ML20002A945

Inservice Testing Program for Pumps & Valves. Constitutes Amend 1 to PGE-1022

ML20002A945
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1980
From:	Gerlt D PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20002A942	List: ML20002A941 ML20002A945
References
PGE-1022, NUDOCS 8012090217
Download: ML20002A945 (92)

Text

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PGE-1022 Amendment 1 (December 1980)

INSERVICE TESTING PROGRAM FOR PUMPS AND VALVSS by Danny H. Gerit Generation Engineering, PGE June 1979 Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 802n90'117

T TROJAN NUCLEAR PLANT PUMP AND VALVE INSERVICE TESTING PROGRAM.

i CONTENTS Section Title Page

1.0 INTRODUCTION

1.0-1 2.0 ADMINISTRATIVE C0hTROLS.

2.0-1

.e 3.0.

INSER'VICE TESTING OF PUMPS.

3.1-1

3.1 DESCRIPTION

OF PROGRAM 3.1-1 3.1.1 Pump Summary.

3.1-1 3.1.2 Pump Data Sheet.

3.1-3 3.1.3 Reference Data and Tolerances.

3.1-3 3.1.4 Test Data.

3.1-4 3.1.5 Maintenance or Corrective Action.

3.1-5 3.1.6 Current Status.

3.1-5 3.1.7 Retention and Accessibility of Records.

3.1-6 3.2 RELIEF REQUEST BASES FOR PUMPS 3.2-1 3.2.1 Service Water System:

Pumps P108A, P108B, P108C.

3.2-1 3.2.2 Diesel Fuel Oil System:

Pumps P144A & P144B.

3.2-3 s

4.0 INSERVICE TESTING OF VALVES.

4.1-1

4.1 DESCRIPTION

OF PROGRAM 4.1-1 4.1.1 Valve Summary..

4.1-1 4.1.2 Valve Data:

Category A and B Valves.

4.1-3 4.1.3 Test Data: Category.* and B Valves.

4.1-4 4.1.4 Category C (Safety and Relief Valves).

4.1-4 4.1.5 Category C (Check. Valves).

4.1-5 4.1-6 Multiple Category Valves.

4.1-5 4.1-7 Maintenance or Corrective Action.

4.1-5 4.1-8 Current Status..................

4.1-5 4.1-9 Retention and Accessibility of Records.

4.1-6 i

4.2 RELIEF REQUEST BASES FOR VALVES.

4.2-1 4.2.1 Reactor Coolant System (RCS).

4.2-1 4.2.2 Chemical and Volume Control System (CVCS).

4.2-4 4.2.3 Residual Heat Removal System (RHRS).

4.2-8 4.2.4 Safety Injection System (SIS).

4.2-13 4.2.5 Containment Spray System.

4.2-18 4.2.6 Main Steam System.

4.2-19 j

4.2.7 Main and Auxiliary Feed System.

4.2-20

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TROJAN hTCLEAR PLANT PUMP AND VALVE INSERVICE TESTING PROGRAM CONTENTS Section Title Page 4.2.8 Component Cooling Water System (CCW).

4.2-22 4.2.9 Instrument and Service Air System.

4.2-24 4.2.10 Generic Relief Requests.............

4.2-26 APPENDIX A-1 Pump Data Sheet A-1-1 APPENDIX A-2 Reference Data and Tolerances For A-2-1 APPENDIX A-3 Test Data For A-3-1 APPENDIX A-4 Maintenance Request A-4-1 APPENDIX A-5 Current Status, ASME,Section XI, IWP.

A-5-1 APPENDIX B-1 Valve Data Sheet, ASME,Section XI, Category A and B Valves.

B-1-1 APPENDIX B-2 Test Data Sheet, ASME,Section XI, Category A and B Valves.

B-2-1 APPENDIX B-3 Valve Data Sheet, ASME,Section XI, Category C, Safety and Relief Valves..

B-3-1 APPENDIX B-4 Test Data Sheet, ASME,Section XI, Category C, Safety and Relief Valves.

B-4-1 APPENDIX B-5 Valve Data Sheet, ASME,Section XI, Category C, Check Valves.

B-5-1 APPENDIX B-6

. Test Data Sheet, ASME,Section XI, Category C, Check Valves..

B-6-1 APPENDIX B-7 Maintenance Request B-7-1 APPENDIX B-8 ASME Class 1, 2 and 3 Valve, ASME,Section XI, IWV Current Status.

B-8-1 APPENDIX C Color-Coded Drawings.

C-1-1 11 i

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D TROJAN NUCLEAR PLANT PUMP AND VALVE INSERVICE TFSTING PROGRAM

1.0 INTRODUCTION

Title 10, Chapter 1, Code of Federal Regulations - Energy, Part 50, Section 50.55a(g) sets forth the requirements for inservice inspection of nuclear power plant components.

The American Society of Mechanical Engineers (ASME) Boiler and Fressure Vessel Code,Section XI, is referenced by 10 CFR 50.55a(g) as the stan-dard to be used in developing a program for testing the operational readiness of pumps and valves.

The Trojan Nuclear Plant ASME,Section III, Class 1 and 2 components are committed to design and provision for access to enable the. performance of tests for the operational readiness of pumps and valves in accordance with the 1971 edition-and addenda through the winter of 1972.

The ef fective date for commercial operation of Trojan is May 20, 1976. The initial Pump and Valve Inservice Testing (IST)

Program for Trojan has been developed for the first 10 years of commercial operation which extends-through May 20, 1986. Tests for the operational readiness of ASME,Section III, Class-1, 2, and 3 pumps and valves which

[3 perform a function necessary for the safe shutdown of the plant and/or mitigate the consequences of an accident are required to meet the standards in the 1974-edition and addenda through the summer of 1975. Portland General Electric Company (PCE) has taken the option to use the 1977 j

edition and addenda through - the summer of 19 '3 which has been approved in 10 CFR 50.55a(b)(2). Category E valves which were deleted in this edition have been retained in the valve listings for information purposes only.

Revisions to the pump and valve IST program are required to be made at 120-month ' intervals to upgrade the program to reflect subsequently approved editions and addenda of Section XI.

Approved editions and addenda are as ' referenced in the ef fective issue of 10 CFR 50.55a(b)(2).

Successive 120 month intervals are required to meet the standards of the 1.0-1

' Amendment I (December 1980)

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t approved edition and addenda in ef fect 12 months prior to the commence-ment of the applicable 120-month period.

C Certain systems at the Trojan Nuclear Plant are safety-related or are required for safe shutdown, but were not designed to ASME,Section III, O

Class 1, 2, or 3 standards (eg, component cooling water, service water, etc).

For the Trojan Nuclear Plant. those systems designated Quality Group 4, 2, 3A and 3B in the Final Safety Analysis Report (FSAR) are included in the IST program to meet the intent of proving operational 3

readiness of components required to-function in the event of an accident.

Subsections IWP and IWV of Section XI of the ASME Code, 1977 edition and addenda through the summer of 1978, give the specific requirements for inservice testing of pumps and valves and are a part of the Trojan Nuclear Plant Pump and Valve Inservice Testing Program.

Implementing procedures for the IST program are to comply with these standards.

.Those pumps and valves for which conformance with certain provisions of j

the approved code requirements is impractical are identified'by relief request.

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l Amendment 1 1.0-2 (December 1980)

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2.0 ADMINISTRATIVE CONTROLS The Inservice Testing Program for pumps and valves is required by the Trojan Nuclear Plant Technical Specifications, Appendix A to Facility I

Operating License (FOL) NPF-1.

The program as described in this topical report will be initially reviewed and recommended for approval by the Plant Review Board (PRB) and Nuclear Operations Board (NOB). Subsequent revisions to this program, as permitted by 10 CFR 50.55a(g), wiLL also be reviewed and approved by the PRB and NOB.

i Implementation of the program described in this report will be accom-piished through plant procedures in accordance with the Nuclear Plant Quality Assurance Program for Operations.

Such procedures will identify the specific plant status, valve lineups, operating steps, and return of

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valves to a normal lineup to accomplish the required testing at the frequency established in this report. Personnel responsible for per-forming the testing required by this program will be identified in plant procedures. Compliance with the provisions of the testing require-5 ments of ASME,Section XI, Subsections IWP and IWV shall be assured by an inspector as required by Paragraph IWA-2120.

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2.0-1

~ Amendment 1 (December 1980)

's 3.0 INSERVICE TESTING OF PUMPS ASME, SECTION XI, SUBSECTION IWP The Inservice Testing Program for Pumps is described in Section 3.1.

Section 3.2 provides the requests for relief and bases for these requests.

3.1 DESCRIPTION

OF PROGRAM 3.1.1

SUMMARY

LISTING Table 3.1-1 is a complete listing of all pumas to be tested under the Trojan Nuclear Plant Pump and Valve Inservice Testing (IST) program. The listing includes:

(1) The identification number, description, and P&ID loca-tion of each pump to be tested; (2) The applicable ASME Code class designation for each pump; (3) The test parameters to be measured for each pump; and (4) The required test frequency for esch pump.

Pump design criteria for the Trojan Nuclear Plant is summarized in Section 3.2 and tabulated in Table 3.2-3 of the Final Safety Analysis Report (FSAR). Pump design code designations used in this program for determining IST requirements are summarized below:

i ASME Code Class ASME VIII Designation 1

2 3

Division 1 Trojan Quality Group 1

2 3A 3B Minimum Code ASME III l P&V P&V ASME VIII Application Class A Class II '

Class III Division 1 3.1-1 Amendment 1 (December 1980)

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Notes:

ASME III: ASME Boiler & Pressure Vessel Code, 1968, Nuclear Vessels plus addenda and code interpretations to the date of 1

I purchase award. For purchase awards on or after July 1, 1971, reference to ASME III, should be to ASME Boiler & Pressure Vessel Code, 1971, Nuclear Power Plant Components plus addenda and code interpretations to the date of purchase award.

P&V: the November 1968 Draft ASME Code for Pumps and Valves plus addenda and code interpretations to the date of purchase award.

ASME VIII means ASME Boiler & Pressure Vessel Code,Section VIII, Pressure Vessels, 1968 edition plus addenda and Code interpreta-tions to the date of purchase award. These pumps are to meet the IST requirements for ASME Code Class 3 pumps.

For pumps designed to Quality Group 3(b) operating above 150 psi and 212*F,Section VIII, Division 1 of the Boiler and Pressure Vessel Code was used as a guide in calculating the thickness of the pressure rating parts and in sizing the cover bolting. Below 150 psi and 212*F the manufacturer's standard for service was used.

