Text

Attachment 4, Diablo Canyon Power Plant Chemical Analysis Procedure, CAP A-8 Offsite Dose Calculation Procedure, Revision 29
	ML061250124
Person / Time
Site:	Diablo Canyon
Issue date:	06/22/2005
From:	; Pacific Gas & Electric Co
To:	; Office of Nuclear Reactor Regulation
References
	DCL-06-048, OL-DPR-80, OL-DPR-82 CAP A-8, Rev 29
	Download: ML061250124 (79)
	v • d • e

Attachment 4 PG&E Letter DCL-048 Attachment 4 Diablo Canyon Power Plant Chemical Analysis Procedure, CAP A-8, "Offsite Dose Calculation Procedure," Revision 29

- - ISS'ED FOR USE BY: DATE: EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 NUCLEAR POWER GENERATION REVISION 29 DIABLO CANYON POWER PLANT PAGE 1 OF 62 CHEMICAL ANALYSIS PROCEDURE UNITS TITLE: Off-Site Dose Calculations 1 A 2 06/22/05 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION P'AGE SCOPE ......................................................................... 2 DISCUSSION ......................................................................... 3 RESPONSIBILITIES ......................................................................... 3 PREREQUISITES ......................................................................... 3 PRECAUTIONS ......................................................................... 4 INSTRUCTIONS ......................................................................... 4 Liquid Effluents ......................................................................... 4 Liquid Effluents - Dose Calculation ......................................................................... 4 10 CFR 20, Appendix B, Table 2, Column 2, Effluent (liquid) Concentration Limit (ECL) Calculation.6 Liquid Effluent Radiation Monitor Set Point Methodology ...................................................................... 7 Dose Projection (for Liquid Effluents) ........................................................................ 13 Liquid Limiting Flow Rate Methodology - ECL Based ........................................................................ 15 Liquid Limiting Flow Rates - LLD Based ........................................................................ 16 Gaseou; Effluents ........................................................................ 18 Plant Vent Noble Gas Monitor - RE-14 HASP ........................................................................ 21 Containment Purge - RE-44 HASP ........................................................................ 28 Dose To Critical Receptor Due To Radioiodines, Tritium and Particulates Released in Gaseous Effluents ........................................................................ 34 40 CFR 190 Dose Calculations ........................................................................ 42 ACCEPTANCE CRITERIA ........................................................................ 47 REFERENCSCES .............. 47 RECORDS ........... .47 APPENDICES ............ 48 ATTACHMENTS ........... 48 Table 6.1 - Typical Liquid Effluent Discharge Pathway Allocation Factors ................ .................... 8 Table 6.2 - Typical Gaseous Effluent Discharge Pathway Allocation Factors .............. .................. 20 Table 6.3 - Expected On-Site Distance and Visitation Times for Members of the Public ................ 46 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 2 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

1. SCOPE This procedure describes the methodology for the following:

Effluent RECP or RECP or Tech Spec Surveillance Requirement Implements Type Tech Spec Liquids 6.1.1.1 (RECP) Determination of alarm/trip setpoints for RE-18, 10 CFR 20 App. B 6.1.3.1 (RECP) RE-23, and RE-3 Table 2, Col. 2 Gases 6.1.2.1 (RECP) Determination of alarm/trip setpoints for RE-22, NUREG 01 ;3 6.1.6.1 (RECP) RE-14, and RE-14R Liquids 6.1.3.2 (RECP) Prerelease analyses of effluents 10 CFR 20 App. B 6.1.3.3 (RECP) Table 2, Col. 2 Postrelease analysis of effluents Liquids 6.1.4.2 (RECP) Dose calculations 10 CFR 50 App. I Liquids 6.1.5.2 (RECP) Dose projections 10 CFR 50 App. I Gases 6.1.6.2 Dose Rate calculations, Noble Gases, Total Body and NUREG 0113 Skin Gases 6.1.6.3 Dose Rate calculations, Iodines, Particulates and NUREG 0133 Radionuclides other than Noble Gases, per organ, per age group Gases 6.1.7.2 (RECP) Noble Gas Air Dose Calculations 10 CFR 50 App. I Gases 6.1.8.2 (RECP) lodines, Particulates, and Radionuclides other than 10 CFR 50 App. I Noble Gases Organ Dose Calculations per age group Gases 6.1.9.2 (RECP) Noble Gases, lodines, Particulates, and Radionuclides 10 CFR 50 App. I other than Noble Gases, Dose Projection Liquids 6.1.10.2 (RECP) Cumulative Dose from: Liquids, Noble Gases, 40 CFR 190 and 4.4.2.b.1 Iodines, Particulates, and Radionuclides other than Gases (RECP) Noble Gases per age group, per organ Direct 6.1.10.3 (RECP) Direct Radiation Dose Rate and Dose Calculations to 40 CFR 190 Radiation unrestricted areas due to plant and high radwaste storage sky-shine 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.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 3 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

2. DISCUSSION 2.1 This procedure is used in support of the Radiological Monitoring and Controls Program (RMCP), and Radioactive Effluent Controls Program (RECP), and the portion that deals with routine radioactive liquid and gaseous releases to the unrestricted area. Limits are based on the dose commitment to a member of the general public related to the release of radionuclides through either direct or indirect exposure (e.g., submersion in a cloud cf radioactive Noble Gases, radionuclides deposited on the ground, direct radiation from radionuclides stored on-site, inhalation of radionuclides or ingestion of radionuclides via a food pathway such as milk, meat, vegetable or fish, etc.).

2.2 The conduct of the Environmental Radiological Monitoring Procedure (ERMP) is found in RPL.IDI 1.

2.3 Changes to CAP A-8 shall be processed in accordance with the requirements of DCPP Technical Specification Section 5.5.1.

3. RESPONSIBILITIES 3.1 The director, chemistry is the overseeing authority of responsibility for ensuring that the off-site dose calculational procedure (ODCP) meets all RECP and Tech Spec requirements with regards to calculated doses delivered by the plant to the unrestricted area surrounding the site.

3.:2 The senior radiochemistry engineer assumes the overall responsibility for ensuring that this procedure's program is followed and implemented where appropriate, especially in regards to RECP or Tech Spec requirements.

3.:3 The radiochemistry effluents engineer has the responsibility of correct and timely implementation of all the procedure's calculational methodology, where appropriate, for each radioactive effluent released. Furthermore this engineer is responsible for:

reviewing the results; cross (spot) checking the calculations; and maintaining an updated archive of post release calculated doses for annual report purposes.

3.A The senior engineer tech maintenance computer group assures that any supporting computer software is maintained current and compatible with the procedure's calculational methodology and that the computer hardware is maintained operable at all times.

3.5 The radiochemistry staff engineer provides an oversight of the effluents program's ODCP to: confirm compliance with RECP or Tech Specs; provide technical support; recommend or design improvements to the dose calculational methodology and the effluent program control; and investigate long-term planning toward effluent related activities and their associated dose calculations.

3.6 Responsibilities as described in CYI, " Chemistry and Radiochemistry," and CYI.D('1, "Analytical Data Processing Responsibilities," apply.

4. PREREQUISITES Not Applicable 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 4 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND 2

5. PRECAUTIONS Not Applicable

6. INSTRUCTIONS 6.1 Liquid Effluents 6.1.1 Liquid Effluents - Dose Calculation 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) due to consumption of saltwater fish and saltwater invertebrate is calculated for all radionuclides identified in liquid effluents released to unrestricted areas using the following expression:

Do= FtAtzAiOCieAI (l1)

Where:

Do = The dose commitment to organ, o, in mrem.

Ft = Near field average dilution factor during the period of he release. It is defined as:

Ft Waste Flow

' Dilution Flowx Z Where:

Z Z is the site specific factor for the mixing effect of the discharge structure. Specifically, it is the credit taken ior dilution which occurs between the discharge structure and the body of water which contaminates fish or invertebrates in the liquid ingestion pathway. For DCPP Z = 5.

At = The time period for the release in hours.

Ai= The site specific ingestion dose commitment factor to organ, o, due to radionuclide, i, in mrem/hr per gCi/ml as defined by Equation 3.

C; = Concentration of radionuclide, i, in the undiluted liquid effluent, in jtCi/ml.

= Decay constant of radionuclide, i.

tm = Time interval between end of sampling and midpoint of release.

00692329.1D04, 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 5 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 The site specific ingestion dose commitment factor, A(,, is defined as:

Aio = kO(UFBF, + U1 BIi)DF; {3)

Where:

k = Units conversion factor of 1.14x 105 in units of pCi/pCi x ml/I x yr/hr.

UF = Saltwater fish consumption rate in kilograms of fish per year. DCPP value for this parameter is 21 kg/yr and is taken from NUREG 0133, Section 4.3.1.

BFi = Saltwater bioaccumulation factor for nuclide, i, in fish flesh in units of pCi/Kg per pCi/l. Values for BFi are taken from Table A-I of Reg. Guide 1.109.

U, = Saltwater invertebrate consumption rate in kilograms per years. DCPP value for this parameter is 5 kg/yr and is taken from NUREG 0133, Section 4.3.1.

BlI = Saltwater bioaccumulation factor for nuclide, i, in invertebrate flesh in units of pCi/Kg per pCi/l. Values for Bli are taken from Table A-I of Reg. Guide 1.109.

DFi = Adult ingestion dose conversion factor for nuclide, i, in mrem per pCi ingested, from Table E-1 I of Regulatory Guide 1.109, with the following exceptions: H-3, Br-:32, Sb-124 and Sb-125 ingestion dose conversion factors Ere taken from NUREG/CR4013. As-76, Sn-1 13, Sn-i 17m and Sb-122 ingestion dose conversion factors were calculated by ORNL using ICRP-2 methodology.

The site specific values for Ai. are listed in Table 10.1. When necessary, these factors were corrected for the ingrowth of daughter radionuclides following ingestion of the parent. All radionuclides treated in this manner are followed by a "+D." Reference NUREG-0172, "Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake," and A0619601.

Units I and 2 share a common liquid radwaste (LRW) treatment system. The effluent doses due to releases discharged via the common LRW are apportioned between the units with 50% credited to Unit I and 50% credited to Unit 2.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 6 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.1.2 10 CFR 20, Appendix B, Table 2, Column 2, Effluent (liquid) Concentration Limit (ECL) Calculation

a. The ECL for the identified mixture of radionuclides in the ,jthit batch of liquids is calculated as follows:

n CCy ECL = i(,4)

ECLU Where:

ECLj The unrestricted area total undiluted ECL for the

,,jth",particular mixture of identified radionucli Jes, in gCi/ml.

Cij = The concentration of radionuclide "i," in pjCi/rnl for the jith," mixture.

ECLj= The ECL in unrestricted area water for radionuclide "i," in general, in giCi/ml (from 10 CFR 20, Appendix B, Table 2, Column 2).

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 7 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

b. The overall ECL for simultaneous discharges is given by Equation 5.

E DjCj ECLoveral = jet C (5) j=, ECLj Where:

ECLove,,, = The unrestricted area ECL for the current radionuclide mixture for concurrent "j" discharges (in pjCi/ml).

Cj = The total activity concentration for the 'wjht" individual stream in ipCi/ml.

ECLj = The total ECL for the "jth individual mixture (or stream) determined as defined in Equation 4, in ItCi/ml.

Sj = The ratio of an individual discharge ,jth,, pathway flowrate to the sum total of all individual undiluted pathway flowrates as defined by:

(I If (6) fj Where:

fj = Undiluted effluent flowrate for pathway, "j" 6.1.3 Liquid Effluent Radiation Monitor Set Point Methodology

a. Introduction The DCPP radiological effluent controls program requires that the liquid effluent monitors be operable with their alarm/trip set points set to ensure that the effluent concentration limits of 10 CFR 20 are not exceeded.

The alarm/trip set point for the liquid effluent radiation monitors is derived from the concentration limit set forth in Appendix B, Table ,,

Column 2 of 10 CFR 20.1001-2404.

The alarm/trip set points are applied at the unrestricted area boundary.

The set points take into account appropriate factors for dilution, dispersion, or decay of radioactive materials that may occur between the point of discharge and the unrestricted area boundary.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 8 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

b. Allocation and Safety Factors The limits of RECP 6.1.3.1 are site limits which require that the set point methodology must ensure simultaneous releases do not exceed the liquid effluent concentration limits of 10 CFR 20 in the unrestricted area. The DCPP High Alarm Set Point (HASP) methodology makes use of an Allocation Factor (AF) to limit the effluent concentrations from simultaneous liquid discharges. The Allocation Factors can be adjusted based upon operational requirements with the restriction that the sum of the Allocation Factors must be less than or equal to 1.

Typical Allocation Factors are shown .

Table 6.1 Typical Liquid Effluent Discharge Pathway Allocation Factors Discharge Pathway Rad Monitor Allocation Factor (AF)

Oily Water Separator RE-3 0.01 Liquid Radwaste System RE-18 0.90 Steam Generator Blow Down (Unit 1) RE-23 (Ul) 0.04 Steam Generator Blow Down (Unit 2) RE-23 (U2) 0.04 Miscellaneous none 0.01 An additional level of conservatism in the HASP methodology is implemented by the use of a Safety Factor (SF). The Safety Factor i; defined as 0.9 and provides for a High Alarm Set Point at 90% of the 10 CFR 20 concentration limits.

c. Tritium Correction Factor As result of an aggressive liquid radwaste treatment program, the liquid effluents at DCPP typically contain very low levels of gamma emitters.

In order to reduce the over all volume of liquid waste discharged, DCPP also recycles waste water. This recycling results in higher tritium concentration in liquid effluents when compared with the low gamma emitter concentrations. As a result, standard HASP methodology results in very low set points. In some cases the calculated set points are barely above the monitor background.

The liquid HASP methodology used by DCPP uses a Tritium Correction Factor (TCF) which assumes a constant, but conservative tritium concentration in the liquid effluent. This results in an operationally reasonable set point while ensuring that the liquid effluent concentrations released to the unrestricted areas do not exceed the limits of 10 CFR 20.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 9 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 The Tritium Correction Factor is defined as shown in Equation 7.

TCF /ECLH. (7)

Where:

ECLI,10 effluent concentration limit of tritium C} = concentration of tritium in the release mix, pre-dilution (p~i/ml)

F conservative dilution flow rate (gpm) f conservative undiluted effluent flow rate (gpni)

The concentration of tritium, C113, is conservatively estimated.

d. Liquid Effluent Radiation Monitor Set Point Calculations The High Alarm Set Point (HASP) are calculated to ensure that the liquid effluent concentration limits of 10 CFR 20 are not exceeded. The set points represent the maximum operational set point. The actual set point used by operations will be equal to or less than the actual value as determined by the HASP methodology described in this section.

1. Set Point Methodology for RE-3 HASP: Oily Water Separator Under normal conditions, the Oily Water Separator stream does not contain any radioactive material. Only in the event that there is primary to secondary leakage does this become a potential liquid effluent discharge point. In order to insure that no unplanned cr unmonitored releases take place by way of the Oily Water Separator, RE-3 serves to monitor the discharge even when no activity has been identified in the effluent. When no significant primary to secondary leakage is taking place or when no activity has been identified in the Oily Water Separator, the High Alarm Set Point for RE-3 is calculated as shown in Equation 8.

