. (mi)b Sectorb j

Ocean Water A

Station Dicharge Outfall - Unit 1 0.5 SW B

'0utfall - Unit 2 0.7 SW

(

C Outfall - Unit.3 0.7 SW 6

I D

~ Newport Beach 30 NW Drinking Water i

1 I

1 Tri-Cities Municipal Water District Res.

8.7 NW 2

San Clemente Golf Course Well 3.5 NNW 3

Huntington Beach 37 NW l

l 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 4

Newport Beach (North End) 30 NW I

Local Crops 1

San Mateo Canyon 2.6 NW 2

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 D

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 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.

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 l

l i

Station Dist. (Mi.)

Dir. (*)

Description 1

35.0 346 Featherly Park 2

35.0 346 Featherly Park I

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 O

C33

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APPDIDIX D Evaluation of Changes to the ODW, FCP, and Radante Treatment Systems for the San Onofre Nuclear Generating Station Unit 1 I

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G D2

D.1 EVAUJATION OF QW1GES 70 THE ODQ4 The Southern California Edison Company (SCE), the Licensee for the San Onofre Nuclear Generatiry Station with Units 1, 2 and 3, prepared an

~

Offsite Dose Calculation Manual (OD04) for Unit 1 and another ODCM for Units 2 and 3.

Revisions to the OD04 are required by the Licensee's 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 OD04s in the Semiannual Radioactive Effluent Release reports for the first half of B85(1) for Unit 1 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 OD04 Revision 2 dated 06-15-85 for Unit 1 and OD04 Revision 17 dated 06-15-85 for Units 2 and 3.

The NRC mailed the OD04 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 ODQi evaluation for Unit 1 is intended to be a stand-alone document and is given in Supplement 1 to this appendix.

D.2 EVAIDATION OF Q W1GES TO THE FCP Initially, the SCE prepared individual Process Control Programs (PCP) that were unit and processing specific. The individual PCP3 were subsequently replaced with a generic PCP which allowed several process j

mLhods for the site ard the generic FCP 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, 1935(4).

Changes to the ICP

~

are required by the licensee's technical specifications to be reported to the NRC in the Semiannual Radioactive Effluent Relenne Reports. Three changes to the generic PCP were reported in the Semiannual Radioactive

~

Fffluent Release Report for the second half of 1985(5)

Two of the changes were editorial and the third changed the free-standing liquid

requirement when dewatering resins to <0.5% instead of <1.0%.

'Ihe 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 hn=nt was not made and the

' NRC interim approval of the generic PCP should be extended to include,

these reported changes.

D.3 REPORIED CHANGES 'IO 'IHE RADWASTE TREA'IMENT SYSTD4S

'Ihe lioensee's technical specifications require changes to'the

' radioactive liquid, gaseous, and solid waste treatment systems to be reportedintheSNannualRadioactiveEffluentReleaseReports. No major changes to these systems have been reported in the Semiannual Radioactive i

Effluent Release Reports for years 1984 and-1985.

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i D.4 REFERDiCES 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.

l l

i 2.

I.etter frun H. E. Morgan (SCE) to J. B. Martin (NRC),

Subject:

Monthly Operating Reports for August 1985 San Onofre Nuclear Generating Station, Units 2 and 3, September 16, 1985.

3.

I.etter from H. E. Morgan (SCE) to J. B. Martin (NRC),

Subject:

San Onofre Nuclear Generating Station, Units 1, 2, ard 3, September 17, 1985.

4.

I.etter from G. W. Knighton (NRC) to K. P. BasPdn (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 Reaulatiora, Part 61.56, " Waste Characteristics".

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SUPPIB4E2R 1 to APPENDIX D EVAIDATION OF GANGES TO TIE ODCM 9

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INITODUCTION

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Purnose of Review The purpose of this document is to report the review and evaluation of the revised Offsite Dose Calculation Manual (ODCM) submitted by the Southern California Edison Company (SCE) for the San Onofre Nuclear Generating Station Unit 1.

The ODCM is a supplementary document for i

implementing the Radiological Effluent Technical Specifications (RETS) in compliance with 10 CFR 50, Appendix I requirementsIll.