((t Abbreviations for measured parameters in Table 3.1-1 are identical to those listed in Table IWP-2100-1 and are repeated below for convenience:

N = Rotative speed (rpm).

Rotative speed is not required to be measured for pumps directly coupled to motor drivers per Paragraph IWP-4400.

Pi =. Inlet pressure (psig).

?

Inlet pressure is measured prior to starting the pump and during testing.

Amendment 1 3.1-?

(December 1980)

AP = Differential pressure across the pump (psi).

j This value is determined by measuring the pump discharge pressure (Po) and subtracting pump inlet pressure (P ) in i

accordance with Paragraph IWP 4240.

Q = Pump flow rate (gpm).

V = Vibration amplitude (mils).

Tb = Bearing temperature (F').

3.1.2 PUMP DATA SHEFT 1

An example of the format to be used in summarizing the pump design and manufacturer's acceptance test data is provided in Appendix A-1.

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This summary is to be filled out with available data for each pump listed in Table 3.1-1 and is to be used as a cover sheet for the data package for that pump. The data in this summary is provided for general infonna-tion only and is not to be used as a constraint in determining the l

acceptability of test data.

i 3.1.3 REFERENCE DATA AND TOIIF12.CES

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An example of the format for documenting the required instrumentation and established reference values for each individual pump is provided in Appendix A-2.

These data sheets are to be finalized for each pump in the applicable reference procedure. The test date and test procedure used for establishing reference values are to be indicated. The instru-ments used for determination of reference values are to be listed and instrument location is to be specified in implementing Plant procedures.

Instrumentation must be calibrated prior to taking data which is to be used for reference values.

Reference values are to be determined from the results of testing during the initial inservice test for each pump, and are to be taken from 3.1-3 Amendment 1 (December 1980)

procedures which are readily reproducible for future testing. Once a set of reference values is established, the values are to remain fixed for comparison with future test data, except as provided in Paragraphs IWP-3111 and IWP-3112.

- Paragraph IWP-3111 requires that af ter a pump has been replaced or repaired in a manner that affects the established reference values, the old reference ~ values are to be reconfirmed or a new set of reference values are to be established within 96 hr of returning the pump to se rvice. Test requirements resulting from repair or replacement of a pump are to be controlled in accordance with Trojan Nuclear Plant administrative orders and maintenance procedures. The reason for changing a set of refer-ence values must be recorded. Tolerance ranges show allowable variation from the reference values for subsequent test data. These ranges are to be established according to the alert ranges listed in Table IWP-3100-2, the acceptance criteria set forth in the Trojan Nuclear Plant Standard

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Technical Specifications, and limitations imposed by the Trojan FSAR.

In any case, the most limiting tolerances are to be used.

The operator performing the test shall record the data and sign to signify the data war taken in accordance with the referenced procedure. The-shift Super-visor reviews and analyzes the data for acceptability and signs the sheet I

i to indicate his approval of the reference values.

Review of the data must be completed within 96 hr from the time of completion of the test.

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3.1.4 TEST DATA An example of a test data sheet to be. filled out for subsequent tests is provided in Appendix A-3.

The same procedure used in establishing reference values should be used in conducting future tests. Deviations or revisions to the procedure shall be provided with an evaluation of the

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potential iroact on test data.

Paragraph IWP-3112 defines the criteria for establishing new reference values and is applicable to changes in test procedures. Administrative control of deviations or revisions to procedures should comply with the Trojan Nuclear Plant administrative orders.

Amendment 1 3.1-4 (December 1980)

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Instrumentation should be identical or equivalent to that used for es-tablishment of reference values.

Instrument location is to be specified in implementing plant procedures. Calibration for subsequent testing can be accomplished under the standard calibration program in effect (recalibration is not required). Ilowever, instrument calibration should be considered prior' to taking other corrective action for test data outside the tolerance range.

The operator performing the test analyzes the test data for acceptibility and signs to indicate the recording of measured parameters in accordance with the reference procedure. Test data outside the established tolerance range is to be reported in accordance with the Trojan Nuclear Plant procedure for anomalous indication during periodic surveillance. The Shif t Supervisor reviews the data and signs to indicate his concurrence with the test results. Final review is to be completed within 96 hr of j

completion of the test.

3.1.5 MAINTENANCE OR CORRECTIVE ACTION An example of the format to be used for documenting maintenance or cor-rective action on a pump is provided in Appendix A-4.

Following comple-tion of the maintenance and/or corrective action, verification and review signatures are to be completed and a copy of Appendix A-4 is to be re-tained with the applicable Test Data Sheet.

3.1.6 CURRENT STATUS An example of the table to be maintained to reflect the current status of the pump-testing program is provided in Appendix A-5.

Following final review of the test data, the Engineering Supervisor or his delegate

[3 is to update the current status of the pump test program by filling in the date of completion (month / day) of the tert in the appropriate column.

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3.1-5 Amendment 1 i

(Decenber 1980) i

3.1.7 RETENTION AND ACCESSIBILITY OF RECORDS Following final review, the Engineering Supervisor is to receive the C

original of all data for retention. All inservice testing records shall be retained for the service lifetime of the pump. Records shall be readily accessible for review and shall be maintained in accordance with the Trojan Nuclear Plant procedure for the control of plant records.

Amendment 1 3.1-6 (Decenber 1980)

Ol TABLE 3.1-1 Sheet 1 of 3 INSERVICE TESTING PROGRAM ASME CODE CLASS 1, 2, AND 3 PUMPS Pump ASME P&ID No.

Measured Test Relief

'ID No.

Desc ription Code Class (Coordinates)

Pa rameters[ a]

Frequency Request N, P, AP, V, T [b]

Monthly P102 A Auxiliary Feedwater ASME VIII M-213 i

b (Turbine)

Division 1 (B-7)

N, P, AP, V, T [b]

Monthly P102 B Auxiliary Feedwater ASME VIII M-213 i

b (Diesel)

Division 1 (B-7)

P108 A Service Water ASME VIII M-218 P, AP, Q, V Monthly Section 3.2.1 i

Division 1 (F-7)

O P108 B Service Water ASME VIII M-218 P, AP, Q, V Monthly Section 3.2.1 i

Division 1 (D-7)

P108 C Service Water ASME VIII M-218 P, AP, Q, V Monthly Section 3.2.1 i

Division 1 (D-7)

P, AP[b]

Monthly Section 3.2.2 P144 A Diesel Oil Transfer ASME VIII M-226 i

Division 1 (F-7)

P144 B Diesel Oil Transfer ASME VIII M-226 P, AP[b]

Monthly Section 3.2.2 i

Division 1 (D-7) a ti$'

P148 A Service Water Booster 3

M-218 P, AP, Q, V, Tb Monthly i

8$

(C-5)

B8' l$

P148 B Service Water Booster 3

M-218 P, AP, Q, V, Tb Monthly i

(C-6) 4 g e-. '

E$

P148 C Service Water Booster 3

M-218 P, AP, Q, V, Tb Monthly i

(D-5)

P148 D Service Water Booster 3

M-218 P, AP, Q, V, Tb Monthly 1

(D-6)

m.

A

-M.

TABLE 3.1-1 Sheet 2 of 3 C

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@ $* rs Pump ASME P&ID No.

Measured Test Relief

- Ei$ Cd ID No.

De sc ript ion Code Class (Coordinates)

Parameters [a]

Frequency Request-nn G"'

P202 A Residual Heat Removal 2

M-205 P, AP, Q, V, Tb Monthly i

jj (C-4)

P, AP, Q, V, Tb Monthly P202 B Residual Heat Removal 2

M-205 i

(D-4)

P203 A Safety Injection 2

M-206 P, AP, Q, V, Tb Monthly i

(B-3)

P203 B Safety Injection 2

M-206 P, AP, Q, V, Tb Monthly i

(B-3)

P204 A Containment Spray 2

M-207 P, AP, Q, V, Tb Honthly i

(C-4) i P204 B Containment Spray 2

M-207 P, AP, Q, V, Tb Monthly i

(C-4) 1 P, AP, V, T [b]

Monthly I

P205 A Centrifugal Charging 2

M-202 i

b C

(C-6) v P, AP, V, T [b]

Monthly P205 B Centrifugal Charging 2

M-202 i

b (B-6) f P210 A Component. cooling Water 3

M-215 P, AP, Q, V, Tb Monthly i

(C-2)

P210 B Component Cooling Water 3

M-215 P, AP, Q, V, Tb Monthly i

(C-2)

P210 C Component Cooling Water 3

M-215 P, AP, Q, V, Tb Monthly i

(E-2)

b[I TABLE 3.1-1 Sheet 3 of 3 Pump ASME P&ID No.

Measured Test Relief ID No.

Description Code Class (Coord inates)

Parameters [a]

Frequency Request P, AP, V, T [b]

Monthly P211 A Boric Acid Transfer 3

M-202 i

b (C-2)

P, AP, V, T [b]

Monthly P211 B Boric Acid Transfer 3

M-202 i

h

,s

f (C-1)

P, AP, V, T [b]

Monthly P218A CCW Makeup 3

M-215 1

b (11-1)

P, AP, V, T [b]

Monthly P218B CCW Makeup 3

M-215 i

b (B-3)

P220 A BIT Recirculation 3

M-206 P, AP, Q, V. Tb Monthly 1

(C-3)

P220 B BIT Recirculation 3

M-206 P, AP, Q,DV, Tb Monthly 1

(C-3) q)g

[a] Lubricant level and/or pressure are to be observed and/or verified to be within manufacturer's 8 @,,

tolerances for each individual component. The requirement for observation of lubricant level y g ;3 and/or pressure is to be incorporated into each pump test procedure.

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[b] Flow (Q) is not required to be measured for a fixed resistance system.

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3.2 RELIEF REQUEST BASES FOR PUMPS The Code of Federal Regulations, 10 CFR 50.55a(g)(5)(iii), states that, "If the licensee has det-rmined that conformance with certain code requirements is impractical for his facility the licensee shall notify the Commission and submit information to support his determinations."

By interpretation, testing of pumps which does not conform to the standard test requirements for measurement of specific par. meters or for the b

frequency of performance of tests is assumed to be a nonconformance.

This section identifies those pumps for which Trojan Nuclear Plant is in nonconformance with the standard test requirements and provides the basis for relief from testing and the provisions for alternate testing of those pumps when applicable.

