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Semiannual Radioactive Effluent Release Rept,Jul-Dec 1985
	ML20137X746
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Site:	Diablo Canyon
Issue date:	12/31/1985
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DIABLO CANYON POWER PLANT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT i

i JULY 1 - DECEMBER 31,1985 i

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DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE OF CONTENTS INTRODUCTION ...................................................... ~3 I. SUPPLEMENTAL INFORMATION .................................... 4 II. MAJOR CHANGES TO LIQUID, GASEOUS AND SOLID RADWASTE TREATMENT SYSTEMS...................................................... 9 III. CHANGES TO THE PROCESS CONTROL PROGRAM ...................... 9 IV. CHANGES TO THE ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE (ERMP) ............................................ 9 V. CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE (ODCP) .... 10 VI. 1985 LAND USE CENSUS ........................................ 10 VII. GASE0US AND LIQUID EFFLUENTS ................................ 11 Table 1 - Gaseous Effluents - Summation of All Releases ..... 12 Table 2 - Gaseous Effluents - Ground-Level Releases ......... 13 Table 3 - Gaseous Effluents - Lower Limits of Detection ..... 15 Table 4 - Liquid Effluents - Summation of All Releases ...... 17 Table 5 - Liquid Effluents - Nuclides' Released .............. 19 Table 6 - Liquid Effluents - Lower Limits of Detection ...... 21 VIII. SOLID RADWASTE SHIPMENTS .................................... 23 IX. RADIATION DOSE DUE TO GASEOUS AND LIQUID EFFLUENTS .......... 26 Table 7 - Radiation Dose Due to the Release of Radioactive Liquid Effluents ..................... 29 Table 8 - Radiation Dose Due to the Release of Radioactive Gaseous Effluents .................... 30 Table 9 - Percent of Technical Specification Limits for Radioactive Liquid Ef fluents . . . . . . . . . . . . . . . . . 34 Table 10 - Percent of Technical Specification Limits for Radioactive Gaseous Effluents ................ 35 DC0003 1

DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE OF CONTENTS IX. (Continued)

Table 11 - On Site Dose to Members of the Public

( Fi rst and Second Qua rte r) . . . . . . . . . . . . . . . . . . . . . . 38 Table 12 - On Site Dose to Members of the Public (Third and Fourth Quarter) ...................... 39 X. METEOROLOGICAL DATA ........................................ 40 ATTACHMENTS

1. MAJOR CHANGES TO LIQUID, GASE0US AND SOLID RADWASTE TREATMENT SYSTEMS

2. CHANGES TO THE PROCESS CONTROL PROGRAM

~3. CHANGES TO THE ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE (ERMP) 4 CHANGES TO THE OFFSITE DOSE. CALCULATION PROCEDURE (ODCP)

5. 1985 LAND USE CENSUS DC0003 2

i DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 INTRODUCTION This Semiannual Radioactive Effluent Release Report sumrarizes the gaseous and liquid effluent releases made from Diablo Canyon Power Plant's Units 1 and 2 for the third and fourth quarters of 1985. This report also includes the doses due to the release of radioactive liquid and gaseous effluents and a summary of solid radwaste shipments. This report contains the information required by Unit 1 and 2 Technical Specification 6.9.1.6 and is generally presented in the format of Regulatory Guide 1.21, Appendix B.

The Unit I reactor operated at full power throughout the report period except for short periods of forced outages in August, October and December. The Unit 2 reactor achieved initial criticality on August 20 and progressed through the low power and power ascension testing programs during this' report period. Unit 2 achieved 100'. power on December 20, 1985. The first shipments of solid radioactive wastes were sent from Diablo Canyon to the Hanford, Washington burial site during the month of December.

DC0003 3

I. SUPPLEENTAL INFORMATION A. Regulatory Limits

1. Gaseous Effluents

a. Noble Gas Dose Rate Limit The dose rate in unrestricted areas due to radioactive noble gases released in gaseous effluents is limited to less than or equal to 500 millirem per year to the total body and less than or equal to 3000 millirem per year to the skin.

(Technical Specification 3.11.2.1.a.)

b. Particulate and lodine Dose Rate Limit The dose rate in unrestricted areas due to lodine-131.

Iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents is limited to less than or equal to 1500 millirem per year to any organ. (Technical Specification 3.11.2.1.b.)

c. Noble Gas Dose Limit The air dose due to noble gases released in gasecus effluents, from each reactor unit, from the site, is limited to the following.

CALENDAR QUARTER CALENDAR YEAR Gamma radiation 5 millirad 10 millirad Beta radiation 10 millirad 20 millirad (Tech. Spec. 3.11.2.2)

d. Particulate and Iodine Dose Limit The dose to an individual from lodine-131, lodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents released, from each reactor unit, from the site, is limited to less than or equal to 7.5 millirem to any organ in any calendar quarter and less than or equal to 15 millirem to any organ during a calendar year. (Technical Specification 3.11.2.3)

DC0003 4

2. Liquid Effluents

a. Concentration The concentration of radioactive material released from the site is limited to the concentrations specified in 10 CFR Part 20, Appendix B. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration is limited to 2 x 10'* microcuries/ml total activity.

(Technical Specification 3.11.1.1)

b. Dose The dose or dose commitment to an individual from radioactive materials in liquid effluents released, from each reactor unit, from the site, is limited to the following:

CALENDAR QUARTER CALENCAR YEAR Total Body 1.5 millirem 3 millirem Any Organ 5 millirem 10 millirem (Technical Specification 3.11.1.2)

B. Maximum Permissible Concentrations

1. Gaseous Effluents Maximum permissible concentrations are not used in the methodology for determining allowable release . rates for gaseous effluents at Diablo Canyon Power Plant.

2. Liquid Effluents The concentrations listed in 10 CFR 20, Appendix B, Table II, Column 2 for radionuclides other than dissolved or entrained noble gases are used for determining the allowable release rate at the point of discharge from the site for liquid effluents.

For dissolved or entrained noble gases, the allowable release rate concentration at the point of discharge is limited to 2 x 10% microcuries per milliliter total activity for liquid effluents.

-S-DC0003 5

C. Measurements and Approximations of Total Radioactivity

1. Gaseous Effluents

a. Fission and Activation Gases The gaseous radioactivity released from the plant vent is-measured by a pair of off line monitors each using Geiger-Mueller detector readings from these monitors. These monitor readings are correlated to 1sotopic concentration based on isotopic analysis of a grab sample using a germanium detector. A noble gas grab sample is obtained and analyzed at least weekly. The isotopic mixture is assumed to remain constant between grab sample analyses.

Containment purges, gas decay tank releases and air ejector discharge are all routed through the plant vent for release.

The gaseous radioactivity released from the steam generator blowdown tank vent is measured by analyzing grab samples with a germanium detector. The isotopic concentrations are assumed to remain constant between grab samples.

When the plant vent measurements as indicated by the process monitors are below the lower limit of detection, the results of the grab samples are used to quantify releases. In addition, the individual batch release data is used to quantify the radioactivity discharged from the gas decay tanks and containment.

Other potential pathways for releasing gaseous radioactivity are periodically monitored by collecting grab samples and analyzing these samples with a germanium detector system.

b. Iodines Radioiodines released from the plant vent are monitored by continuous sample collection on silver zeolite cartridges.

The cartridges are changed at least weekly and analyzed with a germanium detector. The radioiodine releases are averaged over the period of cartridge sample collection.

Other potential pathways for releasing radioiodines are periodically monitored by collecting samples using charcoal cartridges and analyzing these cartridges with a germanium detector.

DC0003 6

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c. Particulates -

Radioactive materials in particulate form released from the plant vent are monitored by continuous sample collection on particulate filters. The filters are changed at least weekly and analyzed with a germanium detector. The

, particulate radioactivity is averaged over the period of particulate filter sample collection. Each filter is l analyzed for alpha emitters using an internal proportional counter. All of the plant vent particulate filters collected during a quarter are used for the composite analysis for strontium 89 and 90 which is counted on an internal proportional counter af ter chemical separation.

Other potential pathways for releasing radioactive !

particulates are periodically monitored by collecting '

samples using particulate filters and analyzing these filters with a germanium detector,

d. Tri tium Tritium released from the plant vent is monitored by passing a measured volume of plant vent sample through a water column and determining the tritium increase in the water.

An aliquot of the water is counted in a liquid scintillation l

spectrometer. Tritium is determined at a minimum sample frequency of weekly. The tritium concentration is assumed to remain constant between samples.

2. Liquid Effluents

a. Batch Releases ;

Each tank of liquid radwaste is analyzed for principal gamma emitters using a germanium detector prior to release. The pre-release analysis includes dissolved and entrained gases, i

Volume proportional monthly and quarterly composites are prepared from aliquots of each tank released. The monthly composite is analyzed for tritium using a liquid scintillation spectrometer and gross alpha radioactivity using an internal proportional counter and phosphorous-32 using an internal proportional ccunter following chemical separation. The quarterly composite is analyzed for tron-55 t using thin sodium iodide detector and for strontium-89 and 90'using an internal proportional detector following chemical separations.

t 7-DC0003 7

b. Continuous releases For the continuous liquid releases of steam generator blowdown tank and turbine building sump oily water separator, daily grab samples are collected and volume proportioned for weekly, monthly and quarterly composites.

The oily water separator weekly composite is analyzed for gross gamma and principal gamma emitters using a germanium detector. The steam generator blowdown tank weekly composite is analyzed for principal gamma emitters and iodine 131. The steam generator blowdown tank monthly composite is analyzed for tritium using a liquid scintillation spectrometer and for gross alpha using an internal proportional counter and for phosphorous-32 using an internal proportianal counter following chemical separation. The steam generator blowdown tank quarterly composite is analyzed for iron-55 using a thin sodium iodide detector and for strontium-89 and 90 using an internal proportional counter following chemical separations. The results for each of the composites is averaged over the period of the composite. In addition, one grab sample of the steam generator blowdcwn tank is analyzed monthly for dissolved and entrained gases using a germanium detector.

The results of this analysis are assumed to remain constant over the period of one month.

D. Batch Releases

1. Liquid

a. Numbe r o f ba tc h re lea s e s . . . . . . . . . . . . . . . . . . . . . . . 427

b. Total time period for batch releases........... 1419 hours0.0164 days 0.394 hours 0.00235 weeks 5.399295e-4 months

c. Maximum time period for a batch release. . . . .. . . 12.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months

d. Average time period for a batch release.. . . . .. . 3.32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months

e. Minimum time period for a batch release. . . . . . .. 0.50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months

f. Average saltwater flow during batch releases.. 1.31E6 GPM

2. Gaseous

a. Number of ba tch releases . . . . . . . . . . . . . . . . . . . . . . . 122

b. Total time period for ba tch releases. . . . . . . . . . 294.01 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

c. Maximum time period for a batch release........ 24.00 hours0 days 0 hours 0 weeks 0 months

d. Average time period for a batch release. . . . . . . . 2.41 hours4.74537e-4 days 0.0114 hours 6.779101e-5 weeks 1.56005e-5 months

e. Minimum time period for a ba tch release. . . . . . . . 0.05 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months DC0003 8

E. Abnormal Releases On August 18, 1985, an unplanned release from a waste evaporator condensate tank occurred when a Flow Control Valve (FCV-446) malfunctioned. The release was monitored by the Liquid Process Monitor (RE-18). A total of 2.64 E-7 curies of C0-58,1.24 E-7 curies of C0-60, 7.13 E-6 curies of P-32, 3.45 E-6 curies of Xe-133 and 2.21 E-1 curies of H-3 were released during this event.

On October 16, 1985, an unplanned release from a gas decay tank occurred when a drain valve on a boric acid evaporator was inadvertently lef t open. The release occurred inside the auxiliary building and was monitored by the plant vent monitors. A total of 1.62E-2 curies of Xe-133 were released during this event.

II, MAJOR CHANGES TO LIOJiD, GASEOUS AND SOLID RADWASTE TREATFENT SYSTEMS One design change package. -DCP-C-299953, was approved by the Plant Staff Review Committee (PSRC) during this report period for modifications of the solid radwaste storage facilities. This change is a modification of previously approved design change DC0-EC-11030 which was reported in the Cecember 1983 monthly operating report. The 1983 design change modified the existing racwaste storage building to provide five years of radwaste storage. The 1985 design change cancelled the majority of changes to the existing building and added an additional building adjacent to the south end of the existing building. The total capacity of the two buildings remains at five years storage. The design change was approved on August 26, 1965. The minutes of the PSPC meeting and a description of the design change evaluation is included as Attachment 1.

III CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

Two Revisions to Diablo Canyon Power Plant Adrinistrative Procedure C-253, Frecess Control Program, were made during the report period. These revisions were reviewed and found acceptable by the Plant Staff Peview Committee (PSRC) on November 7 and December 20, 1985. Both of these changes were administrative in nature and did not change the methodology of the PCP. The minutes of the PSRC meetings during which these changes were approved, the procedure history forms e;rplaining the changes, and a copy of the changed pages are included as Attachment 2.

IV, CHANGES TO THE ENVIRCMENTAL PADIOLCGICAL MCAITORING PRCCEDURE (EFFP)

One revision to Planning and Research Department Procedure A-7, Environrental Radiological Monitoring Procedure - DCPP (Normal Operatior.s),

was made during this report period. This revision was reviewed and found acceptable by the PSRC on November 7, 1985. The changes made during this revision were administrative in nature and did not change the conduct or methodology of the Radiological Environmental Monitoring Program. The minutes of the PSRC meeting during which this charge was approved and a description of the changes is included as Attachment 3.

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DC0003 9

I V. CHANGES TO THE OFFSITE DOSE CALCULATION PROCEDURE (0DCP)

One revision to Diablo Canyon Power Plant Chemical Analysis procedure A-8, Off-Site Dose Calculations, was made during this report period. This i

revision was reviewed and found acceptable by the PSRC on November 8, 1985.

The majority of the exchanges made in this revision were slight editorial changes to clarify the language of the previous revision or to correct typographical errors. The language was modified in several places to reflect the same language as the combined Unit I and 2 Technical Specifications. The dose factors for particulate radionuclides with half-lives less than 8 days were removed from Tables 5, 6 and 7 for gaseous releases to reflect the change in language of the combined Unit 1 and 2 Technical Specifications. Tables 7C and 7D were removed since the dispersion parameters in-these tables were superceded by the updated dispersion parameters in Tables 7A and 78. The minutes of the PSRC meeting during which this change was approved, a description of the changes, and a copy of the changed pages is included as Attachment 4.

VI, 1985 LAND USE CENSUS The only change from the 1984 land use census is the deletion of the garden at the residence in the east sector. The 1985 land use census results are included as Attachment 5.

t DC0003 10

VII, GASEQUS AND L10JlD EFFLLENTS "II" DC0003 11

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DIABLO CANYON POWER PLAffi SEMIANNbAL RADICACTIVE EFFLUEhT PELEASE PEPORT 1985 TABLE 1 GASEOUS EFFLUENTS - SL WITION OF ALL FELEASES Units Third Fourth Est. Total Quar +pr Quarter Error,'-

A. Fission & activetion gases

1. Total release C1 1.23 E+2 3.87 E+2 5.0 El

2. Average release rate for period uCi/sec 1.55 E+1 4.87 E+1

3. Percent of technical specification limit" % 5.88 E-3 1.02 E-2 B. Iodines i

1. Total indine-131 Ci 1.30 E-5 2.12 E-4 2.3 El

2. Average release rate for period uCi/sec 1.64 E-6 2.67 E-5

3. Percent of technical specificatinn linit2 % 4.17 E-3 6.80 E-2 C. Particulates

1. Particulates with half-lives > 8 days Ci MDA MDA 2.3 El

2. Average release rate for period. uCi/sec PDA MCA

3. Percent of technical specification limit2 % 0.00'E+0 0.00 E+0

4. Gross alpha radioactivity Ci MDA MDA D. Tritium

1. Total release Ci 1.68 E-1 8.63 E+0 1.2 El

2. Average release rate for period uCi/sec 2.11 E-2 1.09 E+0

3. Percent of technical specification limit 2 % 5.07 E-5 2.62 E-3 NOTE:

1 MDA = Less than the "a posteriori" nininun detectable activity (microcuries per unit rass or volume). This note applies to all tables, a Technical Specification 3.11.2.1 Limit DC0003 DIABLO CANYON POWER PLANT SBilANNUAL PAD 10 ACTIVE EFFLUENT PELEASE REFORT 1985 TABLE 2 GASEOUS EFFLUENTS - GPCLFD-LEVEL RELEASES THIRD QUARTER FOUPTP CUAPTEP CONTINUGUS RATCH CONTIFUOUS BATCH Nuclides. Released Unit MODE MODE t10DE MODE

1. Fission gases krypton-85 Ci MDA 5.37 E-3 MDA MDA krypton-85m Ci 3.96 E-2 8.92 E-2 MDA P.51 E-1 krypton-87 Ci MDA MDA MDA l1DA krypton-88 Ci MDA 3.92 E-2 fTA 1.40 E-1 xenon-131n Ci MDA 9.72 E-1 MDA 4.31 E+0 xenon-133 Ci 2.38 E+0 1.15 E+2 3.13 E+0 3.64 E+2 xenon-133m Ci MDA 1.18 E+0 MDA 4.26 E+0 xeron-135 Ci 1.46 E-1 1.31 E+0 1.31 E-2 6.65 E+0 xenon-135m Ci itDA MDA MDA MDA xenon-138 Ci MDA !!DA MDA MDA argon-41 Ci MDA 1.52 E+0 MDA 4.08 E+0 TOTAL FOR PEP!OD C1 2.57 E+0 1.?0 E+2 3.14 E+0 3.84 E+2

2. todires iodine-131 Ci 1.30 E-5 2.1? E 4 iodine-133 Ci 5.13 E-6 5.60 E-5 iodine-135 Ci MDA MDA TOTAL FOR PERICD C1 1.81 E-5 ?.68 E-4 DC0003 DIABLO CANYON POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 2 (CcNTiteuED)

GASEOUS EFFLUENTS - GROUND-LEVEL PELEASES CONT!?!tt005 MODE f!uclidesReleased Unit Third Quar +er Fourth Quartar

3. Particulates cerium-141 Ci MDA MDa cerium-144 Ci MDA MDA cesium-134 Ci MDA MDA cesium-137 Ci MDA MDA cobalt-58 Ci MDA MDA cobalt-60 ci tTA MDA iron-59 Ci MDA MDA manganese-54 Ci MDA t1DA molybdenum-991 Ci MDA MDA strontion-89 Ci MDA MDA strontium-901 C1 MDA MDA zirc-65 Ci MDA MDA TOTAL FOR PERIOD Ci 0.0DE+0 0.00E+0 f;0TES:

1 Includes Daughters DC0003 DIABLO CAN D POWER PLANT SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TEE 3 GASEOUS EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Unit Continuous Mode Batch Mode Containment Gas Decay

1. Fission gases Purge Tank krycton-85 pCi/ml 2.63 E-6 E.63 E-6 3.67 E-3 krypton-85m uCi/ml 6.90 E-9 6.90 E-9 9.58 E-6 krypton-87 uCi/ml 1.88 E-8 1.88 E-8 1.36 E-5 krypton-88 uti/mi 2.26 E-8 2.26 E-8 3.23 E-5 xennn-131m uti/ml 1.87 E-7 1.87 E-7 3.39 E-4 xenon-133 uti/ml 1.97 E-8 1.97 E-8 6.97 E-5 xenon-133m uC1/ml 4.61 E-8 4.61 E-8 9.35 E-5 xenon-135 uti/ml 4.15 E-9 4.15 E-9 6.37 E-5 xenon-135m uCi/ml 4.13 E-8 4.13 E-8 2.67 E-5 xenon-138 uC1/ml 1.09 E-7 1.09 E-7 3.30 E-5 argon-41 uti/ml 3.34 E-8 3.34 E-8 2.84 E-5

2. Tritium hydrogen-3 uCi/ml 3.52 E-10 4.12 E-10

3. Iodines iodine-131 uti/ml 2.83 E-13 iodine-133 uC1/ml 4.77 E-13 iodine-135 uti/ml 6.66 E-12 DC0003 DIABLO CANYON POWER PLAhT SEMIANNUAL RADIDACTIVE EFFLUENT PELEASE REPCRT 1985 TABLE 3 (CONTINUED)

GASECUS EFFLUENTS - LOWER LIMITS OF DETECT 10f1 Nuclide Unit Continuous Mode 4 Particulates cerium-141 uCi/ml 2.82 E-13 ceriun-144 uCi/n1 1.51 E-12 casium-134 uCi/nl 3.45 E-13 cesium-137 pCi/nl 2.72 E-13 cobalt-58 uCi/nl 3.03 E-13 cobal*.-60 4.91 E-13 uCi/n1 iron-59 uC1/ml 7.29 E-13 nanganese-54 uCi/nl 4.37 E-13 nolybdenun-99 1 uti/nl 2.36 E-12 strontium-89 uCi/ml 2.26 E-14 strontion-901 uCi/ml 2.06 E-14 zinc-65 uCi/n1 8.12 E-13 gross alpha uCi/nl 7.23E-15 Notes:

lincludes daught.ers 3

l l

! 0C0003 -. ._ - _ _ - . - _ _ , - _ - - _ . _ _ _ .

DIABLO CANYON NUCLEAR POWEP PLANT SEMIANNUAL PAD 10 ACTIVE EFFLUENT RELEASE FEPORT 1c85 TABLE 4 LIQUID EFFLUENTS - SUff% TION OF ALL RELEASES Third Fourth Est Tetel Unit Quarter Quarter Errnr

A. Fission and activation products

1. Total release (not including tritium, gases, alpha) Ci 1.22 E-1 8.25 E-1 2.1 El

2. Average diluted concentration during period uti/n1 7.49 E-10 3.19 E-9

3. Percent of applicable limit! "'

. 1.29 E-2 2.01 E-?

B. Tritium

1. Total release Ci 1.35 E+2 2.19 E+2 1.3 El

2. Average diluted cnncentration during period uti/n1 8.?8 E-7 8.46 E-7

3. Percent of applicable limitt % 2.77 E-2 2.82 E-2 C. Dissolved and entrained gases

1. Total release Ci 2.39 E-3 3.45 E-3 2.1 El

2. Average diluted concentration during period uCi/nl 1.47 E-11 1.?3 E-11

3. Percent of applicable limit l % 7.36 E-6 6.66 E-6

0. Gross alpha radioactivity

1. Total release Ci MDA MDA 6.0 El 1 Technical Specification 3.11.1.1 Limit DC0003 17

DIABLO CANYON POWER PLANT SEMIANNUAL PADICACTIVE EFFLUENT RELEASE FEPORT 1985 TABLE 4 (CONTINUED)

LIQUID EFFLUENTS - Su% TION OF ALL PELEASES Third Fourth ~ Est Total Urit Quarter Quarter Error, t E. Volume of waste released (prior to dilution) liters- 8.73 E+6 1.45 E+7 5.0 E0 F. Volume of circulating saltwater used during release liters 1.63 E+11 P.59 E+11 6.6 E0 DC0003 18

DIABLO CANYON POER PUJ'T SEMIANNUAL RADI0 ACTIVE EFFLUEhT RELEASE FEFORT 1985 T/6LE 5 LIQUID EFFLUENTS THIDD OUAPTER FOURTH QllAPTEP CONTINUCUS BATfh CONTINUOUS BATCH Nuclides Peleased Unit MODE MOCE MODE fiODE antirony-124 Ci itDA 2.06 E-5 MDA 3.04 E a beryllium-7 Ci t10A l4.20E-4 f1DA 3.05 E-3 cerium-141 Ci MDA l MDA MDA MDA cerium-144 Ci MDA MDA MCA MDA cesium-134 Ci MDA l4.:'7E-4 MDA 9.80 E-4 cesium-136 Ci MDA l8.06E-5 MD4 9.80 E-5 cesium-137 Ci MDA l1,29E-3 l MDA 2.38 E-3 chroniun-51 Ci l MDA 1.10 E-2 MDA 1.79 E-2 cnbalt-57 Ci l MDA 4.32 E-5 l MDA l 6.43 E A cobalt-58 Ci f1DA l4.84Ec2 MDA I6.75 E-1 cobalt-60 Ci MDA 1.76 E-2 MDA 4.88 E-2

~

iron-55 Ci MDA MDA fiDA 1.09 E-2 iron-59 Ci MDA 1.72 E-3 MDA 1.06 E-2

~

lanthanum-140 Ci MDA 8.91 E-5 ftDA 5.22 E-4 manganese-54 Ci MDA 8.71 E-3 MDA , 1.59 E-2 molybder.um-99 1 Ci MDA 2.35 E-3 ftDA 4.82 E-3 phosphorous-32 Ci MDA 5.13 E-3 MDA 3.?5 E

sodium-24 Ci HDA 1.46 E-3 MDA 8.53 E-3

~

NOTES:

IIncludes daughters e

e sw DC0003 l

DIABLO CANYON P0kER PLAhT SEMIANNUAL RADI0 ACTIVE EFFLUEhT PELEASE FEPORT 1985 TAELE 5 (CONTINUED)

LIQUID EFFLUENTS THIRD QUARTER FOURTH OllAPTER C0tF:tiUOUS BATCF C0tlTIt4U0i's BATCH Nuclides Released Unit MODE f!0DE MODE MODE strnntiun-89 Ci MDA 1.08 E-2 MDA 4.69 E 4 strontiun-901 Ci MDA MDA MDA ftDA tin-1131 Ci MDA 5.99 E-5 MDA MDA tungsten-187 Ci MDA 9.60 E-5 MDA 1.50 E-3 zirconium-951 Ci MDA 6.66 E-3 tiDA 1.06 E-2 zinc-65 Ci MDA 6.32 E-5 MDA 2.62 E-5 iodine-131 Ci MDA 4.27 E-3 MDA 9.51 E-3 iodine-133 Ci l MDA 1.24 E-3 ,

MDA 2.22 E-3 iodine-135 Ci MDA 8.26 E-7 MDA 3.81 E-5 TOTAL FOR PERIOD Ci 0.00 E+0 1.22 E-1 0.00 E+0 8.25 E-1 xenon-133 Ci MDA 2.32 E-3 MDA 3.16 E-3 xenon-135 Ci MDA 7.31 E-5 MDA 2.92 E-4 NOTES:

IIncludes daughters DC0003 o .

e DIABLO CANYON POWER PET SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEAS$ REFORT 1985 TABLE 6 LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Unit LLD antinony-124 uC1/ml l 2.06 E-8 beryllium - 7 wCi/mi 1.82 E-6 cerium-141 pCi/nl 3.49 E-8 cerium-144 uCi/n1 1.88 E-7 casium-134 uC1/ml l 2.92 E-0 cesium-136 uCi/mi 5.06 E-8 cesium-137 uCi/n1 I 4.90,E-8 l chronium-51 l uCi/mi 2.50 E-7 l

cobalt-57 uC1/n1 l 2.17 E-8 l cobalt-58 uCi/nl 3.82 E-8 l

cobalt-60 l' uC1/n1 4.36 E-8 iron-55 uC1/n1 3.00 E-7 iron-59 ' uC1/n1 6.45 E-8 lan tha'num-140 uCi/n1 1 5.6E E-8 manganese-54 vCi/n1 3.91 E-8 molybdenun-991 uCi/ml 2.79 E-7 l phosphorous-32 l uC1/n1 3.31 E-7 sodium-24 uCi/ml 4.72 E-8 strontium-89 uCi/ml 4.09 E-8

- strontium-901 pCi/n1 4.00 E-8 fl0TES: 4 IIncludes Daughters r :

DC0003 - 21

DIABLO CANYON POWER PLANT J

SEMIAlHJAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 1985 TABLE 6 (CONTINUED)

LIQUID EFFLUENTS - LOWER LIMITS OF DETECTION Nuclide Unit LLO tin-1131 DCi/mi 7.11.E-7 tungsten-187 pC1/mi 8.96 E-8 zirconium-951 uti/ml 6.51 E-8 zinc-65 uti/ml 7.22 E-8 gross alpha uCi/mi 9.00 E-8 iodine-131 uti/ml 2.55 E-8 iodine-133 9C1/ml 2.12 E-8 iodine-135 uCi/ml 1.63 E-7 xenon-133 uCi/mi 2.08 E-7 xenon-135 uti/mi 2.16 E-8 NOTES:

!!ncludes daughters 5

DC0003 Vill. SOLID RADWASTE SHIFFENTS DC0003 DIABLO CANYON POWER PlfAT SBilANNUAL RADI0 ACTIVE EFFLUENT ELEASE REPORT 1985 SOLID WASTE AND IRRADIATED FUEL SHIPMENT A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

Est. Total

1. Type'of Weste Unit 6-Month Period Error. *.

a. Spent Resins r3 8.60 E+0 Ci 4.02 E+1 10.0

b. Dry Compressible m3 1.95 E+1 Waste, Contaminated Ci 3.66 E+0 11.0 Equip. Etc.

c. Irradiated m3 0.00 E+0 Components, Control Ci 0.00 E+0 t'/A Rods, Etc.

d. Absorbed liquids, m3 2.97 E+0 Sand, Puilding Ci 9.60 E-2 11.0 Pubble, Biological Waste

2. Estimate of Major Nuclide Corposition (by typa of waste) a.

C0-60 t 46 CO-58 % 42 b.

H-3 % 98 c.

NOT APPLICAELE % uf; d.

H-3 % 98

3. Supplemental Information Required by T.S. 6.9.1.6 Solidification Type of Number of 10 CFR 61 Agent Container Containers Waste Class Type A 1 A

_ Cement Absorbant LSA 38 A None LSA 64 A 0C0003 -24.

DIABLO CANYON POWER PLAAT SBilANNUAL RADI0 ACTIVE EFFLUEhT PELEASE REPCRT 1985 SOLID WASTE AND IRRADIATED FUEL SHIPFENT A. Solid Waste Shipped Offsite for Burial or Disposal (flot irradiated fuel)

(Continued)

3. Solid Waste Disposition Number of Shionents Mode of Transporta*.ine Destinatinn 3 Truck Hanford, WA.

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination l'0NE N/A N/A 4

LC0003 IX. RADIATION DOSE DUE TO GASEOUS AND LIQUID EFFLUENTS Oc0003 RADIATION DOSES-Radiation doses for the first and second quarter of 1985'were also reported in an October 24, 1985 supplement to the mid-year semiannual radioactive effluent release report.

A. Radiation doses due to radioactive liquid effluerts The radiation dose contributions due to releases of radioactive liquid affluents to the total body and each individual organ for the maxinur exposed adult have been calculated in accordance with the methodoloay in the Offsite Dose Calculation Procedure. Since the liquid radwasta systen is common to both units, no atternt has been made to segrecate each unit's contribution to the total dose. The dose contributions may be assumed to be due to a single unit. Dose contributions, listed in Tabla 7, show conformance with Technical Specification 3.11.1.2.

B. Radiation doses due to radioactive gasaous effluents The radiation dose contributions due to radioactive gaseous ef fluents at the site boundary for the lard sectors have been calculated in 'accordance with the calculated rethodology in the Offsite Dose Calculation Procadure.

Each unit's dose contributier has been calculated separately. The meteorology concurrent with the time of discharge were used in these calculations. Ir addition to the site boundary doses, the dose to all age groups at the nearest residence within the inw population zone for each of the land sectors and a five nile infant milk dose in each of the land sectors is included. Dose contributions, listed in Table 8 for the third and fourth quarters, show conformance with Tachnical Specifications 3.11.2.2 and 3.11.2.3.

C. Radiation doses due to direct radiation (line-n'-sight plus sky-shina) -

closest site boundary (800 m)

There were no radiation doses due to direct radiation during the first three quarters of 1985. The radiation doses for the fourth ouartar is evaluated to be 4.56 E-4 mrem due to the presence of radioactive waste containers outside of plant buildinos.

D. 40 CFP 190 Considerations The release of radioactivity in ifquid and gaseous effluents during 1985 resulted in doses that are small percentages of the technical specification limits as shown in Tables 9 and 10. This coupled with the fact that there are no other uranium fuel cycle sources within eight kilometers of the Diablo Canyon Nuclear Power Plant shows conformance with 40 CFR 100 DC0003 E. Radiation doses from radioactive liquid and gaseous ef'luents to members of the public due to their activities inside the site boundary.

1. Liquid effluents The radiation dose to members of the public within the site bnundary due to the release of radioactive liquid effluents is negligible.

This is because the discharge piping fnr liquid radwaste is mostly buried in concrete walls, is located in rennte or inaccessible areas or is underground. In addition, the quantity o' radicar.tivity released was very low during 1985.

2. Gaseous effluents The radiation dose to members of the public within the site boundary due to the release of radioactive gasecus effluents are listed in Table 11 ard 12 for the year of 1985.

DC0003 _ _ _ _

DIABLO CANYON NUCLETE, POWER PLAhT SEMI,W?JAL RADI0 ACTIVE EFFLUEhT RELEASE PEPORT 1985 TAFLE 7 RADIATION DOSE DUE TO THE RELEASE OF RADI0 ACTIVE LICUID EFFLUE1ES mil 11ran ORGAfl First Second Third Fourth Quarter Quarter Ouartar Cuarter Anru.=1 To tal Total Body 6.97 E-3 1.46 E-2 2.79 E-3 1.41 E-3 2.58,E-2' Bone 1.21 E-1 1.14 E-1 6.57 E-2 4.33 E-3 3,05 E-1 Liver 1.26 E-2 1.31 E-2 4.49 E-3 2.14 E-3 3.23 E-?

Thyroid 1.99 E-5 1.06 E-3 3.80 E-4 6.60 E-4 2.12 E-3 Kidney 5.82 E-5 1.10 E-4 6.80 E-5 7.76 E-5 3.14 E 4 Lung 1.34 E-3 4.84 E-4 1.01 E-4 5.18 E-4 2.34 E-3 G. 1. LLI 3.45 E-2 1.03 E-1 9.40 E-3 1.26 E-2 1.60 E-1 DC0003 DIABLO CANYON MICLEAR IOWER ftANT SEMINNIAL RADI0 ACTIVE EFFLUENT RELEASE REf0RT 19P5 TAf1E 8A I

RADI ATION DOSE DlE TO TlE RELEASE OF RADI0 ACTIVE GASEOUS EFFLUENTS (LINIT 1)

FIRST GUARTER SEcot'D OUARTER l SECTOR 2 DOSE SECTOR DOSE l

! Site Boundary Noble Gas l Gamna air dose mrad ESE5 1.?3 E-4 ESE 3.00 E-3 l

Beta air dose mrad ESE 4.00 E-5 FSE 5.77 E-3 I,P,T 3 Teen' (Thyraid) nrem int 5.71 E-5 ESE 4.02 E-5 Residence Noble Gas Ganu air dose mrad ESE 2.21 E-5 ESE 9.51 E-4 Eeta air dose mrad ESE 9.01 E-6 ESE 2.43 E-3 1,P,T

~ThIld6 (Thyroid) mrem ESE 2.57 E-6 ESE 1.6? E-4 Five Mile Dairy I,P,T Infant (Thyroid) mren ESE 2.00 E-5 ESE 1.31 E-4 DC0003 .

DIABLO CANWM NXI. EAR IDER PLANT SEMIANWAL RADIDACTIVE EFFLUENT ELEASE EPORT 1985 -

TABLE 8A (CON 11PUED) l RADIATION DOSE DtE TO TlE RELEASE OF RADIDACTIVE GASEOUS EFFLUENTS (UNIT 1)

THIRD QUARTER FOUR m OUARTER Arnut TOTAL-SECTOR 2 DOSE SECTOR DOSE SECTm DOSE i

l Site Boundary i i

l Moble Gas Ganuma air dose mrad NW 1.46 E-1 NNW 6.55 E-2 '

Beta air dose mrad NW 1.74 E-1 NW 3.71 E-1 NNW 1.14 E-1 NW 4.44 E-1 I.P.T3 '

Child" (Thyroid) arem ESE5 6.45 E-5 NNW 6.75 E-4 NW 7.58 E-4

^!

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i Noble Gas -

Garuna air dose mrad E 7.57 E-3 NNW 4.51 E-3 E 7.80 E-3 !

Beta air dose mrad E 2.29 E-2 NNW 9.53 E-3 E 2.33 E-2 l 1.P.T s Tid (Thyroid) mrem ESE 4.62 E-4 NNW l.37 E-3 MNW l.42 E-3 i

Five Mile Dairy i

I.P,T Infant (Thyroid) mrem ESE -4.88 E-4 ESE~ 1.61 E-3 ESE 2.13 E-3 'i DC0003 .- - _ _

DIABLO CANEN 10 CLEAR POER PUWT SEMIAMUAL RADIDACTIVE EFFLLDIT KLEASE KIMT 1985 TABLE 88 l

RADIATION DOSE DUE TO TIE RELEASE OF RADI0 ACTIVE GASE0US EFFLUENTS (ttllT 2)

THIRD QUARTER FOURTil OUARTER ANf0AL TOTAL -

SECTOR 2 Dose SECTOR D0sE SECTOR D0sE ,

site Boundary soble Gas Gassa air dose mrad ESE 9.14 E-5 N 2.46 E-3 N 2.46 E-3 Beta air dose rrad ESE 2.80 E-4 N 1.19 E-3 N 1.20 E-3 I,P,T 3 Child" (Thyroid) mrem N/A 0.00 E+0 N 1.21 E-4 N 1.21 E-4 Residence table Gas Gansna air dose mrad ESE 1.17 E-5 NNW 8.57 E-4 NNW 8.57 E-4.

