ML041420378

2003 Annual Radioactive Effluent Release Report, Attachment 5 Through 8

ML041420378
Person / Time
Site:	Diablo Canyon
Issue date:	04/30/2004
From:	Pacific Gas & Electric Co
To:	Office of Nuclear Reactor Regulation
References
DCL-04-050
Download: ML041420378 (144)

Text

Attachment 5 PG&E Letter DCL-04-050 Offsite Dose Calculation Procedure (Procedure CAP A-8, Revision 26)

UCONTROLLED PROCEDURE-DO NOT USE TO PERFORM UWORI( tor"ISSUEFOR USE, *-,

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 NUCLEAR POWER GENERATION REVISION 26 DIABLO CANYON POWER PLANT PAGE 1 OF 62 CHEMICAL ANALYSIS PROCEDURE UNITS TITLE:

Off-Site Dose Calculations l

AND 2 06/04/02 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE 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 Gaseous 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 REFERENCES........................................................................

47 RECORDS................................................................................................................ 47 APPENDICES........................................................................

48 ATTACHMENTS........................................................................

48 SPONSOR........................................................................

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 vil 00692326.DOC 08 0604.0656

.UACONTROLLED PROCEDURE -'DOONOT USE TOPERFORM WORI(orISSUE OR USE V*.*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 0133 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 0133 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, Iodines, Particulates, and 10 CFR 50 App. I Radionuclides other than Noble Gases, Dose Projection Liquids 6.1.10.2 Cumulative Dose from: Liquids, Noble Gases, 40 CFR 190 and (RECP) lodines, Particulates, and Radionuclides other than Gases 4.4.2.b.1 Noble Gases per age group, per organ (RECP)

Direct 6.1.10.3 Direct Radiation Dose Rate and Dose Calculations to 40 CFR 190 Radiation (RECP) 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.

vll 00692326.DOC 08 0604.0656

U~**NCONTROLLED PROCEDURE -BDO NOT USE TO PERFORM ~WORKo~r.ISSUE FOR USE *

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 of 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 RP1.ID11.

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.

3.4 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 CYl.DCI, "Analytical Data Processing Responsibilities," apply.

4.

PREREQUISITES Not Applicable vll 00692326.DOC 08 0604.0656

UNCONTROLLEDPROCEDUREVO NOT USE TO PERFORM WORK oi ISSUE FOR USE.*;-&

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 4 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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 =FAtZA 0 C jeA" (1)

Where:

Do

=

The dose commitment to organ, o, in mrem.

F

=

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

F =

Waste Flow Dilution Flow x Z (2)

Where:

Z

=

Z is the site specific factor for the mixing effect of the discharge structure. Specifically, it is the credit taken for 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 giCi/ml as defined by Equation 3.

C;

=

Concentration of radionuclide, i, in the undiluted liquid effluent, in glCi/ml.

k

=

Decay constant of radionuclide, i.

tm

=

Time interval between end of sampling and midpoint of release.

v I 100692326.DOC 08 0604.0656

- 0.UNCONTROLLED PROCEDURE'-DONOT USE.TO PERFORMWORKor ISSUE FOR USE,

• h PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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(UFBFi + U1 BIj)DFj (3)

Where:

k.

=

Units conversion factor of 1.1 4x 105 in units of pCi/jCi x ml/l 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/I. Values for Bli are taken from Table A-I of Reg. Guide 1.109.

DFj =

Adult ingestion dose conversion factor for nuclide, i, in mrem per pCi ingested, from Table E-1 1 of Regulatory Guide 1.109, with the following exceptions: H-3, Br-82, Sb-124 and Sb-125 ingestion dose conversion factors are taken from NUREG/CR4013. As-76, Sn-l 13, Sn-l 17m and Sb-122 ingestion dose conversion factors were calculated by ORNL using ICRP-2 methodology.

The site specific values for Aio are listed in Table 10.1.

Units 1 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.

vl 100692326.DOC 08 0604.0656

,* **UNCONTROLLED PROCEDURE - DO NOT USE TO PERFORMAWORKor ISSUEFOR SE

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 "j"' batch of liquids is calculated as follows:

E Cu ECLJ n1-CY (4)

ECLY Where:

ECLj

=

The unrestricted area total undiluted ECL for the "j'll particular mixture of identified radionuclides, in plCi/ml.

Cij

=

The concentration of radionuclide "i," in pCi/ml for the "jt" mixture.

ECLij

=

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

v I 100692326.DOC 08 0604.0656

UNCONTROLLED PROCEDUBE, WO

'NOUSE TO PERFORM WORBKorISSSUEFOR USE. * *. ;.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-Z DIABLO CANYON POWER PLANT REVISION 26 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.

n ECLoverait =

C (5)

,ECLj Where:

ECLeveraji

= The unrestricted area ECL for the current radionuclide mixture for concurrent "j" discharges (in IiCi/mil).

Cj

= The total activity concentration for the "jt" individual stream in pCi/ml.

ECLj

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

(Dj

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

fj Where:

fj=

Undiluted effluent flowrate for pathway, nj".

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 2, 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.

vl 100692326.DOC 08 0604.0656

- -UNCONTROLLED PROCEDURE.-: BDONO TUSE TO PERFORM WORBKor ISSUE FOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 I0 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.

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

Oily Water Separator RE-3 0.01 Liquid Radwaste System RE-I 8 0.90 Steam Generator Blow Down (Unit 1)

RE-23 (UI) 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 is 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 I 0 CFR 20.

vl 100692326.DOC 08 0604.0656

• '9-

,.**4UNCONTROLLEDPROCEDURE-. -DO NOT USE TO PERFORM.WORK orlSSUEFORUSE A*.*;

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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{1 (

3 3 ECL H3 ]

(7)

Where:

ECLu3

=

effluent concentration limit of tritium C113

=

concentration of tritium in the release mix, pre-dilution (pCi/ml)

F

=

conservative dilution flow rate (gpm) f

=

conservative undiluted effluent flow rate (gpm)

The concentration of tritium, CH3, 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 or 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.

HASP 3 =3 x BKGD, 3 (8) vll 00692326.DOC 08 0604.0656

A !, 'UNCONTROLLED PROCEDURE -"DO NOfT UtSETOPERFORM WORor ISSUEFOR USE * *

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 k7C [

Ff x TCF (9)

J*H3 Where:

HASPR&.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 Table 6.1 (SF)

=

safety factor for RE-3 (0.9) k,

=

monitor response factor (cpm/ijCi/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)

Ci

=

concentration of isotope "i, in the release mix, pre-dilution (lCi/ml)

ECLi

=

effluent concentration limit of isotope "i" TCF

=

tritium correction factor as defined by Equation 7.

v I 100692326.DOC 08 0604.0656

UNCONTROLLED PROCEDURE -DO WOT USE TO PERFORM WORK, r ISSUEFOR USE" PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-S DIABLO CANYON POWER PLANT REVISION 26 PAGE 11 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2

2.

Set Point Methodology for RE-18 HASP:

Liquid Radwaste System The High Alarm Set Point for the RE-18 Liquid Radwaste System liquid effluent radiation monitor is calculated as shown in Equation 10.

HASPRE-18 BKGDRE-18 + (AFXSF)x ky Cy F/f x TCF (10)

Where:

HASPRE-is

=

high alarm setpoint for RE-18 (cpm)

BKGDRE.is background reading for RE-18 (cpm)

(AF)

=

allocation factor for the liquid radwaste effluent system from Table 6.1 (SF)

=

safety factor for RE-18 (0.9) ky

=

monitor response factor (cpm/nLCi/ml)

C1

=

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

F

=

dilution flow rate (gpm) f

=

undiluted effluent flow rate (gpm)

Ci

=

concentration of isotope "i," in the release mix, pre-dilution (liCi/ml)

ECLi

=

effluent concentration limit of isotope "I" TCF

=

tritium correction factor as defined by Equation 7.

vil 00692326.DOC 08 0604.0656

• • • UNCONTROLLEOPROCEDURE-DO NOT USE.TO PERFORMWORKorISSUEFOR UE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 12 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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 11.

HASPRE-23 = BKGDRE-23 + (AFXSF) x Z k C.

F/

x TCF (11) i*3 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 Table 6.1 (SF)

=

safety factor for RE-23 (0.9) k=

monitor response factor (cpm/pCi/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 (pCi/ml)

ECLi

=

effluent concentration limit of isotope "i" TCF

=

tritium correction factor as defined by Equation 7.

v I 00692326.DOC 08 060-4.0656

UNCONTROLLED PROCEDURE -DO NOT USE TO PERFORM WORK or ISSU E

FOR USE*.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-S DIABLO CANYON POWER PLANT REVISION 26 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 every 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.

Projections will be made, at least by the end of each month with attention to the frequency requirement contained in the radiological effluent controls program.

The projected dose from each reactor unit is given by:

Dp = Dpu + 1 Dp,com (12)

Where:

Dp

=

Projected Dose.

DpU

=

Projected dose attributed to reactor unit, U.

DpCom

=

Projected dose common to both reactor units.

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

D/'" +d?" +d' 8 (T+I)

Where:

Dp

=

Monthly Projected Dose D PA'

=

Previous Month's Actual Dose dc"!

=

Current Month Actual Dose to date d pc

=

Projected Dose from Current Batch Release T

=

Number of days in the previous month t

=

Number of days into the present month vll 00692326.DOC 08 0604.0656

a:-vs UNCONTROLLED PROCEDURE - DO NOT UrSE TJOPERORM WORK br ISSUEFOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 14 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Projected quarterly doses are determined by Equation 14.

DcQ=dcQ + (92-)DA +AdA A

dP Pr(T+t)

Where:

(14)

DcQ

=

Projected dose for the current calendar quarter.

=

Current quarter to date actual dose.

DPQ A

CB

=

Previous quarter's actual dose.

=

Projected dose as a result of the current batch release.

=

Number of days in the previous quarter.

T t

=

Number of days into the present quarter.

Projected yearly doses are determined by Equation 15.

Dcr =dc +(3 6 6 -)DA

+dD¶

+

8 (15)

Where:

=

Projected dose for the current calendar year.

=

Current year to date actual dose.

=

Previous year's actual dose.

=

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.

vI 100692326.DOC 08 0604.0656

K'*:*.UNCONTROLLED PROCEDURE - tDO NOOT.USE TO.PERFORM WORK-orl SSUEFOR USE *.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 15 OF 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-18, 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(AFXSFXTCF) f Ci(16) i*H ECL, 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 Table 6.1.

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 (gCi/ml)

ECLI effluent concentration limit of isotope "i" (iCifml)

When the term E ECi = 0 then the Limiting Flow Rate is calculated

IH3ECL, by:

f = F(AFXSFXTCF)

(17)

Where the terms are as previously defined.

vl 100692326.DOC 08 0604.0656

~*:*UNCONTROLLE9 PROCED URE"LJD NOT USE TO,PERFORM:WORK( or ISSUE FOR USE

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-S DIABLO CANYON POWNER PLANT REVISION 26 PAGE 16 OF 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.

While no activity may be p~resent, Equation 18 assumes a concentration equal to the Lower Limit of Detection for the nuclides listed in CY2.11)1, Appendix 6. 1, Table 6.1.3-1.

F(AFXSF)

(8 f

4.3 (8

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 Table 6. 1.

SF safety factor (0.9).

4.3

=

Total ECL fraction as given by:

LLDi

IECL, Where:

LLD, =

Lower im it of detection for isotope "i " from CY2.ID 1, Appendix 6.1, Table 6.1.3-1. (ji1i/ml)

ECLI

=

effluent concentration limit of isotope "i" (jiCi/mI) vli 00692326.DOC 08 06.05 0604.0656

UNCONTROLLED PROCEDURE

-,'DO NOT USETO PERFORMWORKrISSUE FOR USE.

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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.

vI 100692326.DOC 08 0604.0656

'UNCONTROLLED PROCEDURE -DO :NOT USE TO PERFORM WORKor 'ISSUE FOR USE '*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 18 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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 1.111 and NUREGs 0133 and 0472. The historical average dispersion (X/Q) and deposition (D/Q) values are derived from the methodology of Regulatory Guide 1.111 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 DIQ 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 1.111, NUREG 0133 and NUREG 0472.

Short-term releases are defined as those which occur for a total of 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> or less in a calendar year but not more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 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.

v I 100692326.DOC 08 0604.0656

d UCOGNT)OED PROCEDURE "P OWSO TO PERFORMOT WORK o E

USE

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 mrem/yr to the skin. For iodine-13 1, 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.

vll 00692326.DOC 08 0604.0656

NCONTROLLED PROCEDURE',DO NOTUSE

,TO PRFORM

,ORK 5r ISSEO

USE, PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 20 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Typical Allocation Factors are shown in Table 6.2.

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 Factor is defined as 0.9 and provides for a High Alarm Set Point at 90% of the dose rate limits.

vl 100692326.DOC 08 0604.0656

Ži.R-' UNCONTROLLEDPROCEDURE-DO NOT USE TO PERFORM WORK or ISSUEFOR USE '

• PACIFIC GAS ANDELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 21 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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.

14A/arC (NG) = AF x SF x

500 (19) 472xF(,

xFQ)f x 294 Where:

W 4MaXCT(NG)

= the maximum allowable total concentration of noble gas in the plant vent, in J4Ci/cc AF

= the allocation factor for the plant vent for one unit from Table 6.2 SF

= a safety factor to ensure that dose rate limits of the radiological effluent controls are not exceeded (0.9) 500

= (mremlyr) 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) i/QLs,= = 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 (mremlyr/pCi/m3) for Xe-133 as presented in Table 10.3, (for the plant vent HASP, the release is assumed to be all Xe-133) vl 100692326.DOC 08 0604.0656

"UNCONTROLLED PROCEDURE-;BDO

-NOT US T P W

OR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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.

CPMS Cr=CPM xC (20)

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 CPMs, based upon noble gas grab sample (giCi/cc).

CT

= Scaled concentration of noble gas (pCi/cc).

vl 100692326.DOC 08 0604.0656

.UNCONTROLLED PROCEDURE;- DO NOT USE ;T0 PERFORM.WORK or ISSUEFFOR USE *-**-

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 23 OF 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 I-1 31. 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,'=CT(Iodine) = SFx AF x fl-1 3 1 1500 (21) 2 4 AIXCT(Iodne)472x~,

x F~(,i/Q)

L 3 pwf, Where:

2 4 MaXCT(lodine) = the maximum allowable concentration of I-131 in the plant vent AF =

The allocation factor for the plant vent for one unit from Table 6.2 SF

=

A safety factor to insure that the dose rate limits of the radiological effluent controls are not exceeded (0.9).

firm3=

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

A-131 C 1 (22) vll 00692326.DOC 08 0604.0656

-. A-v"UNCONTROLLEO PROCEDURE-- DOWO T;USE TO P ERFORM:

6or 1SSUEFORUSE-..* :

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 Fp,

=

total flowrate in the plant vent, in cfm (maximum plant vent flowrate is 263,000 cfm)

@,IQ~fa =

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

Ptw

=

Inhalation dose factor for nuclide "i" (mremlyr/ipCilm3) 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, and defined as:

C, A

rc-(23) vI 100692326.DOC 08 0604.0656

V UNCONTROLLEDPROCEDURE-;DO JNOTUSE.TOPERFORM WORK or ISSUEFOR USE:..** :

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 25 OF 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 upon 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.

28A1OCT(Particulates)= AFxSFx (0.05x IKfafiines +

jfp i

)

lodines Particulates 1500 (24) 472 X Fx,, x FIQ-),tfE Pwf, Where:

2 "MiXCT(Particulate)

= Maximum allowable particulate concentration in the plant vent AF

= The allocation factor for the plant vent for one unit from Table 6.2 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.

flodnes

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

fpanicultes

=

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 Fpv1

= Total flowrate in the plant vent, in cfm (maximum plant vent flowrate is 263,000 cfm) vl 100692326.DOC 08 0604.0656

.* *UNCONTROLLED PROCEDURE -. DON!OTUSE TO PERFORM fWORvr.ISSUE R USF I PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 26 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 010Qtfar = Maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological database, from Table 10.2 pJw

= Inhalation dose factor for nuclide "i" (mremlyr/lCilm3) 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.

vl 100692326.DOC 08 0604.0656

l,",.

A; UNCONTROLLED'PROCEDURE-DONOTUSE TO PERFORM WORKfor 1SSUE.FOR USE;

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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.

22Afaxc (NG) =AFxSFx 3000 (25 472xF,,i X(2)MAX1.34X1O0325 Where:

22MaxCT(NG)

= the maximum allowable total concentration of noble gas in the gas decay tank exhaust line, in ACi/cc AF

= the allocation factor for the waste gas decay tank for one unit from Table 6.2 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 Fgd& = maximum flow rate for the gas decay tank system (31 cfm)

V;ZQ-)Xfax

=

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/ gCi/rn3, from Table 10.3.

vl 100692326.DOC 08 0604.0656

• 'UNCONTROLLED PROCEDURE-DO NO TUSE TO PERFORM WORK orISSUE FOR USE v PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 28 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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 more limiting set point is used. The High Alarm Set Point methodology for RE44 is given by Equations 26 and 27.

a)

Limiting Concentration Based on Total Body Dose 44AIBAf=Ca(NG)= AFxSFx 500 (26) 472xFe, xVI7Ql)m x E Kifi Where:

44A"MaCT(NG)

=

the maximum allowable total concentration of noble gas in the containment purge exhaust line, in piCi/cc AF =

the allocation factor for the containment purge for one unit from Table 6.2 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 Ft=

maximum flow rate in the containment purge system (maximum containment purge flowrate is 55,000 cfm)

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

vl 100692326.DOC 08 0604.0656

s'- NdEONROLEDPRWOCEDURE

-DO WOT USETO PERFORM WORK or ISSUE ORUS PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 29 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 K

=

whole body dose factor (mremlyrljCi/m3) 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.

