Text

License Change Application 50 to Amend License NPF-1 Re Radiological Tech Specs
	ML19274E250
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	03/15/1979
From:	Goodwin C; PORTLAND GENERAL ELECTRIC CO.
To:	;
Shared Package
ML19274E249	List: ML19274E248; ML19274E250;
References
	TAC-07721, TAC-7721, NUDOCS 7903210215
	Download: ML19274E250 (60)
	v • d • e

y' PORTLAND GENERAL ELECTRIC COMPANY EUCENE WATER & ELECTRIC BOARD NiD PACIFIC POWER & LIGHT COMPANY TROJAN NUCLEAR PLANT Operating License NPF-1 Docket 50-344 License Change Application 50 This License Change Application is submitted in response to the USNRC's letters of July 11, 1978 and November 15, 1978, requesting all radio-logical Technical Specifications be combined into Appendix A of FOI.

NPF-1 in accordance with 10 CFR 50, Appendix I, and 40 CFR 190.

PORTLAND GENERAL ELECTRIC COMPANY h

By

- C C.Goodwin,J/r Assistant Vice Prdsident Thermal Plant Operation and Maintenance Subscribed and sworn to before me this 15th day of March 1979.

AuL a rb>w Notary Public ofeDregon 7- [ /f,7f My Commission Expires:

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LCA 50 Page 1 of 6 LICENSE CHANGE AEPLICATION 50 1.

Appendix A (a) Add to Section 1.0 " Definitions" new definitions for " Source Check", " Process Control Program", " Solidification", "Offsite Dose Calculation Manual (ODCM)", " Gaseous Radwaste Treatment System", and " Ventilation Exhaust Treatment System" in accord-ance with the use of these terms in the new specifications outlined below and as identified in replacement pages in Attachment A.

(b) Add a new Section 3.3.3.8 " Radioactive Liquid Effluent Instrumen-tation" as identified in replacement pages in Attachment A.

The inclusion of this section reflects new criterion put forth by USNRC's Effluent Standard Technical Speciff 0ations.

(c) Add new Section 3.3.3.9 " Radioactive Gaseous Process and Effluent Monitoring Instrumentation" as identified in replacement pages in Attachment A.

The inclusion of this section reflects new criteria put forth by USNRC's Effluent S tandard Technical Spec 4 fications.

(d) Add new Section 3.11.1 " Liquid Ef fluents" as identified in re placement pages in Attachment A.

The contents of this specification reflect the guidance put forth in the USNRC's Ef fluent S tandard Technical Specifications. This section ensures that the requirements of 10 CFR 20 and 10 CFR 50 (including Appendix I) are met with respect to liquid effluent concentrations, resulting doses to the general public and maintenance and use of liquid radwaste treatment systems.

(e) Add new Section 3.11.2 " Caseous Ef fluents" as identified in replacement pages in Attachment A.

The contents of this section reflect the guidance put forth in the USNRC's Ef fluent Technical Specifications. This section ensures tha t the requirements of 10 CFR 20 and 10 CFR 50 (including Appendix 1) and 40 CFR 190 are met with respect to doses to the general public resulting f rom plant effluents and the maintenance, use and integrity of the gaseous radwaste treatment systems.

(f) Add new Section 3.11.3 " Solid Radioactive Waste" as identified in replacement pages in Attachment A.

This section ensures that radioactive waste exceeding the specific activities of 49 CFR 173.389(e) that are transported from the site are absent of free standing water.

(g) Add new Section 12.1 "Rafiological Environmental Monitoring" as identified in replacement page s in Attachment A.

The contents of this section reflect the guidance put forth in USNRC's Effluent Standard Technical Specifications.

This section supplements the radiological effluent monitoring program by verifying that the measuremcats of radiation are not higher than expected on the basis of the ef fluent measurements and modeling of the environmental exposure pa thways.

?

5 n

LCA 50 Page 2 of 6 LICENSE CilANCE APPLICATION 50 (h) Add new Section 12.2 " Land Use Census" as identified in replace-ment pages in Attachment A.

The contents of this section re flec t guidance put forth in the USNRC's Ef fluent Technical Specifications and will identify annually the location of land uses which could affect the calculated dose to individuals from plant effluents.

(1) Add new Section 12.3 "Interlaboratory Comparison Program" as identified in replacement pages in Attachment A.

This new section deals with quality control of laboratory aralyses performed on samples collected as part of the Environmental bbnitoring Program and is in accordance with USF.RC's Ef fluent Standard Technical Specifications.

(j) As part of the Administrative Controls, add to Section 6.5.1.6, PRB Responsibilities, requirement for review of the Solid Radwaste Process Control Program and the Offsite Dose Calculation Manual.

(k) As part of the Administrative Controls, add to Section 6.5.2.7, NOB Responsibilities, requirement for review of :he Radio-logical Environmental Monitoring Program.

(1) Add new Sections C.9.1.5.2 and 6.9.1.5.1, " Annual Radiologi-cal Environmental Report" as identified in replacement pages in Attachment A.

This section describes the annual reporting requirements for the Environmental Monitoring Program, Land Use Census, and the Interlaboratory Compari-son Program and is in accordance with the USNRC's Effluent Standard Technical Specifications.

(m) Add new Sec tions 6.9.1.5.4 and 6.9.1.5.5, " Semiannual Radioactive Effluent Release Report" as identified in re placement pages in Attachment A.

This section describes the semiannual teporting requirements for radioactive effluents which are consistant witn USNRC Regulatory Guide 1.21.

Additionally, unrestricted area maximum noble gas air doses, information on unplanned releases of radio-activity to the environment and any changes made to the Offsite Dose Calculational Manual or Process Control Program shall be included in this report. This section is in accordance with the USNRC's Ef fluent Standard Tech-nical Specifications.

(n)

In Section 6.9.1.9 " Thirty Day Written Reports" add new requireme nt for unplanned releases of radioactivity and environmental sampling concentrations in excess of limita in accordance with USNRC's Effluent Standard Technical Specifications, as identified in replacement pages in Attachment A.

LCA 50 Page 3 of 6 LICENSE CHANGE APPLICATION 50 (o) Add new Section 6.13 " Process Control Program" as identi-fled in replacement pages in Attachment A.

This section describes the function of the program used to verify solidification of waste from liquid systems.

(p) Add new Section 6.14 "Offsite Dose Calculation Manual" as identified in replacement pages in Attachment A.

This section describes the function and revision process of the Offsite Dose Calculation Manual. This section is in accordance with the USNRC's Ef fluent Standard Technical Specification.

(q) Revise Figure 5.1-1 to show plant unrestricted area bounda ry.

2.

Appendix B (a) Delete Section 2.4, " Radioactive Effluents". This section has been incorporated into Appendix A in accordance with the USNRC's Effluent S tandard Technical Specifications.

(b) Delete Section 4.2, " Radiological Environmental Monitering".

This section has been incorporated into Appendix A in accordance with USNRC's Effluent Standard Technical Specifications.

(c)

In Section 5.5.1, delete the paragraphs describing the Annual Operating Report and the Radioactive Effluent Release Report.

This section has been incorporated into Appendix A in accordance with USNRC's Effluent Standard Technical Specifications.

(d) Delete Section 5.5.2 "Non-Routine Reports".

This section has b+en incorporated into Appendix A in accordance with USNRC's Effluent Standard Technical Specifications.

REASON FOR CHANGE This License Change Request is in response to the USNRC's request (via letters dated 7/11/78 and 11/15/78 B. K. Grimes to All Power Reactor Licensees) to amend the Trojan Operating License to combine all radio-logical and environmental Technical Specifications into Appendix A in accordance with 10 CFR 50, Appendix I and 40 CFR 199.

SAFETY / ENVIRONMENTAL EVALUATION This License Change Request has been reviewed and determined to not constitute an unreviewed safety question.

No new accidents are created and the probability of occurrence and consequences of accidents already considered remain unchanged. Environmental impacts remain within those identified in the Tro jan Environmental Report and Final Environmental S ta tement (FES ).

LCA 50 Page 4 of 6 LICE"SE CHANGE APPLICATION 50 SAFETY / ENVIRONMENTAL EVALUATION (Continued)

T he proposed changes in this License Change Request reflect the USNRC's requirement to impleme nt 10 CFR 20,10 CFR 50 (including Appendix I) and 40 CFR 190 by replacing the current effluent and environmental monitoring Technical Specifications in Appendix B of FOL NPF-1 with the USNRC's Ef fluent Standard Technical Specifications in Appendix A.

The current effluent and environmental Technical Specifications in Appendix B have received a safety / environmental evaluation and the Ef fluent Standard Technical Specifications are obviously acceptable to the NRC.

The following areas which are not equivalent to either of the above pre-viously approved Technical Specifications are also considered to not involve an unreviewed safety question as discussed below:

1.

Solidification. This specification represents current Trojan radwaste solidification practice and procedures whereby the absence of free standing water in solidified radwaste is assured. Absence of free standing water will assure safety in transportation of the solidified waste to disposal sites. This change to the Effluent Standard Technical Specifications does not involve an unreviewed safety question in that it reflects current approved procedures and sound engineering practices.

2.

Deletion of Time Limits on Instrumentation Action State-ments. The time requirements were deleted to allow suf fi-cient time for detailed permanent repairs instead of a temporary approach to get the instrument back on line be fo re planc operations are af fected. This does not constitute an unreviewed safety / environmental question because the Action Statemer.ts contain a high level of surveillance during periods of instrument inoperability.

In addition, the grcatly increased surveillance require-ments constitute sufficient additional burden to precipi-tate maximum instrumentation operation.

3.

Alteration of Lower Limit of Detection (LLD) Definition.

The NRC, realizing that under certain circumstances it is no t possible to measure radionuclides in concentrations near the LLD, proposed an alternate method where the LLD may be increased inversely proportional to the gamma yield.

The method proposed here would f acilitate u's of the NRC concept of increasing the LLD to a maximum 10 percent of the 10 CFR 20 Maximum Permissible Concentrations (HPC).

This does not constitute an unreviewed safety / environmental question because the maximum limit, 10 percent of t'e MPC, n

will still be used.

4.

Annual Dose Limiting Conditions of Operation (LCO). The annual dose LCO's in the NRC's Effluent Standard Technical Specifications were deleted because (a) they are design objectives which are intended for use in system design and (b) 10 CFR 50, Appendix I, specifies only quarterly LCO's and not annual values.

UCA 50 Page 5 of 6 LICENSE CllANGE APPLICATION 50 SAFETY / ENVIRONMENTAL EVALUATION (Continued)

Compliance with these design objectives have been demon-strated in the Trojan Final Safer y Analysis Report and thus deletion of the annual dose LCO's does not constitute an unreviewed safety / environmental question.

5.

Radwaste System Operability Requirements.

Sections in the USNRC's Ef fluent S tandard Technical Specifications which require radwaste treatment systems to be " operable" were changed to the exact wording in 10 CFR 50.36a, Technical Specifications on Effluents from Nuclear Power Reactors which states that radwaste treatment systems be " maintained and used".

This does not constitute an unreviewed safety / environmental question because the wording and intent is identical to both 10 CFR 50.36a and to current Appendix B Trojan Technical Specifications.