HASPRE 3 = 3 x BKGD.,-3 (8) 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 10 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 In the event that primary to secondary leakage results in activity being detected in the Oily Water Separator, Equation 9 will be used to calculate a High Alarm Set Point value. The greater HASP value as determined by Equation 8 or Equation 9 will be used.

HASPRE-3 = BKGDRE 3 + (AFXSF)x E kZC 7 [ E i ECf x TCF ,9)

Where:

HASPRE-3 = high alarm setpoint for RE-3 (cpm)

BKGDRE-3 = background reading for RE-3 (cpm)

(AF) = allocation factor for the oily water separator effluent system from (SF) = safety factor for RE-3 (0.9) k = monitor response factor (cpm/,Ci/ml)

CY = concentration of gamma emitting isotopes in the release mix, pre-dilution (gCi/ml)

F = dilution flow rate (gpm) f = undiluted effluent flow rate (gpm)

C; = concentration of isotope "i,"in the release mix, pre-dilution (hgCi/ml)

ECLI = effluent concentration limit of isotope "i" TCF tritium correction factor as defined by Equation 7.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 11 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

2. Set Point Methodology for RE-I 8HASP: Liquid Radwaste System The High Alarm Set Point for the RE-I 8 Liquid Radwaste System liquid effluent radiation monitor is calculated as shown in Equation 10.

HASPRE-1 = BKGDPX_ 1 8 + (AFXSF)X Z kC [ Flf x TCF (1.0) i*H3 Where:

HASPRF- 18 = high alarm setpoint for RE-i 8 (cpm)

BKGDRE-18 background reading for RE-I 8 (cpm)

(AF) = allocation factor for the liquid radwaste effluent system from (SF) = safety factor for RE-18 (0.9) ky= monitor response factor (cpm/pCi/ml)

Cy = concentration of gamma emitting isotopes in the release mix, pre-dilution (pCi/ml)

F = dilution flow rate (gpm) f = undiluted effluent flow rate (gpm)

C; = concentration of isotope "i," in the release mix, pre-dilution (pCi/ml)

ECLI = effluent concentration limit of isotope "I" TCF = tritium correction factor as defined by Equation 7.

00692329.DOA 08 0527.144 1

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 12 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 ANDI 2

3. Set Point Methodology for RE-23 HASP: Steam Generator Blowdown Tank The High Alarm Set Point for the RE-23, Steam Generator Blowdown Tank liquid effluent radiation monitor, is calculated as shown in Equation I 1.

HASPR 23 =BKGD -2 3 +(AFXSF)x HASPP-23 IE-23 7

7C C

7[

F/

Ci/ECLI 1f j TCF (11)

C Where:

HASPRE-23 = high alarm setpoint for RE-23 (cpm)

BKGDRE-23 = background reading for RE-23 (cpm)

(AF) = allocation factor for the steam generator blowdown effluent system for each unit from (SF) = safety factor for RE-23 (0.9) kj = monitor response factor (cpm/pCi/ml)

G7 = concentration of gamma emitting isotopes in the release mix, pre-dilution (pCi/ml)

F = dilution flow rate (gpm) f = undiluted effluent flow rate (gpm)

C; = concentration of isotope "i," in the release mix, pre-dilution (pCi/ml)

ECLI = effluent concentration limit of isotope "i' TCF = tritium correction factor as defined by Equation 7.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 13 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.1.4 Dose Projection (for Liquid Effluents)

The projected dose contributions from each reactor unit due to liquid effluents for the current calendar month, quarter and current calendar year must be determined in accordance with the methodology and parameters in the ODCP at least once per 31 days.

The purpose of this is to determine if appropriate treatment of liquid radioactive materials in relation to maintaining releases "as low as reasonably achievable," is necessary.

The projected dose from each reactor unit is given by:

Dp = Dpu + 2 DpC0 (12)

Where:

= Projected Dose.

= Projected dose attributed to reactor unit, U.

DpCol = Projected dose common to both reactor units..

The 31-day projected dose is calculated by Equation 13.

Dp =3lxA D'Af +dc A + dcB P (13)

(T +t)

Where:

= Monthly Projected Dose DAI = Previous Month's Actual Dose

= Current Month Actual Dose to date

= Projected Dose from Current Batch Release T = Number of days in the previous month t Number of days into the present month 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 14 01 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 Projected quarterly doses are determined by Equation 14.

DP + dcQ +dcB DcQ =dCQ + (92 - t) A A P (1.4)

P A (T +t)

Where:

Dpc = Projected dose for the current calendar quarter.

dCQ = Current quarter to date actual dose.

DQ Previous quarter's actual dose.

drB = Projected dose as a result of the current batch release.

T = Number of days in the previous quarter.

t Number of days into the present quarter.

Projected yearly doses are determined by Equation 15.

D d +( 366 -)D) + dCA +Ad P- A ~(T+t) (5 Where:

Dp = Projected dose for the current calendar year.

dy Current year to date actual dose.

DA Previous year's actual dose.

dCB = Projected dose as a result of the current batch release.

T = Number of days in the previous year.

t Number of days into the present year.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO, CANYON POWER PLANT REVISION 29 PAGE 15 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.1.5 Liquid Limiting Flow Rate Methodology - ECL Based The maximum effluent flow rate through monitors RE-3, RE-I 8, and RE-23 as well as for releases from the Condensate Demineralizer Regenerate waste tank or miscellaneous release points is established in order to provide further control over the effluent releases. The release rate limit is determined by the effluent concentration and the 10 CFR 20 Effluent Concentration Limits (ECLs) as shown in Equation 16.

f =F(AFXSFXTCF) (IF6) v Ci I*j-.3 ECLj Where:

f Maximum operational undiluted liquid radwaste effluent discharge flow rate (gpm)

F = Expected dilution flow rate (gpm)

AF = allocation factor for the liquid radwaste effluent source from .

SF = safety factor (0.9).

TCF tritium correction factor as defined by Equation 7.

C; concentration of isotopes "i" in the release mix, pre-dilution (pCi/ml)

ECL, = effluent concentration limit of isotope "i" (pCi/ml)

When the term C = 0 then the Limiting Flow Rate is calculated by:

i*ll-3 ECUi f = F(AFXSFXTCF) (17)

Where the terms are as previously defined.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 16 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.1.6 Liquid Limiting Flow Rates - LLD Based When there is no primary to secondary leakage, the Oily Water Separator and various miscellaneous release points are assumed to be uncontaminated.

Furthermore, in order to establish practical operational flow rate limits for any sources when they are considered uncontaminated, Equation 18 is used. VWNhile no activity may be present, Equation 18 assumes a concentration equal to -:he Lower Limit of Detection for the nuclides listed in CY2.1D1, Appendix 6.1, Table 6.1.3-1.

f F(AFXSF)

(1.8)

4.3 Where

f = Maximum operational undiluted liquid radwaste effluent discharge flow rate (gpm)

F = Expected dilution flow rate (gpm)

AF = allocation factor for the liquid radwaste effluent source from .

SF = safety factor (0.9).

4.3 - Total ECL fraction as given by:

ELLDj i ECUS Where:

LLD, = Lower limit of detection for isotope "i" from CY2.ID1, Appendix 6.1, Table 6.1.3-1. (gCi/ml)

ECLi = effluent concentration limit of isotope "i" (gCi/ml) 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 17 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.1.7 Unplanned Liquid Releases (Abnormal Releases)

An unplanned release is an unexpected and potentially unmonitored release to the environment due to operational error or equipment malfunctions.

a. Unmonitored unplanned releases shall have a report written by the Radiochemistry Effluents Engineer describing the event with a calculation, if possible, of the percent of Tech Spec release rate limit.

This will then be forwarded to PSRC for review. Describe these unplanned releases in the Annual Radioactive Effluent Release Report.

b. Monitored unplanned releases which exceed 1%of the RECP release rate limit will also have a report written describing the event and must be forwarded to the PSRC for review. Describe these unplanned releases in the Annual Radioactive Effluent Release Report.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 18 01 62 TITLE: Off-Site Dose Calculations UNITS 1 ANli 2 6.2 Gaseous Effluents The only significant path for gaseous radioactive releases to the environment during normal operations is via the plant vent. This source is used for calculating dose rates and real-time doses to the unrestricted area due to noble gases, vaporous radioiodines and airborne radio-particulates. The plant vent also has redundant monitoring for these types of gaseous releases.

Other paths such as the steam generator blowdown tank vent, the chemistry lab fume hood, the main condenser Nash vacuum pump discharge, hot machine shop vent, etc., are considered miscellaneous release sources. These miscellaneous release sources are not continuously monitored but can have dose rates and dose calculated for their path to the unrestricted area.

6.2.1 Meteorological Methodology The equations for determining gaseous effluent concentration limits, high alarm setpoints, dose rates, and critical receptor doses make use of the historical average atmospheric conditions in accordance with methodologies of Regulatory Guides 1.109 and 1.11 1 and NUREGs 0133 and 0472. The historical average dispersion (X/Q) and deposition (D/Q) values are derivei from the methodology of Regulatory Guide 1.11 1 as implemented by NUREG 2919 (computer code XOQDOQ). The DCPP dispersion and deposition values are based on the latest five years of meteorological data and are updated when the value of X/Q or D/Q changes by more than ten percent.

The present values are listed in Table 10.2.

Long-term releases are characterized as those that are generally continuous and stable in release rate, such as normal ventilation systems effluents. Doses due to long-term releases are modeled using historical annual average dispersion and deposition values in accordance with the guidance of Regulatory Guide 1.109, Regulatory Guide 1.1 11, NUREG 0133 and NUREG 0472.

Short-term releases are defined as those which occur for a total of 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months or less in a calendar year but not more than 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months in any quarter. In accordance with NUREG 0133 and based upon an operational history that has demonstrated short term gaseous releases can be characterized as random in both time of day and duration, historical average atmospheric dispersion and deposition values are used to model doses due to short-term releases.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 19 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.2.2 Gas Effluent Concentration Limits

a. Philosophy of Concentration Limits The radiological effluent controls restrict at all times the dose rate due to radioactive materials released in gaseous effluents from the site to areas at or beyond the site boundary for noble gases to less than or equal to 500 mrem/yr to the total body and 3000 mremlyr to the skin. For iodine-131, iodine-133, tritium and for all radionuclides in particulate form with half-lives greater than 8 days, the dose rate is limited to less than or equal to 1500 mrem/yr to any organ.

These dose rate limits act to restrict at all times the instantaneous concentrations of radionuclides in gaseous effluents at the site boundary.

1. Allocation and Safety Factors The limits set forth by RECP 6.1.6.1 are site limits which require that the set point methodology must ensure simultaneous releases do not exceed the off-site dose rate limits set forth by RECP 6.1.6.1(a) and 6.1.6.1(b). The DCPP High Alarm Set Point methodology makes use of an Allocation Factor (AF) to limit the noble gas effluent dose rate from simultaneous atmospheric releases.

The Allocation Factors can be adjusted based upon operational requirements with the following restrictions:

The sum of the Allocation Factors for RE-14 (plant vent noble gas monitor), the SGBD tank vents, and miscellaneous release points from both units must be less than or equal to 1.

The Allocation Factors for RE-22 (Waste Gas Decay Tanks) and RE-44 (Containment Purge) can also be adjusted based upon operational requirements with restriction that the sum of the Allocation Factors for RE-22 and RE-44 must be less than or equal to the Allocation Factor for RE-14.

The Allocation Factors for RE-24 (Plant Vent Iodine Monitor) and RE-28 (Plant Vent Particulate Monitor) are set equal to the Allocation Factor for RE-14.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 20 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 Typical Allocation Factors are shown in.

Table 6.2 Typical Gaseous Effluent Discharge Pathway Allocation Factors Discharge Pathway Rad Monitor Allocation Factor (AF)

Plant Vent - NG Monitor RE-14 0.48 Plant Vent Iodine Monitor RE-24 0.48 Plant Vent Part Monitor RE-28 0.48 Waste Gas Decay Tank RE-22 0.10 Containment Purge RE-44 0.38 SGBD Tank Vent 0.01 Miscellaneous 0.01 An additional level of conservatism in the HASP methodology is implemented by the use of a Safety Factor (SF). The Safety Fa.ctor is defined as 0.9 and provides for a High Alarm Set Point at 90% of the dose rate limits.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 21 01' 62 TITLE: Off-Site Dose Calculations UNITS I AND 2

b. Gaseous Effluent Radiation Monitor Set Points

1. PLANT VENT NOBLE GAS MONITOR - RE-14 HASP The Plant Vent effluent stream is monitored by rad monitor RE,-14.

RE-14 provides alarm function only.

The High Alarm Set Point methodology for RE-14 is given by Equation 19, which is based upon the assumption that the total body dose rate limit is most limiting.

4MarcT(NG)= AFx Sx 500 (19) 472xFP, x(1Q7)far x 294 Where:

4 MaXCT(NG) = the maximum allowable total concentration of noble gas in the plant vent, in pCi/cc AF = the allocation factor for the plant vent for one unit from SF

= a safety factor to ensure that dose rate limits of the radiological effluent controls are not exceeded (0.9) 500 = (mrem/yr) the site Total Body dose rate limit for instantaneous releases 472 = the conversion constant to cc/sec from cfm Fp, = total flow rate in the plant vent, in cfm (maximum plant vent flow rate is 263,000 cfm)

/Ql)Ar = the maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological data base, from Table 10.2.

294 = the whole body dose factor (mrem/yrlCi/m3 ) for Xe-133 as presented in Table 10.3, (for the plant vent HASP, the release is assumed to be all Xe-133) 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO, CANYON POWER PLANT REVISION 29 PAGE 22 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

2. PLANT VENT NOBLE GAS MONITOR - RE-14 SCALING In order to correlate the readings of RE-14 to noble gas concentration during periods between samplings, the concentration is scaled according to Equation 20.

CT = CrMTX CS (

CPMS Where:

CPMT = RE-14 time weighted arithmetic mean (cpm).

CPMs = RE-14 gross count rate at the time of sampling (cpm).

Cs = Concentration of noble gas corresponding to CPM;,

based upon noble gas grab sample (ptCi/cc).

CT = Scaled concentration of noble gas (ptCi/cc).

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 23 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

3. PLANT VENT IODINE MONITOR - RE-24 The Plant Vent Iodine concentration is monitored by rad monitor RE-24. RE-24 provides alarm function only. The alarm setpoint methodology is based upon the assumption that RE-24 responds only to 1-131. The methodology also presumes a release mixture based upon the RCS source term.

The High Alarm Set Point methodology of RE-24 is given by Equation 21.

24 AfarT4(Iodine) = SF x AF x -1372 X 1500 (21)

Where:

24 MaXCT(Iodine) = the maximum allowable concentration of 1-131 in the plant vent AF = The allocation factor for the plant vent for one unit from SF = A safety factor to insure that the dose rate limits of the radiological effluent controls are not exceeded (0.9).

fl.131 = fraction of the total non-noble gas concentration that is due to 1-131. Defined as:

Af CI-131 (22)

EZi 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 24 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 1500 = (mrem/yr) the site organ dose rate limit for Iodine-131, for Iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days.