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.

44AIEarCr (NG) = AF x SF x 3000 4 472x F, x /),,zx E(Li

+ 1. IM,)f Where:

4 4AIBMaxCT(NG)

=

the maximum allowable total concentration of noble gas in the plant vent in jiCi/cc AF =

the allocation factor for the containment purge for one unit from Table 6.2 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 Ft=

total flow rate in the containment purge system, in cfm (maximum containment purge flow rate is 55,000 cfm)

VI-ar

=

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

v I 100692326.DOC 08 0604.0656

UNCONTROLLED PROCEDURE-DO NOTUSE TO PERFORM WORK or ISSUEFOR USE*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-Z DIABLO CANYON POWER PLANT REVISION 26 PAGE 30 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Li

=

the skin dose factor (mremlyr per piCi/m 3) for isotope "i."

Dose factors are presented in Table 10.3.

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

M

=

the gamma air dose factor (mrad/yr per pCi/m3) 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 accident 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) vl 100692326.DOC 08 0604.0656

!t '-i a * *UNCONTROLLED PROCEDURE -: DO NOT USE TOPERFORM WORKior ISSUE FOR USE

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 31 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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:

j/Q),,,jKjQj <500 mrem/year (28)

Where:

Q

=

The release rate of radionuclide i in units of pCi/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:

ONQf.

(Li + 1.1M, )I Q <3000 mrem/year (29)

Where the terms are as previously defined.

vl 100692326.DOC 08 0604.0656

• • IUNCONTROLLED DPROCEDURE.-

Wfl OTfLTSE 1

Tf DPERFORM.WORlICSSUFFOR.USE ***

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 32 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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:

C/QX=ZPiQ,-

5 00 mrem/year (30)

Where:

Pi.

Kt(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.

DFAE

=

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.

v1 1-00692326.DOC 08 0604.0656

• 0UNCONTROLLED PROCEDURE -'DO NOT USE TO PERFORM WORK orI!SSUE FOR 'USE.,* *.'

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 33 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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 = 3.17Xl0-$(/lQ)',,zMiQi (31)

Where:

Doy

= Gamma air dose in mrad.

3.17x10-8

= Conversion constant yr/sec.

Mi

= Gamma air dose factor for nuclide i, in mrad/yr per pCi/M3. Values are listed in Table 10.3.

Q,

= 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:

Da9 =3.17x10(-IT/Q),L ZNjiQ (32)

Where:

Dap

= Beta air dose in mrad.

Ni

= Beta air dose factor for nuclide i, in mrad/yr per pCi/M3. Values are listed in Table 10.3.

All other terms are as previously defined.

vil 00692326.DOC 08 0604.0656

'UNCOSTROLLEDP.ROOEDURE

)'DO.

NOTUSETO PERFORM WORK Si'SSU FORU PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 34 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 6.2.5 Dose To Critical Receptor Due To Radioiodines, Tritiumn 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.

vll 00692326.DOC 08 0604.0656

UNCONTROLLED PROcEDURE-b DONOT USETO PERFORM WORk orISSUEFOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 = 3.17 X I 0 WCR ZRa.poQj (33)

Where:

Dapo

=

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

WCR

=

Critical receptorZ/Q for immersion, inhalation and all tritium pathways (seconds/m3) from Table 10.2.

=

Critical receptorD/Q for ground plane and all ingestion pathways (1/m2) from Table 10.2.

Rjpo,

=

Site specific dose factor for age group a, radionuclide i, pathway p, and organ j (mrem/yr per PCi/m3 for inhalation and tritium pathways - mrem/yr per piCi/(sec in2) 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-4013.

Q

=

The total release of radionuclide i, in units of glCi.

v I 100692326.DOC 08 0604.0656

,:4***. UNCONTROLLEDPROCEDURE

- DOWOT USE TO PERFORM WORKorISSUE FOR USE * **

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 36 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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.

VX/Q)4f,. E KE~

PRRL =

i x100%

(34)

(0.48X500inrem / yr)

Where:

IQLu

=

The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

=

Whole body dose factor (mremlyr per pCi/m3) 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 piCi/sec.

0.48

=

Plant vent allocation factor for one unit from Table 6.2.

500 mrem/yr =

Site noble gas dose rate limit.

vli 00692326.DOC 08 0604.0656

Af**,'-UONTROLEDPROCEDURE-

.DO WNT.USE TO PERFORM WORAoISSUEFOR USE. *-*;

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 37 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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, 36, and 37.

ER(E 22) = BKG(E 22 ) + E k(E-2 2 ) I C(E-2 2 ) E (35)

Where:

ER RE)=

Expected reading on monitor RE-22 in lCi/cc.

BKG(RE-22) =

Monitor background.

kRE-22)

=

Noble gas monitor response factor for nuclide "i" for monitor RE-22.

C(-22)

=

Concentration of nuclide "i" seen by RE-22.

ER(RE-44) =BKG(RE44) + CCSP(RE-44 )

(36)

Where:

ERRE44)=

Expected reading on monitor RE-44 in ptCi/cc.

BKGwA) =

Monitor background.

CCSP(RE4-)

=

Conversion constant setpoint for monitor RE-44.

ktRE.44)i

=

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

CE44)

=

Concentration of nuclide ";" seen by monitor RE-44.

ER(PE-14) =BKG(RE-14) + CCSP( E_14)k(RE.

14) iC(RE 14),

(37)

Where:

ER(RE-14)

=

BKG(RE.14) =

CCSP(RE-14)

=

Expected reading on monitor RE-14 in ipCi/cc.

Monitor background.

Conversion constant setpoint for monitor RE-14.

vll_00692326.DOC 08 0604.0656

,-.*f*,,..UNCONTROLLED PROCEDURE '; 00 NOTUSE TO PERFORM WORK or,SSUEFOR USE.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 38 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 k(RE.14)i

=

Noble gas monitor response factor for nuclide "i" for monitor RE-14.

CRE-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.

V7)Mo E PaQ PRRLO =

x100%

(38)

(0.48X 500mremlyr)

Where:

WX/

ax1 =

The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

Pi*

=

Inhalation dose factor for nuclide "i" (mrem/yr/g.Ci/m3) 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.

=

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

0.48

=

Plant vent location factor for one unit from Table 6.2.

1500 mrem/yr =

Site radioiodine, tritium and particulate dose rate limit.

vl 100692326.DOC 08 0604.0656

-'UNCONTROLLED PROCEDURE - DONOT, USJO PERFORM WORK1or SSUEFOR.USE'.* *.'

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 39 OF 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 every 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.

Projections will be made, at least by the end of each month with attention to the frequency requirement contained in radiological effluent controls program.

The projected dose from each reactor unit is given by:

Dp = Dp~u + 2 Dpcom (39)

Where:

Dp

=

Projected Dose.

DPU

=

Projected dose attributed to reactor unit, U.

DPCOm

=

Projected dose common to both reactor units.

vl1 00692326.DOC 08 0604.0656

D o*.* UNCONTROLLED PROCEDURE - DO NOTUSE TO PERFORM WORKoriSSUEFOR USE

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 40 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 The 31 day projected dose is calculated by Equation 40.

D'+d

+d D!'=3 1X (T+ )

(40)

Where:

Dp

=

Projected Dose for the next 31 day period.

DP"

=

Previous Month's Actual Dose da

=

Current Month Actual Dose to date dp8

=

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.

Dc=dcQ +((92T-tt))

(41)

Where:

DpcQ

=

Projected dose for the current calendar quarter.

dCQ

=

Current quarter to date actual dose.

DPQ

=

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.

vI 1-00692326.DOC 08 0604.0656

UNCONTROLLCE DURE-DOOTUSETO PERFOR WORKor S E PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 41 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Projected yearly doses are determined by Equation 42.

Dpc=dcr +(366-1)DA +d

+d(42)

A(T

+i)

(2 Where:

Dy

=

Projected dose for the current calendar year.

dcy

=

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.

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.

1.

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 through the plant vent may use one hour integrated resolution times.

vll 00692326.DOC 08 0604.0656

N*UICONTROLLED PROCEDURE9DO NOT USE TO PERFORMWORK or ISSUEFOR.USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 42 OF 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.

D sb I [

D' x(9.57)xeI-(6.38)

(43) sL. 800ir where:

D's.b. = the dose rate at the site boundary, in mrem D'eo = the dose rate from the dosimetry reading, in mrem radj = the distance from the point source to the dosimetry, in meter 800 = the distance from the point source to site boundary, in meter v1 1-00692326.DOC 08 0604.0656

" UNCONTROLLED PROCEDURE "- DO NOT USE.TO PERFORM, WORK orI'SSUEFOR 'USE N*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 43 OF 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 I 04 (zIQ)R E KQj (44)

Noble Gas Skin Dose 3.17 x 104 (Z/Q)R (L, + I. IM, i, (45)

Where:

3.17x104

=

Conversion constant yr/sec.

(/QA)R

=

Maximum historical dispersion factor for receptor of interest, based on 5 year averages from Table 10.2.

i

=

Whole body dose factor for nuclide i, in mrem/yr per pCi/M3. Values are listed in Table 6.3.

Li

=

Skin dose factor for nuclide i, in mrem/yr per pCi/r 3. Values are listed in Table 6.3.

1.1

=

Conversion factor mrernlmrad. Converts air dose to skin dose.

Mi

=

Gamma air dose factor for nuclide i, in mrad/yr per gCi/n 3. Values are listed in Table 10.3.

Q

=

Total release of noble gas radionuclide, i, in ACilsec.

vl 100692326.DOC 08 0604.0656

~f#~UNCONTROLLED PROCEDURE-D OW S T EFR WORK oiSEFRUE~

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 44 OF 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.

v01 00692326.DOC 08 0604.0656

UNCONTROLLED PROCEDURE -DiO NOT USETO PERFORM WORtor iSSdt PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 45 OF 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 R1'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.

1oglxld~on-site -

1og

[(X/S tlx

)[log(dist.on - site) - log(dist.S.B.)] (46) log(dist.S.B.) -loditc.

+ 1og[XIQ]S.B 1°g[DIQ]on-site 1og[D/Q]B. - 1og[D/g]_,c [-og(dist on site) - log(distS.SB.)] (47)

Iog(dist.SAB) - lo~ito.

+ log[DI/]S.B.

Based upon Regulatory Guide 1.1 11, 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 TLD 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.

vll 00692326.DOC 08 0604.0656

.':*UNCONTROLLED PROCEDURE-iDO NOJTUSE TOEPERFORM WORK orI.SSUE FOR USE *.'-*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 46 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 The activities of the members-of-the-public while on-site (described above), are at or beyond 200 meters. Table 6. 3 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 <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> shooting range Tour Participants Simulator Bldg S

(SE) 310m 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Bio Lab SSE (SE) 460m 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Overlook E

210m 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> American Indians NW 200m 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> at burial grounds NNW 200m 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> Ranch hands driving NW 250m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cattle around site NNW 350m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> N

320m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> NNE 450m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> NE 630m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> v I 100692326.DOC 08 060>4.0656

-*UNCONTROLLEDPROCEDURE-DO NOTtUSE TO PERFORM MWRKorISSUEFOR USE;S**-*; -

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 Draft Radiological Tech Specs for PWRs, NUREG No. 0472, May 1978.

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 I, 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.ID1, "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.

9.

RECORDS 9.1 Data Sheets and records will be maintained in the Records Management System (RMS) in accordance with CYl.DCl, "Analytical Data Processing Responsibilities."

v1 1-00692326.DOC 08 0604.0656

'UNCONTROLLED PROCEDURE- 'DO NOT USE TO PERFORM WORK or ISSUE FOR.RUSE-**:..

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 48 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2

10.

APPENDICES 10.1 Tables

11.

ATTACHMENTS 11.1 "Liquid Discharges (LRW) Monitored for Radioactivity," 10/04/00 11.2 "Gaseous Releases (GRW) Monitored for Radioactivity," 10/31/00

12.

SPONSOR John Knemeyer vl 100692326.DOC 08 0604.0656

'- f, UNCONTROLLED PROCEDURE --DO NOT USE TO PERFORM WORK or iSSUEFOR USE '**

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 49 OF 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 J4Ci/ml) organ "o" Nuclide Tot Body Thyroid Kidney Lung GI-LLI Bone Liver H-3 Na-24 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-65 Cu-64 Zn-65 Zn-69 As-76 Br-82 Br-84 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91m Y-92 Zr-95 Zr-97 Nb-95 Mo-99 Tc-101 Ru-103 Ru-105 Ru-106

• Ae-110m Sn-113 Sn-1 17m Sb-122 Sb-124 Sb-125 1.61E-01 1.61E-01 1.61E-01 1.61E-01 4.57E-01 4.57E-01 4.57E-01 4.57E-01 5.58E+00 3.34E+00 1.23E+00 7.40E+00 1.35E+03 0.00E+00 2.10E+03 0.00E+00 3.15E+01 0.00E+00 2.26E+02 0.00E+00 8.23E+03 0.OOE+00 0.00E+00 1.97E+04 7.27E+04 0.00E+00 0.00E+00 5.30E+04 2.36E+02 0.00E+00 0.OOE+00 0.00E+00 1.35E+03 O.OOE+00 0.00E+00 O.OOE+00 3.82E+03 0.00E+00 0.00E+00 0.OOE+00 1.20E+01 0.00E+00 0.00E+00 0.00E+00 1.01E+02 0.00E+00 5.40E+02 0.00E+00 2.32E+05 O.OOE+00 3.43E+05 0.00E+00 4.56E+01 O.OOE+00 4.26E+02 0.00E+00 4.42E+01 0.00E+00 8.72E+01 0.00E+00 4.07E+00 0.00E+00 0.OOE+00 0.00E+00 9.39E-02 0.00E+00 0.00E+00 0.00E+00 2.91E+02 0.00E+00 0.00E+00 0.OOE+00 9.49E-01 O.OOE+00 O.OOE+00 0.00E+00 8.34E-01 0.00E+00 0.00E+00 0.00E+00 1.43E+02 0.00E+00 O.OOE+00 0.00E+00 2.83E+03 0.00E+00 0.OOE+00 0.00E+00 3.71E+00 0.00E+00 O.OOE+00 0.00E+00 1.51E+00 O.OOE+00 O.0+00 0.00E+00 1.63E-01 0.00E+00 O.OOE+00 O.OOE+00 2.22E-03 0.00E+00 0.00E+0 0.0OOE+00 1.56E-02 O.OOE+00 0.00E+00 0.00E+00 3.46E+00 O.OOE+00 8.02E+00 0.00E+00 8.13E-02 O.OOE+00 2.68E-01 0.00E+00 1.34E+02 O.OOE+00 2.46E+02 0.OOE+00 2.43E+01 0.00E+00 2.89E+02 O.OOE+00 1.88E-01 0.00E+00 3.46E-01 9.81E-03 4.60E+01 0.OOE+00 4.07E+02 0.00E+00 3.51E+00 0.00E+00 1.15E+02 0.OOE+00 2.01E+02 0.00E+00 3.06E+03 0.00E+00 8.60E+02 0.OOE+00 2.85E+03 0.00E+00 3.53E+03 9.85E+02 0.00E+00 0.OOE+00 8.76E+02 2.52E+02 0.00E+00 0.00E+00 6.65E+00 3.09E-01 O.OOE+00 1.18E+01 1.09E+02 6.70E-01 0.00E+00 2.15E+02 4.20E+01 1.79E-01 0.00E+00 1.36E+02 1.61E-01 0.00E+00 1.61E-01 4.57E-01 4.57E-01 4.57E-01 1.40E+03 0.00E+00 0.00E+00 2.16E+04 0.OOE+00 7.06E+03 5.67E+03 O.OOE+00 1.78E+02 2.03E+04 5.11E+04 3.53E+04 6.32E+05 8.06E+04 1.90E+05 3.59E+03 0.00E+00 1.42E+02 1.22E+04 O.OOE+00 6.03E+02 3.25E+04 0.OOE+00 1.73E+03 6.65E+02 2.02E+02 2.62E+01 1.83E+04 0.00E+00 2.14E+02 3.23E+05 1.61E+05 5.13E+05 9.85E+01 3.43E+02 6.56E+02 0.00E+00 O.OOE+00 4.62E+01 4.67E+00 0.00E+00 0.00E+00 7.37E-07 0.00E+00 0.00E+00 1.23E+02 0.00E+00 6.24E+02 2.47E-11 0.00E+00 1.79E+00 6.89E-14 0.OOE+00 1.19E+00 8.00E+02 4.99E+03 0.OOE+00 3.55E+03 1.41E+05 0.00E+00 4.37E+02 9.18E+01 0.00E+00 6.90E+02 3.48E+01 0.00E+00 6.42E+04 6.06E+00 0.00E+00 1.68E-01 5.73E-02 0.OOE+00 9.32E+03 5.32E-01 0.00E+00 1.62E+04 1.59E+01 5.11E+00 5.51E+04 8.81E-01 1.78E-01 1.51E+06 4.47E+02 2.49E+02 2.96E+02 0.00E+00 1.28E+02 5.77E-14 1.33E-02 1.92E-02 1.25E+04 1.07E+02 0.00E+00 5.44E+03 8.89E+00 O.OOE+00 1.03E+05 1.59E+03 0.00E+00 5.91E+05 1.56E+03 1.45E+03 0.00E+00 6.06E+04 1.66E+03 0.OOE+00 3.02E+03 3.41E+02 0.OOE+00 2.19E+01 4.47E-01 7.84E+03 2.76E+02 5.22E+00 1.94E+03 1.77E+02 1.97E+00 vl 100692326.DOC 08 0604.0656