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3.2.1 SERVICE WATER SYSTEM: PUMPS P108A, P108B, P108C ASME Code Class: ASME VIII, Division 1 Function: The service water pumps provide cooling and make up water for safety-related and non-safety-related equipment and systems. The pumps are also used for dilution of liquid radwaste during discharge.

Test Requirement: Measure pump inlet pressure, vibration amplitude, and bearing temperature.

Basis for Relief: " Instrumentation Not Originally Provided." Class 3 pumps at Trojan are not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).

The pumps are totally subcerged inside the Intake l

St ruc ture. Pump bearings are inaccessible and the instrumentation required for measurement of pump inlet pressure, vibration amplitude, and bearing temperature was not provided in the original system design.

3.2-1 Amendment 1 (December 1980)

7 Alternate Testing:

Inlet pressure for these pumps will be determined by measuring the. Intake Structure water level and substituting the measured value into the following formula which relates this level to the pump inlet pressure:

Pi = 0.433 (24.75 - Intake Structure level).

31 The pumps are submerged in the Intake Structure and are not accessible for attachment of transducers for displacement measurement of vibration amplitudes during pump operation. The pump motor inboard bearing will be periodically monitored for vibration b

amplitude. Motor inboard bearing vibration measure-ments provide indication of pump shaft alignment and deterioration. The pump bearing vibration amplitude will not be measured.

The pump bearing temperature will not be measured.

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Amendment 1 3.2-2 (December 1980)-

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$ $ $ g 2.0 ll L

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3.2.2 DIESEL FUEL OIL SYSTEM: PUMPS P144A & P144B ASME Code Class: ASME VIII, Division 1 Function:

The diesel oil transfer pumps provide flow of fuel oil from the diesel oil storage tanks to the fuel oil day tanks.

Test Requirement: Measure pump inlet pressure, differential pressure, vibration amplitude and bearing temperature.

Basis for Relief:

" Instrumentation Not Originally Provided." Class 3 pumps at Trojan are not required to be designed for testing for operational readiness as per 10 CFR 50.55a(g).

These pumps are located inside the diesel oil storage tanks. The pumps are inaccessible and instrumentation was not provided for measurement of inlet pressure, differential pressure, flow, vibration amplitude, or bearing temperature.

Alternate Testing:

Pump discharge pressure will be measured and the inlet pressure will be calculated from tank level and the suction head on the pump. The differential pressure will be taken as the difference between pump discharge pressure and calculated inlet pressure.

[3 The pumps are enclosed within the diesel oil storage tanks and accessability is not available for measuring pump vibration amplitude. The pump motor will be periodically monitored for vibration amplitude.

Motor vibration measurements provide indication of

[3 pump shaf t alignment and deterioration.

The pump bearing temperature will not be measured.

v 3.2-3 Amendment 1 (December 1980)

A THIS FACE INTENTIONALLY DELETED i

Amendment 1 3.2-4 (December 1980)

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4.0 INSERVICE TESTING OF VALVES i

ASME SECTION XI, SUBSECTION IWV 4

j The Inservice Testing Program for valves is described in Section 4.1.

Section 4.2 provides the requests for relief and the bases for these requests.

4.1 DESCRIPTION i

4.1.1 VALVE

SUMMARY

i Table 4.1-1 is a complete listing of all valves to be tested under j

the Trojan Nuclear Plant Pump'and Valve Inservice Testing (IST) program.

The listing includes:

(1) The identification number, description, P&ID location, and normal position of each valve to be tested ;

(2) The applicable ASME Code Class designation and Section XI I

category for each valve ;

a (3) The required tests for each valve ; and a

(4) The required test frequency for each valve.

Valve design criteria for the Trojan Nuclear Plant are summarized in i

i Section 3.2 and tabulated in Table 3.2-3 of the Final Safety Analysis Report (FSAR).. Valve design code designations used in this program for determining IST requirements are summarized below:

i ASME Code Class ANSI Designation 1

2 3

B31.1 4-l Trojan Quality Group 1

2 3A 3L

'l 4

t l

Minimum Code ANSI B16.5 P&V P&V Non-nuclear Application-MSS-SP-66 Class II Class III ANSI B31.1 4.1-1 Amendment 1 (December 1980) s I

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..,,..n-,

,., ~..,, - - -,.,, -, -,. -, -, -,..,,,

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4 Notes:

P&V: means the November 1968 Draf t ASME Code for Pumps and Valves plus addenda and code interpretations to date of purchase award.

Valves designated ANSI B31.1 are to meet the IST requirements for ASME Code Class 3 valves.

Valves chose test requirements deviate from the standard frequency requirements of Subsection IWV are referenced to their applicable relief request.

j Valves which have a limitation on their maximum stroke time in fulfilling their accident function have the maximum opening or closing time, as appropriate, annotated in the remarks column.

The following abbreviations are used in Table 4.1-1:

VALVE DESCRIPTION:

A0 = Ali Operated MO = Motor Operated NORMAL POSITION:

C = Closed 0 = Open The test frequency for valves is indicated by one of the following phrases with the attendant definition:

(1) Every 3 months implies at least once every 92 days.

Amendment 1 4.1-2 (December 1980) 1

---..,,,,v,

l (2) Cold shutdown implies when the plant is in Mode 5 & 6.

g In the case of frequent cold shutdowns, the test need not be performed if less than 92 days have elapsed since the last performance of the test.

O 4

v (3) Each refueling implies when the plant has been shutdown for a scheduled refueling outage. Leakage testing is exempted from this program under Paragraph 4.2.10.

f (4) At refuelings refers to the schedule for testing of safety

]

and relief valves which has been established to comply with Table IWV-3510-1.

4.1.2 VALVE DATA: CATEGORY A AND B VALVES An example of the Valve Data Sheet to be filled out with available data for each Category A and B valve listed in Table 4.1-1 is orovided in

-O Appendix B-1.

Preservice testing of new valves which fall under the cognizance of this program is mandatory. Valves which have been repaired

.r replai:ed must be tested prior to being returned to service. Test quirements resulting from maintenance or replacement of a valve are to l

"e c;ntrolled in accordance with the Trojan Nuclear Plant administrative

,mders and maintenance procedures. The design criteria, manufacturer's

.ceptance test data, and preoperational test data are provided for ueral information only and are not to be used as acceptance criteria j

for subsequent testing.

l A copy of all available previous test results for the valve is to be retained as a permanent record. This data and subsequent test data are to be used to show performance trends of valve parameters for determina-f tion of valve deterioration.

4

.The testing of valves is to be accomplished in accordance with the designated reference procedure. Administrative control of deviations or revisions to procedures shall comply with the Trojan Nuclear Plant adminiscrative orders.

4 4.1-3 Amendment 1 (December 1980)

, ~ - - _. _.... _, _. _ _ _. _ - _ -. - _. -

Tolerances a.re established from design specification criteria, limita-tions imposed by the Trojan Nuclear Plant Standard _ Technical Specifi-cations and ! imitations imposed by the FSAR. Containment isolation valves are not to be tested for seat leakage rate under AS!1E Section XI.

4 Seat leakage rate testing and analyses are to comply with Appendix J to l

10 CFR 50.for establishing Containment isolation valve integrity.

Paragraph 4.2.10 provides ' the relief request and justification for exemption of seat leakage rate testing from the _ requirements of ASME Section XI.

The requirements fc esting in-series check valves which provide isolation between the Reactor Coolant System and other systems with a lower design presssure are included within the scope of this program. Table 4.1-1 indentifies all valves which are to be leak tested and lists the required test frequency.

4.1.3 TEST DATA: CATEGORY A AND B VALVES An example of the format of the Test Data Sheet to be filled out for Category A and B valves tested under this program is provided in Appen-dix B-2.

These data sheets are to be finalized for each valve in the applicable reference procedure. The operator performing the test is 3

responsible for collecting and analyzing data in accordance with the referenced procedure. The Shif t Supervisor reviews the data and signs to indicate his concurrence with the test results. Valves whose test data is outside the tolerance ranges are to be evaluated for corrective action in accordance with Paragraphs IWV-3417 and IWV-3427. Test data 4

outside the established tolerance ranges is to be reported in accordance with the Trojan Nuclear Plant procedure for anomalous indication during periedic surveillance. Final review is to be completed within 96 hr of completion of the test.

4.1.4 CATEGORY C (SAFETY AND RELIEF VALVES)

An example of the Valve Data Sheet for Category C, safety and relief valves is provided-in Appendix B-3.

An example of the format for the Test Data Sheet for these valves is provided in Appendix B-4.

The guidelines for performance of tests is the same as that listed above.

Amendment 1 4.1-4 (December 1980)

The operator performing the test is responsible for collecting and analyzing data in accordance with the referenced procedure. The Main-tenance Supervisor reviews the data and signs to indicate his concur-rence with the test data. Corrective action for these valves is to be in accordance with Paragraph IWV-3510.

4.1.5 CATEGORY C (CHECK VALVES)

An example of the Valve Data Sheet for Category C, check valves is provided in Appendix B-5.

An example of the Test Data Sheet for these valves is provided in Appendix B-6.

The guidelines for performance of tests and review of data is the same as that listed for Category A and B valves. Corrective action for these valves is to be in accordance with Paragraph IWV-3520.

4.1.6 MULTIPLE CATEGORY VALVES When a valve has a multiple category classification, auch as AC, the test requirements of boch categories must be met; however, duplication of

~

testing is not required. Documentation should meet the requirements of both categories as listed above.

4.1.7 MAINTENANCE OR CORRECTIVE ACTION C

An example of the format to be used to document maintenance or corrective action performed on a valve is provided in Appendix B-7.

Following completion of maintenance and/or corrective action, verification and review signatures are to be completed and a copy of Appendix B-7 is to be retained with the applicable Test Data Sheet.

4.1.8 CURRENT STATUS An example of a table to be maintained to reflect the current status of 1

the valve testing progras is provided in Appendix B-8.

Following final review of the test data, the Engineering Supervisor or his delegate is

{}

to update the current status of the Valve Testing Program by filling 4.1-5 Amendment 1 (December 1980)

0 l

in the date of completion (month / day) of the test in the appropriate 3

column.

4.1.9 RETENTION AND ACCESSIBILITY OF hECORDS i

i 31

. Following final review the Engineering Supervisor is to receive the original of all data for retention. ' All inservice inspection records l

shall be retained for the service lifetime of the valve. Records shall be readily accessible for review and shall be controlled in accordance with the Trojan Nuclear Plant procedures for the control of plant records.

i i

1 1

4 5

E 6

t i

4 1

I t

Amendment 1 4.1-6 7

-(December 1980)

I a

L TABLE 4.1-1 Sheet 1 of 37.