Scope of Review j

As specified in NUREG-0472[2] aM 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 effluent systems. As a minimum, the ODQ4 should provide equations and a

methodology for the following topics:

o Alarm and trip setpoints on effluent instnmentation o

Liquid effluent concentrations in unrestricted areas o

Gaseous effluent dose rates at or beyond the site boundary o

Liquid and gaseous effluent dose contributions o

Liquid and gaseous effluent dose projections.

In addition, the ODQ4 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 description and the location of samples in support of the environmental monitoring program are also needed in the ODQ4.

O D1-3

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Plant-Soecific Backarourd The SCE prepared an 00CM for San Onofre Unit 1 and another ODCM for Units 2 and 3.

NRC notification of approval of 0D04 Revision 2 dated September 20, 1984 for Unit 1 was transmitted to the Licensee with letter dated August 30, 1985[43 The Licensee submitted 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 Units 2 and 3.

he revisions were also submitted to the NRC with letter dated September 17, 1985[5]. h e letter contained ODCM Revision 2 dated 06-15-85 for Unit 1 and ODCM Revision 17 dated 06-15-85 for Units 2 and 3.

Revision 2 of the ODCM approved by the NRC for Unit 1 with letter dated August 30, 1985 is not the same ODCM Revision 2 submitted for review by the Licensee with letter dated September 17, 1985.

h e NRC transmitted the ODCM revisions to the Idaho National Engineering laboratory (INEL) for review. h e INEL reviewed the Unit 1 ODCM Revision 2 dated 06-15-85 as a whole and the results and conclusions of the evaluation are presented in this supplement.

~

REVIEW CRITERIA l

Review criteria for the OD04 were provided by the NRC in three documents:

NURB3-0472, REIS for PWRs[2]

NURB3-0473, REIS for BWRs[3]

NURD:;-0133, Preparation of RETS for Nuclear Power Plants [6].

In the ODCM review, the following NRC guidelines were also used:

" General Contents of the Offsite Dose Calculation Manual,"

Revision 1,[7] ard Regulatory Guide 1.109.[8] me ODCM format is left to the Licensee and may be simplified by tables and grid printouts.

1 D1-4 i

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[

i EVAIDATION i

'Ihe Licensee, to provide reasonable assurance that the maximum

]

permissible concentrations (MPCs) specified in 10 CFR 20E93 will not be J

exceeded by discharges fram the liquid or gaseous release points, has in j

general followed the methodology of NUREG-0133 to determine the setpoints for the liquid ard gaseous effluent monitors.

{

'Ihere are three nuclear power units at the San Onofre site. Unit 1 has it's own liquid radwaste discharge system and releases liquid radwaste to it's own circulating water outfall pipe which returns Unit 1 condenser cooling water to the Pacific Ocean. Units 2 and 3 share a common radwaste treatment system whose effluents are discharged to the Unit 2 circulating water outfall pipe which returns Unit 2 condenser cooling water to the Pacific Ocean. Since the liquid radwaste system of Unit 1 is served by a dilution stream separate from the Unit 2 dilution stream, then liquid releases from Unit 1 may be made independent of releases from Units 2 a

and 3.

~

The methodology to determine the setpoints for the radioactive liquid effluent monitors is contained in Section 1.1.

As shown in Figure 4-1 of the San Onofre Unit 1 (SONGS 1) ODCM, there are four sources of potentially radioactive liquids that may be discharged to the circulating water outfall line: the liquid radwaste effluent line, the steam generator blowdown effluent line, the turbine building sump effluent line (reheater pit sump), and the yard sump effluent line. Section 1.1 of the ODCM irdicates that releases are made in both the batch and continuous modes.

Section 1.1.1 identifies batch releases as releases from the liquid radwaste effluent line, and the steam generator blowdown effluent line.

Section 1.1.2 identifies continuous releases as releases from the steam generator blowdown effluent line, the turbine building sump effluent line, and the yard sump effluent line. Each release pathway is continuously monitored for radioactivity during the release and the methodology for determining the monitor's setpoints is contained in the ODQ4.

Administrative factors are included in the methodology to determine D1-5

the monitor's setpoints to assure release limits will not be exceeded by j

simultaneous releases into the Unit 1 circulating water outfall pipe. The Licensee's methodology, described in Section 1.1 of the OD04, 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.