472 = the conversion constant to cc/sec from cfm Fpv = total flowrate in the plant vent, in cfm (maximum plant vent flowrate is 263,000 cfm)

= maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological database, from Table 10.2.

pI' = Inhalation dose factor for nuclide "i" (mrem/yr/pCi/m 3 ) for child age group for worst case organ, from Table 10.4. Dose factors are based upon NUREG 0133 methodology. Inhalation dose conversion factors are taken from Reg. Guide 1.109, Rev 1, Table E-9, with the following exceptions: H-3, Sb-124 and Sb-125 inhalation dose conversion factors taken from NUREG/CR-4013.

f = fraction of total non-noble gas concentration (excluding tritium) that is due to nuclide, i, and defined as:

fC.

i s (23)

>c, 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 25 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

4. PLANT VENT PARTICULATE MONITOR - RE-28 The Plant Vent Particulate concentration is monitored by rad monitor RE-28. The alarm setpoint methodology is based upo:l the assumption of a 5% cross talk from the iodine channel. This is due to the retention of a small portion of iodine on the particulate filter.

A release mixture based upon the RCS source term is also assumed.

The High Alarm Set Point methodology for RE-28 is given by Equation 24.

28AaxcT (Particulates)= AF x SF x (0.05 x Eo dm ,,es + ZPanlats E ,es )

lodines Panficuat~es 1500 (24) 4 72 x (F7,pt piWfi Where:

28 MaXCT(Particulate) = Maximum allowable particulate concentration in the plant vent AF = The allocation factor for the plant vent for one unit from SF = A safety factor to insure that the dose rate limits of the radiological effluent controls are not exceeded (0.9).

0.05 = Fraction of total iodine activity retained on particulate filter.

fiodines = Fraction of the total non-noble gas concentration that is due to iodines.

fparticulatcs = Fraction of the total non-noble gas concentration that is due to particulates.

1500 = (mrem/yr) the site organ dose rate limit for Iodine-131, for Iodine-133, for tritium, and for all radioactive materials in particulate form with half-lives greater than 8 days.

472 = Conversion constant to cc/sec from cfm FPV = Total flowrate in the plant vent, in cfm (maximum plant vent flowrate is 263,000 cfm) 00692329.DO.4 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 26 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 ANM 2 VIOL = Maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological database, from Table 10.2 piw = Inhalation dose factor for nuclide "i" (mrem/yr/J4Ci/m 3 ) for child age group for worst case organ, from Table 10.4. Dose factors are based upon NUREG 0133 methodology.

Inhalation dose conversion factors are taken from Reg. Guide 1.109, Rev 1, Table E-9, with the following exceptions: H-3, Sb-124 and Sb-125 inhalation dose conversion factors taken from NUREG/CR-4013.

fi = Fraction of total non-noble gas concentration (excluding tritium) that is due to nuclide, i, as defined by Equation 23.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 27 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

5. WASTE GAS DECAY TANK MONITOR - RE-22 HASP Effluent releases from the Waste Gas Decay Tank are monitored by rad monitor RE-22. RE-22 provides alarm and automatic release termination functions.

The High Alarm Set Point methodology for RE-22 is given by Equation 25, which is based upon the assumption that the skin dose rate limit is most limiting.

22 3000 AfavC(NG)=AF xSFx (25) 472xFh xFz/Q)- x 1.34 x 103 Where:

22 Ma-CT(NG) = the maximum allowable total concentration of noble gas in the gas decay tank exhaust line, in pCi/cc AF = the allocation factor for the waste gas decay tank for one unit from SF safety factor to ensure that dose rate limits of the radiological effluent controls are not exceeded (0.9) 3000 = (mrem/yr) the site Skin dose rate limit for instantaneous releases 472 = the conversion constant to cc/sec from cfm Fgdt = maximum flow rate for the gas decay tank system (31 cfm)

(lQ)'var = the maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological data base from Table 10.2.

1.34x 103 = the skin dose factor for Kr-85 (mremlyr/ pCi/m i, from Table 10.3.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 28 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND 2

6. CONTAINMENT PURGE - RE-44 HASP The Containment Purge is monitored by rad monitor RE-44. RE-44 provides alarm and automatic release termination functions.

The HASP for RE-44 must limit the noble gas dose rate for skin and total body exposure. In order to address this, two set points are calculated. One set point is calculated based upon limiting the total body dose rate and the other limits the skin dose rate. The mote limiting set point is used. The High Alarm Set Point methodology for RE-44 is given by Equations 26 and 27.

a) Limiting Concentration Based on Total Body Dose 500 44A4/tfarc (NG) = AF x SF x (2:6) 472xEF,,xFzQ~x~Kf Where:

44 AIBMax C(NG) = the maximum allowable total concentration of noble gas in the containment purge exhaust line, in ,uCi/cc AF = the allocation factor for the containment purge for one unit from SF = safety factor to ensure that dose rate limits of radiological effluent controls are not exceeded (0.9) 500 = (mrem/yr) the site Total Body dose rate limit For instantaneous releases 472 = the conversion constant to cc/sec from cfm Fat = maximum flow rate in the containment purge system (maximum containment purge flowrate is 55,000 cfm)

V7I-A-L =

the maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological data base averages, from Table 10.2.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 29 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 K = whole body dose factor (mrem/yr/jCi/m3 ) for isotope "i" Dose factors are presented in Table 10.3.

f = the fraction of the concentration of the individual noble gas radionuclide, "i," in the total mix of noble gas effluents in the containment purge line.

b) Limiting Concentration Based on Skin Dose Skin dose should be calculated whenever an RCS sample contains a significant fraction of Kr-85.

The concentration limit calculated by this method should then be compared to the concentration limit calculated for total body dose. The smaller concentration should be selected as the limiting concentration for the HASP.

-44A1BtavC (NG) = AF x SFx 3000 (27) 472xFc, x1Q)BGarNx E (Li + 1.*Mi)f(

Where:

44A/BMaXCT(NG) = the maximum allowable total concentration of noble gas in the plant vent in piCi/cc AF = the allocation factor for the containment purge for one unit from SF = safety factor to ensure that dose rate limits of the radiological effluent controls are not exceeded (0.9) 3000 = (mrem/yr) the site skin dose rate limit for instantaneous releases.

472 = the conversion constant to cc/sec from cfm Fc, = total flow rate in the containment purge system, in cfm (maximum containment purge flow rate is 55,000 cfm)

= the maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological data base averages, from Table 10.2.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 30 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 L = the skin dose factor (mrem/yr per PtCi/M 3 ) for isotope "i." Dose factors are presented in Table 10.3.

1.1 = Conversion factor mrem/mrad. Converts air (lose to skin dose.

M; = the gamma air dose factor (mrad/yr per piCi/mn3 )

for isotope 'i." Dose factors are presented in Table 10.3.

fi = the fraction of the concentration of the individual noble gas radionuclide, "i," in the total mix of noble gas effluents in the containment purge line.

c. Mode 6 Particulate activity.

The HASP calculation specified in this section based upon Noble Gas effluent limitations conservatively bounds the Tech. Spec. requirement for particulate activity in Mode 6. The FSAR expected case acciden: for Mode 6 is a containment fuel handling accident which does not include a particulate release. Therefore, the HASP for RM-44 in this section conservatively satisfies the Tech. Spec. (Ref.: 8.15) 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 31 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 ANI 2 6.2.3 Gaseous Dose Rate Calculation Methodology

a. Total Body Noble Gas Dose Rate Methodology The dose rate to the total body due to immersion in a cloud of noble gases is given by:

(X-Q-LEKi~j <500 mrem/year (,'8)

Where:

Q. The release rate of radionuclide i in units of GCi/sec.

All other terms are as previously defined.

b. Skin Dose Rate Methodology The dose rate to the skin due to immersion in a cloud of noble gases is given by:

(i/Q)- Cz(Li +1.lM, )Q <3000mrem/year (29)

Where the terms are as previously defined.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 32 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND 2

c. Radioiodine, Tritium and Particulate Dose Rate Methodology The dose rate to organ, o, due to radioiodines, tritium and particulates released in gaseous effluents is given by:

klQ) ZPi-Qj-1500 mremlyear (20)

Where:

Pi, = KP(BR)DFAio and K' = 106 pCi/ACi BR = The breathing rate of the a child age group in m3 /yr. The default value of 3700 m3 /yr is taken from Table E-5 of Reg. Guide 1.109.

DFA, = The inhalation dose factor for organ o, for the child age group for radionuclide, i, from Table E-9 of Reg. Guide 1.109 in mrem/pCi, with the following exceptions: H-3, Sb-124 and Sb-125 inhalation dose conversion factors taken from NUREG/CR4013.

All other terms are as previously defined.

Values for Pi, are listed in Table 10.6.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 33 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 ANli 2 6.2.4 Noble Gas Air Dose Calculation Methodology

a. Gamma Air Dose The gamma air dose due to immersion in a cloud of noble gases is given by:

Dar =3.17x 108($z/Q7)AaKMjQj (I 1)

Where:

Day = Gamma air dose in mrad.

3.1 7x 10-8 = Conversion constant yr/sec.

M; = Gamma air dose factor for nuclide i, in mrad/yr per

) Ci/m3 . Values are listed in Table 10.3.

Qj = Total release of noble gas radionuclide, i, in pCi.

All other terms are as previously defined.

b. Beta Air Dose The beta air dose due to immersion in a cloud of noble gases is given by:

Dan = 3.17x10-8(/Q-)Af.NjiQ ( 22)

Where:

Dap = Beta air dose in mrad.

Ni = Beta air dose factor for nuclide i, in mrad/yr per giCilm3 .

Values are listed in Table 10.3.

All other terms are as previously defined.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP .- 8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 34 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.2.5 Dose To Critical Receptor Due To Radioiodines, Tritium and Particulates Released in Gaseous Effluents

a. Calculation Methodology The dose to an individual (critical receptor) due to radioiodines, tritium and particulates released in gaseous effluents with half-lives greater than 8 days is determined based upon the methodology described in NUREG 0133. This methodology makes use of the maximum individual concept described in Regulatory Guide 1.109. The maximum individual is characterized as maximum with regard to food consumption, occupancy, and other usage parameters. This concept therefore models those individuals within the local population with habits representing reasonable deviations from the average. In all physiological and metabolic respects, the maximum individual is assumed to have those characteristics that represent the average for the age group of interest:.

The concept of critical receptor is introduced as a further refinement of the maximum individual. The critical receptor is defined as that individual that receives the largest dose based upon the combination of dose pathways that have been shown to actually exist. The critical receptor concept is applied at that location where the combination of dispersion (X/Q), deposition (D/Q), existing pathways, occupancy time, receptor age group, and effluent source term indicates the maximum potential exposure. The inhalation and ground plane exposure pathways are considered to exist at all locations. The grass-cow-milk, grass-cow-meat, and vegetation pathways are considered based on their actual existence in the vicinity of the plant.

The dose pathways that have been shown to actually exist at DCPP are the ground plane, inhalation and the vegetation pathways. These dose pathways are reviewed yearly and updated based upon the annual land use census survey in order to insure that actual exposure to an individual will not be substantially underestimated.

The locations of the pathways and descriptions are listed in Table 10.2.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 35 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

b. Dose Calculation The dose contributions to the total body and each individual organ (bone, liver, thyroid, kidney, lung and GI-LLI) of the maximum exposed individual (Critical Receptor) due to radioactive gaseous effluent releases is calculated for all radionuclides identified in gaseous effluents released to unrestricted areas using the following expression:

Dapo =3.17xI 0o8 WCR RaipoQi (233)

Where:

Dapo = Dose to the critical receptor for age group a, pathway p, and organ o, in mrem.

WCR = Critical receptorx/Q for immersion, inhalation and all tritium pathways (seconds/M 3 ) from Table 10.2.

= Critical receptor D/Q for ground plane and all ingestion pathways (I/M2 ) from Table 10.2.

Raipo = Site specific dose factor for age group a, radionuclide i, pathway p, and organ j (mrem/yr per ACi/m3 for inhalation and tritium pathways - mrem/yr per piCi'(sec mi2 ) for ground plane and ingestion pathways). These dose factors are listed in Table 10.6.

The site specific dose factors are calculated based upon NUREG 0133 methodology. All dose conversion factors are taken from Reg. Guide 1.109, Rev 1,Tables E6-E14, with the following exceptions: H-3, Sb-124 and Sb-125 dose conversion factors taken from NUREG/CR-40 13.

Q = The total release of radionuclide i, in units of pCi.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 36 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 ANl 2 6.2.6 Noble Gas Gaseous Radioactive Waste (GRW) Batch Release Percent Release Rate Limits (PRRLs) and Expected Reading (ER)

The Percent Release Rate Limit (PRRL) for noble gas releases for each unit is calculated based upon the 500 mrem/yr whole body dose rate limit, and is given by Equation 34.

W--Q)MKi~i PRiL= i x1% (,,4)

(0.48X500mrem/yr)

Where:

00'u'z' = The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

= Whole body dose factor (mrem/yr per P.Ci/m 3 ) for isotope "i." Dose factors are presented in Table 10.3.

= Total release rate of isotope "i" from all sources discharged through this release point in pCi/sec.

0.48 - Plant vent allocation factor for one unit from .

500 mrem/yr = Site noble gas dose rate limit.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 37 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND)2 The Expected Reading (ER) is the anticipated monitor response based upon the known plant vent concentration and the monitor response factors. The Expected Readings for RE-22, RE-44, RE-14 are given by Equations 35, $6, and 37.

ER(Pr-22) -=BKG(pg.. 22) + Ij k(E-2 iC(RE-.22) 1 (2;5)

Where:

ER(RE-22) = Expected reading on monitor RE-22 in ptCi/cc.

BKG(RE-22) = Monitor background.

k(RE-22)i = Noble gas monitor response factor for nuclide "i" for monitor RE-22.

C(RE-22) = Concentration of nuclide "i" seen by RE-22.

ER(RE-44 ) -BKG(RE- 44 ) +CCSP(RE-44 )Z:k(PE-4 4 ) jC(pr;44 )i (2,6)

Where:

ER(RE44) = Expected reading on monitor RE-44 in pCi/cc.

BKG(RE44 ) = Monitor background.

CCSP(RE44 ) = Conversion constant setpoint for monitor RE-44.

kfU44)i = Noble gas monitor response factor for nuclide "i" for monitor RE-44.

C(RE44)i =. Concentration of nuclide "i" seen by monitor RE-44.

ER(RE14 ) = BKG(REI 4 ) + CCSP(P-I 4Z(4 1 )iC(RE 14 )i (127)

Where:

ER(RE-14 ) Expected reading on monitor RE-14 in ptCi/cc.

BKG(RE.14 ) = Monitor background.

CCSP(RE-14 ) Conversion constant setpoint for monitor RE-14.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 38 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND 2 k(RE-14)i Noble gas monitor response factor for nuclide "i" for monitor RE-14.

C(RE 14); = Concentration of nuclide "i" seen by monitor RE-14.

Generally if the Expected Reading (ER) is greater than the existing HASP setting (an "administrative limit" as set by CY2.DC1) then no release should be made until a calculation shows that the HASP (Admin Limit) can be raised so the release can be legally discharged. On the other hand should the ER be less than the existing HASP (Admin Limit), then the release can be discharged.