INSERVICE TESTING PROCRAM i

ASME CODE CLASS 1, 2, AND 3 VALVES SYSTEM:

Reactor Cooltat ~

.P&ID NO:

M-201 ASME Sict Valve Valve

.Drwg Code AI No rm Test Frequency Relief-ID No.

Description Locn Class-Cat Pos Exercise Leakage Request ' Remarks l'

PCV-455A 3" A0 Relief H-7 1

BC C

Every 3 months NA 10 tec t

1

.PCV-456 H-7 C

& at Refuelings 10 vec s-MO-8000A 3" MO Cate H-7 1

B 0

Every 3 months NA 10 sec MO-8000B H-7 0

10 sec PSV-8010A 6" Safety H-6 1

C C

At Refuelings NA PSV-8010B H-6 C

PSV-8010C H-5 C

l' CV-8025 3/8" A0 Globe H-1 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 see CV-8026 H-2 0

10 see CV-8028 3" A0 Diaphragm o-1 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 see n

l CV-8032 3/8" A0 Globe D-4' 2

B 0

Every 3 months NA 10 sec 27 l

CV-8033 3/4" A0 Dia-H-2 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 sec j

phragm b

cIW gg 8046 3" Check C-2 2

AC C

Each Refueling Each Refueling 4.2.1.4 i

i m n.

4.2.10.1 l

Er$

8047 3/4" Check H-2 2

AC C

Each Refueling Each Refueling 4.2.1.4 f

' $S 4.2.10.1 49 1

i 1

I' r'

TABLE 4.1-1 Sheet 2 of 37 UN 88 BR gg SYS1EM:

Reactor Coolant P&ID NO:

M-201 n e,.

7 ASME Sect g

Valve Valve

.Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks v

8069A 3/4" Clobe D-4 2

E O

NA NA.

4.2.10.3 8069B D-4 C

8079 4" Check F-2 2

AC C

NA NA 4.2.10.4 Passive O

8082 1" Clobe F-3 1

E

.LO NA NA 4.2.10.3 8090A 1/8" Manual C-5 2

A C

NA Each Refueling 4.2.10.1 Pa ssive 8090B Needle C-5 C

8900A 1-1/2" Check B-5 1

C C

Cold Shutdown NA~

4.2.1.1 8900B E-5 C

8900C E-4 C

8900D B-4 C

8948A 10" Check B-5 1

AC C

Cold Shutdown Cold Shutdown 4.2.1.2 8948B E-5 C

4.2.10.2 8948C E-4 C

8948D B-4 C

O 8949A 6" Check C-6 1

AC C

Cold Shutdown Cold Shutdown 4.2.1.3 8949B D-6 C

4.2.10.2 8949C C-4 C

8949D C-4 C

i i

i i

i i

+

T..BLE 4.1-1 Sheet 3 of 37 SYSTEM:

Chemical and Volume Control P5ID NO:

H-202 ASME Sect Valve Valve Drwg Codo XI No rm Test Frequency Relief

__ ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks FO-ll2B 4" H0 Cate E-5 2

B 0

Every 3 months NA 10 sec

,s%

HO-ll2C 0

10 see MO-Il2D 8" M0 Cate C-5 2

B C

Every 3 months NA 10 sec h)

MO-Il2E C

10 sec Ho-8104 2" H0 Globe D-4 2

B C

Every 3 months NA 10 sec H0-8105 3" Mo Cate

.F-7 2

B 0

Cold Shutdown NA 4.2.2.1 10 sec c,

MO-8106 F-7 0

4.2.10.4 10 see PSV-8117 3" Safety 11 - 7 2

AC C

At Refuelings NA 4.2.2.2 4.2.10.4 PSV-8118 3/4" Safety E-6 2

C C

At Refuelings NA PSV-8119 2" Safety 11-4 2

C C

At Refuelings NA PSV-8120 3" Safety C-5 2

C C

At Refuelings NA PSV-8124 1" Safety B-5 2

C C

At Refuelings NA CV-8149A 2" A0 Globe C-8 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec CV-81493 C-7 0

10 sec

,sk

?

CV-8149C C-7 C

10 sec a R. ::

h. g

CV-8152 2" A0 Globe C-7 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 sec aE 8381 3" Check F-7 2

AC 0

NA NA 4.2.10.4 Passive

r. g S

i

b TABLE 4.1-1 Sheat 4 of 37 mN cs*a to n.

0N gg SYSTEtt:

Chemical and Volume. Control P&ID H-202 ww g

ASME Sect S

Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks 8392 3/4" Clobe C-7 2

E LO NA NA 4.2.10.3 8394 4" Cate D-5 2

E ID NA im 4.2.10.3 8435 1" Cate D-5 2

E 14 NA NA 4.2.10.3 8439 I" Cate D-5 2

E LC NA NA 4.2.10.3

~

8441 2" Cate C-3 2

E LC NA NA 4.2.10.3 0

8471A 2" Cate C-6 2

E LO NA te.

4.2.10.3 8471B B-6 ID 8481A 4" Check C-6 2

C 0

Every 3 months NA 4.2.2.3 848IB B-6 0

8482 4" Cate F-6 2

E 14 NA NA 4.2.10.3 4

8546 8" Check C-5 2

C C

Cold Shutdown NA 4.2.2.4 7

/

7 s

e e

e 3

k c

ec c

v v

v r

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i i

i f

a s

ss s

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00 0

c a

a 5

R 1

1 1 1

P P

P te t

1 1

1 4

~

5. 0

5. 0 e

f s 0

0 0

h ee S

3 i u 21 21 1

1 1

0 l q 2

ee 22 22 2

2 2

RR M

44 44 4

4 4

g g

g n

n n

i i

i e

l l

l g

e e

e

o a

u u

u N

k f

A f

A A

f A

A a

e N

e N

N e

N N

D y

e R

R R

l c L n

h h

h P

e c

c c

u a

a a

q E

E E

er F

s n

h n

s s

t w

t w

g g

s e o

n o

n n

e s d

o d

i i

T i

t m

t l

l c

u u

e e

r h

3 h

u u

A A

A e

S S

f f

N N

N x

y e

e E

d r

d R

R l

e l

e v

o t

t r

E C

A A

1 m

1 rs oo 0

00 0

C C

C 0000 0000 4

NP ELB t

A cI t C

C C

T eX a A

B A

C C

A A

A S

C lor s

t E es n

Md a 2

2 2

2 2

2 2

2 o

S ol c

ACC emu lo gn V

wc 2

33 2

2 2

2 7643 7643 ro d

DL F

CC F

F F

BBBB BBBB 1

1 na lac n

i o

m i

e e

et e

b e

k h

vp t

o t

y y

c e

C l i a

l a

t t

e k

l ar G

G C

e e

h c

d c

f f

C e

e e

H 1

0 a

a h

e s

O 0

M S

S c

N 1

D 4

!E

/

T 4

2 4

2 2

3 2

1 S

YS 1

3 eo 0

01 2

2 2

vN 0

1 1 1

1 1

l 1

1 1 1

8 8

ABCD ABCD aD 8

88 8

0 8S88 9999 VI V

V 8

6666 6333 666 O

OO O

S S

1 3331 M

MM M

P P

8 888*

3 88

]

b Cw mhmE, ~

gEyc$ ~ o 8" r

j

~

9 TABLE 4.1-1 Sheet 6 of 37 9$

8a RR SYSTEM:

Residual lleat Removal P&ID NO:

M-205 G **

l ASME Sect g

Valve Valve Drwg Code XI Norm Test Frequency Relief ID_No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks llCV-606 8" A0 Butterfly F-7 2

B 0

Every 3 months HA 40 sec

,,cl IICV-60/

D-7 0

40 sec FCV-610 2" MO Globe 11-5 2

B C

Every 3 months NA 10 sec

{}

FCV-611 C-5 C

10 sec CV-1782 3/4" Globe

!!-7 2

B C

Every 3 months NA 10 see CV-178's B-6 C

10 see MO-8700A 14" MO Cate F-3 2

B 0

Every 3 months NA 4.2.10.4 120 see MO-8700B E-3 0

120 see C

MO-8701 14" MO Gate E-2 1

B C

Cold SI atdown NA 4.2.3.1 120 see v

MD-8702 D-2 C

4.2.10.4 120 see MO-8703 12" M0 Cate B-2 2

B C

Cold Shutdown NA 4.2.3.4.

120 sec 4 2.10.4 PSV-8708 3" Safety E-3 2

C C

At Refuelings NA 4.2.10.4 PSV-8709 3/4" Safety B-3 2

C C

At Refuelings NA MO-8716A 8" M0 Cate F-7 2

B 0

Ever;y 3 months Nf 40 sec MO-8716B D-7 0

40 sec 8730A 8" Check F-4 2

C C

Every 3 months NA 4.2.3.5

,sr, 8730B D-4 C

8735 8" Gate D-8 2

E LC NA NA 4.2.10.3

P 7

s c

3 k

e ee e e

r e

ee e s

f a

s ss s o

m 0

e 0

00 7 2

7 R

4 44 1

1 te t

3 3

2. 0 6 7 30 8

3 2

4 2

4 4

1 e

f s h

ee 0

0 0

0 0

0 0

S 5

i u 1

31 1

1 3

1 1

3 31 1

3 1

0 l q 2

ee 2

2 2

22 2 2

2 2 22 RR 2

2 2

M 4

4 4

44 4 4

4 4 44 4

4 4

g i

n n

n w

i w

e o

l o

g d

e d

O a

t u

t N

k A

A A

u A

A f

A u A A A

A a

N N

N h

N N

e N h N N N

N-D y

e S

R S

I c L n

d h

d P

e l

c l

u o

a o

q C

E C

er t

F s

s g

n n

h h

n n s

n t

w w

t t

w w g

i s e o

o n

n o o n

l e s d

d o

o d d i

e T

i t

t m

m t

t l

u c

A A

A u

u u u A e f

r N

N N

h h

3 3

h h N u A

e e

S S

S S f

N R

x y

y e

E d

d r

r d d R

h l

l e

e l

l c

o o

v v

o o t

a C

C E

E C C A

E 1

m 1

rs DO fC nn oo I L I L I I CC CC 00 CC 0 CCCC C CC CC C 4

NP EL B

t A

cI t C

C T

eXa E

E E

A B

B A

B A A C A

C S

C i

l o

a E es v

Md a 2

2 2

1 2

2 2

2 1

2 2 2

2 o

S ol m

ACC e

R ta e

gn H

wc 55 55 55 22 77 77 33 4 8888 2 77 82 3 ro l

DL FD FD FD CB GB GC GD E GGCC C GC FE E au d

i se n

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R o

b b

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o et e

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t l

l vp t

t a

a G

y G

k li k

a a

G C k t

c ar e

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c C

C c

0 e

0 e

Vc t

t t

e O

O e A

f A

h s

a a

a h

0 0

H M h a

C e

C C

C C

M M

C S

M D

4 4

E "8

"8 4

4 "

/ "

/

4 T

8 8

8 8

1 1

6 3 2 3

1 S

YS AB AB AB AB 66 A8 eo 44 99 1 1 2

5 55 00 vN 00 00 1 1 1

2 88 99 l

AB AB AB AB 88 88 88 8 ABCD 8 88 88 aD 44 66 88 66 88 88 88 8 8888 8 88 8 VI 22 22 22 33 1 1 1 1 VV - -

5 77 77 77 77 OO OO Oo O 8888 V SS VV 9 88 88 88 88 MM MM MH M 8888 C PP CC 8 g

ggkg 7g.

gg Q

4 j

]jj j.