Beta air dose erad ESE 3.58 f-5 NNW 4.27 E-4 NNW 4.27 F-4 I,P,T Child 6 (Thyroid) arem N/A 0.00 E+0 ESE5 4.13 E-5 ESE 4.13 E-5 l

Five Mile Dairy I,P,T Infant (Thyroid) arem M/A 0.00 E+0 N 8.95 E-5 N 8.95 E-5 DC0003 t

DIASLO CANYON NUCLEAR POWER PLART SEMIA%UAL RADICACTIVE EFFLUENT RELEASE FEPORT 1985

! TABLE 8 (CoraittuED) :

I .

a NOTES:

i

1. This represents the maxinum dose of age groups, orgars, and geographic j locations for the quarter and arnual total. '

2. The ocean sectors SSE, 5, SSW, SW, WSu, W, and W'lW, are ret included.

! 3. Radiciodines, Radioac*ive Material in Particulate Forn and Radirruclides.

Other Tha'n Noble Gases With Hal'-lives Greater Than Eight Days.

I 4 The inhalation, grcund plane and animal-meat pathways are included in this dese calculation.

5. This Incation is a vegetab'e farm located throughnut the ESE sector '

starting at 2 niles.

6. The inhalation, ground plane, animal-meat and vegetable pathways are included for this location. An occupancy factor of 0.5 was used for the '

inhalation and ground plane pathways. The child age group had the highest ,

calculated dose for this lccation.

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DIABLO CANYON f0 CLEAR PChER PLANT SEMIANNUAL RAD 10 ACTIVE EFFLUENT RELEASE REPORT 19f5 ,

TABLE 9 I

PERCENT OF TECHNICAL SPECIFICATICA LIMITS FOR RADIDACTIVE LIQUID EFFLUENTS r PEarENT I ODGAN Firs

Sacced Third Feurth I QuPrter Cuarter Ouarter Currtar ArnualTr*r1i!

i Total Body 4.65 E-1 c.73 E-1 1.06 E-1 9.40 E-2 P.59 E-1 i Bone 2.42 E+0 2.28 E+0 1.31 E+0 8.66 E-2 3.05 E+0 Liver 2.52 E-1 2.62 E-1 8.96 E-2 4.28 E-2 3.?3 E-1 1

Thyroid 3.98 E 4 2.12 E-2 7.60 E-3 1.32 E-2 2.1? E-2 l

Kidney 1.16 E-3 2.20 E-3 1.36 E-3 1.55 E-3 3.14 E-3 Lung 2.60 E-2 9.68 E-3 2.0? E-3 1.04 E-2 2.44 E-?

G. I. LL! 6.90 E-1 ?.06 E C 1.88 E-1 2.!? E-1 1.f0 E+0 i i

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DIABLO C#fE3 ?UCLEAR IGER IUNT SEMIt#UAL RADI0 ACTIVE EFFLlENT ELEASE REFORT 1985 TABLE 10A (CffiTI?AE))

EPCENT OF TE0flICAL SPECIFICATION LIMITSIFOR PED 10 ACTIVE GATOUS EFFtlENTS (lf;IT 1)

THIRD QDRTER FC@ TH OuARTFR Af#UAL TOTAL

% OF % OF % OF SEcTm T.S. LIMIT SECTm T.S. LIMIT SEcTm T.S. LIMIT Site Boundary Noble Gas Gare.a air dose f:W 2.94 E+0 hrM 1.31 E+0 NW 1.74 E+0 Beta air dose f!w 3.72 E+0 nrtW l.14 E+0 flW ?.?? E+0 I,P,T l Child (Thyroid) ESE 8.60 E-4 hriW 8.76 E-3 fS 5.05 E-3 Residence Moble Gas Gama air dose E 1.5? E-1 hnW 9.02 E-? E 7.80 E-?

Beta air dose E 2.29 E-1 NNW 9.53 E-2 E 1.17 E-1 I,P,T Child (Thyroid) ESE 6.16 E-3 fit;V 1.83 E-? fir:W 9.47 E-3 Five Mile Dairy I ,P .T Infant (Thyroid) ESE 6.51 E-3 ESE 2.15 E-2 ESE 1.42 F-?

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DIOLO CANYON f0 CLEAR ITER FIM.T SEMINf0AL RADIDACTIVE EFFLtBT PELEASE REPORT 1985 l

l TAPLE Im PERCEllT OF TEOiNICAL SECIFICATKri LIMITS FOR RADIDACTIVE GASEOUS EFFLUEffiS (tfllI 2)

I l TillRD QUARTTR FOURTii OuARTER ATIfJUAL TOTAL ZW %W %W SECTm T.S. LittIT SEcTm T.S. LIMIT SEcTm T.S. LIMIT Site Boundary -

Noble Gas Gama air dose ESE 1.83 E-3 N 4.97 E-? N 2.46 E-2 Beta a:r dose ESE 2.80 E-3 tl 1.?O E-2 fl 6.00 E-3 I,P,T Child (Thyroid) N/A 0.00 E+0 rs 1.61 E-3 r1 8.07 E-4 l

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Technical Specification 3.11.2.2 and 3.11.?.3 l DC0003 l l

DIABLO CANYON POVER PLANT SEX 1 ANNUAL PAD 10f.CTIVE EFFLUENT RELEASE FEPORT 1985 TABLE 11 RADIATION DOSE DUE TO RELEASE OF PADI0 ACTIVE GASEOUS EFFLUEhTS IST AND 2ND CUARTERS, 1985 ONSITE DOSE TO F9 EERS OF THE PUBLIC SFECIAL INTEFEST GROUPS.

FIRST OUARTER WHCLE EODY SKIN SPECIFIC EXPOSt:RE EXPOSURE 00SE EXPMllPE EXPOSURE DOSE ACTIVITY T!!!E LOCATION MPEft TIf tE LOCAT10fl fPEM (H0l'PS) (SECTORS fPOURS) fSECTORS)

NW flW NNW NNW Rancher 1 N 1.33 E-8 1 N 1.96 E-C NNE ?!NE NE flE PG&E Guided Tour 1 ESE 1.93 E-7 1 ESE 2.85 E-7 Special Tours (To Bio Lab) 1.5 ESE 2.89 E-7 1.5 ESE 4.20 E-7 Police (Rifle Rarge) 18 ESE 1.17 E-6 18 ESE 1.74 E-6 SECCf0 QUARTER WHOLE RODY S Kl f.

SPECIFIC EXPOSUPE EXPOSUPE 00SE EXF05UPE EXPOSURE DOSE ACTIVITY TIME LOCAT!0fl f'P EM T!!!E LOCATION MDEM (HOUPS) (SECTORS] (HOUPS) (SECTORS' fiW NW NNU f'f'W Rancher 1 fi 1.61 E-6 1 i fl ?.?S E-6 NNE f4fiE NE NE PG&E Guided Tour 1 ESE 4.40 E-6 1 ESE 8.01 E-6 Special Tours (To Eio Lab) 1.5 ESE 6.62 E-6 1.5 ESE 1.32 E-6 Police (Rifle Range) 18 ESE 2.68 E-5 18 ESE 5.36 E-5 0C0003 t -

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l DIABLO CANYON POWER PUAT L SBilANNUAL PLD10 ACTIVE EFFLUENT RELEASE REP 0FT 1985 TME12 FADIATION DOSE DUE TO RELEASE OF RADI0 ACTIVE GASECUS EFFLUENTS l 3RD AND 4TH CUARTERS, 1985 l ONSITE DOSE TO EMERS OF THE PUBLIC l SCECIAL INTEREST GROUPS l

THIRD OVARTER

! WHOLE BODY SKIN SPECIFIC EXPOSURE EXPOSURE DOSE EXPOSURE FXPOSURE DOSE ACTIVITY TIME LOCATION f5 EP T!!!E LOCATION t'PEM (P0llPS) ISECTORS: (HOURS) (SECTOPS) i NW NW fNW NfiW Rarcher 1 fl 3.09 E-5 1 f! 6.44 E-5 NiiE NNE NE NE

~

PGAE Guided Tour 1 ESE 1.53 E-5 1 ESE 3.19 E '

Special Tours (To Bio Lab) 1.5 ESE 2.30 E-5 1.5 ESE 4.78 E-5 Folice (Rifle Pange) 18 ESE 9.32 E-5 18 ESE 1.94 E d FOURTH QUARTER WHOLE BODY SKIN SPECIFIC EXP050PE EXP05UPE COSE EXPOSUFE EXPOSUDE DOSE ACTIVITY TIME LOCAT!0fl MPEM TIME LOCAT10f PP Ef t (HOURS) (SECTORS) (H0)RS) (SECTOPS)

NW flW NNW NNW

! Rancher 1 N 1.16 E 4 1 N 8.00 E-5 NNE NNE I

flE t'F PG&E Guided Tour 1 ESE 3.05 E-5 1 ESE 6.49 E-5 Special Tours (To Bio Lab) 1.5 ESE 4.58 E-5 1.5 ESE 9.74 E-5 l Police l (Rifle Parge) 18 ESE 1.69 E-4 18 ESE 3.57 E-4 DC0003 m -- +- --

X. ETEOROLOGICAL DATA l

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ETEOR0 LOGICAL DATA The hour-by-hour listing of wind speed, wind direction, atmospheric stability and precipitation is being submitted on magnetic tape in accordance with Technical Specification 6.9.1,6.

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DISCUSSION OF DESIGN CHANGE REQUEST DC0-EC-29953 NEW CONCRETE RADWASTE STORAGE BUILDING ITEM:

a. A summary of the evaluation that led to the determination that the change could be made in accordance to 10CFR50.59 RESP.ONSE:

The new radwaste storage building is to be located adjacent and to the south of the original waste storage building. The new radwaste storage building has a capacity of approximately four years of projected waste storage. The shielding properties of the new facility are similar to the original building. The new facility has not created the possibility for an accident or malfunction of a type not previously evaluated in the FSAR.

The function of the new building is the same as the original storage l building. The Technical Specifications do not prohibit increased storage.

ITEM:

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information.

RESPONSE

This design change adds a new radwaste storage building to the south of the original storage building to ensure continued plant operations shculd burial sites close or DCPP be excluded access to such sites. The addition of the new building maintains the extended storage capacity and alleviates the modification work required to provide such storage capacity in the original radwaste storage building.

. ITEM:

1 c. A detailed description of the equipment, corponents and processes involved and the interfaces with other plant systems.

RESPONSE

4 The new radwaste storage building will include a truck bay which i

accommodates transport casks, two liner storage vaults with bridge cranes, a liner inspection station, a liner closed Freon decentamination station, a control room, a HVAC room, and a drum / box storage vault. The shielding properties will be similar to the original storage building.

ITEM:

i d. An evaluation of the change which shows the predicted releases of I radioactive materials in liquid and gaseous ef fluents and/or quantity of solid waste that dif fer from those previously predicted in the i j Ifcense application and the amendments thereto, i

1 i

DC0003

RESPONSE

There will be no Ibid releases from the new storage building. All stored waste will be containerized and tightly capped. Surveillance of liners in the storage vaults will be maintained by CCTV cameras. The predicted gaseous releases from storage remain unchanged from the previous design.

The new waste storage building will be continuously ventilated with all ventilation air released through a new HEPA filter bank and sampled.

ITEM:

e. An evaluation of the change which shows the expected maxirrum exposures to indiviouals in unrestricted areas or to the general population that differ from those previously estimated in the license application and amendments thereto.

RESPONSE

There is no change in the expected maximum exposures to individuals in unrestricted areas or the general population previously estimated in the Monthly Operating Report.

ITEM:

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes 6re made.

RESPONSE

There is no change in the predicted releases of radioactive materials in the gaseous effluents. Since no actual release of radioactive materials has been made frort the original radwaste storage building prior to the design change, no comparison can be made.

ITEM:

g. An estimate of the exposure to plant operating personnel as a result of the change.

RESPONSE

There will be no change in the estimated radiation exposure to plant operating personnel from that previously predict?d for the mooified original waste storage butiding. The remote hancling equipment provided in the new building and operating procedures will maintain exposures to ALAFA per Regulatory Guides 8.8 and 8.10.

ITEM:

h. Documentation of the fact that the change was reviewed and found acceptable by the PSRC.

RESPONSE

This design change was approved by the PSRC on August 26. 1985.

DC0003

File.206.2 3 ,

.85-165 I -

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT PLANT STAFF REVIEW COMMITTEE Plant Superintendent's Office Minutes of a Special Meeting August 26, 1985 Regular Members Present:

R. Patterson, Assistant Plant Manager / Plant Superintendent (Acting Chairman)

J. V. Boots, Chemistry and Radiation Protection Manager C. L. Eldridge, Quality Control Manager (Secretary)

Special Members Present:

i l K. C. Doss, Senior Nuclear Power Generation Engineer (W. T. Rapp's Alternate)

R. P. Flohaug, Quality Assurance Engineer (O. A. Taggart's Alternate)

Guests:

M. P. Hanrahan, Senior Instrument and Controls Supervisor J. C. Nolan, Pav.er Production Engineer l M. J. Peterson, Chemistry and Radiation Protection Engineer The Acting Chairran -- the quorum requirement satisfied -- convened the meeting h

at 4:00 p.m. to review the following:

1. Review of Plant Procedure Surveillance Test Procedure l- I-4382 Calibration Precedure (Control) For Red Limit Computer Channels.

Rev. 4 l The PSRC has evaluated the above procedure and determined that it does nct constitute a change to the facility or procedures as described in the FSAR or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not required. Furthermore, this procedure does not present an unreviewed safety question, a change to the plant's Technical Specifications, or an unreviewed environmental question.

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DC0461 1

Plant Staf ? Review Comitte,e Minutes - . .85-165 August 26, 1985 -

Page 2 of 2

2. Review of Design Changes

a. DCO-E-A-29953, " Additional Radwaste Storage Building" DCO-E-C-29953, "Radwaste Building" CC0-E-E-29953, "New Radwaste Storage Building" DCO-E-H-29953, "Radwaste Storage Building" DC0-E-J-29953, "Radwaste Storage and Laundry Facility" DCO-E-M-29953, " Concrete Radwaste Storage Building" DCO-E-T-31103, " Telecommunication Cable" The above design changes have been issued to construct a new radaaste bu11dirig for the storing of solidified radioactive waste and dry active waste.

b. DC2-E-C-32987, " Pipe Rupture Restraints" This rodification loosens the wedge nuts en restrairts 12-2RR and 13-3RR to ensure that an unanalyzed t'.ress point is not encountered during norrral plant operation.

After sore discussion and based upon the written safety evaluation of the design changes listed, the Ccmittee recomends approval by the Plant Manager and work may proceed. The Comittee believes no unreviewed safety questions as defined in 10CFR50.59 are created by these changes.

The meeting adjourned at 4: 25 p.m.

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C. L.'ELDRIDGt Secretary CLE:dc R. Mi r.sSON Assis nt Plant Manager / Plant Superintendent Com16 tee Charter's Standard Olstributien ca ,/,085 DC0461 2

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I6812ENT TECF EvlMe M in:NG Catt lo/9/If Armavs CaTE N/J#//.a" Disinteuft m DATE N/Whf P9tC kvitw Daft I ' ittTire 'u et, s .' / T Accrmo e n eTc O Pum ut Ez flopw. s,urs 0

I AP C.253 Diaako CAwvom eowen M. ant vaat sos ! AND 2 OR BATE 10/9/45 PAsl 3 0F 5 titta PROCESS CONTa0L Pa3 GRAM

d. LASORATORT MIXING OF SAMPLES Qualtfled vendor procedures approved by the PlaC provide l written instructions on sampling, processing and handitng for the determination of process parameters prior 'a the -

actual solletficatice. These procedures contain the description of the laboratory staing methods used for these samples,

e. SOLIDIFICATION PROCESS Qualified vendors used by DCPP for the radioactive weste solidification are requir64 to provide the Process Control Program and wrttten procedures. These procedures and changes thereto aust he approved by the PSAC prior to use.

Further, the vendors are required to have a topical report, as referenced, on the unste forms seich will he seltdified at DCPP. This topical report should deuenstrete compliance with the NRC requirements for weste form. These doc uents should include:

1) Description of the solidtfication process

2) Type of solidification used Process control parameters 3p) 4 Parameter boundary esnditions

5) Proper meste form properties 6J 5pecific instructions to ensure the systems are operated within established process parameters.

f. SAMPLING PROGAAN FOR $0LIO!FICATION Vendors, utilized by DCPP for radioactive weste solidf f kation, are required to include in their appruved procedures, requirements to sample at least every tenth batch to ensure solidification and to provide actions to be taken if a sample falls to verify solidification. These s

procedures and changes tPereto must he approved by the PSRC-prior to use.

g. FREE STAE!NG WATER (F5W)

Yendors utilized by DCPP to process set unstes are required to include in their procedures provisions to verify that the F5W Criteria in the Federal and State regulattens and the Burial Site License Criteria are est for the specific type of weste being processed. These procedures and changes thereto must be approved by the PSRC prior to use.

DC0112 3Y

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Omo cA= von pouvem nu=7 wet nosi 1 AND 2 fC263 BATE 10/9/85 PAGE 6 0F 6 tir a PROCESS CONTAOL PA0GAAM REFERENCES

1. Title 10 Code of Federal Regulations

2. NUREG 0472 and 0473

3. NUREG-0800. 11.4 US Rtc Standard Review Plan Solid Westa Management Systems

4. AP C-25351 Process Control Progres Countering g ATTAC W NTS

1. CRSI Procedure 50-CP-003 (PCP) Selfdification

2. CRSI Procedure ON-0P-022 (PCP) Dastneralf satfon

3. CNSI - DW-11118-01 Deustering Topical Report 4 CR$1 - 2(P) & (NP) 4313-01354-01P-A Rev. 2 No611e Cement Solidification Topical

5. CNSI 50-0P-026 Rev. A Process Contrcl Program for Cement /011 Solidification

6. Ca51 SD-0P-053 Rev. A Process Control Progree for CN5! Acid Sol 1dification g: The above attachments are stored in DCPP Library under CNSI Documents.

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File 206.2 85-211 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT

.( PLANT STAFF REVIEW COMMITTEE Plant Manager's Office Minutes of a Regular Meeting November 7, 1985 Regular Members Present:

R. C. Thornberry, Plant Manager (Chairman)

J. V. Boots, Chemistry and Radiation Protection Manager C. L. Eldridge, Quality Control Manager (Secretary)

S. R. Fridley, Senior Operations Supervisor (J. A. Sexton's Alternate)

J. M. Giscion, Assistant Plant Manager / Technical Services T. J. Martin, Training Supervisor (W. B. Kaefer's Alternate)

D. B. Miklush, Maintenance Manager R. Patterson, Assistant Plant Manager / Plant Superintendent Special Members Present:

W. E. Coley, Resident Startup Engineer K. C. Doss, Senior Nuclear Power Generation Engineer (W. T. Rapp's Alternate)

D. A. Taggart, Acting Director Quality Support Guests:

S. G. Santen, Senior Fower Production Engineer C. G. Cestarollo, OPEG Plant Design Group Supervisor M. P. Hanrahan, Senior Instrument and Controls Maintenance Superviser C. E. Johnson, Fire Marshall C..D. Morowski, Assistant Onsite Project Engineer D. C. Tateosian, OPEG Mechanical Group Leader J. H. White, Fealth Physicist, DER The Chairman -- the Corrittee being a quorun and those sponsoring supervisers having general responsibility for the topics on the agenda present -- callec the meeting to order at 1:00 p.m.

1. Review of Temporary Procedure Changes The Ccmmittee reviewed the Terporary Procedure Changes listed en Attachment I and. recommends that the changes be approved by the Plant Manager. It is the opinion of the Committee that these procedure changts do not constitute a change to the facility or procedures as described'in the FSAR or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not required. Furthermore, these procedure changes do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed environmental

. questions.

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Plan? Staff Review Committee Minutes85-211

November 7,1985 Page.2 of 6

2. - Review of Open Item Reports The Open Item Reports are being withheld until the next regularly scheduled PSRC meeting.

3. Review of Open PSRC NPPRs/ Action Requests The Open PSRC NPPRs/ Action Requests are being withheld until the next regularly scheduled PSRC meeting.

4. Review of Nonconformance Report DC2-85-MM-N114, " Accumulator Tanks 2-1 and 2-3"

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After some discussion, the Committee concurs with the resolutf or.,

corrective action and reportability proposed by the Technical Review Group and concurs that this NCR is now ready for closure. I 1

The Com.ittee believes no unreviewed safety question as defined in 10CFR5C.59 is created by this nonconformance report.

5. Review of IE Information Notices

(

, a. 85 42, " Loose Phosphor in Parasonic 800 Series Badge There:luminescer.:

I Desimeter (TLD) Elenents" and Response Letter Fron D. W. Shelley The above notice cercerns a problem in sore Panasonic 800' series TLD i badges that has caused spurious high readings in one of the badges'

! TLD elements. Sev'eral Panasonic TLD users have identified badges where crystals of the phosphor have detached themselves fror the i backing of the element, resulting in high erratic readings in that-element.

The Committee does not agree with Mr. D. W. Shelley's response letter l and will request a revised response letter to be reviewed by the'PSPC i.

l at a later date.

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Plant Staff Review Committee Minutes85-211 November 7, 1985 Fage 3 of 6 1

5. Review of IE Information Notices (Continued)

b. 85-44, " Emergency Communication Systen Monthly Test" and Response Letter From D. W. Shelley The subject notice was issued to alert licensees of emergency preparedness exercises and specific tests by NRC Headquarters Operations Officers identifying serious communication malfunctions at other plants, which were previously undetected because of inadequate monthly testing. In most of those cases, neither the Emergency Notification System (ENS) nr Health Physics Network (HPN) telephores were found to have been rout.nely tested.

The PSRC agrees with Mr. Shelley's response letter dated Octcber 7,1955, stating that STP I-29E, "NRC Emergency hotificaticn System and Health Physics Netwerk Functional Test" requires that trere specific tests be performed monthly. Adequate documentatien is provided by this STP; therefore, no further acticns are req,irec te address the concerns of this notice.

c. 85-52, " Errors in Dose Assessment Ccmouter Codes and Reportirg Requirements Under 10 CFR Part 21" and Response Letter : rom D. W. Shelley The above notice anrounced that the Sar Onofre Nuclear Gererating Station staff discovered c programming error in the 'suclear Data sup;1ied Energency Assessrent and Pesponse System fE*r3) pecgra .

This computer code error led to substantial postulated radiation expcsures which are reportable under 100FR21.

The Radiological, Environmentel, and Chemical Er.gineering Sectice indicated that our extensive verification and validatior ?lty) procer:

in 1982 to study the EARS dispersion computation, identified and ccrrected calculational errors in the vendor supp'ie programs. Thi

-findings are well-documented in the V&V Report published in 1983. The current version of EARS software does not resemble the vendor supplied code due to the substantial changes made during the V&V improvement effect.

The Committee agrees with the conclusiens brought 'crth in Mr. D. W. Shelley's response ietter as stated above. Due tc the corrections already made and the results of the V&V process verifying code validity, the PSRC feels that no actions are required to address this notice.

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Plan 2 Staff Review Committee-Minutes85-211 November 7,1985 Page 4 of 6

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6. Review of Plant Procedures The procedures listed on Attachment 2 are not a chan)e to the facility or

, procedures as described in the FSAR, or a test or experiment not described

. 'in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not

'. required. Furthermore, these procedures do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed ,

environmental questions.

The following procedures were previously approved by the PSRC:

Startup Test Procedures 41.1 Plant Shutdown From Outside the Main Control Room (Unit 2),

Rev. 1

43.5 Red Group Drop and Plant Trip (Unit 2), Rev. 0 4I

. 7. Rescission of Plant Procedures

. The folicwing procedures are nc longer needed and are rescinded:

l Administrative Procedure e-85051 Qualification of Quality Control Department Personnel, Rev.1.

Mechanical !!aintenance Procedures J M-1 Reactor Head Thermal Insulation Installatien and Removal, Rev. O M-110 Thermal Spraying on Metal Surface, Rev. 0

'i Chemical Analysis Procedure B-13 Multichannel Analyzer, Rev. 0

8. Review of Procedure Two-Year Followup

The Committee reviewed the-following procedure and finds that it is acceptable for continued use:

i Nuclear Plant Administrative Procedure 0-11 Equipment Restricted From Nuclear Safety Applications, Rev.1 l*

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Plant Staff Review Committee Minutes85-211 November 7,1985 Page 5 of 6 I.

9. Other items of Business

a. " Change of Intent" The Committee reviewed a proposed definition of " Change of Intent" as it applies to procedure changes. The' Committee essentially agreed with the definition. Various members were to forward their comments to the Quality Control Manager by 11/14/85.

b. NCR Trend Analysis - OSRG t

The PSRC reviewed a NCR Trend Analysis recort prepared by the Onsite ;

Safety Review Group for the third quarter,1985.

c. PSRC Licensing Docurent Interpretation - Technical Specificatier 4.7.5.lb.1.

The Committee approved the above Licensing Document Interpretetion, 85-10, Revision O. A copy is attached to these minutes.

d. Response to Generic Letter 85-03 (Technical Specificatiens fcr Generic Letter No. 83-28, Item 4.3)

Tne PSRC approved the attached craf t of PGard5's respor.se tc the h C '

en Generic Letter 85-09. This respense is based on the Westinghcuse. t Owrers Group position that was reviewed at the September General Session,

e. Annunciater Respcnse Drocedures Mr. S. R. Fridley inferred the Committee that the folicwir.g Annunciator Response Precedures of Flar,t Mar.ual Volu e IC have been revised:

PK-0101 PK-0519 PK-1113 PK-0107 PK-0907 PN-1115 PK-0203 PK-0908 PK-1301 PK-0301 PK-1001 PK-1316 PK-03C2 PK-1002 PK-1501 PK-0321 PK-1005 PK-15CS PK-0325 PK-1010 PK-1903 I PK-0416 PK-1012 PK-1904 i PK-0509 PK-1025 PK-1914

f. Tracking Commitments to the NRC '

Mr. J. M. Giscion brought to the Committee's attention that Regulatcry l Compliance is tracking commitrents to the NPC. Regulatory Compliarce

(' has an open items list which they intend to issue on a bi-weekly ,

l basis.

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Plant Staff Review Committee Minutes85-211

, November 7.1985 Page 6 of 6

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I 9. Other items of Business (Continued)

+

g. Unit 2 Snubber Problem The PSRC had a discussion with OPEG regarding failed snubbers'on the steam supply line to Unit 2 auxiliary feedwater turbine. The Committee directed that Maintenance inspect the snubbers, Operations perform another cold start of the turbine, and Maintenance would then reinspect the snubbers for damage. If damage was found Engineering would perform an evaluation for operability.

h. Testing for Components Receiving Redundant Actuation Signals From the SSPS Trains Mr. S. G. Banton asked for the Comrittee's guidance as to the extent cf testing required for components receiving redundant actuation signals frcm the SSPS trains. It was agreed by the PSRC that Engineering shoulo test the feedwater pump trips and pick the rest of the tests up at the strainer outage.

The meeting adjourned at 3:15 p.rr.

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f'_,l',e DRIDGE, Secreta ry CLE:cc Attachrents A"PFC'. AL S :

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a. c. acR:asa g

Plant Manager tC\' 2 7 '500 sf A5m

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R. PATTERSON "

Assistant Plant Maneger/ Plant Superintendent Cemittee Charter's Standard Distribution 5

i CC0481 6

1 File 206.2 11/7/85 PSRC Meeting No.85-211 .

ATTACHMENT 1 7

I Temporary Procedure Changes recommended by PSRC'for Plant Manager's approval:

Startuo Test Procedures 4.1 Calibration of Steam and Feedwater Flow Instrumentation at Power j (Unit 2), Rev. 1, Change 5 7.5 Reactor Coolant System Flow Measurerent (Unit 2), Rev. O, Change 7 16.12A3 Preoperational of Makeup Water Pretreatment System (Unit 1),

Rev. 1, Change 4 16.12A3 Preoperational of Makeup Water Pretreatment System (Unit 1),

Rev. O, Change 5 19.2.5A9 Flush and Preoperational Equipment Drain Receiver System (Unit 1), Rev. O, Change 14 l 28.19 Isophase Bus' Temperature Test (Unit 2), Rev. O, Change 2 38.2 Automatic Steam Generator Level Control (Unit 2), Rev. C.

Change 4

! 40.0 Startup Program Master Document (Unit 2), Rev. 1, Change 4 ,

41.8 Dynanic Automatic Steam Dump (Unit 2), Rev. 0, Change 9 42.2 RCCA Pseudo Ejection and RCCA Above Bank Position Measurements (Unit 2), Rev. O Change 1

42.2 RCCA Pseudo Ejection anc RCCA Above Bank Position Measurements i

} (Unit 2), Rev. O, Change 2

2.5 Statepcint Data Collection (Unit 2), Rev. 0, Change 4 0;erating Procedures l J-10:II Instrurent AC Systen - Alignrent Verificaticr. (Unit 1), Rev. 4, 11/6/85 L-4 Normal Operaticn at Power, Fev. 7,11/1/E5 Electrical Maintenance Procedure t

E-54.2 Hign Voltage Testing'of Electrical Equipment, Rev. 5, 10/24/E5 t

s Surveillance Test Procedures t' .

I-1A Routine Shift Checks Required by Licenses (Unit 2), Rev. 1, 10/30/85 j I-1A Routine Shift Checks Fe;uired by Licenses (Unit 2), Ft.. 1, i 11/5/85 I-1E Analog Channel Operational Tests Required Prior to Each Reactor

,j Startup, Rev. O, 11/7/85

. 1-12B7 Calibration of Steam Flow Transmitters, Rev. 5,11/4/85 I-53 Channel Calibration First Stage Pressure Channel 505, Pev. 6, 11/5/85 R-3A Use of Flux Mapping Equipment, Rev. 4, 10/29/85 M-16P Continuity Testing of Equipment Slave Relay Actuating Circuitry,

! Rev. 7, 11/5/85 i f

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File 206.2 ~

11/7/85 PSRC Meeting No.85-211 ATTACHMENT 2

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Procedures reconsnended by PSRC for Plant Manager's approval:

Startup Test Procedures 2.5A36 Condensate, Feedwater, Main Steam, and Auxiliary Feedwater System Flush (Unit 2), Rev. I 16.9Al Seawater Evaporator Distillate Demineralizer Preoperational Test (Unit 1), Rev. 0 17.11 Circulating Water System Demusseling Test (Hot Condition)

(Unit 2), Rev. 1 Nuclear Plant Administrative Procedures C-20 Independent Verification of Calculations Important to Safety.

Rev. 1 C-201 General Requirements for Cherical and Radiochemical Control Programs, Rev. 5 Administrative Procedures C-951 Supplement I to touclear Plar,t Administrative Procedure Sealed Valve, Rev. 7 C-253 Process Contrcl Progran, Rev. 2 Ocerating Procedure G-5:I Spent Resin Transfer Systen CVCS, SFP, Evaporator Demineralizer Resir Transfer to SRST 0-1 (0-2), Rev. 2 Emergency Procedures R-6 Radiological Fire, Rev. 9 M-6 Nonradiological Fire, Rev.11 Electrical Maintenance Procedures E-53.9 Limitorque/Rotork Motor Operator Preventive Maintenance, Rev. 4 i E-54.8 Calibration of Wire Strippers and Crimpers, Rev.1 E-57.3 Peat Trace Cable Testing, Rev. 1 E-61.1 Calibration of the Main Generator Voltage Regulator Power Systen

! Stabilizer, Rev. O t

j Mechanical Maintenance Procedures M-51.8 Limitoroue Valve Operator Disassembly Inspection Maintenance and Reassembly, Rev. 7 j*

M-53.2 Calibration of Micrometer Calipers, Rev. 2 i <

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File 206.2 II l PSRC Meeting No. 85-211-ATTACHMENT 2 (Continued)

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i Surveillance Test Procedures I-79A Functional Test of Waste Gas System Oxygen Analyzers 75 (76),

.Rev. 2

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V-7C Leak Test of RHR Suction Valves 8701 and 8702 (Unit 1), Rev. 4 M-3A Auxiliary Building Ventilation System - D0P and Halide Penetration Test, Rev. 3 ;

M-79 Fire Hose Inspection, Gasket Replacement, and Reracking, Rev. 5 i Chemical Analysis Procedures B-27 . Sentry Gas Chromatograph for Containment Atmosphere Calibration,

, Rev. I r B-33 Calibration of Sentry Gas Chromatograph for Hydrogen in RCS 1 Off-Gas, Rev. 1 B-34 Ion Chromatograph Calibration, Rev. 1 C-71 Total Particulate Contaminant of Fuel Oil, Pev.1 Tem::orary Procedure

! TC-8503 Use cf the Box Corpactor, Res. 0 DER Procedures

! A-7 Environmental Radiological Monitoring Procedure - DCPP (Normal :

Operations), Rev. 1 D4 I-131 Determination of Pilk and Water Samples by Esta-Gamra l

Coincidence Counting of Cuprous Iodide, Rev. 3

D-6a Preparation and Analyses of Marine and Terrestrial Sarples fer Potassium Content, Rev. 1

D-6b Preparation and Analyses of Sediment and Soil Samples for 1

Potassium Content, Rev. 1 i E-4 Beta-Gamma Coincidence Spectrometer Calibraticn, Res. 2 E-7 Intercomparison Study, Rev. 2 Nondestructive Examination Manual

N-UT-1 Ultrasonic Examination Procedure for Pipe Welds, Rev. I I

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ACCEFfDh kJECTD D

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I DIABLO CANYON POWER PLANT UNIT NO($> 1 At'D 2 R ON DATE 11/21/E5 PAGE 3 0F 5 TITLE PROCESS CONTROL PROGRAM

d. LABORATORY MIXING 0F SAMPLES Qualified vendor procedures approved by the PSRC provide written instructions on sampling, processing and handling for the detemination of process parameters prior to the actual solidification. These procedures contain the description of the laboratory mixing methods used for these samples.

e. SOLIDIFICATION PROCESS Qualified vendors used by DCPP for the radioactive waste solidification are required to provide the Process Control Program and written procedures. These procedures and changes thereto must be approved by the PSRC prior to use.

Further, the vendors are required to have a topical report, as referenced, on the waste foms which will be solidified at DCPP. This topical report should demonstrate compliance with the NRC requirements for waste fom. These documents should include:

1) Description of the solidification process

2) Type of solidification used

3) Process control parameters

4) Parameter boundary conditions

5) Proper waste fom properties

6) Specific instructions to ensure the systems are operated within established process parameters,

f. SAMPLING PROGRAM FOR SOLIDIFICATION Vendors, utilized by DCPP for radioactive waste solidification, are required to include in their approved procedures, requirements to sample at least every tenth batch to ensure solidification and to provide actions to be taken if a sample fails to verify solidification.

Verification of such sampling is to be accomplished by 1 completing Form 69-10350, " Processing Control Program (PCP) ,

Verification". These foms will be maintained in the l Chemistry and Radiation Protection Department and the Records Management System (RMS). These procedures and changes thereto must be approved by the PSRC prior to use.

DC0112 3V

0iAsLO cANvON POWER PLANT UNIT NO(S) 1 AND 2 ON' DATE 11/21/85 PAGE 5 0F 5 TITLE PROCESS CONTROL PROGRAM

a. Implementing procedures would be developed comparable to those used for normal plant solid waste activities based on the guidance of this PCP and incorporating the applicable provisions for process control and testing,

b. The implerenting peocedure would receive PSRC approval prior to use.

c. Use of this provision and supporting information would be included in the next Semi-annual Effluent Report to the NRC.

REFERENCES

1. Title 10 Code of Federal Regulations

2. NUREG 0472 and 0473

3. NUREG-0800, 11.4 US NRC Standard Review Plan Solid Waste Management Systems

4. AP C-25351 Process Control Progran Dewatering ATTACHMENTS

1. CNSI Procedure SD-0P-003 (PCP) Solidification

2. CNSI Procedure CM-CP-022 (PCP) Demineralization

3. CNSI - DW-11118-01 Dewatering Topical Repcrt 4

CNSI - 2(P) & (NP) 4313-01354-01P-A Rev. 2 Mobile Cement Solidification Topical

5. CNSI SD-0P-026 Rev. A Process Control Program for Cement /011 Solidification

6. CNSI SD-0P-053 Rev. A Process Control Program for CNSI Acid Solidificatien POTE: The above attachments are stored in DCPP Library under CNSI Documents.