The system design dose Itmits for requirement to treat all waste through the radwaste treatment systems have been changed from a monthly dose projection period to a quarterly dose allotment period; however, surveillance to determine whether the quarterly limit has been exceeded will be performed at least once per 31 days. Additionally, the limits are changed to correspond to one fourth of annual design dose objectives, thereby implementing 10 CFR 50, Appendix I, Section II and PGE's 1972 Agreement with Intervenors. The dose limits are on a prorated basis; i.e.,

treatment of wastes will be required if the dose contribution over a time period is greater than the proportional fractions of the quarterly dose limit allotted for that time period. These changes do not represent an unreviewed safety / environmental question because the doses are estimated once per 31 days in accordance with USNRC's Effluent Standard Technical Specifications; the system design operation dose limits for the radwaste treatment LCO represent the annual design objectives of 10 CFR 50, Appendix 1,Section II; and the use of a prorated dose limit will assure that the annual design objectives are not significantly exceeded even during anticipated operational occu r rence s.

6.

Explosive Gas Mixture. The addition of this specifica-tion and associated additional monitoring equipment dces not constitute an unreviewed safety / environmental question be cause they provide even greater assurance than current Trojan Technical Specifications that explosive mixtures of oxygen and hydrogen will not be present in the waste gas system, e

7.

Deletion of Waste Gas Storage Tank Activity Limit. The deletion of this specification from the NRC's Standard Efflue"t Technical Specifications does not constitute an unrevi wed safety / environmental question because it is

LCA 50 Page 6 of 6 LICENSE CllANCE APPLICATION 50 SAFETY / ENVIRONMENTAL EVALUATION (Concluded) shown in the Offsite Dose Calculation Manual using NRC calculational methods in NUREG 0133 that it is physically impossible to put enough gaseous activity in one storage tank to result in an offsite dose of 0.5 rem based on the reactor coolant specific activity Specification 3.4.8(b) and the corresponding total inventory of noble gases in the reactor coolant system.

8.

Environmental Sampling for Surface Water. The sampling and analyses of the drinking water location (City of Rainier intake, 4.5 miles downstream of Trojan) will be analyzed as both surface water and drinking water. This does not represent an unreviewed environmental question because the large distar.cc to the drinking water sample location insures complete mixing and thus a representative sample of both drinking and surface water.

SCllEDULE CONSIDERATIONS To meet Federal regulatory requirements, this License Change Applica-tion should be approved prior to December 1,1979.

BASIS FOR DETERMINATION OF AMENDMENT CLASS NRC letter of July 11, 1978 identifies this amendment request as Class III, requiring a fee of $4000 in accordance with 10 CFR 170.22. This License Change Application will result in an amendment that involves "a single environmental, safety, or other issue", and has the " acceptability for the issue clearly identified by an NRC position".

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LCA 50 Page 6 of 6 LICENSE CHANGE APPLICATION 50 SAFETY /ENVIRONMEKrAL EVALUATION (Concluded) shown in the Offsite Dose Calculation Manual using NRC calculational methods in NUREG 0133 that it is physically impossible to put enough gaseous activity in one storage tank to result in an offsite dose of 0.5 rem based on the reactor coolant specific activity Specification 3.4.8(b) and the corresponding total inventory of noble gases in the reactor coolant system.

8.

Environmental Sampling for Surface Water. The sampling and analyses of the drinking water location (City of Rainier intake, 4.5 miles downstream of Trojan) will be analyzed as both surface water and drinking water. This does not represent an unreviewed environmental question because the large distance to the drinking water sample location insures complete mixing and thus a representative sample of both drinking and surface water.

SCREDULE CONSIDERATIONS To meet Federal regulatory requirements, this License Change Applica-tion should be approved prior to December 1, 1979.

BASIS FOR DETERMINATION OF AMENDMENT CLASS NRC letter of July 11, 1978 identifies this amendment request as Class III, requiring a fee of $4000 in accordance with 10 CFR 170.22.

This License Change Application will result in an amendment that involves "a single environmental, safety, or other issue", and has the " acceptability for the issue clearly identified by an NRC position".

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LCA 50 Attachment A Page 1 of 78 INDEX DEFINITIONS SECTION Page 1.0 DEFINITIONS De f i n e d Te rm s.......................

1-1 T h e rma l P owe r.......................

1-1 Rated Thermal Power....................

1-1 Operational Mode......................

1-1 Action...

1-1 Operable - Operability.

1-1 Reportable Occurrence...................

1-2 Contai nment Integ ri ty...................

1-2 Channel Calibration....................

1-2 Channel Check.......................

1-2 Channel Functional Test......

1-3 C o re Al te ra ti o n......................

1-3 Shu t down Ma rgi n......................

1-3 Identi fied Leakage.....................

1-3 Unidentified Leakage.

1-3 Pressure Bounda ry Leakage.................

1-4 Controlled Leakage 1-4 Quadrant Power Til t Ratio.................

1-4 Dose Equivalent I-131...................

1-4 Staggered Test Basis 1-4 Frequency Notation 1-4 Reactor Trip System Response Time.............

1-5 Engineered Safety Feature Response Time..........

1-5 Axial Flux Difference...................

1-5 P hy s i c s T e s t s.......................

1-5 TROJAN-UNIT 1 I

LCA 50 Attachment A Page 2 of 78 INDEX DEFINITIONS SECTION Page 1.0 DEFINITIONS E-Ave ra ge D i s i n teg ra ti on E ne rgy..............

1-5 Source Check........................

1-Sa Process Control Program.

1-Sa Sol i di f i ca ti on.......................

1-Sa Offsite Dose Calculation Manual (0DCM).

1-Sa Gaseous Radwaste Treatment System.............

1-Sa Ventilation Exhaust Treatment System 1-Sa TROJAN-UNIT 1 la

LCA 50 Attachment A Page 3(' 78 INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCL REQUIREMENTS SECTION Page 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 Axi al Fl ux Di f fe rence................. 3/4 2-1 3/4.2.2 Heat Flux Hot Channel Factor............. 3/4 2-5 3/4.2.3 Nuclear Enthalpy Hot Channel Factor.......... 3/4 2-8 3/4.2.4 Quadrant Power Til t Ratio............... 3/4 2-lu 3/4.2.5 DNB Parameters...

3/4 2-12 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.......... 3/4 3-1 3/4.3.2 ENGINEERED SAFETY FEAiURE ACTUATION SYSTEM INSTRUMENTATION.

3/4 3-14 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation......... 3/4 3-33 Movable Incore Detectors............... 3/4 3-37 Seismic Instrumentation................ 3/4 3-38 Meteorological Instrumentation.

3/4 3-41 Remote Shutdown Instrumentation............ 3/4 3-44 Chlori ne Detection Systems.............. 3/4 3-47 Fire Detection Instrumentation...........

3/4 3-48 Radioactive Liquid Effluer,t Instrumentation...... 3/4 3-50 Radioactive Gaseous and Process Effluent In strumenta ti on................... 3/4 3-56 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS No rma l Ope ra ti o n................... 3/4 4-1 TROJAN-UNIT 1 IV

LCA 50 Attachment A Page 4 of 78 INDEX LlHITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION.................. 3/4 9-1 3/4.9.2 INSTRUMENTATION.................... 3/4 9-2 3/4.9.3 DECAY TIME...................... 3/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........... 3/4 9-4 3/4.9.5 COMMUNICATIONS.................... 3/4 9-5 3/4.9.6 MANIPULATOR CRANE OPERABILITY............. 3/4 9-b 3/4.9.7 CRANE TRAVEL - FUEL BUILDING............. 3/4 9-7 3/4.9.8 COOLANT CIRCULATION.................. 3/4 9-6 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM....... 3/4 9-9 3/4.9.10 WATER LEVEL-REACTOR YESSEL.............. 3/4 9-10 3/4.9.11 STORAGE POOL WATER LEVEL............... 3/4 9-11 3/4.9.12 SPENT FUEL POOL EXHAUST SYSTEM......

3/4 9-12 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGIN.

3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS. 3/4 10-2 3/4.10.3 PRESSURE / TEMPERATURE LIMITATION-REACTOR CRITICALITY.. 3/4 10-3 3/4.10.4 PHYSICS TESTS..................... 3/4 10-5 3/4.10.5 NATURAL CIRCULATION TESTS............... 3/4 10-b 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS................... 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS................... 3/4 11-8 3/4.11.3 SOLID RADI0 ACTIVE WASTE................ 3/4 11-lb TROJAN-UNIT 1 VIII J

LCA 50 Attachment A P rn 5 of 78 3

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION Page 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGR AM..................

3/4 12-1 3/4.12.2 LAND USE CENSUS...................

3/4 12-9 3/4.12.3 INTERLABORATORY COMPARISON PROGR AM........... 3/4 12-10 TROJAN-UNIT 1 VIIIa

LCA 50 Attachment A Page 6 of 78 INDEX BASES SECTION Page 3/4.9.6 MANIPULATOR CRANE OPERABILITY............

B 3/4 9-2 3/4.9.7 CRANE TRAVEL - FUEL BUILDING.

B 3/4 9-2 3/4.9.8 COOLANT CIRCULATION.

B 3/4 9-2 3/4.9.9 CONTAINMENT VENTILATION ISOLATION SYSTEM......

B 3/4 9-2 3/4.9.10 and 3/4.9.11 WATER LEVEL-REACTOR VESSEL AND STORAGE POOL....................

B 3/4 9-2 3/4.9.12 SPENT FUEL P0OL EXHAUST SYSTEM...........

B 3/4 9-3 3/4.10 SPECIAL TEST EXCEPTIONS 3/4.10.1 SHUTDOWN MARGINS..................

B 3/4 10-1 3/4.10.2 GROUP HEIGHT, INSERTION AND POWER DISTRIBUTION LIMITS B 3/4 10-1 3/4.10.3 PRESSURE / TEMPERATURE LIMITATIONS-REACTOR CRITICALITY B 3/4 10-1 3/4.10.4 PHYSICS TESTS....................

B 3/4 10-1 3/4.10.5 NATURAL CIRCULATION TESTS..............

B 3/4 10-1 3/4.11 RADI0 ACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS..................

B 3/4 11-1 3/4.11.2 GASE0US EFFLUENTS B 3/4 11-2 3/4.11.3 SOLID RADIDACTIVE WASTE B 3/4 11-5 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MO N I T OR I N G PR OGR AM.................

B 3/4 12-1 3/4.12.2 LAND USE CENSUS...................

B 3/4 12-1 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM.........

B 3/4 12-1 TROJAN-UNIT 1 XIV

LCA 50 Attachment A Page 7 of 78 IhDEX ADMINISTRATIVE CONTROLS SECTION Page Consultants......................

6-9 Meeti ng F requency...................

6-9 Quorum........................

6-9 6-10 Review........................

Au d i t s........................

6-11 6-11 Au thori ty.

R ec o rd s........................

6-12 6.6 REPORTABLE OCCURRENCE ACTION 6-12 6.7 SAFETY LIMIT VIOLATION.

6-13 6.8 PROCEDURES.........................

6-13 6.9 REPORTING FEQUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES........

6-14 6.9.2 SP E C I AL RE P OR T S.....................

6-18 6.10 RECORD' RETENTION.

6-19 6.11 RADI ATION PROTECTION PROGR AM...............

6-20 6.12 HIGH RADIATION AREA....................

6-20 6.13 PROCESS CONTROL PROGRAM..................

6-21 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6-22 TROJAN-UNIT 1 XVII

LCA 50 Attachment A Page 8 of 78 1.0 DEFINITIONS (Continued)

SOURCE CHECK 1.27 A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

PROCESS CONTROL PROGRAM 1.28 A PRUCESS CONTROL PROGRAM (PCP) shall be the manual or set of operating procedures detailing the program within which SOLIDIFICATION of radioactive wastes from liquid systems is assured. Requirements of the PCP are provided in Specification 6.13.

SOLIDIFICATION 1.29 SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a solid that is free of standing water.