1!!I

i d

7 s

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k ec ec ec c

ce cvev cvcv r

ee ee ee e

ee eieieiei f

a ss ss ss s

ss sssssss s o

m s

s s

s e

00 00 00 0

00 2 a2 a2 a2 a 8

R 1 1 22 1 1 4

33 1 p1 p1 p1 p t

e t

4 4

3 e

f s 7

1 h

ee 0

0 0

S 6

i u 1

1 4

4 1

0 l q 2

ee 2

2 2

2 2

RR M

4 4

4 4

4 e

g O

a N

k A

A A

A A

A A

a N

N N

N N

N N

D y

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c L n

P euqer F

s s

s s

h h

h n

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t t

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i m

m m

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3 3

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S N

x y

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r r

r d

r d

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E C

E C

1 mrs 1

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CC 0

0 0

0 OOOO 4

NP LLLL E

L B

t A

cI t T

eX a B

B B

B B

B E

S C

s E es Md a 2

2 2

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n S ol o

ACC i

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wc 66 66 44 2

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DL DD BA CC B

CC F

F F

F EDDD te fa S

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B C

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0 0

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88 8

8 8

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n n

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k a

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c b

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3 2

2 2

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AB eo 34 1 1 34 5

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CD 88 ABCD 88 8

aD 88 5

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TABLE 4.1-1 Sheet 10 of 37 9lY aa a R-SYSTEM:

Safety Injection P&ID NC.

H-206 ASME Sect g

Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Lacn Class Cat Pos Exercise Leakage Request Remarks

{}* CV-8843 3/4" AO, Globe D-6 2

A C

NA NA 4.2.10.4 10 see PSV-8851 3/4" Safety B-6 2

C C

At Refuelings NA

{}

PSV-8852 3/4" Safety E-6 2

C C

At Refueling NA PSV-8853A 3/4"_ Safety B-6 2

C C

At Refuelings NA PSV-88538 B-6 C

PSV-8855A 1" Safety C-7 2

C C

At Refuelings NA PSV-8855B C-6 C

PSV-8855C C-4 C

PSV-8855D C-3 C

4 PSV-8858 3/4" Safety B-2 2

C C

At Refuelings NA CV-8870A 1" A0 Globe D-6 2

B 0

Every 3 months NA 10 see CV-8870B D-5 0

10 see CV-8871 3/4" A0 Globe E-3 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec CV-8880 1" A0 Clobe H-7 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see C

?

CV-8SS1 3/4" A0 Globe C-6 2

A C

NA NA 4.2.10.4 10 see CV-8883 1" A0 Clobe C-4 2

B 0

Every 3 months NA 10 sec CV-8888 3/4" A0 Clobe A-6 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec

~

TABLE 4.1-1 Sheet 11 of 37 SYSTEM:

Safety Injection P&ID NO:

M-206 ASME Sect Valve Valve Drwg Code XI No rm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Req:est Remarks 8905A 2" Check B-7 1

C C

Cold Shutdown Cold Shutdown 4.2.4.4 8905B A-7 C

4.2.10.2

-s O

8905C B-7 C

8905D A-7 C

8915 1" Clobe C-5 2

E LC NA NA 4.2.10.3 8919A 3/4" Check B-4 2

C C

Every 3 months NA 8919B A-4 8920A 3/4" Clohe B-4 2

E LO NA NA 4.2.10.3 8920B A-4 LO

[7 8921A 4" Ga'.e B-4 2

E LO NA NA 4.2.10.3 8921B A-4 ID 8922A 4" Check B-4 2

C C

Every 3 months NA 4.2.4.9 8922B B-4 HO-892 3A 6" Ho Cate B-2 2

B 0

Even 3 months NA 30 see MO-8923B B-2 0

30 see MO-8924 6" H0 Cate C-2 2

B O

Every 3 months NA 30 sec 8925 1" Clobe C-3 2

AE LC NA NA 4.2.10.3 4.2.10.4 8926 8" Check B-2 2

C C

Every 3 months NA 4.2.4.9 b

8956A 10" Check F-7 1

C C

Cold Shutdown NA 4.2.4.5 S S.

8956B F-6

!c @

8956C F-4 NN 8956D F-3

{ "'

CV-8964 3/4" A0 Clobe E-2 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec 03 8968 1" Check H-7 2

AC C

Each Refueling Each Refueling 4.2.4.6 4.2.10.1 s

TABLE 4.1-1 Sheet 12 of 37 EN aa 08' SYSTEM:

Containment Spary P&ID NO:

M-207 ASME Sect 8

Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks 2-CCB-CK 2" Check

.E-4 2

C C

Every 3 months NA 2-CCB-CK D-4 C

3 10-IICB-CK 10" Check G-7 2

C C

5 years NA 4.2.5.1 10-IICB-CK C-7 C

14-IICB-CK 14" Check F-3 2

C C

Every 3 months NA 4.2.5.2 14-l!CB-CK C-2 C

M0-2050A 14" MO Cate

.G-3

'2 E

LO NA NA 4.2.10.3 MO-2050B C-2 o

MO-2052A 14" MO Cate F-3 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec MO-2052B C-2 C

10 see MO-2053A 10" M0 Cate G-7 2

B C

Every 3 months NA 4.2.10.4 10 sec MO-20538 C-7 C

10 sec MO-2056A 2" MO Globe D-4 2

B C

Every 3 months NA 10 see MO-2056B D-4 C

10 sec MO-2069A 18" M0 Cate D-2 2

A 0

Every 3 months Each Refueling 4.2.10.1 17 sec MO-2069B 0

t CS-001 14" Gate G-3 2

E LC NA NA 4.2.10.3 CS-002

-C-3 Lo CS-003 2" Globe D-4 2

E ID NA NA 4.2.10.3 CS-004 D-4 LO 1

i i

m h

i TABLE 4.1-1 Sheet 13 of 37 SYSTEM:

Containment Spray P&lD NO:

M-207 ASME Sect Valve Valve D wg Code X1 Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks CS-005 2" clobe D-4 2

E LC NA NA 4.2.10.3

'CS-006 E-4 LC CS-007 3" Globe F-5 2

E LO NA NA 4.2.10.3 CS-008 C-5 LO CS-011 1" Clobe F-6 2

E LC NA NA 4.2.10.3 CS-012 C-6 LC n

I CS-013 3" Gate C-6 2

E LC NA NA 4.2.10.3 CS-014 G-6 LC CS-015 3" Glob-H-2 2

E LC NA NA 4.2.10.3 CS-016 10" Cate C-6 2

E LO NA NA 4.2.10.3 9k CS-017 10" Cate C-6 2

E LO NA NA 4.2.10.3 Of CS-020 1" Globe D-5 2

E LC NA NA 4.2.10.3

. $E e

i

1_.

~., _

4 TABLE 4.1-1 Sheet 14 of 37 U[I aB (II SYSTEM:

Main Steam P&ID NO:

H-208 n u, G"

ASME Sect 8

Valve Valve Drug Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks MS-001 1-1/2" Globe 11 - 7 2

E LC NA NA 4.2.10.3 MS-002 F-7 LC MS-003 D-7 LC MS-004 C-7 LC MS-021 6" Cate 11 - 3 2

E LO NA NA 4.2.10.3 MS-022 F-3 LO i

MS-023 D-3 Lo MS-024 C-3 LO b

MS-026 3" Clobe F-2 2

E LO NA NA 4.2.10.3 MS-027 C-2 LO MS-143 11 - 2 LO MS-144 D-2 LO r

4 k

SG-Of,4 3/4" Globe G-7 2

E LC NA NA 4.2.10.3 SG-066 E-7 LC SG-068 C-7 LC j

SG-070 B-7 LC i

CV-2210 6" A0 Relief H-3 2

BC C

Every 3 months NA

)

j PSV-2211 6" Safety 11 - 3 2

C C

At Refuelings NA PSV-2212 11 - 3 C

PSV-2213 11 - 3 C

}

PSV-2214 11 - 2 C

PSV-2215 11 - 2 C

1

TABLE 4.1-1 Sheet.15 of 37 SYSTEM:

Main Steam P&ID NO:

M-208 i

ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief

{.

ID No.

Description Locn Class dat Pos Cxerclac Leakage Request Remarka O

.CV-2216 28" Piston Op H-2.

2 BC 0

Cold Shutdown NA 4.2.6.1 5 sec Check MO-2218 3" Mo Cate C-2 2

B C

Every 3 months NA 15 sec

{

MO-2228

.E-3 C

15 see CV-2230 6" A0 Relief F-3 2

BC C

Every 3 months NA PSV-2231 6" Safety F-3 2

C.

C At Refuelings NA PSV-2232 F-3 C

PSV-2233 F-3 C

PSV-2234 F-2 C

PSV-2235 F-2 C

CV-2236 28" Pis;on Op F-2 2

BC 0

Cold Shutdown NA 4.2.6.1 5 see Check b

MO-2238 3" M0 Cate D-3 2

B C

Every 3 months NA 15 sec

)

MO-2248 C-2 I;

15 sec

.i CV-2250 6" AO Relief D-3 2

BC C

Every 3 months NA gg PSV-2251 6" Safety D-3 2

C C

At Refuelings NA gg PSV-2252 D-3 C

m PSV-2253 D-3 C

Eg m

PSV-2254 D-2 C

l i

'$ N PSV-2255 D-2 C.