6.2.7 IPT - PRRL The Percent Release Rate Limit (PRRL) for radioiodines, tritium and particulates for each unit is calculated based upon the 1500 mrem/yr organ dose rate limit. The dose rate is calculated for the inhalation pathway to the child age group using the highest (worst case) organ dose factor for nuclide.

The Percent Release Rate Limit based on the worst case organ is given by Equation 38.

PRRL0 = 'x 100% (Q8)

(0.48Xl500mrem/yr)

Where:

(z-Q)M = The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

paw = Inhalation dose factor for nuclide "i" (mrem/yr/+/-Ci/m 3 ) for child age group for worst case organ, from Table 10.4. Dose factors are based upon NUREG 0133 methodology.

Inhalation dose conversion factors are taken from Reg. Guide 1.109, Rev 1, Table E-9, with the following exceptions:

H-3, Sb-124 and Sb-125 inhalation dose conversion factors taken from NUREG/CR4013.

Release rate of isotope "i" in jtCi/sec.

0.48 Plant vent location factor for one unit from.

1500 mrem/yr Site radioiodine, tritium and particulate dose rate limit.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO, CANYON POWER PLANT REVISION 29 PAGE 39 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.2.8 Alternate Dose Methodologies For purposes of routine gaseous effluent dose assessment, the methodology of NUREG 0133 (described in Section 6.2.5) will be used. However, DCPP may elect to utilize the dose methodologies of Regulatory Guide 1.109 or the GASPAR computer code for special purposes such as evaluation of potential new gaseous effluent dose pathways or critical receptors.

6.2.9 Gas Effluent Dose Projection The projected dose contributions from each reactor unit due to gaseous effluents for the current calendar month, quarter and current calendar year must be determined in accordance with the methodology and parameters in the ODCP at least once per 31 days.

The computer program, Radioactive Effluent Management System (REMS), is used for this projection. Therefore, by the first day of the year, the following tables in REMS need to be updated:

GRW dose receptor

GRW dose rate receptor

GRW external dose select

GRW external occupancy

GRW internal dose select

GRW internal occupancy The purpose of this is to determine if appropriate treatment of gaseous radioactive materials in relation to maintaining releases "as low as reasonably achievable," is necessary.

The projected dose from each reactor unit is given by:

DP = DPU + 2 Dr 0conl (2'9)

Where:

D = Projected Dose.

Dp u = Projected dose attributed to reactor unit, U.

Dptom = Projected dose common to both reactor units.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP AM-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 40 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 The 31 day projected dose is calculated by Equation 40.

D =31 DXA +dcA +dCB (4.0)

Where:

D" Projected Dose for the next 31 day period.

DA" Previous Month's Actual Dose dCM Current Month Actual Dose to date dCB Projected Dose from Current Batch Release T Number of days in the previous month t Number of days into the present month Projected quarterly doses are determined by Equation 41.

DcQ dcQ +(9 2 _)DA +d +dA (41)

P A(T + )(4)

Where:

DCQ Projected dose for the current calendar quarter.

dcQ = Current quarter to date actual dose.

D -Q Previous quarter's actual dose.

dCB = Projected dose as a result of the current batch release.

T = Number of days in the previous quarter.

t = Number of days into the present quarter.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO' CANYON POWER PLANT REVISION 29 PAGE 41 01' 62 TITLE: Off-Site Dose Calculations UNITS I AND 2 Projected yearly doses are determined by Equation 42.

DCT =dcy +(366-t)DA +dc +dp Where:

Dcy Projected dose for the current calendar year.

dcy Current year to date actual dose.

Dpy Previous year's actual dose.

d CB Projected dose as a result of the current batch release.

T = Number of days in the previous year.

t = Number of days into the present year.

6.2.10 Unplanned Gaseous Releases (Abnormal Releases)

a. An unplanned release is an unexpected and potentially unmonitored release to the environment due to operational error or equipment malfunctions.

I. Unmonitored unplanned releases shall have a report written by the Radiochemistry Effluents Engineer describing the event with a calculation, if possible, of the percent of RECP limit. This will then be forwarded to PSRC for review. Describe these unplanned releases in the Annual Radioactive Effluent Release Report.

2. Monitored unplanned releases which exceed 1% of the RECP limit will also have a report written describing the event and must be forwarded to the PSRC for review. Describe these unplanned releases in the Annual Radioactive Effluent Release Report. For purposes of classification only, unplanned release puffs throug l the plant vent may use one hour integrated resolution times.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 42 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.3 40 CFR 190 Dose Calculations 6.3.1 Pathways Calculation of total uranium fuel cycle dose for purposes of demonstrating; compliance with 40 CFR 190 requires the contributions from liquid and gaseous effluent as well as direct radiation from the units and outside storage tanks to be considered. The total uranium fuel cycle dose to any member of the public will be calculated by summing the following doses:

Direct Radiation Dose

Liquid Effluent Dose

Noble Gas Dose

Radioiodine, Tritium and Particulate Gaseous Effluent Dose 6.3.2 Methodology

a. Direct Radiation Dose Determination of direct radiation dose from the reactor units and from outside storage tanks may be made by direct survey measurements, derived from environmental TLD data, or calculated by shielding code.

The direct radiation dose will also take into account residence times near the site based upon land use census information.

The direct radiation determination using environmental TLD is given by equation 43.

Ds.b. =800] IradiJ D r x(.

x (9.57)Xx e(- (6.38) (43.)

where:

D's.b. the dose rate at the site boundary, in mrem D'ro = the dose rate from the dosimetry reading, in mrem rad= the distance from the point source to the dosimetry, in meter 800 the distance from the point source to site boundary, in meter 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 43 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

b. Noble Gas Dose The noble gas skin dose and total body dose contributions to the total uranium fuel cycle dose to a member of the public will be determined as shown in Equations 44 and 45.

Noble Gas Total Body Dose = 3.17 x 10-8(z/Q)R KQ 1 (44)

Noble Gas Skin Dose = 3.17 x 10 (z/Q)RZ(Li + 1.0M,)Q (45)

Where:

3.17x10-8 = Conversion constant yr/sec.

(IQ)R = Maximum historical dispersion factor for receptor of interest, based on 5 year averages from Table 10.2.

K = Whole body dose factor for nuclide i, in mrem/yr per ptCi/m 3 . Values are listed in Table 6.3.

L = Skin dose factor for nuclide i, in mrem/yr per ACi/m 3 . Values are listed in Table 6.3.

1.1 = Conversion factor mrem/mrad. Converts air dose to skin dose.

Mi = Gamma air dose factor for nuclide i, in mrad/yr per jiCi/m3 . Values are listed in Table 10.3.

Qj = Total release of noble gas radionuclide, i, in pCi/sec. 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 44 01 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

c. Liquid and Gaseous Effluent Dose The doses from liquid effluents and radioiodines, tritium and particulates in gaseous effluents will be determined by Equations I and 33, respectively.

For purposes of calculating the dose required by the radiological effluent controls, more realistic assumptions concerning the liquid and gaseous effluent dose pathways will be used, based upon the most recent land use census data as well as the latest environmental monitoring information.

These assumptions may include, but not be limited to: more realistic liquid dilution factors, location and age of actual individuals, site specific food pathway parameters, and documentation of true food consumption. Other assumptions may be used provided they can be substantiated by census or direct measurement.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 45 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 6.4 On-Site Dose to Members of the Public Members of the public are occasionally granted access within the site boundary, but only in the owner controlled area up to the protected area boundary. The most common public access activities are: tours to the simulator (training building) or Bio Lab, policemen using the shooting range (most frequent activity), cattle drives through to adjacent properties, and visits of American Indians to on-site burial grounds (closest to the plant).

Exposure to members of the public due to liquid releases while on-site is highly unlikely and therefore not addressed. Exposure due to gaseous releases and direct radiation are credible and therefore are considered.

The dose to members of the public during on-site activities will be primarily determined by the duration of the on-site visitation time and by the closest proximity to the plant.

For gaseous releases the doses are calculated using Equations 44, 45 and 33. The Ri's; in Equation 33 consider only the inhalation and ground plane pathway and exclude the infant age group.

The X/Q and D/Q values are modified using logarithmic extrapolation from the site boundary to the on-site location of interest as shown in Equations 46 and 47.

log[X/Q]on-site log[X/Q]SB. - log[x/Q]1 oc ist.on - se)-

log(dist.S.B.) - 1og(dist loc.)[Iog~d -og~dist.S.B.)]

+ 1og[X/Q]LS.

1og[DIQ]ln ,site -

1og[D/Q]S.B. - 1og[D/Q] I- [log(dist.on- site) - log(dist.S.B.) (47) log(dist.S.B.) - log(dist.loc.)

+ Iog[D/Q9]..

Based upon Regulatory Guide 1.11 1, these equations can be expected to provide reasonable dispersion and deposition estimates for distances as close as 200 meters.

Determination of direct radiation dose from the reactor units and from outside storage tanks may be made by direct survey measurements, derived from environmental TLE:

data, or calculated by shielding code.

A distance of 200 meters from the plant (both units) equidistant from the plant vent is arbitrarily selected as the closest perimeter for which on-site doses will be calculated.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 46 OF 62 TITLE: Off-Site Dose Calculations UNITS I AND 2 The activities of the members-of-the-public while on-site (described above), are at or beyond 200 meters. details the types of on-site activities that members-of-the-public might be expected to participate in at DCPP. The sectors and closest distances in which they may visit as well as expected visitation duration are also shown (based on Security Section information).

Table 6.3 Expected On-Site Distances and Visitation Times for Members of the Public SECTOR CLOSEST POINT AVERAGE EXPECTED ONSITE MEMBER OF OF APPROACH VISITATION OF THE PUBLIC VISITATION TO PLANT TIME PER YEAR Police at SE 700m 208 hours0.00241 days 0.0578 hours 3.439153e-4 weeks 7.9144e-5 months shooting range Tour Participants Simulator Bldg S (SE) 310m 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Bio Lab SSE(SE) 460m 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Overlook E 210m I hours American Indians NW 200m 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months at burial grounds NNW 200m 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months Ranch hands driving NW 250m I hour cattle around site NNW 350m I hour N 320m I hour NNE 450m I hour NE 630m I hour 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 47 OF 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

7. ACCEPTANCE CRITERIA 7.1 There is no quantitative acceptance for this procedure. If the task or analysis has been accomplished within the bounds of this procedure, it is considered acceptable.

8. REFERENCES 8.1 License Amendment 67/66, January 22, 1992.

8.2 Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1,Regulatory Guide 1.109, Rev. 0, March 1976.

8.3 Calculation of Annual Doses to Man From Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR 50, Appendix 1, Regulatory Guide 1.109, Rev. 1,October 1977.

8.4 Preparation of Radiological Effluent Tech Specs for Nuclear Power Plants, NUREG No. 0133, October 1978.

8.5 LADTAP II - Technical Reference and User Guide, NUREG/CR-4013.

8.6 Methods for Demonstrating LWR Compliance with the EPA Uranium Fuel Cycle Standard 40 CFR 190, NUREG No. 0543, January 1980.

8.7 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.

8.8 Radioactive Decay Data Tables, David C. Kocher. DOE/TIC-1 1026, 1981.

8.9 CAP A-6, "Gaseous Radwaste Discharge Management."

8.10 CAP A-5, "Liquid Radwaste Discharge Management."

8.11 CAP D-15, "Steam Generator Leak Rate Determination."

8.12 CAP D-19, "Correlation of Rad Monitors to Radioactivity."

8.13 CY2.DC1, "Radiation Monitoring System High Alarm Setpoint Control Procedure."

8.14 CY2.1DI, "Radiological Effluent and Controls Program" (RECP) 8.15 "Setpoint Calculation for Containment Ventilation Exhaust Monitor,"

Calc # NSP-1&2-39-44, 10/92 and 11/92 and AR A0430610.

8.16 NUREG 2919, Computer Code XOQDOQ, Revision 2, September, 1982.

8.17 Technical and Ecological Services Report Number 420DC.04.46, April 2004 (XOQDOQ data) 8.18 Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, NUREG-0 172, November 1977.

8.19 Include Tc-99M In ODCM and ARER Reports, Action Request A0619601.

9. RECORD IS 9.1 Data Sheets and records will be maintained in the Records Management System (RMS) in accordance with CYI.DC1, "Analytical Data Processing Responsibilities."

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 48 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2

10. APPENDICES 10.1 Tables

11. ATIACHMENTS 11.1 "Liquid Discharges (LRW) Monitored for Radioactivity," 10/04/00 11.2 "Gaseous Releases (GRW) Monitored for Radioactivity," 10/31/00 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY I NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 49 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.1 LRW COMPOSITE DOSE FACTORS', Ai,,

FOR ADULTS AT A SALTWATER SITE (mrem/hour per ptCi/ml) organ "o" Nuiclide Tot Body Thyroid Kidney Lung GI-LLI Bone Liver H-3 1.61E-01 1.61E-01 1.61E-0I I.61E-01 1.61E-01 0.OOE+00 1.61E-01 Na-24 4.57E-01 4.57E-01 4.5713-01 4..57E-01 4.5713-01 4.57E-01 4.57E-01 Cr-51 5.58E+00 3.34E+00 1.2313+00 7.40E+00 1.40E+03 0.0013+00 0.0013+00 Mn-54 1.35E+03 O.OOE+00 2.1 OE+03 0.0013+00 2.16E+04 0.0013+00 7.06E+03 Mn-56 3.15E+01 O.OOE+00 2.26E+02 0.OOE+00 5.67E+03 O.OOE+00 1.78E+02 Fe-5f 8.23E+03 0.OOE+00 0.0013+00 I.97E+04 2.03E+04 5.1 IE+04 3.53E+04 Fe-SS, 7.27E+04 0.0013+00 O.OOE+00 5.30E+04 6.32E+05 8.06E+04 1.90E+05 Co-57 2.36E+02 0.00E+00 0.00E+00 0.00E+00 3.5913+03 0.00E+00 1.42E+02 Co-5S3 1.35E+03 O.OOE+00 0.OOE+00 0.0013+00 1.22E+04 0.0013+00 6.03E+02 Co-60) 3.82E+03 0.OOE+00 O.OOE+00 0.OOE+00 3.25E+04 O.OOE+00 1.73E+03 Ni-65 1.20E+O I 0.OOE+00 O.OOE+00 0.OOE+00 6.65E+02 2.02E+02 2.62E+0I Cu-64 1.01 E+02 0.00E+00 5.40E+02 0..OOE+00 1.83E+04 0.0013+00 2.144E+02 Zn-65 2.32E+05 O.OOE+00 3.43E+05 0..OOE+00 3.23E+05 1.61 E+05 5.1313+05 Zn-69 4.56E+0I 0.0013+00 4.26E+02 .OOE+00 9.85E+01 3.43E+02 6.56E+02 As-76) 4.42E+0 I 0.0013+00 8.7213+0 I 0..OOE+00 O.OOE+00 O.OOE+00 4.62E+01 Br-82 4.07E+00 0.00E+00 0.0013+00 0..OOE+00 4.67E+00 O.OOE+00 0.OOE+00 Br-84 9.39E-02 O.OOE+00 O.OOE+00 0..OOE+00 7.37E-07 O.OOE+00 0.0013+00 Rb-86 2.91 E+02 O.OOE+00 O.OOE+00 0..OOE+00 1.23E+02 O.OOE+00 6.24E+02 Rb-88 9.49E-0 I O.OOE+00 0.0013+00 0..OOE+00 2.47E-I I O.OOE+00 1.7913+00 Rb-8"+D 8.34E-01 O.OOE+00 O.OOE+00 0..OOE+00 6.8913-14 O.OOE+00 1.19E+00 Sr-89+D 1.43E+02 O.OOE+00 O.OOE+00 0. OOE+00 8.00E+02 4.99E+03 0.0013+00 Sr-90+D 2.83E+03 O.OOE+00 O.OOE+00 0. OOE+00 3.55E+03 1.41E+05 0.OOE+00 Sr-91 +D 3.7 1E+00 0.OOE+00 O.OOE+00 0. OOE+00 4.37E+02 9.18E+0I 0.0013+00 Sr-92+D 1.51 E+00 0.OOE+00 O.OOE+00 0. 0013+00 6.90E+02 3.48E+01 O.OOE+00 Y-90 1.63E-01 O.OOE+00 O.OOE+00 0. 0013+00 6.4213+04 6.06E+00 O.OOE+00 Y-91rn+D 2.22E-03 O.OOE+00 O.OOE+00 0. OOE+00 1.68E-01 5.73E-02 O.OOE+00 Y-92 1.56E-02 0.OOE+00 O.OOE+00 0. OOE+00 9.32E+03 5.32E-01 O.OOE+00 Zr-95+D 3.46E+00 O.OOE+00 8.02E+00 0. .OOE+00 1.62E+04 1.59E+01 5.111E+00 Zr-97+D 8.131E-02 0.00E+00 2.68E-01 0. 0013+00 5.511E+04 8.811E-01 1.78E-01 Nb-9'5 1.34E+02 O.OOE+00 2.4613+02 0. OOE+00 1.51 E+06 4.47E+02 2.49E+02 Mo-99+D 2.4313+01 O.OOE+00 2.89E+02 0. 0013+00 2.96E+02 0.0013+00 1.28E+02 Tc-101 1.88E-0 1 O.OOE+00 3.46E-0 I 9..811E-03 5.77E1-14 1.33E-02 1.92E-02 0,.