W e methodology to determine the setpoints for the radioactive gaseous effluent monitors is contained in Section 2.1.

According to the description in Section 2.1 there are two monitored radioactive gaseous effluent release pathways for Unit 1:

Unit 1 vent stack j

Unit 1 containment purge A simplified diagram showing the gaseous radwaste treatment system for Unit 1 is shown in Figure 4-2 of the OD04. 'Ihe waste ' gas decay tanks are i

released to the waste gas header which subsequently discharges to the atmosphere via the Unit 1 vent stack and noble gases from the waste gas decay tanks are monitored prior to release to the waste gas header.

The methodology to determine the setpoints for the noble gas mnitors for Unit 1 uses the historical annual average dispersion factor of 3

1.35E-05 sec/m. Noble gas effluent monitor setpoints are dependent on NUREG-0472 dose rates which are site limits and not individual limits for each reactor on the site. Since simultaneous noble gas release rates are j

additive, then the methodology to determine the setpoint for each noble gas monitor must consider simultaneous releases, including releases from the six release points at Units 2 and 3.

However, the methodology contained in Section 2.1 for determining the setpoints for the Unit 1 noble gas monitors does not consider simultaneous releases from Units 2 I

and 3.

As a minimum, an adjustment factor should be included to consider l

simultaneous vent releases from the three units. Notification of approval

)

of a Revision 2 to the OD04 was transmitted by the NRC to the Licensee

)

with letter dated August 30, 1985. The OD04 Revision 2 approved with NRC f

t letter dated August 30, 1985 is not the ODCM Revinion ? dated 06-15-85 l

D1-6

L reviewed in this report. At the time of the approval of ODCM Revision 2

~ for Unit 1, Units 2 and 3 'were at the near term operating license (NIOL) stage and consequently the effects of their simultaneous releases were not a consideration. 'Ihe Licensee's method to calculate setpoints for the noble gas effluent monitors is, in general, in agreement with the e

guidelines of NUREG-0133 except for consideration of simultaneous noble gas releases from all release points at the site. Because of this exception, 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 calculation of MPC described in Section 1.1.1.

eff The methodology for determining the dose rate to an individual due to the release of noble gases is contained in section 2.2.

The release rate calculation uses the highest calculated annual average relative 3

concentration factor of 1.3E-05 sec/m for any area at or beyond the k

unrestricted area boundary. Noble gas discharges frun the site are not assured to be within the NUREG-0472 dose rate limits by correctly determining the setpoints for the noble gas monitors since the setpoint calculation does'not consider simultaneous noble gas releases from all release points at the site including those of Units 2 and 3.

Section 2.2.2 of the ODCM contains the methodology to demonstrate that the dose rate to the critical organ in the child age group via the inhalation pathway from I-131, I-133, for all radioactive materials in 1

particulate form with half-lives greater than 8 days and tritium shall be limited to <1500 mrem / year from the site. The release rate calculation uses the highest calculated annual average dispersion factor of 3

1.3E-05 sec/m for estimating the dose to an individual at or beyond the unrestricted area boundary. However, the release rate term in Equation 2-9 of Section 2.2.2 does not include the release rate for these nuclides from all release points on the site including the releases from Units 2 and 3.

'Iherefore, it is uncertain if tin Licensee's method Dl-7

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provides reasonable assurance that the NUREG-0472 dose rate' limit of

$1500 mrent/yr frun the site will not be exceeded due to simultaneous releases of these nuclides from the site.

2 e 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 l

stated that both pathways are included in the definition for Alt IU Section 1.2.

We 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.

Se methodology to determine the air dose in unrestricted areas due to noble gases released is contained in Section 2.3.1.

The dose limits are limits for each reactor on the site and.the methodology appears'to-q

- correctly consider only the releases frun Unit 1.

W e definition for Qi in Section 2.3.1.1 should clearly state that the releases are from Unit 1.