OFFSITE DOSE CALCULATION MANUAL (0DCM) 1.30 An 0FFSITE DOSE CALCULATION MANUAL (00CM) shall be a manual contain-ing the methodolcgy and parameters to be used in the calculation of off-site doses due tc radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints. Requirements of the ODCM are providtd in Specification 6.14.

GASE0US RADWASTE TREATMENT SYSTEM 1.31 The GASE0US RADWASTE TREATMENT SYSTEM is the system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system of fgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

VENTILATION EXHAUST TREATMENT SYSTEM 1.32 VENTILATION EXHAUST TREATMENT SYSTEMS are those systems designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation exhaust from the Fuel and Auxiliary Buildings and Containment through chircoal adsorbers and/or HEPA filters prior to the release to the environment.

Such systems are not considered to have any et 4ct on noble gas ef fluents.

Engineered Safety Feature (ESF) atmospheilc cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM ccmponents.

TROJ AN-UNIT 1 1-Sa

LCA SO Attachment A Page 9 of 78 TABLE 1.2 FREQUENCY NOTATION NOTATION FREQUENCY S

At ler.st once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

W At least once per 7 days.

M At least once per 31 days.

Q At least once per 92 days.

SA At least once per 6 months.

R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release.

N.A.

Not applicable.

TROJAN-UNIT 1 1-7

/.

LCA 50 Attachment A Ppge 10 cf 78 INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION LlHITING CONDITION FOR OPERATION 3.3.3.8 The radioactive l' quid ef fluent monitoring instrumentation channels shown in Table 3.3-11 shall be OPERABLE with their alarm / trip setpoints set to ensure that the ?,imits of Specification 3.11.1.1 are not excceded.

APPLICABILITY: As shown in Table 3.3-11.

ACTION:

a.

With a radioactive liquid ef fluent monitoring instrumen-tation channel alarm / trip sctpoint less conservative than a value which will ensure that the limits of 3.11.1.1 are met, immediately suspend the release of radioactive liquid effluents monitored by the af fected channel or declare the channel inoperable.

b.

With one or more radioactive liquid effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-11.

c.

The provisions of Specifications 3.0.3 and 3.u.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.8.1 The setpoints shall be determined in accordance with procedures as described in the GDCM and shall be recorded.

4.3.3.8.2 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION, and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3-11.

TROJAN-UNIT 1 3/4 3-60

TABLE 3.3-11 Y

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUNENTATION 8

E h

MINIMUM q

CHANNELS INSTRUMENT OPERABLE APPLICABILITY ACTION 1.

Gross Radioactivity Monitors Providing Automatic Temination of Release 23 a.

Liquid Radwaste Effluent Line (1) b.

Steam Generator Blowdown (1) 24 Effluent Line R

a y

2.

Gross Radioactivity Monitors g

Not Providing Automatic Temination of Release Component Cooling Water System (1)

At all times 25 ENG

$Eaa

~E

, P, u >-

During releases via this pathway.

TABLE 3.3-11 (Continued) ff RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION 2-MINIMUM E

CHANNELS a

INSTRUMENT OPERABLE APPLICABILITY ACTION 3.

Flow Rate Measurement Devices **

20 a.

Liquid Racwaste Effluent Line (1) 20 b.

Discharge Structure (1) c.

Steam Generator Blowdown (1) 26 Effluent Line 3d 4.

Composite Sampler a

Y' Steam Generator Blowdown (1) 24 Effluent Line

During releases via this pathwry.

- Pump curves or valve position calibrations may be utilized in lieu of the flow device; in such 2NE cases, action statement 26 is not applicable.

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LCA 30 Atrachment A Page 13 of 78 TABLE 3.3-11 (Continued)

TABLE NOTAT10h ACTION 23 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE re,uirement, ef fluent releases may continue provided that prior to initiating a release:

1.

At least two independent samples are analyzed in accordance with Specification 4.11.1.1.3, and; 2.

At least two technically qualified r Mers of the Facility Staff independently verify the release rate calculations and discharge volving; Otherwise, suspend release of radioactive effluents via this pathwa.

ACTION 24 With the number of channels UPERABLE less than required by the Minimum Channels OPERABLE requirement, ef fluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at a limit of detection of at least 10-7 uCi/ gram; 1.

At least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months when the specific activity of the secondary coolant is > 0.01 uCi/ gram DOSE EQUIV/ LENT I-131.

2.

At least once per 7 days when the specific activity of the secondary coolant is < U.01 uCi/ gram DOSE EQUIVALENT I-131.

ACTION 25 With the numbers of channels OPERABLE less than required by the Minimum Channels CPERABLE requirements, at least once per 7 days collect and analyze grab samples for gross radioactivity 10 pa or gamma) at a lower limit of detection of at least (be uCi/ml.

ACTION 26 With the number of channels O'ZRABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during actual releases.

TROJAN-UNIT 1 3/4 3-53

TABLE 4.3-11 Y

RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

E CHANNEL d:

CHANNEL SOURCE CHANNEL FUNCTIONAL

]

INSTRUMENT CHECK CHECK CALIBRATION TEST

~

1.

Gross Beta or Gamma Radioactivity Monitors Providing Alarm and Automatic Isolation a.

Liquid Radwaste Effluents Line D*

P R(3)

Q(1) b.

Steam Generator Blowdown Effluent D*

M R(3)

Q(1)

Line 2.

Gross Beta or Gamma Radioactivity w1 Monitors Providing Alarm But Not Providing Automatic Isolation w

Component Cooling System D*

M R(3)

Q(2) 3.

Composite Sampler Steam Generator Blowdown Effluent W*

N/A R

N.A.

'g,g g Line

,o =

4.

Flow Rate Monitors 4[$

l o a.

Liquid Radwaste Effluent Line D(4)

N.A.

R Q

$5 N>

b.

Steam Generator Blowdown Line DI4)

N.A.

R N.A.

c.

Discharge Structure D(4)

N.A.

R 4

LCA 50 Attachment A P.83". I.1 "I.7 0 TABLE 4.3-11 (Continued)

TABLE NOTATION

During releases via this p.thway.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and/or control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(2) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm / trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

4.

Instrument controls not set in operate mode.

(3) The initial CHANNEL CAllBRATION for radioactivity measurement instrumentation shall be performed using one or more reference standards certified by or traceable to the National Bureau of Standards or using standards that have been obtained from supplier that participate in measurement assurance activities with NBS.

For subsequent CHANNEL CAllBRATION, sources that have been related to the initial calibration should be used.

(4) CHANNEL CHECK shall consist of verifying indication of flow during perieds of release. CHANNEL CHECK shall be made at least once daily on any day on which continuous or periodic releases are made.

TROJAN-UNIT 1 3/4 3-55

LCA 50 Attachment A Page f oi 78 n

INSTRUMENTATION RADI0 ACTIVE GASE0US PROCESS AND EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.9 The radioactive gaseous process and effluent monitoring instru-mentation channels shown in Table 3.3-12 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded.

APPLICABILITY: As shown in Table 3.3-12.

ACTION:

a.

With a radioactive gaseous process or effluent monitoring instrumentation channel alarm / trip setpoint less conservative than a value which will ensure that the liaits of 3.11.2.1 are met, declare the channel inoperable.

b.

With one or more radioactive gaseous process or effluent monitoring instrumentation channels inoperable, take the ACTION shown in Table 3.3-12.

c.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 The setpoints shall be determined in accordance with procedures as described in the ODCM and shall be recorded.

4.3.3.9.2 Each radioactive gaseous process or effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, Ci ANNEL CALIBRATION, and CHAKWEL FUNCTIONAL TEST operation at the frequencies shown in Table 4.3-12.

TROJAN-UNIT 1 3/4 3-56

TABLE 3.3-12 Y

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION E

E MINIMUM E-CHANNELS INSTRUMENT OPERABLE APPLICABILITY PARAMETER ACTION 1.

Waste Gas Holdup System Explosive Gas Monitoring System

% 0xygen 29 Oxygen Monitor (2) 2.

Containment Purge Monitoring System N/A 30 a.

Iodine Sampler (1)

N/A 30 b.

Particulate Sampler (1) w c.

Effluent System Flow Rate (1)

System Flow 27 h

Measuring Device Rate Measurement d.

Sampler Flow Rate Measuring (1)

Sampler Flow 27 Device Rate Measurement 2NE 2;>

Of$

u s>

TABLE 3.3-12 (continued)

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUMENTATION 2>

?

MINIMUM E

CHANNELS p

INSTRUMENT UPERABLE APPLICABILITY PARAMETER ACTION 3.

Auxiliary Building Ventilation Monitoring System Radioactivi ty 26 a.

Noble Gas Activity Monitor (1)

Rate Measurement N/A 30 b.

Iodine Sampler (1)

N/A 30 c.

Particulate Sampler (1) t System Flow Rate 27 d.

Ef fluent System Flow Rate (1)

Y Measuring Device Measurement E

e.

Sampler Flow Rate Measuring (1)

Verify Sampler 27 Device Flow 4.

Condenser Air Ejector Monitoring System gng aw Raaioactivi ty 26

-S$

a.

Noble Gas Activi ty Monitor (1)

[j Rate Measurement mn N/A 3u g>

b.

Iodine Sampler (1)

N/A 30 c.

Particulate Sampler (1)

System Flow Rate 27 d.

Effluent System Flow Rate (1)

Measuring Device Measurement Verify Sampler 27 e.

Sampler Flow Rate Measuring (1)

Device Fl ow

LCA 50 Attachment A Page 19 of 78 TABLE 3.3-12 (Continued)

TABLE NOTATION

During releases via this pathway.

- During waste gas compressor operation.

ACTION 27 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 28 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and these samples are analyzed for gross activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 29 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, operation of the waste gas compressors may continue provided grab samples are taken and analyzed once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . With both channels inoperable, operation of the waste gas compressors may continue provided grab samples are taken and analyzed once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 30 With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via this pathway may continue provided grab samples are taken and analyzed once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

TROJAN-UNIT 1 3/4 3-59

TABLE 4.3-12 f!,

RADI0 ACTIVE GASE0US EFFLUENT MONITORING INSTRUNENTATION SURVEILLANCE REQUIREMENTS 7

CHANNEL E

CHANNEL SOURCE CHANNEL FUNCTIONAL O

INSTRUMENT CHECK CHECK CALIBRATION TEST 1.

Waste Gas Holdup System Explosive Gas Monitoring System a.

Oxygen Monitor D**

N/A Q(3)

M 2.

Containment Purge Monitoring System a.

Iodine Sampler N/A N/A N/A N/A b. Particulate Sampler N/A N/A N/A N/A Y c. System Effluent Flow D* N/A R Q E Rate Measurfng Device d. Sampler Flow Rate Measuring W* N/A N/A N/A Device ?NE ~?8 oR RE a>

TABLE 4.3-12 RADI0 ACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E CHANNEL h CHANNEL SOURCE CHANNEL FUNCTIONAL p INSTRUMENT CHECK CHECK CALIBRATION TEST 3. Auxiliary Building Ventilation Monitoring System a. Noble Gas Activity Monitor D* M R(2) Q(1) b. Iodine Sampler N/A N/A N/A N/A c. Particulate Sampler N/A N/A N/A N/A R d. System Effluent Flow Rate D* N/A R Q Measuring Device Y e. Sampler Flow Rate Measuring W* N/A N/A N/A Device 4. Condenser Air Ejector Monitoring System g>q q-> a. Noble Gas Activity Monitor D* M R(2) Q(1) 5 g -a b. Iodine Sampler N/A N/A N/A N/A gj c. Particuiate Sampier N/A N/A N/A N/A

5 #

d. System Effluent Flow Rate D* N/A R Q Measuring Device e. Sampler Flow Rate Measuring W* N/A N/A N/A Device

LCA 50 Attachment A Page 22 of 78 TABLE 4.3-12 (Continued) TABLE NOTATION

During or prior to releases via this pathway.
- During waste gas compressor operation.