i 1N-rUNCONTROLLED PROCEDURE-.DO NOTUSE TOPERFORM WORKF o ISSUE FOR USE-f PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 gCi/ml) organ "of Nuclide Te-129m Te-129 Te-131m Te-131 Te-132 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-144 Nd-147 W-187 Np-239 Tot Body Thyroid Kidney Lung GI-LLI Bone 1.47E+02 6.19E-01 5.71E+01 5.03E-01 1.24E+02 1.79E+02 9.96E+00 3.95E+01 5.40E+00 2.24E+01 1.33E+04 2.04E+03 7.85E+03 5.94E+00 2.30E-01 1.08E+02 1.29E-01 2.10E-01 9.13E-03 2.63E-01 4.94E-02 9.59E+00 9.64E-04 2.74E-01 2.68E+00 1.91E-03 3.20E+02 1.95E+00 1.08E+02 1.3E1+00 1.46E+02 1.02E+05 9.96E+02 1.90E+04 2.62E+02 4.01E+03 0.00E+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.89E+03 1.07E+01 6.94E+02 6.99E+00 1.27E+03 5.35E+02 4.54E+01 2.26E+02 2.40E+01 9.75E+01 5.27E+03 1.57E+03 4.07E+03 8.81E+00 5.23E-03 7.02E-01 2.68E-03 O.OOE+00 0.00E+00 1.081E+00 1.97E-01 4.43E+01 4.44E-03 2.68E+00 0.OOE+00 1.08E-02 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 1.75E+03 2.16E+02 1.35E+03 8.70E-01 3.17E-03 1.18E+00 1.63E-03 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.00E+00 4.69E+03 1.92E+00 6.80E+03 2.26E1-1 6.24E+03 8.23E+01 5.35E+00 1.16E+02 1.32E-02 6.87E+01 2.85E+02 3.21E+02 2.32E+02 5.12E-05 1.39E+01 3.38E+03 1.80E-09 5.83E+04 2.68E+02 8.86E+03 1.67E+04 6.04E+04 2.73E-09 2.20E+04 2.51E+03 7.11E+02 9.31E+02 2.54E+00 1.40E+02 1.59E+00 2.04E+02 2.18E+02 1.06E+01 7.45E+01 5.56E+00 2.32E+01 6.84E+03 7.16E+02 8.77E+03 6.07E+00 7.85E+00 1.64E+03 3.81E+00 1.57E+00 8.06E-02 3.43E+00 6.04E-01 1.79E+02 1.90E-02 3.96E+00 9.16E+00 3.53E-02 Liver 3.47E+02 9.55E-01 6.85E+01 6.66E-01 1.32E+02 3.12E+02 2.85E+01 1.30E+02 1.51E+01 6.08E+01 1.63E+04 2.83E+03 1.20E+04 1.20E+01 5.59E-03 2.06E+00 2.88E-03 7.94E-01 3.67E-02 2.32E+00 4.46E+02 7.47E+01 7.87E-03 4.58E+00 7.66E+00 3.47E-03

' Dose factors are based upon NUREG 0133 methodology.

vl1_00692326.DOC 08 0604.0656

. *.*, ' UNCONTROLLED PROCEDURE - DO NOT USETO PERFORM WORK or ISSUEFOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 51 OF 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 4.4 5.70E-8 9.40E-11 unknown use residence 3.3 8.70E-8 1.60E-10 cabin - limited use NE residence 4.9 3.70E-8 6.20E-Il full time occupancy ENE residence 4.4 4.10E-8 7.60E-1 full time occupancy residence 5.0 3.40E-8 6.OOE-11 full time occupancy E

residence 4.0 5.40E-8 1.40E-10 cabin - unknown use residence 3.7 6.10E-8 1.60E-10 part time occupancy residence +

4.5 4.40E-8 1.10E-10 full time occupancy garden ESE oat hay and 3.3 1.50E-7 9.20E-10 field workers present only during the sugar peas day - 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 5.50E-6 1.90E-8 Gas effluent dose rates. PRRLs and boundary HASPs evaluated at this location.

dispersion value residence 1.2 1.20E-6 4.30E-9 cabin - very limited use residence 3.6 2.20E-7 6.40E-10 full time occupancy NNW residence 1.5 7.40E-7 2.20E-9 full time occupancy (trailer) - critical receptor ground plane and inhalation dose assessed at this location vl 1-00692326.DOC 08 0604.0656

N

• CONTROLLEDPROEDDURE

- DO NOT USE TO PERFORM;WORK or ISSUEFOR USE. **.,.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 52 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.3 GRW DOSE FACTORS FOR NOBLE GASES' Whole Body Dose Factor (mrem/yr per pCi/m3)

Skin Dose Factor L

(mrem/yr per pCi/M3)

Gamma Air Dose Factor M i (mrad/yr per plCi/m3)

Beta Air Dose Factor Ni (mrad/yr per pCi/m3)

Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-13lnm Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02 2.94E+02 3.12E+03 1.81E+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.O1E+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.1 1E+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51E+03 9.21E+03 9.30E+03 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 1 From Table B-1 of Regulatory Guide 1.109 (Rev. 1, Oct. 1977) vll 00692326.DOC 08 0604.0656

UNCONTROLLED 'PROCEDURE.-DO NOTUSE TO PERFORM WORK orI.SSUEFOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 53 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.4 CHILD INHALATION PATHWAY DOSE FACTORS FOR WORST CASE ORGAN Radionuclide H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 P,

6.40E+02 1.70E+04 1.58E+06 1.27E+06 1.11 E+06 7.07E+06 9.95E+05 1.98E+05 2.16E+06 2.68E+05 3.85E+07 2.23E+06 6.14E+05 6.62E+05 1.43E+07 5.48E+06 3.24E+06 2.32E+06 1.76E+06 1.62E+07 3.85E+06 1.01E+06 1.71E+05 9.07E+05 1.74E+06 5.44E+05 1.20E+07 3.28E+05 vI 1-00692326.DOC 08 0604.0656

.- UNCONTROLLEDPROCEDURE-DO NOT USE TOPERFORMWORK r ISSUEFOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 54 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.5 GROUND PLANE DOSE FACTORS GRW DOSE PARAMETERS', Ri.op FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW),

ANY AGE GROUP, GROUND PLANE PATHWAY (mrem/yr per p.Ci/(sec m2))

Nuclide Bone H-3 0.00E+00 CR-51 4.65E+06 MN-54 1.38E+09 FE-59 2.73E+08 CO-58 3.80E+08 CO-60 2.15E+10 ZN-65 7.46E+08 RB-86 8.98E+06 SR-89 2.16E+04 Y-90 4.50E+03 SR-90 0.00E+00 ZR-95 2.45E+08 NB-95 1.37E+08 RU-103 1.08E+08 RU-106 4.20E+08 AG-llOM 3.45E+09 SB-124 5.99E+08 SB-125 2.34E+09 TE-129M 1.98E+07 1-131 1.72E+07 1-133 2.45E+06 CS-134 6.90E+09 CS-136 1.51E+08 CS-137 1.03E+10 BA-140 2.05E+07 CE-141 1.37E+07 CE-144 6.96E+07 ND-147 8.39E+06 Liver 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+ 10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+ 10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 T Body 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+ 10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.5lE+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Thyroid 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+ 10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Kidney 0.00E+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+ 10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Lung 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+ 10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 GI-LLI 0.00E+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+ 10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.OOE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Dose factors are based upon NUREG 0133 methodology.

vii 00692326.DOC 08 6.05 0604.0656

..*UNCONTROLLED PROCEDURE-DO NOT USE-TOPERFORM WORK orISSUEFOR PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 55 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6 GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IP-T), GASEOUS EFFLUENTS (GRW) v I 100692326.DOC 08 0604.0656

+* UNCONTROLLED -PROCEDURE-DO NOT.USEiTO PERFORM WORK or ISSUEFOR USE, PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 56 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.1 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IP1T), GASEOUS EFFLUENTS (GRW), INFANT AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per pCi/m3 ) RIjnhal Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.OOE+00 0.OOE+00 0.OOE+00 1.36E+04 0.OOE+00 0.OOE+00 1.93E+04 0.OOE+00 3.98E+05 3.29E+03 1.55E+07 1.15E+05 1.57E+04 2.02E+03 8.68E+04 9.98E+03 3.79E+04 5.17E+04 1.41E+04 3.79E+04 1.32E+04 3.96E+05 4.83E+04 5.49E+05 5.60E+04 2.77E+04 3.19E+06 7.94E+03 3.68E+02 0.OOE+00 2.53E+04 2.35E+04 1.22E+03 8.02E+03 6.26E+04 1.90E+05 0.00E+00 0.OOE+00 0.OOE+00 2.79E+04 6.43E+03 0.OOE+00 0.OOE+00 7.22E+03 5.56E+02 4.77E+02 6.09E+03 4.44E+04 1.92E+04 7.03E+05 1.35E+05 6.12E+05 5.60E+01 1.67E+04 1.21E+06 8.13E+03 3.68E+02 8.95E+01 4.98E+03 9.48E+03 1.82E+03 1.18E+04 3.11E+04 8.82E+04 1.14E+04 8.82E+01 3.12E+05 2.03E+04 3.78E+03 6.79E+02 1.09E+04 5.OOE+03 1.20E+04 1.09E+04 2.23E+03 1.96E+04 5.60E+03 7.45E+04 5.29E+04 4.55E+04 2.90E+03 1.99E+03 1.76E+05 5.00E+02 3.68E+02 5.75E+01 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 1.O1E+02 6.23E+01 5.47E+03 1.48E+07 3.56E+06 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 3.68E+02 1.32E+01 4.98E+03 0.OOE+00 0.OOE+00 0.OOE+00 3.25E+04 O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 3.11E+04 4.72E+03 4.24E+03 1.07E+05 1.09E+04 0.OOE+00 0.00E+00 3.18E+04 5.18E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 5.25E+03 5.38E+05 3.15E+03 3.68E+02 1.28E+04 1.OOE+06 1.02E+06 7.77E+05 4.51E+06 6.47E+05 0.OOE+00 2.03E+06 2.69E+05

1. 12E+07 1.75E+06 4.79E+05 5.52E+05 1.16E+07 3.67E+06 2.65E+06 1.64E+06 1.68E+06 0.OOE+00 0.OOE+00 7.97E+04 1.18E+04 7.13E+04 1.60E+06 5.17E+05 9.84E+06 3.22E+05 3.68E+02 3.57E+02 7.06E+03 2.48E+04 1.1IlE+04 3.19E+04 5.14E+04 3.04E+03 6.40E+04 1.04E+05 1.31E+05 2.17E+04 1.27E+04 1.61E+04 1.64E+05 3.30E+04 5.91E+04 1.47E+04 6.90E+04 1.06E+03 2.16E+03 1.33E+03 1.43E+03 1.33E+03 3.84E+04 2.16E+04 1.48E+05 3.12E+04 1 Dose factors are based upon NUREG 0133 methodology.

vii_00692326.DOC 0806

.66 0604.0656

- X *. X UNCONTROLLED PROCEDURE-DO NO TUSE TO PERFORM WORK or ISSUE-FOR USE.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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'"

(mremlyr per pCi/m3) RI,,nhal Nuclide Bone Liver T Body Thyroid Kidney Lune GI-LLI H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.00E+00 0.00E+00 0.00E+00 2.07E+04 0.OOE+00 0.00E+00 4.26E+04 0.OOE+00 5.99E+05 4.11 E+03 3.85E1+07 1.90E+05 2.35E+04 2.79E+03 1.36E+05 1.69E+04 5.74E+04 9.84E+04 1.92E+04 4.81E+04 1.66E+04 6.51E+05 6.51E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.08E+04 6.40E+02 0.00E+00 4.29E+04 3.34E+04 1.77E+03 1.31E+04 1.13E+05 1.98E+05 0.OOE+00 0.OOE+00 0.00E+00 4.18E+04 9.18E+03 0.00E+00 0.00E+00 1.14E+04 7.40E+02 7.59E+02 6.85E+03 4.81E+04 2.03E+04 1.O1E+06 1.71E+05 8.25E+05 6.48E+01 1.95E+04 2.12E+06 8.73E+03 6.40E+02 1.54E+02 9.51E+03 1.67E+04 3.16E+03 2.26E+04 7.03E+04 1.14E+ 05 1.72E+04 1.11E+02 7.66E+05 3.70E+04 6.55E+03 1.07E+03 1.69E+04 9.14E+03 2.00E+04 2.07E+04 3.04E+03 2.73E+04 7.70E+03 2.25E+05

1. 16E+05 1.28E+05 4.33E+03 2.90E+03 3.61E+05 6.81E+02 6.40E+02 8.55E+01 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 1.26E+02 9.101E+01 6.33E+03 1.62E+07 3.85E+06 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 6.40E+02 2.43E+01 1.00E+04 0.OOE+00 0.00E+00 0.OOE+00 7.14E+04 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 5.96E+04 8.62E+03 7.03E+03 1.84E+05 2.12E+04 0.00E+00 0.00E+00 5.03E+04 7.88E+04 3.38E+04 3.30E+05 9.55E+04 2.82E+05 2.1 1E+01 8.55E+03

1. 17E+ 06 4.81E+03 6.40E+02 1.70E+04 1.58E+06 1.27E+06 1.1lE+06 7.07E+06 9.95E+05 0.OOE+00 2.16E+06 2.62E+05 1.48E+07 2.23E+06 6.14E+05 6.62E+05 1.43E+07 5.48E+06 3.24E+06 2.32E+06 1.76E+06 0.00E+00 0.00E+00 1.21E+05 1.45E+04 1.04E+05 1.74E+06 5.44E+05 1.20E+07 3.28E+05 6.40E+02 1.08E+03 2.29E+04 7.07E+04 3.44E+04 9.62E+04 1.63E+04 7.99E+03 1.67E+05 2.68E+05 3.43E+05 6.11lE+04 3.70E+04 4.48E+04 4.29E+05 1.00E+05 1.64E+05 4.03E+04 1.82E+05 2.84E+03 5.48E+03 3.85E+03 4.18E+03 3.62E+03 1.02E+05 5.66E+04 3.89E+05 8.21E+04

' Dose factors are based upon NUREG 0133 methodology.

vl 100692326.DOC 08 0604.0656

UNCONTROLLED PROCEDURE.DO.O.USE TO PERFORM WORK or ISSUEFOR.USE. *

• PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 58 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.3 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per liCi/m3 ) Rjnha, Nuclide Bone Liver T Body Thyroid Kidney Lun2 GI-LLI H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.OOE+00 7.25E+02 0.00E+00 0.00E+00 0.00E+00 5.11E+04 1.59E+04 3.70E+04 0.00E+00 2.07E+03 0.00E+00 1.51E+04 3.86E+04 1.34E+05 0.00E+00 1.90E+05 4.34E+05 0.00E+00 2.98E+03 0.00E+00 3.31E+07 0.00E+00 1.46E+05 4.58E+04 1.86E+04 1.03E+04 2.10E+03 0.00E+00 9.84E+04 0.00E+00 1.38E+04 1.31E+04 4.30E+04 7.94E+02 7.38E+04 8.08E+02 1.39E+04 6.58E+03 3.54E+04 4.91E+04 1.22E+04 2.05E+04 5.02E+05 1.13E+06 5.15E+04 1.94E+05 6.70E+05 8.48E+05 5.47E+04 6.70E+01 2.84E+04 1.90E+04 4.89E+06 2.02E+06 7.86E+03 8.56E+03 7.25E+02 1.35E+02 8.40E+03 1.43E+04 2.78E+03 1.98E+04 6.24E+04 8.40E+04 1.25E+04 8.OOE+01 6.66E+05 3.15E+04 5.66E+03 8.96E+02 1.24E+04 7.99E+03 1.68E+04 1.72E+04 2.25E+03 2.64E+04 6.22E+03 5.49E+05 1.37E+05 3.1 lE+05 3.52E+03 2.17E+03 2.62E+05 5.13E+02 7.25E+02 7.50E+01 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 9.76E+01 7.04E+01 4.58E+03 1.46E+07 2.92E+06 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 7.25E+02 7.25E+02 3.07E+01 2.10E+04 1.27E+04 1.98E+06 0.OOE+00 1.53E+06 0.00E+00 1.34E+06 O.OOE+00 8.72E+06 8.64E+04 1.24E+06 0.00E+00 0.00E+00 0.OOE+00 2.42E+06 0.00E+00 2.93E+05 0.00E+00 1.65E+07 6.74E+04 2.69E+06 1.00E+04 7.51E+05 7.43E+03 7.83E+05 1.90E+05 1.61E+07 2.50E+04 6.75E+06 0.00E+00 3.85E+06 0.00E+00 2.74E+06 5.19E+04 1.98E+06 8.40E+04 0.00E+00 3.59E+04 0.00E+00 3.75E+05 1.46E+05 1.10E+05 1.78E+04 3.04E+05 1.21E+05 2.28E+01 2.03E+06 8.88E+03 6.14E+05 1.21E+06 1.34E+07 5.02E+03 3.72E+05 7.25E+02 3.00E+03 6.68E+04 1.78E+05 9.52E+04 2.59E+05 4.66E+04 1.77E+04 3.71E+05 5.59E+05 7.65E+05 1.49E+05 9.68E+04 1.09E+05 9.60E+05 2.73E+05 3.98E+05 9.92E+04 4.05E+05 6.49E+03 1.03E+04 9.76E+03 1.09E+04 8.48E+03 2.29E+05 1.26E+05 8.64E+05 1.82E+05 Dose factors are based upon NUREG 0133 methodology.