7 Form 69-10350, " Process Control Progran (PCP) Verification."

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DC0112 SV

Form 69-10350 11/85 DEPARTMENT OF NUCLEAR PLANT OP'ERATIONS DIABLO CANYON POWER PLANT PROCESS CONTROL PROGRAM (PCP) VERIFICATION

DATE WASTE BATCH PCP NOTES OPERATOR iERIFIE

l Number Type Passed l Failed l l

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File 206.2 85-229 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT PLANT STAFF REVIEW COMMITTEE C.

Plant Manager's Office Minutes of a Regular Meeting December 19, 1985 Regular Members Present:

R. Patterson, Assistant Plant Manager / Plant Superintendent (Acting Chairman)

C. L. Eldridge, Quality Control Manager (Secretary)

J. M. Giscion, Assistant Plar.t Manager / Technical Services W. B. Kaefer, Assistant Plant Manager / Support Services D. B. Miklush, Maintenance Manager R. P. Powers, Senior. Chemistry and Radiation Protection Engineer (J. V. Boots' Alternate)

J. A. Sexton, Operations Manager Special Members Present:

W. E. Coley, Resident Startup Engineer L. A. Hagen, Nuclear Power Generation Engineer (W. T. Rapp's Alternate)

H. J. Hansen, Quality Assurance Engineer (D. A. Taggart's Alternate)

Guests:

( W. G. Crockett, Instrument and Controls Maintenance Manager S. R. Fridley, Senior Operations Supervisor T. L. Gr ebel, Regulatory Compliance Supervisor B. D. Guilbeault, Construction Coordinator Supervisor J. R. Hinds, Power Production Engineer J. C. Nolan, Power Production Engineer C. G. Rao, Assistant Lead Startup Engineer N. J. Sullivan, General Construction Mechanical Systems Engineer B. R. Tinkle, Staff Field Engineer L. F. Womack, Engineering Manager The Acting Chairman -- the Consnittee being a quorum and those sponsoring supervisors having general responsibility for the topics on the agenda present -- called the meeting to order at 1:00 p.m.

1. Review of Temporary Procedure Changes The Committee reviewed the Temporary Procedure Changes listed on Attachment 1 and recommends that the changes be approved by the Plant

Manager. It is the opinion of the Consnittee that these procedure changes

' do not constitute a change to the facility or procedures as described in

' the FSAR or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not required. Furthermo re, these procedure changes do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed environmental questions.

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Plant Staff Review Connittee Minutes85-229 December 19,1985 Page 2 of 7

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1. Review of Temporary Procedure Changes (Continued)

The following Temporary Procedure Change was rejected by the Committee:

Radiation Control Procedure G-3 Personnel Internel Expcsure Control, Rev. 4, 12/18/85

2. Review of Open NCRs

'The Open NCRs listing is being withheld until the next regularly scheduled PSRC meeting.

-3. Review of Nonconformance Reports DCO-85-PG-N095, " Review of Action Requests ( ARs)"

DC2-85-TI-N100, " Loss of Source Range Indication" DC2-85-TI-N103 " Accumulator Pressure Transmitters Out of Tolerance" DC2-85-TI-N104 " Accumulator Level Transmitters Out of Tolerance" DC0-85-TC-N107, " NPDES Discharge - Zinc" DC2-85-OP-N129, " Unit 2 - Turbine Trip / Reactor Trip" DC2-85-OP-N132. " Unit 2 - Reactor Trip - Load Rejection Test at 50t" DC2-85-0P-N137, " Unit 2 - Reactor Trip 'nith Safety Injection" I~

General Construction NCRs:

DCO-84-SC-N015. " Material Supplies by Cardinal" DCO-85-RE-N001, " Broken Lugs on Conax RTD Wires" 1 ,

DC2-85-RM-N001 " Linear Indication in Wide Flange"

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DCO-85-SC-N001, "NRC Information Notice No. 84-52" DC2-85-RM-N002, " Purchase of Materials From NPS" DC2-85-RS-N002, " Change *2 for T. P. 7.5" DC1-85-SC-N002, " Bolts Under PGandE PO 4R-66170" DC2-85-RM-N003, "BSSG Ouality Organization" l DC2-85-SC-N003, "10CFRSO Appendix B and PO 57706" DC2-85-RM-N004 " Steam Generator Upper Lateral Shims" DCO-85-SC-N004, " Cardinal ASTM A490 Fasteners" After some discussion, the Committee concurs with the resolution, corrective action and reportability preposed by the Technical

, Review Group and concurs that these NCRs are now ready for closure,

j i The Connittee believes no unreviewed safety questions as defined in 10CFR50.59 are created by these nonconformance reports.

The following nonconformance report was withheld from review:

j DC2-85-RS-N001, " Reactor Control and Protection" l (

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Plant Statt keview Committee Minutes85-229 December 19, 1985

. Page 3 of 7

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4. Review of Reportable Events Licensee Event Reports 1

85-010-00, "Prccedural Inadequacy and Inattention Caused a High Steam

Generator Level Turbine Trip and Subsequent Reactor Trip" l 85-014-00, " Wiring Error Leads to Inoperability of Feedwater Isolation Valve FCV-439" 2-85-015-00, " Personnel Error Resulting in a High Steam Generator Level Turbine Trip and Subsequent Reactor Trip" 85-033-00, " Failed Comparator Module.Results in Reactor Coolant Purp Breaker Open Reactor Trip" The PSRC has reviewed the above and concurs with the actions taken.

5. Review of Information Notice 84-93, " Potential for Loss of Water From the Refueling Cavity" and Response Letter From D. W. Shelley This notice is provided to alert licensees and applicants to features in some PWRs and BWRs that may have a significant potential to cause loss of water in the refueling cavity.

The Committee does not agree with Mr. D. 'W. Shelley's response letter and is awaiting a revised response letter to be reviewed by the PSRC at a later

date.

.: 6. Significant Maintenance and Operating Activities (November) i I

a. Two Unit 1 Steam Generator secondary side manway cover leaks had

. previously been temporarily repaired with leak sealant. The manway covers were removed and cleaned, steam cuts weld repaired and machined, and the covers replaced.

b. Several Unit 1 condenser tubes were severed and others dented by a i broken section of thermal sleeve from an extraction line. OCPP Maintenance, in conjunction with General Construction, removed a tube for analysis, plugged the severed tubes, sealed with epoxy all tube plugs, re-staked loose tubes and modified steam dump to condenser di f fusers, i c. Unit 2 was paralleled to the grid on November 15 and reached the 75%

1 power plateau for the first time that day.

d. On November 28, Unit 2 experienced a reactor trip. Attached to these minutes is a detailed description of this reactor trip.

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elant statt Aeview Lommittee Minutes65-249 D2cember 19, 1985

.. Page 4 of 7

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.! 7. Review of Plant Procedures

', The procedures listed on Attachment 2 are not a change to the facility er procedures as described in the FSAR, or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not

- required. Furthermore, these procedures do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed environmental. questions.

The following procedure is being withheld from review:

Project Procedure i

PI-58 Security Systems Document Control, Rev. O The following procedure was previously reviewed and appr,0ved by the PSRC:

Startup Test Procedure 4.6 Steam Generator Moisture. Carryover Test (Unit 2), Rev. 0 l 8. Rescission of Plant Procedure Surveillance Test Procedure V-3L8 Exercising Valve 8916, Nitrogen Accumulator Fill Check, Rev. 2

9. Review of Design Changes

a. OCO-E-C-33459, " Firewater System" The above design change relocates post indicator vahe assemblies, 2-FP-24 and 2-FP-25, to a better Iccation to avoid interference with the flow of traffic,

b. DC1-5-M-23459R1, " Fuel Handling Building" This change provides-sample tubing and a centrally located sample sink 3

to sample the contents of the primary water storage tank, condensate storage tank, refueling water storage tank, transfer tank, and the fire water. storage tank. The reason for this change is to reduce the

. potential of contaminated water spillage.

l c. DCl-E-M-33479, " Auxiliary Feedwater System" l

, This modification represents a correction of tag numbering on the i auxiliary feedwater pumps maintenance valves and is a drawing change only.

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Plant Staff Review Committee Minutes 85-EC9

. December 190 1985 Page 5 of 7 ,

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9. Review of Design Changes (Continued)

d. DC2-E-P-30929, " Pipe Support No. 921-64" l

The above DCN allows for pipe support 921-64 to be upgraded Free Class E to Class F per analysis24-511.

e. OC2-E-C-32308R1,. "Firewa ter and Sewage Systems" This design change represents an extension of firewater and seinge lines to the new administration building.

f. DC2-E-E-34480, " Control Room HkAC System" 4 The subject design change provides Unit 2 electrical work to support the removal of temporary control r,oom ventilation system flow switches anticipated by the relocation of the permanent flow switches as described in DC1-E-H-23499.

4

g. DC2-E-J-34543, " Accumulator Tanks Narrow Range Level" This modification revises the classification of the accumulator tanks

. narrow range level transmitters from instrument class II to instrument l class IC to extend the pressure boundary to the transmitters.

o After some discussion and based upon the written safety evaluation of the design changes listed, the Committee recommends approval by the Plant Manager and work may proceed. The Committee believes no unreviewed safety questions are defined in 10CFR50.59 are created by these changes, e 10. Other Items of Business

a. Plan for General Construction Procedure Usage and Peview The Committee is in agreement with the information on the attached memo from the Field Construction Manager dated November 15, 1985 i

b. Design Changes 1'

The PSRC was informed of the attached lists of design changes approved for construction or completed.

c. Curves and Miscellaneous Data Section - Plant Manual Volume 9 l Mr. L. F. Womack has approved Revisions 112, 113, and 114 to the t

Curves and Miscellaneous Data Section of Plant Manual Volume 9. These i

revisions include changes to the Table of Contents and other specific pages noted on the transmittals dated 11/21/85, 11/26/85, and 12/10/85.

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Plant Staff Review Committee Minutes85-229 Dec@mber 19, 1985 Page 6 of 7 '

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10. Other Items of Business (Continued)

d. Construction Work Package The PSRC approved Construction Work Package G-93 *M-276 as a or.e-time application to modify snubber hanger 22-555SL.

e. License Amendment Requests The Committee discussed and approved the following License Amendment Requests:

1. 85-12, Revision 1 " Diesel Generator Technical Specification Changes" LAR 85-12 requested changes to the DCPP Technical Specifications to reduce excessive testing of the diesel generators and to provide preventive maintenance tines for the diesel generators corsistent with manufacturer's recommendations and previous maintenance and repair experience. Revision 1 eliminates the preventive maintenance outage times for the diesel generators.

2. 85-15 " Containment Fan Cooler and Containment Pressure Technical Specification Changes" This LAR proposes to change the Units 1 and 2 Technical Specification 3/4.6.2.3 " Containment Cooling System," to assure two containment fan cooler units are available assuming a single failure. This LAR also proposes.to change Technical Specification 3/4.6.1.4 " Internal Pressure," and its bases to specify a maximum positive containment internal pressure of +1.2 psig and a maximum pressure of 46.6 psig in the event of a Loss of Coolant Accident (LOCA). In addition, this LAR proposes to change Bases 3/4.6.1.6 to specify the maximum containment pressure in the event of a

, LOCA to be 46.6 psig.

(Note - The PSRC approved LAR 85-15 contingent upon the necessary information from Engineering Department which documents that the analysis is good for 80 seconds.)

3. 85-15 Technical Specification 3.8.1.1, One-Time Exemption I This LAR proposes a one-time exemption from tne 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months shutdown requirement for 10 days on the swing diesel generator. This exemption will allow preventive maintenance, inspection, and acceptance testing on the swing diesel generator during the Unit I refueling outage without requiring Unit 2 to be shutdown and without requiring the

other operable diesel generators to be tested every 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

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Plant Staff Review Committee Minutes85-229 i December 19, 1985 I

Page 7 of 7 i-li-('

f- 10. Other Items of Business (Continued)

f. Unit 2 - 100% Power i The PSRC approved the readiness of Diablo Canyon Power Plant Unit 2 to j ascend to 100% power.

-' The meeting adjourned at 3:45 p.m.

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Secretary t-

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Attachments

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R; Vm i ER50T' Assistant Plant Manager / Plant Superintendent Comittee Charter's Standard Distribution I

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File 2C6.2 12/19/65 PSRC Meeting No.85-229 4

ATTACHMENT 1 1

.( Temporary Procedure Changes recommended by PSRC for Plant Manager's approval: ,

Startup Test Procedures L 2.11A4 Main Condenser Tube Sheet Leak Detection System (Unit 2), '

Rev. O, Change 5 .

i 3.7A5 Turbine Driven Auxiliary Feedwater Pump Preoperational and

Performance Demonstration (Unit 2), Rev.1 Change 1

- 6.7 Boilout and Preoperational . Test of New Auxiliary Boiler and j Deaerator (Unit 1), Rev. 2 Change 6 6.7 Boilout and Preoperational Test of New Auxiliary Boiler and Deaerator (Unit 1), Rev. 2. Change 7

7.5 RCS Flow Measurement (Unit 2), Rev. O. Change 9

! 7.7Al Vibration and Loose Parts Monitor System (Unit 2), Rev. O, l Change 6 7.7Al Vibration and Loose Parts Monitor System (Unit 2), Rev. O, 1 Change 7 7.7Al Vibration and Loose Parts Mcnitor System (Unit 2), Rev. O, !

Change 8 20.1A3 Flush Lube Oil Distribution and Purification (Unit 2), Rev. O, ,

! Change 1

! 23.3Al Auxiliary and Area FuelVentilation Handling (Unit Suilding) ventilation Preoperational I Test GE/GW 2 , Rev. O Change 2 .

! 25.3A24 Compressed Air System Cleaning Procedure (Unit 2), Fev. O, [

l Change 1 !

42.1 Power Coefficient Measurement (Unit 2), Rev. O. Chr.nge 4 43.3Al Large Load Reduction Tests (Unit 2), Rev. O Change 1 43.3Al Large Load Reduction Tests (Unit 2), Rev. O Change 2

!i Administrative Procedures

( Notification of Significant Event, Rev. 4, 12/6/85 (This C-1152 l

Temporary Procedure is no longer needed and is rescinded.)

C-1152 Notification of Significant Event, Rev. 4, 12/9/85 ;

i Operatino Procedures l K-10G3 ECCS System Requirements Mode 4, Rev. 3, 12/6/85 .

h L-4 Normal Operation at Power, Rev. 8, 12/18/85 1

! Mechanical Maintenance Procedure t

M-17.6 Traveling Water Screen Removal, Rev. 1, 12/5/85 a l d Surveillance Test Procedures '

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j I-5A Analog Channel Operational Test OTDT, OPDT, T(avg), and Delta-T Channels, Rev. 7, 12/17/85 Channel Calibration: OTDT, OPDT, T(avg), and Delta-T, Rev 5, h I-582 it 12/17/85 '

I-1287 ' Calibration of Steam Flow Transmitters, Pev. 5, 12/14/35 i Determination and Update of Target Axial Flux Difference, i'j ('

d R-23 Rev. 2, 12/5/85 M

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l File %U0.2 . 12/19/E5 1 PSRC Meeting No.85-229 .

ATTACHMENT 1 (Continued)

a. -(- Radiation Control Procedure 1 %:.

A G-3 Personnel Internal Exposure Control Rev. 4, 12/19/85 I Chemical Analysis Procedure j

E-9 Water Storage Tank Sampling, Rev. O,12/6/85

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File 206.2 12/19/85 PSRC Meeting No.85-229 ATTACHMENT 2

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Procedures recommended by PSRC for Plant Manager's approval:

Interim Revision DCP-100 Drilling of Concrete. Rev.1 Project Precedures DCP-111 Removal and Reinstallation of Thermal Insulation, Rev.1

> DCP-112 Stain'ess Steel Tool Control. Rev. 1 DCP-206 Containrent Field Coatings, Rev. 1 DCP-207 Pyrocrete 201 Installation, Rev. 1 DCP-404 Purging, Filling and Testing of Barton Bellcws Sensor Type Capillary Systems with Water, Rev.1 DCP-405 Purging, Filling and Testing of Barton Bellows Sensor Type Capillary Systems with Oil, Rev. 1 DCP-406 Purging, Filling and Testing of Ashcroft Diaphragm Sensors, Rev. 1 DCP-501 Installation of Permanent Mechanical Equipment, Rev.1 Startuo Test Procedures 2.11A5 Main Condenser Tube Sheet Leak Detection System (Unit 1),

Rev. 1 8.3.3A3 Boric Acid Addition and Control (Unit 2), Rev. O

43.2 Net Load Trip From 100% Power (Unit 2), Rev. 2 -

43.4 Plant Trip From 100% Power (Unit 2), Rev. 2 Electrical Performance Tests

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18 misc. *1 Smoke Damper 22 Actuator (Unit 1), Rev.1 23.60I Control Room Ventilation Charcoal Pre-Heater IEH-27A, IEH-278 (Unit 1), Rev. 0 23.60I Control Room Ventilation Charcoal Pre-Peater 2EH-27A, 2EH-27B (Unit 2), Rev. O Nuclear Plant Administrative Procedures

! A-4 Nuclear Plant Security, Pev. 5 C-10 Housekeeping - General, Rev. 7 Control and Accountability of Special Nuclear Paterial, Dev. 2 0-7 Administrative Procedures I C-1052 Housekeeping - General, Rev. O

! C-253 Process Control Program, Rev. 3 a C-453 Procedural Requirements for Performance of Instrumentation and Controls Work, Rev.1 I

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DC0481 10

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File 20o.2 12/19/85

. PSRC Meeting No.85-229 ATTACHMENT 2 (Continued)

( Operating Procedures AP-20 Condenser Tube Leak, Rev. 0 0-1:!I Auxiliary Startup (Unit 1), Rev. 6Feedwater System - Alignment Verification for Plan 0-1:II Auxiliary Startup (Unit 2), Rev.1Feedwater System - Alignment Verificaticn for Plan 0-1:III Auxiliary Fecdwater System - Shutdown and Clearing (Unit 1),~

Rev. 9 D-1:III Auxiliary Feedwater System - Shutdown and Clearing (Unit 2),

Rev. 2 E-3:I Chlorination System - Place in Service, Rev. 5 Emergency Procedures M-4 Earthquake, Rev. 10 EF-4 Activation of tne Mobile Environmental Mcnitoring Laboratory, Rev. 7 Electrical Maintenance Procedures E-50.36 Maintenance of General Electric Type IFC66 Relay, Rev. 0 E-57.2A Wire and Cable Installation, Rev. 0 Instrurent and Controls Maintenance Procedure 2.1-1 Coaxial and Triaxial Cable Termination Procedure, Rev.1 Surveillance Test Procedures 1-1602 Actuation Logic Test of Protection System Logic. Including Master Relays and Reactor Trip Breakers (Modes 5 or 6), Rev. 6 I-6EC Pressurizer Power Operated Relief Yalve PCV-455C Actuation Timing, Rev. 1 I-69C Pressurizer Power Operated Pelief Valve PCV-456 Actuation Timing, Rev. 1 I-1228 Calibration of Plant Vent Air Particulate Monitors RM-28A and

RM-288, Rev. 1 l I-12281 Plant Vent Air Particulate Monitors RM-28A and RM-288 Removal

. From Service, Rev. 2 1-122B4 Reinstatement to Service: Plant Vent Air Particulate Monitors

. RM-28A and RM-288, Rev. 2 P-24 Testing of the Portable Long Term Cooling Pumps, Rev.1 R-1C Digital Rod Position Indicator Fanctional Test, Rev. 1 I

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$'f,'", D ,n, Engineering Research To D w+on or Department FILE NO. 420 (6100/64.x 6200/10)

RE: LETTER OF SUBJECT DCPP ERMP December 11, 1985 (fDAVID CHIN:

This letter is regarding changes made to the DCPP Environmental Radiological Monitoring Procedure (ERMP). Technical Specification 6.14.2 requires that licensee-initiated changes to the ERMP be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the changes were made effective. The changes will be made effective December 16, 1985.

'The'following are the rationale for the changes'(the numbers are keyed to the revision bars on the procedure):

1. Removed reference to Unit 2. This revision is a result of the combined Technical Specifications, hence the ERMP now applies to both Units.

2. Removed reference to Unit 2.

3. Changed "will" to "shall".

4. Added paragraph from Section 6.9.1.5 of' Technical Specifications.

5. Changed title to match title of Table 4.12-1 of Technical Specifications.

6. Added footnotes from Table 4.12-1 of Technical Specificaions.

7. Added reference to Technical Specification 6.9.1.5.

Pursuant to Technical Specification 6.14.2.a.2 I have determined that these changes will not reduce the accuracy or reliability of dose calculations or

- setpoint determinations. This conclusion results from the fact that the changes made to the ERMP were largely editorial and do not change the conduct of the Radiological Environmental Monitoring Program.

r .

's David Chin 2 December 11, 1985 Pursuant to Technical Specification 6.14.2.a.3 requiring documentation of the fact that the changes have been reviewed and found.icceptable by the PSRC I have at,tached a copy of the signed Nuclear-Related Procedural Transmittal.

/

PAUL A. SZALINSKI TAS(551-332):cml 671A/CML4, Attachments s

cc: JRAdams TLGrebel NLKnox (Nuclear Indexer)

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PACh A GAS /ElECTR/C CCWPANY DEPARMENT of ENGINEERING RESEARCH NUCLEAR-RELATED PROCEDURE TRANSMITTAL

1. To: cd* 1 Department:

Loc ion: bbk

2. Submitted by: </M I7 M Date- /O' /NO5 DER Represent 1tive

3. Please review and coment and/or approve, as appropriate, the follcuing DER Nuclear-related Procedure for use at or f r Department or facility. Quality Control Manual Volume -

M Procedure Num6er N~} Revision . . !

Title or Description buWm/AAf /d M gda/

47LO-4YOh ktD 0Ak i r{DM. 'DrPP V

i f 4. We ask h perform your review and return this transmittal by

5. Record of Review and Approval or Rejection (Please check one or more i box . as appropriate).

The Procedure is approved as written.

I C The Procedure is approved as modified by our ccreents. (Please complete block 6 or attach comments.)

~

U The' Procedure ved with is apprftness the i )lusion of our Quality points.

Control hold and/or w 1 ease indicate where Q.C '

hold and/or witness points are to be inserted in block 7 or

.attachascheduleofQ.C.holdand/orwitnesspoints.)

EU The Procedure is not acceptable and is rejected. (Please document anappropriateexplanationinblock6oronanattachment.)

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6. Carments k$ M b 4 ot2A M d / I //-96 45-) / I

7. Q.C. Hold and/or witness points l

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8. By . f? c 0 b blkS$d NL Departmental r Site Quality 3enior ntf1'or site Repre ive or Authorized Control Representitive Deleg

//- f ff cate pate

9. Return to: DepartmenPpfEMneerin eseanch Attent1on s H Ujj n

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3400 Crow Canyon A6as San Ramon CA M583 i- - - _ . . - . _ _ _ . _ . - _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _

Pacific Gas and Elactric Company PRECEDURE NO.: A-7 Planning and Research De artment "EVISION R NO.: 1 ENVIRONMENTAL RADIOLOGICAL MONITORING EFFECTIVE DATE: 1?'16/95 PROCEDURE - DCPP (NORMAL OPERATIONS)

VOLUME NO.: V-A APPROVED:

V W ATE: #M V EWED BY -

V y SCOPE This procedure constitutes the Environmental Radiation Monitoring Procedure (ERMP) and describes the methodology for the conduct of the Radiological Environmental Monitoring Program (REMP) for Diablo Canyon

1. l Power Plant. The REMP is conducted by Pacific Gas and Electric Company's Department of Engineering Research (DER). Description is also provided for the annual land use census, DER's participation in the EPA Intercomparison Program, and DER's cross-check program with the State of California. Esth routine (annual) and nonroutine reports detailing the results of tne aforementioned activities are also described.

DISCUSSION

2. l This procedure is utilized to support the portions of the DCPP Technical Specifications (Sections 3/4.12) which deal with radiological environmental monitoring, land use census, and laboratory intercomparison.

This procedure describes the minimum required radiological monitoring program; additional samples may be collected, and other analytical procedures may be utilized in order to provide additional environmental data. These additional samples and analyses will be used to supplement, but not as a sut'stitute for, the required samples and analyses.

REQUIR EMENTS 3.l 1. Environmental sawles shall be collected and analyzed according to Table 1 at the locations shown in Table 5 and Figures 1, 2, and 3.

Analytical techniques used will be such that the detection capabilities in Table 2 are routinely achieved.

Deviations from the sampling schedule may be necessary if specimens cannot be collected due to hazardous conditions, seasonal unavailability of samples of the media of choice, malfunctions of automatic sampling equipment, or other legitimate reasons. If specimens are unavailable due to sampling equipment malfunction, an effort will be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule and sampling equipment malfunctions shall be documented in the Annual Radiological Environmental Operating Report.

9204b 855y sm/ mat

PROCEDURE NO. A-7 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 2 0F. 20 DCPP (NORMAL OPERATIONS) REVI3TurNO. I VOLUE NO. V-A

2. DER will conduct 'a land use census at least once per year between the dates June 1 and October 1 which will identify the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 50 m2 (500 so f t) producing broadleaf vegetation in each of the 16 meteorological sectors within the distance of 8 km (5 mi). This census of milk animals and gardens producing broadleaf vegetation is required in order to identify changes in use of unrestricted areas to permit modifications in monitoring programs for evaluating doses to individuals from principal exposure pathways.

If the land use census identifies a location (s) that yields a calculated dose or dose comitment greater than the values currently being calculated, the new location (s) shall be identified in the next Semiannual Radioactive Effluent Release Report.

If the land use census identifies a location (s) that yields a calculated dose or dose comitment (via the same exposure pathway) 20 percent greater than at a location from which samples are currently being obtained in accordance with Table 1, add the new location (s)

- within 30 days to the Radiological Environmental Monitoring Program given in this ERMP. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose comitment(s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Documentation for a change in the ERMP will be submitted in the next Semiannual Radioactive Effluent Release Report including a revised figure (s) and table (s) for the ERMP reflecting the new location (s) with information supporting the change in sampling locations.

3. a. Participation will be maintained in the Environmental Protection Agency's (EPA) Environmental Laboratory Intercomparison Studies (cross-check) Program. This participation will include each of the determinations (sample medium-radionuclide combination) that are offered by the EPA as of January 1 each year which are also included in the monitoring program. The results of analyses of these cross-check samples will be included in the annual report.

If the analyses are not being performed as required, report the corrective action to prevent a recurrence in the Annual Radiological Environmental Operating Report.

b. Participation will be maintained in a cross-check, split sampling program with the State of California Department of Health Services (DHS) as required by DHS. The program will consist of radio-analyses of duplicate samples or replicate analyses of the same sample by both DER and DHS. The results of DER's analyses of the samples will be transmitted to DHS as soon as practicable af ter the end of the quarter in which the samples were collected. The sample types, analyses performed, and frequencies of collection are given in Table 6.

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PROCEDURE NO A-7 I ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 3 0F 20 DCPP (NORMAL OPERATIONS)

REVI N NO. 1 VOLUMC NO. V-A l

4. Reporting Requirements i

i a. Annual Radiological Environmental . Operating Report.

f A report on the Radiological Environmental Monitoring Program will be prepared annually. This report, prepared by DER, will be reviewed by PGandE Co. Nuclear Power Generation (NPG) staff prior to submission to the Regional Administrator of the NRC Regional Office prior to May 1. The submission will be made by NPG.

1 The Annual Radiological Environmental Operating Reports shall include sumaries, interpretations, and an analysis of trends of i the results of the radiological environmental surveillance activities for the report period, including a comparison with preoperational studies, operational controls (as appropriate), and I previous environmental surveillance reports and an assessment of

' the observed impacts of the plant operation on the environment.

i The reports shall also include the results of land use censuses.

The Annual Radiological Environmental Operating Reports shall 3

include the results of analysis of all radiological environmental j samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in tables e and figures in this ERW as well as sumarized and tabulated results of these analyses and measurements in the format of Table 3. In the event that some results are not available for i- inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted as soon as possible in a supplementary report.

j The reports shall also include the following: a sumary description of the Radiological Environmental Monitoring Program; at least two legible maps

covering all sampling locations keyed to a table giving distances and directions from the centerline of l

one reactor; the results of licensee participation in the Interlaboratory Comparison Program and the corrective action taken if the specified program is not being performed as required by

4. Requirement 3.a. (above); reason for not conducting the Radiological Environmental Monitoring Program as required by j Requirement 1 (above), and discussion of all deviations from the l

sampling schedule of Table 1; discussion of environmental sample -

measurements that exceed the reporting levels of Table 4, but are not the result of plant effluents, pursuant to Reporting Requirement 4.6.2 above; and discussion of all analyses in which the LLD required by Table 2 was not achievable.

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f *0ne map shall cover stations near the SITE BOUNDARY; a second shall l

include the more distant stations.

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PROCEDURE NO. A-7 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 4 0F 20 REVI'5TUTNO. I DCPP (NORP%L OPERATIONS)

VOLUME NO. V.A

b. Nonroutine Environmental Radiological Operating Reports

1) Report of Program Variance If the radiological environmental monitoring program is not being conducted as specified in Table 1, in lieu of any other report, prepare and submit to the Regional Administrator of the NRC Regional Office in the Annual Radiological Environ-mental Operating Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. The submission will be made by NPG.

2) Anomalous Result Report If a measured radionuclide concentration resulting from plant effluents in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting

- level given in Table 4, a written report will be submitted to the Regional Administrator of the NRC Regional Office within 30 days from the end of the quarter. The report shall identify the cause(s) for exceeding the limit (s) and define the corrective actions to be taken to reduce radioactive effluents 50 that the potential annual dosel to a MEMBER OF THE PUBLIC is less than the calendar year limits of Technical Specifications 3.11.1.2, 3.11.2.2, or 1.11.2.3. When more than one of the radionuclides in Table 3.12-2 are detected in the sampling medium, this report shall be submitted if:

Concentration (1) Concentration (2)

~

Reporting Leve1 (i) # Reporting Level (2) + . . . 21 0 When radionuclides other than those in Table 3.12-2 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dosel to a MEMBER OF THE PUBLIC from all radionuclides is equal to or greater than the calendar year limits of Technical Specificaions 3.11.1.2, 3.11.2.2, or 3.11.2.3. This report is not reauired if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report.

1 The methodology and parameters used to estimate the potential annual dose to a MEPEER OF THE PUBLIC shall be indicated in this report.

- PROCEDURE NO. A-7

, ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 5 0F 20 t l DCPP (NORP%L OPERATIONS) REVI N NO. I ;

VOLUE NO. V-A

3) Notification of Sample Unavailability If milk or vegetation sampling is not being performed as required by Table 1, identify specific locations for obtaining replacement samples and add them within 30 days to the

! Radiological Environmenal Monitoring Program given in the ERW . The specific locations from which samples were unavailable may then be deleted from the monitoring program.

Pursuant to Technical Specification 6.14, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ER W including a revised figure (s) and table for the ERMP reflecting the new location (s) with supporting information identifying the cause of the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

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TABLE I Radiological Environmental Monitoring Program gg 45m

^9 Exposure Pathway Number of Representative Sampling and Type and Frequency hM and/or Sample Samples and Sample Locations (l) Collection Frequency of Analysis 3$

"N

1. Direct Thirty-one routine monitoring stations

Quarterly. Ganma dose quarterly. %=

Radiation (2) either with two or more dosimeters or 9E with one instrument for measuring and DB' recording dose rate continuously, 55

. placed as follows: *{

N An inner ring of stations, one in each terrestrial meteorological sector in 3 the general area of the SITE BOUNDARY; y o

An outer ring of stations, one in each terrestrial meteorological sector in 5 the 2.5 to 12 km range from the site; g and g m

The balance of the stations to be g placed in special interest areas such m as population centers, nearby resi- .

dences, schools, and in one or two areas to serve as control stations.

$NER

Inner ring stations: 051, WN1, 052, 151, 251, 351, 451, 551, 553, 651, 751, 851, 852, 951, and Mil. E588 Outer ring stations: l Al, 0B1, ICl, 201, 301, 4C1, SC1, 6DI, and 7Cl. 45 Special interest stations: 401, 5F1, 7F1, 701, 7D2, and 7C2. g E *@=

Control station 2F2. . g o,

,o O

> ~

TABLE 1 - contd.

Number of Representative Sampling and Type and Frequency Exposure Pathway Samples and Sample Locations (l) Collection Frequency of Analysis M.;;

5 and/or Sample z9 gg

2. Airborne B*

Radiolodine Samples from six locations (MT1, 052, Continuous sampler Radiolodine Canister: rp 851, 2F2, SF1, and 701): operation with sample I-131 analysis g9 and collection weekly, or weekly, m>

particulates Three samples (Mil, OS2, and 851) from more frequently if required by dust Particulate Sampler:

Q

-g close to the three SITE BOUNDARY loca- zg tions, in different tectors, two in loading. Gross beta radio-sector with the highest calculated activly analysis n following filter M annual average ground level D/Q, the other in south sector; change (3) and gansna g isotopic analysis (4) z l

One sample (701) from the vicinity of of composite (by y l location) quarterly. x a consnunity having the highest calcu-lated annual average ground level D/Q; g m

One sample (5F1) from the San Luis g Obispo area; and g One sample (2F2) from a control location.

l

3. Waterborne <=mm

a. Surf ace One sample from Diablo Creek (552). Monthly grab sample. Gansna isotopic analysis (4) monthly.

[3M gg g Composite for tritium ,g ug analysis quarterly. p,o m o nz Monthly grab sample. Gansna isotopic P

b. Drinking One sample of plant drinking water l analysis (4) monthly. < -

g>

l (DWI). Composite for tritium > w l

analysis quarterly.

l l

TABLE 1 - contd.

Exposure Pathway Number of Representative Sampling and Collection Frequency (l)

Type and Frequency y and/or Sample Samples and Sample Locations of Analysis mg

^9

4. Ingestion gg

a. Milk Samples from milking animals in three Semimonthly when Gamma isotopic (4) locations within 5 km distance having animals are on and I-131 analysis o the highest dose potential. If there pasture; monthly at semimonthly when 7,5 are none, then one sample from milking other times. animals are on 50 .

animals in each of three areas between pasture; monthly at d8 5 to 8 km distance where doses are cal- other times. 98 culated to be greater than 1 mrem per =

year. One sample from milking animals #

at a control location 15 to 30 km distant-and in the least prevalent wind !

direction. ]

m

b. Fish and One sample rockfish (Sebastes sp.), one Sample in season, or Ganna isotopic E Inverte- sample surfperch (Family Embiotocidae), semiannually if they analysis (4) on edible o brates and one sample abalone (Hallotis sp.) are not seasonal, portions of each from the vicinity of plant discharge sample. 8 area (DCM). G Sii One sample of the above in areas not m influenced by plant discharge (POS or e PON).

c. Food Samples of three different kinds of Monthly during Ganna isotopic (4) and ,,,,

Products

broadleaf vegetation (5) grown nearest growing season. 1-131 analysis. pqgg each of two different off- site loca- c-mm tions of highest predicted annual EU ""E average ground level D/Q if milk gE g sampling is not performed. .gg O One sample of each of the similar Monthly during Ganna isotopic (4) and

broadleaf vegetation grown 15 to 30 km growing season. I-131 analysis. ?

~

Ej !'"

distant in the least prevalent wind direction if milk sampling is not performed.

If food products are unavailable, additional air sampling as specified in Table 1, Part 2 will be done in the SE (Station 852) and NNW (Station ISI) sectors.

-_m - __ <_ _ _.__ ___ ._.-_;-__.__ ,. -, . _ . _ _ . ._m _. _ __ . -_. ___ _.

i TABLE 1 - contd.

Tablo Notation Rz o<

(1) Deviations are permitted from the required sampling schedule if <pecimens are unobtainable due to ';;;

circumstances such as hazardous conditions, seasonal unavailability, and malfunction of automatic ^g sampling equipment. If specimens are unobtainable due to sampling equipment malfunction, effort $3 shall be made to complete corrective action prior to the end of the next sampling period. n .1 Eaj deviations from the sampling schedule shall be documented in the Annual Radiological Environmental F je Operating Report. It is recognized that, at times, it may not be possible or practicable to %

m>

continue to obtain samples of the media of choice at the most desired location or time. In these instances, suitable specific alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the Radiological Q

gg Environmental Monitoring Program. Pursuant to Technical Specification 6.14, submit in the next g Semiannual Radicactive Effluent Release Report documentation for a change in the ERW including a e -

revised figure (s) and table for the ERW reflecting the new location (s) with supporting Information E

identifying the cause of the unavailability of samples for that pathway and justifying the section g cf the new location (s) for obtaining samples. z, !