(1) The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exist: 1. Instrument indicates measured levels above the alarm / trip setpoint. 2. Circuit failure. 3. Instrument indicates a dowr. scale failure. 4. Instrument controls not set in operate mode. (2) The initial CHANNEL CALIBRATION for radioactivity measurement instrumentation shall be performed using one or more reference standards certified by or traceable to the National Bureau of Standards or using standards that have been obtained from suppliers that participate in measurement assurance activities with NBS. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration should be used. (3) The CHANNEL CAllBRATION shall include the use of standard gas sampl es. TROJAN-UNIT 1 3/4 3-62

LCA 50 Attachment A Page 23 of 78 3/4.11 RADI0 ACTIVE EFFLUENTS 3.4.11.1 LIQUID EFFLUENTS CONCENTRATION LIMITING CONDITION FOR OPERATION 3.11.1.1 The concentration of radioactive material released from the site to unrestricted areas (see Figure 5.1-1) shall be limited to the concentrations specified in 10 CFR Part 20, Appenoix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble For dissolved or entrained noble gases, the concentration shall gases. be limited to 2 x 10-4 uCi/ml total activity. APPLICABILITY: At all times. ACTION: a. With the concentration of radioactive material released from the site to unrestricted areas exceeding the above limits, immediately restore concentration within the above limits and provide prompt notification to the Commission pursuant to Specification 6.9.2. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.1.1 The concentration of radioactive material in liquid effluents released from the site shall be monitored in accordance with Table 3.3-11 of Specification 3.3.3.8. 4.11.1.1.2 The radioactivity content of each batch of radioactive liquid waste to be discharged shall be determined prior to release by sampling and analysis in accordance with Table 4.11-1. The results of pre-release analyses shall be used with the calculational methods in the ODCM to assure that the concentration at the point of release is limited to the values in Specification 3.11.1.1. 4.11.1.1.3 Post-release analyses of samples from batch releases shall be performed in accordance with Table 4.11-1. The results of the post-release analyses shall be used with the calculational methods in the ODCM to assure that the average concentrations at the point of release were limited to the values in Specification 3.11.1.1. 4.11.1.1.4 The radioactivity concentration of liquids discharged f rom continuous release points shall be determined by collection and andlysis of samples in accordance wi th Table 4.11-1. The results of the analyses shall be used with the calculational methods in the ODCM to assure that the average concentrations at the point of release were limited to the values in Specificatica 3.11.1.1. TROJAN-UNIT 1 3/4 11-1

LCA 50 Attachment A pag 24 of 78 TABLE 4.11-1 RADI0 ACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Minimum Lower Limit of Liquid Release Sampling Analysis Type of Activi y Detection (LLD) Type Frequency Frequency Analysis (uCi/ml)a b A. Batch P P Principal Gamma 5 x 10_7 Waste Each Batch Each Batch Emitters 9 Release Tankse I-131 1 x 10-6 P Dissolved arid 1 x 19-5 One Batch /M M Entrained Gases P H-3 1 x 10-5 Each Batch M Gross alpha 1 x 10-7 Compositec P-32i 1 x 10-6 P 37 39, 37_99 5 x 19-8 Each Batch Q Compositec Fe-55i 1 x 10-6 B. Plant Continuous Continuousd W Principal Gamma D Releases Composited Emitters 9 5 x 10-7 1. Steam I-131 1 x 10-6 Generator Blowdownf,h M Grab sample M Dissolved and Entrained Gases 1 x 10-5 Continuousd M H-3 1 x 10-b Composited Gross alpha 1 x 10-/ P-321 1 x 10-b l 1 Continuousd Q Sr-89, Sr-90 5 x 10-8 Composited Fe-55i 1 x 10-5 TROJAN-UNIT 1 3/4 11-2

~ LCA 50 Attachment A Page 25 of 78 TABLE 4.11-1 (continued) RADICACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Mi nimum Lower Limit of Liquid Release Sampling Analysis Type of Activity Detection (LLD) Type Frequency Frequency Analysis (uCi/ml)a 2. Turbine W Principal Gamma b Building Grab Sample W Emitters 5 x 10-7 Sump

3.

Condensate Deminerali-W Principal Gamma zer Build-Grab Sample W Emitters b x 10-7 ing Sump

4.

Service W Principal Gamma Water Grab Sample W Emi tters 5 x 10-7b Sy stem *

i
Grab samples shall be taken daily and composited for weekly analysis whenever activi ty exceeds 10-6 m_Ci/ml.
- Grab samples shall be taken daily and composited for weekly analysis whenever Component Cooling Water System activity exceeds 10-5_mC1/ml.

TROJAN-UNIT 1 3/4 11-3

1,CA 50 Attachment A Page 26 of 78 TABLE 4.11-1 (Continued) TABLE NOTATION a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1. b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-stances, the LLD may be increased provided that such an increase will not result in a discharge of that radionuclide which is greater than 10 percent of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2, in the diluted stream, c. A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen which is representative of the liquids released. d. Prior to analyses, all samples taken for the composite shall be thoroughly mixed in order for the composite sample to be representa-tive of the affluent release. These samples to be obtained with the steam generator blowc' wn composite sampler, A batch release is the discharge of liquid wastes of a discrete e. volume. f. A continuous release is the discharge of liquid wastes of a nondiscrete volume; e.g., from a volume of system that has an input flow during the continuous release. g. The principal gamma emitters for which the LLD specification will apply are exclusively the following radionuclides: Mn-54, Fe-69, Co-58, Co-6U, Zn-65, Mo-99, Cs-134, and Cs-137. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identified and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semi-annual Radioactive Ef tluent Release Report. h. Sampling and analysis only required during periods of blowoown to the river.

i. Fe-55 and P-32 analyses may be deleted if the analyses obtained for 1 year after implementation of this specification demonstrate that either isotope contributes less than lu percent of the offsite dose from liquid effluents.

1RDJAN-UNIT 1 3/4 11-4

LCA 50 Attachment A Page 27 of 78 RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitmant to an individual from radioactive materials in liquid effluents released to unrestricted areas (see Figure 5.1-1) shall be limited: During any calendar quarter to < 1.5 mrem to the total body and to < 5 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days of the end of the current calendar quarter, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to prevent recurrence and to reduce releases to below the design objectives. This Special Report shall also include (1) the results of radiological analyses of the drinking water source, and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR 141, Safe Drinking Water Act. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.2.1 Dose Calculations. Doses due to liquid releases to unre-stricted areas shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once per 31 days. TRGJAN-UNIT 1 3/4 11-5

LCA 50 Attachment A Page 28 of 78 RADI0 ACTIVE EFFLUENTS LIQUID WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be maintained and the appropriate subsystem shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the dose due to liquid ef fluent releases to unrestricteo areas (see Figure 5.1-1) when averaged over a calendar quarter would exceed 0.75 mrem to the total body or 1.25 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With radioactive liquid waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days of the end of the current semiannual period, pursuant to Specification 6.9.2, a Special Report which includes the following information: 1. Identification of equipment or subsystems not OPERABLE and the reason for inoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABLE status. 3. Summary description of action (s) taken to prevent a recurrence. b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases to unrestricted areas shall be determined in accordance with the Offsite Dose Calculation Manual (0DCM) at least once per 31 days. TROJAN-UNIT 1 3/4 11-6

LCA 50 Attachment A Page 29 of 78 RADI0 ACTIVE EFFLUENTS 3/t.11.2 GASE0US EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION 3.11.2.1 The dose rate in the unrestricted areas (see Figure 5.1-1) due to radioactive materials released in gaseous effluents from the site shall be limited to the following values: a. The dose rate limit for noble gases shall be < 500 mrem /yr to the total body and < 3000 mrem /yr to the skin 7 and b. The dose rate limit for all radioiodines and for all radioactive materials in particulate form and radionuclides other than noble gases with half lives greater than 8 days shall be < 1500 mrem /yr to any organ. APPLICABILITY: At all times. ACTION: a. The dose rate (s) exceeding the above limits, immediately decrease the release rate to comply with the limit (s) given in Specification 3.11.2.1 and provide prompt notification to the Canmission pursuant to Specification 6.9.2. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.1.1 The release rate of noble gases in gaseous ef fluents shall be controlled by the offsite dose rate as established above in Specification 3.11.2.1. 4.11.2.1.2 The release rate of radioactive materials, other than noble gases, in gaseous effluents shall be determined by obtaining representa-tive samples and performing analyses in accordance with the sampling and analysis program, specified in Table 4.11-2. 4.11.2.1.3 The dose rate in unrestricted areas, due to radioactive materials other than noble gases released in gaseous effluents, shall be determined to be within the required limits by using the results of the sampling and analysis program, specified in Table 4.11-2, in performing the calculations of dose rate in unrestricted areas. TROJAN-UNIT 1 3/4 11-7

TABLE 4.11-2 RADI0 ACTIVE GASE0US WASTE SAMPLING AND ANALYSIS PROGRAM { Minimum ! Lower Limit of Sampling Analysis Type of Detection (LLD) { Gaseous Release Type Frequency Frequency Activity Analysis (uCi/ml)a z P P G A. Waste Gas Storage Each Tank Each Tank Principal Gaseous Gamma Emitters 9 1 x 10-4b Tank Grab Sample P P B. Containment Purge Each Purge Each Purge Principal Gaseous Gamma Emitters 9 1 x 104b l Grab Sample H-3d i x 19-6 l C. Mc,e M Principal Gama Emitters 9 1 x 10-4b 1. Fuel ana Auxili-Grab ary Building Sampl e H-3 1 x 10-6 R Ventilation Exhaust. C 2. Conaenser Air I:o Ejector Exhaust. 3. Containment Pressure Relief. s' R E D. All Release Types Continuousf W I-131 1 x 10-12 l gg> as listed in B Charcoal v9 8 and C above. Sample I-133 1 x 10-10 og ,E Continuousf W I~ > Particulate Principal Gamma Emitters 9 Sample (I-131, Others) 1 x 10-11 Continuousf M Gross alpha 1 x 10-11 l Composite Particulate Sample i Continuousf Q Sr-89, Sr-90 l1x10-11 l Composite Particulate ' Sample j

LCA 50 Attachment A Page 31 of 78 TABLE 4.11-2 (Continued) TABLE NOTATION a. The lower limit of detection (LLD) is defined in Table Notation a. of Table 4.12-1 of Specification 4.12.1.1. b. For certain radionuclides with low gamma yield or low energies, or for certain radionuclide mixtures, it may not be possible to measure radionuclides in concentrations near the LLD. Under these circum-stances, the LLD may be increased provided that such an increase will not result in a discharge of that radionuclide which is greater than 10 percent of the MPC value specified in 10 CFR 20, Appendix B, Table II, Column 2, in plant effluents. c. Analyzers shall also be performed following shutdown, startup, or similar operational occurrences which could alter the mixture of radionuclides. d. For the Containment Purge Exhaust tritium grab samples shall be taken at least once per 24 hours when the refueling canal is flooded. Alternatively, tritium samples shall be continuously collected and analyzed weekly. Purge can commence prior to canpletion of the tritium analysis. e. Tritium grab samples shall be taken at least once per 7 days from the ventilation exhaust from the spent fuel pool area. f. The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications 3.11.2.1, 3.11.2.2 and 3.11.2.3. g. The principal gamma enitters for which the LLD specification will apply are exclusively the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, and Cs-137 fer particulate emissions. This list does not mean that only these nuclides are to be detected and reported. Other peaks which are measurable and identifiable, together with the above nuclides, shall also be identi-fied and reported. Nuclides which are below the LLD for the analyses should not be reported as being present at the LLD level for that nuclide. When unusual circumstances result in LLD's higher than required, the reasons shall be documented in the semiannual effluent report. TRGJAN-UNIT 1 3/4 11-9