vll 00692326.DOC 0806

.0 6

0604.0656

UNCONTROLLED PROCEDURE- -00 NOT USE TO PERFORM WORwor iSSUE FOR USE PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 59 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.4 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per IiCi/m3 ) R.,ha, Nuclide Bone H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-10l SB-124 SB-125 TE-129Mv 1-131 I-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.00E+00 0.00E+00 0.00E+00 1.18E+04 O.OOE+00 0.00E+00 3.24E+04 0.00E+00 3.04E+05 2.09E+03 2.87E+07 1.07E+05 1.41E+04 1.53E+03 6.91E+04 4

1.08E+04 3.12E+04 5.34E+04 I

9.76E+03 2.52E+04 8.64E+03 3.73E+05 3.90E+04 4.78E+05 3.90E+04 1.99E+04 3.43E+06 5.27E+03 Liver 7.18E+02 0.00E+00 3.96E+04 2.78E+04 1.58E+03 l.15E+04 1.03E+05 1.35E+05 0.OOE+00 0.OOE+00 0.00E+00 3.44E+04 7.82E+03 0.00E+00 0.00E+00 1.00E+04 5.89E+02 5.95E+02 4.67E+03 3.58E+04 1.48E+04 8.48E+05 1.46E+05 6.21E+05 4.90E+01 1.35E+04 1.43E+06 6.103E+03 T Body Thyroid 7.18E+02 7.18E+02 1.00E+02 5.95E+01 6.30E+03 0.00E+00 1.06E+04 0.00E+00 2.07E+03 O.OOE+00 1.48E+04 0.00E+00 4.66E+04 0.00E+00 5.90E+04 0.00E+00 8.72E+03 0.00E+00 5.61E+01 0.00E+00 5.77E+05 0.OOE+00 2.33E+04 0.00E+00 4.21E+03 0.00E+00 6.58E+02 0.00E+00 8.72E+03 0.00E+00 5.94E+03 0.00E+00 1.24E+04 7.55E+01 1.26E+04 5.40E+01 1.58E+03 3.44E+03 2.05E+04 1.19E+07 4.52E+03 2.15E+06 7.28E+05 0.00E+00 1.10E+05 0.00E+00 4.28E+05 0.00E+00 2.57E+03 0.00E+00 1.53E+03 0.00E+00 1.84E+05 0.OOE+00 3.65E+02 0.OOE+00 Kidney 7.18E+02 2.28E+01 9.84E+03 0.00E+00 0.OOE+00 0.00E+00 6.90E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 5.42E+04 7.74E+03 5.83E+03 1.34E+05 1.97E+04 0.00E+00 0.00E+00 3.66E+04 6.13E+04 2.58E+04 2.87E+05 8.56E+04 2.22E+05 1.67E+01 6.26E+03 8.48E+05 3.561E+03 Lung 7.18E+02 1.44E+04 1.40E+06 1.02E+06 9.28E+05 5.97E+06 8.64E+05 0.00E+00 1.40E+06 1.70E+05 9.60E+06 1.77E+06 5.05E+05 5.05E+05 9.36E+06 4.63E+06 2.48E+06 1.74E+06 1.16E+06 0.00E+00 0.00E+00 9.76E+04 1.20E+04 7.52E+04 1.27E+06 3.62E+05 7.78E+06 2.21E+05 GI-LLI 7.18E+02 3.32E1+03 7.74E+04 1.88E+05 1.06E+05 2.85E+05 5.34E+04 1.66E+04 3.50E+05 5.06E1+05 7.22E+05 1.50E+05 1.04E+05 1.101E+05 9.12E+05 3.02E+05 4.06E+05 1.01E+05 3.83E+05 6.28E+03 8.88E+03 1.04E+04 1.17E+04 8.40E+03 2.18E+05 1.20E+05 8.16E+05 1.73E+05 Dose factors are based upon NUREG 0133 methodology.

vll 00692326.DOC 0806466 0604.0656

.: ;* *.-UNCONTROLLED PROCEDURE-.ODO NOT USE TO PERFORM WORK or ISSUEFOR 'USE'I PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 60 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 TABLE 10.6.5 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IP1), GASEOUS EFFLUENTS (GRW), CHILD AGE GROUP, VEGETATION PATHWAY ORGAN "O" (mrem/yr per tiCi/(sec m2 )) Rji egj I

Nudide H-32 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.OOE+00 0.00E+00 0.00E+00 3.97E+08 0.00E+00 0.00E+00 8.12E+08 0.00E+00 3.59E+ 10 2.31E+04 1.87E+12 3.86E+06 4.12E+05 1.53E+07 7.45E+08 3.21E+07 3.52E+08 4.99E+08 8.40E+08 1.43E+08 3.52E+06 1.60E+ 10 8.18E+07 2.39E+ 10 2.77E+08 6.55E+05 1.27E+08 7.27E+04 Liver 2.29E+03 0.0OE+00 6.65E+08 6.42E+08 6.45E+07 3.78E+08 2.16E+09 4.54E+08 0.OOE+00 O.O0E+00 0.00E+00 8.50E+05 1.61E+05 0.00E+00 O.O0E+00 2.17E+07 4.57E+06 3.85E+06 2.35E+08 1.44E+08 4.36E+06 2.63E+ 10 2.25E+08 2.29E+ 10 2.43E1+05 3.27E+05 3.98E+07 5.89E+04 T Body 2.29E+03 1.17E+05 1.77E+08 3.20E+08 1.97E+08 1.12E+09 1.35E+09 2.79E+08 1.03E+09 6.18E+02 3.77E+10 7.56E1+05 1.15E+05 5.89E+06 9.30E+07 1.74E+07 1.23E+08 1.05E+08 1.30E+08 8.17E+07 1.65E+06 5.55E+09 1.46E+08 3.38E+09 1.62E+07 4.85E+04 6.78E+06 4.56E+03 Thyroid 2.29E+03 6.49E+04 0.00E+00 0.OOE+00 0.OOE+00 0.O0E+0O 0.00E+00 0.00E+00 0.O0E+0O 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 7.78E+05 4.62E+05 2.71E+08 4.75E+ 10 8.09E+08 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Kidney 2.29E+03 1.77E+04 1.86E+08 0.00E+00 0.OOE+00 0.00E+00 1.36E+09 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.22E+06 1.51E+05 3.86E+07 1.O1E+09 4.04E+07 0.OOE+00 0.00E+00 2.47E+09 2.36E+08 7.26E+06 8.16E+09 1.20E+08 7.46E+09 7.90E+04 1.43E+05 2.21E+07 3.23E+04 Lung 2.2913+03 1.18E+05 0.OOE+OO 1.86E+08 0.OOE+OO 0.OOE+OO 0.OOE+00 0.OOE+OO

.0OOE+OO 0.OOE+OO 0.OOE+OO 0.OOE+00 0.OOE+00 0.OOE+OO 0.OOE+OO 0.OOE+00 1.96E+08 2.78E+08 0.OOE+OO 0.OOE+OO 0.OOE+OO 2.9313+09 1.79E+07 2.68E+09 1.45E+05 0.OOE+OO 0.OOE+OO 0.OOE+OO GI-LLI 2.29E+03 6.20E+06 5.58E+08 6.69E+08 3.76E+08 2.I0E+09 3.80E+08 2.92E+07 1.39E+09 6.57E+07 1.67E+ 10 8.86E+08 2.97E+08 3.96E+08 1.16E+10 2.58E+09 2.20E+09 1.19E + 09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 7.90E+06 1.43E+08 1.40E+08 4.08E+08 1.04E+10 9.33E+07 I Dose factors are based upon NUREG 0133 methodology.

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

vll 00692326.DOC 08 06466 0604.0656

_,.,UNCONTROLLED PROCEDURE-'DO NOT USEXTO PERFORM WORK or.ISSUEFOR USE.,*,,!.*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 PAGE 61 OF 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 gCi/(sec m2)) Ri evg Nuclide H-32 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.OOE+00 0.00E+00 0.00E+00 1.79E+08 0.00E+00 0.00E+00 4.24E+08 0.OOE+00 1.51E+10 1.24E+04 9.22E+ 11 1.72E+06

• 1.93E+05 6.82E+06 3.09E+08 1.52E+07 1.55E+08 2.14E+08 3.61E+08 7.68E+07 1.93E+06 7.10E+09 4.35E+07 1.O1E+ 10 1.38E+08 2.83E+05 5.27E+07 3.67E+04 Liver 1.47E+03 0.00E+00 4.54E+08 4.18E+08 4.37E+07 2.49E+08 1.47E+09 2.75E+08 0.OOE+00 0.OOE+00 0.00E+00 5.44E+05 1.07E+05 0.OOE+00 0.00E+00 1.44E+07 2.85E+06 2.34E+06 1.34E+08 1.08E+08 3.28E+06 1.67E+ 10 1.71E+08 1.35E+ 10 1.69E+05 1.89E+05 2.18E+07 4.OOE+04 T Body 1.47E+03 6.16E+04 9.011E+07 1.61E+08 1.O1E+08 5.60E+08 6.86E+08 1.29E+08 4.33E+08 3.35E+02 1.84E+10 3.74E+05 5.90E+04 2.91E+06 3.90E+07 8.73E+06 6.03E+07 5.01E+07 5.72E+07 5.78E+07 1.OOE+06 7.75E+09 1.15E+08 4.69E+09 8.90E+06 2.17E+04 2.83E+06 2.39E+03 1.47E+03 3.42E+04 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.51E+05 2.05E+05 1.17E+08 3.14E+ 10 4.58E+08 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Thyroid Kidney 1.47E+03 1.35E+04 1.36E+08 0.OOE+00 0.OOE+00 0.OOE+00 9.41E+08 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 7.99E+05 1.04E+05 2.40E+07 5.97E+08 2.74E+07 0.00E+00 O.OOE+00 1.51E+09 1.85E+08 5.75E+06 5.31E+09 9.31E+07 4.59E+09 5.74E+04 8.89E+04 1.30E+07 2.35E+04 Lung 1.47E+03 8.79E+04 0.00E+00 1.32E+08 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.35E+08 1.88E+08 0.00E+00 0.00E+00 O.OOE+00 2.03E+09 1.47E+07 1.78E+09

1. 14E+05 0.OOE+00 0.00E+00 0.00E+00 GI-LLI 1.47E+03 1.03E+07 9.32E+08 9.89E+08 6.02E+08 3.24E+09 6.23E+08 4.06E+07 1.80E+09 1.02E+08 2.11E+10 1.26E+09 4.58E+08 5.69E+08 1.48E+ 10 4.03E+09 3.11 E+09 1.67E+09 1.36E+09 2.13E+07 2.48E+06 2.08E+08 1.38E+07 1.92E+08 2.13E+08 5.40E+08 1.33E+ 10 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 pCi/m3 for all pathways, and they must be multiplied by XIQ.

vl 100692326.DOC 08 0604,0656

I I.

". "I;

.I.1I...

I

-EO T~ tD R C

D R

-O

1. T S

.TP R O~ W~ oIS E O US,..+-

• !* UNCONTROLLED PROCEDURE; -DO NOT-USE, To PEFRhOK "ISEFO S,;

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 26 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 piCi/(sec m2)) R.vgi Nuclide Bone Liver T Body Thyroid Kidney Lung GI-LLI H-32 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-llOM SB-124 SB-125 TE-129M 1-131 I-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.00E+00 0.00E+00 0.00E+00 1.26E+08 0.00E+00 0.00E+00 3.17E+08 0.00E+00 9.95E+09 1.33E+04 6.95E+ 11 1.18E+06 1.43E+05 4.77E+06 1.93E+08 1.05E+07 1.04E+08 1.37E+08 2.51E+08 8.07E+07 2.08E+06 4.67E+09 4.25E+07 6.36E+09 1.29E+08 1.97E+05 3.29E+07 3.37E+04 1.29E+03 0.00E+00 3.13E+08 2.96E+08 3.08E+07 1.67E+08 l.O1E+09 2.20E+08 0.OOE+00 0.00E+00 0.OOE+00 3.77E+05 7.95E+04 0.00E+00 O.OOE+00 9.75E+06 1.96E+06 1.53E+06 9.37E+07

1. 15E+08 3.62E+06 1.11E+10 1.68E+08 8.70E+09 1.61E+05 1.33E+05 1.38E+07 3.90E+04 1.29E+03 4.64E+04 5.97E+07 1.13E+08 6.90E+07 3.69E+08 4.56E+08 1.03E+08 2.86E+08 3.57E+02 1.40E+ 10 2.55E1+05 4.27E+04 2.05E+06 2.44E+07 5.79E+06 4.1 1E+07 3.25E+07 3.97E+07 6.62E+07 1.10E+06 9.08E+09 1.21E+08 5.70E+09 8.42E+06 1.51E+04 1.77E+06 2.33E+03 1.29E+03 2.77E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.52E+05 1.39E+05 8.62E+07 3.78E+ 10 5.32E+08 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.29E+03 1.02E+04 9.31E+07 0.OOE+00 0.OOE+00 0.00E+00 6.75E+08 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 5.92E+05 7.86E+04 1.82E+07 3.72E+08 1.92E+07 0.OOE+00 0.00E+00 1.05E+09 1.98E+08 6.31E+06 3.59E+09 9.33E+07 2.95E+09 5.49E+04 6.19E+04 8.16E+06 2.28E+04 1.29E+03 6.15E+04 0.00E+00 8.27E+07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 8.08E+07 1.05E+08 0.00E+00 0.00E+00 0.00E+00 1.19E+09 1.28E+07 9.81E+08 9.24E+04 0.00E+00 0.00E+00 0.00E+00 1.29E+03

1. 17E + 07 9.58E+08 9.87E+08 6.24E+08 3.14E+09 6.36E+08 4.34E+07 1.60E+09 1.41E+08 1.75E+ 10 1.20E+09 4.83E+08 5.57E+08 1.25E+10 3.98E+09 2.95E+09 1.50E+09 1.26E+09 3.05E+07 3.25E+06 1.94E+08 1.90E+07 1.68E+08 2.65E+08 5.09E+08 1.11 E+10 1.87E+08

' Dose factors are based upon NUREG 0133 methodology.

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

vll 00692326.DOC 08 6.06 0604.0656

L P

T S

T or IS-

-R U

E

":.,**UNVCON/TRO~LEDPROCAOURE'- DOAdUETFRR Oor,lSUFOS 10/04/00 Page I of I DIABLO CANYON POWER PLANT CAP A-8 ATTACHMENT 11.1 1AN TITLE:

Liquid Discharges (LRW) Monitored for Radioactivity LIQUID RADWASTE SYSTEM CONDENSATE DEMINERALIZER STEAM GENERATOR BLOWDOWN nnfnlq9nn vl 100692326.DOC 08 0604.0656

Uw,.TR ROGEDURE DO NOTIUSE T

-f.o.ER-FOM WR.

K o-.~r

, IE 1 f, _.#X.., USE,

., I.

-'.1 IIN

^UCONTROtLLEV PROCEURE N

00I/TSE TO P. E

WORKor, ISSUE FOR F US-

^.^'

10/31/00 Page I of I DIABLO CANYON POWER PLANT CAP A-8 ATTACHMENT 11.2 1

AND 2 TITLE:

Gaseous Releases (GRW) Monitored for Radioactivity

• Si

-I I- -

II4j 1

I rI-1 II

_..................a 1-1 i_._-..-.

3 III W

Di.

'B WASTE WASTE GAS GAS COMPPESEOR COMPRESSOR MOS JMOIST I

UNIT 2

...... 1.

I e

joIc l RI r _a t*-*-- *ti

..................I.......

1 1 TANI(

~

TANK r

A O

N 2 -

DSD.

0 I.

l J

EV1AF

1. i)t A

ID 1

VtUUE h l

-n- -l- --- >----------------Ll_

I Is COMPONENT HO

-LRS._

DUP t,

~ttUANoun SGt I---.

• I TN S

TANKD TANSN

• -T-1GAA

~

DECAY DECAY UK]

I MISC[Lii TANK IIIDUMP TO ATMOSPHERE DIUMTAOSERDUP TO ATMOIPHt{E I

I-L A I

RHA so 51

.35%

ATMOS I

ATMO&

SAFETYA A

4 4 4E SAREHTY VALVE :

D1D1.D VAV VALVES VOLUME

'.N-CONTRo, I I.7.?.&

ASMOS ID IDID IDIDD 40% SEAM, MAIN DUMPS2 R

a BOTAMK

)

UNIT2

_____+------

UNIT 2 r---

DECAY I

TANK I

_' J l

PLANT VENT TO ATMOSPHERE 2V2lt~4R

'--- i........0 ATUOS.

t5R

?? tS ATbtOS.