Ru-I 03+D 4.6013+01 0.00E+00 4.0713+02 0. 0OOE+00 1.2513+04 1.0713+02 0.0013+00 Ru-1 05+D 3.5 1E+00 0.0013+00 1.15E+02 0013+00 5.44E+03 8.8913+00 O.OOE+00 Ru-I 06+D 2.01 E+02 O.OOE+00 3.06E+03 0013+00 1.03E+05 1.59E+03 O.OOE+00 Ag-I 'LOm+D 8.6013+02 O.OOE+00 2.85E+03 0.1OOE+00 5.911E+05 1.5613+03 1.45E+03 Sn-I 13 3.53E+03 9.85E+02 O.OOE+00 0.i0013+00 0.0013+00 6.06E+04 1.66E+03 Sn-1 17m 8.76E+02 2.52E+02 O.OOE+00 0013+00 O.OOE+00 3.02E+03 3.41 E+02 Sb-122 6.65E+00 3.09E-0 I O.OOE+00 1.18E+01 0.0013+00 2.1913+01 4.47E-0 I Sb-124 1.09E+02 6.70E-0 I O.OOE+00 2. 15E+02 7.84E+03 2.76E+02 5.2213+00 Sb-125 4.20E+01 1.79E-01 0.OOE+00 1.:36E+02 1.94E+03 1.77E+02 1.97E+00 00692329.DO.4 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 50 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 LRW COMPOSITE DOSE FACTORS', Ai, FOR ADULTS AT A SALTWATER SITE (mrem/hour per J4Ci/ml) organ "o" Nuclide Tot Body Thyroid Kidney Lung GI-LLI Bone Liver Te-1:29m+D 1.47E+02 3.20E+02 3.89E+03 0.OOE+00 4.69E+03 9.31 E+02 3.47E+02 Te-1:29 6.19E-01 1.95E+00 1.07E+01 0.00OE+00 1.92E+00 2.541E+00 9.55E-01 Te-131m+D 5.71E+0I 1.08E+02 6.94E+02 0.OOE+00 6.80E+03 1.40E+02 6.85E+01 Te-131+D 5.03E-01 1.31E+00 6.99E+00 0.00E+00 2.26E-01 1.59E+00 6.66E-0 1 Te-1:32+D 1.24E+02 1.46E+02 1.27E+03 0.OOE+00 6.24E+03 2.04E+02 1.32E+02 I-131+D 1.79E+02 1.02E+05 5.355E+02 0.00E+00 8.23E+01 2.18E+02 3.12E+02 1-132 9.96E+00 9.96E+02 4.54E+01 0.00E+00 5.35E+00 1.06E+01 2.85E+01 I-133+D 3.95E+01 1.90E+04 2.26E+02 0.00E+00 1.16E+02 7.45E+01 1.30E+02 1-134- 5.40E+00 2.62E+02 2.40E+01 0.OOE+00 1.32E-02 5.56E+00 1.51E+01 1-13'+D 2.24E+01 4.01E+03 9.75E+01 0.OOE+00 6.87E+01 2.32E+01 6.08E+01 Cs-134 1.33E+04 0.OOE+00 5.27E+03 1.75E+03 2.85E+02 6.84E+03 1.63E+04 Cs-136 2.04E+03 0.OOE+00 1.57E+03 2.16E+02 3.211E+02 7.16E+02 2.83E+03 Cs-1:37+D 7.85E+03 0.00E+00 4.07E+03 1.35E+03 2.32E+02 8.77E+03 1.20E+04 Cs-138 5.94E+00 0.OOE+00 8.81 E+00 8.70E-01 5.12E-05 6.07E+00 1.20E+01 I

Ba-139 2.30E-01 0.OOE+00 5.23E-03 3.17E-03 1.39E+01 7.85E+00 5.59E-03 Ba-140+D 1.08E+02 0.OOE+00 7.02E-01 1.18E+00 3.38E+03 1.64E+03 2.06E+00 Ba-141+D 1.29E-01 0.00E+00 2.68E-03 1.63E-03 1.80E-09 3.81E+00 2.88E-03 La-140 2.1OE-01 0.00E+00 0.00E+00 0.OOE+00 5.83E+04 1.57E+00 7.94E-0 I La-142 9.13E-03 0.OOE+00 0.00E+00 0.OOE+00 2.68E+02 8.06E-02 3.67E-02 Ce-141 2.63E-01 0.OOE+00 1.08E+00 0.OOE+00 8.86E+03 3.43E+00 2.32E+00 Ce-1i43+D 4.94E-02 0.OOE+00 1.97E-01 0.OOE+00 1.67E+04 6.04E-01 4.46E+02 Ce-144+D Pr-144 9.59E+00 9.64E-04 0.00E+00 4.43E+01 0.00E+00 6.04E+04 1.79E+02 0.00E+00 4.44E-03 0.OOE+00 2.73E-09 1.90E-02 7.47E+01 7.87E-03 I

Nd-147+D 2.74E-01 0.OOE+00 2.68E+00 O.OOE+00 2.20E+04 3.96E+00 4.58E+00 W-lI:7 2.68E+00 0.00E+00 0.00E+00 0.00E+00 2.51 E+03 9.16E+00 7.66E+00 Np-239 1.91 E-03 0.00E+00 1.08E-02 0.OOE+00 7.11 E+02 3.53E-02 3.47E-03 1Dose factors are based upon NUREG 0133 methodology.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 51 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.2

SUMMARY

OF LAND USE CENSUS EVALUATION Sector Receptor Distance X/Q D/Q Comments Description (miles)

N none no receptors within 5 miles NNE residence + garden 4.4 5.70E-8 1.10E-10 full time occupancy residence 3.3 8.70E-8 1.80E-10 trailer - limited use residence 3.2 9.20E-8 1.90E-10 cabin - limited use NE residence 4.9 4.OOE-8 7.80E-I I full time occupancy ENE residence 4.4 3.50E-8 8.60E-I I full time occupancy residence 5.0 2.90E-8 6.80E-I I full time occupancy E residence 4.0 4.90E-8 1.50E-10 cabin - limited use residence 3.7 5.50E-8 1.70E-I0 part time occupancy residence + garden 4.5 4.IOE-8 1.20E-I0 full time occupancy ESE oat hay and sugar 3.3 1.50E-7 8.90E-10 field workers present only during the day -

peas critical receptor ground plane, inhalation, and vegetation ingestion dose assessed at this location SE none no receptors within 5 miles SSE none over water S none over water SSW none over water SW none over water WSW none over water W none over water WNW none over water NW highest site 0.5 5.90E-6 1.90E-8 Gas effluent dose rates. PRRLs and boundary HASPs evaluated at this location.

dispersion value residence 1.2 1.30E-6 4.40E-9 cabin - very limited use residence 3.6 2.40E-7 6.50E-10 full time occupancy NNW residence 1.5 7.60E-7 2.20E-9 part time occupancy (trailer) - critical receptor ground plane and inhalation dose assessed at this location Public campground 4.6 1.40E-7 3.1OE-10 Ranger Station 4.6 1.40E-07 3.10E-10 Occupied during normal work hours 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 52 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.3 GRW DOSE FACTORS FOR NOBLE GASES' Whole Body Gamma Air Beta Air Dose Factor Skin Dose Factor Dose Factor Dose Factor K; Li M i N; Radionuclide (mrem/yr per pCi/m3 ) (mrem/yr per PlCi/M3) (mrad/yr per pCi/M3) (mrad/yr per pCi/rn3 )

Kr-83m 7.56E-02 1.93E+O1 2.88E+02 Kr-85m 1.17E+03 1.46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+O I 1.95E+03 Kr-87 5.92E+03 9.73E+03 6.17E+03 1.03E+04 Kr-88 1.47E+04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E+04 1.0 IE+04 1.73E+04 1.06E+04 Kr-90 1.56E+04 7.29E+03 1.63E+04 7.83E+0 3 Xe-131m 9.15E+01 4.76E+02 1.56E+02 1.1 IE+0.3 Xe-133m 2.51 E+02 9.94E+02 3.27E+02 1.48E+0.3 Xe-133 2.94E+02 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11 E+02 3.36E+03 7.39E+02 Xe-135 1.81 E+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 9.21 E+03 4.75E+0.3 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.28E+0.3 1 From Table B-l of Regulatory Guide 1.109 (Rev. I, Oct. 1977) 00692329.DOA 08 0527.1441

PACIFIC(GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 53 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.4 CHILD INHALATION PATHWAY DOSE FACTORS FOR WORST CASE ORGAN Radionuclide Piw H-3 6.40E+02 CR-51 1.70E+04 MN-54 1.58E+06 FE-59 1.27E+06 CO-58 1.1 IE+06 CO-60 7.07E+06 ZN-65 9.95E+05 RB-86 1.98E+05 SR-89 2.16E+06 Y-90 2.68E+05 SR-90 3.85E+07 ZR-95 2.23E+06 NB-95 6.14E+05 RU-103 6.62E+05 RU-106 1.43E+07 AG-110M 5.48E+06 SB-124 3.24E+06 SB-125 2.32E+06 TE-129M 1.76E+06 1-131 1.62E+07 I-133 3.85E+06 CS-134 1.01E+06 CS-136 1.71E+05 CS-137 9.07E+05 BA-140 1.74E+06 CE-141 5.44E+05 CE-144 1.20E+07 ND-147 3.28E+05 00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 54 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.5 GROUND PLANE DOSE FACTORS GRW DOSE PARAMETERS', Ri.GP FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW),

ANY AGE GROUP, GROUND PLANE PATHWAY (mrem/yr per pCi/(sec m2 ))

Nuclide Bone Liver T Body Thyroid Kidney Lune GI-LLI H-3 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 CR-51 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65E+06 4.65 E+06 MN-54 1.38E+09 1.38E+09 1.38E+09 1.388E+09 1.38E+09 1.38E+09 1.38E1+09 FE-59 2.73E+08 2.73E+08 2.731E+08 2.73E+08 2.73E+08 2.73E+08 2.73E+08 CO-58 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 3.80E+08 CO-60 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 2.15E+10 ZN-65 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 7.46E+08 RB-86 8.98E+06 8.98E+06 8.98E+06 8.98E+06 8.98E+06 8.98E+06 8.98E-+06 SR-89 2.16E+04 2.16E+04 2.16E+04 2.166E+04 2.16E+04 2.16E+04 2.16E-+04 Y-90 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E+03 4.50E-'03 SR-90 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.0OE+00 0.00E--00 ZR-95 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E+08 2.45E1+08 NB-95 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E+08 1.37E-'-08 RU-103 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E+08 1.08E--08 RU-106 4.20E+08 4.20E+08 4.20E+08 4.20E+08 4.20E+08 4.20E+08 4.20E--08 AG-I 1OM 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E+09 3.45E--09 SB-124 5.99E+08 5.99E+08 5.99E+08 5.99E+08 5.99E+08 5.99E+08 5.99E--08 SB-125 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E+09 2.34E--09 TE-129M 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E+07 1.98E--07 1-13 1 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 1.72E+07 I-133 2.45E+06 2.45E+06 2.45E+06 2.45E1+06 2.45E+06 2.45E+06 2.45E+06 CS-134 6.90E+09 6.90E+09 6.90E+09 6.90E+09 6.90E+09 6.90E+09 6.90Ei+09 CS-136 1.51 E+08 1.511E+08 1.51 E+08 1.51 E+08 1.5 1E+08 1.511E+08 1.51 E--08 CS-137 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03E+10 1.03Ei-10 BA-140 2.05E+07 2.05E+07 2.05E+07 2.05E+07 2.05E+017 2.05E+07 2.05EE+07 CE-141 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 1.37E+07 CE-144 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 6.96E+07 ND-147 8.39E+06 8.39E+06 8.39E+06 8.39E+06 8.39E+06 8.39E+06 8.39E--06 1 Dose factors are based upon NUREG 0133 methodology.