LCA 50 Attachment A Page 32 of 78 RADI0 ACTIVE EFFLUENTS DOSE, NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose in unrestricted areas (see Figure 5.1-1) due to noble gases released in gaseous effluents shall be limited to the following: During any calendar quarter to ;[ 5 mrad for gamma radiation and j! 10 mrad for beta radiation. APPLICABILITY: At all times. ACTION: a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days of the end of the current calendar quarter, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to prevent recurrence and to reduce releases to below the design objectives. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.2.1 Dose Calculations Doses due to noble gas releases to unrestricted areas shall be determined in accordance with the Offsite Dose Calculation Manual (ODCM) at least once every 31 days. TROJAN-UNIT 1 3/4 11-10

LCA 50 Attachment A Page 33 of 78 RADI0 ACTIVE EFFLUENTS DOSE, RADIOI0 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM, AND RADT0hUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to an individual from radiciodines, radioactive materials in particulate form, and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluents released to unrestricted areas (see Figure 5.1-1) shall be limited to the following: During any calendar quarter to < 7.5 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With the calculated dose from the release of radioiodines, radioactive materials in particulate form, or radionuclides other than noble gases in gaseous effluents exceeding the above limit, prepare and submit to the Commission within 30 days of the end of the current calendar quarter, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to prevent recurrence and to reduce releases to below the design objectives. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.3.1 Dose Calculations Doses due to radioiodine and particulate releases to unrestricted areas shall be determined in accordance with the ODCM at least once every 31 days. TROJAN-UNIT 1 3/4 11-11

LCA 50 Attachment A Page 34 of 78 RADI0 ACTIVE EFFLUENTS GASE0US RA[ WASTE TREATMENT LIMITING CONDITION FOR OPERATION 3.11.2.4 The gaseous radwaste treatment system shall be maintained and used to reduce radioactive materials in gaseous waste prior to their discharge when the gaseous effluent air doses due to gaseous ef fluent releases to unrestricted areas (see Figure 5.1-1) when averaged over a calendar quarter would exceed 2.5 mrad for gamma radiation and 5.0 mrad for beta radiation. The ventilation exhaust treatment system shall be maintained and tne appropriate subsystem shall be used to reduce radio-active materials in gaseous waste prior to their discharge when the doses due to radioiodines, radioactive materials in particulate form and radionuclides other than noble gases with half-lives greater than 8 days in gaseous effluent releases to unrestricted areas (see Figure 5.1-1) when averaged over a calendar quarter would exceed 1.25 mrem to any organ. APPLICABILITY: At all times. ACTION: a. With gaseous waste being discharged for more than 31 days l without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days of the l end of the current semiannual period, pursuant to Specifi-cation 6.9.2, a Special Report which includes the following information: 1. Identification of equipment of subsystems not OPERABLE and the reason far inoperability. 2. Action (s) taken to restore the inoperable equipment to OPERABLE STATUS. 3. Summary description of action (s) taken to prevent a recurrence, b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.4.1 Doses due to gaseous releases to unrestricted areas shall be determined in accordance with the ODCM at least once per 31 days. l TRGJAN-UNIT 1 3/4 11-12

ICA 50 Attachment A Page 35 of 78 RADI0ACTIVF EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.2.5 The dose or dose commitment to a real individual in the unre-stricted area is limited to twice the limits of Specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. APPLICABILITY: At all times. ACTION: a. With the calculated dose from the relea se of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifications 3.11.1.2, 3.11.2.2, 3.11.2.3, prepare and submit a Special Report to the Commission within 60 days of the end of the current calendar quarter which includes the meteorological data and doses normally provided in the Seniannual Effluent Release Report of Speci fication 6.9.1.5.4. This Special Report shall include an analysis of the radiation exposure to all real indi-viduals from all effluent pathways and direct radiation. b. The provisions of Specifications 3.0.3 and 3.0.4 are r.at applicable. SURVEILLANCE REQUIREMENTS l 4.11.2.5.1 Dose Calculations Cumulative dose contributions from liquid and gaseous effluents shall be determined in acordance with Specifica-tions 3.11.1.2, 3.11.2.2, and 3.11.2.3, and in accordance with the Offsite Dose Calculation Manual (ODCM). TROJAN-UNIT 1 3/4 11-13

LCA 50 Attachment A Page 36 of 78 ,R_A_DI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTUPE LIMITING CONDITION FOR OPERATION 3.11.2.6 The concentration of oxygen being discharged by the waste gas compressors shall be limited to < 2% by volume. APPLICABILITY: At all times. ACTION: a. With the concentration of oxygen being discharged by the waste gas compressors > 2% by volume, restore the concen-tration of oxygen to within the limit within 48 hours. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.2.6 The concentration of oxygen shal' be determined to be within the above limits by continuously monitoring the waste gases being dis-charged by the waste gas compressors with the oxygen monitors required OPERABLE by Table 3.3-12 of Specification 3.3.3.9. TROJAN-UNIT 1 3/4 11-14

1,CA 50 At tacliment A f"E"_.17_Pf 78 RADI0 ACTIVE EFFLUENTS 3/4.11.3 SOLID RADI0 ACTIVE WASTE LIMITING CONDITION FOR OPERATION 3.11.3.1 Radioactive wastes transported from the site shall meet SOLIDIFICATION requirements when the specific activity of the waste exceeds 0.002 pCi/g as defined for Radioactive Material in 40 CFR 173.389(e). APPLICABILITY: At all times. ACTION: a. With the above requirements not satisfied, suspend shipments of noncompliant containers of solid radioactive wastes from the site. b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.11.3.1.1 Representative containers of radioactive wastes transported from the site shall be tested and inspected in accordance with the Process Control Program to verify the absence of free standing water. TROJAN-UNIT 1 3/4 11-15

LCA 50 Attachment A Page 38 of 78 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.1 MONITORING PROGRAM LIMITING CONDITION FOR OPERATION 3.12.1 A radiological environmental monitoring program as specified in Table 3.12-1 shall be conducted in accordance with written procedures. APPLICABILITY: At all times. ACTION: a. With the radiological environmental monitoring program not being conducted as specified in Table 3.12-1 and the ODCM, prepare and submit to the Commission, in the Annual Radio-logical Environmental Report, a description of the reasons for not conducting the program as required and the plans for preventing a recurrence. With milk or fresh leafy vegetable samples unavailable from any of the sample locations required by the ODCM, identify in the Annual Radiological Environmental Report the cause of the unavailability of samples and the locations for obtaining replacement samples. The locations from which samples were unavailable may then be deleted from the ODCM provided the locations from which the replacement samples were obtained are aded to the environmental monitoring program as replacement locations, if available. (Deviations are permitted from the required sampling schedule if specimens are unobtainable cue to hazardous conditions, seasonal unavailability, or to malfunction of automatic sampling equipment. If the latter, every effort shall be made to complete corrective action prior to the end of the next sampling period.) b. With the level of radioactivity in an environmental sam-pling medium at one or more of the locations specified in Table 3.12-1 exceeding the limits of Table 3.12-2 when averaged over any calendar quarter, prepare and submit to the Commission within 30 days from the end of the affected calendar quarter, a Thirty Day Written Report which includes an evaluation of any release conditions, environmental factors or other aspects which caused the limits of Table 3.12-2 to be exceeded. This report is not required if the measured level of radioactivity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Report. c. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable. TROJAN-UNIT 1 3/4 12-1

LCA 50 Attachment A Page 39 of 78 SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the locations shown in the ODCM and shall be analyzed pursuant to the requirements of Tables 3.12-1 and 4.12-1. TROJ AN-UNIT 1 3/4 12-2

TABLE 3.12-1 Y RADIOLOGICAL ENVIRONMENTAL MONITORING PRCGRAM e E Minimum E Number 5 Exposure Pathway of Sample Sampling and Type and Frequency [ and/or Sample Locations Collection Frequency of Analysis 1. AIRBORNE Radiof odine and 6 Continuous operation of sampler Radioiodine canister. Particulates with sample collection as required Analyze at least once by dust loading but at least once per 7 days for I-131. per 7 days. Particulate sampler. Analyze for gross beta radioactivity > 24 hours w2 following filter change. Perform gamma isotopic -7 analysis on each sample when gross beta activity is > 10 times the mean of control sample. Perform gamma isotopic analysis on composite (by location) ,,y sample at least once per j"p 92 days. Ru SI 2. DIRECT RADIATI.qN 18 At least once per 92 days. > 2 dosimeters at each a3 Tocation. Gamma dose. At least once per 92 days. g>

TABLE 3.12-1 (Continued) f RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f Minimum c Number Exposure Pathway of Sample Sampling and Type and Frequency and/or Sample Locations Collection Frequency of Analysis 3. WATERBORNE a. Ground Water 3 At least once per 92 days. Gamma isotopic and tritium { analyses of each sample, j i b.

Surface, 6

At least once per 31 days. Gross beta and gamma i Including isotopic analysis of each Drinking sample. Tritium analysis R Water of composite sample at l 1 east once per 92 days. l g I-131 analysis if gross } L beta attributable to plant exceeds 1 pCi/L. c. Sediment 6 At least once per 184 days. Gamma isotopic analysis from of each sample. m>r Shoreline @"Q i' N u i o k5 s>

TABLE 3.12-1 (Continued) RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM f Minimum E Number Exposure Pathway of Sample Sampling and Type and Frequency and/or Sample Locations Collection Frequency of Analysis 4. INGESTION a. Milk 5 At least once per 31 days. Gamma isotopic and I-131 analysis of each sample. b. Fish and In-5 Sample in season, or at least once Gamma isotopic analysis vertebrates per 184 days if not seasonal. on edible portions. Sample from each location two R species of fish and/or inverte-brates reflecting current sporting M and/or commercial interests in i l7, the vicinity. l c. Food 3 At time of harsest. One sample Gamma isotopic analysis Products of each of the following classes on edible portion. _, > r of food products: $"9

%w 1.

grains l Olo 2. nuts { c@ 3. fruits and vegetables 4 is# 1 At tinte of harvest. One sample of Gamma isotopic analysis. broad leaf vegetation.

A E TABLE 4.12-1 E E-MAXIMUM VALUES FOR THE LOWER LIMITS OF DETECTION (LLD)d 5 ~ l Airborne Particulate Analysis Water or Gas Fish Milk Food Proaucts Sediment (pCi/1) (pC1/m3) (pCi/kg, wet) (pCi/1) (pCi/kg, wet) (pCi/kg, dry ) gross beta lb 1 x 10-2 b 3g 2000 (1000 ) w S 54 n 25 130 M IG 59 e 25 260 F 58,60 o 25 130 C 65 n 25 26 0 Z 95 r-Nb 25 ,y > g Z _i?" 1311 25(1)* o1 1 60c , gg Mg 134,137 s 25 0.3 15 80 150 3g C E* 140 a-La 25 130 15 B

25 pCi/t LLD for gamma isotopic analysis; 1 pCi/t LLD if I-131 analysis mquirea.