Y A-I,

I 55~K PO vl 100692326.DOC 08 06014.0656 00692319 PG&E Letter DCL-04-050 Offsite Dose Calculation Procedure (Procedure CAP A-8, Revision 27)

• • • ISSUED FOR USE BY:

DATE:

EXPIRES:____

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 NUCLEAR POWER GENERATION REVISION 27 DIABLO CANYON POWER PLANT PAGE 1 OF 62 CHEMICAL ANALYSIS PROCEDURE UNITS TITLE:

Off-Site Dose Calculations 1

AN 2 05/20/03 EFFECTIVE DATE PROCEDURE CLASSIFICATION: QUALITY RELATED TABLE OF CONTENTS SECTION PAGE 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 Gaseous 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 REFERENCES......................................................................

47 RECORDS......................................................................

47 APPENDICES......................................................................

48 ATTACHMENTS......................................................................

48 SPONSOR......................................................................

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 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 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-I 8, 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 0133 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 NIJREG 0133 Skin Gases 6.1.6.3 Dose Rate calculations, lodines, 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. ]

Noble Gases Organ Dose Calculations per age group Gases 6.1.9.2 (RECP)

Noble Gases, Iodines, 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 4A.2.b.1 lodines, 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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 of 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.

3.4 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 CY], " Chemistry and Radiochemistry," and CYI.DCI, "Analytical Data Processing Responsibilities," apply.

4.

PREREQUISITES Not Applicable 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 4 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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 = F, AtXAioCj eA (1)

Where:

D, F.

The dose commitment to organ, o, in mrem.

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

Ft Waste Flow Dilution Flow x Z (2)

Where:

Z Z is the site specific factor for the mixing effect of the discharge structure. Specifically, it is the credit taken for 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 pCi/ml as defined by Equation 3.

C; Concentration of radionuclide, i, in the undiluted liquid effluent, in IiCi/mil.

"I.

=

Decay constant of radionuclide, i.

tm

=

Time interval between end of sampling and midpoint of release.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 5 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 The site specific ingestion dose commitment factor, Ai., is defined as:

Aio = kO(UFBFi + UIBIi)DF; (3)

Where:

k.

=

Units conversion factor of 1.14xI05 in units of pCil/Ci x ml/l 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 BF, 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/i. 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-l I of Regulatory Guide 1.109, with the following exceptions: H-3, Br-82, Sb-124 and Sb-125 ingestion dose conversion factors are taken from NUREG/CR4013. As-76, Sn-I 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.

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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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 'j*" batch of liquids is calculated as follows:

E: CoJ ECLj =nC (4) zu i-, ECLY Where:

ECLj

=

The unrestricted area total undiluted ECL for the "jh." particular mixture of identified radionuclides, in jLCi/ml.

Cij

=

The concentration of radionuclide "i," in gCi/ml for the Ij," mixture.

ECLIj

=

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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.

ECL~y, 1

j

-(5) bjCj ECLoverall =

D i bC

(

,,, ECLj Where:

ECL0,;,,11

=

The unrestricted area ECL for the current radionuclide mixture for concurrent "J" discharges (in pCi/ml).

Cj

= The total activity concentration for the "jt" individual stream in J4Ci/ml.

ECLj

=

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

O,

= The ratio of an individual discharge 'jh" pathway flowrate to the sum total of all individual undiluted pathway flowrates as defined by:

(Di of (6)

Jfj 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 2, 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 8 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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.

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 (UI) 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 is 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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[1 (I C 3 IECL H 3 J]

(7)

Where:

ECLH3

=

effluent concentration limit of tritium CH3 concentration of tritium in the release mix, pre-dilution (pLCi/mnl)

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

The concentration of tritium, CH3, 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 or 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.

HASPE3 =3 x BKGD, 3

(8) 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

Off-Site Dose Calculations NUMBER CAP A-8 REVISION 27 PAGE 10 OF 62 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

/kfCI-xTCF fheH3 (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 Table 6.1 (SF)

=

safety factor for RE-3 (0.9) ky=

monitor response factor (cpm/ACi/rml)

CY

=

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

F

=

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

C=

concentration of isotope "i," in the release mix, pre-dilution (gCi/ml)

ECLi

=

effluent concentration limit of isotope "i" TCF

=

tritium correction factor as defined by Equation 7.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 11 OF 62 UNITS 1 AND 2 TITLE:

Off-Site Dose Calculations

2.

Set Point Methodology for RE-18 HASP: 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.

HASPps-18 = BKGDpRE-18 +(AFXSF)x kCr F/f I xTCF Zjc, /ECLI (10)

Where:

HASPRE.18 BKGDRE.Is (AF)

(SF)

C7 F

f C;

ECLi TCF

=

high alarm setpoint for RE-1 8 (cpm)

=

background reading for RE-1 8 (cpm) allocation factor for the liquid radwaste effluent system from Table 6.1 safety factor for RE-8 (0.9)

=

monitor response factor (cpm/pCi/ml)

=

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

=

dilution flow rate (gpm)

=

undiluted effluent flow rate (gpm)

=

concentration of isotope "i," in the release mix, pre-dilution (puCi/ml)

=

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 12 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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 11.

HASPRE-23 = BKGDRE-23 + (AFXSF)X k,, C7

]x TCF (11)

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 Table 6.1 (SF)

=

safety factor for RE-23 (0.9) kr

=

monitor response factor (cpm./pCi/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 (IiCi/ml)

ECL;

=

effluent concentration limit of isotope "i" TCF

=

tritium correction factor as defined by Equation 7.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 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:

I

-1 Dp = Dpu + 2 DPCor (12)

Where:

Dp

=

Projected Dose.

=

Projected dose attributed to reactor unit, U.

Dpbcom

=

Projected dose common to both reactor units.

The 3 1-day projected dose is calculated by Equation 13.

DAl D3AX +daf +dcB D~

31x (T + )

(13)

Where:

Dp' DAP" Monthly Projected Dose

=

Previous Month's Actual Dose

=

Current Month Actual Dose to date

=

Projected Dose from Current Batch Release

=

Number of days in the previous month t

=

Number of days into the present month 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 14 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Projected quarterly doses are determined by Equation 14.

DP + dcQ dB DcQ =d cQ + (92 - t) A A +d p (14)

(T +t)

Where:

Dp

=

Projected dose for the current calendar quarter.

dCQ

=

Current quarter to date actual dose.

DAQ

=

Previous quarter's actual dose.

dp" C

=

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.

Dcy=dcy +(3 6 6 -t)DA

+dA

+dC (15)

P A(T

+t)

Where:

Dpcy

=

Projected dose for the current calendar year.

dC=

Current year to date actual dose.

Dpy 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 15 OF 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-1 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(AFXSFXTCF)

(16) eH-33ECL, 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 Table 6.1.

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/mil)

ECLi

=

effluent concentration limit of isotope "i" (gCi/ml)

When the term Ci

= 0 then the Limiting Flow Rate is calculated by:

i*H-3 ECL, f = F(AFXSFXTCF)

(17)

Where the terms are as previously defined.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 16 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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. While no activity may be present, Equation 18 assumes a concentration equal to the Lower Limit of Detection for the nuclides listed in CY2.lDl, Appendix 6. 1, Table 6.1.3-1.

f F(AFXSF)

(18)

4.3 Where

f F

AF

=

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

Expected dilution flow rate (gpm)

=

allocation factor for the liquid radwaste effluent source from Table 6.1.

SF

=

safety factor (0.9).

4.3 Total ECL fraction as given by:

ZLLDj i ECLj Where:

LLDj =

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

ECL; =

effluent concentration limit of isotope "i" (pCi/ml) 00692327.DOA OS 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 18 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 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 1.111 and NUREGs 0133 and 0472. The historical average dispersion (X/Q) and deposition (D/Q) values are derived from the methodology of Regulatory Guide 1.111 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 <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> or less in a calendar year but not more than 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 19 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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 mrem/yr to the skin. For iodine-13 1, 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 mremlyr 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 20 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Typical Allocation Factors are shown in Table 6.2.

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 RE44 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 Factor is defined as 0.9 and provides for a High Alarm Set Point at 90% of the dose rate limits.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

Off-Site Dose Calculations NUMBER CAP A-8 REVISION 27 PAGE 21 OF 62 UNITS 1 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.

44M=CT (NG)= AFxSFx 500 472xF,, x(Qg),em x 294 (19)

Where:

4MaXCT(NG)

= the maximum allowable total concentration of noble gas in the plant vent, in piCi/cc AF

= the allocation factor for the plant vent for one unit from Table 6.2 SF

=a safety factor to ensure that dose rate limits of the radiological effluent controls are not exceeded (0.9) 500 472

=

(mremlyr) the site Total Body dose rate limit for instantaneous releases

= the conversion constant to cc/sec from cfm FPV

= total flow rate in the plant vent, in cfm (maximum plant vent flow rate is 263,000 cfm)

(il/Qlfx = '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/yr/pCi/m3) forXe-133 as presented in Table 10.3, (for the plant vent HASP, the release is assumed to be all Xe-133) 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 22 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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 CPMT CS (20)

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 CPMs, based upon noble gas grab sample (gCi/cc).

CT

=

Scaled concentration of noble gas (plCi/cc).

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 23 OF 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.

2 4AI=C (Iodine)= SFx AFx 1500 (21)

Where:

2 4 MCT(Iodine) =

the maximum allowable concentration of 1-131 in the plant vent AF =

The allocation factor for the plant vent for one unit from Table 6.2 SF

=

A safety factor to insure that the dose rate limits of the radiological effluent controls are not exceeded (0.9).

fil-31 =

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

A C-131 (22)

ZC, i

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 24 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 1500 =

(mrem/yr) the site organ dose rate limit for Iodine-13 1, 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 Fp

-=

total flowrate in the plant vent, in cfm (maximum plant vent flowrate is 263,000 cfm)

(I/)AQ&

= 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" (mremlyr/pCi/m3) 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:

vC, (23)

I 00692327.DOA 0

0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 25 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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 upon 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.

281= c(Particulates)

= AF x SF x (0.05x f/o,,n¢5 + PaninjPalcls lodnes Particulates 1500 (24) 472xFpV x (Q=Zpif, Where:

28 MaxCT(Particulate)

= Maximum allowable particulate concentration in the plant vent AF

= The allocation factor for the plant vent for one unit from Table 6.2 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.

flodines

=

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

fpaniculates

=

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 lodine-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 flovvTate in the plant vent, in cfm (maximum plant vent flowvrate is 263,000 cfm) 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 26 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2

V70tuAa,

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

=

Inhalation dose factor for nuclide "i" (mrem/yr/pCi/m3) 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 NTJREG/CR-40 13.

f

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 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.

22A10.rC (NG)=AFxSFx 3000 (25) 472xF?, xVz/Q)lfx1.34x103 Where:

22maxCT(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 Table 6.2 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 Fgd& = maximum flow rate for the gas decay tank system (31 cfm) 00Q{4fr = the maximum historical site boundary dispersion factor, based on 5 year averages derived from the meteorological data base from Table 10.2.

1.34x103

=

the skin dose factor for Kr-85 (mrem/yr/ gCi/m 3, from Table 10.3.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 28 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 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 more 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 44 AIB^'axCC (NG)= AF x SF x 500 xX Ktf; (26) 472xF,, xv/Q-),,x,

~

(6 Where:

44AIBaCT(NG) =

the maximum allowable total concentration of noble gas in the containment purge exhaust line, in pCifcc AF

=

the allocation factor for the containment purge for one unit from Table 6.2 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 F~t

=

maximum flow rate in the containment purge system (maximum containment purge flowrate is 55,000 cfm)

/Q)tfaix =

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 29 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 K;

whole body dose factor (mrem/yr4lCi/m3) 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.

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.

44A BAlar (NG)= AF x SF x 3000 472xF, x(j'Q ),a,,x Z(L, + 1.M,)f1 (27)

Where:

44AIMZxC.I(NG)

=

AF =

the maximum allowable total concentration of noble gas in the plant vent in IiCi/cc the allocation factor for the containment purge for one unit from Table 6.2 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 F.,

=

total flow rate in the containment purge system, in cfm (maximum containment purge flow rate is 55,000 cfm)

W-7)= =

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 30 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 L,

=

the skin dose factor (mrem/yr per ipCi/m3) for isotope "i." Dose factors are presented in Table 10.3.

1.1

=

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

Mi

=

the gamma air dose factor (mrad/yr per pCi/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.

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 accident 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) 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 31 OF 62 TITLE:

Off-Site Dose Calculations UNITS I AND 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),sf,,

KjQj <500mrem/year (28)

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:

+

/Q),w<z(Li +l.lM )Q <*3000mremn/year (29)

Where the terms are as previously defined.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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:

PiQi§SO50mrem/year (30)

Where:

Pi0

=

K'(BR)DFAio and K'

=

106 pCi/liCi 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 33 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations 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:

Di,, = 3.17 xl081(ZIQ),,f.zMi~i (31)

Where:

Doe

=

Gamma air dose in mrad.

3.17x10-8

= Conversion constant yr/sec.

M;

= Gamma air dose factor for nuclide i, in mrad/yr per pCi/M3. Values are listed in Table 10.3.

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

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:

D,,6=3.17x10-'(i/-QLyNj
i i

(32)

Where:

Dp

=

Beta air dose in mrad.

Ni

= -Beta air dose factor for nuclide i, in mrad/yr per pCi/m3.

Values are listed in Table 10.3.

All other terms are as previously defined.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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 lo 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.

00692327.DOA 0

0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 35 OF 62 TITLE:

Off-Site Dose Calculations UNITS I 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 =3.17x10-8WcRXR zP0Qi (33)

Where:

Dapo

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

WcR

=

Critical receptorZ/Q for immersion, inhalation and all tritium pathways (seconds/M3) from Table 10.2.

= Critical receptor D/Q for ground plane and all ingestion pathways (1/m2) from Table 10.2.

RajNo

=

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.iCi/(sec in2) 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-4013.

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 36 OF 62 TITLE:

Off-Site Dose Calculations UNITS I AND 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.

PRRL =

i x100%

(0.48X500mrem/yr)

(34)

Where:

(CIQL = The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

K

=

Whole body dose factor (mrem/yr per PCi/M3) for isotope "i." Dose factors are presented in Table 10.3.

Q.

=

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 Table 6.2.

500 mrem/yr =

Site noble gas dose rate limit.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 PAGE 37 OF 62 UNITS I AND 2 TITLE:

Off-Site Dose Calculations 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, 36, and 37.

ER(RgE22) = BKG(RE-2 2 ) + E k(E-22) J C(R2)1 i

(35)

Where:

EB(RE-22) =

Expected reading on monitor RE-22 in pCi/cc.

BKGM.22) =

Monitor background.

k(RE-22Xi 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)j k(RE-44) i C(RE-44) i (36)

Where:

ER(RE4 4)

=

BKG(RE4 4) =

CCSPRE44)

=

k(RE.44)i

=

C(RE44)i=

Expected reading on monitor RE-44 in PtCi/cc.

Monitor background.

Conversion constant setpoint for monitor RE-44.

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

Concentration of nuclide "i" seen by monitor RE-44.

ER(RE-14) =BKG(RE 14) + CCSP(RE_14)k(E-14)/C(E-14)

(37)

Where:

ER(mE.14)

=

BKG.RE.14) =

CCSP.REI1 4)

=

Expected reading on monitor RE-14 in pCi/cc.

Monitor background.

Conversion constant setpoint for monitor RE-14.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 38 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 k{RE-14)i

=

Noble gas monitor response factor for nuclide "i" for monitor RE-14.

C(RE-4)i

=

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.DCI) 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.

(-Q) zaPj Q PRRL0 =

i x100%

(38)

(0.48Xl500mrem/yr)

Where:

-QL = The maximum site boundary dispersion factor based on 5 year averages from Table 10.2.

pEw

=

Inhalation dose factor for nuclide "i" (mrem/yr/pCilm 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.

Q

=

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

0.48 Plant vent location factor for one unit from Table 6.2.

1500 mrem/yr =

Site radioiodine, tritium and particulate dose rate limit.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 39 OF 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 +jDpC.m (39)

Where:

Dp

=

Projected Dose.

Dpu

=

Projected dose attributed to reactor unit, U.

DpC..

=

Projected dose common to both reactor units.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 40 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 The 31 day projected dose is calculated by Equation 40.

D =

AI + d'

+ d DA'=31X (TA A

(40)

Where:

Dp

=

Projected Dose for the next 31 day period.

DA'

=

Previous Month's Actual Dose dc'

=

Current Month Actual Dose to date dB

=

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

+DA

+ d cQ + d cB Where:

DQ

=

Projected dose for the current calendar quarter.

dA

=

Current quarter to date actual dose.

DAPL

=

Previous quarter's actual dose.

dpB

=

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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 41 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2 Projected yearly doses are determined by Equation 42.

,,p + dcy +upl Dcy=dcy +(366 -I A

A (42)

Where:

Dc

=

Projected dose for the current calendar year.

dcy

=

Current year to date actual dose.

A DY

=

Previous year's actual dose.

dpCB

=

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.

1.

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 through the plant vent may use one hour integrated resolution times.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 42 OF 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.