G~

8 t

i

~

i, t

g TABLE 4.1-1 Sheet 16 of 37 8&

wo

$ f, SYSTEM:

Main Steam P&ID NO:

H-208 se ASME Sect 8-Valve Valve Drwg Code XI Norm Test Frequency Relief i

ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks O

CV-2256 2d" Piston Op D-2 2

BC 0

Cold Shutdown NA 4.2.6.1 5 sec Check CV-2270 6" A0 Relief C-3 2

BC C

Every 3 months NA PSV-2271 6" Safety C-3 2

C C

At Refuelings NA PSV-2272 C-3 C

PSV-2273 C-3 C

PSV-2274 C-2 C

PSV-2275 C-2 C

O CV-2276 28" Piston op B-2 2

BC 0

Cold Shutdown NA 4.2.6.1 5 sec Check CV-2277 3" Piston Op

.C-2 2

B 0

Every 3 months NA 10 see CV-2278 Globe F-2 0

10 sec-O CV-2279 D-2 0

10 sec CV-2280 B-2 0

10 see CV-2294 1" A0 Gate E-4 2

B 0

Every 3 months NA 10 sec CV-2295 C-4 0

10 see

).

O CV-2296 A-4 0

10 sec l

CV-2297 C-3 0

10 sec 3-EBD-CK 3" Check G-2 ANSI B31.1 C

C Every 3 months NA 3-EBD-CK E-3 C

3-EBD-CK D-3 C

i 3-EBD-CK C-2 C

i

_m TABLE 4.1-1 Sheet'17 of 37 s

SYSTEM: Main and Auxiliary Feedwater P&ID NO:

M-213 8 ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief-ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks 2-CCC-CK 2" Check

-C-7 ANSI B31.1 C

C Cold Shutdown NA 4.2.7.2 2-CCC-CK C-6 C

2-CCC-CK C-6 C

2-CCC-CK C-5 C

3-EBE-CK 3" Check H-7 2

C C

Cold Shutdown NA 4.2.7.2 3-EBE-CK H-7 C

3-EBE-CK H-6 C

3-EBE-CK H-6 C

3-DBE-CK 3" Check H-7 2

C C

Cold Shutdown NA 4.2.7.2 3-DBE-CK

- H-6.

C 3-DBE-CK H-6 C

3 3-DBE-CK H-5 C

w 6-DBD-CK 6" Check C-8 ANSI B31.1 C

C Cold Shutdown NA 4.2.7.2 6-DBD-CK B-8 6-HBD-CK 6" Check B-7 ANSI B31.1 C

C NA NA 4.2.7.4 6-HBD-CK B-7 C

6-HBD-CK 6" Check

. B-7 ANSI B31.1 C

C Every 3. months NA 4.2.7.3 6-HBD-CK B-7 C

3 2-HKD-CK

'2" Check A-7 ANSI B31.1 C

C Every 3 months NA

^$

y, 6-HKU-CK 6" Check C-7 ANSI B31.1 C

C Every 3 months NA oa 14-EBE-CK 14" Check C-7 2

C 0

Cold Shutdown NA 4.2.7.5 14-EBE-CK C-6 14-EBE-CK C-6 7

14-EBE-CK G-7 E$

m i

2 1

4

~

..-.. ~. -..

e' e

TABLE 4.1-1 Sheet 18 of 37 9I

.M $

R&

{$

SYSTEM: Main and Auxiliary Feedwa'ter P&ID No:

M-213 1

5" ASME Sect 8

. Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks FW-087 3" Gate H-5 2

E O

N*.

NA 4.2.10.3 FW-088 H-6 0

FW-089 H-6 0

FW-090 H-7 0

FW-091 3" Cate C-5 2

E O

NA NA 4.2.10.3 FW-092 C-6 0

FW-093 G-6 0

FW-094

~G-7 0

FW-103 3" Cate G-7 ANSI B31.1 E

O NA NA 4.2.10.3 FW-104 C-7 0

FW-105 G-6 0

FW-106 C-6 0

g

+

v-FW-107 3" Cate C-6 ANSI B31.1 E

O NA NA 4.2.10.3.

FW-108 G-6 0

FW-109 G-5 0

FW-110 C-5 0

4 FW-111 6" Cate B-7 ANSI B31.1 E

LO NA NA 4.2.10.3 FW-112 B-7 LO FW-113 6" Butterfly B-7 ANSI B31.1 E

O NA NA-4.2.10.3 FW-114 B-7 0

1 FW-115 1" Globe B-7 ANSI B31.1 C

NA NA 4.2.10.3 FW-116 B-7 C

d FW-117 2" Cate B-8 ANSI B31.1

.E

.LO NA NA 4.7.10.3 i

FW' 118 B-8 LO i

4 4

I TABLE 4.1-1 Sheet 19 of 37 SYSTEM: Main and Auxiliary Feedwater P&ID NO:

H-213 ASME I Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks FW-119 6" Cate C-8 ANSI B31.1 E

LO NA NA 4.2.10.3 FW-120 B-8 LO M0-3045A 6" M0 Cate B-7 ANSI B31.1 B

C Every 3 months NA 10 sec

^

MO-3045B B-7 C

10 sec MO-3060A 2" M0 Butterfly A-7 ANSI B31.1 B

C Every 3 months NA 10 see HO-3060B 6" M0 Butterfly C-7 ANSI B31.1 B

C Every 3 months NA 30 see CV-3004A1 3" M0 Clobe C-7 ANSI B31.1 B

0 Every 3 months NA 15 sec CV-3004B1 C-5 0

15 see C

CV-3004C1 C-6 0

15 see CV-3004D1 C-6 0

15 sec CV-3004A2 2" M0 Globe H-7 ANSI B31.1 B

0 Every 3 months NA 10 see CV-3004B2 H-5 0

10 sec C

CV-3004C2 11 - 6 0

10 sec CV-3004D2 11 - 6 0

10 sec 9$

a8 8&

i T8 nn

>-a 8

~

f l

t 4

TABLE 4.1-1 Sheet 20 of 37 ou0$

- Ef B SYSTEM: Main and Auxiliary Feedwater P&ID NO:

M-214 ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks MO-3071 4" M0 Globe B-4 ANSI B31.1 B

C Every 3 months-NA 10 sec

^ l MO-3170 B-4 B

0 10 see I

4

~.. -

. _~ -.

t i

TABLE 4.1-1 Sheet 21 of 37 SYSTEM:

Component Cooling Water P&ID No:

M-215 ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks MO-3210A.

12" MO F-8 ANSI 531.1 B

C Every 3 months NA 120 sec

. cl MO-3210B Butterfly D-8 C

120 sec 4

CV-3287 18" A0 F-4 ANSI B31.1 B

0 Every 3 months NA 22 see CV-3288 Butterfly D-4 0

22 see t

3 MO-3290 14" A0 C-4 2

B 0

Cold Shutdown NA 4.2.8.1 120 see i

MO-3291 Butterfly C-4 0

4.2.10.4 120 sec l

MO-3292 H-4 0

120 sec

}

i_

MO-3293 14" MO

-G-8 ANSI B31.1 B

0 Every 3 months NA 17 see i

Butterfly MO-3294 6" MO Cate H-4 ANSI B31.1 B

0 Cold Shutdown NA 4.2.8.1 10 see 1

MO-3295 8" MO D-5 ANSI B31.1 B

o Cold Shutdown NA 4.2.8.2 10 see I

gj Butterfly i

MO-3296 4" M0 Cate C-4 ANSI B31.1 B

0 Cold Shutdown NA 4.2.8.1 10 see i

MO-3300 6" M0 Cate C-6 ANSI B31.1 B

o Cold Shutdown NA 4.2.8.1 10 sec CV-3303 18" A0 E-1 ANSI B31.1 B.

O Every 3 months NA 10 sec 9@

CV-3304 Butterfly 0

10 sec l

MO-3319 8" MO C-6 ANSI B31.1 B

0 Cold Shutdown NA 4.2.8.2 10 sec e$ b Butterfly 4

n re H

I 8

MO-3320 4" M0 Cate B-6 ANSI B31.1 B

0 Cold Shutdown NA 4.2.8.1 10 sec I

i T

I

1 1

TABLE 4.1-1 Sheet 22 of 37 I

me l

8&

asgg SYSTEM:

Component Cooling Water P&ID NO:

M-215 we i

g ASME Sect S

Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks j

r PSV-332 3A 2" Safety F-7 ANSI B31.1 C

C At Refueling NA PVS-3323B C-7 C

O l

MO-3346 14" M0 B-4 2

B 0

Cold Shutdown NA 4.2.8.1 120 see I

Butterfly 4.2.10.4 MO-3347 14" M0 B-6 ANSI B31.1 e

C Every 3 months NA 17 sec Botterfly a

1 24-HBD-CK 24" Check C-3 ANSI B31.1 C

0 Every 3 months NA 24-ilBD-CK C-3 0

]'

24-ilBD-CK C-3 0

24-llBD-CK D-3 0

I

{

CC- 009 24" Butterfly C-3 ANSI B31.1 E

LO NA NA 4.2.10.3 CC-010 C-3 LO l

CC-011 F-3 LC CC-012 E-3 LC 4

CC-013 C-3 LO i

CC-014 C-3 ID i

CC-021 F-4 LO CC-022 D-4 ID v

CC-049 C-2 LO i

i CC-050 C-2 LO u

CC-151 F-2 LC CC-152 D-2 If L

CC-153 F-2 LC CC-154 E-2 LC -

4 l

I l

a 4

4 1

- -. ~ -.. -

- _ - _ ~.