LCA 50 Attachment A Page 44 of 78 TABLE 4.12-1 (Continued) TABLE NOTATION a The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability with 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radio-chemical separation): 4.66 sb " E V 2.22 Y expFATtT where LL3 is the i>ver limit of detection as defined above (as pCi per unit mass or volume) sb is the standard deviation of the background counting rate or cf the counting rate of a blank sample as appropriate (as counts per minute) E is the counting efficiency (as counts per transformation) V is the sample size (in units of mass or volume) 2.22 is the number of transformation per minute per picocurie Y is the fractional radiochemical yield (when applicable) A is the radioactive decay constant for the particular radionuclide at is the elapsed time between sample collection (or end of the sample collection period) and time of counting The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. In calculating the LLD for a radionuclide determined by gammi-ray spectrometry, the background shall include the typical contributions of other radionucludes normally present in the sataes (e.g., potassit,-40 in milk sampl es ). TROJAN-UNIT 1 3/4 12-7

LCA 50 Attachment A Page 45 of 78 TABLE 4.12-1 (Continued) TABLE NOTATION Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidable small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDs unachievable. In such cases, the contributing factors will be identified and described in the Annual Radiological Environmental Operating Report. b LLD for drinking water. c LLD for leafy vegetables. TROJAN-UNIT 1 3/4 12-8

LCA 50 Attachment A Page 46 of 78 RADIOLOGICAL ENYlRONMENTAL MONITORING 3/4.12.2 LAND USE CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A land use census shall be conducted and shall identify the location of the nearest milk animal, the nearest residence and the nearest garden

of greater than 500 square feet producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of five miles.

APPLICABILITY: At all times. ACTION: a. With a land use census identifying a location (s) which yields a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3.1, prepare and submit to the Commission within 30 days of the end of the current semiannual period, pursuant to Specification 6.9.2, a Special Report which identifies the new location (s). b. With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, prepare and submit to the Commission in the Semiannual Radio-logical Effluent Release Report identifying the new location. The new location shall be added to the radiological environmental monitoring program within 30 days, if possible. The sampling location having the lowest calculated dose or dose commitment (via the same exposure pathway) may be deleted from this monitoring program af ter (October 31) of the year in which this land use census was conducted. c. The provisions of Specifications 3.0.3 and 3.0.4 are not appli-cable. SURVEILLANCE REQUIREMENTS 4.12.2.1 The land use census shall be conducted at least once per 12 months between the dates of June 1 and October 1, by door-to-door survey, aerial survey, or by consulting local agriculture authorities.

Broad leaf vegetation sampling may be performed at the site boundary in the direction sector with the highest D/Q in lieu of the garden Census.

TROJAN-UNIT 1 3/4 12-9

LCA 50 Attachment A Page 47 of 78 RADIOLOGICAL ENVIRONMENTAL MONITORING 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program which has been approved by NRC. APPLICABILITY: At all times. ACTION: a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report. b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.12.3 The results of analyses performed as part of the above required Interlaboratory Comparison Program shall be included in the Annual Radio-logical Environmental Operating Report pursuant to Specification 6.9.1.6. TROJ AN-UNIT 1 3/4 12-10

1.CA 50 Attachment A P ge_48 of 78 INSTRUMENTATION BASES 3/4.3.3.6 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection system ensures that sufficient capability is available to promptly detect and initiate protective l action in the event of an accidental chlorine release. This capability is required to protect control room personnel and is consistent with the recommendations of Regulatory Guide 1.95, " Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release," February 1975. 3/4.3.3.7 FIRE DETECTION INSTRUMENTATION OPERABILITY of the fire detection instrumentation ensures that adequate warning capabiiity is avaiiable for the prompt detection of fires. This capability is required in order to detect and locate tires in their early stages. Prompt detection of fires will reduce the potential for damage to safety related equipment and is an integral element in the overall facility fire protection program. In the event that a portion of the fire detection instrumentation is inoperable, the establishment of frequent fire patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is restored to OPERABILITY. 3/4.3.3.8 RADI0 ACTIVE LIQUID EFFLUENT INSTRUMENTATION g The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance with NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Desiga Criteria 60, 63 and 64 of Appendix A to 10 CFR Part 50. 3/4.3.3.9 RADI0 ACTIVE GA5E0VS EFFLUENT INSTRUMENTATION The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases. The alarm / trip setpoints for these instruments shall be calculated in accordance witn NRC approved methods in the ODCM to ensure that the alarm / trip will occur prior to exceeding the limits of 10 CFR Part 20. This instrumentation also includes provision for monitoring (and controlling) the concentra-tions of potentially explosive gas mixtures in the waste gas holdup sy s tem. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60 and 64 of Appendix A to 10 CFR Part 50. TRDJAN-UNIT 1 B 3/4 3-3

e LCA 50 Attachment A Page 49 of 78 3/4.11 RADI0 ACTIVE EFFLUENTS BASES 3f,4.11.1 LIQUID EFFLUENTS J/4.11.1.1 CONCENTRATION This specification is provided to ensure that the concentration of radioactive materials released in liquid waste effluents from the site to unrestricted areas will be less than the concentration levels specified in 10 CFR Part 20.106 and Appendix B, Table 11. This limitation provides additional assurance that the levels of radioactive materials in bodies of water outside the site will not result in exposures within (1) the Section ll.A design objectives of Appendix I,10 CFR Part 50, to an individual and (2) the limits of 10 CFR Part 20.106(e) to the population. The concentration limit for noble gases is based upon the assumption that Xe-135 is the controlling radioisotope and its MPC in air (submersion) was converted to an equivalent concentration in water using the methods described in International Commission on Radiological Protection (ICRP) Publication 2. 3/4.11.1.2 DOSE This specification is provided to implemer.t the requirements of Section II. A and III. A and IV. A of Appendix 1,10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix 1 to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable". Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculations in the ODCM implement the requirements in Section Ill.A of Appendix 1 that conformance with the guides of Appendix 1 is to be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents will be consistent with the methodology provided in Regulatory Guides 1.109 (Rev.1) and 1.113 (Rev.1). TROJAN-UNIT 1 8 3/4 11-1

LCA 50 Attachment A Page 50 of 78 RADIOACTIVE EFFLUENTS BASES 3/4.11.1.3 LIQUID WASTE TREATMENT This specification ensures that this system wl be available for use whenever liquid effluents require treatment p' or to release to the environment. The requirements that the appropria e portions of this system be used when specified provides assurance tnat the releases of radioactive materials in liquid effluents will be kept "as low as is reasonable achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50 and design objective Section 11.D of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the liquid radwaste treatment system were specified as one quarter of the annual design objective set forth in Section 11.A of Appendix I,10 CFR Part 50, for liquid effluents (3 mrem /yr whole body; $ mrem /yr maximum organ per PLE Agreement with Intervenors dated May 1972). The dose calculational procedures specified in the ODCM include sufficient factors of conservatism to ensure that the sum of both treated and untreated releases will not resuit in doses exceeding the design objectives. 3/4.11.2 GASEOUS EFFLUENTS 3/4.11.2.1 DOSE RATE This specification is provided to ensure that the dose rate at anytime at the exclusion area boundary from gaseous ef fluents from all units on the site will be within the annual dose limits of 10 CFR Part 20 for unrestricted areas. The annual dose limits are the doses associated with the concentrations of 10 CFR Part 20.106 and Appendix B, Table II. These limits provide reasonable assurance that radioactive material discharged in gaseous et tluents will not result in the exposure of an individual in an unrestricted area, either within or outside the exclu-sion area boundary, to annual average concentrations exceeding the limits specified in Appendix 0, Table II of 10 CFR Part 20 (10 CFR Part 20.106(b)). For individuals who may at times be within the exclusion area boundary, the occupancy of the individual will be sufficiently low to compensate for TROJAN-UNIT 1 B 3/4 11-2

LCA 50 Attachment A Paje 51 of 78 RADIOACTIVE EFFLUENT 5 L ~ ~~ D X X X~ ~ ~ X T~22: T~ any increase in the atmospheric diffusion factor above that for the exclusion area boundary. The specified release rate limits restrict the corresponding gamma and beta dose rates above background to an individual at or beyond the exclusion area boundary to < (500) mrem / year to the total body or to < (3000) mrem / year to the skin. These release rate limits also restrict the corresponding thyroid dose rate above background to an infant via the cow-milk-infant pathway to < 1500 mrem / year for the nearest cow to the plant. 3/4.11.2.2 DOSE, N0BLE GASES This specification is providet to implement the requirements of Sections II.B Ill. A and IV. A of Appendix I,10 CFR Part 50. The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I assure that the releases of radioactive material in gaseous ef fluents will be kept "as low as is reasonably achievable." The Surveillance Requirements implement the requirements in Section III.A of Appendix I that conform with the guides of Appendix I to be snown by calculational procedures based on models and data such that the actual exposure of an individual through the appropriate pathways is unlikely to be substantially under-estimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous ef fluents will be consistent with the methodology provided in Regulatory Guides 1.109 (Rev.1) and 1.111 (Rev.1). The ODCM equations provided for determining the air doses at the site boundary will be based upon the historical average atmospheric conditions. 3/4.11.2.3 DOSE, RADIO 10 DINES, RADI0 ACTIVE MATERIAL IN PARTICULATE FORM _Aff[RADIONUCLIGES OTHER THAN NOBLE 6ASES This specification is provided to implement the requirements of Sections II.C, III. A and IV. A ct Aopendix I,10 CFR Part 50. TROJ AN-UNIT 1 B 3/4 11-3

LCA 50 Attachment A Pase.122Ll! RADI0 ACTIVE EFFLUENTS BASES The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appen-dix 1 to assure that the releases of radioactive materials in gaseous effluents will be kept "a_ w as is reasonably achievable." The ODCM calculational methods specified in the surveillance requirements imple-ment the requirements in Section III.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data such that the actual exposure of an individual through appropriate pathways is unlikely to be substantially underestimated. The dose calculations established in the ODCM for calculating the doses due to the actual release rates of radioiodine and particulates in gaseous effluents will be consistent with the methodology provided in Regulatory Guides 1.109 (Rev.1) and 1.111 (Rev.1). The 00CM equations provided for determining these doses will be based upon the historical average atmospheric conditions. The release rate specifications for radioiodines, ratioactive material in particulate form and radionuclides other than noble gases are dependent on the existing radionuclide pathways to man, in the unrestricted area. The pathways which are examined in the development of these calculations are:

1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onte green leafy vegetation with subsequent consumption by man, 3) deposition cnto grassy areas where milk animals and meat producing animals graze with consump-tion of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man.