Db= [800] Dr' x (9.57)x e- (6.38)

(3) where:

D'sb. = the dose rate at the site boundary, in mrem D',o = 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 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 43 OF 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 I

(

/Q)RXKIQ1 (44)

Noble Gas Skin Dose =3.17 x 1 0'

/Q)RZ(Li + 1.1M,Vj (45)

Where:

3.17x 1 0-8

=

Conversion constant yr/sec.

(71Q)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 gCi/m 3. Values are listed in Table 6.3.

L

=

Skin dose factor for nuclide i, in mrem/yr per PCi/m3. Values are listed in Table 6.3.

1.1

=

Conversion factor mremlmrad. Converts air dose to skin dose.

Mi

=

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

Qj

=

Total release of noble gas radionuclide, i, in gCi/sec. 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 44 OF 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 wvell 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.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 45 OF 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 RWs 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.

10g[X/I~onssite log[X/I..B.- Iog[X/Q10, og ton - site)- log(dist.S.B.)](46) log(dist.S.B.)- log(disJocjof d~t

+ 1og[X/QJAB 10g[D1QJnesite -

1og[DIQ1.B.- 1og[D/Q10c' og(dist-on -site)- log(dist.S.B.)](4 7)

+ 10g[D/Ql.B.

Based upon Regulatory Guide 1.1 11, 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 TLD 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.

00692327.DQA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER CAP A-8 REVISION 27 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. Table 6. 3 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 <br />0.0578 hours <br />3.439153e-4 weeks <br />7.9144e-5 months <br /> shooting range Tour Participants Simulator Bldg S

(SE) 310m 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Bio Lab SSE(SE) 460m 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Overlook E

210m I hours American Indians NW 200m 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> at burial grounds NNW 200m 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> Ranch hands driving NW 250m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> cattle around site NNW 350m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> N

320m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> NNE 450m 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> NE 630m I hour 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 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 Draft Radiological Tech Specs for PWRs, NUREG No. 0472, May 1978.

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 I, 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 I, 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-11026, 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.ID1, "Radiological Effluent and Controls Program" (RECP) 8.15 "Setpoint Calculation for Containment Ventilation Exhaust Monitor,"

Calc # NSP-1&2-3944, 10/92 and 11/92 and AR A0430610.

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

9.

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

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 48 OF 62 TITLE:

Off-Site Dose Calculations UNITS 1 AND 2

10.

APPENDICES 10.1 Tables

11.

ATTACHMENTS 11.1 "Liquid Discharges (LRW) Monitored for Radioactivity," 10/04/00 11.2 "Gaseous Releases (GRW) Monitored for Radioactivity," 10/3 1/00

12.

SPONSOR John Knemeyer 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT TITLE:

Off-Site Dose Calculations NUMBER CAP A-8 REVISION 27 PAGE 49 OF 62 UNITS I AND 2 TABLE 10.1 LRW COMPOSITE DOSE FACTORS', Ai.,

FOR ADULTS AT A SALTWATER SITE (mrem/hour per ptCifml) organ "o" Nuclide Tot Body Thyroid Kidney Lung GI-LLI Bone Liver H-3 Na-24 Cr-51 Mn-54 Mn-56 Fe-55 Fe-59 Co-57 Co-58 Co-60 Ni-65 Cu-64 Zn-65 Zn-69 As-76 Br-82 Br-84 Rb-86 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-9lm Y-92 Zr-95 Zr-97 Nb-95 Mo-99 Tc-101 Ru-103 Ru-I 05 Ru-106 APz-IIOim Sn-113 Sn-I 17m Sb-122 Sb-124 Sb-125 1.61E-01 4.57E-0 I 5.58E+00 1.35E+03 3.15E+OI 8.23E+03 7.27E+04 2.36E+02 1.35E+03 3.82E+03 1.20E+0 I 1.01E+02 2.32E+05 4.56E+01 4.42E+0 I 4.07E+00 9.399E-02 2.91E+02 9.49E-01 8.34E-01 1.43E+02 2.83E+03 3.71E+00 1.51E+00 1.63E-01 2.22E-03 1.56E-02 3.46E+00 8.133E-02 1.34E+02 2.43E+01 1.88E-01 4.60E+01 3.51E+00 2.0 1E+02 8.60E+02 3.53E+03 8.76E+02 6.65E+00 1.09E+02 4.20E+01 1.61E-01 4.57E-01 3.34E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.001E+00 0.00E+00 0.00E+00 0.O0E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.001E+00 0.OOE+00 0.001E+00 0.OOE+00 9.85E+02 2.52E+02 3.09E-01 6.70E-01 1.79E-0 I 1.61E-01 4.57E-01 1.23E+00 2.10E+03 2.26E+02 0.0OE+00 0.OOE+00 0.00E+0O 0.OOE+00 0.00E+00 O.0OE+00 5.40E+02 3.43E+05 4.26E+02 8.72E+01 0.00E+00 0.00E+0O O.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.O0E+00 0.00E+00 0.00E+00 8.02E+00 2.68E-01 2.46E+02 2.89E+02 3.46E-01 4.07E+02 1.1 5E+02 3.06E+03 2.85E+03 0.0OE+0O 0.00E+00 0.OOE+00 0.0OE+00 0.00E+00 1.61E-01 4.57E-01 7.40E+00 0.OOE+00 0.00E+00 I.97E+04 5.30E+04 0.0OE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 9.81E-03 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 1.18E+01 2.15E+02 1.36E+02 1.61E-01 4.57E-0I 1.40E+03 2.166E+04 5.67E+03 2.03E+04 6.32E+05 3.59E+03 1.22E+04 3.25E+04 6.65E+02 1.83E+04 3.23E+05 9.85E+01 0.00E+00 4.67E+00 7.37E-07 1.23E+02 2.47E-1 1 6.89E-14 8.00E+02 3.55E+03 4.37E+02 6.90E+02 6.42E+04 1.68E-01 9.32E+03 1.62E+04 5.51E+04 1.51E+06 2.96E+02 5.77E-14 1.25E+04 5.44E+03 1.03E+05 5.91E+05 0.OOE+00 0.00E+00 0.00E+00 7.84E+03 1.94E+03 0.OOE+00 4.57E-01 0.00E+00 0.OOE+00 0.0OE+00 5.1 1E+04 8.06E+04 0.OOE+00 0.0OE+00 0.0OE+00 2.02E+02 0.OOE+00 1.61E+05 3.43E+02 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 4.99E+03 1.4IE+05 9.18E+01 3.48E+01 6.06E+00 5.73E-02 5.32E-01 1.59E+01 8.81E-01 4.47E+02 0.OOE+00 1.33E-02 1.07E+02 8.89E+00 1.59E+03 1.56E+03 6.06E+04 3.02E+03 2.19E+01 2.76E+02 1.77E+02 1.61E-01 4.57E-01 0.00E+00 7.06E+03 1.78E+02 3.53E+04 1.90E+05 1.42E+02 6.03E+02 1.73E+03 2.62E+01 2.14E+02 5.13E+05 6.566E+02 4.62E+0 I 0.00E+00 0.00E+00 6.24E+02 1.79E+00 1.1 9E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 5.1 IE+00 1.78E-01 2.49E+02 1.28E+02 1.92E-02 0.00E+00 0.00E+0O 0.O0E+00 1.45E+03 1.66E+03 3.41 E+02 4.47E-01 5.22E+00 1.97E+00 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE CAP A-8 27 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 pCi/ml) organ "o" Nuclide Te-129m Te-129 Te-131m Te-131 Te-132 1-131 1-132 1-133 1-134 1-135 Cs-134 Cs-136 Cs-137 Cs-138 Ba-139 Ba-140 Ba-141 La-140 La-142 Ce-141 Ce-143 Ce-144 Pr-144 Nd-147 W-1 87 Np-239

- Tot Body 1.47E+02 6.19E-01 5.71E+01 5.03E-01 1.24E+02 1.79E+02 9.96E+00 3.95E+01 5.40E+00 2.24E+0 I 1.33E+04 2.04E+03 7.855E+03 5.94E+00 2.30E-0 I 1.08E+02 1.29E-01 2.10E-01 9.13E-03 2.63E-01 4.94E-02 9.59E+00 9.64E-04 2.74E-01 2.68E+00 l.91E-03 Thyroid 3.20E+02 1.95E+00 1.08E+02 1.31 E+00 1.46E+02 1.02E+05 9.96E+02 1.90E+04 2.62E+02 4.011E+03 0.00E+00 0.001E+00 0.00E+00 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.00E+00 Kidney 3.89E+03 1.07E+01 6.94E+02 6.99E+00 1.27E+03 5.35E+02 4.54E+01 2.26E+02 2.40E+01 9.75E+01 5.27E+03 1.57E+03 4.07E+03 8.81E+00 5.23E-03 7.02E-01 2.68E-03 0.OOE+00 0.00E+00 1.08E+00 1.97E-0I 4.43E+01 4.44E-03 2.68E+00 0.00E+00 1.08E-02 Lung GI-LLI Bone 0.OOE+00 4.69E+03 9.31 E+02 0.OOE+00 1.92E+00 2.54E+00 0.OOE+00 6.80E+03 1.40E+02 0.00E+00 2.26E-01 1.59E+00 0.OOE+00 6.24E+03 2.04E+02 0.OOE+00 8.23E+01 2.18E+02 0.00E+00 5.35E+00 1.06E+01 0.OOE+00 1.16E+02 7.45E+01 0.00E+00 1.32E-02 5.56E+00 0.00E+00 6.87E+01 2.32E+01 1.75E+03 2.85E+02 6.84E+03 2.16E+02 3.21E+02 7.16E+02 1.35E+03 2.32E+02 8.77E+03 8.70E-01 5.12E-05 6.07E+00 3.17E-03 1.39E+01 7.85E+00 1.18E+00 3.38E+03 1.64E+03 1.63E-03 1.80E-09 3.81 E+00 0.00E+00 5.83E+04 1.57E+00 0.00E+00 2.68E+02 8.06E-02 0.00E+00 8.86E+03 3.43E+00 0.00E+00 1.67E+04 6.04E-01 0.0OE+00 6.04E+04 1.79E+02 0.00E+00 2.73E-09 1.90E-02 0.OOE+00 2.20E+04 3.96E+00 0.OOE+00 2.51E+03 9.16E+00 0.00E+00 7.1 1E+02 3.53E-02 Liver 3.47E+02 9.55E-01 6.85E+01 6.66E-0 1 1.32E+02 3.12E+02 2.85E+01 1.30E+02 1.5 1E+01 6.08E+01 1.63E+04 2.83E+03 1.20E+04 1.20E+01 5.59E-03 2.06E+00 2.88E-03 7.94E-01 3.67E-02 2.32E+00 4.46E+02 7.47E+01 7.87E-03 4.58E+00 7.66E+00 3.47E-03 1 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 51 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations 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 4.4 6.OOE-8 1.1OE-10 unknown use residence 3.3 9.10E-8 1.80E-10 cabin - limited use NE residence 4.9 4.OOE-8 7.40E-1 I full time occupancy ENE residence 4.4 4.OOE-8 8.70E-II full time occupancy residence 5.0 3.30E-8 6.90E-1 I full time occupancy E

residence 4.0 5.20E-8 1.50E-10 cabin - unknown use residence 3.7 5.80E-8 1.80E-10 part time occupancy residence +

4.5 4.30E-8 1.20E-I0 full time occupancy garden ESE oat hay and 3.3 1.40E-7 8.80E-10 field workers present only during the sugar peas day - 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 5.50E-6 1.90E-8 Gas effluent dose rates. PRRLs and boundary HASPs evaluated at this location.

dispersion value residence 1.2 1.20E-6 4.30E-9 cabin - very limited use residence 3.6 2.20E-7 6.30E-10 full time occupancy NNW residence 1.5 7.80E-7 2.30E-9 full time occupancy (trailer) - critical receptor ground plane and inhalation dose assessed at this location 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 52 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.3 GRW DOSE FACTORS FOR NOBLE GASES' Whole Body Dose Factor K

i (mnrem/yr per lCi/M3)

Skin Dose Factor L

i (mrem/yr per,uCim3)

Gamma Air Dose Factor M i (mrad/yr per lCi/M3)

Beta Air Dose Factor N,

(mradlyr per pCi/m3)

Radionuclide Kr-83m Kr-85m Kr-85 Kr-87 Kr-88 Kr-89 Kr-90 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 7.56E-02 1.17E+03 1.61E+01 5.92E+03 1.47E+04 1.66E+04 1.56E+04 9.15E+01 2.51E+02 2.94E+02 3.12E+03 1.8 lE+03 1.42E+03 8.83E+03 8.84E+03 1.46E+03 1.34E+03 9.73E+03 2.37E+03 1.0IE+04 7.29E+03 4.76E+02 9.94E+02 3.06E+02 7.1 IE+02 1.86E+03 1.22E+04 4.13E+03 2.69E+03 1.93E+01 1.23E+03 1.72E+01 6.17E+03 1.52E+04 1.73E+04 1.63E+04 1.56E+02 3.27E+02 3.53E+02 3.36E+03 1.92E+03 1.51 E+03 9.21E+03 9.30E+03 2.88E+02 1.97E+03 1.95E+03 1.03E+04 2.93E+03 1.06E+04 7.83E+03 1.11 E+03 1.48E+03 1.05E+03 7.39E+02 2.46E+03 1.27E+04 4.75E+03 3.28E+03 1 From Table B-l of Regulatory Guide l.109 (Rev. 1, Oct. 1977) 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY NUMBER CAP A-8 DIABLO CANYON POWER PLANT REVISION 27 PAGE 53 OF 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. IEIE+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-11OM 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 00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 54 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.5 GROUND PLANE DOSE FACTORS GRW DOSE PARAMETERS', R2.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 gCi/(sec m 2 ))

Nucli H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-10 RU-10 AG-1I SB-12' SB-I2' TE-12!

1-131 1-133 CS-13, CS-13i CS-13 BA-14 CE-14 CE-14' ND-14 de Bone 0.0OE+00 4.65E*06 1.3 8E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.00E+00 2.45E+08 1.37E+08 3

1.08E+08 6

4.20E+08 OM 3.45E+09 I

5.99E+08 5

2.34E+09 9M 1.98E+07 1.72E+07 2.45E+06 I

6.90E+09 6

1.51E+08 7

1.03E+10 0

2.05E+07 I

1.37E+07 4

6.96E+07 7

8.39E+06 Liver 0.0OE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.OOE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.5 1E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 T Body 0.00E+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.OOE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+I0 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Thyroid 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.OOE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.901E+09 1.51E+08 1.03E+I0 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Kidney 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.0OE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.51E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Lung 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.501E+03 0.0OE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.5 1E+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 GI-LLI 0.OOE+00 4.65E+06 1.38E+09 2.73E+08 3.80E+08 2.15E+10 7.46E+08 8.98E+06 2.16E+04 4.50E+03 0.OOE+00 2.45E+08 1.37E+08 1.08E+08 4.20E+08 3.45E+09 5.99E+08 2.34E+09 1.98E+07 1.72E+07 2.45E+06 6.90E+09 1.5 lE+08 1.03E+10 2.05E+07 1.37E+07 6.96E+07 8.39E+06 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 55 OF 62 I AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.6 GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW) 00692327.DOA 0