00692329.DOA 08 0527:1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 55 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6 GRWI DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW) 00692329.DOo 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 56 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.1 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND A.NY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), INFANT AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per ptCi/m 3 ) Rj1 ,ala Nuclide Bone Liver T Body -

Thyroid -

Kidney Lung GI LLI H-3 0.OOE+00 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.68E+02 3.6813+02 CR-51 0.00E+00 0.00E+00 8.95E+01 5.75E+01 1.32E+01 1.28E+04 3.:57E+02 MN-54 0.00E+00 2.53E+04 4.98E+03 0.OOE+00 4.98E+03 1.001E+06 7.016E+03 FE-59 1.36E+04 2.35E+04 9.48E+03 0.00E+00 0.00E+00 1.02E+06 2.48E+04 CO-58 0.0013+00 1.2213+03 1.82E+03 0.0013+00 0.0013+00 7.77E+05 1.1 I E+04 CO-60 0.00E+00 8.02E+03 1.18E+04 0.OOE+00 0.00E+00 4.51 E+06 3.193E+04 ZN-65 1.93E+04 6.2613+04 3.1 1E+04 0.00E+00 3.25E+04 6.47E+05 5.14E+04 RB-86 0.001E+00 1.9013+05 8.82E+04 0.OOE+00 0.00E+00 0.0013+00 3.014E+03 SR-89 3.9813+05 0.OOE+00 1.14E+04 0.OOE+00 0.00E+00 2.03E+06 6.410E+04 Y-90 3.29E+03 0.00E+00 8.82E+01 0.00E+00 0.OOE+00 2.69E+05 1.014E+05 SR-90 1.55E+07 0.00E+00 3.12E+05 0.OOE+00 0.00E+00 1.123E+07 1.3 I E+05 ZR-95 1.15E+05 2.79E+04 2.03E+04 0.OOE+00 3.11 E+04 1.75E+06 2.1 7E+04 NB-95 1.57E+04 6.43E+03 3.78E+03 0.OOE+00 4.72E+03 4.79E+05 1.2713+04 RU-103 2.02E+03 0.00E+00 6.79E+02 0.00E+00 4.24E+03 5.52E+05 1.61E+04 RU-106 8.68E+04 0.00E+00 1.09E+04 0.00E+00 1.0713+05 1.16E+07 1.64E+05 AG-110M 9.98E+03 7.22E+03 5.0013+03 0.00E+00 1.0913+04 3.6713+06 3.30E+04 SB-124 3.79E+04 5.56E+02 1.20E+04 1.0 1 E+02 0.0013+00 2.65E+06 5.91E+04 SB-125 5.17E+04 4.77E+02 1.09E+04 6.23E+0 I 0.0013+00 1.6413+06 1.4713+04 TE-129M 1.41 E+04 6.09E+03 2.23E+03 5.47E+03 3.1813+04 1.6813+06 6.')0E+04 1-131 3.79E+04 4.44E+04 1.96E+04 1.48E+07 5.18E+04 0.0013+00 1.0(6E+03 I-133 1.32E+04 1.92E+04 5.60E+03 3.56E+06 2.24E+04 0.00E+00 2. :16E+03 CS-134 3.96E+05 7.03E+05 7.45E+04 0.00E+00 1.90E+05 7.9713+04 1.3313+03 CS-136 4.83E+04 1.35E+05 5.29E+04 0.00E+00 5.64E+04 1.18E+04 1.43E+03 CS-137 5.49E+05 6.12E+05 4.55E+04 0.00E+00 1.72E+05 7.13E+04 1.33E+03 BA-140 5.60E+04 5.60E+01 2.90E+03 0.0013+00 1.34E+01 1.60E+06 3.84E+04 CE-141 2.77E+04 1.67E+04 1.9913+03 0.00E+00 5.25E+03 5.1713+05 2.16E+04 CE-144 3.19E+06 1.21 E+06 1.76E+05 0.0013+00 5.3813+05 9.8413+06 1.4813+05 ND-147 7.94E+03 8.13E+03 5.00E+02 0.00E+00 3.15E+03 3.22E+05 3.2l2E+04 1 Dose factors are based upon NUREG 0133 methodology.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 57 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.2 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), CHILD AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per PCi/m3 ) RijIrha)

Nuclide -

Bone Liver T Body Thyroid Kidney Lung GI- LLI H-3 0.0OE+00 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.40E+02 6.410E+02 CR-51 0.OOE+00 0.OOE+00 1.54E+02 8.55E+01 2.43E+01 1.70E+04 I .08E+03 MN-54 0.OOE+00 4.29E+04 9.51 E+03 0.0OE+00 1.OOE+04 1.58E+06 2.29E+04 FE-59 2.07E+04 3.34E+04 1.67E+04 0.0OE+00 0.OOE+00 1.27E+06 7.07E+04 CO-58 0.OOE+00 1.77E+03 3.16E+03 0.00E+00 0.OOE+00 1.1I E+06 3.44E+04 CO-60 0.OOE+00 1.31 E+04 2.26E+04 0.OOE+00 0.OOE+00 7.07E+06 9.62E+04 ZN-65 4.26E+04 1.13E+05 7.03E+04 0.OOE+00 7.14E+04 9.95E+05 1.63E+04 RB-86 0.OOE+00 1.98E+05 1.14E+05 0.OOE+00 0.0OE+00 0.OOE+00 7.99E+03 SR-89 5.99E+05 0.OOE+00 1.72E+04 0.OOE+00 0.0OE+00 2.16E+06 1.67E+05 Y-90 4.1 IE+03 0.00E+00 1.1 IE+02 0.00E+00 0.OOE+00 2.62E+05 2.68E+05 SR-90 3.85E+07 0.00E+00 7.66E+05 0.OOE+00 0.00E+00 1.48E+07 3.43E+05 ZR-95 1.90E+05 4.18E+04 3.70E+04 0.OOE+00 5.96E+04 2.23E+06 6.11 E+04 NB-95 2.35E+04 9.18E+03 6.55E+03 0.OOE+00 8.62E+03 6.14E+05 3.-70E+04 RU-103 2.79E+03 0.OOE+00 1.07E+03 0.00E+00 7.03E+03 6.62E+05 4.48E+04 RU-106 _.

1.36E+05 0.OOE+00 1.69E+04 0.OOE+00 1.84E+05 1.43E+07 4.29E+05 AG-1 10M 1.69E+04 1.14E+04 9.14E+03 0.00E+00 2.12E+04 5.48E+06 1.00E+05 SB-124 5.74E+04 7.40E+02 2.0OE+04 1.26E+02 0.0OE+00 3.24E+06 1.64E+05 SB-125 9.84E+04 7.59E+02 2.07E+04 9.1 OE+0 1 0.OOE+00 2.32E+06 4.03E+04 TE-129M 1.92E+04 6.85E+03 3.04E+03 6.33E+03 5.03E+04 1.76E+06 1.82E+05 1-131 _.

4.81 E+04 4.81 E+04 2.73E+04 1.62E+07 7.88E+04 0.OOE+00 2.84E+03 1-133 1.66E+04 2.03E+04 7.70E+03 3.85E+06 3.38E+04 0.001E+00 5.48E+03 CS-134 6.51 E+05 1.OIE+06 2.25E+05 0.OOE+00 3.30E+05 1.2 1E+05 3.85E+03 CS-136 6.51E+04 1.71 E+05 1.16E+05 0.OOE+00 9.55E+04 1.45E+04 4.1. 8E+03 CS-137 9.07E+05 8.25E+05 1.28E+05 0.OOE+00 2.82E+05 1.04E+05 3.62E+03 BA-140 _.

7.40E+04 6.48E+01 4.33E+03 0.00E+00 2.1 1E+01 1.74E+06 I .02E+05 CE-141 3.92E+04 1.95E+04 2.90E+03 0.001E+00 8.55E+03 5.44E+05 5.66E+04 CE-144 6.77E+06 2.12E+06 3.61 E+05 0.OOE+00 1.17E+06 1.20E+07 3.89E+05 ND-147 _.

1.08E+04 8.73E+03 6.81E+02 0.00E+00 4.8 1E+03 3.28E+05 8.21 E+04 1 Dose factors are based upon NUREG 0133 methodology.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 58 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.3 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND A.NY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per jiCi/m3 ) R,,,,,,, 0, Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 O.OOE+00 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 7.25E+02 CR-51 O.O0E+00 0.OOE+00 1.35E+02 7.50E+01 3.07E+01 2.1 OE+04 3.00E+03 MN-54 0.00E+00 5.1 IE+04 8.40E+03 0.OOE+00 1.27E+04 1.98E+06 6.68E+04 FE-59 1.59E+04 3.70E+04 1.43E+04 0.OOE+00 0.O0E+00 1.53E+06 1.78E+05 CO-58 0.OOE+00 2.07E+03 2.78E+03 0.00E+00 0.OOE+00 1.34E+06 9.52E+04 CO-60 0.OOE+00 1.51 E+04 1.98E+04 0.00E+00 0.OOE+00 8.72E+06 2.59E+05 ZN-65 3.86E+04 1.34E+05 6.24E+04 0.00E+00 8.64E+04 1.24E+06 4.66E+04 RB-86 0.00E+00 1.90E+05 8.40E+04 0.00E+00 0.00E+00 0.OOE+00 1.77E+04 SR-89 4.34E+05 0.OOE+00 1.25E+04 0.OOE+00 0.OOE+00 2.42E+06 3.71E+05 Y-90 2.98E+03 0.00E+00 8.00E+01 0.OOE+00 0.00E+00 2.93E+05 5 .59E+05 SR-90 3.31 E+07 0.0OE+00 6.66E+05 0.OOE+00 0.OOE+00 1.65E+07 7.65E+05 ZR-95 1.46E+05 4.58E+04 3.15E+04 0.00E+00 6.74E+04 2.69E+06 1.49E+05 NB-95 1.86E+04 1.03E+04 5.66E+03 0.00E+00 I.OOE+04 7.51 E+05 9.68E+04 RU-103 2.1 OE+03 0.00E+00 8.96E+02 0.00E+00 7.43E+03 7.83E+05 1.09E+05 RU-106 9.84E+04 0.OOE+00 1.24E+04 0.00E+00 1.90E+05 1.61 E+07 9.60E+05 AG-I IOM 1.38E+04 1.31 E+04 7.99E+03 0.OOE+00 2.50E+04 6.75E+06 2.73E+05 SB-124 4.30E+04 7.94E+02 1.68E+04 9.76E+0 I 0.OOE+00 3.85E+06 3.98E+05 SB-125 7.38E+04 8.08E+02 1.72E+04 7.04E+01 0.OOE+00 2.74E+06 9.92E+04 TE-129M 1.39E+04 6.58E+03 2.25E+03 4.58E+03 5.19E+04 1.98E+06 4.05E+05 1-131 3.54E+04 4.91 E+04 2.64E+04 1.46E+07 8.40E+04 0.00E+00 6.49E+03 1-133 1.22E+04 2.05E+04 6.22E+03 2.92E+06 3.59E+04 0.00E+00 1.03E+04 CS-134 5.02E+05 1.13E+06 5.49E+05 0.OOE+00 3.75E+05 1.46E+05 9.76 E+03 CS-136 5.1 SE+04 1.94E+05 1.37E+05 0.OOE+00 1. IOE+05 1.78E+04 I.(19E+04 CS-137 6.70E+05 8.48E+05 3.1 lE+05 0.0OE+00 3.04E+05 1.21E+05 8.z.8E+03 BA-140 5.47E+04 6.70E+0 1 3.52E+03 0.0OE+00 2.28E+01 2.03E+06 2.29E+05 CE-141 2.84E+04 1.90E+04 2.17E+03 0.OOE+00 8.88E+03 6.14E+05 1.26E+05 CE-144 4.89E+06 2.02E+06 2.62E+05 0.OOE+00 1.21 E+06 1.34E+07 8.64E+05 ND-147 7.86E+03 8.56E+03 5.13E+02 0.OOE+00 5.02E+03 3.72E+05 I.E:2E+05 1 Dose factors are based upon NUREG 0133 methodology.

00692329.DO.A 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 59 01 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.4 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND A:.Y RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT AtGE GROUP, INHALATION PATHWAY ORGAN "O" (mremlyr per pCi/M3 ) Rii,,ta Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 0.00E+00 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 7.18E+02 CR-51 0.OOE+00 0.00E+00 1.00E+02 5.95E+01 2.28E+01 1.44E+04 3.32E+03 MN-54 0.00E+00 3.96E+04 6.30E+03 0.OOE+00 9.84E+03 1.40E+06 7.74E+04 FE-59 1.18E+04 2.78E+04 1.06E+04 0.OOE+00 0.00E+00 1.02E+06 1.88E+05 CO-58 0.OOE+00 1.58E+03 2.07E+03 0.00E+00 0.OOE+00 9.28E+05 1.06E+05 CO-60 0.OOE+00 1.15E+04 1.48E+04 0.OOE+00 0.00E+00 5.97E+06 2.35E+05 ZN-65 3.24E+04 1.03E+05 4.66E+04 0.OOE+00 6.90E+04 8.64E+05 5.34E+04 RB-86 0.00E+00 1.35E+05 5.90E+04 0.OOE+00 0.00E+00 0.OOE+00 1.66E+04 SR-89 3.04E+05 0.00E+00 8.72E+03 0.00E+00 0.OOE+00 1.40E+06 3.50E+05 Y-90 2.09E+03 0.OOE+00 5.61E+01 0.OOE+00 0.OOE+00 1.70E+05 5.06E+05 SR-90 2.87E+07 0.OOE+00 5.77E+05 0.OOE+00 0.00E+00 9.60E+06 7.2:2E+05 ZR-95 1.07E+05 3.44E+04 2.33E+04 0.00E-+00 5.42E+04 1.77E+06 1.50E+05 NB-95 1.41E+04 7.82E+03 4.21E+03 0.00E+00 7.74E+03 5.05E+05 1.04E+05 RU-103 1.53E+03 0.OOE+00 6.58E+02 0.00E+00 5.83E+03 5.05E+05 1.l01E+05 RU-106 6.91E+04 0.00E+00 8.72E+03 0.00E+00 1.34E+05 9.36E+06 9.12E+05 AG-110M 1.08E+04 1.00E+04 5.94E+03 0.00E+00 1.97E+04 4.63E+06 3.02E+05 SB-124 3.12E+04 5.89E+02 1.24E+04 7.55E+01 0.00E+00 2.48E+06 4.06E+05 SB-125 5.34E+04 5.95E+02 1.26E+04 5.40E+01 0.00E+00 1.74E+06 I.(I)E+05 TE-129M 9.76E+03 4.67E+03 1.58E+03 3.44E+03 3.66E+04 1.16E+06 3.83E+05 1-131 2.52E+04 3.58E+04 2.05E+04 1.19E+07 6.13E+04 0.OOE+00 6. 8E+03 1-133 8.64E+03 1.48E+04 4.52E+03 2.15E+06 2.58E+04 0.OOE+00 8.88E+03 CS-134 3.73E+05 8.48E+05 7.28E+05 0.OOE+00 2.87E+05 9.76E+04 1.04E+04 CS-136 3.90E+04 1.46E+05 1.IOE+05 0.OOE+00 8.56E+04 1.20E+04 1.1 7E+04 CS-137 4.78E+05 6.21E+05 4.28E+05 0.00E+00 2.22E+05 7.52E+04 8.40E+03 BA-140 3.90E+04 4.90E+01 2.57E+03 0.OOE+00 1.67E+01 1.27E+06 2.1 8E+05 CE-141 1.99E+04 1.35E+04 1.53E+03 0.00E+00 6.26E+03 3.62E+05 1.,!0E+05 CE-144 3.43E+06 1.43E+06 1.84E+05 0.OOE+00 8.48E+05 7.78E+06 8.1 6E+05 ND-147 5.27E+03 6.1OE+03 3.65E+02 0.00E+00 3.56E+03 2.21E+05 1.73E+05 1 Dose factors are based upon NUREG 0133 methodology.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 60 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 ANDI 2 TABLE 10.6.5 GRW DOSE PARAMETERS' FOR RADIOJODINES, RADIOACTIVE PARTICULATES, AND ANY RADION4UCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), CHILD AGE GROUP, VEGETATION PATHWAY ORGAN "O" (mrem/yr per ,uCi/(sec m 2 )) RjiVegi Nuclide Bone Liver T Body Thyroid Kidney Lune GI-LLI 7 32 0.OOE+00 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 2.29E+03 CR-51 0.OOE+00 0.0OE+00 1.17E+05 6.49E+04 1.77E+04 1.18E+05 6.20E+06 MN-54 0.OOE+00 6.65E+08 1.77E+08 0.OOE+00 1.86E+08 0.OOE+00 5.58E+08 FE-59 3.97E+08 6.42E+08 3.20E+08 0.OOE+00 0.001E+00 1.86E+08 6.69E+08 CO-58 0.OOE+00 6.45E+07 1.97E+08 0.OOE+00 0.00E+00 0.OOE+00 3.'76E+08 CO-60 0.OOE+00 3.78E+08 1.12E+09 0.00E+00 0.OOE+00 0.OOE+00 2.1 OE+09 ZN-65 8.12E+08 2.16E+09 1.35E+09 0.OOE+00 1.36E+09 0.OOE+00 3.80E+08 RB-86 0.OOE+00 4.54E+08 2.79E+08 0.00E+00 0.OOE+00 0.00E+00 2.92E+07 SR-89 3.59E+10 0.0OE+00 1.03E+09 0.00E+00 0.OOE+00 0.OOE+00 1.39E+09 Y-90 2.31 E+04 0.OOE+00 6.18E+02 0.0OE+00 0.OOE+00 0.00E+00 6.!57E+07 SR-90 1.87E+12 0.OOE+00 3.77E+10 0.00E+00 0.OOE+00 0.OOE+00 I .67E+10 ZR-95 3.86E+06 8.50E+05 7.56E+05 0.OOE+00 1.22E+06 0.OOE+00 8.86E+08 NB-95 4.12E+05 1.61E+05 1.15E+05 0.OOE+00 1.51E+05 0.OOE+00 2.97E+08 RU-103 1.53E+07 0.OOE+00 5.89E+06 0.OOE+00 3.86E+07 0.00E+00 3.96E+08 RU-106 7.45E+08 0.OOE+00 9.30E+07 0.OOE+00 1.01 E+09 0.OOE+00 1.:16E+10 AG-110M 3.21 E+07 2.17E+07 1.74E+07 0.00E+00 4.04E+07 0.00E+00 2.'i8E+09 SB-124 3.52E+08 4.57E+06 1.23E+08 7.78E+05 0.OOE+00 1.96E+08 2.20E+09 SB-125 4.99E+08 3.85E+06 I .OSE+08 4.62E+05 0.OOE+00 2.78E+08 1.]9E+09 TE-129M 8.40E+08 2.35E+08 1.30E+08 2.71 E+08 2.47E+09 0.00E+00 1.02E+09 1-131 1.43E+08 1.44E+08 8.17E+07 4.75E+1 0 2.36E+08 0.001E+00 1.,28E+07 1-133 3.52E+06 4.36E+06 1.65E+06 8.09E+08 7.26E+06 0.00E+00 1.,6E+06 CS-134 1.60E+10 2.63E+I0 5.55E+09 0.OOE+00 8.16E+09 2.931E+09 1.42E+08 CS-136 8.18E+07 2.25E+08 1.46E+08 0.OOEf00 1.20E+08 1.79E+07 7.90E+06 CS-137 2.39E+10 2.29E+10 3.38E+09 0.00E+00 7.46E+09 2.68E+09 1.43E+08 BA-140 2.77E+08 2.43E+05 1.62E+07 0.OOE+00 7.90E+04 1.45E+05 1.40E+08 CE-141 6.55E+05 3.27E+05 4.85E+04 0.00E+00 1.43E+05 0.OOE+00 4.08E+08 CE-144 1.27E+08 3.98E+07 6.78E+06 0.OOE+00 2.21E+07 0.OOE+00 1.04E+10 ND-147 7.27E+04 5.89E+04 4.56E+03 0.OOE+00 3.23E+04 0.OOE+00 9.33E+07 1 Dose factors are based upon NUREG 0133 methodology.