_3/4.11.2.4 GASE0US WASTE TREATMENT This specification ensures that the gaseous radwaste treatment system and ventilation exhaust treatment systems will be used whenever gaseous ef fluents require treatment prior to release to the environment. The requirement that the appropriate portions of these systems be used when specified provides reasonable assurance that the releases of radio-active materials in gaseous effluents will be kept "as low as is rea-sonably achievable." This specification implements the requirements of 10 CFR Part 50.36a, General Design Criterion 60 of Appendix A to 10 CFR Part 50, and design objective Section IID of Appendix I to 10 CFR Part 50. The specified limits governing the use of appropriate portions of the systems were specified as one quarter of the annual design objectives set forth in Sections II.B and II.C of Appendix I, 10 CFR Part 50, for gaseous effluents (20 mrad /yr beta air dose; 10 mrad /yr gamma air dose; 5 mrem /yr maximum organ dose per PGE Agreement with Intervenors, dated May 1972). The dose calculational procedures of the ODCM include sufficient factors of conservatism to ensure that the sum of both treated and untreated releases will not result in doses exceeding the design objectives. TROJAN-UNIT 1 B 3/4 11-4

LCA 50 Attachment A Page 53 of 78 RADI0 ACTIVE EFFLUENTS p A_S E S__ 3/4.11.2.5 DOSE This specification is provided to meet the reporting requirements of 40 CFR 190. 3/4.11.2.6 EXPLOSIVE GAS MIXTURE This specification is provided to ensure that the concentration of potentially explosive gas mixtures contained in the waste gas treat-ment system is maintained below the flammability limits of hydrogen and oxygen. Maintaining the concentration of hydrogen and oxygen below their flammability limits provides assurance that the releases of radioactive materials will be controlled in conformance with the requirements of General Design Criterion 60 of Appendix A to 10 CFR Part 50. 3/4.11.3 SOLID RADI0 ACTIVE WASTE This specification ensures that radioactive wastes that are transported from the site shall be free of standing water. This specification applies to wastes from liquid systems (evaporator concentrates, spent resin, and filter sludges) having a specific activity greater than 0.002 pCi/g, which corresponds with the defi-nition of Radioactive Material in the Department of Transportation Regulations (49 CFR 173.389(e), and assures that wastes of significant activity will not be subject to leakage following hypothetical transport accidents. TROJAN-UNIT 1 B 3/4 11-5

LCA 50 Attachment A Page 54 of 78 3/4.12 RADIOLOGICAL ENVIRONMENTAL MONITORING BASES 3/4.12.1 MONITORING PROGRAM The radiological nonitoring program required by this specification provides measurements of radiation and of radioactive materials in those exposure pathways and for those radi nuclides which lead to the highest potential radiation exposures of ildividuals resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measur-able concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. The initially specified monitoring program will be ef fective for at least the first three years of commercial operation. Following this period, program changes may be initiated based on operational experience. The detection capabilities required by Table 4.12.-1 are state-of-the-art for routine environmental measurements in industrial labora-tories. The LLD's for drinking water meet the requirements of 40 CFR 141. 3/4.12.1 LAND USE CENSUS This specification is provided to ensure that changes in the use of unrestricted areas are identified and that modifi-cations to the monitoring program are made if required by the results of this census. This census satisfies the requirements of Section IV.B.3 of Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/ year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used,1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/ square meter. 3/4.12.3 INTERLABORATORY COMPARISON PROGRAM The requirement for participation in an Interlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of a quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid. TROJAN-UNIT 1 B 3/4 12-1

LCA 50 Attachment A Page 55 of 78 ADMINISTRATIVE CONTROLS c. Review of all proposed changes to Appendix "A" Technical Specifications. d. Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety. e. Investigation of all violations of the Technical Specifications including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence to the Executive Vice President and to the Chairman of the Nuclear Operations Board. f. Review of those REPORTABLE OCCURRENCES requiring 24 hour notification of the Commission. g. Review of facility operations to detect potential safety hazards. h. Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Nuclear Operations Board.

i. Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to Chainnan of the Nuclear Operations Board.

j. Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Chairman of the Nuclear Operations Board.

k. Review of the Offsite Dose Calculation Manual. 1. Review of the Process Control Program. AUTHORITY 6.5.1.7 The Plant Review Board shall: a. Recommend to the Plant Superintendent written approval or disapproval of items considered under 6.5.1.6(a) through (d) above. b. Render determinations in writing with regard to whether or not each item considered under 6.5.1.6(a) through (e) above constitutes an unreviewed safety question. c. Provide written notification within 24 hours to the Executive Vice President and the Nuclear Operations Board of disagreement between the PRB and the Plant Superintendent; however, the Plant Superintendent shall have responsibility for resolution of such disagreements pursuant to 6.1.1 above. TROJAN-UNIT 1 6-7

LCA 50 Attachment A Page 56 of 78 ADMINISTRATIVE CONTROLS REVIEW 6.5.2.7 The N0B shall review: a. The safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments completed under the provision of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question, b. Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section

50. 59, 10 CFR.

c. Proposed tests or experiments which involve an unreviewed safety question as defined in Section 50.59, 10 CFR. d. Proposed changes in Technical Specifications or licenses, e. Violations of applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance. f. Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear sa fe ty. g. REPORTABLE OCCURRENCES requiring 24 hour notification to the Commission. h. All recognized indications of an uninticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.

i. Reports and meetings minutes of the Plant Review Board.

J. The Radiological Environmental Monitoring Program. TROJAN-UNIT 1 6-10

I.CA 50 Attachment A Page 57 of 78 ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated: a. The facility shall be placed in at least HOT STANDBY within one hour. b. The Safety Limit violation shall be reported to the Commission, the Executive Vice President and to the NOB within 24 hours. c. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the PRB. This report shall oescribe (1) applicable circumstances preceding the viola-tion, (2) ef fects of the violation upon facility components, systems or structures, and (3) corrective action taken to pr vent recurrence. d. T te Safety Limit Violation Report shall be submitted to the ammission, the NOB and the Executive Vice President within .4 days of the violation. 6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and main-tained covering the activities referenced below: a. The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, November,1972. b. Refueling operations. c. Surveillance and test activities of safety related equipment. f d. Security Plan. e. Radiological Energency Response Plan, f. Fire Protection Program implementation. 6.8.2 Each procedure and administrative policy ef 6.8.1 above, and changes thereto, shall be reviewed by the PRB and approved by the Plant Superintendent prior to implementation and reviewed periodically as set forth in administrative procedures. TROJAN-UNIT 1 6-13

LCA 50 Attachment A Page 58 of 78 ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL REPORT 6.9.1.5.2 Routine radiological environmental reports covering the operation of the unit during the previous calendar year shall be sub-mitted prior to May 1 of each year. The initial report shall be sub-mitted prior to May 1 of the year following initial criticality. 6.9.1.5.3 The annual radiological environmental reports shall include summaries, interpretations, and statistical evaluation of the results of the radiological environmental surveillance activitie for the report period, including a comparison with preoperational studi es, operational controls (as appropriate), and previous environmental surveillance reports and an assessment of the observed impacts of the plant operation on the environment. The reports shall also include the results of the land use censuses required by Specification 3.12.2. If harmful effects or evidence of irreversible damage are detected by the monitoring, the report shall provide an analysis of the problem and a planned course of action to alleviate the problem. The annual radiological environmental reports shall include summarized and tabulated results in the format of Table 6.9-1 of all radiological environmental samples taken during the report period. In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing resul ts. The missing data shall be submitted as soon as possible in a supplementary report. The reports shall also include the following: a summary description of the radiological environmental monitoring program including sampling methods for each sample type, size and physical characteristics of each sample type, sample preparation methods, analytical methods, and measuring equipment used; a map of all sampling locations keyed to a table giving distances and directions from one reactor; the result of land use censuses required by the Specification 3.12.2; and the results of licensee participation in the Quality Assurance Program required by Specification 3.12.3. SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.5.4 Routine radioactive effluent release reports covering the operating of the unit during the previous 6 months of cperation shall be submitted within 60 days af ter January 1 and July 1 of each year. The period of the first report shall begin with the date of initial cri ticali ty. TRajAN-UNIT 1 6-1Sa

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LCA 50 Attachment A Page 60 of 78 ADMINISTRATIVE CONTROLS 6.9.1.5.5 The radioactive effluent release reports shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit as outlined in Regulatory Guide 1.21 (Rev.1), " Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plant," with data summarized on a quarterly basis following the format of Appendix B thereof. lhe radioactive effluent release reports shall include a summary of the meteorological conditions concurrent with the release of gaseous ef flu-ents during each quarter as outlined in Regulatory Guide !.21 (Rev.1), with data summarized on a quarterly basis following the format of Appendix B thereof. The racioactive effluent release reports shall include an assessment of the radiation doses from radioactive effluents to individuals due to their activities inside the unrestricted area boundary (Figure 5.1-1) during the report period. All assumptions used in making these ossess-ments (e.g., specific activity, exposure time and location) shall be included in these reports. The radioactive ef fluent release reports shall include a copy of the licensee event reports required by Specification 6.9.1.9 for each unplanned release to unrestricted areas of radioactive materials in gaseous and liquid ef fluents that occurred during the report period. The radioactive effluent release reports shall include an assessment of radiation doses from the radioactive liquid and gaseous effluents released from the unit during each calender quarter as outlined in Regulatory Guide 1.21. In addition, the unrestricted area boundary maximum noble gas gamma air and beta air doses shall be evaluated. The meteorological conditions concurrent with the releases of effluents shall be used for determining the gaseous pathway doses. The assessment of radiation doses shall be performed in accordance with the Offsite Dose Calculation Manual (ODCM). The radioactive effluent release reports shall include any changes to the PROCESS CONTROL PROGRAM or to the Offsite Dose Calculation Manual (00CF) made during the reporting period, as provided in Specifica-tions 6.13 and 6.14. TROJAN-UNIT 1 6-15c

LCA 50 Attachment A Page 61 of 78 ADMINISTRATIVE CONTROLS ddditional narrative material tC provide Complete explanation of the circumstances surrounding the event. a. Reactor protection system or engineered safety feature instru-ment settings which are found to be less conservative than those established by the technical specifications but which do not prevent the fulfillment of the functional requirements of affected systems. b. Conditions leading to operation of reactor protection systems or engineered safety feature systems in a degraded mode pennitted by a limiting condition for operation or plant shutdown required by a limiting condition for operation. c. Observed inadeauacies in the implementation of administrative or procedurai controls which threaten to cause reduction of degree of redundancy provided in reactor protection systems or engineered safety feature systems. d. Abnormal degradation of systems other than those specified in 6.9.1.8.c above designed to contain radioactive material resulting from the fiscion process. e. ^. unp 'nnea off site release of 1) more than 1 curie of radioacthe material in liquid effluents, 2).nore than 150 curies of noble gas in gaseous effluents, or 3) more than 0.05 curies of radioiodine in gaseous effluents. The report of an unplanned offsite release of radioactive material shall include the following infonnation: 1. A description of the event and equipment involved. 2. Cause(s) for the unplanned release. 3. Actions taken to prevent recurrence. 4. Consequences of the unplanned release. f. Measured levels of radioactivity in an environmental sampling medium determined to exceed the reporting level values of Table 3.2-12 when averaged over any calendar quarter sampling peri od. When more than one of the radionuclides in Table 3.2-12 are detected in the sampling medium, this report shall be sub-mitted if: ccncentration (1) concentration (2) +.. J 1. 0 limit level (1) limit level (2) TROJAN-UNIT 1 6-18

LCA 50 Attachment A Page 62 of 78 ADMINISTRATIVE CONTROLS When radionuclides other than those in Table 3.2-12 are detected and are the result of plant effluents, this report shall be submitted if the potential annual dose to an individual is equal to or greater than the calendar year limits of specifications 3.11.1.2, 3.11.2.2 and 3.11.2.3. This report is not required if the measured level of radio-activity was not the result of plant effluents; however, in such an event, the condition shall be reported and described in the Annual Radiological Environmental Operating Report. SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Director of the Office of Inspection and Enforcement Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification: Inoperable Seismic Monitoring Instrumentation, Speci-a. tication 3.3.3.3. b. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4. Inservice Inspection Program Reviews, Specifications 4.4.10.1 c. and 4.4.10.2. d. ECCS Actuation, Specifications 3.5.2 and 3.5.3. Sealed Source Leakage in excess of limits, Specifica-e. tion 4.7.7.1.3. f. Seismic Event Analysis, Specification 4.3.3.3.2. g. Fire Detection Instrumentation, Specification 3.3.3.7. h. Fire Suppression Systems, Specifications 3.7.8.1 and 3.7.8.2.

i. Radioactive Effluents, Specifications 3.11.1.1 and 3.11.2.1, in accordance with 10 CFR 20.403 and 20.405.

j. Radioactive Effluents, Specifications 3.11.1.2, 3.11.1.3, 3.11.2.2, 3.11.2.3, 3.11.2.4 and 3.11.2.5.