(2)For the purposes of this table, a thermoluminescent dosimeter (TLD) is considered to be one $

z phosphor; two or more phosphors in a packet are considered as two or more dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

E (3) Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more g o

af ter sampling to allow for radon and thoron daughter decay. If gross beta activity in air particulate samples is greater than 10 times the yearly mean of control samples, gama isotopic k analysis shall be performed on the individual samples. ,

(4) Gamma isotopic analysis means the identification and quantification of gama-emitting radionuclides that may be attributable to the effluents from the f acility.

2 5555 ,

(5)Broadleaf vegetation is that with leaf surface area exqeeding 100 gm . Vegetation approaching g3g; gr m broadleaf is that with leaf surface area between 50 cet and 100 cm2 zE eze .

r n~

_;_-- .,m _ - . - _ _ .. .- -w.,. _ _ _ . , . _ _ ._

PROCEDURE NO. A-7 ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 10 0F 20 DCPP (NORMAL OPERATIONS) REV! M NO. I VOLUE NO. V-A TABLE 2 Detection Capabilities for Environmental Spmple Analysis (1)(2)

5. Lower Limits of Detection-(LLD)t3 1 Airborne Food Particulate Fish Products Sediment Of 085'S (pC1/kg, Milk (pCi/kg, (pC1/kg, Water Analysis (DCi/1) (pCi/m ) wet) (DC1/1) wet) dry)

Gross beta 4 0.01 H-3 2000*

Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-Nb-95 15 I-131 1** 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-La-140 15 15

For surface water samples, a value of 3000 pC1/1 may be used.

- !f no drinking water pathway exists, a value of 15 pCi/1 may be used.

Table Notations (1) This list does not mean that only these nuclides are to be

6. considered. Other peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Specification 6 . 9.1. 5.

i PROCEDURE NO. A-7 ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 11 0F 20 REVITT F NO. I DCPP (NORMAL OPERATIONS) V-A VOLUE NO.

TABLE 2 - contd.

Table Notation - contd.

(2) Required detection capabilities for thermoluminescent dosimeters used 6*

for environmental measurements shall be in accordance with the recomendations of Regulatory Guide 4.13, Revision 1. July 1977.

(3) The LLD is defined, for purposes of these specifications, as the smallest concentration of radioactive material in a semple that will ;

i yield a net count, above system background, that will be detected ;

with 95 percent probability with only 5 percent probability of f alsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

S 4.66 b LLD = E x v x 2.22 x Y x exp (- At) where LLD is "a priori" the lower limit of detection as defined above (as pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate ;

or of the counting rate of a blank sample as appropriate (as !

counts per minute) i E is the counting efficiency (as counts per transformation)

V is the sample size (in units of mass or volume) ;

2.22 is the number of transformations per minute per picoeurie Y is the f ractional radiochemical yield (when applicable)

A is the radioactive decay constant for the particular radionuclide t is the elapsed time between sample collection (or end of the .

Sample collection period) and time of counting i

The value of sb used in the calculation of the LLD for a detection j system will be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as . !

i appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gama ray spectrometry, the background will include the typical r t

contributions of other radionuclides normally present in the samples t (e.g., potassium-40 in milk samples),

t

I L

e PROCEDURE NO. A-7 ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE :.2 0F 20

. DCPP (NOR mL OPERATIONS) REVIT F NO. I l VOLUE NO. v-A l

Analyses will be perfomed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or l other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing f actors will be identified and described in

7. the Annual Environmental Radiological Operating Report pursuant to Technical Specification 6.9.1.5.

t r

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l TABLE 3 Environmental Radiological Monitoring Program Summary Name of Facility Docket No. y Reporting Period kN Location of Facility gz (County, State) r-y 5

Medium or Type and Lower Limit Location with Highest All Indicator Control 5S Pathway Sampled Total Number of Annual Mean locations locations Number of d8 (Unit of of Analyses Detection (a) Name Distance Mean(ll(b) Mean(l)(b) Mean(l)(b) Reportable 98 Measurement) Performed (LLD) and Direction Range [b) Range (b) Range (b) Occurrences ON 5

1 3 3

! M 3 .

2 o

EO 2

O l %m e

(a]Unless indicated the LLDs specified in Table 3 were met.

<: :o v i (b]Mean and range based upcn detectable measuremer.ts only. Fraction of detectable measurements at specified locations is indicated in parentheses (1); e.g., (10/12) means that 10 out of 12 samples 8055 contained detectable activity. g{2 29 "' E ,

ez,-

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PROCEDURE NO. A-7 ENVIRONMENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 14 0F 20 DCPP (NORMAL OPERATIONS) REV[5 TUN NO. I VOLUME NO. V-A TABLE 4 Reporting Levels for Radioactivity Concentrations in Environmental Samples Airborne Particulate Water or Gases Fish Milk Ve Analysis (pCi/1) (pCi/m3 ) (pCi/kg, wet) (pC1/1) (pCletables/kg. wet)

H-3 20,000*

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400 I-131 2** 0.9 3 100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2, 000 B a-L a-140 200 300

For drinking water samples. This is the 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 DCi/l may be used.

- !f no drinking water pathway exists, a value of 20 pCi/1 may be used.

,- l PROCEDURE NO. A-7 ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 15 0F 20

' REVIITOR~NO. I DCPP (NOR mL OPERATIONS) v-A 1 VOLUE NO.

TABLE 5 Distances and Directions to Environmental Monitoring Stations (Stations are shown on Figures 1. 2, and 3)

Sta- Radial Direction Radial Distance tion (True Heading) f rom Plant Code

Station Name (Decrees) km (Miles) 051 Exclusion Fence-Northwest Corner 320 .16 (0.1) !

052 North Gate 320 .8 (0.5) 151 Wastewater Pond 330 .64 (0.4) 251 Back Road-300 m North of Plant 0 .32 (0.2)

351 Road NW of 230 kv Switchyard 23 .64(0.4) 451 Back Road Between Switchyards 43 .8 (0.5)

, 551 400 kv Switchyard 58 .64 (0.4 '

i 552 Diablo Creek Weir 65 .96 (0.6 i 553 Microwave Tower Road 70 1.02 (0.7 i 651 Microwave Tower 94 .8 0.5 1 - 751 Overlook Road 112 48 0.3 l i 851 Target Range 125 .8 0.5 l 1 852 Southwest Site Boundary 128 1.76 (1.1 1 951 South Cove 167 .64 (0.4 l I Mil Meteorological Tower 185 .32 (0.2 ,

DCM Diablo Cove 270 .32 0.2) ,

WN1 Northwest Guard Shack 290 .32 0.2 >

1A1 Crowbar Canyon 327 2.56 1.6 )I ,

081 Point Buchon 325 5.76 (3.6) '

f 1C1 Montana de Oro Campground 336 7.52 (4.7) '

i 4C1 Clark Valley Gravel Pit 45 9.28 (5.8)

SC1 Junction Prefumo/See Canyon Roads 64 7.52 (,4.7? -

l 7C1 Pecho Creek Ruins 118 6.56 (4.1 J 201 Sunnyside School 10 11.04 (6.9 ,

j 3D1 Clark Valley 24 9.92 f6.2 i 401 Los Osos School 36 12.16 J7.6 j 601 Junction See/ Davis Canyon Roads 89 12.0 (7.5 701 Avila Gate 120 10.56(6.6) 702 Avila Beach 110 12.16 (7.6) '

2F1 Morro Bay 0 17.44(10.9) 2F2 Morro Bay Power Plant 359 17.92(11.2 (

l 5F1 SLO Zone 1 Substation 68 17.92(11.2 i' 5F2 Cal Poly Farm 60 20.16 12.6 5F3 SLO County Health Department 70 20.32 12.7) 7F1 Shell Beach 110 17.28 10.8) 7F2 Pismo Beach 115 20.16 12.6) 7G1 Arroyo Grande 115 26.88(16.8) 7G2 Oceano Substation 118 27.68(17.3) 8H1 Caroni Dairy 141 41.28(25.8)

l*

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! PROCEDURE NO. A-7 l ENVIRONENTAL RA010 LOGICAL MONITORING PROCEDURE - PAGE 16 0F 20

- DCPP (NORMAL OPERATIONS) REV15TUrNO._ 1 VOLUE NO. v-A ,

TABLE 5 - contd.

Sta- Radial Direction Radial Distance tion (True Heading) from Plant t

Code

Station Name ,

(Degrees) (Miles) i SM Santa Maria 127 47.52(29.7) l LO Lompoc 154 71.4 (44.6)

SV Solvang 144 89.8 (56.1) ,

i OUT Plant Outf all 270 .32( 0.2) ;

j DW1 Orinking Water from Administration Building In plant ---

PON Pacific Ocean North of Diablo Cove 350 2.4 ( 1.5)

POS Pacific Ocean South of Diablo Cove 145 1.28( 0.8)

5tation Code (XYZ):

X - First number (0-9) represents the radial sector in which the station is located: j O - Northwest 5 - East-northeast 1 - North-northwest 6 - East ,

2 - North 7 - East-southeast l 3 - North-northeast 8 - Southeast l 4 - Norttieast 9 - South-southeast l l

Y - Letter ($, A-H) represents the distance from the plant:

S - On-site A 2 miles from plant (but off-siteJ .

8 4 miles from plant C 6 miles from plant t 0 8 miles from plant

! E 10 miles from plant l F 15 miles from plant l' G 20 miles f rom plant .

H - Greater than 23 miles from plant I l Z - Second number represer,ts the station number within the Zone.

l

Station Code (LO. SM. SV. OCH. MT1 WNI PON, POS, OUT. 0W1):

The follrwin stations do not follow the coding system: Lompoc(LO)

Santa Ma*ia SM). Solvang (SV), Diablo Cove Marine (OCM), Meteorological Tower Pacific (PTI),

OceanNorthwest South (PO !uard shack

), Plant (WN1),(Pacific outf all 0UT), and DrinkingOceanwater North (PON)(DWI)

I l t______________________

4 I

L PROCEDURE NO. A-7 l

{

ENVIRONENTAL RADIOLOGICAL MONITORING PROCEDURE - PAGE 7 0F 20 DCPP (NORP%L OPERATIONS)

REV1 NO., I .

VOLUE NO. V.A j 1

TABLE 6 .

?

Sumary of Cross-Check Program with State of California Radioanalyses I Sample Type Station No. Frequency

i Milk SF2 Quarterly Gama Isotopic !

2 (incl. 1-131) (

K-40 ,

t Milk 8H1 Monthly Gamma Isotopic i '

(incl. 1-131) i K-40 ,

t I

Orinking Water OW1 Monthly Gama Isotopic i l

i (incl.1-131)

H-3 Outfall OUT Monthly Gama Isotopic, H-3

! Surface Water SS2 Quarterly Gama Isotopic, H-3 ;

1 I Vegetative Greens 7G1 Quarterly Gama Isotocic l 4

(incl. 1-131) ;

i Quarterly Gama Isotopic j - Bull Kelp DCM I

Fish or Invertebrate OCM Quarterly Gama Isotopic Air Particulates and SF1 Quarterly Gross Beta, !-131 I l

Radiciodine 701 ;

3 Sediment DCM Annually Gama Isotopic i,

Direct Radiation (TLD) Mil, 401, SF3 Quarterly Gama Exposure (mR)

) 701, 7C1 t l

'When available. t L

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File 206.2 85-211 ;

I PACIFIC GAS AND ELECTRIC COMPANY '

l OIABLO CANYON POWER PLANT

( PLANT STAFF REVIEW COMMITTEE

. t Plant Manager's Office Minutes of a Regular Meeting Novenber 7,1985 4

Regular Members Present:

R. C. Thornberry, Plant Manager (Chairman) l J. V. Boots, Chernistry and Radiation Protection Manager i

C. L. Eldridge Quality Control Manager (Secretary) l S. R. Fridley, Senior Operations Supervisor (J. A. Sexton's Alternate) i J. M. Giscion. Assistant Plant Manager / Technical Services T. J. Martin, Training Supervisor (W. B. Kaefer's Alternate)

C. B. Miklush, Maintenance Manager i R. Patterson, Assistant Plant Manager / Plant Superintendent i

i Special Ve-ters Present: i W. E. Coley, Resident Startup Engineer K. C. Dess, Senicr touclear Pcwer Generation Engtrur (W. T. Rapp's i i

Alternate) '

i C. A. Taggart, Acting Cirectcr Cuality Suppcrt l

l Gues ts :

S. G. Banten Senior Pcwcr Productict Engineer C. G. Cestarello, OrEG Plant Design Group Superviser l M. P. Harrahan, Serior Instrurent and Cortrols Maintenance Surceviser l C. E. Jchnser, Fire Marshall l L. D. Forowski, Assistant Onsite Project Engireer l D. C. Tateosian, OPEG Mecharical Group Leader l

J. H. White, Health Physicist. DER t

The Chairran - the Cerrittee t,eirg a quorum and those spnrscring surtrvisers having general responsibility for the terics on the agend3 present -- called the natirg to order at 1:00 p.r.

1. Feview of Terrerary Procedure Changes ;

i' 7tt C&ittee reviewed the Te porary Procecare Chargas listed et Attachetrt 1 and recemrends that the changes be approved by the Plant '

Forager. It it the opinion of the Committee that these procedure chv ge!

l do not corstitute a charge to the facility or procedures as described it!

the FSAR or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not required. Fu r thermore ,

these procedure changes do not pretent unreviewed safety questions, changes to the plart's Technical Specifications, or unreviewed environmental quertions. r I

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I Plant Staff Review Committee Minutes85-211 l; November 7,1985 l: ~

Page 2 of 6

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, c. Review of Open Item Reports l

l, The Open Item Reports are being withheld until the next regularly scheduled l

PSRC meeting.

3. Review of Open PSRC NPPRs/ Action Requests The Open PSRC NPPRs/ Action Requests are being withheld until the next regularly scheduled PSRC meeting.

4. Review of Nonconformance Report DC2-85-MM-N114. " Accumulator Tanks 2-1 and 2-3" Af ter sore discussion, the Comittee concurs with the resolution, corrective action and reportability propcsed by the Technical Review Group and concurs that this' NCR is now ready for closure.

l The Co-rittee believes no unreviewed safety question as defined in 10CFRSC.59 is crea*ed by this conconferrance recort.

5. Review of IE Infermation Notices

a. 85 42 " Loose Phosphor in Paresonic 800 Series Badga Thermoluminescent Dosimeter (TLC) Elements" and Response Letter Fren D. W. Shelley The above notice concerns a problem in sore Panasonic 800 series TLD badges that has caused spurious high readings in one of the badges' 4 TLD elements. Several Panasonic TLD users have identified badges where crystals of the chosphor have detached themselves froa the l

backing of the element, resulting in high erratic readirgs in that element.

1, l

The Comittee does not agree with Mr. D. W. Shelley's response letter l

and will request a revised response letter to be reviewed by the PSCC l

st a 1 ster date.

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Plant Staff Rev ew Committee Minutes i

85-211 November 7. 1985 Page 3 of 6

[

5. Review of IE Information Notices (Continued)

b. 85-44, " Emergency Communication Systen Monthly Test" and Response Letter From D. W. Shelley The subject notice was issued to alert licensees of emergency preparedness esercises and specific tests by NRC Headquarters Operaticns Officers identifying serious comrunication malfunctions at other plants, which were previously undetected because of inadequate monthly testing. In most of those cases, neither the Emergency Notification System (ENS) nor Health Physics Network (HPN) telephones were found to have been routinely tested.

The PSRC agrees with Mr. Shelley's response letter dated October 7,1985, stating that STP I-298, "NRC Erergency Notification Systen and Health Physics Network Functional Test" requires that trete specific tests be perforced monthly. Adecuate documentatien is provided by this STP; therefore, no further actiers ar. required to address the concerns of this notice.

c. 85-52, " Errors in Dose Assessment Ccrputer Codes and Repertinc Requirerents l'nder 10 CFR Part 21" and pesponse Letter Fror

, D. W. Shelley l

The abcve notice anrcunced that the San Onofre Nuclear Generating Station staff discesered a programing error in the Nuclear Data supplied Emergency Assessrert and Resperse Systen (EAR $1 rr?;re .

This cJrputer code error led to substantial pcstulated rediation exposures which are rescrtable under 100FR21.

The r adioiegical Environ entet, and Chemical Engineering Section indicated that our estesive veri'icetion and validation (WVi proce:s in 1933 to study the EARS dispersion computation, idertiffed and corrected calculational errors in tre vendor supplied pro yam . The

) findings are well-documented in the V&V Report published in 1983. The current version of EARS sof tware does not resemble the vendor supplied code due to the substantial changes made during the V&Y improverent effect.

The Cer*ittee agraes with the conclutiers brou7t f ceth in Mr. D. W. Shelley's response letter as stated above. Due tr tu corrections already made and the results of the V&V process verifying code validity, the PSRC feels that no actions are required to address i this notice.

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Plan? Staff Review Committee Minutes 1 5-211 >

November 7,1935 Page 4 of 6

6. Review of Plant Procedures The procedures listed on Attachment 2 are not a change to the facility or procedures as described in the FSAR, or a test or experiment not described in the FSAR. Therefore, a written safety evaluation per 10CFR50.59 is not required. Furthermere, these procedures do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed environmental questions.

1 The following procedures were previously approved by the PSRC:

Startuo Test Procedures 41.1 Plant Shutdown From Outside the Main Cnntrol Room (Unit 2), '

Rev. 1 '

43.5 Red Group Drop and Plant Trip (Unit 2), Rev. 0

7. Rescissier cf Plant Procedures The folicwing procedures are r- 1rnger ree:!a: and are retcinded:

Ad.inistrative Procedure 6-85051 Qualification of Quality Con.rol Departrent Person e!, Re<.1 Mechanical Maintenance Procedures M-1 Reacter Head Thermal Insulaticn Installatic" and Re?osal, Dev. O M-110 Thernal Spraying on Metal Surfa:c, Rev. 0 Cte-ital Analysis Procedure B-13 Multichannel Analyn r, Rav. 0

8. Review of Procedure Two-year Followup The Committee reviewed the following p acedure and finds that it is acceptable for continued use:

Nuciaar Plant Administrative Procadure l, 0-11 Equipment Restricted From Nuclear Sefety App 1tcations, Rev. !

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DC0481 .4 '

Plant Staff Review Committen Minutes85-211 November 7, 1985 Page 5 of 6

(

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9. Other Items of Business 3

a. " Change of Intent" The Committee reviewed a proposed definition of " Change of Intent" as it :pplies to procedure changes. The Committee essentially agreed with the definition. Various members were to forward their comments to the Quality Control Manager by 11/14/85.

b. NCR Trend Analysis - OSRG The PSRC reviewed a NCR Trend Analysis report prepared by the Onsite Safety Review Group for the third quarter, 1985.

c. PSRC Licersing Docurent Interpretatio - Technical Specificaticr 4.7.5.lb.1.

The Committee approved the above Licensing Document Interpretatice,

, 85-10, Revision 0. A copy is attached to these minutes.

c. Response to Ger.eric Letter 85-09 (Technical Specificatior.s for Gercric Letter No. 83-28, Item 4.3)

The P5RC approved the attached draf t of PGardE's response to the f EC on Generic Letter 85-09. This respense is based on the hestirghouse Owners Group pcsition that was reviewed at the September General Session.

a. Annunciator Response Procedurcs Mr. 5. R. Fridley informed the Committee that the following Annunciator Response Procedures of Plant Marual Volurt 16 havc bo.-

revised: -

' PK-0101 PK-0519 PK-1113 PK-0107 PK-0907 PK-1115 PK-0203 PK-0908 PK-1301 PK-0301 PK-1001 PK-1316 PK-0302 FE-1002 PK-1501 PK-0321 PK-1005 PK-1508 PK-0325 PV-1010 PK-19C3 PK-0416 PK-1012 PK-1904

, PK-0509 PK-1025 PK-1914

f. Tracking Commitments to the NRC Mr. J. M. Giscion brought to the Committee's attention that Regulatcry

'. Corpliance is tracking ' commitments to the NRC. Regulatory Corpliance

( has an open itens list which they intend to issue on a bi-weekly

basis.

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! OC0481 5 .

a Plant Staff Review Committee Minutes85-211 November 7,1985 Page 6 of 6 ,

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. 9. Other Items of Business (Continued) ,

g. Unit 2 Snubber Problem ,

The PSRC had a discussion witn' 0 PEG regarding failed snubbers on the steam supply line to Unit 2 aux:iliary feedwater turbine. The Committee directed that Maintenance inspect the snubbers, Operations perform another cold start of the' turbine, and Maintenance would ther, reinspect the snubbers for damage. If damage was found Engir.eering

( would perform an evaluation for operability.

h. , Testing for Components Receiving Redundant Actuation Signals From the SSPS Trains Mr. S. G. Banton asked for the Committee's guidance as to the extert cf testing required for components, receiving redundant actuation signals from the SSPS trains. It was agreed by the PSRC that Engineering should test the feedwater pump trips and pick the rest of the tests up at the strainer outage.

The meeting adjourned at 3:15 p.m.

i i? ,

i'/d:TI'

.L. b.DRIDG5 '/

Secreta ry CLE:dc Attachments s

'~

APPPCiALS:

., j /s 6? e 7 R . C . It10 R.'iE E R a f Plant Manager >]

t;0\' 2 7 E.-

C3 q .

),j -

'l k.~PhiTER501r' YSA W ~

,- Assistant Plant Manager / Plant Superintendent i Cosnittee Charter's Standard Distribution l(

3 i,

i -

! CC0481 6

. ._, ... l

4 A - - + -,.

O e

i ATTACHMENT 4 4

DC0003

"'# "---N* * , . + - - - , - ,

,._. ., ,__ _,_ __ # "'"Nr~'d-WYy-N --...c . - .7,_,

DEPAR'?CC OF ttJCLEfe PJIC OPENJ10 tr9-1 33 D% (100) DIAiLD CAO PDS PLNG mli iCS 1 #C 2

. g fitIDLE M15fGN gy M A.O. Tavior pnacgru E No CAP A-8 WITNo 20 2 0 2 2 B T17tz 0FFSITF 00Sr CALCULATION PROCEDURE (ODCP)

E To M _--_.4As A M,suLT: New combined two units' Tech seec's. reductinn Ova h H g g 3 9 H E C,copsiggpat]Qns, deletion of obsolete historical averace met parameter:

Pucccutt Is leaRT mT To SAFETY hb leaRTmt to EwimmeetTAL QALITY bb OO Stam!Tv- h ATED DD Apt!N!stnATivt (A to E Setits AP)

@d Pucccutt %eut=Es PSRC REVIEW OC %2JIEs IEEPDe(T TECH REVIDs

, ., WA O /

Conc'mnENcE:

I ! * /' J ' l APPipA:

a ra-n a ri & -- L oraAm.c ne T kh// Mk W SPCris0R's AssEssteiT - IEscAISE CrW<f($1: Ova vwmsrs 51w.aE SEE ATTACHED SHEETS

- ~

%Asa FOR PEW PCCcuti[r10Ccuti %v151mij Ihe new two units' combined tech specs. eliminate the need for consideration ot han8daysexceptingI-133oseAlsonew .

duetoglSeouseffluentisotQpeswithhalflivesless ive-year runninD historical averacee reteorological dispersion parameters at the candidate controlling dose locations obviate the previous older set also included in CAP A-8. Finally, slight editorial clarifications and spelling corrections were " piggy-backed" in on this revision.

DaEs T4 lEn PloccutE(noccuqE REVis!CieWITUTt M lHEVIEED SAFETY 4mlENENTAL Q1S PloCEuE IESattaED IN FsAR? YEs O to O l .ggr1FICATICN:

LSEDITORIE CanesCEs; %0mGAN!ZE)%80RST PnocE3tmE 1 l

O lete<xTarion or tee ist %2uinee<T (% tnENcE GIPf'.DENTATION or Tsoes specs CnnNat D iacaemATEo Te,ane pnocs:uit CamcEs DATES 80Teo Eliminate obsolete met carameter tables 1*Erecett TEcu tvloet AssEssrtNT - hATuE or kviEW s CacustaNs CheckedReviewed editorial the new "five vear" clarifications.

runnin hi torical dis wit $$earameters.the new two units' combined Tech. . Specs.

Compar$d t$1s procedurSersi n to ensure compliance. Verified the changes of tables 1 through 6 with the dose parameters as calculated by P.G&E. 's /km/ry'Mn //~" 7-M-

" Tech. Soec',' code and Rectd .109 or - JcEai<Ev' TEP 0:09 7,gk k i-If.-ty W -'* Arrem A DATE M/M/ P " METulaufim DATE d.A M PSP %vio. DaTE // [( Jgg;gg b ggp - ACCEPTC %JECTED O PLIAsE SE A3StimA. $*EETs O

,.m_--_ _ _ . _ _ . , _ . . , , _ _ _ _ _ .--_ ._.- -,,, _ . _ , _ _ . _ _ . - _ _ . _ . , , - , , . , . _ - - . _ . - _

m- ____v...._,

_ - - - . - ~ - -- .

PAGE 2 0F 5 69-10733-1 11/82 (50) PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT PROCEDURE HISTORY CONTINUATION SHEET PROCEDURE NO. CAP A-8 rey. ((

DESCRIBE CHANGE (S)/ REASON FOR CHANGE:

1. Under SCOPE: Liquids Tech Stec. surv'll. req., change " batches" to " effluents".

2. "

": Liquids Tech. Spec. surv'll req., delete " analysis of. continuous releases:

3.

" ": Gases Tech. Spec. surv'll. reg., clarify..." radionuclides other than Noble Gases" for doserates.

4. " ": Gases Tech. Spec. surv'll. req. , clarify. . ." Noble Gases, Iodines. . ."

for dose projections.

5. "

": Implements, change "10CFR50 App. !" to "10CFP50 App. 1" (typo).

6.

": Liquids and Gases Tech. Spec change 6.9.1.9 to 6.9.1.6 and clarify surv'll. req.

7. "

": Direct Radiation Tech. Spec. surv'11. rec., clarify skyshine as being from plant and rad storages.

8. Under PROCEDUREi change "x10 "" notation to "E:p" notation, throuchout.

9. "

" :1.Licuid Effluents 1.a. def'n. C'7, change "and" betveen RE16 and RE23 to "or".

. 10.

" " :" Licuid Ef fluents 1.a. , def'n F , footncte "1", change rs=

(. section "11.2.7." to "11.2.6."C

" :" Liquid Effluents 1.c.1), def'n P9C's , change "are" tc " area" 11.

after " unrestricted" (typo).

12. "

" :" Liauid Effluents 1.c. 2), def'n k: 3, change "and" to "to the" before "radionuclide".

13. " "

" Liquid Effluents 1. c. 4), def'n ku , change "PE23" to "RE16" and "and" to "to the" before "radionuclide".

14

" " : " Liquid Effluents 1. d. 1), add end 1st sentence "...scurces (max. default flowrate).

15.

" :" Liquid Effluents 1. d. 1), a), delete "(max flowrate)" after

" tanks".

16.

" :" Liquid Effluents 1. d. 1), b), add "both units" between

" blowdown" and "(150 gpm)".

17.

" :" Licuid Effluents 1. d. 2), delete "I-131" in second sentence.

18.

" " :2. Gaseous Effluents, 2., introductory paragraph,'Pange

" ingredients" to " constituents".

19.

" Gaseous Effluents, 2. a. 2), def'n. D"'., change "all" tc "each of" after " calculated for",

20.

" Gaseous Effluents, 2. a. 2), def'n. Dg , change "all' to "each of" after " calculated for".

21.

" " :" Gaseous Effluents, 2. a. 2), def'n, (X/0), change "all" to "each of" after " average".

22.

" " :" Gaseous Effluents, 2 wherever reference is made to a paragraph further ahead or back in the text with just the paragraph, e.g. "2)", replace with the corplete part, section and paracraoh location, i.e."2. h. 2)", etc.

69-10733-1 11/82 (50) PACIFIC GAS AND ELECTRIC COMPANY PAGE 3 CF 5 OIABLO CANYON POWER PLANT PROCEDURE HISTORY CONTINUATICN SHEET REV. 7 di **-

PROCEDURE NO. CAP A-8 DESCRIBE CHANGE (S)/ REASON FOR CHANGE:

23. Under PROCEDU E:2. Gaseous Effluents 2. a. 3), replace " tissue dose to reac" with "... tissue dose to real...".

24

" ":" Gaseous Effluents 2. a. 3), replace "6.9.1.9" with "6.9.1.6".

25. "

":" Gaseous Effluents 2. a. 3), def'n Dd , replace "all" with "each of the" before " candidate".

26. "

":" Gaseous Effluents 2. a. 3), def'n Dsk , replace "all" with "each of the" before " candidate".

27. " ":" Gaseous Effluents 2. a. 3), def'n (X/0), replace "all" with "each of the" before " candidate". y 2E. ":" Gaseous Effluents 2. a. 3), def'n. 0(, spelling " Rad /Che "

instead of " Red /Cher.".

29. " ":" Gaseous Effluents 2. a. 3), insert an assortrent of adjectives, adverbs, and prepositions to clarify.

30.

" :" Gaseous Efflurnts 2. b., clarify and strearline awkward wording.

31

" ":" Gaseous Effluents 2.c, clarify and strea-line awkward g

wording, for example,1st paragraph 4tn senter.ence insteac of "...because of random wind and...", should read

...because random windofwith.gher hi " probability and the fact that the

32. "

" :" Gaseous Effluents 2, c., spelling correction 2nd paragrach, 4th sentence ". . . meat on his properly. . ." to ". . .reat on his troperty probably...".

33. " " :" Gaseous Effluents 2. c. 4), 3rd senter.ce, change "interr.al" to " external", add " external" after " ground plane", and

" internal" after " inhalation". Also, Change "but" to "and".

34

" :" Gaseous Effluents, 2. c.,1st rain paragraph past 6),1st sentence, delete "... organ doses and sum over.. ." and reolece with "... dose...". In 2nd sentence chance " entities" to

" pathways". In 3rd sentence add " week" between "any" and

" month".

35. "

" :" Gaseous Effluents 2. d., subtitle section as "Gasecus Effluents contingency levels for real-tire calculation..."

instead of " Contingency levels...." Also, indent for paragraph.

36. " " :" Gaseous Effluents, 2. d., lead paragraph last sentence, change "is" between"...these: and "the met tower" to

" concerns".

37. " " :" Gaseous Effluents 2. d. 1) thru 4) caps on " Unavailability" (1st letter). Also add "where possible" in 4) after " hand".

5 PAGE 4 CF 69-10733-1 11/82 (50) PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT PROCEDURE HISTORY CONTINUATION SHEET v

PROCEDURE NO. CAP A-8 REY. I' h '

DESCRISE CHANGE (S)/ REASON FOR CHANGE:

35. Under PROCEDURE:2. Gaseous Effluents, 2. e., add " Gaseous Effluents" ahead cf

" Alarm Setpoints" in subtitle.

39.

" ":" Gaseous Effluents, 2. e. 1)'s footnote "1" add "rax." after

" site dose".

E.

' ":" Gaseous Effluents, 2. e.1) clarify or streamline awkward wording (eg. "First the release rate..." instead of "the release rate..." and "then" added before " calculate" in 3rd pa rag ra ph . ,

41. " . 1) change ..."Fy is 109250 ft /rin"

":" Gaseous te ..."FyEffluents, 2. g/

is 220000 ft min" and change "(one au> bldo far and one fuel bldg ...)" to "two aux bldg fans and two fuel bldg ...)"

":" Gaseous Effluents, 2. e.1), in def'n"k", add " gross" between 42.

"the" and " channel".

43. " ":" Gaseous Effluents, 2. e. 3), 1st paragraph, last sentence, change "two-year" to "two unit".

44 " ":" Gaseous Effluents, 2. e. 3), replace (0.33) in expressicr.

( (17) with "R".

45. " ":" Gaseous Effluents, 2. e. 3), added def'n for "R".

(R = 0.32, for most of the tire assuming inlet terp is

~ 490*F)".

46. " ":" Gaseous Effluents, 2. f., subtitle " Gaseous Effluents Cose Projections" instead of " Dose Projections".

47. " ":" Gaseous Effluents, 2. f., clarify wording and detail core specifically.

48. " ":3. Direct Radiation, add subtitle anc make spelling corrections.

49. " ":" Direct Radiation, Equations (26) and (27), place nissing tire derivative ' dot' (".") over "0"'on R.H.S.

50. "

": Table 1, add dose factor data-all organs for for Be-7.

51 .

": Table 1, correct. dose factor data on GI-LLI for Cr-51 to 1.40E03, 52.

": Table 1, correct dose factor data on Kidney for Cu-64 to 5.40E02,

53. "

. ": Table 1, correct. dose factor data on liver for RB-89 to 1.19E00.

54

": Table 1, correct dose factor data on bone for Sr-92 to 3.48E01.

55.

": Table 1, correct dose f actor on thyroid and kidney for Te-129 to 1.95E00 and 1.07E01.

56. "

": Table 1, correct dose factor data on GI-LLI for Ba-141 to 1.80E-09.

69-10733-1 11/82 (50) PACIFIC GAS AND ELECTRIC COMPANY PAGE 5 0F 1 DIABLO CANYON POWER PLANT PROCEDURE li! STORY CONTINUATICN SHEET PROCEDURE NO. CAP A-8 REV. F ^S.

DESCRIBE CHANGE (S)/ REASON FOR CHANGE:

57. Under PROCEDURE:3. Table 1, correct "Zr-65" to "Zn-65".

58.

" ": Table 1, correct "Ce-142" to "Ce-143".

59.

" ": Table 2, add dose factor data - all organs for Be-7.

60.

": Table 2, correct Br-85 GI-LLI dose factor to "No Data".

61. "

": Table 2, correct Y-90 T-Body dose factor to 2.58E-10

62. " ": Table 2, correct Ba-140 T-Body dose factor to 1.33E-06

63. "

": Table 2, correct Cs-134 to Cs-138 64

" ": Table 3, add dose factor data for Be-7.

65.

" ": Table 5A thru 50, correct dose factors principally for Sr-90/Y-90, Y-91 and Cd-115e/Cd115.

66. "

": Table SP, correct all dose factors.

67. " ": Table SA thru SP, delete all dose factors for all orcans for radioisotopes with half lives less than 8 days, excepting I-133. *'s 65., 66.,

65.

": Tables 6A and 65 -- corrections same as change

(. and 67.(above).

69.

" ": Delete Table 7C

70. " ": Delete Table 78

PAGE 5 0F 5 69-10733-1 11/82 (50) PACIFIC GAS AND ELECTRIC COMPANY 01ABLO CANYON POWER PLANT PROCEDURE HISTORY CONTINUATICN SHEET PROCEDURE NO. CAP A-8 rey. F 1,"

DESCRIBE CHANGE (S)/ REASON FOR CHANGE:

57. Under PROCEDURE:3. Table 1, correct "Zr-65" to "Zn-65".

58.

" ": Table 1, correct "Ce-142" to "Ce-143".

59.

" ": Table 2, a'dd dose factor data - all organs for Be-7, 60.

" ": Table 2, correct Br-85 GI-LLI dose factor to "No Data".

61. " ": Table 2, correct Y-90 T-Body dose factor to 2.58E-10

62. "

": Table 2, correct Ba-140 T-Body dose factor to 1.33E-06

63. " ": Table 2, correct Cs-134 to Cs-138 64

": Table 3, add dose factor data for Be-7.

65. "

": Table SA thru 50, correct dose factors principally for Sr-90/Y-90, Y-91 and Cd-115m/Cd115.

66.

" ": Table 5P, correct all dose factors.

67. " ": Table SA thru SP, delete all dose factors for all orcans for radioisotopes with half lives less than 8 days, excepting I-133.

68. "

": Tables 6A and 6E -- corrections same as change s's 65., 66.,-

and 67.(above).

69. " ": Delete Table 7C

70. "

": Delete Table 7/p ,tp

2 File 206.2 85-212 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT

( PLANT STAFF REVIEW COMMITTEE Plant Superintendent's Office Minutes offa Special Meeting ,

November 8, 1985 Regular Members Present:

R. Patterson, Assistant Plant Manager / Plant Superintendent (Acting Chairman)

.J. V. Scots, Chemistry and Radiation Protection Manager C. L. Eldridge, Quality Control Manager (Secretary)

S. R. Fridley, Senior Operations Supervisor (J. A. Sexton's Alternate)

J. M. Giscion, Assistant Plant Manager / Technical Services Special Members Present:

W. E. Coley, Resident Startup Engineer W. T. Rapp, Chairman, Onsite Safety Review Group D. A. Taggart, Acting Directo.r Quality Support Guests:

S. G. Banton, Senior Power Production Engineer T..L. Grebel,. Regulatory Ccepliance.Superviser-i M.~P. Hanrahan, Senior Instrument and Controls Maintenance Superviser

.J. C. Nclan, Power Producticr. Engineer E. L. Peterson, Instrument and Controls Maintenance General Foreman L. F. Womack, Engineering Manager The Acting Chairman -- the quorum requirement satisfied -- convened the reeting at 1:30 p.m. to review the following:

1. Review cf Temporary Procedure Changes Startuo Test Procedures 2.4A1 Condensate Booster Pumps Initial Start (Unit 2), Rev. G. Changc 1

~

2.8 Condensate System Preoperational Test (Unit 2), Rev.1, Change 22 16.7 Seawater Evaporator System Initial Flush (Unit 2), Rev.1, 1 Change 9 38.1 Automatic Reactor Ccntrol (Unit 2), Rev. O, Change 2 40.0 Startup Program Master Document (Unit 2), Rev.1, Change 5 i

>4 7

' .i 3

k i

}

,i

DC0481 1 . . ..