0509.0942

PACIFIC GAS AND ELECTRIC COM1PANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 56 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.6.1 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), INFANT AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per iiCi/m3) RjhInhal Nuclide Bone Liver T Bodv Thyroid Kidney Lune GI-LLI H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 O.OOE+00 0.OOE+00 0.OOE+00 1.36E+04 0.OOE+00 0.0OE+00 1.93E+04 0.001E+00 3.98E+05 3.29E+03 I.55E+07 1.1 5E+05 1.57E+04 2.02E+03 8.68E+04 9.98E+03 3.79E+04 5.17E+04 1.41 E+04 3.79E+04 1.32E+04 3.96E+05 4.83E+04 5.49E+05 5.60E+04 2.77E+04 3.19E+06 7.94E+03 3.68E+02 0.00E+00 2.53E+04 2.35E+04 1.22E+03 8.02E+03 6.26E+04 1.90E+05 0.OOE+00 0.OOE+00 O.OOE+00 2.79E+04 6.43E+03 0.OOE+00 0.OOE+00 7.22E+03 5.56E+02 4.77E+02 6.09E+03 4.44E+04 1.92E+04 7.03E+05 1.35E+05 6.12E+05 5.60E+0 1 1.67E+04 1.21E+06 8.13E+03 3.68E+02 8.95E+01 4.98E+03 9.48E+03 1.82E+03 1.18E+04 3.1 IE+04 8.82E+04 1.14E+04 8.82E+01 3.122E+05 2.03E+04 3.78E+03 6.79E+02 1.09E+04 5.00E+03 1.20E+04 1.09E+04 2.23E+03 1.96E+04 5.60E+03 7.45E+04 5.29E+04 4.55E+04 2.90E+03 1.99E+03 1.76E+05 5.00E+02 3.68E+02 5.75E+01 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.001E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.01 E+02 6.23E+01 5.47E+03 1.48E+07 3.56E+06 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 3.68E+02 1.32E+01 4.98E+03 0.00E+00 0.OOE+00 0.OOE+00 3.25E+04 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.1 IE+04 4.72E+03 4.24E+03 1.07E+05 1.09E+04 0.00E+00 0.00E+00 3.18E+04 5.188E+04 2.24E+04 1.90E+05 5.64E+04 1.72E+05 1.34E+01 5.25E+03 5.38E+05 3.1 5E+03 3.68E+02 1.28E+04 I.OOE+06 1.02E+06 7.77E+05 4.51 E+06 6.47E+05 0.001E+00 2.03E+06 2.69E+05 1.12E+07 1.75E+06 4.79E+05 5.52E+05 1.1 6E+07 3.67E+06 2.65E+06 1.64E+06 1.68E+06 0.00E+00 0.00E+00 7.97E+04 1.18E+04 7.13E+04 1.60E+06 5.17E+05 9.84E+06 3.22E+05 3.68E+02 3.57E+02 7.06E+03 2.48E+04 1.1I E+04 3.19E+04 5.14E+04 3.04E+03 6.40E+04 1.04E+05 1.31 E+05 2.17E+04 1.27E+04 1.61E+04 1.64E+05 3.30E+04 5.91 E+04 1.47E+04 6.90E+04 1.06E+03 2.16E+03 1.33E+03 1.43E+03 1.33E+03 3.84E+04 2.16E+04 1.48E+05 3.12E+04 1 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 57 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations 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 J.Ci/M3) Rj11 m01 Nuclide H-3 CR-51 MN-54 FE-59 C0-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.00E+00 0.00E+00 0.00E+00 2.07E+04 0.00E+00 0.00E+00 4.26E+04 0.00E+00 5.99E+05 4.1 lE+03 3.85E+07 1.90E+05 2.35E+04 2.79E+03 1.36E+05 1.69E+04 5.74E+04 9.84E+04 1.92E+04 4.81E+04 1.66E+04 6.5 1E+05 6.51E+04 9.07E+05 7.40E+04 3.92E+04 6.77E+06 1.08E+04 Liver 6.40E+02 0.00E+00 4.29E+04 3.34E+04 1.77E+03 1.31 E+04 1.13E+05 1.98E+05 0.00E+00 0.00E+00 0.00E+00 4.18E+04 9.188E+03 0.00E+00 0.00E+00 1.14E+04 7.40E+02 7.59E+02 6.85E+03 4.8 1E+04 2.03E+04 1.OlE+06 1.71 E+05 8.25E+05 6.48E+01 1.95E+04 2.12E+06 8.73E+03 T Body 6.40E+02 1.54E+02 9.5 lE+03 1.67E+04 3.16E+03 2.26E+04 7.03E+04 1.14E+05 1.72E+04 1.1 E+02 7.66E+05 3.70E+04 6.55E+03 1.07E+03 1.69E+04 9.14E+03 2.OOE+04 2.07E+04 3.04E+03 2.73E+04 7.70E+03 2.25E+05 1.16E+05 1.28E+05 4.33E+03 2.90E+03 3.6 1E+05 6.8 1E+02 Thvroid 6.40E+02 8.55E+01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.0OE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 1.26E+02 9.1 0E+0 1 6.33E+03 1.62E+07 3.85E+06 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Kidney 6.40E+02 2.43E+01 I1.OOE+04 0.00E+00 0.OOE+00 0.OOE+00 7.14E+04 0.OOE+00 0.001E+00 0.00E+00 0.OOE+00 5.96E+04 8.62E+03 7.03E+03 1.84E+05 2.12E+04 0.00E+00 0.00E+00 5.03E+04 7.88E+04 3.38E+04 3.30E+05 9.55E+04 2.82E+05 2.1 lE+01 8.55E+03 1.17E+06 4.81E+03 Lung 6.40E+02 1.70E+04 1.58E+06 1.27E+06 1.1 IE+06 7.07E+06 9.95E+05 0.00E+00 2.166E+06 2.62E+05 I.48E+07 2.23E+06 6.14E+05 6.62E+05 1.43E+07 5.48E+06 3.24E+06 2.32E+06 1.76E+06 0.00E+00 0.OOE+00 1.21E+05 1.45E+04 1.04E+05 1.74E+06 5.44E+05 1.20E+07 3.28E+05 GI-LLI 6.40E+02 1.08E+03 2.29E+04 7.07E+04 3.44E+04 9.62E+04 1.63E+04 7.99E+03 1.67E+05 2.68E+05 3.43E+05 6.11 E+04 3.70E+04 4.48E+04 4.29E+05 11.OOE+05 1.64E+05 4.03E+04 1.82E+05 2.84E+03 5.48E+03 3.85E+03 4.18E+03 3.62E+03 1.02E+05 5.66E+04 3.89E+05 8.211E+04 1 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 58 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.6.3 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), TEEN AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per jtCi/m3 ) Rjinhal Nuclide H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-i lOM SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.00E+00 0.00E+00 0.00E+00 1.59E+04 0.00E+00 O.OOE+00 3.86E+04 0.OOE+00 4.34E+05 2.98E+03 3.3 IE+07 1.46E+05 1.86E+04 2.1 OE+03 9.84E+04 1.38E+04 4.30E+04 7.38E+04 1.39E+04 3.54E+04 1.22E+04 5.02E+05 5.15E+04 6.70E+05 5.47E+04 2.84E1+04 4.89E+06 7.86E+03 Liver 7.25E+02 0.OOE+00 5.1 IE+04 3.70E+04 2.07E+03 1.5 1E+04 1.34E+05 1.90E+05 0.001E+00 0.00E+00 0.00E+00 4.58E+04 1.03E+04 0.OOE+00 0.OOE+00 1.31 E+04 7.94E+02 8.08E+02 6.58E+03 4.91E+04 2.05E+04 1.13E+06 1.94E+05 8.48E+05 6.70E+01 1.90E+04 2.02E+06 8.5 61+03 T Body 7.25E+02 1.35E+02 8.40E+03 1.43E+04 2.78E+03 1.98E+04 6.24E+04 8.40E+04 1.25E+04 8.00E+01 6.66E+05 3.155E+04 5.66E+03 8.96E+02 1.24E+04 7.99E+03 1.68E+04 1.72E+04 2.25E+03 2.64E+04 6.22E+03 5.49E+05 1.37E+05 3.1 IE+05 3.52E+03 2.17E+03 2.62E+05 5.13E+02 Thyroid 7.25E+02 7.50E+0 I 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 9.76E+01 7.04E+01 4.58E+03 1.46E+07 2.92E+06 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Kidney 7.25E+02 3.07E+01 1.27E+04 0.00E+00 0.00E+00 0.00E+00 8.64E+04 0.00E+00 0.001E+00 0.00E+00 0.00E+00 6.74E+04 1.00E+04 7.43E+03 1.90E+05 2.501E+04 0.00E+00 0.OOE+00 5.19E+04 8.40E+04 3.59E+04 3.75E+05 1.IOE+05 3.04E+05 2.28E+01 8.88E+03 1.21E+06 5.02E+03 Lung 7.25E+02 2.1 OE+04 1.98E+06 1.53E+06 1.34E+06 8.72E+06 1.24E+06 0.OOE+00 2.42E+06 2.93E+05 1.65E+07 2.69E+06 7.51 E+05 7.83E+05 1.61E+07 6.75E+06 3.85E+06 2.74E+06 1.98E+06 0.00E+00 0.00E+00 1.46E+05 1.78E+04 1.21E+05 2.03E+06 6.14E+05 1.34E+07 3.72E+05 GI-LLI 7.251E+02 3.00E+03 6.68E+04 1.78E+05 9.52E+04 2.599E+05 4.66E+04 1.77E+04 3.71E+05 5.59E+05 7.651E+05 1.49E+05 9.68E+04 1.09E+05 9.60E+05 2.73E+05 3.98E+05 9.92E+04 4.05E+05 6.49E+03 1.03E+04 9.76E+03 1.09E+04 8.48E+03 2.299E+05 1.26E+05 8.64E+05 1.82E+05 1 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 59 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations TABLE 10.6.4 GRW DOSE PARAMETERS FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), ADULT AGE GROUP, INHALATION PATHWAY ORGAN "O" (mrem/yr per I.Ci/m3) RiInhaI Nuclide Bone Liver T Bodv Thyroid Kidney H-3 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.0OE+00 0.OOE+00 0.0OE+00 1.18E+04 0.00E+00 0.OOE+00 3.24E+04 0.OOE+00 3.04E+05 2.09E+03 2.87E+07 1.07E+05 1.41 E+04 1.53E+03 6.91E+04 1.08E+04 3.12E+04 5.34E+04 9.76E+03 2.52E+04 8.64E+03 3.73E+05 3.90E+04 4.78E+05 3.90E+04 1.99E+04 3.43E+06 5.27E+03 7.18E+02 0.00E+00 3.96E+04 2.78E+04 1.58E+03 1.1 5E+04 1.03E+05 1.35E+05 0.OOE+00 0.00E+00 0.OOE+00 3.44E+04 7.82E+03 0.0OE+00 0.0OE+00 1.OOE+04 5.89E+02 5.95E+02 4.67E+03 3.58E+04 1.48E+04 8.48E+05 1.46E+05 6.21E+05 4.90E+0 1 1.35E+04 1.43E+06 6.1 OE+03 7.18E+02 11.OOE+02 6.30E+03 1.06E+04 2.07E+03 1.48E+04 4.66E+04 5.90E+04 8.72E+03 5.61E+0I 5.77E+05 2.33E+04 4.21E+03 6.58E+02 8.72E+03 5.94E+03 1.24E+04 1.26E+04 1.58E+03 2.05E+04 4.52E+03 7.28E+05 1.1OE+05 4.28E+05 2.57E+03 1.53E+03 1.84E+05 3.65E+02 7.18E+02 5.95E+0 I 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.010E+00 0.00E+00 0.00E+00 7.55E+01 5.40E+01 3.44E+03 1.19E+07 2.15E+06 0.00E+00 0.00E+00 0.0OE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 7.18E+02 2.28E+01 9.84E+03 0.OOE+00 0.00E+00 0.OOE+00 6.90E+04 0.00E+00 0.OOE+00 0.001E+00 0.00E+00 5.42E+04 7.74E+03 5.83E+03 1.34E+05 1.97E+04 0.OOE+00 0.OOE+00 3.66E+04 6.13E+04 2.58E+04 2.87E+05 8.56E+04 2.22E+05 1.67E+O1 6.26E+03 8.48E+05 3.56E+03 Lung 7.18E+02 1.44E+04 1.40E+06 1.02E+06 9.28E+05 5.97E+06 8.64E+05 0.00E+00 1.40E+06 1.70E+05 9.60E+06 1.77E+06 5.05E+05 5.05E+05 9.36E+06 4.63E+06 2.48E+06 1.74E+06 1.16E+06 0.00E+00 0.OOE+00 9.76E+04 1.20E+04 7.52E+04 1.27E+06 3.62E+05 7.78E+06 2.21 E+05 GI-LLI 7.18E+02 3.32E+03 7.74E+04 1.88E+05 1.06E+05 2.85E+05 5.34E+04 1.66E+04 3.50E+05 5.06E+05 7.22E+05 1.SOE+05 1.04E+05

1. IOE+05 9.12E+05 3.02E+05 4.06E+05 1.01E+05 3.83E+05 6.28E+03 8.88E+03 1.04E+04 1.177E+04 8.40E+03 2.18E+05 1.20E+05 8.16E+05 1.73E+05 1 Dose factors are based upon NUREG 0133 methodology.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE CAP A-8 27 60 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations UNITS TABLE 10.6.5 GRW DOSE PARAMETERS' FOR RADIOIODINES, RADIOACTIVE PARTICULATES, AND ANY RADIONUCLIDE OTHER THAN NOBLE GAS (IPT), GASEOUS EFFLUENTS (GRW), CHILD AGE GROUP, VEGETATION PATHWAY ORGAN "O" (mrem/yr per pCi/(sec m2)) Rj1 g Nuclide H-32 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-1 10M SB-124 SB-125 TE-129M 1-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.OOE+00 0.00E+00 0.00E+00 3.97E+08 0.OOE+00 0.OOE+00 8.12E+08 0.OOE+00 3.59E+10 2.3 1E+04 1.87E+12 3.86E+06 4.12E+OS 1.53E+07 7.45E+08 3.21 E+07 3.52E+08 4.99E+08 8.40E+08 1.43E+08 3.52E+06 1.60E+10 8.18E+07 2.39E+1 0 2.77E+08 6.55E+05 1.27E+08 7.27E+04 Liver 2.29E+03 0.OOE+00 6.65E+08 6.42E+08 6.45E+07 3.78E+08 2.16E+09 4.54E+08 0.OOE+00 0.OOE+00 0.OOE+00 8.50E+05 1.61E+05 0.OOE+00 0.00E+00 2.17E+07 4.57E+06 3.85E+06 2.35E+08 1.44E+08 4.36E+06 2.63E+10 2.25E+08 2.29E+10 2A3E+05 3.27E+05 3.98E+07 5.89E+04 T Body 2.29E+03 1.17E+05 1.77E+08 3.20E+08 1.97E+08 1.12E+09 1.35E+09 2.79E+08 1.03E+09 6.188E+02 3.77E+10 7.56E+05 1.15E+05 5.89E+06 9.30E+07 1.74E+07 1.23E+08 1.05E+08 1.30E+08 8.17E+07 1.65E+06 5.55E+09 1.46E+08 3.38E+09 1.62E+07 4.85E+04 6.78E+06 4.56E+03 Thyroid Kidney 2.29E+03 6.49E+04 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.0OE+00 0.00E+00 0.00E+00 0.OOE+00 0.0OE+00 0.OOE+00 0.00E+00 0.0OE+00 7.78E+05 4.62E+05 2.71E+08 4.75E+1 0 8.09E+08 0.OOE+00 0.0OE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 2.29E+03 1.77E+04 1.86E+08 O.OOE+00 0.OOE+00 0.OOE+00 1.36E+09 0.00E+00 0.0OE+00 0.00E+00 0.00E+00 1.22E+06 1.51E+05 3.86E+07 1.0IE+09 4.04E+07 0.00E+00 0.00E+00 2.47E+09 2.36E+08 7.26E+06 8.16E+09 1.20E+08 7.46E+09 7.90E+04 1.43E+05 2.21E+07 3.23E+04 Lunt!

GI-LLI 2.29E+03 1.18E+05 0.00E+00 1.86E+08 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 O.00E+00 1.96E+08 2.78E+08 0.OOE+00 0.00E+00 0.OOE+00 2.93E+09 1.79E+07 2.68E+09 1.45E+05 0.00E+00 0.00E+00 0.OOE+00 2.29E+03 6.20E+06 5.58E+08 6.69E+08 3.76E+08 2.10E+09 3.80E+08 2.92E+07 1.39E+09 6.57E+07 1.67E+10 8.86E+08 2.97E+08 3.96E+08 1.16E+10 2.58E+09 2.20E+09 1.19E+09 1.02E+09 1.28E+07 1.76E+06 1.42E+08 7.90E+06 1.43E+08 1.40E+08 4.08E+08 1.04E+10 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 PCi/m3 for all pathways, and they must be multiplied by X/Q.

00692327.DOA 08 0509.0942

PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT NUMBER REVISION PAGE UNITS CAP A-8 27 61 OF 62 1 AND 2 TITLE:

Off-Site Dose Calculations 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 pCi/(sec m2)) Rj.vj Nuclide H-3' CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M I-131 I-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 Bone 0.001E+00 0.00E+00 0.00E+00 1.79E+08 0.00E+00 0.00E+00 4.24E+08 0.00E+00 1.51E+10 1.24E+04 9.22E+1 I 1.72E+06 1.93E+05 6.82E+06 3.09E+08 1.52E+07 1.55E+08 2.14E+08 3.6 1E+08 7.68E+07 1.93E+06 7.1OE+09 4.35E+07 1.01E+10 1.38E+08 2.83E+05 5.27E+07 3.67E+04 Liver 1.47E+03 0.00E+00 4.54E+08 4.18E+08 4.37E+07 2.49E+08 1.47E+09 2.75E+08 0.00E+00 0.00E+00 0.00E+00 5.44E+05 1.07E+05 0.00E+00 0.00E+00 1.44E+07 2.85E+06 2.34E+06 1.34E+08 1.08E+08 3.28E+06 1.67E+10 1.71E+08 1.35E+10 1.69E+05 1.89E+05 2.18E+07 4.OOE+04 T Body 1.47E+03 6.16E+04 9.01E+07 1.6 1E+08 11.OIE+08 5.60E+08 6.86E+08 1.29E+08 4.33E+08 3.35E+02 1.84E+10 3.74E+05 5.90E+04 2.91E+06 3.90E+07 8.73E+06 6.03E+07 5.01E+07 5.72E+07 5.78E+07 1.00E+06 7.75E+09 l.lSE+08 4.69E+09 8.90E+06 2.17E+04 2.83E+06 2.39E+03 Thyroid Kidney 1.47E+03 1.47E+03 3.42E+04 1.35E+04 O.OOE+00 1.36E+08 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 O.00E+00 9.411E+08 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 O.OOE+00 7.99E+05 0.OOE+00 1.04E+05 0.00E+00 2.40E+07 0.00E+00 5.97E+08 0.OOE+00 2.74E+07 3.51 E+05 0.00E+00 2.05E+05 0.00E+00 1.17E+08 1.SlE+09

• 3.14E+10 1.85E+08 4.58E+08 5.75E+06 0.00E+00 5.31E+09 0.OOE+00 9.3 1E+07 O.OOE+00 4.59E+09 0.00E+00 5.74E+04 0.OOE+00 8.89E+04 0.00E+00 1.30E+07 0.00E+00 2.35E+04 Lung 1.47E+03 8.79E+04 0.00E+00 1.32E+08 0.00E+00 0.00E+00 O.OOE+00 0.001E+00 0.00E+00 0.001E+00 0.OOE+00 0.00E+00 0.00E+00 0.001E+00 0.00E+00 0.001E+00 1.35E+08 1.88E+08 0.00E+00 0.00E+00 0.001E+00 2.03E+09 1.47E+07 1.78E+09 1.14E+05 0.00E+00 0.00E+00 0.OOE+00 GI-LLI 1.47E+03 1.03E+07

'9.32E+08 9.89E+08 6.02E+08 3.24E+09 6.23E+08 4.06E+07 1.80E+09 1.02E+08 2.1 IE+10 1.26E+09 4.58E+08 5.69E+08 1.48E+10 4.03E+09 3.1 IE+09 1.67E+09 1.36E+09 2.133E+07 2.48E+06 2.08E+08 1.38E+07 1.92E+08 2.13E+08 5.40E+08 1.33E+10 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 jiCi/m3 for all pathways, and they must be multiplied by X/Q.