W e air doses are calculated using the maximum annual average i

atmospheric dispersion factor _X/Q for any sector,and distance at or beyond 1

)

the unrestricted area boundary. The methodology identified in i

Section 2.3.1 of the ODCM to calculate air. doses due to the release of noble gases is, in general, in agreement with the guidelines presented in 3

NUREG-0133 arxi should provide reasonable assurance that the air dose limits of 10 CFR 50 will not be exceeded.

1 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 dose limits are limits for each reactor on the site and the methodology appears to correctly consider only the releases from Unit 1.

The definition for Qi in Section 2.3.2.1 should clearly state that the releases are from Unit 1.

S e Licensee identifies the inhalation, the food, and ground D1-8

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i' 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 Dr identified in Section 2.3.2.2 is the " annual" ' dose and not just the dose 4

for the reporting period whether the reporting period be quarterly or annual. %e methodology described in the ODCM.for calculating the dose to an individual is, in general, in agreement with the guidelines in NUREG-0133 and should provide reasonable assurance that the dose limits of 3

10 CFR 50 will not be exceeded.

l We methodology to project doses due to liquid and gaseous effluent is l

contained in Section 3.0.

W e dose projections are based on the doses due j

to releases from the previous twelve months which were determined using methodology that is in agreement with the guidelines of NUREC-0133.

l W erefore, the dose projections are in agreement with the guidelines of l

NUREG-0133.

Simplified diagrams for the liquid, gaseous, and solid waste treatment systems are shown in Figures 4-1, 4-2, and 4-3 of the CDQ4. However, a map showing site boundaries and unrestricted areas and effluent release points is not included in the ODCM.

W e methodology to demonstrate compliance to 40 CFR 190 is contained d

in Section 2.4.

W e methodology includes all doses from the site including direct radiation ard considers uranium fuel cycle sources within 5 miles of the site.

W e Radiological Environmental Monitoring program for Unit 1 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 buildinj complex and additional information have been provided for each and every sample required by the REI'S Environmental Monitoring Technical Specification in the ODCM Tables 5-1, 5-2, and 5-3.

Additionally, Tabhe 2-15 is a synopsis of the land use surrounding the San Onofre site.

D1-9

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In sununary, the Licensee's ODCM as revised uses methods that are generally consistent with the methode,1cgy and guidance in NUREG-0133, However, because the methodology does not consider simultaneous releases l

frcan all gaseous release points at the_ site, it is questionable if the setpoints determined for the noble gas effluent monitors and the dose rates due to P-1= releases provide reasonable assurance that the dose l

rate lhnits of NUREG-0472 for gaseous releases will not be exceeded.

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D1-10

CONCIDSIONS

'Ihe San Onofre Unit 1 ODCM Revision 2 dated 06-15-85 submitted to the NRC by the Licensee with letter dated September 17,1985(5) uses mthods' that are, in general, consistent with the guidelines of NUREG-0133.

However, because the methodology does not consider simultaneous gaseous releases fran all release points at 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 assurance that the dose rate limits will not be exceeded. Exceptions to the ODCM are identified below:

o The methodology containal in Section 2.1 for determining the setpoints for the Unit i noble gas effluent monitors does not consider simultaneous releases from Units 2 and 3.

Therefore, the methodology does not provide reasonable assurance that the NURM-0472 dose rate limits will not be exceeded.

o Section 2.2.1 containing the methodology for determining the dose rate to an individual due to noble gas releases does not consider simultaneous noble gas releases from Units 2 and 3.

'Iherefore, the methodology does not provide reasonable assurance that the NUREG-0472 dose rate limits will not be exceeded.

o Section 2.2.2 containing the methodology for determining the dose rate to the critical organ in the child age group via the inhalation pathway due to the release of I-131, I-133, radioactive materials in particulate form with half lives greater than eight days, and tritium does not consider simultaneous releases from Units 2 and 3.

Therefore, the methodology does not provide reasonable assurance that the NUREG-0472 duo. rate limits will not be exceeded.

D1-11

,$1 p

' additional modifications that should be made to the OD04 are identified below:

o.