Plant Staff Review Comittee Minu.tes '85-212 November 8, 1985 Page 2 of 4 f

1. Review of Temporary Procedure Changes (Continued)

Startup Test Procedures (Continued) 43.1 Load Swing Test (Unit 2), Rev. 2, Change 1 43.1 Load Swing Test (Unit 2), Rev. 2, Change 2 The PSRC has evaluated the above procedure changes and determined that they i do not constitute a change to the facility or procedures as described in the FSAR or a test or experiment not described in the FSAR. Therefore,.a l written safety evaluation per 10CFR50.59 is not required. Furthermore,

! these procedure changes do not present unreviewed safety questions, changes to the plant's Technical Specifications, or unreviewed environmental

! questions.

4

2. Review of Plant Procedures i Ocerating Procedure AP-8 Control Room Inaccessibility, Rev. 2 ,

! Emergency Precedure MC _ Hazardous Waste Management Contingency Plan, Fev. 4 Chemical Analysis Precedures 1 .

A-5 Liquid Raowasta Discharge Management, Rev. 4 A-E Off-Site Dose Calculations, Rev. 3 B-15 Operation of the Liquid Scintillation Counter Mcdel 4530, Rev. O D-11 Tritium in Liquid Samples, Rev. 2 2

0-17 Tritium in Airborne Samples, Rev. 1 The PSRC has evaluated the above procedures and determined that they do not j constitute a change to the facility or procedures as described in the FSAR cr a test or experirent not described in the FSAR. Therefore, a written

safety evaluaticn per 10CFR50.59 is not required. Furthermore, these precedures do not present unreviewed safety questions, changes to the plant's Tecnnical Specifications, or unreviewed environmental quesstions.

1, .

]

I*

4

'i!

,e l .

1 -- ar e u _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ,

Plant Staff Review Comittee Minutes65-212 November 8, 1985 Page 3 of 4

(

3. Review of Design Changes

a. DC1-0-J-29946, " Post-LOCA Sampling System" This change replaces some RCS Post-LOCA Sanpling System equipment due to poor performance and incompatibility with other electronic compenents.

b. DCO-E-M-31394R2, " Makeup Water" The subject design change installs and connects a rental seawater reverse osmosis system. Revision 2 of this modification (1) extends the seawater tank drain line, (2) connects the pemeate tank overflow to the brine line, (3) adds a 2" flush connection on perreate purp discharge, anc (4) adds vents to the brine line. The purpose fc tFfs changc is to provide an additicnal reliable scurce of makeup water te suppcrt the startup cf Unit 2 while Unit 1 is in cperat1cr..

c. DCl-E-C-31459, "Moncrail MS 10-1 (AF-100-08)"

The above design change accs sway bracing te rancrali beam MS 10-1 tc lir.it the unnecessary moverents of the r.oncrail bear, and irprove the i

structural integrity cf the ncncrail to reet the IEC reqsiremees ir, NUREG-0612.

c. DC1-E-M-31561, " Diesel Ergine Generaters" DC2-E-M-32562, " Diesel Engine Generetcrs" The above changes acc roct valves to expansion tank sight glasses, Ll76 anc LI77, to allow for the cleaning of sight glass on the levei indicator withct t draining the ccolant; thus recucing c wn tire ce diesel engine generators.

NOTE: The PSRC approved DCl-E-N-31561 contingent upcn it being icentical to DC2-E-M-32562.

e. DCO-E-M-33128R1, " Makeup Water" This mcdification extends the brine discharge line frer the screen wash discharge to the ASW purp suction in order to dilute ionic cancentration. Revision 1 of tnis DCh ecos construction cetails.

Af ter some discussion and based upon the written safety evaluation of the design changes listed, the Comittee reconnends approval by the Plant Marager and work may proceed. The Committee believes no unreviewed safety questions as defined in 10CFR50.59 are created by these changes.

t i

i I

i nrnaA1,,,ft, ,, ,

Plant Staff Review Coninittee Minutes85-212

- November.8. 1985 Page 4 of 4 j 4 Review of PSRC Licensing Document Interpretations The Committee approved the attached Licensing Document Interpretations, 85-08, " Technical Specification 4.6.1.3" and 85-09, " Technical

! Specification 3.3.1 Table 4.3-1 item 20.b".

b The meeting adjourned at 2:30 p.m.

~

> -) /*

2' C. L. EL RIDG Secretary CLE:dc Attachments i !

,. DA &

~ -

,- R. vii . TcR5ut,'

Assistant Plant Manager / Plant Superintendent

, Cerr.ittee Charter's Standard Distribution I,

l I~

~i

l. NOV 2 71555 :

4

=-

0 S ,

,t I

i.

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.,,,%.-er,- . -- w n m...g. , .w,-,--.-,.%.- e., _ - - - , -. .- , - ,,,,-.-,.,m,._-- _ _ _ - - , , - - , -- ,s.,

File 206.2 11/7/85

[ PSRC Meeting No.85-211 e l

ATTACHMENT 1 P. I i V

Temporary Procedure Changes recommended by PSRC for Plant Manager's approval: i Startup Test Procedures.

$ 4.1 Calibration of Steam anc Feedwater Flow instrumentation at Power (Unit 2), Rev. 1, Change 5

7.5 Reactor Coolant System Flow Measurement (Unit 2), Rev. O,

Change 7

16.12A3 Preoperational of Makeup' Water Pretreatment System (Unit 1),

Rev. 1, Change 4 J 16.12A3 Preoperational of Makeup Water Pretreatment System (Unit 1),

Rev. O, Change 5 19.2.5A9 Flush and Preoperational Equipment Drain Receiver System (Unit 1), Rev. O. Change 14 l 28.19 Isophase Bus Temperature Test (Unit 2), Rev. O, Change 2 i

~

4' 38.2 Automatic Steam Generator Level Control (Unit 2), Rev. O, I'

Change 4-40.0 Startup Program Master Document (Unit 2), Rev.1, Change 4

'~

41.8 Dynanic Automatic Steam Durp (Unit 2), Rev. O. Chante 9

42.2 RCCA Pseudo Ejection and RCCA Above Bank Position Measurements

(Unit 2), Rev. O Change 1 42.2 RCCA Pseudo Ejection and RCCA Above Bank Position Measurements (Unit 2), Rev. O, Change 2 42.5 Statepoint Data Collection (Unit 2), Rev. O, Change 4 4

Operatine Procedures i

J-10:11 Instrument AC Systen - Alignment verification (Unit 1), Rev. 4, 11/6/85 L-4 Normal Operaticn at Power, Rev. 7, 11/1/25 Electrical Maintenance Procedure E-54.2 High Voltage Testing'cf Electrical Equipment, Rev. 5, 10/24/E5 i Surveillance Test Procedures ;

I' I-1A Routine Shift Checks Required by Licenses (Unit 2), Rev. 1, 10/30/85 1-1A Routine Shift Checks Required by Licenses (Unit 2), Rev. 1, i 11/5/85

, 1-1E Analog Channel Operational Tests Required Prior to Each Reactur Startup, Rev. O, 11/7/85

. 1-1287 Calibration of Steam Flow Transmitters, Rev. 5, 11/4/85 ,

'i I-53 Channel Calibration First Stage Pressure Channel 505, Rev. 6, l 11/5/85

i R-3A Use of Flux Mapping Equipment, Rev. 4, 10/29/85 M-16P Continuity Testing of Equipment Slave Relay Actuating Circuitry, l! Rev. 7, 11/5/85

,I ( t I

l .

! DC0481 7 _.

File 206.2 11/7/85 PSRC Meeting No.85-211

ATTACHMENT 2

(

Procedures recommended'by PSRC for Plant Manager's approval:

1 Startup Test Procedures

' 2.5A36 Condensate, Feedwater, Main Steam, and Auxiliary Feedwater System i Flush (Ur.it 2), Rev. I

? 16.9Al Seawater Evaporator Distillate Demineralizer Preoperational Test

. (Unit 1), Rev. 0' 17.11 Circulating Water System Demusseling Test (Hot Condition)

(Unit 2),-Rev. 1 Nuclear Plant Administrative Procedures

[.

C-20 Independent Verification of Calculations Important to Safety, Rev. 1

~

C-201 General Requirements for Chemical and Radiochemical Control Programs, Rev._5 L

j Administrative Procedures !

t

. C-951 Supplement I to Nuclear Plant Adninistrative Procedure Sealeo '

a Valve, Rev. 7

. C-253 Process Control Program, Rev. 2 j Ooerating Procedure 1

G-5:I Spent Resin Transfer Systen CVCS, SFP, Evaporator Demineralizer (Q 1 Resin Transfer to SRST 0-1 (0-2), Rev. 2 i it

'. Emergency Procedures l R-6 Radiological Fire, Rev. 9

,; M-6 Nonradiological Fire, Rev. 11

Electrical Maintenance Procedures

!3 E-53.9 Limitorque/Rotork Motor Operator Preventive Maintenance, Rev 4 1 E-54.8 Calibration of Wire Strippers and Crimpers, Rev.1 i E-57.3 Heat Trace Cable Testing, Rev. I t E-61.1 Calibration of the Main Generator Voltage Regulator Power Systen Stabilizer, Rev. O

. i

l Mechanical Maintenance Procedures ij .

M-51.8 Limitorque Valve Operator Disassembly Inspection Maintenance and iji, Reassembly, Rev. 7 M-53.2 Calibration of Micrometer Calipers, Rev. 2 l l

s i

,i .

' '?""i . "T- _ _ _ . 3 ~i'# _,.l~~1._,_,______.,

NUMBER CAP A-8 ySyG. Pacific Gas and Electric Company REVISION 3 DEPARTMENT OF NUCLEAR PLANT OPERATIONS 1 AND 2 I

DIABLO CANYON POWER PLANT UNIT NO(S)

CHEMICAL ANALYSIS PROCEDURE OFF-SITE DOSE CALCULATIONS MLE lMPORTA,y f TO APPAOVED SAFETY PLANT MANAGER DATE IMPORTANT TO SCOPE ENVIRONMENTAL QUAL!TY This procedure describes the methodology for the following:

Effluent Technical Specification Implements Type T.S. Surveillance Requirement Liquids 4.3.3.9.1 Detemination of alarm / trip set- 10 CFR20, App.8, points for RE-18, RE-23, RE-3 Table II, Col. 2 and RE-16 Gases 4.3.3.10 "eterTnination of alam/ trip 10CFR20, App.B.

2etpoints for RE-22. RE-14A, 14B Table II, Col. I and RE-27 Liquics 4.11.1.1.1 Pre-release analyses of effluents 10CFR20, App. 5, Table II, Col. 1 4.11.1.1.2 Post-release analysis of effluents ._

Liouios 4.11.1.2 Dose caiculations 10CFR50. App. I Licuids 4.11.1.3.1 Dose projections 10CFR50, ADD.I Gases 4.11.2.1.1 Dose rate calculations, Noble 10CFR20, App. B, Gases, Total Body and Skin Table II, Col.1 Gases 4.11.2.1.2 Dose rate calculations, Iodines, 10CFR20 App. 5, Particulates,and Radionuclides Table II, Col. 1 other than Noble Gases, per organ, per age group Gases 4.11.2.2 Noble Gas Air Dose Calculations 10CFR50, App. I Gases 4.11.2.3 Iodines, Particulates, and Radio- 10CFR50 App. I nuclides other than Noble Gases Organ Dose' Calculations per aga group Gases 4.11.2.4.1 Noble Gases.lodines, 10CFR50, App. F l Particulates, and Radionuclides other than Noble Gases, Dose Projection Liquios 4.11.4 and Cumulative Dose from: Liquids; 40CFR190 and 6.9.1.6 Noble Gases; Iodines; Gases Particulates; and Radionuclides other than Noble Gases per age group- per organ Direct 4.11.4.2 Direct Radiation Dose Rate and 40CFR190 Radiation Dose Calculations to unrestricted areas due to plant and high radwaste storage sky-shine.

DCD467 III

DiA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[h0N DATE 9/14/85 PAGE 2 0F 71 TITLE OFF-SITE DOSE CALCULATIONS The calculational methodology for doses are based on models and data that make it unlikely to substantially underestimate the actual exposure of an individual through any of the appropriate pathways.

Tables containing the values for the various parameters used in these expressions are also included. This procedure, and any changes thereto, requires PSRC review.

DISCUSSION This procedure is used in support of the portion of the Appendix A Technical Specifications that deals with routine radioactive liquid and gaseous releases to the unrestricted area. Limits are based on the dose comitment to a member of the general public related to the release of radionuclides through either direct exposure (i.e.,

submersion in a cloud or inhalation of radionuclides or indirect exposure [i.e., via a food pathway such as milk, meat, vegetable or fish]).

PROCEDURE

1. Liquid Effluents

a. Dose calculation (T.S. 3.11.1.2).

The dose contributions to the total body and each individual organ (bone, liver, thyroid, kidney, lung and GI-LLI) of the maximum exposed individual (adult) for the total time period:

m I at ,g shall be calculated for all radionuclides t= 1 identified in liquid effluents released to unrestricted areas using the following expression:

n m D

=

I [A 9 (I at tCit Fg)]

i=1 t=1 (1) where D = The cumulative dose to the total body or an organ T

T from the liquid effluents for the total time period, m

I at , in mrem g

t= 1 DC0467 2!!

otAsLO CANYON POW 5R PL[NT UNIT NO(S) NUMBER CAP A-8 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 3 0F 71 TITLE OFF-SITE DOSE CALCULATIONS A

ir = Composite dose parameter for the total body or an organ r of an adult for nuclide i, for salt water site, in mrem /hr per pCi/ml:

Aj = (1.14ES)(2184f + 58,j) 0F3 ,

(refer to Table 1) 0F 4*

= The adult ingestion dose factor to the total body or any organ i for each identified radionuclide i, in mrem /pCi (Refer to Table 2)

B jf = The bicaccumulation factor in fish for each identified radionuclide i, in pC1/kg per pCi/ liter (refer to Table 3).

B 99

= The bicaccumulation factor in invertebrates for each identified radionuclide i, in pCi/kg per pCi/ liter (refer to Table 3).

1.14E5 = Units conversion factor (1.0E6 pCi/uci)(1.0E3ml/l) 8760 hr/yr at g = The length of the tth time period over which C an hddrs.d F, are averaged for liquid releases in C = The concentration of radionuclide i in liquid iI effluent passing thru RE-18, RE-3, RE-16 or RE-23 (or from any liquid stream entering the circulating water discharge) during the time period at tfrom any liquid release in pCi/ml.

F =

A The duringnear anyfield average liquid dilution effluent factor release. of C 'as Defineb the ratic of the maximum liquid waste flow passing an effluent monitor during release to the product of the averaged measured liquid waste flow from the site discharge structure to unrestricted receiving waters and any applicable factor for the mixing effect of the discharge structure. The applicable factor for nenas:7 1rr

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 4 0F 71 TITLE OFF-SITE DOSE CALCULATIONS the mixing effect of the discharge structure is 5 from the point of release to the organism or dose point.1 Therefore, p , I undilated waste flow rate i T circulating water flow rate 21 = The adult usage factor for fish in kg/yr (from Table E-5 in Regulatory Guide 1.109).

5 = The adult usage factor for other seafood (i.e. , invertebrates) in kg/yr (from Table E-5 Regulatory Guide 1.109).

b. Maximum Permissible Concentration (MPC) calculation (T.S. 3.11.1.1.)

1) The MPC for the identified mixture of radionuclides in liquids is calculated as follows:

n I C Il i=1 MPC t n C,, (2)

MPC jg i=1 where:

MPC = The unrestricted area total MPC for the t

particular mixture of identified radionuclides in uCi/ml.

MPC = The MPC in water for an unrestricted area for Il radionuclides i, in uCi/ml, from 10CFR20, Appendix B, Table II, Column 2.

1 Refer to the FSAR, Section 11.2.8, " Dilution Factors".

nF0467 4TT

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[h [ b8 DATE 9/14/85 PAGE 5 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

2) The overall MPC for a combination of discharges (e.g.,

simultaneous discharge of a batch of liquid radwaste, discharge of steam generator blowdown, discharge of oily water separator via the turbine building sump, and discharge of condensata demireralizer regenerate waste also via the turbine building sump) is calculated by reapplication of equation (2) using the total concentration for the pathway and its associated MPC:

n I fCj MPCoverall " (3) j=1 MPC) where:

MPCoverall = The unrestricted area MPC for the current radionuclide mixture for concurrent discharges in Ci/ml.

W C = The total activity concentration for the d

individual stream in "Ci/ml.

MPC = The MPC for the individual stream d detemibed from equation (2) in "Ci/ml.

f d

= The ratio of an individual discharge pathway flow rate to the sum total of all individual undiluted pathway flow rates.

c. Alarm setpoint deteminations Alarm setpoints are detemined from the expressions in this section. These expressions enable detemination of the appropriate maximum alarm setpoint for each liquid effluent pathway (i.e., liquid radwaste system, steam blowdown and turbine building sump effluents)generatortaking into account concurrent discharges. The alam setpoints should normally be established at levels just above the value corresponding to the nomal concentrations observed for the individual systems (but in no case above the maximum calculated alarm setpoint) for early warning of off-normal effluent concentrations.

DCOM67 SII

DIASLO CANYON POWER PLANT UNIT NO(S)

NUMBER CAP A-8 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 6 0F 71 TITLE- 0FF-SITE DOSE CALCULATIONS

1) Liquid radwaste system discharge monitor, detector RE-18 The high alam setpoint for RE-18 is detemined as follows:

ke l MPC tb CF22 CF33 CgFu CF5 (C F3i 5 Ri e<_Bl e + F C N MN "E b

kt 1 2 t

3 4 5_

where:

Rgi = The high alarm setpoint for RE-18,in cpm.

Bel = The background count rate of RE-18,in cpm.

kel = The conversion factor for RE-18 relating the channel count rate to the radionuclide l concentration, in cpm per uCi/ml.

F b

= The undiluted liquid radwaste batch discharge flow rate, in gpm.

F c

= The total dilution water flow rate, in gpm.

with:

F =

e Fb+Fi + F 2.+ F3 + Fu + F5+F F = Main or Aux. Circ. (sea or saltwater) flow l rate, in gpm.

l MPC tb

= Unrestricted area total MPC for the particular radionuclide mixture in a batch discha rge.

C b

= The total radionuclide concentration in the liquid effluent for the particular batch discharge that may be in progress in uCi/ml.

l C3

= The total radionuclide concentration in the i liquid effluent from the Unit I steam generator blowdown tank, in pCf/ml.

l DC0467 6II i

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 VfSON DATE 9/14/85 PAGE 7 0F 71 TITLE OFF-SITE DOSE CALCULATIONS F3

= The Unit 1 steam generator blowdown tank effluent flow rate, in gpm.

MPC = Unrestricted area total MPC for water in the 1

Unit I steam generator blowdown tank effluent, in uCi/ml.

C2

= The total radionuclide concentration in the liquid effluent from the Unit 2 steam generator blowdown tank, in pCi/ml.

F2 = The Unit 2 steam generator blowdown tank effluent flow rate, in gpm.

MPC = Unrestricted area total MPC for water in the t2 Unit 2 steam generator blowdown tank effluent, in uCi/ml.

C3

= The total radionuclide concentration in the liquid effluent from the oily water separator, in uti/ml.

= The oily water separator effluent flow rate, F3 ia gpm.

MPC = The unrestricted area :ntal MPC for water in t3 the oily water separator effluent, in pCi/ml.

Cu = The total radionuclide concentration in the liquid effluent from the Unit 1 Cond. Demin.

Regen. System Waste Transfer Discharge Line, in uCi/ml.

Fw = The Unit 1 Cond. Demin. Regen. System Waste Transfer Discharge Line effluent flow rate, in gpm.

MPC t"

=

The unrestricted area total MPC for water in Unit 1 Cond. Demin. Regen. System Waste Transfer Discharge Line effluent, in uCi/ml.

Cs

= The total radionuclide concentration in the liquid effluent from the Unit 2 Cond. Demin.

Regen. System Waste Transfer Discharge Line, in uCf/ml.

DC0467 71!

otAsto CANYON POWER PLANT UNIT NO(S) .

NUMBER' CAP A-8 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 8 0F 71 TITLE OFF-SITE DOSE CALCULATIONS Fs

= The Unit 2 Cond. Demin. Regen. System Waste Transfer Discharge Line effluent flow rate. l in gpm.

MPC = The unrestricted area total MPC for water in ts Unit 2 Cond. Demin. Regen. System Waste Transfer Discharge Line effluent, in uCi/ml.

2) Steam generator blowdown tank liquid effluent monitor, detector RE-23.

The expressions for the high alarm setpoint for RE-23 have the same fom as equation (4) with permutation of appropriate terms.

~

k MPC I/C bb F CF CF CF CF 23 '1 t

' 22 33 4 4 5 5 Cl (MPC R <B + F (5) 23,1 23,1 p tb MPC t

MC g MN t

" t 2 3 4 5-and

~

k MPC CF CF CF CF R <B +

3 t, [C Fbb

, i i, 33 4 5 ,

5s C

2 3,r 2 3,2 y (MPCtb MPC MPC g MPC MPCg/

_ t t 1 3 4 5-where:

C b

= The total radionuclide concentration in the liquid effluent for the particular batch discharge that may be in progress in uCt/ml.

R 23 = The high alarm setpoint for RE-23,in cpm.

= The background count rate of RE-23,in epm.

B23 k23

= The conversion factor for RE-23 relating the channel count rate to the radionuclide concentration, in epm per pCi/ml.

The extra subscripts ",1" and ",2" refer to the effluents of Unit 1 and Unit 2, respectively.

1 1

DC0467 811

NUMBER CAP A-8 DIA8LO CANYON POWER PLANT UNIT NO(S) ,

1 AND 2 REVISION 3 DATE 9/14/85 PAGE 9 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

3) Oily water separator ifquid effluent monitor, detector RE-3.

~ ~

k MPC CF CF CF CF CF \

3 t bb 11 22 4 4 55 1

' * (}

R <B + F C~ I F3 F 3 MPC b

MPC t

" t t t/

~ "

1 2 4 5 where:

R3 = The high alarm setpoint for RE-3, in cpm.

83 = The background count rate of RE-3, in cpm.

k3

= The conversion factor for RE-3 relating the channel count rate to the radionuclide l concentration, in epm per uCi/ml.

4) Condensate Demin. Regen. Syst. Waste Transfer Discharge for Unit 1, detector RE-16

~

k MPC CF CF CF CF

[C Fbb p

16,1 t 11 22 33 55

{(8A) 16,1 16,1 F5 (MPCtb MPC t t

" t

" t )

1 2 3 5 Condensate Demin. Regen. Syst. Waste Transfer Discharge for Unit 2. detector RE-16

~

k MPC CF CF CF CF

'* ' [C F

R <B + 5 F * * * (00) 16, T" 16,2 F5 C~l(MPC MPC MPC " "

tb t t t t 4

~

- 1 2 3 where:

Rsi = The high alarm setpoint for RE-16,in cpm.

Bsi = The background count rate of RE-16,in cpm.

DC0467 9II

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[N ON DATE 9/14/85 PAGE 10 0F 71 TITLE OFF-SITE DOSE CALCULATIONS k is = The conversion factor for RE-16 relating the channel count rate to the radionuclide concentration, in cpm per uCi/ml.

Again, the extra subscripts ",1" and ",2" refer to the effluents of Unit 1 and Unit 2, respectively,

d. Dose Projection (T.S. 4.11.1.3.1)

Dose projections for the categories of csiculated total body exposure and organ exposure are made at least once per 31 days. The period over which projections are made is 31 days.

The purpose of the projection is to determine appropriate L treatment of liquid radioactive materials in relation to maintaining releases "as low as reasonably achievable".

Projections will nonnally be made on the last working day of each month with attention to the Technical Specification frequency requirement contained in Section 4.11.1.3.1. l The projected dose is calculated by application of equation

(!). The following guidance is provided for selecting appropriate values to use in equation (1).

1) Estimation of at g Estimate the planned release volume for the next 31 day period from each of the following sources (max. default flowrate),

a) Chemical Drain Tanks (26 gpm).

b) Laundry Waste Tanks (13 gpm).

c) Floor Drain Receiver Tanks (35 gpm),

d) Waste Concentrator Condensate Tanks (60 gpm),

e) Equipment Drain Receiver Tanks (36 gpm).

f) Steam Generator Blowdown, both units. (150 gpm).

g) Spent Regenerant Receiver Tanks (180 gpm).

DC0467 10!!

DIAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 AUMBER CAP A-8 REVISION 3 DATE 9/14/85 PAGE 11 0F 71 TITLE OFF-SITE DOSE CALCULATIONS h) Oily Water Separator (Turbine Building Sump) (100 gpm).

1) Condensate Demin. Regen. Syst. Waste Transfer Discharge Line, Unit 1, (Max 180 gpm).

j) Condensate Demin. Regen. Syst. Waste Transfer Discharge Line, Unit 2, (Max 180 gpm).

Calculate at for each of these categories using the normaloperafionsdischargeflowratefromthat subsystem by dividing the subsystem planned release volume by the product of the flow rate (in gpm) times 60 minutes per hour. If the value for the normal operations subsystem flow rate is not known, use the default value for the maximum design flow rate shown above in parentheses following each subsystem source.

2) Estimation of C 4g For C current typical values for the corresponding subsyskdmsoutlinedaboveshouldbeused. Recent composite sample analysis results should be used for radionuclides such as H-3, Sr-89, Sr-90 and Fe-55. 4

3) Estimation of F g Estimate the average plarned flow rate for the projection period of the circulating cooling water, the auxiliary saltwater, and the screen wash water supplied to the service cooling water heat exchangers and sum the three. Use this value and the subsystem flow rate (i.e. , the undiluted flow rate) estimated above (for atg ) for determining Fg .

2. Gaseous Effluents In view of the more instantaneous impact of gaseous releases, a variety of calculational disciplines is necessitated. Each calculational method (herein described in detail) is dedicated wholly to a specific Technical Specification or purpose and consequently must be totally comprehensive toward that goal even though some of the ecuations and their constituents appear repeated or very similar.

DC0467 11II

N DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 9/14/85 PAGE 12 0F 71 TITLE OFF-SITE DOSE CALC'JLATIONS

a. Noble gases (exists as a unique pathway dose and applies equally to all age groups when tissue doses are calculated). ,

1) Release rate limit of Noble Gases (Tech. Spec. l 3.11.2.1.). This discipline is primarily used in detemining gaseous effluent rad monitor high alarm setpoints and pre-batch release decision criteria. The release rate limit for the noble gases is determined in accordance with the following expressions:

n .

I (Kj ) (T M9 ) (09 ) < 500 mrem /yr (9) i=1 n .

I (L9 + 1.1Mg ) (IM) (0 ) 9<3000 mrem /yr (10) i=1 where:

Kj = The total body dose factor due to gama emissions for each identified noble gas radionuclide, in mrem /yr per uCi/m3 (fron Table 4).

L = The skin dose factor due to beta emissions 9

for each identified noble gas radionuclide, in mrem /yr per uCi/m3 (from Table 4).

M = The air dose factor due to gama emissions 9

for each identified noble gas radionuclide, in mrad /yr per uCi/m3 (from Table 4) (unit conversions constant of 1.1 mrem / mrad converts air dose to skin dose).

OC0467 12II

1 l

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 9/14/85 PAGE 13 0F 71 TITLE OFF-SITE DOSE CALCULATIONS f

(777)= The " controlling"I historical five year running average meteorological diffusion dispersing factor, in sec/m3 . This is almost always the highest amongst the past five year running averages of hourly X/Q's for the candidate dose recipient locations in any land sector area at or beyond the unrestricted area boundary (See Table 8). It is based on the five years of data just previous to the current year but always updated each cilendar year (by dropping the fifth year back and adding the current year's data - See Table 7A). X/Q's used here are __

from the Gaussian plume model (Reg. Guide 1.111), sec 3

.m.

Q9 = The release rate of radionuclide i, in gaseous effluents from all release points at the site, in uCi/sec. This-is tied to Chem / Rad Laboratory analyses and effluent rad monitor data plus flow rates (plant vent, etc.). See discussion following Qj below.

2) Air dose in unrestricted areas due to noble gases (T.S.

3.11.2.2 and T.S. 3.11.2.4).

The air dose in unrestricted areas due to noble gases released ~in gaseous effluents shall be calculated in accordance with the following expressions:

n D,7 = 3.17E-8 I M g[(X/Q)d]

j (11) n 0,3 = 3.17E-8 E Ng [(X/Q)Qj ] (12) i=1 I See the explanation on controlling in c. on page 24 DC0467 13II

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 14 0F 71 TITLE OFF-SITE DOSE CALCULATIONS where:

0 ay

= -The set of air doses due to gama emissions for all identified noble gas radionuclides, in mrad, calculated for each of the site boundary center-of-sector locations (land sector) or any other candidate hypothetical individual dose recipient in the unrestricted area during time at.

0 as

= The set of air doses due to beta emissions for all identified noble gas radionuclides, in mrad, calculated for each of the site boundary center-of-sector locations (land sector), or any other candidate hypothetical individual dose recipient in the unrestricted area during time at.

3.17E-8 = The reciprocal of the number of seconds in a year.

(X/Q) = The " set" of read time hourly average X/Q's for each of the site boundary center-of-sector (land) locations or any other candidate hypothetical individual dose recipient location in the unrestricted area (See Table 8). The first contingency level values to use in the ,

event of Met Tower Data collection failure are the set of T/U's generated for 2.a.1) above preferably from Table 7A. X/Q's used here are from the Gaussian plume model (Reg. Guide 1.111) 'sec" 3

,m, N

I

= The air dose factor due to beta emission for each identified noble gas radionuclide, in mrad /yr per pC1/m3 (from Table 4).

OC0467 14!!

CAP A-8 DIABLO CANYON POWER PLANT UNIT NO(S) ' 1 AND 2 N DATE 9/14/85 PAGE 15 0F 71 TITLE. OFF-SITE DOSE CALCULATIONS At this junction its well to point out, that aside from satisfying the Tech. Spec. 3.11.2.2, the gama air dose of 2.a.2) will always provide for all noble gases a suitably conservative (approximately + 5%) surrogate to the whole body external tissue dose to individuals.

Furthemore, "ith the exception of the extremely short half-lived nobia gases of Kr-88 and Xe-135M. (which in all probability will never dominate the isotopic constituency of any release), indirectly, the beta air i dose of 2a.2) with its Tech. Spec. 4.11.2.2 never l exceeded, will also (vis-a-vis Tech. Spec. 4.11.2.1),

ensure a safe su'rrogate for the skin dose to individuals. At all candidate dose recipient locations which are not recognized by the annual land use census as being locations for real individuals (residences, farms, etc.) but where individuals could hypothetically exist (e.g. , site boundary), then the gama and beta air dose calculations will serve as surrogates to the external whole body and skin tissue doses.

i

3) External tissue dose to real individuals in unrestricted areas due to noble gases (Tech. Spec.

4.11.4 and 6.9.1.6). The whoie body and skin doses to real individuals in unrestricted areas due to noble gases released in gaseous effluents shall be calculated in accordance with the following expressions:

n D

ab

= 3.17E-8 I K g[(X/Q)Dj] (lla) i=1 n

D 3p = 3.17E-8 I (Lj+1.1M)[(x/0)Dj]

j (12a) i=1-where:

D wb

= The N' of external whole body tissue doses frft at identified noble gas radionuclides b, .re calculated for each of the candidate usi cividual dose recipients in the unrestricted areas during period at.

DC0467 ISII

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 hM hAPA-8 DATE 9/14/85 PAGE 16 0F 71 TITLE OFF-SITE DOSE CALCULATIONS I I

D sk

= The set.of external skin doses from all identified noble gas radionuclides, in mrem, calculated for each of the candidate real !

individual dose recipients in the unrestricted area during period at.

(X/Q) = The set of real time hourly average X/Q's for each of the candidate real individual dose l recipient locations in the unrestricted area i (e.g. , residences, fanns, etc. , based on the annual land use census). (See Table 8.) The first contingency level values to use in the event of Met Tower Data collection failure l are the set of M's generated for 2.a.1) above, preferably from Table 7A. X/Q's used here are from the Gaussian plume model (Reg.

Guide 1.111). It is noteworthy here to also mention that the X/Q's calculated here are for real individuals as opposed to those hypothetical individuals of 2a.2) and include !

all off-center-line (from plume or wind direction) contributions using y '< 2a# as the consideration cut-off criteria. sec OC0467 1611

OIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 h ON DATE 9/14/85 PAGE 17 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

@9

= The average release of noble gas radionuclides in uCi over time period at. .

This eritity is a product of a release rate 0, and a release time, at. Nomally at = 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (or less) so as to be compatible with the computer's hour-by-hour "real time" dose calculation which depends on a matching.

hourly average X/Q from the Met Data. O g comes from the product of a release vent s concentration, C and flowrate F (plant vent and/or steam gendr,ator b*owdown tank vent) information during at. C results from a 3

detailed Rad / Chem Lab grad sample isotopic l analysis (perfomed weekly, monthly as a maximum, or two hourly at minimum) and scaled by the attendant effluent rad monitor's gross sensitivity k factor, for the periods at that occur out of sequence or between the grab sampling by the Rad / Chem Lab.

Should the plant vent grab samples indicate l 1ess than LLO or the rad monitors fail to register detection when a known batch release is in progress (e.g., containment purge or G.D.T. release), however short at, then if a more measurable and reliable C sampled from the batch source)9 can(directly be made and scaled by batch-to-vent flowrate ratios to give the C the Shouldtherele,ase'nitshouldbepursued.

s at be less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and within the hourly clock time X/Q period, then the X/Q for that hour will prevail for at's period. Any at with any other span (greater

< 1 hr.) than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or that overlaps the regular hourly clock time X/Q periods (wherein X/Q changes but C is constant),

then separate fractioning bf the at should occur to yield the correspondingly different dthatcoincideswiththeX/Qchanges.

j

b. Radiofodines, radioactive materials in particulate form and radionuclides other than noble gases.

DC0467 17II

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 18 0F 71 TITLE OFF-SITE DOSE CALCULATIONS In contrast to the calculational methodology just seen in 2.a. for the external doses (and dose rates) from noble gases, the methods utilized here are quite different and l more complex with the exception of the " ground plane" deposition pathway dose, which is also an external dose and similar to the noble gases (but considers only the who'e body and not the skin). Doses (and dose rates) other chan

" ground plane", delivered here are strictly internal and are segregated according to intake pathway as well as age group.

Furthermore, while noble gases (and " ground plane" I.P.T.)

essentially dose only the two organs, namely whole body and skin, here seven major radiation sensitive organs of the body are considered, namely: bone, liver, total body, thyroid, kidney, lung and GI-LLI tract. The internal intake pathways are four (aside from the external ground plane mentioned) in number, with one being inhalation, which is X/Q (diffusion dispersion factor) dependent and the other three being food ingestion pathways, which are D/Q (deposition dispersion factor) dependent (as is ground plane). The three food ingestion pathways are, namely:

foliage-to-cow-to-milk-to-human; foliage-to-animal-to-meat-to-human; and vegetable-to-human.

Finally, the four age groups considered here are respectively: infant, child, teen and adult (see Reg. Guide 1.109 or NUREG 0133). The infant i:: subjected to only the inhalation, cow-milk and ground plane pathways by the assumption of not being old encugh to consume meats and vegetables.

For each of the radionuclides, intake pathways, age groups, and organs affected, their dose (and dose rate) factors are given in Tables SA through Sp to be used in the equations which follow below.

DC0467 1811

0.Asto CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER CAP A-8 REVISION 3 DATE 9/14/85 PAGE 19 0F 71 TITLE OFF-SITE DOSE CALCULATIONS To add to the complexity and in deference to the hour-by-hour "real time" pace set by the noble gas chronology of dose archiving, the real time matching X/0's and D/Q's used here must be recalled, in " flash-back" fashion, from temporary storage by the computer. This is necessary since at the present time, and until an upgrading on the gaseous effluent iodine and particulate rad monitoring system occurs, the existing effluent rad monitors, unlike for noble gases, are not being used to scale the in between hour-by-hour periods for knowledge on isotopic concentrations in the release quantities (as is '

provided from the composite or grab sampling and analysis).

Tritium analysis plus gama isotopic analyses on iodine and particulates are normally conducted on a week-to-week basis and daily at best from spot grab sampling or composite.

sampling. Consequently, the C9 's which generate the Q4 's s

and Q9 's used in the expressions below, must be fractionated or pro-rated according to the at's when F (vent flowrate),

or X/Q, (or D/Q) change. Certainly the Strontium's (Sr-90 and Sr-89) mandate this with their quarterly composites or minimum monthly reliable sampling and analysis period.