- - - -.... - - -. - - ~

-i L

1 TABLE 4.1-1 Sheet 23 of 37 SYSTEM:

Service Water P&ID NO:

M-218 ASME Sect i

Valve Valve Drwg Code XI Norm Test Frequency Relief f

ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks CV-3712A 8" A0 C-4 ANSI B31.1 B

C Every 3 months NA 10 sec l

bl CV-37128 Butterfly H-4 C

10 sec CV-3714 8" A0 H-4 ANSI B31.1 B

0 Every 3 months NA 10 sec Butterfly CV-3720A 8" A0 C-4 ANSI B31.1 B

0 Every 3 months NA 10 sec CV-3720B Butterfly C-6 0

10 see i

^

PSV-3708A 1" Safety F-3 ANS I B 31.1 C

C At Refueling NA PVS-3708B E-3 C

l CV-3725 8" A0 H-4 ANSI B31.1 B

0 Every 3 months NA 10 sec Butterfly CV-3803 3" A0 D-7 ANSI B31.1 B

0 Every 3 months NA 10 sec CV-3804 Butterfly E-7 0

10 sec PSV-3832A 2" Clobe C-3 ANSI B31.1 C

C At Refuelings NA

{

PVS-3832B C-1 C

PVS-3832C C-3 C

,k,O y

PVS-3832D H-3 C

I i

2 i!.

g.g PSV-3833A 3/4" Safety H-3 ANSI B31.1 C

C At Refuelings NA 3

eD PSV-3833B C-2 C

PSV-3834 2" Safety C-7 ANSI B31.1 C

C At Refuelings NA l

PSV-3835 1-1/2" Safety C-8 ANSI B31.1 C

C At Refuelings NA e

l 8

4 i

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B B

B B

B B

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B Md a S ol I

I I

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S S

S S

S S

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wc 44 64 4

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TABLE 4.1-1 Sheet 26 of 37 a5 G~

8 SYSTEM:

Clean Radioactive Waste P&ID NO:

H-220 ASME Sect

~

Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks CV-4000 1" A0 Clobe C-8 2

A O

Every 3 months Each Refueling 4.2.10.1 10 sec l

HO-4005 3" H0 Cate F-7 2

A 0

Every 3 moaths Each Refueling 4.2.10.1 10 see b

CV-4006 3" A0 Cate F-7 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 see 1-CBB-CK 1" Check C-P 2

AC C

Each Refueling Each Refueling 4.2.9.1 4.2.10.1 L

i

l i

l 7

s 3

k c

c r

e e

f a

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1 i u 1

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2 l q 2

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4 4

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l g

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u a

a q

E E

er F

s s

h h

t t

t s e n

n e

s o

o T

i m

m c

r 3

3 ex y

y E

r r

e e

v v

E E

1 m

1 rs oo 0

0 4

NP EL B

t A~

cI t T-eX a A

A S

C e

t E

s s

H es a

Sd a 2

2 W

AolCC s

uo e

sa gn C

wc 8

8 ro e

DL E

E v

i tcao n

i o

d i

a et e

e R

vp t

t l i a

a ar C

C V c s

O 0

e M

A M

D ET 3"

3" SYS eo 0

1 vN 0

0 l

3 3

aD 4

4 VI O

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, i 4

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TABLE 4.1-1 Sheet 29 of 37 i

SYSTEM:

Instrument and Service Air P&ID NO:

M-223 i

ASME Sect s

i Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks CV-4470 2" A0 Globe D-1 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec j

CV-4471 2" A0 Clobe F-1 2

A O

Each Refueling Each Refueling 4.2.9.2 10 see f

4.2.10.1 2-IIBE-CK 2" Check D-1 2

AC C

Each Refueling Each Refueling 4.2.9.2 4.2.10.1 t

2-IIBE-CK 2" Check F-1 2

AC O

Each Refueling Each Refueling 4.2.9.2 4.2.10.1 i

l J

9k a8 2

8&

l8 nn 8

3 4

i

4 TABLE 4.1-1 Sheet 30 of 37 Em 2 R.

8M SYSTEM:

Diesel Fuel Oil P&ID NO:

M-226

. e-. e ASME Sect S

valve valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise l

Leakage

' Request Remarks MO-4903A 3" Cate F-5 ANSI B31.1 B

C Every 3 months NA 10 sec 3

MO-4903B B-5 C

10 sec MO-4907A l2" M0 Globe C-6 ANSI B31.1 B

C Every 3 months NA

'1 Jec MO-49078 B-6 10 sec 3-HBD-CK 3" Check F-7 ANSI B31.1 C

C Every 3 months NA 3-IIBD-CK D-7 C

DO-001 3 Gate F-7 ANSI B31.1 E

la NA NA 4.2.10.3 DO-002 D-7 LO DO-005 C-5 LO DO-006 D-5 LO DO-007-F-5 LC D0-OO3 E-5 I4 DO-G99 E-5 IE DO-010 D-5 LO DO-011 C-5 LO l

3 DO-014 1" Clobe B-8 ANSI B31.1 E

la NA NA 4.2.10.3 DO-015 E-4 LC DO-016 C-4 LC DO-017 3" Cate E-4 ANSI B31.1 E

LO NA NA 4.2.10.3 DO-018 C-4 LO DO-019 E-4 If DO-020 2" Clobe B-7 ANSI B31.1 E

LO NA NA

. 4.2.10.3 DO-021 E-5 to 1

i L

7 s

3 kr f

a o

me 1

R 3

3 3

3 t

t e

f s e

ee 0

0 0

h 6

i u 1

1 1

S 2

l q 2

ee 2

2 2

RR M

4 4

4 e

O a

N k

A A

A a

N N

N D

y e

I c L n

P e

u q

e r

F ts e e s T

i c

A A

A r

N N

N ex E

1 mrs 1

oo CC 0oO C

4 NP LL 0LL L

E L

B t

A cI t T

eX a E

E E

S C

1 1

1 1

1 1

s 3

3 3

E es B

B B

Md a S ol I

I I

l ACC S

S S

i N

N N

O A

A A

lea gn F

wc r o 44 577 7

l DL e

DD DBB B

se l

i D

no i

et vp li r

e ar e

b b

V c t

o o

s a

l l

e C

C C

M D

E T

3 2

1 SY S

eo vN 23 234 6

l 22 333 3

aD 00 000 0

VI OO OOO O

DD DDD D

7' 8&8n 0'

88ln 8-2 l

i i

i!

ii

,+

9$

8a Bit gg TABLE 4.1-1 Sheet 32 of 37 et n V

E SYSTEM:

Spent Fuel Pool Cooling P&ID NO:

M-227 v

ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Ex:rcise Leakage Request Remarks,

SF-046 8" Cate F-2 2

AE LC NA Each Refueling 4.2.10.1 Passive SF-051 E-1 LC 4.2.10.3 SF-062 3" Cate E-2 2

AE LC NA Each Refueling 4.2.10.1 Passive SF-063 E-2 4.2.10.3 SF-073 10" Cate B-2 2

AE LC NA Each Refueling 4.2.10.1 Pa ssive O

SF-074 B-2 4.2.10.3 SF-075 10" Gate A-3 2

E LC NA NA 4.2.10.3 Passive SF-080 8" Cate F-2 2

A C

NA Each Refueling 4.2.10.1 Passive l

CV-5075 4" A0 C6 te A-6 3

B C

Every 3 months NA 10 sec CV-5076 A-6 C

10 sec 6

1

~ ^ "

- - - ~ ~ ^ ~ - - ~ ~

TABLE 4.1-1 Sheet 33 of 37 SYSTEM:

Make-up Water Treatment P&ID NO:

M-228 ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks MD-059 3" Manual Cate F-1 2

AE LC NA Each Refueling 4.2.10.1 Passive 4.2.10.3 O

~

3 a.un-C" 2" Chack F-1 2

AC C

NA Each Refueling 4.2.10.1 Passive 4

A

• 8 gg-1 o~ e OD M n 8

i

.__m t

9I TABLE 4.1-1 Sheet 34 of 37 I

B 8'

~

SYSTEM:

Sampling P&ID NO:

M-2 31 V

l

~ $

ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description.

Locn Class Cat Pos Exercise Leakage Request Remarks CV-2809 3/4" A0 Globe

.H-6 2

B 0

Every 3 months NA 10 sec CV-2811 H-7 0

10 sec CV-2814 H-6 0

10 sec l'

CV-2880 H-7 0

10 sec MO-5651A 3/4" MO Globe H-4 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see MO-56518 H-4 C

10 see MO-5651C H-4 C

10 sec 1

MO-5651D H-4 C

10 sec CV-5652 3/4" A0 Globe G-4 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see t

MO-5653 3/8" MO Globe H-6 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec MO-5654 H-5 C

10 see d

b CV-5655 3/4" A0 Globe G-6 2'

A C

Every 3 months Each Refueling 4.2.10.1 10 sec

[

CV-5656 3/4" M0 Globe II-5 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see CV-5657 3/4" A0 Globe G-5 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see i

1

~

MO-5658 3/4" MO Globe H-5 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec 2

CV-5659 3/4" AO Clone G-5 2

A C

Every 3 months Each Refueling 4.2.10.1 10 sec MO-5660 3/4" MO Globe C-7 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 see 1

i CV-5661 3/4" A0 Clobe B-7 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 sec i

TABLE 4.1-1 Sheet 35 of 37 l

i SYSTEM:

Containment Ventilation P&ID NO:

M-243 ASME Sect Valve Valve Drwg Code X1 Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request-Remarks MO-5663 1" M0 Globe E-7 2

A 0

Every. 3 months Each Refueling 4.2.10.1 10 sec t

MO-5671 1" MO Globe E-7 2

A 0

Every 3 months Each Refueling 4.2.10.1 10 sec MO-5672 E-6 0

10 see MO-5673 1" M0 Clobe E-7 2

A 0

Every 3 months Each Refueling 4.2.10 1-10 see MO-5674 1" M0 Clobe E-7 2

A C

Every 3 months Each Refueling 4.2.10.1 10 see MO-5675 F-7 C

10 sec MO-5676 1" MO Clobe E-7 2

A C.

Every 3 months Each Refueling 4.2.10.1 10 see MO-5677 F-8 10 see

0-5678 E-8 10 sec l

CV-10001 54" A0 D-2 2.

A C

Cold Shutdown Each Refueling 4.2.9.3 3 see Butterfly 4.2.10.1 MO-10002 54" MO D-2 2

A C

Cold Shutdown Each Refueling 4.2.9.3 5 see MO-10003 Butterfly D-7 4.2.10.1 5 sec Q

CV-10004 54" A0 D-7 2

A C

Cold Shutdown Each Refueling 4.2.9.3 3 sec Butterfly 4.2.10.1

' MO-10005 8" MO C-2 2

A C

Every 3 months Each R::. fueling 4.2 9.4 5 see MD-10006 Butterfly C-2 C

4.2.10.1 5 see Ho-10007 C-2 C

5 sec MO-10008 C-2 C

" sec MO-13009 C-7 C

5 see MO-10010 C-7 C

5 sec gg MO-10011 C-7 C

5 sec

• g MO-10012 C-7 C

5 sec e o.

g.g 10610A J/4" Cate D-7 2

AE LC NA Each Refueling 4.2.10.1 Passive gg 10610B D-7 LC 4.2.10.3 10611A C-7 LC l

yyg 10611B C-7 I4 S

~. -.