Equations 1-11 and 1.12 have a typographical error,in the "$_"

symbol..

l -.

o

'Ihe narrative for Section l'1.2.3 has a typographical error-in the "$" symbol.

l o

It should be clearly stated that the pathways of saltwater fish and saltwater invertebrates are included in the definition of f

Ait.in Section 1.2.

o Identified corrections to Table 1-2 which appear to be generic to both ODCMs for all three units are listed below:

l Nuclide T. Body Bone,

Kidney GI-L1i Na-24' 4.57E Fe-59 6.32E05 Sr-91 3.71E00 9.18E01 Ru-103 1.25E04 Te-132 2.04E02 I-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, ard Sb-125.

o Equations 2-1, 2-2, 2-4, and 2-5 have the following typographical errors:

3 Numerator:

.Ihe units of C1/nCi should be m /cc.

3 Dernninator:: 'Ihe units of mrem.m / mci.yr should be 3

mrem.m /mC1.yr.

1 D1-12 1

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'Ihe units for D in Section 2.3.1.1~should be " mrad" instead-b of " rad".

o

'Ibe definitions for Qi in Sections 2.3.1.1 and 2.3.2.1 should j

clearly state that the releases are from Unit 1.

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It is not clear why D identified in Section 2.3.2.2 is the r

" annual" dose and not just the dose. for the reporting period whether the reporting period be quarterly or annual.

o A map showing site boundaries and unrestricted areas and effluent release points is not included in the ODCM.

o Figure 5-1 identifying the environmental monitoring sample locations referenced in Section 5.0 is not included in the ODCM, 9

D1-13

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4 D1-14

ut;rn<tRCES t

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-Oooled Nuclear Power Reactor Effluents".

2.

" Radiological Effluent Technimi Specifications for Pressurized Water Reactors," Rev. 3, Draft 7", intended for contractor guidance in reviewing REIS proposals for operating reactors, NUREG-0472, September 1982.

I 3.

" Radiological Effluent Technical Specifications for Boiling Water Reactors," Rev. 3, Draft 7", intended for contractor guidance in reviewing REIS proposals for operating reactors, NUREG-0473, September 1982.

4.

Letter from J. A. Zwolinski (NRC) to K. P. Baskin (SCE),

Subject:

OFFunt DOSE CAICUIATION MANUAL, August 30, 1985.

5.

Intter from H. E. MortJan (SCE) to J. B. Martin (NRC),

Subject:

San Onofre Nuclear Generating Station, Units 1, 2, and 3, September 17, 1985.

6.

" Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants, A Guidance Manual for Users of Standard Technical Specifications," NUREG-0133, October 1978.

7.

" General Contents of the Offsite Dose Calculation Manual," Revision 1 Branch Technical Position, Radiological Assessment Branch, NRC, February 8, 1979.

8.

" Calculation of Annual Dases to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Apperdix I," Regulatory Guide 1.109, Rev.1, October 1977.

D1-15

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Title 10, Code of Federal Regulations, Part 20, " Standards for Protection Against Radiation."

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9 APPENDIX E Tables of Licensee's Report Commitments SAN ON0FRE NUCLEAR GENERATING STATION, UNIT 1 (Updated through Amendment 90, effective January 1, 1985) er 1

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,,,,fe.~o.3..,lEvaluationReportfortheRadiological i chnica Effluent Release and Radiological Environmental

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Operating Reports for 1985 - San Onofre Nuclear Generatina Station. Unit 1 l

June 1987

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T. E. Young, E. H. Magleby, W. Serrano

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T. S. Bohn, J. W. Mandler and F. B. Simpson June 1987

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Radiological Physics Unit oaea>~v"a EG&G Idaho, Inc.

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Office of Nuclear Reactor Regulation Final V. S. Nuclear Regulatory Commission

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Washington, D. C.

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o aa'aac'uaA rev'iew 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, Unit 1 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 found to be reasonably complete and consistent with the review guidelines.

The Offsite Dose Calculation Manual (ODCH) Revision 2 dated 06-15-85 for San Onofre Unit I was reviewed.

The ODCH uses methods that are generally in agreement with the guidelines of NUREC-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 assurance that the NUREG-0472 The Licensee submitted minor c, dose rate limits will not be exceeded.

hanges to the generic Process Control Program (PCP) which presently has interim NRC approval.

The reported changes were reviewed and it is recommended the interim NRC approval be extended to include the reported changes.

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