Additionally, this facilitates dose projection requirements and their calculations. Since a " previous" period's analysisforsomespecifich'scanbesubstitutedwiththe 9

current X/Q's (or D/Q's) and later purged with the aid of the stored knowledge on these X/Q's (or D/Q's) until the analysisdatabecomesavailableforthecurrentsetofh's. 9

1) Release rate limit (T.S. 3.11.2.1.2).

This discipline is primarily used in determining rad monitor high alarm setpoints and pre-batch release decision criteria. The release rate limit for all radiciodines and radioactive materials in particulate form and radionuclides other than noble gases is determined in accordance with the following expression:

n (o)(o) W Q ] <1500 mrem /yr I (13) i=1(3)P9[ 9 i

DC0467 1911

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER CAP A-8 REVISION 3 DATE 9/14/85 PAGE 20 0F 71 TITLE OFF-SITE DOSE CALCULATIONS where:

(p) (o)

P = The dose factor for gaseous (a)j radionuclides (trailing subscript "i")

other than noble gases. The dose

. factors are based on organ (trailing superscript "(o ", age group leading subscript"(a)" and pathway leading superscript "(o "). For the inhalation inh (o) pathway, Pg ; the units are in [ mrem /yr per uCi/m3]. For the ground 9p plant pathway, P9 ; the cow-milk cm (o) pathway, P g

the meat-animal ma (o) pathway , Pg ; and vegetable pathway v (o)

P ; the units are in [m -mrem 2 /yr (a)9 per pCi/m). Refer to Tables 5A through SN and Table SP.

W = The " controlling"! historical five year running average meteorological dispersion factor for the candidate dose recipient locations in any land sector at or beyond the unrestricted area bounda ry.

W = T/Q '*sec for the inhalation pathway.

'(refer to Table 7A.)

1 See the explanation on " controlling" in 2.c. which follows.

DC0467 20!!

I NUMBER CAP A-8 ,

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 1 DATE 9/14/85 PAGE 21 0F 71 l OFF-SITE DOSE CALCULATIONS I TITLE W = IT/Q [m-2] for any food and ground plane pathway (refer to Table 78.) (See also definition in b.2) below)

The same logic for obtaining this average (both T/G and IT/6) is that as is explained in 2.a.1)'s definition on the X/ for noble gases there. Remember the values used here, in 2a.1), and seen in Table 7A come from the five year running average of hour-by-hour X/Q's archived for each of the candidate dose recipient locations (See Table 8). For all X/Q's generating the average T/6 at a real individual dose recipient location (e.g. , residence, farm, etc. ),

included are the off-center-line contributions mentioned in 2.a.3). --

Q9 = See definition under 2.a.1).

2) Doses in the unrestricted are due to radiciodines, radioactive materials in particulate fonn and radioactive materials other than noble gases (T.S.

3.11.2.3, T.S. 3.11.2.4, T.S. 4.11.4, and T.S.

6.9.1.6).

The dose to an individual from radiciodines, radioactive materials in particulate form and radioactive materials other than noble gases shall be calculated in accordance with the following expression:

(D) (o) g (0) R(o) s D = 3.17E-8 WO g (14)

(a) i=1 (a) $

DC0467 2111

N OtA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 9/14/85 PAGE 22 0F 71 TITLE. OFF-SITE DOSE CALCULATIONS where:

(o) (o)

(a)Rg

= The dose factor for each identified gaseous radionuclides (trailing subscript "i")

! other than noble gases. The dose factors here are identical to the "P " dose i factors given in the definiti$n 2.b.1).

That is, (o) (o) (p)(o)

P = R (a) I (a) I except for the " ground plane" pathway, where 9PP 4

/ 9PR 9 Refer to Tables SA through SN and Table 50.

' mrem /yr per uC1/m3 ] or lm2 mrem /yr per pCi/sec]

W = The " set" of "real time" hourly average dispersion factors for all of the candidate dose recipient. locations in the unrestricted area.

W = x/Q [sec/M3 ] diffusion dispersion factor for the inhalation pathway (Refer to definition in 2.a.2) and 2.a.3), also see 2.b.1) above).

W = D/Q [M 2] deposition dispersion factor for any food and ground plane pathway.

DC0467 22II

}

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 23 0F 71 TITLE OFF-SITE DOSE CALCULATIONS The D/0 values are extracted from Fig. 6 Reg.

Guide 1.111 for each candidate dose recipient location's downwind distance from the plant. The other variables for dependency in this are wind direction and location's arc length normal to the plant's direction. For site boundary and other hypothetical or virtual individual locations this latter is simply the sector's (22)*) arc length at its particular distance'. For real individual locations (e.g., residences and fanns) the arc length is, arbitrarily chosen as, li times the max property width normal to the plant's direction.

This arc also determines the cut off for the frequency distribution of wind directions to that particular real individual dose recipient location.

s Q4 = The average release of radionuclides, radioactive airborne particulates, and gaseous radionuclides other than noble gases in the gaseous effluents Lin uCi] over time period at. This entity is structured similarly to the definition in 2.a.2) and 2.a.3). The principle exception being, as explained above in 2.b., is that, unlike for the noble gases, these radionuclide releases do not use the attendant rad monitor to scale the C values for periods of at in between grab sambling and analysis. As explained above at 2.b., this makes for a preferred lengthy prorating or fractionation on the C g 's, which are assumed constant over the much shorter hour-by-hour at's or the at's when F (vent flowrate) or W (dispersion factor) is subject to change. The week-to-week, or month-to-month, or quarter-to-quarter (in case of the strontiurrs) composite analyses mandate this.

(p) (o)

D = The set of internal doses (plus the lone external (a) dose from the " ground plane" pathway) per pathway, per age group, per principal organ (of that age group) from all identified non-noble gas airborne radionuclides, in mrem, calculated for each of the candidate individual (real, hypothetical, or virtual - See 2.c. below) dose recipients in the unrestricted area during period at.

DC0467 23II

NUMBER CAP A-8 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 24 0F 71 TITLE . 0FF-SITE DOSE CALCULATIONS

c. Gaseous effluents' candidate dose recipients (and locations).

Much reference in 2.a. and 2.b. above, was made to the so called " candidate dose recipient" locations. These are l particular site specific geographical locations in land areas of the unrestricted area between (or at) the site boundary and a 5 mile circular perimeter around the plant site. Particular to these locations are positions where a maximum exposed individual might in all probability exist without benefit of licensee control. These are labeled candidate dose recipients simply because of the higher probability and the fact that the random wind with its meteorological dispersion makes the final decision on who, when, and how much gets dosed. For obvious reasons, the

. site boundary provides part of the set of locations.

However, the Annual Land Use Census dictates the ultimate locations. Here an extensive survey, locates the residences, farms and other institutions where real individuals may exist along with information on their occupation factors, property dimensions, and potential pathways for doses.

Conveniently the areas for these locations are divided into the 22i' land sectors between site boundary and the 5 mile outer limit. Finally, reasonableness or cormon sense probability with implicit guiding by NUREG 0543 tempers the final selection of " candidates". For example, the individual that wanders to the' site boundary daily from a nearby town only to inhale and be externally exposed is unlikely to also drink the milk from the imaginary cows at 5 miles. Similarly the child living at 41 miles in the N sector while inhaling and simultaneously ingesting cattle meat on his property probably does not eat vegetables grown on the fann in the ESE sector, and so on.

From the land use census, only the closest-to-the-plant residence per sector was selected. Since information as to the ages of the residents (or their visiting relatives) was not garnered, then conservatively all age groups must be assumed to live year-round at the residences.

Furthennore, specific to the site the following is assumed to exist:

DC0467 24II

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER CAP A-8 REVISION 3 DATE 9/14/85 PAGE 25 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

1) Meat cattle for marketing are assumed to be able to graze right up to site boundary in all land sectors.

This generates the newly defined " degraded" hierarchy of dose recipients called the " virtual" individual.

Degraded in the sense that the only, but most probable, dose received is via the meat ingestion pathway (for all age groups except infants).

2) The vegetable farm in the ESE sector while possessing virtual individuals of the type defined in 2.c.1),

above, (but for vegetables in place of meat), do indeed-have real individuals. These are migrant farm workers who in all probability spend 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per work day there with their entire family and more than likely take home vegetables grown there and cattle meat from there. For this reason, this is treated conservatively as a real individual residence for all age groups possessing meat animals and a vegetable garden.

3) While each residence is assumed to have its meat animals or vegetable gardens confined within their property boundary the one exception is the residence in the NNW sector at li miles where its meat anirals can graze right up to the site boundary in both the N and NNW sectors.

4) At the site boundary another form of " degraded" hierarchy of dose recipients is now defined, namely the

" hypothetical" individual. Degraded here in the sense that the land use census does not recognize this individual as a bonaffde real individual residing there with property to enclose meat animals, vegetatle gardens, and such. Reasonableness assumes however that this type of individual could wander daily to the site boundary and receive the external doses from the nobles along with ground plane external doses from the non-nobles and only the inhalation internal dose from the non-nobles (applies to all age groups). Here the ganrna air and beta air doses serve as a surrogate to the noble external doses.

DC0467 25I!

otAato CANYON POWER PLANT UNIT NO(S) 1 AND 2 NUMBER

CAP'A-8 REVISION 3 DATE 9/14/85 PAGE 26 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

5) Thus far the land use census indicates no milk cows within the 5 mile perimeter. However, the utility has conservatively assumed imaginary milk cows can exist at or beyond 5 miles in all land sectors for which the milk can be marketed for consumption. This then generates the third virtual individual as in 2.c.1) or 2.c.2), above, but constrained this time to only the cow-milk ingestion pathway for all age groups (generally the infant predominates).

6) Finally for all categories of individual dose recipients described above in 2.c.1) through 2.c.5),

for their respective locations, an occupational factor of one (1) is assumed with exception of the real individuals (all age groups) at the vegetable farm in the ESE sector, namely in 2.c.2), and only in the case of the noble gas, ground plane and inhalation pathways (non-noble) there. In that exception, for the external noble gas (whole body and skin) dose along with the non-noble ground plane and internal non-noble inhalation pathway doses there, a one half (0.5) occupancy factor is assumed.

In usage of the equations of 2.a. and more notably 2.b.,

when computing an individual's dose (or dose rate), it only makes sense to ultimately sum up over the individual's (any age group) dose pathways where permitted at each of the candidate dose recipient locations. It is this summing for a max over these different pathways of doses (i.e., for each age group's organs, etc.) at each location, whether during only a at, daily, weekly, quarterly or annually, that eventuclly detennines the so called controlling candidate (with max dose) and hence " controlling" location in that time period (e.g., site boundary nobles in NW sector; or nobles plus non-nobles for the real child at residence in E sector because of bone dose; or virtual-cow-mfik-infant at 5 miles in NNW sector because of thyroid dose; etc.). For reason that the meteorological conditions may change over or in between any At but most certainly between an month or quarter, then these summations of dose or (y dose week, rate) entities dictate that any of the candidate dose recipient locations can at sometime. (certainly, some month

, or some quarter) be the " controlling" (max dosed) location.

Table 8 indicates the existing land-use-census-based selection of candidate dose recipient locations and is subject to change anytime but is usually detennined annually.

DC0467 2611

NUMBER CAP A-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 27 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

d. Gaseous effluents contingency levels for "real-time" calculation of doses (and dose rates).

Normally the dose (and dose rate) information for all candidate dose recipients shall be calculated hour-by-hour, twenty-four hours per day, 365 days per year using the equations of 2.a. and 2.b. on the data gathered from the l Rad / Chem Lab, rad monitors and met tower's computer and all I perfomed on the HP-1000. In the event of temporary unavailability of certain systems feeding this " train",

certain " default" plans of calculation operation must be pursued. Most important of these concerns the met tower and l HP-1000.

1) Het tower data ("real-time" hourly averages) -

Unavailability.

Here the computer software is instructed to use the historical average met data from Tables 7.

2) HP-1000 - Unavailability Here the HP-9845 computer is instructed to take over with the use of the data from Tables 6A and 68. Since the factors for use in the equations of 2.a. (Table 4) are never the complexity of those used in 2.b. , Tables 6A and 6B represent the conservative degeneration of the dose factors of Tables 5 into the single columns of a " super" age group " critical" organ factor per pathway per nuclide. These were selected.out of Tables 5 as being the maximum factor out of the age groups and in turn amongst the organs for each pathway and nuclide.

3) Met Tower data and HP-1000 - Unavailability Here contingency level 2.d.1) and 2.d.2) are jointly pursued.

DC0467 27II

0AaLO CANYON POWER Pt ANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 28 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

4) HP-1000 and HP-9845 - W availability Calculations by hand where possible, will be conducted on the most significant nuclides sampled by the l Rad / Chem Lab along with the use of met data from Tables 7, and dose factors from Table 4 and Tables 6.

e. Gaseous effluents, alarm setpoint determinations

1) Plant vent noble gas monitor, RE-14A and RE-148 The channel high alann is to be set no higher than a count rate which corresponds to the maximum pennissible dose rate at the " controlling" locations, usually the boundary of the restricted area, which is 500 mrem /yr (250 mrem /yr-2 pint. opr.) for total bod 3000 mrem /yr (1500 mrem /yr-2 pint opr.)fory exposure skin and exposure. Each unit constitutes a release source, and each is therefore allotted one-half! the limiting condition for annual dose.

To calculate the high alarm setpoint, it is necessary to establish the release rate limit, and then working

" backwards", calculate the corresponding max concentration in the plant vent. Once this concentration is known, the corresponding count rate can be calculated using the channel sensitivity value or k, values relating count rate to isotopic activity concentration.

1 The fraction one-half is selected for convenience. Each unit's release may be proportioned differently as long as the site dose max limitations are met.

DC0467 28!!

DIABLO CANYON POWE3 PLANT UNIT NO(S)

I 1 AND 2 R ON DATE 9/14/85 PAGE 29 0F 71

^

TITLE OFF-SITE DOSE CALCULATIONS First, the release rate limit is determined using equations (9) and (10).. the more restrictive release rate being used for establishing the alarm point. Then calculate the concentrations corresponding to the limiting release rate using the expression Of Cg= mF (15) v where:

Cy = the concentration of radionuclide 1, in uCi/ml F = the flow rate in the plant vent in ft /3 min.

y 472 = a conversion constant, ml/sec per f t / 3min.

For nomal operation, the value used for F is 220,000 ft /3 min (two auxiliary butiding exhaust faXs and two fuel handling building exhaust fans in operation).

The high alarm setpoint is then determined as follows:

High Alam Setpoint, cpm < kCt + Bkg epm (16) where:

k = the gross channel sensitivity to typical mixtures, in cpm per uCi/ml (I k gC /C 9

)t i

C = the total concentration of noble gas t

activity, in pCi/ml (I C )g i

2) Gas decay tank monitor, RE-22 The high alarm setpoint for RE-22 is detemined in similar fashion as RE-14A and RC-148. The desired condition is to have RE-22 alam (and thereby trip the release isolation valve (RCV-17) at a release rate which is no higher than that required to cause alam of RE-14A and 8.

[ DC04P 29!!

DIA8tO CANYON POWER PLANT UNIT NO(S) NUMBER CAP A-8 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 30 0F 71 TITLE OFF-SITE DOSE CALCULATIONS First, determine the release rate limit on the basis of the "f,'s", resulting from the projected release of gas decay tanks, being added to the normal plant vent noble gas activity concentration, using equations (9) and (10). This net result must now be converted to the corresponding concentration in the undiluted pathway by multiplying by the ratio of the plant vent flow rate (nomally, 220,000 scfm to the gas decay tank release flow rate (normally, approximately 31 scfm). This represents the limiting concentration passing through RE-22, and the high alarm setpoint is determined as prescribed in equation (16).

3) Steam generator blowdown tank vent monitor, RE-27 The site boundary dose contribution from releases from this pathway during normal operation are expected to be a very small faction of the dose contribution resulting from releases via the plant vent. For purposes of establishing the high alarm setpoint on RE-27, use as a basis release rates such that the dose contribution from this pathway will not exceed one percent of the maximum limits due to noble gases, that is, 5 mrem / year to the total body and 30 mrem / year to the skin. For two-unit operation, one-half of these values should be allotted to each unit.

First, determine the release rate limit for typical mixtures, using equations (9) and (10), but with the reduced doses described above. Next, calculate the corresponding activity concentration which flows through RE-27. Note that a concentrating effect of gaseous activity occurs in the blowdown tank vent b9Cause virtually all of the gaseous activity is carried out by only about one-third of the water mass whien had entered the blowdown tank. Use the following expression to determine the activity concentration flowing through RE-27:

Ot C

t (I7)

(R)Wg DC0467 30!!

oiAaLO CANYON POWER PLANT UNIT NO(S) 1 AND 2

[ h CAP A-8 DATE 9/14/85 PAGE 31 0F 71 TITLE OFF-SITE DOSE CALCULATIONS where:

C g

= the total activity concentration in RE-27, in' uCi/ gram ht = the activity release rate, in pCi/sec W

3

the total steam generator blowdown flow rate from all steam generators, in grams /sec R

the fraction of the blowdown which flashes to steam (R = 0.32, for most of the time, assuming that the inlet temperature is s 490*F).

The high alartn set:-int is established using the same kind of relationsht,2 as described in equation (16).

The value used for Ctshould not exced 0.015 uCf / gram, considered as dose equivalent I-131. because this is the implied concentration in the blowdown tank vent when the secondary coolant is at its technical specification limit of 0.10 u/Ci/ gram dose equivalent I-131.

f. Gaseous effluents dose projections (T.S. 3.11.2.4)

Dose projections for the categories of calculated air dose due to noble gases and calculated dose to an individual due to radiciodines, radioactive materials in particulate form and radionuclides other than noble gases are made at least once per 31 days. Projections will normally be made on the last working day of each month, with attention to the technical specification frequency requirement contained in section 4.11.2.4.1.

The projected dose is calculated by application of equation (11), (lla), (12), (12a), or (14), as appropriate, using estimated releases from expected releases from Gas Decay Tanks, Containment Purges, and building ventilation exhaust.

DC0467 31II

DIABLO CANYON POWED PLANT UNIT NO(S) 1 AND 2 f0N DATE 9/14/85 PAGE 32 0F 71 TITLE OFF-SITE DOSE CALCULATIONS The projected doses, whether from GDT, containment venting (or purging), and plant vent continuous releases could contain interim portions of the calculations (performed by the computer's "real time" software package) based on pre-batch release data or a previous periods composite analyses' data. And, in almost every instance, a scaling is involved by the ratio of 31 days to the number of days in the current quarter added to the previous quarter all multiplied by the sum of last quarter's dose to the doses accrued and calculated to date thus far this quarter. At any rate, this always ends up stored in the instantaneous running archive of doses (by computer). These " interim" dose calculations must eventually be purged and replaced with " correct" dose portions based on actual days involved; update or post-release analysis data on batches; and concurrent data from the composites.

3. Direct Radiation (T.S. 4.11.4.2)

Direct radiation from the plant site to the unrestricted area is composed of two principal components, namely line-of-site (or primary) radiation and sky-shine (or secondary scattered) radiation. For significant distances the latter component becomes quite dominant.

At Diablo Canyon Power Plant, being a P.W.R., turbine building shine (in contrast to B.W.R.'s) is all but non-existent.

Likewise the containment structures being so thickly shielded, never become the major sources for direct radiation. The most itkely candidates for any measurable source of direct radiation to the unrestricted area are the cask liners and drums holding the radioactively hot spent resins; filter beds; evaporator sludges; etc., which are slurried with concrete and compacted for high rad-waste storage. The high rad-waste storage bunkers themselves, although heavily shielded, for storing these casks, drums, etc., do represent the only continuous low level source of direct radiation. The most probable time for concern in calculating doses or dose rates due to direct radiation is during the preparation and transportation (to the bunkers from the Auxiliary building) of the casks, drums, beds, etc. of radwaste.

DC0467 32II

DIABLO CANYON POWE) PLANT UNIT NO(S) 1 AND 2 h0N DATE 9/14/85 PAGE 33 0F 71 TITLE OFF-SITE DOSE CALCULATIONS 4

Two basic assumptions are made in the following expressions used for calculating dose rates and the doses. One, is that, since the nearest unrestricted area (i.e. closest site boundary) location is 800 meters (or greater) away, and the bunker rooms, cask liners, and drums are < 10' or 15' in dimension, then all sources will be assumed point sources. This allows at least two significant figure confidence on dose and dose rate calculations.

Secondly the " sky-shine" or scattered radiation is assumed spherical rather than hemispherical about the source. That is the ground is conservatively assumed to be a perfect mirror to the radiation. In that which follows the so-called " build-up" factor, B, accounts for the sky-shine contribution whereas the e W"/r2 tem accounts for the line-of-sight contribution,

a. Dose rate calculations (air dose rate only).

1) When isotopic concentrations of unshielded directly exposed sources are known.

~

U b(R/hr)=156 I C9 I E jj u' j r2 1 j

,j_

j 8) 9 (18) where:

r = distance from source (i.e. open cask, open drum or exposed source) on site to point of interest for calculating dose rates in unrestricted area, in meters.

C,

= number of curies of isotope "1" in source.

= gama energy, in Mev, of j gama decay scheme E)9 in the ith isotope Y, pure number of gama decays in J O d C87 d

,4, scherre per disintegration of the ith ' isotope 156 = units compatibility constant p' = existing total gama attenuation coefficieelt O

j for air, in meters 1 - a function of E 93 DC0467 33!!

NUMBER CAP A-8 OLA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 34 0F 71 TITLE. 0FF-SITE DOSE CALCULATIONS u' = existing total gama absorptionn coefficient aj for air, in meters ~1 (Note: p, = e, pair with

a * # photo elect * # compt. abs * # pair prod)

- a function of E 93 v's h B

9j

=

1+ru'l[1+ j (Ref 7) (19)

"a j p' = existing compton scattering coefficient for s

j air in meters ~1 -a function of E yj u' =

9', + v'3 (20)

I21) u' (any subscript) = u (any subscript) [ h P = existing press. (atm, mHg, etc.)

T = existing temp. (*R, *K)

Po,To= S.T.P. (i.e. 760 m, 273*K etc. )

From the curves in Ref. 7 and Ref. 8, the following expressions were empirically curve fitted (any subscript).

u,(m'1) = 0.001e[1.34-0.105(in(10E)-1.57)2] (22) u(m1) s

= 0.001e[3.10-0.089(tn(10E)+1.89)2] (23)

POTE: (22) and (23) are accurate within : 10% for 0.1Mev<E<2.5 Mev DC0467 34Il

DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 R ON DATE 9/14/85 PAGE 35 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

2) When isotopic concentrations are not known but, C , the totalconcentration,isknownalongwithaneffeeliveI (gama) (external to the source) per disintegration also known. Equation (18) becomes:

b(R/hr)= 156 C T (curies) E(Mev) u (E) B(I)e-u g (I)r (24) r2(m) 1+

u 5 (I) where: B = 1 + ru, (T) (25)

. " (E) .

Here equations (20), (21), (22) and (23) are repeated for I here.

3) When no isotopic or total concentrations are known, but rather I (gamma external) is known plus an up-close survey meter reading (at some close distanceg r ), i.e.,

b(r)inR/hr,isknown.

g Such is the case for an enclosed source (already in cask, drum, or storage bunker) behind shielding with an effective I (known) in Nev to the outside world.

(Note: rnr g), then:

b(R/hr) = r IPo) B(I)e-u n (D (26)

(NOTE: The buildup factor, B(rg) times the attenuation, e' Fo, for r (<10 g

meter) %1) where: equations (20), (21), (22), (23) and (25) are used here also.

nenu, w,

NUMBER CAP A-8 DIASLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 36 0F 71 TITLE- 0FF-SITE DOSE CALCULATIONS

4) Examples:

Example 1.

i = Cs-137 T = 289* K (16*C or 66'F)

J=1 P = 1 atm r = 800 meters E4 ) = 0.662 Mev

= 0.9 C4 = 2 curies

. i.

B calculates to = 13.45 whereas:

e'W[calculatesto 0.000522 Then: b=7.3E-9R/hr Example 2.

T = 0.662 (Hev) T = 289*

P = 1 atn r = 800 meters r O= 1 meter .

D (rg) = 2.0 R/hr B calculates to = 13.45 and again e "o II calculates to 0.000522 Thus: b=2.19E-8R/hr

b. Here we simply calculate Dose Calculation the dose (air (24),

rate by (18 dose or only().

26) and multiply by the recorded time, at.

D(R)= b(P/hr)at(hr) (27)

1) Continuous at = 1 yr = 365 days = 8760 hrs

2) When processing and moving radwaste for storage in the high radwaste storage area, the radwaste foreman's records for this processing and moving time is used for At. Equation (27) is applied and the dose archived and summed to previous such doses.

DC0467 36!!

NUMBER CAP A-8 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 37 0F 71 TITLE OFF-SITE 00SE CALCULATIONS

3) Example: 2 curies of Cs-137 are lying on ground directly exposed for con %uously direct radiation to site boundary 800 meters away neglecting decay.

0 = 6.4E-5 Rads = 0.064 meads % 0.064 mrems

4. Uranium Fuel Cycle Cumulative Dose (T.S. 3.11.4)

The cumulative dose to any member of the public due to radioactive releases is determined by suming the calculated doses from the following as appropriate.

a. Liquids, using equation (1).

b. Noble gases, using equations (11) and (12) or (lla) and (12a),

c. Iodines and particulates, and radionuclides other than noble gases, using equation (14),

d. Direct radiation from 3. using equation (27).

OC0467 37Il

DIABLO CANYON POWER Pt. ANT UNIT NO(S) 1 AND 2 R[ ON DATE 9/14/85 PAGE 38 0F 71 TITLE OFF-SITE DOSE CALCULATIONS TABLE 1 COMPOSITE DOSE FACTOR, Ah, FOR ADULTS, SALTWATER SITE (mrem / hour per uCi/ml)

NUCLIDE T. BODY THYROID K!0NEY LUNG GI-LLI BONE LIVER H 3 2.82E-01 2.82E-01 2.82E-0 2.82E-01 2.82E-01 NO DATA 2.82E-01 8e 7 6.52E+01 NO DATA NO DATA NO DATA 2.61E+02 2.61E+01 NO DATA l C 14 2.90E 03 2.90E 03 2.90E 03 2.90E 03 2.90E 03 1.45E 04 2.90E 03 Na 24 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 7 T.TSI U5 WO DIG NO DIG NO DAG T.T8T U6 T.T7T U7 T.U4T U6 i Cr 51 5.58E 00 3.34E 00 1.23E 00 7.40E 00 1.40E 03 NO DATA NO DATA I Mn 54 1.35E 03 NO DATA 2.10E 03 NO DATA 2.16E 04 NO DATA 7.06E 03 Rn ST - 3.TSI U1 No DIG - 7.76T U2 N0 0%G - T.T7T U3 WO 0%G T.78T U2-Fe 55 8.23E 03 NO DATA NO DATA 1.97E 04 2.03E 04 5.11E 04 3.53E 04 Fe 59 7.27E 04 NO DATA NO DATA 5.30E 04 6.32E 05 8.06E 04 1.90E 05 To si- T.75T V3 NO 0AG No DIG No 0XG T.72T V4 Wo 0%G T.U3T U2-Co 60 3.82E 03 NO DATA NO DATA NO DATA 3.25E 04 NO DATA 1.73E 03 Ni 63 1.67E 03 NO DATA NO DATA NO DATA 7.18E 02 4.96E 04 3.44E 03 Ni 65 --- T.70T U1 No 0%E No DIG No DIG T.TSI U2 7.U2T U2 7.T2T U1-Cu 64 1.01E 02 NO DATA 5.40E 02 NO DATA 1.83E 04 NO DATA 2.14E 02 Zn 65 2.32E 05 NO DATA 3.43E 05 NO DATA 3.23E 05 1.61E 05 5.13E 05 7n 67 - T.T6T U1 NO DIG T.76T U2 NO DITX V.T5I U1 7.X3I U2- T.T6T U2-Br 83 7.25E-02 NO DATA NO DATA NO DATA 1.04E-01 NO DATA NO DATA Br 84 9.40E-02 NO DATA NO DATA NO DATA 7.38E-07 NO DATA NO DATA Tr 8T - 7.T6T-U3 NO 0XG N0 0%G NO 0%G T.T0E-T8 No 0XS No 0%G -

Rb 86 2.91E 02 NO DATA NO DATA NO DATA 1.23E 02 NO DATA 6.24E 02 Rb- 88 9.49E-01 NO DATA NO DATA NO DATA 2.47E-11 NO DATA 1.79E 00 Yb 8V - T.74T-U1 WO 0%G NO 0XG NO 0XG T.T9T-T4 N0 0%G T.T9E U0-Sr 89 1.43E 02 h0 DATA NO DATA NO DATA 8.00E 02 4.99E 03 NO DATA Sr 90 3.01E 04 NO DATA NO DATA NO DATA 3.55E 03 1.23E 05 NO DATA Tr 9T -- 7.71T UO NO DIG NO DM NO 0%G T.77T U2 V.T8T U1 N0 0%G -

Sr 92 1.51E 00 NO DATA NO DATA NO DATA 6.90E 02 3.48E 01 NO DATA l Y 90 1.63E-01 N0 DATA NO DATA NO DATA 6.42E 04 6.06E 00 N0 DATA Y 9TK- 7.72T-U3 N0 0%G NO DATA N0 0%G T.T8E-U1 T.737-U2 NO DXG -

Y 91 2.37E 00 NO DATA NO DATA NO DATA 4.89E 04 8.88E 01 NO DATA Y 92 1.56E-02 NO DATA NO DATA NO DATA 9.32E 03 5.32E-01 NO DATA Y 97 - T.T6T-U2 NO DIG NCT DIG - NO 0%G T.75T V4 T.39T B0 NO 0%G -

Zr 95 3.46E 00 NO DATA 8.02E 00 NO DATA 1.62E 04 1.59E 01 5.11E 00 Zr 97 8.13E-02 NO DATA 2.68E-01 NO DATA 5.51E 04 8.81E-01 1.78E-01 Eb 9T - T.74T U2 NO DAG 7.T6T U2 No 0%G T.TII V6 T.T7T U2 7.79T U2-Mo 99 2.43E 01 NO DATA 2.89E 02 NO DATA 2.96E 02 NO DATA 1.28E 02 Tc 99M 4.66E-01 NO DATA 5.56E-01 1.79E-02 2.17E 01 1.30E-02 3.66E-02 NOTET TON TAILY T:

1.

Ah = (1.14ES)(2189f + 5899)(DFh)

DC0467 381I

NUMSER CAP A-8 DIA8LO CANYON POWE3 PLANT UNIT NOIS) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 39 0F 71 TITLE OFF-SITE DOSE CALCULATIONS TABLE 1 - (Continued)

NUCLIDE T. BODY THYROID KIDNEY LUNG GI-LLI BONE LIVER Tc101 1.88E-01 NO DATA 3.46E-01 9.81E-03 5.77E-14 1.33E-02 1.92E-02 Rul03 4.60E 01 NO DATA 4.07E 02 NO DATA 1.25E 04 1.07E 02 NO DATA Rul05 3.51E 00 NO DATA 1.15E 02 NO DATA 5.44E 03 8.89E 00 NO DATA rut 0T - 7.UIT U2 NO DAG 7.U6T UT NO DITA T.U3T U5 T.T97 U3 NO DAG -

Ag110M 8.45E 02 NO DATA 2.80E 03 NO DATA 5.80E 05 1.54E 03 1.42E 03 l Sb124 1.09E 02 6.70E-01 NO DATA 2.15E 02 7.84E 03 2.76E 02 5.22E 00

!bT2T - T.70T U1- T.79I-U1 WO DIG - T.76T U2 T.V4T V3 T.77T U2 T.V7T Uo-Te125M 2.91E 01 6.52E 01 8.82E 02 NO DATA 8.66E 02 2.17E 02 7.86E 01 Te127M 6.68E 01 1.40E 02 2.23E 03 NO DATA 1.84E 03 5.48E 02 1.96E 02 TeT27 - T.Y3I U0 T. TOT U0 7.E3I U1 NO DITA 7.U3Y U2 E.Y0I U0 7.70T UO-Te129M 1.47E 02 3.20E 02 3.89E 03 NO DATA 4.69E 03 9.31E 02 3.47E 02 Te129 6.19E-01 1.95E 00 1.07E 01 NO DATA 1.92E 00 2.54E 00 9.55E-01 TeT3TM-- T.71T U1 T.U8T U2 T.Y4T U2 No DAG T.EOT V3 T. TOT U2 T.H5T U1-Te131 5.03E-01 1.31E 00 6.99E 00 NO DATA 2.26E-01 1.59E 00 6.66E-01 Te132 1.24E 02 1.46E 02 1.27E 03 NO DATA 6.24E 03 2.04E 02 1.32E 02 T T3B - T.EIT U1 V.VII UT T.32E U2 No DATA T.U1T U2 7.76E U1 T.T7T U2-I 131 1.79E 02 1.02E 05 5.35E 02 NO DATA 8.23E 01 2.18E 02 3.12E 02 I 132 9.96E 00 9.96E 02 4.54E 01 NO DATA 5.35E 00 1.06E 01 2.85E 01 T T37 - 7.75T U1 T.VUE U4 7.76T U T nu uAiA T.T6E U2 7.TSE U r T.3UE U r I 134 5.40E 00 2.62E 02 2.40E 01 NO DATA 1.32E-02 5.56E 00 1.51E 01

! 135 2.24E 01 4.01E 03 9.75E 01 NO DATA 6.87E 01 2.32E 01 6.08E 01 TsT3% - T.73T U4 No D%fA T.77T U3 T.75T U3 7.EST U2 E.E4T U3 T.i3T U4-Cs136 2.04E 03 NO DATA 1.57E 03 2.16E 02 3.21E 02 7.16E 02 2.83E 03 Cs137 7.85E 03 NO DATA 4.07E 03 1.35E 03 2.32E 02 8.77E 03 1.20E 04 IsT3B - T.74T U0 NO DATA E.EIT UO E.70E-U1 E.T2T-U5 E.U7T U0 T.70T U1-Ba139 2.30E-01 NO DATA 5.23E-03 3.17E-03 1.39E 01 7.85E 00 5.59E-03 Ba140 1.08E 02 NO DATA 7.02E-01 1.18E 00 3.38E 03 1.64E 03 2.06E 00 tat 4T - T.79T-U1 NO 0%fA 7.T8T-U T T.T3T-U T T.30T-U9 7.72T UO 7.38I-U3-Ba142 1.08E-01 NO DATA 1.50E-03 1.00E-03 2.43E-18 1.72E 00 1.77E-03 La140 2.10E-01 NO DATA NO DATA NO DATA 5.83E 04 1.57E 00 7.94E-01 tat 47 - V.T3I-UT N6 DATA NO UATA NO DATA 7.E8T U? E.U6T-U2 7.E7E-UZ-Cel41 2.63E-01 NO DATA 1.08E 00 NO DATA 8.86E 03 3.43E 00 2.32E 00 Cel43 4.94E-02 NO DATA 1.97E-01 NO DATA 1.67E 04 6.04E-01 4.46E 02 l TeT4% - V.T9T B0 NO 0%fA ~~ T.T3T U1 NO DATA E.U4T U4 T.79T U2 7.T7E U1-Pr143 2.87E-01 NO DATA 1.34E 00 NO DATA 2.54E 04 5.79E 00 2.32E 00 Pr144 9.64E-04 NO DATA 4.44E-03 NO DATA 2.73E-09 1.90E-02 7.87E-03 NdI47 - 7.74T-U1 NO 0%fA 7.T8T B0 Nd D%fA 7.70T U4 7.76Y B0 T.T8T UO-W187 2.68E 00 NO DATA NO DATA NO DATA 2.51E 03 9.16E 00 7.66E 00 Np239 1.91E-03 NO DATA 1.08E-02 NO DATA 7.11E 02 3.53E-02 3.47E-03 NOTES FOR TABLE 1:

1. Ah = (1.14E5)(21Bg + 58,,)(DFh)

I DC0467 3911

oiAsto CANYON POWER PLANT UNIT NO(S) AP A-8 1 AND 2 OATE 9/14/85 PAGE 40 0F 71 TITLE OFF-SITE DOSE CALCULATIONS TABLE 2 INGESTION DOSE FACTORS FOR ADULTS 1, DF (mrem per pCi ingested) h NUCLIDE T. BODY THYROID KIDNEY LUNG GI-LLI BONE LIVER Be Nb h Nb h Nb h .