2 For Tritium the units of the dose parameters are mrem/yr per ,uCi/m3 for all pathways, and they must be multiplied by X/Q.

00692329.DOA 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 61 01' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.6 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE GROUP, VEGETATION PATHWAY ORGAN "O" (mrem/yr per piCi/(sec m2 )) RjVegi Nuclide __

Bone Liver TBody Thyroid Kidney Lung GI-LLI 0.OOE+00 1.47E+03 1.47E+03 1.47E+03 1.47E+03 1.47E+03 I1.47E+03 CR-51 0.OOE+00 0.OOE+00 6.16E+04 3.42E+04 1.35E+04 8.79E+04 1.03E+07 MN-54 0.OOE+00 4.54E+08 9.01 E+07 0.OOE+00 1.36E+08 0.00E+00 9.32E+08 FE-59 1.79E+08 4.18E+08 1.61 E+08 0.OOE+00 0.OOE+00 1.32E+08 9.39E+08 CO-58 0.OOE+00 4.37E+07 1.0OIE+08 0.OOE+00 0.00E+00 0.OOE+00 6.02E+08 CO-60 0.00E+00 2.49E+08 5.60E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.24E+09 ZN-65 4.24E+08 1.47E+09 6.86E+08 0.00E+00 9.41 E+08 0.00E+00 6.23E+08 RB-86 0.00E+00 2.75E+08 1.29E+08 0.OOE+00 0.00E+00 0.OOE+00 4.06E+07 SR-89 I.51E+10 0.OOE+00 4.33E+08 0.0OE+00 0.OOE+00 0.00E+00 I .80E+09 Y-90 1.24E+04 0.OOE+00 3.35E+02 0.OOE+00 0.OOE+00 0.OOE+00 1.02E+08 SR-90 9.22E+I I 0.OOE+00 1.84E+10 0.OOE+00 0.OOE+00 0.001E+00 2.:11E+10 ZR-95 1.72E+06 5.44E+05 3.74E+05 0.OOE+00 7.99E+05 0.OOE+00 1.26E+09 NB-95 1.93E+05 1.07E+05 5.90E+04 0.OOE+00 1.04E+05 0.0OE+00 4.';8E+08 RU-103 6.82E+06 0.OOE+00 2.91 E+06 0.OOE+00 2.40E+07 0.00E+00 5.6(9E+08 RU-106 3.09E+08 0.00E+00 3.90E+07 0.001E+00 5.97E+08 0.00E+00 1.48E+10 AG-110M 1.52E+07 1.44E+07 8.73E+06 0.00E+00 2.74E+07 0.00E+00 4.031E+09 SB-124 1.SSE+08 2.85E+06 6.03E+07 3.51E+05 0.001E+00 1.35E+08 3.: 1E+09 SB-125 2.14E+08 2.34E+06 5.01 E+07 2.05E+05 0.OOE+00 1.88E+08 I .67E+09 TE-129M 3.61E+08 1.34E+08 5.72E+07 1.17E+08 1.5 1E+09 0.OOE+00 1.36E+09 I-131 7.68E+07 1.08E+08 5.78E+07 3.14E+10 1.85E+08 0.OOE+00 2.1.3E+07 1-133 1.93E+06 3.28E+06 I1.OOE+06 4.58E+08 5.75E+06 0.00E+00 2.48E+06 CS-134 7.10E+09 1.67E+10 7.75E+09 0.OOE+00 5.31 E+09 2.03E+09 2.08E+08 CS-136 4.35E+07 1.71E+08 1.I 5E+08 0.00E+00 9.31E+07 1.47E+07 1.3;8E+07 CS-137 1.01E+10 1.35E+10 4.69E+09 0.OOE+00 4.59E+09 1.78E+09 1.92E+08 BA-140 1.38E+08 1.69E+05 8.90E+06 0.OOE+00 5.74E+04 1.14E+05 2.i33E+08 CE-141 2.831E+05 1.89E+05 2.17E+04 0.OOE+00 8.89E+04 0.OOE+00 5.40E+08 CE-144 5.27E+07 2.18E+07 2.83E+06 0.00E+00 1.30E+07 0.OOE+00 1.33E+10 ND-147 3.67E+04 4.00E+04 2.39E+03 0.OOE+00 2.35E+04 0.00E+00 1.44E+08 1 Dose factors are based upon NUREG 0133 methodology.

2 For Tritium the units of the dose parameters are mrem/yr per ACi/m 3 for all pathways, and they must be multiplied by X/Q.

00692329.DO.A 08 0527.1441

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 29 PAGE 62 OF' 62 TITLE: Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.7 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT AGE GROUP, VEGETATION PATHWAY ORGAN "O"(mrem/yr per J4Ci/(sec m 2 )) RiVegi Nuclide Bone Liver T Body Thyroid Kidney Lun2 GI-LI, 2

H-3 0.OOE+00 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1.29E+03 1..29E+03 CR-51 0.OOE+00 0.OOE+00 4.64E+04 2.77E+04 1.02E+04 6.15SE+04 1.17E+f07 MN-54 0.OOE+00 3.13E+08 5.97E+07 0.00E+00 9.31 E+07 0.OOE+00 9.';8E+08 FE-59 1.26E+08 2.96E+08 1.133E+08 0.OOE+00 0.OOE+00 8.27E+07 9.37E+08 CO-58 0.OOE+00 3.08E+07 6.90E+07 0.00E+00 0.OOE+00 0.OOE+00 6.2'4E+08 CO-60 0.00E+00 1.67E+08 3.69E+08 0.OOE+00 0.OOE+00 0.OOE+00 3.14E+09 ZN-65 3.17E+08 1.0IE+09 4.56E+08 0.OOE+00 6.75E+08 0.OOE+00 6.36E+08 RB-86 0.OOE+00 2.20E+08 1.03E+08 0.OOE+00 0.OOE+00 0.OOE+00 4.34E+07 SR-89 9.95E+09 0.OOE+00 2.86E+08 0.OOE+00 0.OOE+00 0.OOE+00 I .60E+09 Y-90 1.33E+04 0.OOE+00 3.57E+02 0.OOE+00 0.OOE+00 0.OOE+00 I_ IE+08 SR-90 6.95E+I I 0.OOE+00 1.40E+10 0.OOE+00 0.00E+00 0.OOE+00 I .75E+I O ZR-95 1.18E+06 3.77E+05 2.55E+05 0.OOE+00 5.92E+05 0.OOE+00 I .,!OE+09 NB-95 1.43E+05 7.95E+04 4.27E+04 0.0OE+00 7.86E+04 0.OOE+00 4.83E+08 RU-1 03 4.77E+06 0.OOE+00 2.05E+06 0.0OE+00 1.82E+07 0.OOE+00 5.5'7E+08 RU-106 1.93E+08 0.OOE+00 2.44E+07 0.OOE+00 3.72E+08 0.OOE+00 1.25E+10 AG-I OM 1.05E+07 9.75E+06 5.79E+06 0.OOE+00 1.92E+07 0.OOE+00 3.98E+09 SB-124 1.04E+08 1.96E+06 4.1 IE+07 2.52E+05 0.OOE+00 8.08E+07 2.95E+09 SB-125 1.37E+08 1.53E+06 3.25E+07 1.39E+05 0.OOE+00 I.05E+08 l .';OE+09 TE-129M 2.5 1E+08 9.37E+07 3.97E+07 8.62E+07 1.05E+09 0.00E+00 I.,26E+09 I-13i 8.07E+07 I.15SE+08 6.62E+07 3.78E+10 1.98E+08 0.00E+00 3.05E+07 I-133 2.08E+06 3.62E+06 I. I OE+06 5.32E+08 6.31 E+06 0.OOE+00 3.,25E+06 CS-134 4.67E+09 1.1 IE+10 9.08E+09 0.0OE+00 3.59E+09 1.19E+09 1.94E+08 CS-136 4.25E+07 1.68E+08 1.21E+08 0.OOE+00 9.33E+07 1.28E+07 1.90E+07 CS-137 6.36E+09 8.70E+09 5.70E+09 0.OOE+00 2.95E+09 9.8 1E+08 1.68E+08 BA-140 1.29E+08 1.61 E+05 8.42E+06 0.OOE+00 5.49E+04 9.24E+04 2.65E+08 CE-141 1.97E+05 1.33E+05 1.5IE+04 0.00E+00 6.19E+04 0.OOE+00 5.09E+08 CE-144 3.29E+07 1.38E+07 1.77E+06 0.OOE+00 8.16E+06 0.OOE+00 1.1 lE+10 ND-147 3.37E+04 3.90E+04 2.33E+03 0.OOE+00 2.28E+04 0.OOE+00 1.87E+08 1 Dose factors are based upon NUREG 0133 methodology.

2 For Tritium the units of the dose parameters are mrem/yr per ilCi/m 3 for all pathways, and they must be multiplied by X/Q.

00692329.DOA 08 0527.1441

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00692329.DOA 08 0527.1441 00692319

Attachment rl PG&E Letter DCL-06-048 Attachment 5 Diablo Canyon Power Plant Administrative Procedure, RP2.DC2, "Radwaste Solidification Process Control Program," Revision 14

- - ISS ED FOR USE BY: DATE: EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.U C2 NUCLEAR POWER GENERATION REVISION 14 DIABLO CANYON POWER PLANT PAGE 1 OF 5 ADMINISTRATIVE PROCEDURE TITLE: Radwaste Solidification Process Control Program 11/28/05 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED SPONSORING ORGANIZATION: RADIATION PROTECTION REVIEW LEVEL: "A"

l. SCOPE 1.1 The purpose of the Radwaste Solidification Process Control Program (PCP) is to define the necessary program guidance used at the plant to ensure that activities to solidify wet radioactive waste for disposal, conform to the code of Federal and State regulations and the Waste Burial Site License criteria.

2. DISCUSSION 2.1 Solidification is the conversion of wet radioactive wastes into a form that meets shipping and burial ground requirements.

2.2 This procedure implements the requirements of 10 CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR Part 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to, waste type, waste pH, waste/l iquid/SOLIDIFICATION agent/catalyst ratios, waste oil content, waste principal chemical constituents, and mixing and curing times.

2.3 This procedure contains the individual procedures necessary to perform PCP sample solidifications.

2.4 Cement solidification will not be utilized to stabilize resin or floor drain sludges. Only NRC approved binders, state approved binders or binders submitted for state approval (e.g., Advanced Polymer) may be used to solidify resin or floor drain sludges to meet waste form stability.

3. RE SPONSIBILITIES 3.1 Station director has the overall responsibility for the solid radioactive waste activities and approves changes to the PCP.

3.2 Radiation protection manager is responsible for the implementation of the requirements of this procedure.

3.3 Radwaste engineer is responsible for the development and review of procedures relating to the requirements of this procedure.

3.4 The radwaste foreman is responsible for the implementation of procedures relating to the requirements of this procedure.

3.5 Quality is responsible for verification of compliance with the program requirements.

0 1180414.DOA 0IB 1105.0246

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 14 PAGE 2 OF 5 TITLE: Radwaste Solidification Process Control Program

4. DISTRUCTIONS 4.1 GENERAL It is the policy of the company to conscientiously apply emphasis and attention to those activities associated with generation, processing, packaging, storage and disposal of radioactive waste generated at the plant and to maintain a high level of assurance that:

radioactive waste forms meet or exceed the applicable federal and state regulations and the radioactive waste burial site license criteria.