TROJ AN-UNIT 1 6-18a

TABLE 3.12-2 l Y REPORTING LEVELS FOR RADI0 ACTIVITY CONCENTRATIONS IN ENVT.RONMENTAL SAMPLES 8 N h Reporting Levels Z Water Airborne Particulate Fish Milk Vegetables ~ Analysis (pCi/1) or Gases (pCi/m3) (pCi/Kg, wet) (pCi/l) (pCi/Kg, wet) H-3 3 x 104 Mn-54 1 x 103 3 x 104 l Fe-59 4 x 102 1 x 104 Co-58 1 x 103 3 x 104 i f h Co-60 3 x 102 1 x 104 i Zn-65 3 x 102 2 x 104 Zr-Nb-95 4 x 102 l ,>g nn> I-131 2 0.9 3 1 x 102 mg, CE Cs-134 30 10 1 x 103 l 60 1 x 103 3 0, n Cs-137 50 20 2 x 103 l 70 2 x 103 g> Ba-La-140 2 x 102 3 x 102

LCA 50 Attachment A Page 64 of 78 ADMINISTRATIVE C0!!TROLS 6.13 PROCESS CONTROL PROGRAM (PCP) FUNCTION 6.13.1 The PCP shall be a manual containing procedures detailing the program within which solidification of radioactive wastes from liquid systems is assured, consistent with Specification 3.11.3.1 and the sur-veillance requirements of these Technical Specifications. o.13.2 Changes to the PCP shall be made by either of the following methods: A. Licensee initiated changes: 1. Shall be submitted to the Commission by inclusion in the Semiannual Radioactive Ef fluent Release Report for the period in which the change (s) was made and shall contain: a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental infor-na tion; b. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c. documentation of the fact that the change has been reviewed and found acceptable by the PRB. B. Commission initiated changes: 1. Shall be determined by the PRB to be applicable to the facility af ter consideration of facility design. 2. The licensee shall provide the Commission with written notification of their determination of applicability including any necessary revisions to reflect facility design. TRGJAN-UNIT 1 6-21

I.CA 50 Attachment A pge 65 of '/8 ADMINISTRATIVE CONTROLS 6.14 0FFSITE DOSE CALCULATION MANUAL (ODCM) FUNCTION 6.14.1 An ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid ef fluents and in the calculation of gaseous and liquid ef fluent monitor-ing instrumentation alarm / trip setpoints consistent with the appliCdDie LCO's contained in these Technical Specifications. The ODCM shall be submitted to the Cannission at the time of proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Commission prior to implementation. 6.14.2 Any changes to the ODCM shall be made by either of the following methods: A. Licensee initiated changes: 1. Shall be submitted to the Commission by inclusion in the Semiannual Ef fluent Release Report for the period in which the change (s) was made and shall contain: a. suf ficiently detailed infonnation to totally support the rationale for the change without benefit of additional or supplemer 'al infor-na tion. Information submitted should consist of a package of those pages of the ODCM to be changed with each page numbered and provided with en approval and date box, toqether with appropriate analyses or evaluations justifying the change (s); b. a determination that the change will not reduce Out accuracy or reliability of dose calculations or setpoint determinations; and c. documentation of the fact that the change has been reviewed and found acceptable by the (PRB). 2. Shall become effective upon review and acceptance by the ( PRB ). B. Commission initiated changes: 1. Shall be determined by the (PRB) to be applicable to the facility af ter consideration of facility design. TROJ AN-UNIT 1 6-22

l.t:A 50 At i;iclimerit A '%?.14L ?!. l? ADMINISTRATIVE CONTROLS 2. The licensee shall provide the Connission with written notification of their determination of applicability including any necessary revisions to reflect facility design. TROJAN-UNIT 1 6-29

LCA 50 Attachment A Page 67 of 78 TABLE OF CONTENTS (Cont'd) Page 2.2.2.4 Monitoring Requirements...... 2-10 2.2.2.5 Hasis............... 2-11 2.2.2.6 i 'ferences............. 2-11 2.2.3 Dissolved Solids............. 2-11 2.2.3.1 Appl icabi l i ty........... 2-11 2.2.3.2 Objective............. 2-11 2.2.3.3 Specification........... 2-11 2.2.3.4 Monitoring Requirements...... 2-12 2.2.3.5 Basis............... 2-12 2.2.3.6 References............ 2-12 l 2.2.4 pH.................... 2-13 2.2.4.1 Applicability. 2-13 2.2.4.2 Objective. 2-13 2.2.4.3 Specification. 2-13 2.2.4.4 Monitoring Requirement. 2-13 2.2.4.5 Basis............... 2-13 2.2.4.6 Reference. 2-14 2.3 Hydraulic...................... 2-14 l 3.0 DESIGN FEATURES AND OPERATING PRACTICES.......... 3-1 3.1 Intake System.. 3-1 3.1.1 Appl i cabil i ty. 3-1 ii

LCA 50 Attachment A Page 68 of 78 TABLE OF CONTENTS (Cont'd) Pd9R 4.1.1.1 Ap pl i cabi l i ty........... 4-1 4.1.1.2 Objective............. 4-1 4.1.1.3 Specification. 4-1 4.1.1.4 Basis............... 4-4 4.1.1.5 References............. 4-6 4.1.2 Terrestrial................. 4-t 4.1.2.1 Ap pl i ca bi l i ty........... 4-6 4.1.2.2 Objective............. 4-7 4.1.2.3 Specification........... 4-7 4.1.2.4 Basis............... 4-9 4.1.2.5 Reference. 4-9 4.1.3 Aerial................... 4-9 4.1.3.1 App l i c a bi l i ty........... 4-9 4.1.3.2 Objective. 4-9 4.1.3.4 Basis............... 4-10 4.2 Deleted l 4.3 Special Studies................... 4-21 4.3.1 Cooling Tower Plume Study. 4-21 4.3.1.1 Applicabili ty. 4-21 4.3.1.2 Objective. 4-21 4.3.1.3 Specification. 4-22 4.3.1.4 Basis............... 4-23 5.0 ADMINISTRATIVE CONTROLS.................. 5-1 S-1 Organization, Review and Audit. 5-1 5.1.1 Specification................ 5-1 iv

LCA 50 Attachment A l'a g e 69 of 78 LIST OF TABLES No. Page 2-1 Temperature Rise Across Service Water Pump....... 2-33 2-2 Liquid Effluent Monitoring Survey........... 2-33a l 3-1 Annual Chemical Usage................. 3-9 vi

LCA 50 Attachment A Page 70 of 78 The normal slight alkalinity of the river water used as circu-lating water will be neutralized by addition of sulfuric acid. Continuous monitoring of pH at a point downstream of all chemical injection and dilution systems will assure that the Technical Specification limits are not exceeded. Periodic sample analysis will ensure accuracy of the ph monitor system. Section 2.2.4.4 Monitoring Requirement implements condition (iv) of the Initial Decision dated February 4,1974. 2.2.4.6 Reference 1. Oregon State Department of Environmental Quality NPDES Waste Discharge Permit 1934-J. 2.3 HYDRAULIC See Sections 3.1, 3.2, and 4.1. 2.4 Deleted 2-14

I.CA 50 Attachment A I'ufflI.?(10 Pages 2-15 through 2-32, 2-33b, 2-33c, 2-34, 2-34a, 2-35, 2-35a and 2-36 deleted.

1.CA 50 Attachment A Page 72 af 78 sul f ate, phosphate, conductivi ty, turbidi ty and temperature will be conducted nonthly in the mixing zone and at River Miles 72 and 73. Sampling schedules will avoid tidal reversals. Samples will be collected near the Oregon shore, middle channel, and Washington shore. All samples will be subsurface except those for temperature, conductivity, and dissolved oxygen which will be taken from the surface to the bottom at 3-meter intervals. Zooplankton will also be collected at these locations by vertical hauls from near bottom with a 0.5-meter Nansen-type net. Surveys of the mixing zone will be made on a bimonthly basis, to examine fish behavior in this area. Fish collected for radiological analysis by beach seine will be identified and general condition factors determined. Sampling for eggs and young of eulachon and shad will occur during appro-priate periods in the intake structure vicinity. Replicated monthly samples of the algal community will be obtained on three river transects. Transe:t locations will be up-and downstream of the plume, and in the mixing zone. Samples will be evaluated, the predominant life forms identified, and the community as a whole described by a model to be developed during the final preoperational year. 4-2

LCA 50 Attachment A Page 73 of 78 Pages 4-11 through 4-20, 4-25 and 4-26 deleted.

ICA 50 Attachment A l'a g e 74 of 78 l 4.3 SPECIAL STUDIES 4.3.1 Cooling Tower Plume Study 4.3.1.1 Applicabili ty Applies to surveillance required to provide data for a special study of cooling tower ef fects. 4.3.1.2 Objective To semiquantitatively determine characteristics of the cooling tower plume and to assess its impact upon surface visibility both adjacent to and down, wind of the Pla'nt. Plume charac-teristics of interest are: (a) length, (b) vertical thickness, (c) density, and (d) ground impingement. s 4-21

LCA 50 Attachment A Page 75 of 78 o.4.1 Specification All records of data collected in conformance withythese Technical Specifications including strip charts, chemical analysis results, photographs, and other documentation of monitoring activities shall be retained for the life of the facility. 5.5 REPORTING REQUIREMENTS 5.5.1 Routine Reports a. Annual Operating Report A report on environmental surveillance programs for the previous year of operation shall be submitte! as part of the Annual Operating Report within 60 days af ter January 1 of each year. The period of the first report shall begin with the date of initial cri ti ca li ty. The report shall be a summary and interpretation of the results of the environmental activities for the 6 month period, including a comparison with preoperational studies, and an assessment of the observed impacts of the plant operation on the environment, a. Special Studies Results of the special studies shall be presented in a special summary topical report submitted periodically to the Director of Licensing. Status reports on special studies shall also be included in the Annual Radiological Environmental Report. IROJAN-UNIT 1 5-4

LCA 50 Attachment A Page 76 of 78 S.5.2 Changes a. A report shall be made to the NRC prior to implementation of a change in plant design, in plant operation, or in procedures described in Section 5.5 if the change would have a significant adverse effect on the environment or involves an environmental matter or question not previously reviewed and evaluated by the NRC. The report shall include a description and evaluation of the change and a supporting justification, b. Request for changes in environmental technical specifications shall be submitted to the Deputy Director of Reactor Projects, Directorate of Licensing, USNRC, for review and authorization. The request shall include an evaluation of the impact of the change and a supporting justification. TROJ AN-UNIT 1 5-4a

l.CA 50 Attachment A Lige 77 of 78 Old Pages 5-4a through 5-8 deleted.

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v t e Letter Sequence Other
TAC:07721, (Approved, Closed) TAC:7721, (Approved, Closed)
Initiation Request Acceptance... Supplement Administration Meeting, Meeting Questions 7 February 1979 26 January 1979 Answers Results Approval Other: 05000344/LER-1985-013-01, Forwards Rev 0 to 01-0300-1471, Preliminary Thermal Expansion Evaluation of Reactor Coolant Loop for Trojan Nuclear Plant, as Clarification of LER 85-013-01 in Response to 860430 Telcon, ML19267A316, ML19274E248, ML19274E250, ML20197E758, ML20198Q962, ML20198R016, ML20198R908, ML20198R985, ML20198S019, ML20198S051, ML20199B502, ML20199B510, ML20202C354, ML20204F441, ML20206F998, ML20210S227, ML20210V194, ML20211G407, ML20211G419, ML20212D368, ML20235K098, ML20235Z787
MONTHYEAR1986-05-09 [Table View]

ML19274E250

Text

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