- 44 8 Nb hA l C 14 5.68E-07 5.68E-07 5.68E-07 5.68E-07 5.68E-07 2.84E-06 5.68E-07 Na 24 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 7 37 -- 7.I6T-U6 NO DIfA NO 0%fA Wo 0XfA 7.T77-US T.737-U4- T.70I-US-Cr 51 2.66E-09 1.59E-09 5.86E-10 3.53E-09 6.69E-07 NO DATA NO DATA Mn 54 8.72E-07 NO DATA 1.36E-06 NO DATA 1.40E-05 NO DATA 4.57E-06 Rn' 53 - 7.U4T-38 NO 0XTA - T.I6T-UF No DAfA 7.T7E-Ur No 0XM - T.T5I-U7-Fe 55 4.43E-07 NO DATA NO DATA 1.06E-06 1.09E-06 2.75E-06 1.90E-06 Fe 59 3.91E-06 NO DATA NO DATA 2.85E-06 3.40E-05 4.34E-06 1.02E-05 Uo ST -- T.T7E-Ur No 0%fA - NO 0%fA NO DITA T. TIE-Ur NO DIM - 7.T5T-U7-Co 60 4.72E-06 NO DATA NO DATA NO DATA 4.02E-05 NO DATA 2.14E-06 Ni 63 4.36E-06 NO DATA NO DATA NO DATA 1.88E-06 1.30E-04 9.01E-06 Ni 6T ~ ~ 7.T3T-U8 NO 0%fA NO DIG NO DITX T.747-Ur T.78I-U7 3.E6I-U8-Cu 64 3.91E-08 NO DATA 2.10E-07 NO DATA 7.10E-06 NO DATA 8.33E-08 Zn 65 6.96E-06 NO DATA 1.03E-05 NO DATA 9.70E-06 4.84E-06 1.54E-05 In 63 - T.77T-U9 NO 0XfA T.78E-U8' No 0%fA " 7.76T-U9 T.U3E-U8 T.37I-U8-~

Br 83 4.02E-08 NO DATA NO DATA NO DATA 5.79E-08 NO DATA NO DATA Br 84 5.21E-08 NO DATA NO DATA NO DATA 4.09E-13 NO DATA NO DATA Tr 8T ~ ~ 7.T4E-39 NO 0%fA NO 0%fA - NO DITA - N0' DIfA NO 0%fA NO 0%fA - l Rb 86 9.83E-06 NO DATA NO DATA NO DATE 4.16E-06 NO DATA 2.11E-05 Rb 88 3.21E-08 NO DATA NO DATA NO DATA 8.36E-19 N0 DATA 6.05E-08 Tb 87 -- 7.32T-U8 N0'~0XfA N0' 0%fA - NO- DXfA 7.73E-71 NO 0%fA I.U1T Sr 89 8.84E-06 NO DATA NO DATA NO DATA 4.94E-05 3.08E-04 NO DATA Sr 90 1.86E-03 NO DATA NO DATA NO DATA 2.19E-04 7.58E-03 NO DATA Tr' 9T -- 7.79I-U7 No 0%fA NO 0XfA No DXfA 7.70T-UF T.37I-U6 No- DITI-Sr 92 9.30E-08 NO DATA NO DATA NO DATA 4.26E-05 2.15E-06 NO DATA Y 90 2.58E-10 NO DATA NO DATA NO DATA 1.02E-04 9.62E-09 NO DATA Y - 9TC 7.T2T-T2 No 0%fA No 0%fA No 0%fA 7.37E-To V.U9I-T1 No DITA -

Y 91 3.77E-09 NO DATA NO DATA NO DATA 7.76E-05 1.41E-07 NO DATA Y 92 2.47E-11 NO DATA NO DATA NO DATA 1.48E-05 8.45E-10 NO DATA T 97 -- 7.IOE-T1 NO DATI NCDATI NO DATA H.T0T-US~ 7.T8E-U9 NO DATX -

Zr 95 6.60E-09 NO DATA 1.53E-08 NO DATA 3.09E-05 3.04E-08 9.75E-09 Zr 97 1.55E-10 NO DATA 5.12E-10 NO DATA 1.05E-04 1.68E-09 3.39E-10

1. From Table E-11 of Regulatory Guide 1.109 (Rev.1, Oct.1977) except for Be 7. Sb-124, and Sb-125 which are from NUREG-0172 (November 1977)

DC0467 40!!

DIABLO CANYON POWE3 FLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 41 CF 71 TITLE OFF-SITE DOSE CALCULATIONS TABLE 2 - (continued)

NUCLIOE T. BODY THYROID KIONEY LUNG GI-LLI BONE LIVER Nb 95 1.86E-09 NO DATA 3.42E-09 NO DATA 2.10E-05 6.22E-09 3.46E-09 i Mo 99 8.20E-07 NO DATA 9.76E-06 NO DATA 9.99E-06 NO DATA 4.31E-06 Tc 99M 8.89E-09 NO DATA 1.06E-08 3.42E-10 4.13E-07 2.47E-10 6.981-10 7cTOT - 7.39T-U9 WO DIG - 3.197-U9 T.T7T-To T. TOT-71 7.T4T-To 7.V6E-To-Rul03 7.97E-08 NO DATA 7.06E-07 NO DATA 2.16E-05 1.35E-07 NO DATA Rul05 6.08E-09 NO DATA 1.99E-07 N0 f.ATA 9.42E-06 1.54E-08 NO DATA tut 0E - 7.787-Ur WroIG T.71T-Ur No DIG T.78T-U4 7.75T-U6 NO 0TG -

Ag110M 8.79E-08 NO DATA 2.91E-07 NO DATA 6.04E-05 1.60E-07 1.48E-07 Sb124 1.11E-06 6.79E-09 NO DATA 2.18E-06 7.95E-05 2.80E-06 5.29E-08 Sb125 4.26E-07 1.82E-09 NO DATA 1.38E-06 1.97E-05 1.73E-06 2.00E-08 Te125M 3.59E-07 8.06E-07 1.09E-05 NO DA7A 1.07E-05 2.68E-06 9.71E-07 TeT270 T.75T '0F T.73T-U6 7.75T-Ur No DIG 7.77T-US T.777-U6 7.72T-U6-Te127 2.38E-08 8.15E-08 4.48E-07 NO DATA 8.68E-06 1.10E-07 3.95E-08 Tel29M 1.82E-06 3.95E-06 4.80E-05 NO DATA 5.79E 05 1.15E-05 4.29E-06 TeT23 - 7.T5T ~09 7.T1T-U8 T.72T-UF No 0%G 7.77T-Ur 7.T4"-U8 T.T87 Te131M 7.05E-07 1.34E-06 8.57E-06 NO DATA 8.40E-05 1.73E-06 8.46E-07 Te131 6.22E-09 1.62E-08 8.63E-08 NO DATA 2.79E-09 1.G7E-08 8.23E-09 TeT37 - T.T3T-U6 T.30T-U6 T.T7T-US No DIG 7.71T-US 7.T27-UF T.337-U6-I 130 8.80E-07 1.89E-04 3.48E-06 NO DATA 1.92E-06 7.5f!-07 2.23E-06 I 131 3.41E-06 1.95E-03 1.02E-05 NO DATA 1.57E-06 4.162-06 5.95E-06 T T37 - T.70T-U F T.70T 05~ T.35T-U F No 0% G T.U2T-U F 7.'03T-U P T.T3T-U F I 133 7.53E-07 3.63E-04 4.31E-06 NO DATA 2.22E-06 1.42E-06 2.47E-06 I 134 1.03E-07 4.99E-06 4.58E-07 NO DATA 2.51E-10 1.06E-07 2.88E-07 T T3T - T.787-U F 7.35T-U r T.36T-U r WO DA G T.71T-U6 T.73T-U F T.T6T-U6-Cs134 1.21E-04 NO DATA 4.79E-05 1.59E-05 2.59E-06 6.22E-05 1.48E-04 Cs136 1.85E-05 NO DATA 1.43E-05 1.96E-06 2.92&-06 6.51E-06 2.572-05 TsT37 - 7.T4T-US NO DI G 7.70T-US~ T.737-U5' 7. TIT'06 7.V7T-US T.09T-U4-Cs138 5.40E-08 NO DATA 8.01E-08 7.91E-09 4.65E-13 5.521-08 1.09E-07 Ba139 2.84E-09 NO DATA 6.46E-11 3.92E-11 1.72E-07 9.70E-08 6.91E-11 tat 4U - T.73T '06~ NO DIG T.T7T-39-~ T.76T-38 T.T8T-US 7.U3T-US 7.TST-U8-Ba141 1.59E-09 NO DATA 3.31E-11 2.02E-11 2.22E-17 4.71E-08 3.56E-11 Ba142 1.34E-09 NO DATA 1.85E-11 1.24E-11 3.00f-36 2.13E-00 2.19E-11 tat 4U - 7.73T-To WO DIG NroIG No 0%G V.75T-US 7. TOT-Ur T.767-U9- 1 La142 1.45E-11 NO DATA NO DATA NO DATA 4.25E-07 1.28E-10 5.82E-11 Cel41 7.18E-10 NO DATA 2.94E-09 NO DATA 2.A?E-05 9.36E-09 6.33E-09 TeT47 - T.75T-TO NO 0XTX T.77T-TO-' N0 0%G G6?-Ur T.35T-U9 T.727-U6-Ce144 2.62E-08 NO DATA 1.21E-07 NO DATA 1.65E-04 4.88E-07 2.04E-07 Pr143 4.56E-10 NO DATA 2.13E-09 NO DATA 4.03E-05 9.20E-09 3.69E-09 TrT4T - T.T3T-T2 No 0%G -' 7.UST-T2 NO DIG T.73T-T8 7.UIT-T1 T.75T-T1-Nd147 4.35E-10 NO DATA 4.25E-09 NO DATA 3.49E-05 6.29E-09 1.27E-09 W 187 3.01E-08 NO DATA NO DATA NO DATA 2.82E-05 1.03E-07 8.61E-08 Np737 ~~ ~ T.75T-T1 NO DIG 7.35T-TF WO 0%G 7.XOT-US T.T9T-U9 T.T7T-To-DC0467 41!!

N oiAsto CANYON POWER PLANT UNIT NO(S) 1 AND 2 R S ON DATE 9/14/85 PAGE 42 0F 71 TITLE OFF-SITE DOSE CALCULATIONS TABLE 3 BI0 ACCUMULATION FACTORSI TO BE USED IN THE ABSENCE OF SITE-SPECIFIC DATA (pC1/kg per pCi/ liter)

SALTWATER O 0 if 11 ELEMENT FISH INVERTEBRATE 21 89f + 5 B,4 H 9.0E-01 9.3E-01 2.355E 01 Be2 2.0E 02 2.0E 02 5.20E 03 C 1.8E 03 1.4E 03 4.48E 04 Na 6.7E-02 1.9E-01 2.357E 00 P 2.9E 04 3.0E 04 7.59E 05 Cr 4.0E 02 2.0E 03 1.84E 04 Mn 5.5E 02 4.0E 02 1.355E 04 Fe 3.0E 03 2.0E 04 1.63E 05 Co 1.0E 02 1.0E 03 7.10E 03 Ni 1.0E 02 2.5E 02 3.35E 03 Cu 6.7E 02 1.7E 03 2.257E 04 Zn 2.0E 03 5.0E 04 2.92E 05 Br 1.5E-02 3.1E 00 1.582E 01 Rb 8.3E 00 1.7E 01 2.593E 02 Sr 2.0E 00 2.0E 01 1.42E 02 Y 2.5E 01 1.0E 03 5.525E 03 Zr 2.0E 02 8.0E 01 4.60E 03 Nb 3.0E 04 1.0E 02 6.305E 05 Mo 1.0E 01 1.0E 01 2.60E 02 Tc 1.0E 01 5.0E 01 4.60E 02 Ru 3.0E 00 1.0E 03 5.06E 03 Ag2 3.3E 03 3.3E 03 8.58E 04 Sb2 4.0E 01 5.0E 00 8.65E 02 Te 1.0E 01 1.0E 02 7.10E 02 I 1.0E 01 5.0E 01 4.60E 02 Cs 4.0E 01 2.5E 01 9.65E 02 Ba 1.0E 01 1.0E 02 7.10E 02 La 2.5E 01 1.0E 03 5.525E 03 Ce 1.0E 01 6.0E 02 3.21E 03 Pr 2.5E 01 1.0E 03 5.525E 03 Nd 2.5E 01 1.0E 03 5.525E 03 W 3.0E 01 3.0E 01 7.80E 02 Np 1.0E 01 1.0E 01 2.60E 02 3 From Table A-1 of Regulatory Guide 1.109 (Rev.1, Oct.1977) 2 From Table A-8 of Regulatory Guide 1.109 (Rev. O, March 1976)

DC0467 4211

-4 O TABl.E 4 g g DOSE FACTORS FOR NOBLE GASES AND DAUGHTERSI $

o E

@ Total Body Ganma Air Beta Air 8 m o z Dose Factor Skin Dose Factor Dose factor Dose Factor m 2 K g Lg Mg Ng

[

Radionuclide (mrem /yr per pC1/m 3 ) (mren/yr per pCl/m3 ) (mrad /yr per pCi/m ) (mrad /yr per pCi/m )

3 3 h $

Kr-83m 7.56E-02 ----

1.93E+01 2.88E+02 g

~

Kr-85k 1.17E403 1.46E*03 1.23E403 1.97E+03 .4.

Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E403 h h-Kr-87 5.92E+03 9.73E+03 -

6.17E403 1.03E+04 y 8 Kr-88 1.47E404 2.37E403 1.52E*04 2.93E+03 $ 5 Kr-89 1.66E404 1.01E+04 1.73E+04 1.06E+04 y Kr-90 1.56E+04 7.29E+03 1.63E+01 7.83E+03 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.llE403 [

Xe-133m 2.51E+02 9.94E+02 3.27E+02 1.48E+03 5 ,

Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.36E+03 7.39E+02 Xe-135 1.81E+03 1.86E+03 1.92E+03 2.46E+03 Xe-137 1.42E+03 1.22E+04 1.51E+03 1.27E+04

~

Xe-138 8.83E+03 4.13E+03 9.21E+03 4.75E+03 AR-41 8.84E+03 2.69E+03 9.30E+03 3.28E+03 mom 2

~

$~$25

~c=

5"

1. From Table B-1 of Regulatory Guide 1.109 (Rev. 1, Oct. 1977)

OP9 '

~

1P w w e-=

9s o gz oZ ,o3" (2, c2a 39 - yts N ng $ .

zgg=p;z o

p mgm

>gm

.Q Z f#*

- $eUM gg njgr$gw e I l l ,

c s n y a a 232344443454444543444333334454 w I 000000000000000000000000000000 + + +

e h L + + + 4 + + + + + 4 + + + + + + +++++++++ +d t L EEEEEEEEEEEEEEEEEEEEEEEEECEEEE o a

- 860683288803070846802864846642 C p I 607571933956761303070553233582 G 435041110332126633949013438141

". l

. . . . . . . l 653721353627211 13151 612111 3213 c a e

, p r S S o T 234565650676655766666004446565 f N 000000000000000000000000000000 .

E G + + + + + + + + 4 + + 4 + + + ++++++++++4 + + + + h 3 U N EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE c m L U 864650880013086689680006666620 e /

F L 608917060355581569438006729642 T i F 432907540014775161666009115182 " C EE . . . . . . p V 651917460212145132211007171593 E I S d r TU n e CO a p AE 231300040000433545004445451 353 G DS Y 000000000000000000000000000000 P r A E + + + +++ + + + + + + + + + + ++++++++ + + y I

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+ * + + + +++++++++++++++++++++++++ rGi0 t .

RRF R E N E EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE oE n/

TYI V 860429284000660043840888580614 fR uX EN I 60035125000082002357931 2410613 U 430532029000740024570490316621 sN ey MA L r hb A . .

RD 650221861000260072546417165118 ert AN t o e ,de PA m94i E , a01l SS 040040040575543430444445454463 r1 p OE 000000000000000000000000000000 a . ni DT + + + + + +++++++++++++++++++++++++ p1 ot A E EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE bl L N 060070020680486020464442080228 eeru U O 040050030788561 880961926380793 sd am C B 060030090908150690714739846719 oiC I . . . du e T 020010010345112890351313455237 Gdb R e n A M h . at P 5 t g s 0 l emu rR um E 9 I O Y M/ M o f nt y i

I / 3605459 4670147 L 2 149805690 550011222133334444 oie C 2 455556688919911111 113311111 11 s rh U 31 - - - 9 - - - - - - - - 11 - - - - - - - edTt N - - RNE00NBRR - RBUUGD88E - SSSAEED ue O HCCMFCCZRSSYZNRRACS5T1 I CCCBCCN l srd I aaon D . . . . . . . . . . . . . . . . . . . .. VbF a A . . . . . . . . 012345678901234567890 i 2 R 12345678911 11 1111 1122222222223 o o@ N

TABLE SB -. o DOSE PARAMETERS I , R, OR P , FOR RADIOI0 DINES, RADI0 ACTIVE g S 5

PARTICULATES, AND ANY RADIONOCLIDE OTHER THAN N0BLE GAS, GASE0US EFFLUENTS, 5 INFANT AGE GROUP, COW MILK PATilWAY o g mrem /yr per pCl/sec)

ORGAN (m2

{

o RAD'IONUCLIDE B0NE LIVER TOTAL B00Y THYROID KIDNEY LUNG GI-LLI Z S a

1. H-32 0.000E+00 2.382E+03 2.382E+03 2.382E403 2.382E+03

2. C-142 3.226E+06 6.888E405 6.888E+05 6.888E+05 6.888E+05 2.382E+03 6.888E405 2.382E+03 3 m

6.888E+05

3. CR-51 0.000E+00 0.000E+00 1.441E+05 9.403E+04 2.054E+04 1.829E+05 4.201E+06 g @

4. MN-54 0.000E+00 3.108E+07 7.044E406 0.000E+00 6.888E406 0.000E400' l.142E+07 v> f

5. FE-59 1.929E+08 3.369E+08 1.328E+08 0.000E+00 0.000E400 9.957E407 1.609E+08 $

6. C0-58 0.000E+00 2.018E+07 5.034E407

[

0.000E+00 0.000E+00 0.000E+00 5.029E+07 p g

7. C0-60 0.000E+00 6.984E+07 1.649E+08 0.000E+00 0.000E+00 0.000E+00 1.662E+08 g 8.

9.

ZN-65 RB-86 4.998E+09 0.000E+00 1.714E+10 2.072E+10 7.905E+09 1.024E+10 0.000E+00 0.000E+00 8.313E+09 0.000E+00 0.000E400 0.000E+00 1.448E+10 5.302E+08

- )9

10. SR-89 d

1.077E+10 0.000E+00 3.089E408 0.000E400 0.000E+00 0.000E+00 2.214E+08 e

11. SR-90/Y90 1.009E+11 0.000E+00 2.570E+10 0.000E+00 0.000E+00 0.000E400 1.260E+09 E'

12. Y-91 6.172E+04 0.000E+00 1.644E+03 0.000E+00 0.000E+00 0.000E+00 4.424E+06

13. ZR-95 5.706E+03 1.390E+03 9.860E+02 0.000E+00 1.498E+03 0.000E+00 6.924E+05 -

14. NB-95 5.193E+05 2.139E+05 1.237E+05 0.000E+00 1.533E405 0.000E+00 1.80SE+08 g

15. RU-103 7.544E+03 0.000E+00 2.523E+03 0.000E+00 1.570E+04 0.000E+00 9.175E+04 o

16. RU-106 1.533E+05 0.000E+00 1.915E+04 0.000E+00 1.813E+05 0.000E400 1.164E+06 m

17. AG-110M 3.217E+08 2.348E+08 1.554E+08 0.000E+00 3.359E+08 0.000E+00 1.218E+10

18. CD-IIS/ll5M 0.000E+00 9.053E+06 3.148E+05 0.000E+00 4.720E+06 0.000E+00 5.654E+07 l

19. 5B-124 1.759E+08 2.589E+06 5.448E+07 4.668E+05 0.000E+00 1.101E+08 5.424E+08

20.58-125 1.180E+08 1.142E+06 2.427E+07 1.477E+05 0.000E+00 7.406E+07 1.573E+08

21. TE-129M 5.271E+08 1.808E+08 8.ll7E+07 2.024 E+08 1.318E+09 0.000E+00 3.147E+08

22. 1-131 2.676E+09 3.153E+09 1.386E+09 1.036E+12 3.682E+09 0.000E+00 1.126E+08

23. I-133 3.721E+07 5.417E+07 1.586E+07 9.852E+09 6.370E+07 0.000E+00 9.167E+06

24. CS-134 2.873E+10 5.357E+10 5.410E+09 0.000E+00 1.379E+10 5.654E+09 1.455E+08 yom2

25. CS-136 1.872E+09 5.506E+09 2.056E+09 0.000E+00 2.194E+09 4.487E+08 8.362E+07 gMg

26. CS-137 4.155E+10 4.864E+10 3.447E+09 0.000E+00 1.306E+10 5.286E+09 1.520E+08 "'mg;g

27. BA-140 2.304E+08 2.304E+05 1.187E+07 0.000E+00 5.470E+04 1.415E+05 S.659E+07 ;;"

28. CE-141 3.814E+04 2.326E+04 2.738E+03 0.000E+00 7.173E+03 0.000E400 1.202E+07 2

29. CE-144 1.838E+06 7.524E+05 1.030E+05 0.000E+00 3.040E405 0.000E+00 1.055E+08 ..m

30. ND-147 8.569E+02 8.801E402 5.392E+01 0.000E*00 3.393E+02 0.000E*00 5.578E+05 O %

1 Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code and $

based on Reg. Guide 1.109 or NUREG 0133. Z 2

For Tritium and Carbon 14, the units of the dose parameters are mrer/yr per pCf/m3 for all pathways, and they must be multiplied by X/0.

o $5 ohoZ 8fn" (z, cj b9 ng $

- goN

2gg:n

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ygm u]$%

e#'" 3m 8m npo(dgm ll l ,

d s n y a a 333444443555444555545433335454 w I

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- 5440770222365072349372681 971 54 C I 238963239715007907331474811681 G 170204669618174204608848160682

. . . . ".c l l

161273917161634413141253431538 a e

p r

, S o S 334666650676655766666005456575 f T 000000000000000000000000000000 .

N G + + + + + + + + + + 4 + 4 4 + + + + + + ++++++++++ h 3 E N EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE c m U U 548696730729123265101000403952 e /

L L 239760650502342370426001544398 T i F 176521090156216443237002407412 " C F . . . . . p EE 161 111790212266152321001111513 E V d r IS n e TU a p CO 331400040000433545004445451363 G AE Y 000000000000000000000000000000 P r 0S E + + + + + + + + + + + + 4 + + + 4 + + ++++++++++4 y IA N EEEEEEEEEEEEEEEEEEEEEEEEEEEEEE e /

DG D 541300010000710942002184633730 h m A I 23300004000052332000387042l471 t e r

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TABLE SE -f 9 DOSE PARAMETERS I , R OR P , FOR RADI0I0 DINES, RADI0 ACTIVE # $

j "

PARTICULATES,ANDANYRADIONbCLIDEOTHERTilANN0BLEGAS,GASE0USEFFLUENTS, o CHILD AGE GROUP, ANIMAL MEAT PATilWAY o ORGAN 2(m mrtm/yr per ifi/sec) h o

Z S RADIONUCLIDE BONE LIVER TOTAL BODY THYROID KIDNEY LUNG GI-LLI S 1. H-3 2 0.000E+00 2.341E+02 2.341E+02 2.341E+02 2.341E+02 2.341E+02 2.341E+02- 3 M

2. C-14 2 5.287E+05 1.057E+05 1.057E+05 1.057E+05 1.057E+05 1.057E+05 1.057E+05 m

3. CR-51 0.000E+00 0.000E+00 7.865E+03 4.366E+03 1.193E+03 7.971E+03 4.171E+05 g q'

4. MN-54 0.000E+00 6.376E+06 1.698E406 0.000E+00 1.788E+06 0.000E+00 5.351E+06 ;g 3 -

5. FE-59 3.244E+08 5.250E+08 2.615E+08 0.000E400 0.000E+00 1.522E+08 5.466E+08 n c

6. C0-58 0.000E400 1.367E407 4.185E+07 0.000E400 0.000E+00 0.000E+00 7.975E407 p j

7. C0-60 0.000E400 5.489E+07 1.6'.9E+08 0.000E+00 0.000E+00 0.000E+00 3.040E408 g

8. ZN-65 3.380E+08 9.006E+08 5.601E+08 0.000E+00 5.675E+08 0.000E+00 1.582E+08 g b

9. RR-86 0.000E+00 5.380E+08 3.308E+08 0.000E+00 0.000E+00 0.000E+00 3.461E+07 -j 9

10. SR-89 4.153E+08 0.000E+00 1.186E+07 0.000E+00 0.000E+00 0.000E+00 1.608E+07 cg

11. SR-90/Y90 8.633E+09 0.000E+00 2.189E+09 0.000E+00 0.000E+00 0.000E+00 1.168E+08 l m

12. Y-91 1.521E+06 0.000E+00 4.068E+04 0.000E+00 0.000E+00 0.000E400 2.026E+08

13. ZR-95 2.242E+06 4.928E+05 4.387E+05 0.000E+00 7.054E+05 0.000E+00 5.141E+08

14. NB-95 2.711E+06 1.056E406 7.544E+05 0.000E+00 9.918E+05 0.000E400 1.952E+09 g

15. RU-103 1.350E+08 0.000E+00 5.191E+07 0.000E+00 3.399E+08 0.000E+00 3.492E+09 o N

16. RU-106 3.575E*09 0.000E+00 4.461E+08 0.000E400 4.828E+09 0.000E+00 5.561E+10

17. AG-110M 7.000E+06 4.727E+06 3.779E+06 0.000E+00 8.805E+06 0.000E+00 5.624E+08 t

18. CD-IIS/ll5M 0.000E+00 1.530E406 6.518E+04 0.000E+00 1.137E+06 0.000E+00 2.081E+07 I

( 19. 5B-124 2.454E+07 3.183E+05 8.599E+06 5.416E+04 0.000E+00 1.362E+07 1.534E+08 l

20. SB-125 2.247E+07 1.732E+05 4.707E+06 2.081E+04 0.000E+00 1.252E+07 5.367E+07 l 21. TE-129M 1.701E+09 4.751E+08 2.641E+08 5.485E+08 4.995E+09 0.000E+00 2.075E+09 l

22. 1-131 1.633E+07 1.643E+07 9.334E+06 5.431E+09 2.697E+07 0.000E+00 1.462E+06

23. I-133 6.776E-01 8.379E-01 3.171E-01 1.557E+02 1.396E+00 0.000E+00 3.377E-01 l

24. CS-134 7.262E+08 1.192E+09 2.514E+08 0.000E+00 3.693E+08 1.325E+08 6.424E+06 mm

25. CS-136 1.521E+07 4.180E407 2.705E+07 0.000E+00 2.226E+07 3.319E+06 1.469E+06 gMg

26. CS-137 1.077E+09 1.031E+09 1.521E+08 0.000E+00 3.359E+08 1.209E+08 6.454E+06 mmg

27. BA-140 4.197E+07 3.677E404 2.450E+06 0.000E+00 1.197E+04 2.192E+04 1.126E+07 p

28. CE-141 1.951E+04 9.729E+03 1.445E+03 0.000E+00 4.265E+03 0.000E+00 1.214E+07 z

29. CE-144 1.830E+06 5.737E+05 9.768E+04 0.000E+00 3.177E+05 0.000E+00 1.496E+08 %w

30. ND-147 1.152E+04 9.328E+03 7.223E+02 0.000E+00 5.ll8E+03 0.000E+00 1.478E+07 mb g 1

Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code $

and based on Reg. Guide 1.109 or NUREG 0133.

2 for Tritium and Carbon 14, the units of the dose parameters are mrem /yr per tCi/m3 for all pathways ,

and they must be multiplied by UO.

TABLE SF d 9 DOSE PARAMETERS I , R OR Py, FOR RADIOI0 DINES, RADI0 ACTIVE #

PARTICULATES,ANDANYRADIONhCLIDEOTiiERTilANN0BLEGAS,GASEOUSEFFLUENTS, o ClllLD AGE GROUP, VEGETABLE PATilWAY n g ORGAN (nf mrem /yr per pCi/sec) h o o kRADIONUCLIDE B0NE LIVER TOTAL BODY Tl1YROID KIDNEY LUNG GI-LLI h ,

0 1. 11- 3 2 0.000E+00 4.008E+03 4.008E+03 4.008E*03 4.008E+03 4.008E+03 4.008E+03 2.

3.

C-142 CR-51 3.504E+06 0.000E+00 7.008E+05 0.000E+00 7.008E+05 1.161E+05 7.008E+05 6.442E+04 7.008E+05 1.760E+04 7.008E405 1.176E+05 7.008E+05 6.155E+06 m

8

(

g

4. MN-54 0.000E+00 6.496E+08 1.730E+08 0.000E+00 1.821E+08 0.000E+00 5.452E408 "

5. FE-59 3.932E+08 6.363E+08 3.169E+08 0.000E+00 0.000E+00 1.844E+08 6.62SE+08 n c

6. C0-58 0.000E+00 6.279E+07 1.922E+08 0.000E+00 0.000E+00 0.000E+00 3.663E+08 # $

7. C0-60 0.000E+00 3.769E+08 1.lllE*09 0.000E+00 0.000E400 0.000E+00 2.088E+09 9

8. ZN-65 1.029EE09 2.741E+09 1.705E+09 0.000E+00 1.727E+09 0.000E+00 4.814E408 g 5

9. RB-86 0.000E+00 3

4.566E+08 2.808E+08 0.000E*00 0.000E+00 0.^00E+00 2.937E407 d -

10. SR-89 3.622E+10 0.000E400 1.035E+09 0.000E+00 0.000E+00 0.000E+00 1.402E+09 @

11. SR-90/Y90 1.379E+12 0.000E+00 3.497E+11 0.000E+00 0.000E+00 0.000E+00 1.864E+10 I "

12. Y-91 1.830E407 0.000E+00 4.893E+05 0.000E+00 0.000E400 0.000E+00 2.438E+09

13. ZR-95 3.804E+06 8.363E+05 7.445E+05 0.000E+00 1.197E+06 0.000E+00 8.724E+08 **

14. NB-95 4.039E+05 1.573E+05 1.124E405 0.000E+00 1.477E405 0.000E+00 2.908E+08 g

15. RU-103 1.525E+07 0.000E+00 5.862E+06 0.000E+00 3.839E+07 0.000E+00 3.943E+08 t'

16. RU-106 7.529E+08 0.000E+00 9.395E+07 0.000E+00 1.017E+09 0.000E+00 1.171E+10 N

, 17. AG-Il0M 3.464E+07 2.339E+07 1.870E+07 0.000E+00 4.357E+07 0.000E+00 2.783E+09

18. CD-IIS/ll5M 0.000E+00 1.405E+08 5.%5E406 0.000E+00 1.044E+08 0.000E+00 1.941E+09 1

19. 5B-124 3.420E+08 4.437E+06 1.199E+08 7.549E+05 0.000E+00 1.898E+08 2.138E+09

20.58-125 4.903E+08 3.7 DOE +06 1.027E+08 4.540E+05 0.000E+00 2.732E+08 1.171E+09

21. TE-129M 9.989E+08 2.789E+08 1.551E+08 3.220E408 2.933E+09 0.000E+00 1.218E+09

22. 1-131 1.430E+08 1.438E+08 8.172E+07 4.755E+10 2.361E+08 0.000E+00 1.280E+07

23. I-133 3.577E+06 4.423E+06 1.674E+06 8.218E+08 7.372E+06 0.000E+00 1.783E+06

24. CS-134 1.561E+10 2.562E+10 5.405E+09 0.000E+00 7.940E+09 2.849E409 1.381E+08 oom2

25. CS-136 8.043E+07 2.211E+08 1.431E+08 0.000E+00 1.177E+08 1.756E+07 7.770E+06 R W25

26. CS-137 2.499E+10 2.392E+10 3.530E+09 0.000E+00 7.794E+09 2.804E+09 1.498E+08 m m D;M

27. BA-140 2.762E+08 2.420E+05 1.612E+07 0.000E+00 7.877E+04 1.442E405 1.399E+08 5"

28. CE-141 6.424E+05 3.204E+05 4.757E,04 0.000E+00 1.405E+05 0.000E+00 3.997E+08 2

29. CE-144 1.218E+08 3.817E+07 6.498E+06 0.000E+00 2.ll3E+07 0.000E+00 9.951E+09 u wn

30. ND-147 7.256E+04 5.877E+04 4.551E+03 0.000E+00 3.225E+04 0.000E+00 9.310E+07 *D %

ot >

t Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code ]$ lo and based on Reg. Guide 1.109 or NUREG 0133. .--

2 For Tritium and Carbon 14, the units of the dose parameters are mrem /yr per pCi/m3 for all pathways ,

and they rust be multintind hv Un

TABLE SG w o DOSE PARAMETERSI, R OR Pj , FOR RADI0I0 DINES, RADI0 ACTIVE ?

5 PARTICULATES, AND ANY RAD 10t'6CLIDE OTHER TilAN NOBLE GAS, GASEOUS EFFLUENTS, 5 TEEN AGE GROUP, INilALATION PATilWAY o g

o ORGAN (mrem /yr per pCi/m ) 3 o

{

Z BONE LIVER TOTAL BODY TilYR010 KIDNEY LUNG GI-LLI $ ,

kRADIONUCLIDE e o E 1. 11 - 3 2 0.000E+00 1.272E+03 1.272E+03 1.272E+03 1.272E+03 1.272E+03 1.272E+03 3 3" 4.872E+03 4.872E+03 4.872E+03 4.872E+03 4.872E+03 m

2. C-142 2.600E+04 4.872E+03

3. CR-51 0.000E+00 0.000E+00 1.352E+02 8.400E403 7.496E+01 0.000E+00 3.072E+01 1.272E+04 2.0%E+04 1.984E+06 3.000E+03 6.680E+04 g

g (z

4. HN-54 0.000E400 5.112E+04

5. FE-59 1.592E+04 3.696E+04 1.432E404 0.000E+00 0.000E+00 1.528E+06 1.784E+05 n c

6. C0-58 0.000E+00 2.072E+03 2.776E+03 0.000E+00 0.000E+00 1.344E+06 9.520E+04 p j

7. C0-60 0.000E400 1.512E+04 1.984E+04 0.000E+00 0.000E+00 8.720E+06 2.592E405 g

8. ZN-65 3.856E+04 1.336E405 6.240E+04 0.000E+00 8.640E404 1.240E+06 4.664E404 r- [

2

9. RB-86 0.000E+00 1.904E+05 8.400E+04 0.000E400 0.000E+00 0.000E+00 1.768E+04 $

10. SR-89 4.344E+05 0.000E+00 1.248E+04 0.000E+00 0.000E+00 2.416E+06 3.712E+05 g 0.000E+00 0.000E+00 1.677E+07 1.324E406 m

11. SR-90/Y90 1.080E+08 0.000E+00 6.680E+06 l

12. Y-91 6.608E+05 0.000E+00 1.768E+04 0.000E+00 0.000E+00 2.939E406 4.088E+05 l

13. ZR-95 1.456E+05 4.584E+04 3.152E+04 0.000E+00 6.736E+04 2.688E+06 1.488E+05

14. NB-95 1.856E+04 1.032E+04 5.664E+03 0.000E+00 1.000E+04 7.512E+05 9.680E+04 g 8.960E+02 0.000E+00 7.432E*03 7.832E+05 1.088E+05 o

15. RU-103 2.104E+03 0.000E+00 0.000E+00 1.904E+05 1.608E407 9.600E+05 m

16. RU-106 9.840E+04 0.000E+00 1.240E+04

17. AG-110M 1.384E+04 1.312E+04 7.992E*03 0.000E+00 2.504E+04 6.752E+06 2.728E+05

18. CD-Il5/115M 0.000E+00 2.794E+05 9.162E+03 0.000E+00 2.264E+05 2.578E+06 7.344E+05 l

19. SB-124 4.304E+04 7.936E+02 1.680E+04 9.760E+01 0.000E+00 3.848E+06 3.984E+05

20. SB-125 7.384E+04 8.080E402 1.720E+04 7.040E+01 0.000E+00 2.736E+06 9.920E+04

21. TE-129M 1.392E+04 6.584E+03 2.248E+03 4.576E+03 5.192E+04 1.976E+06 4.048E+05

22. 1-131 3.544E+04 4.912E+04 2.640E+04 1.464E+07 8.400E+04 0.000E+00 6.488E+03

23. 1-133 1.216E+04 2.048E+04 6.224E+03 2.920E+06 3.592E+04 0.000E+00 1.032E+04

24. CS-134 5.024E+05 1.128E+06 5.488E+05 0.000E+00 3.752E+05 1.464E+05 9.760E+03 , a m.

25. CS-136 5.152E+04 1.936E+05 1.368E+05 0.000E+00 1.104E+05 1.776E+04 1.088E+04 gg

26. CS-137 6.704E+05 8.480E+05 3.112E+05 0.000E+00 3.040E+05 1.208E+05 8.480E+03 mmgg

27. BA-140 5.472E+04 6.704E+01 3.520E+03 0.000E+00 2.280E+01 2.032E+06 2.288E+05 g:o 2.168E+03 0.000E+00 8.880E+03 6.136E+05 1.264E+05 z

28. CE-141 2.840E+04 1.896E+04

29. CE-144 4.888E+06 2.024E+06 2.624E+05 0.000E+00 1.208E+06 1.336E+07 8.640E+05 mon

30. ND-147 7.864E+03 8.560E+03 5.128E+02 0.000E+00 5.024E+03 3.720E+05 1.824E+05 on g i Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code [

~

and based on Reg. Guide 1.109 or NUREG 0133. ~

2 for Tritium and Carbon 14, the units of the dose parameters are mrem /yr per pCi/m 3 for all pathways ,

and they must be multiolied by X/0.