4.1.1 Changes to this program requires submission to the US NRC in the annual Radioactive Effluent Release report for the period in which the changes were made.

4.1.2 Any major change to the solid radwaste treatment system shall be reportec to the US NRC in the annual Radioactive Effluent Release report for the period in which the change was approved. The discussion of each system change shall contain the items listed in Attachment 6.2. This information may be submitted as part of the annual FSAR update in lieu of the annual Radioactive Effluent Release report.

4.2 WET WASTE 4.2.1 LIQUID/WET WASTE Liquid/wet wastes are processed to a condition meeting shipping and disposal criteria. These criteria include requirements for immobilization, stability a.nd limits on free standing water (FSW). Specific instructions on processing and required FSW limits are contained in plant procedures and/or qualified vendor procedures.

4.2.2 CONTAINERS, SHIPPING CASKS AND PACKAGING Solid radioactive waste is processed, packaged and shipped in accordance with plant procedures and/or qualified vendor procedures. These procedures provide specific instructions which ensure the container, shipping casks, and packaging methods comply with the applicable code of federal regulations, state regulations and the radioactive waste burial site license criteria.

4.2.3 SHIPPING AND DISPOSAL Solid radioactive waste is prepared, loaded and shipped to a federal and/or state licensed radioactive waste disposal facility (burial ground) in accordance with plant procedures and/or qualified vendor procedures. These procedures provide specific instructions which ensure the shipments meet the intended burial site license requirements as well as applicable federal and state regulations.

4.2.4 SPECIMEN SAMPLES Qualified vendor procedures, approved by the station director, provide written instructions on sampling, processing and handling waste for the determination of process parameters prior to the actual full scale solidification. These procedures contain the description of the laboratory mixing methods used :For specimen sample solidification.

01180414.DOA OIB 115.24 1105.0246

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 14 PAGE 3 OF 5 TITLE: Radwaste Solidification Process Control Program 4.2.5 SOLIDIFICATION PROCESS Qualified vendors used for radioactive waste solidification are required to provide the Process Control program and written procedures. These procedures and changes thereto must be approved by the station director prior to use. Further, the vendors are required to have an NRC topical report, state approval or submittal for state approval on the waste forms which will be solidified. These documents should include:

a. Description of the solidification process.

b. Type of solidification used.

c. Process control parameters.

d. Parameter boundary conditions.

e. Proper waste form properties.

r Specific instructions to ensure the systems are operated within established process parameters.

4.2.6 SAMPLING PROGRAM FOR SOLIDIFICATION T32288 Vendors, utilized for radioactive waste solidification, are required to include in their approved procedures, requirements to sample at least every tenth batch of the same waste type to ensure solidification and to provide actions to be taken if a sample fails to verify solidification. After a test specimen failure, initial test specimens from three consecutive batches of that waste type must demonstrate solidification before testing requirements of every tenth batch can be resumed. Verification of such sampling is to be accomplished by completing Form 69-10350, "Processing Control Program (PCP) Verification."

(See Attachment 6.1.) These forms will be maintained by radiation protection and in the Records Management System (RMS). These procedures and changes thereto must be approved by the station director prior to use.

4.2.7 WASTE FORM VERIFICATION Vendors utilized to process wet wastes are required to include in their procedures provisions to verify that the solidification and/or FSW criteria in the federal and state regulations and the burial site license are met for the specific type of waste being processed.

4.2.8 CORRECTIVE ACTIONS FOR FREE STANDING WATER Vendors utilized to process wet wastes are required to include in their approved procedures provisions for correcting processed waste in which free standing water in excess of the FSW criteria is detected.

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PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 14 PAGE 4 OF 5 TITLE: Radwaste Solidification Process Control Program 4.2.9 EXOTHERMIC PROCESSES Vendors utilized for radioactive waste solidification that use an exothermi',

solidification method are required to include in their approved procedures:

a. Waste/binder temperature monitoring to mitigate the consequence of adverse exothermic reactions which may occur in the full scale solidification but might not be noticeable in the specimen tests.

b. Specific process control parameters that shall be met before capping the container.

4.:3 OILY WASTE Oily wastes are shipped to off-site processor for treatment. These processors provide the proper methods to treat oily wastes to comply with federal and state regulations and applicable burial site license criteria.

4.4 SPECIAL CASES Based upon previous industry experience, the plant foresees the potential for situations arising that may be beyond existing plant capabilities. Anticipating this possibility, provisions are made herein to accommodate such situations in a timely manner by using special techniques or processes. These special cases would be controlled as follows:

4.4.1 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.

4.4.2 The implementing procedure would receive station director approval prior to use.

4.4.3 Use of this provision and supporting information would be included in the next annual Radioactive Effluent Release report to the NRC.

4.:; REMEDIAL ACTIONS 4.5.1 For waste forms which do not meet federal, state and burial site regulations and requirements, suspension of shipment of the inadequately processed waste and correction of the PCP, procedures or processing equipment shall be performed as necessary to prevent recurrence.

4.5.2 For waste forms not prepared in accordance with the PCP, testing of the waste to verify shipping and burial site requirements shall be performed and appropriate administrative action taken to prevent recurrence.

4.6 VENDOR REPORTS T32288 4.6.1 The following are maintained in Document Control Master File, Catalog No. TK 9400/NUKEM-1.

a. US DOE Waste Form Report INEEL/EXT-04-01501, Low-Level Waste Form Qualification Testing of the NUKEM Macro encapsulation Cartridge Filters Waste Form, January 2004.

b. Topical Report TR-002, 10 CFR 61 Qualified Radioactive Waste Forms, Rev. 1.

01180414.DOA 0113 1105.0246

PACIFIC GAS AND ELECTRIC COM1PANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 14 PAGE 5 OF 5 TITLE: Radwaste Solidification Process Control Program 4.6.2 The following are maintained in Document Control Master File, Catalog No. TK 94001 DTI-1.

a. US DOE Waste Form Report INEEL/EXT-04-01505, Low-Level Waste Form Qualification Testing of the Diversified Technologies Polymer Waste Form, January 2004.

b. Topical Report DTI-VERI-100-NP-A, VERIfm (Vinyl Ester Resin In Situ) Solidification Process for Low-Level Radioactive Waste, Rev l.

c. Topical Report DT-VERI-100-NP-A, Addenduml.ENCAP Encapsulation Utilizing the VERI Solidification Process.

d. Topical Report DNS-RSS-200-NP, The Dow Waste Solidification Process for Low-Level Radioactive Waste (Docket Number WM-82).

4.7 VENDOR PROCEDURES A roster of the currently approved vendor Process Control Program procedures is located in NPG Library/Radiation Protection/RadWaste/RW Vendor Waste Form Procedures.

5. RECORDS 5.1 Records of PCP specimen results and Form 69-10350 shall be submitted to the Records Management System on a shipment basis by container per RCP RW-4.

6. A'ITACHMENTS 6.1 Form 69-10350, "Process Control Program (PCP) Verification," 06/03/93 6.2 "Major Change to the Solid Radwaste Treatment System Evaluation," 05/24/01

7. REFERENCES 7.1 Title 10 Code of Federal Regulations.

7.:2 NUREG 0472 and 0473.

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

7.4 RP2.DC3, "Radwaste Dewatering Process Control Program."

7.5 NRC Information Notice 88-08, Chemical Reactions with Radioactive Waste Solidification Agents.

7.6 Technical Position on Waste Form, Revision 1,US NRC, January 1991.

7.7 Cement Encapsulation of Cartridge Filters to Provide Waste Form Stability Basis Document, Rev. 1, PG&E NRS Log 0087.

7.3 Encapsulation of Cartridge Filters In Vinyl Ester Styrene (VES) to Provide Waste Form Stability Basis Document, Rev. 0, PG&E NRS Log 0072.

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69-10350 06/03/93 Page I o:f I DIABLO CANYON POWER PLANT RP2.DC2 ATTACHMENT 6.1 TITLE: Process Control Program (PCP) Verification WASTE BATCH PCP DATE Number lType Passed Failed NOTES OPERATOR VERIFIER

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05/24/01 Page I of I DIABLO CANYON POWER PLANT RP2.DC2 ATTACHMENT 6.2 TITLE: Major Change to the Solid Radwaste Treatment System Evaluation

1. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

2. Suffi.-ient detailed information to totally support the reason for the change without benefit of addit ional or supplemental information;

3. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

4. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the License application and amendments thereto;

5. An evaluation of the change which shows the expected maximum exposures to a MEMBER OF THE PUBLIC in the UNRESTRICTED AREA and to the general population that differ from those previously estimated in the License application and amendments thereto;

6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluent and in solid waste, to the actual releases for the period prior to when the changes are to be made;

7. An estimate of the exposure to plant operating personnel as a result of the change; and

8. Documentation of the fact that the change was reviewed and found acceptable.

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Attachment 6 PG&E Letter DCL-06-048 Attachment 6 2005 Land Use Census

)

Attachment 6 PG&E Letter DCL-06-048 2005 LAND USE CENSUS Diablo Canyon Power Plant (DCPP) radiation protection personnel conducted a Laind Use Census in the vicinity of DCPP for 2005. The land use census is based on Nuclear Regulatory Commission (NRC) Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants" and 10 CFR 50 Appendix I, Section IV. B. 3.

DC:PP Program Directive Procedure CY2, "Radiological Monitoring and Controls Program," requires performance of a land use census.

DC:PP Interdepartmental Administrative Procedure RP1.ID11, "Environmental Radiological Monitoring Procedure," requires identification of the nearest milk animal, nearest residence, and the nearest broadleaf producing garden greater than 50 square meters (500 square feet) in each of the landward meteorological sectors within a distance of 8 kilometers (5 miles) of the plant. The land use census is conducted at least once per year during the growing season (between February 15 and December 1) for the Diablo Canyon environs.

The 2005 Land Use Census was conducted via phone interviews. Nine individual landowners or tenants were contacted on November 28, 2005.

No milk animals were identified within the first 8 kilometers (5 miles) of any sector.

The nearest residence, relative to all sectors, is a small trailer located in the NW sector about 1.93 kilometers (1.2 miles) from the plant. Ranch workers occupy this Blanchard residence approximately 1 month per year during cattle roLind-ups.

The nearest residence in each sector is summarized in Table 1.

The land use census identified two household gardens greater than 50 square meters (500 square feet) that produce broadleaf vegetation. The Read garden is approximately one-quarter acre and located in the NNE sector at 7.08 kilometers (4.41 miles). The Koonze garden is approximately 500 square feet and located in the E sector at 7.24 kilometers (4.5 miles).

Mello manages a farm on the coastal plateau, along the site access road, in the ESE sector. The farm starts at approximately 4.8 km and extends to 7.2 km (3 to 4.5 miles) from the plant. This commercial farm produces no broadleaf vegetation. The farm area is about 100 acres of land with 6 to 10 rotational plantings per year (not all 100 acres planted at any one time). Commercial crops consist of about 25 percent legumes (sugar peas) and 75 percent cereal 1

Attachment 6 PG&E Letter DCL-06-048 grass (oat hay). Less than 10 farm workers periodically occupy this area during the growing season.

MLIch of the area outside the plant site-boundary is used for rotational cattle grazing by five separate cattle operations. For purposes of this census, the five cattle ranches are called Blanchard, Sinsheimer, Read, Andre, and Mello.

Blanchard has about 120 cattle outside the plant site-boundary and utilizes the NW, NNW, N, and NNE sectors. About 80 yearling cattle were sold to mass market in 2005. Blanchard slaughtered two cattle in 2005 for personal consumption.

Additionally, Blanchard managed about 250 goats that were used for weed abatement in all landward sectors within the plant site-boundary. During 2005, approximately 200 baby goats were born and then taken to Santa Margarita, California, where they are grass fed for 1 year. After one year, the 200 yearling goats are then to be sold to mass-market auction. Blanchard did not slaughter any goats in 2005 for personal consumption.

Blanchard also managed about 60 sheep outside the plant site-boundary in the NW and NNW sectors. These sheep were sold to mass market. Blanchard did not slaughter any sheep in 2005 for personal consumption.

Sinsheimer has about 100 cattle outside the plant site-boundary in the NNE sector. These cattle were allowed to breed and about 90 calves were sold to mass market in 2005. Sinsheimer did not slaughter any cattle for personal consumption in 2005.

Read has about 150 cattle outside the plant site-boundary in the NNE sector.

Andre has about 80 cattle outside the plant site-boundary in the ENE sector.

About 80 calves were sold to mass market in 2005. Andre did not slaughter any cattle in 2005 for personal consumption.

Mello manages about 1000 cattle outside the plant site-boundary in the E, ESE, and SE sectors. Harris Ranch Beef Corporation owned these cattle and sold all of them to mass market in 2005. Mello did not slaughter any cattle in 2005 for personal consumption.

Two landowners (Johe and Andre) take wild game for personal consumption outside the plant site-boundary in the NNE, NE, and ENE sectors. This wild game consists of approximately 2 deer and 4 wild pigs per landowner.

There is a California State Park Ranger Office in the NNW sector at 7.483 kilometers (4.65 miles) from the plant. Approximately 3 people occupy this office from 1000 to 1500 each day per week.

2

Attachment 6 PG&E Letter DCL-06-048 There is a public campground located in the NNW sector at Montana de Oro State Park at 7.387 kilometers (4.59 miles). This campground is near Spooner's Cove.

A total of 14 residences were identified within the 8-kilometer (5-mile) radius of the plant, which were confirmed or appear to be occupied during 2005. Two abandoned structures are located in each of the NNW and NNE sectors.

Table 1 summarizes the nearest residence location in each meteorological sector.

Figure 3 shows the location of the residences and gardens in the vicinity of DC:PP.

3

Attachment 6 PG&E Letter DCL-06-048 Table I Land Use Census 2005 Distance in Kilometers (and Miles) from the Point Located Centrally Between both Units Nearest Milk Animal, Residence, and Vegetable Garden 22% Degree Nearest Nearest Residence Nearest (a) Milk Animal Residence Azimuth Vegetable Radial Sector km (mi) Degree Garden km (m i)

NW None 1.93 (1.2) 319.5 None NNW None 2.41 (1 .5 )(b) 331 None N None None None NNE None 5.21 (3.2) 019.8 7.08 (4.4)

.4 (

NE None 7.89 (4.9) 036 None ENE None 7.08 (4.4) 063.5 None E None 5.95 (3.7) 097.5 7.24 4.5)

ESE None None _ 5.31 (3.3)

SE None None None Table Notation:

(a) Sectors not shown contain no land (other than islets not used for the purposes indicated in this table) beyond the site-boundary.

(b) Blanchard residence will remain as full-time residence for critical receptor calculations even though actual occupation is part-time.

Reason is for conservative approach.

(c) The Read vegetable garden is located in the NNE sector and located at the 020 azimuth degree. There is also a full time residence at this location.

(d) The Koonze vegetable garden is located in the E sector and located at the 098 azimuth degree. There is also a full time residence at this location.

(e) The Mello garden is the commercial farm along the westward side of the site access road; however, it does not produce broadleaf vegetation. This farm extends from 4.8 km to 7.2 km (3 to 4.5 miles) from the plant.

4

Attachment 6 PG&E Letter DCL-06-048 5

ML061250124

Text

4.3 Where

SUMMARY

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