00692327.DOA 08 0509.0942

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

Off-Site Dose Calculations 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 liCi/(sec m 2)) R1.v Nuclide Bone Liver T Body Thyroid Kidney Lunp GI-LLI H-32 CR-51 MN-54 FE-59 CO-58 CO-60 ZN-65 RB-86 SR-89 Y-90 SR-90 ZR-95 NB-95 RU-103 RU-106 AG-110M SB-124 SB-125 TE-129M I-131 1-133 CS-134 CS-136 CS-137 BA-140 CE-141 CE-144 ND-147 0.OOE+00 O.OOE+00 0.00E+00 1.26E+08 0.OOE+00 0.0OE+00 3.177E+08 0.001E+00 9.95E+09 1.33E+04 6.95E+1 I 1.18E+06 1.43E+05 4.77E+06 1.93E+08 1.05E+07 1.04E+08 1.37E+08 2.51 E+08 8.07E+07 2.08E+06 4.67E+09 4.25E+07 6.36E+09 1.29E+08 1.97E+05 3.29E+07 3.37E+04 1.29E+03 0.OOE+00 3.13E+08 2.96E+08 3.08E+07 1.67E+08 1.01 E+09 2.20E+08 0.00E+00 0.00E+00 0.OOE+00 3.77E+05 7.95E+04 0.00E+00 0.00E+00 9.75E+06 1.96E+06 1.53E+06 9.37E+07 1.15E+08 3.62E+06 1.1 lE+10 1.68E+08 8.70E+09 1.61E+05 1.33E+05 1.38E+07 3.90E+04 1.29E+03 4.64E+04 5.97E+07 1.13E+08 6.90E+07 3.69E+08 4.56E+08 1.03E+08 2.86E+08 3.57E+02 1.40E+10 2.55E+05 4.27E+04 2.05E+06 2.44E+07 5.79E+06 4.1 1E+07 3.25E+07 3.97E+07 6.62E+07 1.1OE+06 9.08E+09 1.21E+08 5.70E+09 8.42E+06 1.5 1E+04 1.77E+06 2.33E+03 1.29E+03 2.77E+04 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.52E+05 1.39E+05 8.62E+07 3.78E+10 5.32E+08 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 1.29E+03 1.02E+04 9.3 1E+07 O.OOE+00 0.00E+00 0.OOE+00 6.75E+08 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 5.92E+05 7.86E+04 1.82E+07 3.72E+08 1.92E+07 0.00E+00 0.00E+00 1.05E+09 1.98E+08 6.31 E+06 3.59E+09 9.33E+07 2.95E+09 5.49E+04 6.19E+04 8.16E+06 2.28E+04 1.29E+03 6.15E+04 0.OOE+00 8.27E+07 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.0OE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 8.08E+07 1.05E+08 0.001E+00 0.00E+00 0.00E+00 1.19E+09 1.28E+07 9.8 1E+08 9.24E+04 0.OOE+00 0.00E+00 0.00E+00 1.29E+03 1.17E+07 9.58E+08 9.87E+08 6.24E+08 3.14E+09 6.36E+08 4.34E+07 1.60E+09 1.4 1E+08 1.75E+10 1.20E+09 4.83E+08 5.57E+08 1.25E+10 3.98E+09 2.95E+09 1.50E+09 1.26E+09 3.05E+07 3.25E+06 1.94E+08 1.90E+07 1.68E+08 2.65E+08 5.09E+08 1.1 E+10 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 PCi/M3 for all pathways, and they must be multiplied by X/Q.

00692327.DOA 08 0509.0942

1 0104100 Page I of I DIABLO CANYON POWER PLANT CAP A-8 ATTACHMENT 1 1.1 1A2

- TITLE:

Liquid Discharges (LRW) Monitored for Radioactivity LIQUID RADWASTE SYSTEM CONDENSATE DEMINERALIZER REGENERATE TANKS STEAM GENERATOR BLOWDOWN SW)

N ?,O nnnrqvnnq 00692327.DOA 08 0509.0942

10/31/00 Page I of I DIABLO CANYON POWER PLANT CAP A-8 ATTACHMENT 11.2 1

AND 2 TITLE:

Gaseous Releases (GRW) Monitored for Radioactivity SRE

-.- $....'a t.... ---..I, im A-

~WASTr 9

. -0+--UNIT S

r-- !-

F t

[i I....

4 WASTE i

i i

l COMPRES5OR COMPRESSOR r7 r

.I I

SEP SEP_

I l

YEACIOR i

I i

COOLAN

'-..--...COOL.-N.

TINDECAYHDWCA TTANK 2

I S

- r ACV?

9 2 N2.e

§I)

L 1-3 1

e----'

-EPA I

DUMP TO ATMOSPHERE DUMP TO ATMOSPHERE DUMP TO ATMOSPHERE I o %

4 4 4 4 A

35%ATIJOS t

4 REHEAT I :

I l ~ f l ~ ) ~ f y ~ l ~ fR EEU E P

!I

!F VALVES VALVES VALVES

IKI ;

23S L7t n,.5 74 i.- -i-i._.L.J RI 1gj__

_J T A TANK I

G 5TEA E

1 CONDENSERDIDIATIS g

L.. J......L.... L......L....

HP.MICCDNE T1BE U

OR.40 STEAM :MA~lDIN P

S j9i.4 SIG S0TAWO GLANO STEAM CONDENSER.

D I-UNIT 2 4

-.UNIT2

_V N

T I

IS IIIO I,3 L _!-.L-J LANTVENT LE-E C

MTO ATMoSPHERE J-J 44A IJ~ T Qll~

I.........

• 5 is)1

_,1 PURGE I

ATMOS.

T SOUD RADWASTEI BLDG. VENT ATMOS s

r 00692319 00692327.DOA 08 0509.0942 PG&E Letter DCL-04-050 Radwaste Solidification Process Control Program (Procedure RP2.DC2, Revision 12)

U ONTROLLEOPROCEDURE- 0 O TV'USE'TOPERFORM W6AORKorISSUE FOR USEj w';

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 NUCLEAR POWER GENERATION REVISION 12 DIABLO CANYON POWER PLANT PAGE 1 OF 5 ADMINISTRATIVE PROCEDURE TITLE:

Radwaste Solidification Process Control Program 02/06/03 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/liquid/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.

RESPONSIBILITIES 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.

v13_01180412.DOC OIB 0206.0933

-.'.GAS

^NCONTROLLEfLPROCEDURE-,DONOTLUSE TOOPERFORM WORKor ISSULEFOR USEB ;

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 2 OF 5 TITLE:

Radwaste Solidification Process Control Program

4.

PREREQUISITES 4.1 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.

4.2 Any major change to the solid radwaste treatment system shall be reported 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.2. This information may be submitted as part of the annual FSAR update in lieu of the annual Radioactive Effluent Release report.

5.

INSTRUCTIONS 5.1 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.

5.2 WET WASTE 5.2.1 LIQUID/WET WASTE Liquid/wet wastes are processed to a condition meeting shipping and disposal criteria. These criteria include requirements for immobilization, stability and limits on free standing water (FSW). Specific instructions on processing and required FSW limits are contained in plant procedures and/or qualified vendor procedures.

5.2.2 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.

5.2.3 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.

5.2.4 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.

v13_01180412.DOC ORB 0206.0933

UaNCONTROLLED PROCEDURE -

ONO TO SE TO PERFORM WORK or ISSUE FOR USE.

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 3 OF 5 TITLE:

Radwaste Solidification Process Control Program 5.2.5 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.

f.

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

5.2.6 SAMPLING PROGRAM FOR SOLIDIFICATION 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 7. 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.

5.2.7 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.

5.2.8 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.

v13_01180412.DOC OIB 0206.0933

TNCONTROLLED PROCEDURE-NO, uIET iuEcFRuM R

ISSU FOR.SEo*

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 4 OF 5 TITLE:

Radwaste Solidification Process Control Program 5.2.9 EXOTHERMIC PROCESSES Vendors utilized for radioactive waste solidification that use an exothermic 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.

5.3 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.

5.4 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:

5.4.1 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.

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

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

5.5 REMEDIAL ACTIONS 5.5.1 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.

5.5.2 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.

5.6 VENDOR REPORTS 5.6.1 Topical Report TR-002, 10 CFR 61 Qualified Radioactive Waste Forms, Rev. l, maintained in Document Control Master File, Catalog No.

TK 9400/ATG-1.

v13_01180412.DOC OIB 0206.0933

• IJNCONTROLLEDPROCEDURE -.DONOTLUSE TOPERFORM WORK or SSUE ORaUSER i

PACIFIC GAS AND ELECTRIC COMPANY NUMBER RP2.DC2 DIABLO CANYON POWER PLANT REVISION 12 PAGE 5 OF 5 TITLE:

Radwaste Solidification Process Control Program 5.6.2 The following are maintained in Document Control Master File, Catalog No.

TK 94001 DTI-l.

a.

Topical Report DTI-VERI-100-NP-A. VERITm (Vinyl Ester Resin In Situ) Solidification Process for Low-Level Radioactive Waste, Rev 1.

b.

Topical Report DT-VERI-I00-NP-A, Addenduml.ENCAP Encapsulation Utilizing the VERI Solidification Process.

C.

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

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

6.

RECORDS 6.1 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.

7.

ATTACHMENTS 7.1 Form 69-10350, "Process Control Program (PCP) Verification," 06/03/93 7.2 "Major Change to the Solid Radwaste Treatment System Evaluation," 05/24/01

8.

REFERENCES 8.1 Title 10 Code of Federal Regulations.

8.2 NUREG 0472 and 0473.

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

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

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

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

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

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

v13_01180412.DOC OIB 0206.0933

69..-

5UCONTROLEDPROCEDURE-' O'NOTUSE JOPERFORM. kRK or ISSUEFOR USE'*

69-10350 06/03/93 Page 1 of I DIABLO CANYON POWER PLANT RP2.DC2 ATTACHMENT 7.1 TITLE:

Process Control Program (PCP) Verification WASTE BATCH PCP DATE Number TypefFailed NOTES OPERATOR VERIFIER I

_- I _

I I1 I_

I__

4-4-

4-4-

4-4-

4-L 4-4-

4-4-

4-4 I

4 4

4 4

4 I

¶ 4

4 4

4 4

I I I

I I

I I

I

.I I I I I I

1 4-1 4-4-

4 1

1

.5.

5

.5. __________

1 1

v13_01180412DOC OIB 0206.0933

.** eUNCONTROLLEDPROCEDURE-DONOTUSE TOPERFORMKWJRK orISSUEFOR USE *,.

05/24/01 Page I of I DIABLO CANYON POWER PLANT RP2.DC2 ATTACHMENT 7.2 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 IO CFR 50.59;

2. Sufficient detailed information to totally support the reason for the change without benefit of additional 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.

v1301180412.DOC OIB 0206.0933 PG&E Letter DCL-04-050 2003 Land Use Census PG&E Letter DCL-04-050 2003 LAND USE CENSUS Diablo Canyon Power Plant (DCPP) radiation protection personnel conducted a Land Use Census in the vicinity of DCPP for 2003. The land use census is based on Nuclear Regulatory Commission (NRC), Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants", 10 CFR 50 Appendix I section IV.

B. 3, and required by DCPP Program Directive CY2, "Radiological Monitoring and Controls Program."

DCPP IDAP RPL.IDI 1, "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 census is conducted at least once per year during the growing season (between Feb 15 and Dec 1) for the Diablo Canyon environs.

The 2003 Land Use Census was conducted using GPS (global positioning),

phone, face-to-face interviews, exploration, and data from the 2002 Land Use Census.

Twelve individual landowners or tenants were contacted between June 5 th and September 1 1th, 2003. Two landowners were unavailable for contact.

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 1.93 kilometers (1.2 miles) northwest of the plant (occupied approximately 1 month per year). Ranchers use this trailer during cattle round-ups. The nearest residence in each sector is summarized in Table 1.

The census identified one household garden greater than 50 square meters (500 square feet) that produces broadleaf vegetation. This garden is located in the East sector at 7.24 kilometers (4.5 miles) from DCPP Unit 1.

Much of the area outside the plant site boundary is used for rotational cattle grazing by four separate cattle operations. Various numbers of cattle or calves are sold to mass market at the end of each year. Goats are allowed to graze within the plant site boundary for weed abatement. Some of the ranchers slaughter small numbers of cattle and goats for personal consumption.

The rancher in the northern cattle operation has about 50 cattle outside the plant site boundary and utilizes the NW, NNW, N, and NNE sectors. About 50 calves are to be sold to mass market in 2003. This rancher slaughtered 2 calves in 2003 for personal consumption. Additionally, he managed about 350 goats that were used for weed PG&E Letter DCL-04-050 abatement in all landward sectors within the plant site boundary. During 2003, approximately 80 goats are to be sold in mass-market auction. This rancher does not plan to slaughter any goats in 2003 for his personal consumption.

The rancher in the NNE cattle operation has about 100 cattle outside the plant site boundary. About 100 calves are to be sold to mass market in 2003. This rancher does not plan to slaughter any cattle for his personal consumption.

The rancher in the ENE cattle operation has about 80 cattle outside the plant site boundary. About 80 calves are to be sold to mass market in 2003. This rancher slaughtered one steer in 2003 for personal consumption.

The rancher in the southern cattle operation manages about 600 cattle outside the plant site boundary and utilizes the E, ESE, and SE sectors. Harris Ranch Beef Corporation owned these cattle and sold all of them to mass market in 2003. This rancher does not plan to slaughter any cattle in 2003 for personal consumption.

A farm is located on the coastal plateau, along the site access road, in the east-southeast (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 75% legumes (sugar peas) and 25% cereal grass (oat hay). Farm workers occupy this area during the day.

Two landowners take wild game for personal consumption in the NNE, NE, and ENE sectors between 4.83 to 8.0 kilometers (3 - 5 miles) from the plant. This wild game consists of approximately 2 deer and 4 wild pigs per landowner.

There is a California State Park Ranger Office in the north-northwest (NNW) sector at 7.483 kilometers (4.65 miles) from the plant. Approximately 3 people occupy this office during work hours, Monday thru Friday from 1000 - 1500.

There is a public campground located in the north-northwest (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 13 residences were identified within the 8-kilometer (5-mile) radius of the plant, which were confirmed or appear to be occupied during 2003. Ownership for some of the properties were changed in the 2003 Land Use Census. Two abandoned structures are located in each of the NNW and NNE sectors.

Table I summarizes the nearest residences in each meteorological sector. Figure 3 shows the locations of the residences and gardens in the vicinity of DCPP.

PG&E Letter DCL-04-050 Table I Land Use Census 2003 Distance in Kilometers (and Miles) from the Unit 1 Center Line to the Nearest Milk Animal, Residence, and Vegetable Garden 22/z Degree (a)

Nearest Nearest Residence Nearest Radial Sector Milk Animal Residence Azimuth Vegetable l

km (mi)

Degree Garden km (mi)

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 None 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) (c)

ESE None None 5.31 (3.3)(d)

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.

(

This 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 vegetable garden located in the East sector is located at the 098 azimuth degree.

There is also a full time residence at this location.

(d) The vegetable garden indicated is the commercial farm along the westward side of the site access road; however, it does not produce broadleaf vegetation.

PG&E Letter DCL-04-050 NW UNITS 1 AND 2 DIABLO CANYON SITE a Gardens or Farm A Residences I

0 1

2 3

4 5

SCALE IN MILES 97033M4anduse 02p Figure 3. Units 1 and 2 Diablo Canyon Power Plant Land Use Census.

bcc/enc*:

David C. Chen Jeffery E. Gardner John R. Knemeyer Robert W. Lorenz To save some paper, bcc's should receive the enclosure without attachments 1-5 (copies of DCPP procedures).

OUTGOING CORRESPONDENCE SCREEN (Remove prior to NRC submittal)

Document:

PG&E Letter DCL-04-050

Subject:

2003 Annual Radioactive Effluent Release Report File Location S:\\RS\\RA\\Annual Reports\\2003 Annual Rad Effluent Report.DOC Version:

FSAR Update Review Utilizing the guidance in X13.1D2, does the FSAR Update need to be revised?

Yes D No 1 If TYes, submit an FSAR Update Change Request in accordance with X13.1D2 (or if this is an LAR, process in accordance with WG-9)

Commitment #1 Statement of Commitment: NONE