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OC0467 55 m

[ TABLE SM d 9 DOSE PARAMETERS I , R OR P , FOR RADIOI0 DINES, RADI0 ACTIVE y 5 3 j PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS, GASE0US EFFLUENTS, 5 ADULT AGE GROUP, ANIMAL MEAT PATHWAY n o ORGAN (m2 mrem /yr per pCi/sec) {

o RADIONUCLIDE BONE LIVER TOTAL BODY THYROID' KIDNEY LUNG GI-LLI h j e o E 1. H-32 0.000E+00 3.248E+02 3.248E+02 3.248E+02 3.248E+02 3.248E+02 3.248E+02 3 3

2. C-142 3.329E+05 6.658E+04 6.658E+04 6.658E+04 6.658E+04 6.658E+04 6.658E+04 m

3. CR-51 0.000E+00 0.000E+00 6.307E+03 3.770E+03 1.389E+03 8.370E+03 1.586E+06 g g'

4. MN-54 0.000E+00 7.306E+06 1.394E+06 0.000E+00 2.174E+06 0.000E+00 2.238E+07 g 3

5. FE-59 2.290E+08 5.381E+08 2.063E+08 0.000E+00 0.000E+00 1.503E+08 1.794E+09 n c .

6. C0-58 0.000E+00 1.518E+07 3.403E+07 0.000E+00 0.000E+00 0.000E+00 3.077E+08 p g

7. C0-60 0.000E+00 5.958E+07 1.314E+08 0.000E+00 0.000E+00 0.000E+00 1.119E+09 g g

8. ZN-65 3.204E+08 1.019E+09 4.608E+08 0.000E400 6.819E+08 0.000E+00 6.421E+08 g 3

9. R8-86 0.000E+00 4.545E+08 2.ll8E+08 0.000E+00 0.000E+00 0.000E+00 8.962E+07 d -

10. SR-89 2.600E+08 0.000E400 7.462E+06 0.000E+00 0.000E+00 0.000E+00 4.170E+07 g

11. SR-90/Y90 1.033E+ 10 0.000E+00 2.534E+09 0.000E+00 0.000E+00 0.000E+00 2.995E+08 I m

12. Y-91 9.558E+05 0.000E+00 2.556E+04 0.000E+00 0.000E+00 0.000E+00 5.260E+08

13. ZR-95 1.576E+06 5.055E+05 3.422E+05 0.000E+00 7.933E+05 0.000E+00 1.602E+09

14. NB-95 2.OllE406 1.119E+06 6.014E+05 0.000E+00 1.106E+06 0.000E+00 6.790E+09 3:

15. RU-103 9.169E+07 0.000E+00 3.950E+07 0.000E+00 3.499E+08 0.000E+00 1.071E+10 o 0.000E+00 4.353E+09 0.000E+00 N

16. RU-106 2.255E+09 0.000E+00 2.853E+08 1.459E+11

17. AG-110M 5.575E+06 5.157E+06 3.063E+06 0.000E+00 1.014E407 0.000E+00 2.105E+09

18. CD-115/Il5M 0.000E+00 1.282E+06 4.090E+04 0.000E+00 1.017E+06 0.000E+00 5.395E407 1

19. 5B-124 1.661E+07 3.137E+05 6.583E+06 4.027E404 0.000E+00 1.293E407 4.715E+08

20.58-125 1.507E+07 1.684E+05 3.587E+06 1.532E+04 0.000E+00 1.162E+07 1.659E+08

21. TE-129M 1.078E409 4.021E+08 1.706E+08 3.702E+08 4.499E+09 0.000E+00 5.427E+09 1

22. 1-131 1.060E+07 1.516E+07 8.687E+06 4.968E+09 2.598E+07 0.000E+00 4.000E+06 1

23. I-133 4.361E-01 7.585E-01 2.312E-01 1.Il5E+02 1.324E+00 0.000E+00 6.817E-01 l

24. CS-134 5.179E+08 1.232E+09 1.008E+09 0.000E+00 3.988E+08 1.324E+08 2.157E+07 yon

25. CS-136 1.130E+07 4.462E+07 3.212E+07 0.000E+00 2.483E+07 3.403E+06 5.069E+06 R$QQ

26. CS-137 7.041E+08 9.630E+08 6.308E+08 0.000E+00 3.269E+08 1.087E+08 1.864E+07 mm;g

27. BA-140 2.751E407 3.456E+04 1.802E+06 0.000E+00 1.175E+04 1.978E+04 5.664E+07 7 2

28. CE-141 1.234E+04 8.345E+03 9.465E+02 0.000E+00 3.876E+03 0.000E+00 3.190E+07

29. CE-144 1.152E+06 4.816E+05 6.186E+04 0.000E+00 2.857E+05 0.000E+00 3.895E+08 i y, o n

30. ND-147 6.965E+03 8.050E+03 4.817E+02 0.000E+00 4.706E+03 0.000E+00 3.865E+07 % 4; I Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code $

and based on Reg. Guide 1.109 or NUREG 0133.

2 For Tritium and Carbon 14, the units of the dose parameters are mrem /yr per pCi/m 3 for all pathways ,

and they must be mult101 led by UO.

TABLE SN w o DOSE PARAMETERS 3, R, OR Pj , FOR RADIOI0 DINES, RADI0 ACTIVE i 5 PARTICULATES, AND ANY RADIONOC'iDE OTHER THAN N0BLE GAS, GASEOUS EFFLUENTS, 5 ADULT AGE GROUP, VEGETABLE PATHWAY o ORGAN (m2 mrem /yr per pCi/sec)

{

o Z

hRADIONUCLIDE B0NE LIVER TOTAL B0DY THYROID KIDNEY LUNG GI-LLI h y e

o .

O 1. H-32 0.000E+00 2.260E+03 2.260E+03 2.260E+03 2.260E+03 2.260E403 2.260E+03 h 3

2. C-142 8.966E+05 1.793E405 1.793E+05 1.793E+05 1.793E405 1.793E+05 1.793E+05 m "

3. CR-51 0.000E+00 0.000E+00 4.599E+04 2.749E+04 1.013E+04 6.103E+04 1.157E+07 g {z

4. MN-54 0.000E+00 3.059E+08 5.836E+07 0.000E+00 9.102E+07 0.000E+00 9.370E+08 v'

5. FE-59 1.246E+08 2.929E408 1.123E+08 0.000E+00 0.000E+00 8.183E+07 9.762E+08 [ 2

6. CO-58 0.000E+00 2.997E407 6.718E+07 0.000E+00 0.000E+00 0.000E+00 6.074E+08 p j

7. C0-60 0.000E+00 1.665E408 3.672E+08 0.000E*00 0.000E+00 0.000E+00 3.128E+09 g 2

8. ZN-65 4.018E+08 1.279E+09 5.778E+08 0.000E+00 8.551E+08 0.000E+00 8.053E+08 g 9

9. RB-86 0.000E+00 2.215E+08 1.032E+08 0.000E+00 0.000E+00 0.000E+00 4.366E+07 d 9

10. SR-89 1.001E+10 0.000E+00 2.873E+08 0.000E400 0.000E+00 0.000E+00 1.605E+09 g

11. SR-90/Y90 6.708E+11 0.000E+00 1.646E+11 0.000E+00 0.000E+00 0.000E+00 1.952E+10 i m

12. Y-91 5.014E+06 0.000E+00 1.341E+05 0.000E+00 0.000E+00 0.000E+00 2.759E+09

13. ZR-95 1.157E+06 3.710E+05 2.511E+05 0.000E+00 5.822E+05 0.000E+00 1.176E+09 ~

14. NB-95 1.401E405 7.796E+04 4.191E+0/ 0.000E+00 7.706E+04 0.000E+00 4.732E+08 g

15. RU-103 4.741E+06 0.000E+00 2.042E+06 0.000E+00 1.809E+07 0.000E+00 5.535E+08 o

16. RU-106 1.947E+08 0.000E+00 2.464E+07 0.000E+00 3.759E408 0.000E+00 1.260E+10 ro

17. AG-110M 1.136E+07 1.051E+07 6.241E406 0.000E+00 2.066E+07 0.000E+00 4.289E409

18. CD-115/ll5M 0.000E+00 5.327E+07 1.701E+06 0.000E+00 4.227E+07 0.000E+00 2.307E+09 l

19.58-124 1.008E+08 1.094E+06 3.996E+07 2.444E+05 0.000E*00 7.848E+07 2.862E+09

20.58-125 1.341E+08 1.498E+06 3.190E+07 1.363E+05 0.000E+00 1.034E+08 1.475E+09

21. TE-129M 2.978E+08 1.lllE+08 4.714E+07 1.023E+08 1.243E+09 0.000E+00 1.500E+09

22. 1-131 8.077E+07 1.155E+08 6.621E+07 3.786E+10 1.980E+08 0.000E+00 3.048E+07

23. I-133 2.112E+06 3.674E+06 1.120E+06 5.400E+08 6.411E+06 0.000E+00 3.302E+06

24. CS-134 4.544E+09 1.081E+10 8.841E409 0.000E+00 3.500E+09 1.162E+09 1.892E+08 mom,

25. C5-136 4.197E+07 1.657E+08 1.193E408 0.000E+00 9.218E+07 1.263E+07 1.882E+07 ggg

26. CS-137 6.641E+09 9.082E+09 5.949E+09 0.000E+00 3.083E+09 1.025E+09 1.758E+08 mmg

27. 8A-140 1.283E+08 1.611E*05 8.404E+06 0.000E+00 5.478E+04 9.225E+04 2.641E+08 gm

28. CE-141 1.933E+05 1.307E405 1.483E404 0.000E+00 6.071E+04 0.000E+00 4.997E+08 z

29. CE-144 3.151E+07 1.317E+07 1.692E+06 0.000E+00 7.814E+06 0.000E+00 1.066E+10 y, o n

30. ND-147 3.367E+04 3.891E+04 2.328E+03 0.000E+00 2.2/SE+04 0.000E+00 1.868E+08 7 g i Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code y, $

and based on Reg. GufA 1.109 or NUREG 0133. ~

~

2 for Tritium and Carbon 14, the units of the dose parameters are mrem /yr per pCi/ml for all pathways ,

and they must be multiplied by X/0.

N A-8 CIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 p DATE 9/14/85 PAGE 58 0F 71 TITLE OFF-SITE DOSE CALCULATION TABLE 50 DOSE PARAMETERS I , R FOR RADIOI0 DINES, RADIOACTIVE 4

PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS, GASEOUS EFFLUENTS ANY AGE GROUP, GROUND PLANE PATHWAY (m2 mrem /yr per pCi/sec)

RADIONUCLIDE R (GROUND)

1. H-3 0.000E+00

2. C-14 0.000E+00

3. CR-51 4.668E+06

4. MN-54 1.342E+09

5. FE-59 2.756E+08

6. C0-58 3.799E+03

7. CO-60 2.149E+10

8. ZN-65 7.501E+08

9. RB-86 9.005E+06

10. SR-89 2.230E+04

11. SR-90/Y90 4.482E+03 1

12. Y-91 1.183E+06 l

13. ZR-95 2.493E+08 l

14. NB-95 1.366E+08

15. RU-103 1.087E+08

16. RU-106 4.200E+08

17. AG-110M 3.482E+09

18. CD-115/115M 4.500E+06 l

19.53-124 5.949E+08

20.58-125 2.286E+09

21. TE-129M 2.001E+07

22. I-131 1.722E+07

23. I-133 2.474E+06

24. CS-134 6.833E+09

25. CS-136 1.491E+08

26. CS-137 1.030E+10

27. BA-140 2.054E+07

28. CE-141 1.360E+07

29. CE-144 6.958E+07

30. ND-147 8.481E+06 1 Values for' the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code and based on Reg. Guide 1.109 or NUREG 0133.

DC0467 73II

_]

NUMBER CAP A-8 DiABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 59 0F 71 TITLE OFF-SITE DOSE CALCULATION TABLE SP DOSE PARAMETERSI, P, FOR RADIOI0 DINES, RADI0 ACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN N08LE GAS, GASEOUS EFFLUENTS, ANY AGE GROUP, GROUND PLANE PATHWAY (m2 mrem /yr per uCi/sec)

RADIONUCLIDE P (GROUND)

1. H-3 0.000E+00

2. C-14 0.000E+00

3. CR-51 6.667E+06

4. MN-54 1.086E+09

5. FE-59 3.922E+08

6. C0-58 5.272E+08

7. CO-60 4.400E+09

8. ZN-65 6.894E+08

9. RB-86 1.286E+07

10. SR-89 3.160E+04

11. SR-90/Y90 6.402E+03

12. Y-91 1.669E+06 ,

13. ZR-95 3.487E+08 t

14. NB-95 1.949E+08

15. RU-103 1.551E+08 l

16. RU-106 2.992E+08

17. AG-110 3.143E+09 18..CD-115/115M 6.300E+06

19.58-124 8.374E+08

20.58-125 7.552E+08 11:I! ills" 3:!!81:83

23. I-133 1.779E+06

24. CS-134 2.813E+09

25. CS-136 2.129E+08

26. CS-137 1.147E+09

27. BA-140 2.934E+07

28. CE-141 1.942E+07

29. CE-144 5.855E+07

30. ND-147 1.212E+07 1 Values for the dose parameters for all pathways are calculated by the PGandE dTech. Spec." Code and based on Reg. Guide 1.109 or NUREG 0133. _;

i DC0467 74II

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 60 0F 71 TITLE OFF-SITE DOSE CALCULATION TABLE 6A DOSEPARAMETERS1,KORT.

FORRADIO!0 DINES,RADI0ACTIVEPARTIdVLATE,AND ANY NON-NOBLE GASES SUPER AGE GROUP, CRITICAL ORGAN INHALATION, C0d-MILK-INGESTION, PATHWAYS INHAL/ TION MILK RADIONUCLIDE (MREM /YR PER uCi/M )

3 (M2, MREM /YR PER uti/SEC)

H 32 1.3E+03 (teen tot. bdy.) 2.4E+032 (inf. tot. body)

C 142 3.6E+04 (child bone) 3.2E+062 (inf. bone)

Cr 51 2.1E+C4 (teen lung) 7.5E+06 (teen GI-LLI)

Mn 54 2.0E+06 (

") 3.1E+07 (inf. liver)

Fe 59 1.5E+06 (

") 3.4E+08 ( "

)

Co 58 1.3E+06 (

") 9.1E+07 (teen GI-LLI)

Co 60 8.7E+06 (

") 2.9E+08 (

)

Zn 65 1.2E+06 (

") 1.7E+10 (inf. liver)

Rb 86 2.0E+05 (child liver) 2.1E+10 ( " )

Sr 89 2.4E+06(teenlung) 1.1E+10 (inf. bone)

Sr 90/Y90 1.1E+08 (teen bone) 1.0E+11 ( " ")

Y91M/Y91 2.9E+06 (teen lung) 5.5E+06 (teen GI-LLI)

Zr 95 2.7E+06 (

") 1.0E+06 (

)

Nb 95M/95 7.5E+05 (

") 2.9E+08 (

)

RJ 103 7.8E+05 (

") 1.3E+05 (

)

Ru 106/Rh106M 1.6E+07 (

") 1.5E+06 (

)

Ag 110M E.8E+06 (

") 2.1E+10 (

)

1 Values for the dose parameters for all pathways are calculated by the PGandE

" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.

2 For tritium and carbon-14, the units of the dose parameters are mrem /yr per uCi/m3 for all pathways, and they must be multiplied by X/Q.

DC0467 75II

DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 ON DATE 9/14/85 PAGE 61 0F 71 TITLE OFF-SITE DOSE CALCULATION TABLE 6A (cont'd)

DOSE PARAMETERS 2, K OR T.

FORRADIOI0 DINES,RADI0ACTIVEPARTIbULATE,AND ANY NON-NOBLE GASES SUPER AGE GROUP, CRITICAL ORGAN INHALATION, COW-MILK-INGESTION, PATHWAYS INHALATION MILK RADIONUCLIDE (MREM /YR PER uCf/M') (H2, MREM /YR PER uCi/SEC)

Cd 115/Cd 115M/ l In 115M 2.8E+06 (teen lung /GI-LLI) 6.9E+07 (teen GI-LLI)

Sb 124 3.9E+06 (teen lung) 7.8E+08 (

)

Sb 125 2.7E+06 (

") 2.2E+08 (

)

Te 129M 2.0E+06 (

") 1.3E+09 (inf. kidney)

Cs 134 1.1E+06 (teen liver) 5.4E+10 (inf. liver) '

Cs 136 1.9E+05 ( ) 5.5E+09 ( " "

)

Cs 137 9.1E+05 (child bone) 4.9E+10 ( " ) i Ba 140 2.0E+06 (teen lung) l 2.3E+08 (inf. bone)

Ce 141 6.1E+05 (

") 1.5E+07 (teen GI-LLI)

Ce 144 1.3E+07 (

") 1.3E+08 (

)

Nd 147 3.7E+05 (

") 6.9E+05 (

)

Unidentified 1.1E+08 1.0E+11 I 131 ,

1.6E+07 (child thyroid) 1.0E+12 (inf. thyroid)

I 133 3.8E+06 (

) 9.9E+09 ( " "

)

1 Values for the dose parameters for all pathways are calculated by the PGandE

" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.

2 For tritium and carbon-14, the units of the dose parameters are mrem /yr per uCi/m3 for all pathways, and they reust be multiplied by X/Q.

DC0467 761I

NUMBER CAP A-8 DIA8LO CANYON PCIWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 62 0F 71 TITLE. OFF-SITE DOSE CALCULATION TABLE 6A (cont'd)-

DOSEPARAMETERS1,KOR'P~,

FORRADIOI0 DINES,RADI0ACTIVEPARTIbOLATE.AND ANY NON-NOBLE GASES SUPER AGE GROUP, CRITICAL ORGAN FARM-ANIMAL-MEAT-INGESTION, VEGETABLE-INGESTION PATHWAYS ANIMAL (MEAT) VEG RADIONUCLIDE (M 2, MREM /YR PER pCi/SEC) (M2, MREM /YR PER uCi/SEC)

H 32 3.2E+022 (adult tot. bdy.) 4.0E+03 2 (child tot.bdy. )!

C 142 5.3E+052 (child bone) 3.5E+062 (child bone) j Cr 51 1.6E+06 (adult GI-LLI) 1.2E+07 (adult GI-LLI) l Mn 54 2.2E+07 ( ) 9.4E+08 ( )

l Fe 59 1.8E+09-( ) 9.8E+08 (teen GI-LLI) i Co 58 3.1E+08 (

) 6.1E+08 (adult GI-LLI) l Co 60 1.1E+09 (

) 3.2E+09 (teen GI-LLI) f Zn 65 1.0E+09 (adult liver) 2.7E+09 (child liver) .

) l Rb 86 5.4E+08 (child liver) 4.6E+08 (

Sr 89 4.2E+08 (child bone) 3.6E+10 (child bone) l Sr 90/Y90 1.0E+10 (adult bone) 1.4E+12 ( ) ,

Y91M/Y91 5.3E+08 (adult GI-LLI) 3.2E+09 (teen GI-LLI)

Zr 95 1.6E+09 (

) 1.2E+09 ( " )

Nb 95M/95 6.8E+09 (

) 4.7E+08 (adult GI-LLI) ,

Ru 103 1.1E+10 (

) 5.7E+08 (teen GI-LLI) l l

( Ru 106/Rh106M 1.5E+11 (

) 1.5E+10 ( " )

Ag 110M 2.1E+09 (

) 4.4E+09 ( " )

l i

l

Values for the dose parameters for all pathways are calculated by the PGandE

" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133.

For tyitium and carbon-14, the units of the dose parameters are mrem /yr per UCi/m for all pathways, and they must be multiplied by X/0.

l i

DC0467' 77II I ..e

NUMBER CAP A-8 DIA8LO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 63 0F 71 TITLE OFF-SITE DOSE CALCULATION TABLE 6A (cont'd)

DOSEPARAMETERSI,KORT.

FORRADICIODINES,RADI0ACTIVEPARTIbULATE,AND ANY NON-NOBLE GASES SUPER AGE GROUP, CRITICAL ORGAN FARM-ANIMAL-MEAT-INGESTION, VEGETABLE-INGESTION PATHWAYS ANIMAL (MEAT) VEG RADIONUCLIDE (M2, MREM /YR PER uC1/SEC) (M2, MREM /YR PER uCi/SEC)

Cd 115/Cd 115M/

In 115M 5.4E+07 (adult GI-LLI) 2.5E+09 (teen GI-LLI)

Sb 124 4.7E+08 ( ) 3.0E+09 ( " )

Sb 125 1.7E+08 ( ). 1.6E+09 ( " )

Te 129M 5.4E+09 (

) 2.9E+09 (child kidney)

Cs 134 1.2E+09 (adult liver) 2.6E+10 (child liver)

Cs 136 4.5E+07 ( ) 2.2E+08 ( )

Cs 137 1.1E+09 (child bone) 2.5E+10 (child bone)

Ba 140 5.7E+07 (adult GI-LLI) 2.8E+08 ( )

Ce 141 3.2E+07 ( ) 5.3E+08 (teen GI-LLI)

Ce 144 3.9E+08 ( ) 1.3E+10 ( " )

Nd 147 3.9E+07 ( ) 1.9E+08 (adult GI-LLI)

Unidentified 1.5E+11 1.4E+12 I 131 5.4E+09 (child thyroid) 4.8E+10 (child thyroid)

I 133 1.6E+02 ( ) 8.2E+08 ( )

1 Values for the dose parameters for all pathways are calculated by the PGandE

" Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133, 2 For tritium and carbon-14, the units of the dose parameters are mrem /yr per uC1/m3 for all pathways, and they must be multiplied by X/Q.

l l

[

DC0467 78II l

NUMBER CAP A-8 DIASLO, CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 64 0F 71 TITLE. OFF-SITE DOSE CALCULATION TABLE 6B DOSEPARAMETERS1,KANDK, FOR RADIOICDINES, RADIOACTIVE PARTICULATE, AND ANY RADIOACTIVE NON-NOBLE GASEGUS EFFLUENTS SUPER AGE GROUP, CRITICAL ORGAN GROUND PLANE PATHWAY RADIONUCLIDE E ( M2, MREM /YR ) g ( M2, MREM /YR )

i UCI/5EC i UCI/5EC H 3 0 0 C 14 0 0 Cr 51 4.7E6 6.7E6 Mn 54 1.3E9 1.1E9 Fe 59 2.8E8 3.9E8 Co 58 3.8E8 5.3E8 Co 60 2.1E10 4.4E9 Zn 65 7.5E8 6.9E8 Rb 86 9.0E6 1.3E7 krb/Y90 !"hk3 k'kE3 Y 91 1.2E6 1.7E6 Zr 95 2.5E8 3.5E8 Nb 95 1.4E8 2.0E8 RU 103 1.1E8 1.6E8 RU 106/Rh106M 4.2E8 3.0E8 Ag 110M 3.5E9 3.1E9 Cd 115/115M 4.5E6 6.3E6 Sb 124 6.0E8 8.4E8 Sb 125 2.3E9 7.6E8 Te 129M 2.0E7 2.9E7 Cs 134 6.8E9 2.8E9 Cs 136 1.5E8 2.1E8 Cs 137 1.0EIO 1.1E9 Ba 140

2.1E7 2.9E7 Ce 141 1.4E7 1.9E7 Ce 144 7.0E7 5.9E7 Nd 147 8.5E6 1.2E7 I 131 1.7E7 2.5E7 I 133 2.5E6 1.8E6 1

Values for the dose parameters for all pathways are calculated by the PGandE " Tech. Spec." Code based on Reg. Guide 1.109 or NUREG 0133. ,

DC0457 79II

y o

-4 TAI 1LE 7A Fn E

r-o DISPERSION PARAMETER, X/Q (sec/m'), HISTORICAL. "FIVF YFAD" AVFRAGE I Q E i O

S o y

g (Applies only to real and hypothe_ti_ cal individuals)

' 0, m g Sector +

Distance N NW NNW N NN E, N[. [NI, I [5[ $[

0. l(0.8km)' 3.94x10 2.70x10

site boundary l.51:10 R.25ml0 ~ - - - 8 ut

(

rn 2, n C 0.6aml(1.08km) 1.16:10

site boundary N

n h

0.73ml(1.2km) 1.5).10 ' % b site boundary Q

1.06ml(1.69hm) - - -~ ~ ~ -

7.31:10 2.13,10's site boundary 1.19ml(1.9km) - - - ~~ ~ ~ ~

4.50x10's -

site boundary z

- o 1.55ml(2.5km) 4.1G 10 ' - - ~ - - - -

ro residence (333*)

2.0 mil (3.2km) - - - - - -

7.07:10 '

vegetable faru (122.)

3.3mI(5.3km) - - -

3.8910 - - ~ ~ ~

residence (018.5*)

3.7ml(5.9km) 1.53x10 - - - - - - - -

residence (326*)

4.4ml(7.lkm) .3,41,10 e - 2= 2= E E 3.64n10 e residence (008*)

(062.5*)

- - ~~

E NE usrn 4.5ml(7.26km) - -

5.89:10., . 5" 2

residence - - __ _

(0% .5* )

5.lml(8.2km) 2 M

wO "

residence - - - - *

f017*)

Nus mI I

Based on hourly sieterological data from 1/1/80 to 12/31/514 %

TABLE 7B -, o k 5 I o DISPERSION PARAMETER, D/Q (m-2), HISTORICAL "flVI YEAR" AVIRAGE n (Applies to real, virtual and hypothetical (ground plane) individuals only) >

a

" k o -

o O 4= s Sector + m Z m s g

N Distance s s NW N_ N_M E- N_[_ [ NL. [ [5[

SE ri

-._. _NNW . .

"c., 0.5ml(0.8km) 1.50:10 ' 6.81x10 3.47x10 '

2.18:10 - - - - -

q k33

-* s b. cattle,gnd m

o 0.68ml(1.08km) 1.43x10 - - - -

8 M

h"

-4 s.b. cattle, gnd C .

n.

2 2 1.64x10 - - -

E 4 0.73ml(1.2km) - -

p g s.b. cattle,gnd a 5 1.67x10 5.53x10 '

- d ~

1.06ml(1.6%m) - -

s.b. cattle,gnd 3.55x10

1.19ml(1.9ha) - -

-a s.b. cattle,gnd o

8.15:10 - - - -

1.55ml(2.56m) -

m res, meat, gnd (333*)

2.0ml(3.2km)l res, - - - - - -

4.77x10 -

veg meat, gnd (122*)

3.3xl(5.3km) - - - 8.75x10 - - - -

res.neet.gnd ( 018. ',' )

3.7ml(5.9km) 3.83x10 - - - - -

res. neat,gnd (326*) '

5.27x10 - -

7.85x10 - - -

2= E= E $

4.4al(7.lkm) - -

Cy<J res. meat gnd (008*) (062.5*) (n m 4.5ml(7.26km) ' - - - - -

1.41x10 - -

gA (096.5*) z res, meat, god.veg.

5.Qat(8.%km) -

1.28x10 6.5?x10 4.09:10 4.48:10 6.13:10 l.13:10 3.77x10 -

he (d Q .o imag. milk cows 4.00x10- - - - - m cn I

5.1ml(8.2te) -

(0);*)

res, mea t,gnd - y e-*

S Based on hourly meteorological data from 1/1/80 to 12/31/84

4 DIA8LO CANYON POWE*, PLANT UNIT NO(S)

NUMBER CAP A-8 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 67 0F 71 TITLE- 0FF-SITE DOSE CALCULATION TABLE 8 LOCATIONS FOR CANDIDATE DOSE (R 4

) AND DOSE RATE (Pq ) RECIPIENTS

. ct..ee i=t.u ta- us. ca.s.s>

' n m s m m u

,,ii.,c 5= - a 1 i

. s t**

.. ~ .i. J ' i t. site mstie.,,i s i i =

s.ite

. ..y i s.e.n i m .e. ,i ;

e.sesi t t .os= > - - -

sit. tounetry s

.n.,m asi . . . . .

stie e i s t.on.i t t.sg=) s, site m .te..,. m ., . s t.tgei t t .g=1 . . . . .

u te W.e. *, - ;

i.sw(t,se.) .

m inac e' . . . . . . .

t.> 0 tw . . . . . . . 3ty'e .

3.3.i(i lam) ,es Meac e 8 94.p a . sy 3.ht($.ges) m , e -e e8 . . . . . .

a a..o.i..) m e e..< ,a

e.v e -< . ' * *

TiimI'T (.a.;ag 59

.. w .ts. 1 . . . . . . g . .

t . ., < a .. , 1 t-, ,t-, 1 t -, 1 t -, 1 1-, t t -, t.eg t -,

g stit estt atta silt stit stlt etla 8 cars' cms' cws

caes' cows

Cors' ca.s

8

1. t e ' t . ts.) , g g g g g , ,

i a$tte beuneary locations oncessess the entire sector estets. wise. But are at tae etstance ta the sector conter.itne.stte teundary interseCtton. At these locattens, tAe canetaste dose and este rate roCiptents for atrterne redteactive todtnes ame particulates are: the nypotnettCal indiviesels esposed to only the tr$41stion ene groung plane petpoeys as well as virtual indtsteuels esposed te only the cattle. coat anteel pethuey. Also at these locations, tne nypotnettcal inetste.at can sisasitaneously be esposed to the notle gas, dele toey and sain esse rate settle dese.utse t>e netle gas gasuna str esse and tota sir esse serve as the Tecn. Spec. surrogate.

88esteente locations contain real indictesals idttch can sisseltaneously be esposed to not only noble lat dele body (and sets) esses as well as esse rates, but also to innalatton, ground plane. (meet) anteel and posstole vegetatie pathway soses, as well as ease rates. pers tne meteorological etspersion parameters 1/Q and 0/Q are casented not just to tne distance in the containtag sector, but also to tne resteence estnuth location. er

'A vegeteele farm in the 15E sector at 2 elles is occupied by eterant worsers (real instetduals . all age groves) with an occupancy factor of 0.5 appites to esternal doses (one eene rates) received from the feele gases and non-nobles sta the groune plane deposition patamey plus the trealetten diffusion patmuey. Neuever, these inelsteuels are else assumed to rwetve non notte mest and vegetatle tagestion pataway soses (and esse rates) esta en occupancy factor af 1. adatttonally tne virtual inetsteual, rectatent only to indirect vegetaale truestion esse (and dose rates). esists ineseeaceatly mere.

Yhts type af indieteual is so esf tned since altaowen not present to receive the strect neele gas esternal esposure or non.notte ground plane and trealattsn doses (or sose rates), can noce the-less receive instrectly soses free tats food grown prostmate to tne plant and concatvably satpoed away.

mita cows, althougn reat eviseaces by the land use census attain $ elles (of plant site) are none.the-less represented nere fictittously as a eefault esse ce+trmtar (so costres by tme NBC) at 5 alles in all lane sectars. Lite at tne .egetsole fare one site temaeary greatns seat antasis, tats esse source meatfesta itself througn creattea of the virtual toe,v,ewel as softnee ta festnote

aseve.

DC0467 8211

NUMBER CAP A-8 DIA8tO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 68 0F 71 TITLE OFF-SITE DOSE CALCULATION

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DC0467 6911

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NUMBER CAP A-8 DIABLO CANYON POWER PLANT UNIT NO(S) 1 AND 2 REVISION 3 DATE 9/14/85 PAGE 70 0F 71 TITLE. OFF-SITE DOSE CALCULATIONS FIGURE 3 SECTOR MAP SHOWING RECEPT 0R LOCATIONS

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DIABLO CANYON POWER PLANT UNIT NO(S) N 1 AND 2 RV ON DATE 9/14/85 PAGE 71 0F 71 TITLE OFF-SITE DOSE CALCULATIONS

=

REFERENCES

1. " Draft Radiological Technical Specifications for PWR's," NUREG No.,0472, May 1978.

2. " Calculation of Annual Doses sto Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I, " Regulatory Guide 1.109, Rev.1, October 1977.

3. " Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," NUREG No. 0133, October 1978.

4. " Age-Specific Radiation Oose Committment Factors for a one-year Chronic Intake," NUREG No. 0172, Noverter 1977.

5. " Methods for Demonstrating LWR Compliance with the EPA Uranium .

Fuel Cycle Standard 40 CFR Part 190." NUREG No. 0543, January 1980.

6. " Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors", Regulatory Guide,1.111, Rev.1. July,1977.

7. "The Atomic Nucleus", R.D. Evans, McGraw-Hill, 1955.

8. " Radiological Health Hanobook", U.S. Dept. Health, Education and Welfare, P.H.S., BRH, 1970.

DC0467 88II

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PGWE FOR INTRA-COMPANY USES S*nien't Engineering Research Ta D vision or Department F LE No. 420 (6100-64/6200-10)

RE: LETTER OF sus;Ec7 Diablo Canyon Power Plant Land Use Census November 21, 1985 MR. W. H. FUJIMOTO:

Here is a copy of the 1985 Land Use Census for Diablo Canyon Power Plant.

The only change from the 1984 census is the deletion of the garden at the residence in the east sector.

. If you have any questions, please call me.

- ,s'.

P. A. SZALINSKI P AS(551-332):mak 6605b,787y(sm)

Attachment cc w/ attach: D0 Brand /HCShaw DEJones/RWRichardson/CMKunde NLKnox(NuclearIndexer)

RWLorenz/TAMack RCThornberry/JVBoots/A0 Taylor JHWhite/A0ng l

DIABLO CANYON LAND USE CENSUS Engineering Research conducted a land use census in the vicinity of Diablo Canyon Power Plant. This census was for 1985. The land use census is required by Nuclear Regulatory Comission, Regulatory Guide 4.8

" Environmental Technical Specifications for Nuclear Power Plants" and by the Diablo Canyon Power Plant Environmental Technical Specification.

These both require that a census be conducted at least once per year during the growing season (between June 1 and October 1 for the Diablo Canyon environs). The census is to identify the nearest residence, the nearest milk animal and the nearest garden greater than 50 square meters (500 sq. ft.) producing broad leaf vegetation in each of the 16 meteorological sectors within a distance of five miles.

The methods for conducting the census were: a helicopter flyover and direct contact with individual land owners or tenants. The land owners were identified from County records. The land owners and tenants were contacted between June 30 and September 30, 1984 Contact with the land owners or tenants identified no household gardens

greater than 500 square feet. No milk animals were identified on these properties. These contacts were made either personally or by phone. In addition much of the area surrounding the plant site is used for cattle 4 grazing and there is a farm in the eastsoutheast sector (along the site access road) producing legumes and cereal grass (grains).

Results The attached table and map sumarize the land use census results. No milk animals were identified within the first five miles in any sector. The only garden or f arm greater than 500 square feet is in the eastsoutheast sectors. The f arm is on the coastal plateau; it starts at approximately two miles from the plant and extends to 4.5 miles from the plant. The nearest rc '!m ee is 1.55 miles north northwest of the plant. A total of nine permanent raidences were identified within five miles of the plant.

6563b 786y idb/mak

T i

TABLE 1 LAND USE CENSUS - DISTANCES IN MILES FROM THE UNIT 1 CENTER LINE TO THE NEAREST MILK ANIMAL. RESIDENCE. VEGETABLE GARDEN Nearest Residence Nearest 22-1/2 Degree (l) Nearest Residence Azimuth Vegetable Radial Sector Milk Animal km (mi) degree Garden NW None 5.95 (3.7) 326 None NNW None 2.50 (1.55) 333 None N None 7.15 (4.44) 008 None NNE None 5.30 (3.3) 018.5 None NE None 8.15 (5.06) 037 None ENE None 7.15(4.44) 062.5 None E None 7.25 (4.5) 096.5 None ESE None None- -- 2 SE None None --

None 1

(1) Sectors not shown contain no land beyond the site boundary, other than islets not used for the purposes indicated in this table.

a 6563b 786y ldb/mak

. . . _ . _,_ _ . - . _ _ ._ .__ . _ _ _ _ _ _ _ . . _ . . _ . , , . - _ . _ _ _ _ _ _ _ _ . _ . _ _ _ -_ _ _ _ _ . , . . _ _ . _ _ _ . - _ _ . . . __-

ML20137X746

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RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

RESPONSE

the total steam generator blowdown flow rate from all steam generators, in grams /sec R

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