8 I

9I aa g g-TABLE 4.1-1 Sheet 36 of 37

'Ea nn g

SYSTEM:

Chilled Water MID NO:

M-248 1

ASME Sect

(

Valve Valve Drug Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Pos Exercise Leakage Request Remarks 1

j MO-10013 4" No Butterfly B-4 2

A 0

Evecy 3 months Each Refueling 4.2.10.1 5 see CV-10014 4" A0 Butterfly B-4 2

A 0

Every 3 months Each Refueling 4.2.10.1 3 see.

O CV-LOO 15 0

3 see w

MO-10016 4" WO Butterfly B-4 2

A 0

Every 3 months Each Refueling 4.2.10.1 5 sec

'[

I i

[

]

I i

i

, - =.., _

e..

TABLE 4.1-1 Sheet 37 of 37 SYSTEM:

Steam Generator Blowdown P&ID NO:

H-348 ASME Sect Valve Valve Drwg Code XI Norm Test Frequency Relief ID No.

Description Locn Class Cat Fos Exercise Leakage Request Remarks MO-2808 2" MO Globe F-7 2

B 0

Eveey 3 months NA 10 see MO-2810 H-5 0

10 see MO-2812 C-7 0

10 sec HO-2813 G-6 0

10 sec MO-6716 H-8 0

10 sec O

MO-6717 C-8 0

10 see MO-6718 G-8 0

10 see MO-6719 C-8 0

10 see 1

d aa 08-sa nn 8

4 4

4.2 RELIEF REQUEST BASIS FOR VALVES The Code of Federal Regulations, 10 CFR 50.55a(g)(5)(iii) requires

[3 that

. "If the licensee has determined that conformance with certain code requirements is impractical for his facility the licensee shall notify the Commission and submit information to support his determinations".

By interpretation, any valves which do not conform to the standard test requirements for measurement of specific parameters or for the frequency of the test are assumed to be in nonconformance. This section identifies those valves for which testing under this program does not comply with the standard test requirements and provides the bases for relief from

[3 testing and provisions for alternate testing.

4.2.1 REACTOR COOLANT SYSTEM (RCS) 4.2.1.1 Valves: 8900A, 8900B, 8900C, 8900D Ca tegory: C (check valve)

Class:

1 Function: Each of these valves prevents backflow from its respective RCS cold leg into the boron injection tank during normal operation and allows flow from the boron injection tank to the RCS during safety injection.

Test Requirement: Exercise for operability every 3 months.

Basis for Relief:

Exercising these valves would require injection of concentrated boric acid into the RCS causing a power transient that could

[3 result in a reactor trip.

4.2-1 Amendment 1 (December 1980)

Alternative Testing: These valves will be full stroke exercised h3 for verification of operability during cold shutdown.

4.2.1.2 Valves: 8948A, 8948B, 8948C, 894bD bl Category: AC (check valve)

Class:

1 Function: Zach of these valves prevents backflow from its respective RCS cold leg and sequentially allows flow from the SIS accumulators, the SIS pump discharge, and the Residual Heat Removal System (RRRS) durirgi safety injection. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Exercising of these valves would require injection of concentrated boric acid into the RCS causing a power transient that could result in a reactor trip. During power operation, the SIS accumulators, SIS pumps or kHRS pumps cannot overcome RCS pressure. O Alternative Testing: These valves will be partial stroke exercised for verification of operability during cold shutdown using RHRS flow. 4.2.1.3 8949A, 8949B, 8949C, 8949D Category: AC (check valve) Class: 1 o Amendment 1 4.2-2 (December 1980)

Function: Cach of these valves prevents backflow from its respective RCS hot leg to the SIS pump discharge during normal operation and allows flow when RCS pressure drops below the SIS pump discharge pressure during shutdown. The RHRS pump discharge is also aligned to provide flow to RCS Loops 2 and 4 through the respective check valves during cooldown and refuelius operations. Test Requirement: Exercise for operability every 3 months. Basis for Relief: During power operation the SIS and RRRS pumps cannot overcome RCS pressure. Alternate Testing: These valves will be full stroke exercised for verification of operability during cold shutdown. 4.2.1.4 Valve: 8046 and 8047 Ca tegory: C (check) C Class: 2 Function: These valves are internal Containment isolation valves which prevent backflow of Containment / Pressurizer Relief Tank contents under accident conditions. Test Requirement: Exercise for operability every 3 months. Basis for Relief: These valves cannot be verified shut during power operation because the test connections 4.2-3 Amendment 1 (December 1980)

i 3 .1 a i I are located inside the Containment. The only available method to verify valve closure is during Icak rate testing during refueling 3 outages. i-2 Alternate Testing: These valves will be exercised for verifi-cation of operability during each refueling. i 4.2.2 CHEMICAL AND VOLUME CONTROL SYSTEM (CVCS) 4.2.2.1 Valves: MO-8105 and MO-8106 4 31 Category: B (MO-8105, MO-8106) Class: 2 Function: These normally open series valves allow flow to the RCS for the normai and alterrate charging lines and for pressurizer auxiliary spray. The motor-operated valves (MO-8105 and MO-8106) shut on a safety injection signal to redirect the charging pump discharge to the ] boron injection tank. The check valve (8381) prevents backflow from the RCS to the charging pump discharge. i Test Requirement: Exercise for operability every 3 months. 1 I j Pasis for Relief: Failure of any of these valves in a closed position would result in loss of pressurizer level control. C Alternate Testing: These valves will be full stroke exercised i for verification of operability during cold I shutdown. Amendment 1 4.2-4 (December 1980) 1 m - f

---

e

, -, = 7 w ,3m-4 ..,---e r w -p-,,-, s-,. o, --n w% 7 . cr-y3

4.2.2.2 Valve: PSV-8117 Category: AC Class: 2 Function: This safety valve provides overpressure protection for the CVCS letdown flow path and acts as an internal Con-tainment isolation barrier between the pressurizer relief tank and the CVCS system. Test Requirement: Test for leakage at each refueling. Basis for Relief: This safety valve is inside the Containment and is on the Containment side of the isolation valves. As such it is labeled a Containment barrier isoJa-tion valve with a specified leakage. An increase () in pressure on the pressurizer relief tank side of the valve tends to seat the valve tighter, however, the design of the bellows is such that high pressure is directed to the inside of the bellows and testing with pressure external to the bellows could result in damage to the relief-actuating mechanism. Ad di-tionally, Paragraph Ik'V-3512 allows that safety and relief valves which are tested for their setpoint are not required to be additionally leak tested. Alternate Testing: This valve will be tested for its relief catpoint at refuelings in accordance with the schedule for testing safety and relief valves. 4.2.2.3 Valves: 8481A and 8481B C Category: C (Check) Class: 2 4.2-5 Amendment 1 (December 1980)

Function: Each of these valves is on the discharge of a centrifugal charging pump and prevents backfit. Test Requirement: Exercise for operability every 3 months. Basis for Relitf: Juring power operatica, the charging flow cath cannot accommodate full flow except through the Boron Injection Tank which would 7 require injection of concentrated boric acid into the RCS causing a power transient that could result in a reactor trip. Alternate Testing: These valves will be partial stroke exercised at power every 3 months and full stroke exercised at cold shutdown. 4.2.2.4 Valve: 8546 Category: C (check) Class: 1 Function: This valve prevents backflow of water from the volume e' trol tank (T-213) to the Refueling Water Storage Tank (RWST) during normal operation and allows flow from the RWST to the centrifugal charging pump suctions during safe shutdown. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Exercising of this valve would require injection of concentrated boric acid from the RWST into the RCS, causing a power (( transient which could result in a reactor trip. Amendment 1 4.2-6 (December 1980)

Alternate Testing. This valve will be full stroke exercised b for verification of operability during cold shutdown. 4.2.2.5 Valves: MO-8100 and M0-8112 Category: A Class: 2 Function: These normally open Containment isolation valves, close on a CIS to isolate the reactor coolant pump seal water return. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Failure of either of these valves in a closed position would result in loss of seal leakoff flow. Alternate Testing: These valves will be full stroke exercised {} for verification of operability during cold shutdown when the reactor coolant pumps are shutdown. 4.2-7 Amendment 1 (December 1980) l i

l i l 4.2.3 RESIDUAL HEAT REMOVAL SYi, TEM (RHRS) f 4.2.3.1 Valves: MO-8701 and MO-8702 Category: B Class: 1 Function: These normally closed series valves connect the suction of the RHRS pumps to the RCS Loop 4 hot leg. These valves are interlocked to prevent opening with s RCS pressure greater than 425 psig and to automati-cally close when RCS pressure exceeds 600 psig. Test 2:quirement: Exercise for operability every 3 monchs. Basis fbr Relief: Exercising of these valves during normal operation sould require overriding of a safety interlock. The potential for over- ] pressurization of the RHRS and depressuriza-i tion of the RCS make testing of these j! valves at normal RCS pressure unsafe. ~, l Alternate Testing: These valves will be exercised for verifica-tion of operability during cold shutdown. 4.2.3.2 Valves: 8736A, 8736B I {} Category: AC (check) i Class: 1 ] Function: These valves prevent backflow from the RCS Loops i I I 2 and 4 hot legs into the RERS during normal operation. j i l I Amendment 1 4.2-8 (December 1980) i <#w _,, )

Test Requirement: Exercise for operability every 3 months. Basis for Relief: During normal operation, the B".RS pumps cannot overcome RCS pressure. Alternate Testing: These valves will be full stroke exercised 3 for verification of operability during cold shutdown. 4.2.3.3 Valves: 8818A, 8818B, 8818C, 8818D e Category: AC Class: 1 Function: Each of these valves prevents backflow from one of the RCS cold legs into the RRRS during normal operation and allow flow from the RRRS into the RCS during the RHR cooldown. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Exercising of these valves would require reducing RCS pressure to an unacceptable level for normal operation. O Alternate Testing: These valves will be exercised for verifica-tion of operability during cold shutdown. 4.2.3.4 Valve: MO-8703 Category: B ^ v Class: 2 i 4.2-9 A=endment 1 (December 1980)

l i Function: This normally closed valve isolates the RHRS flow path to the RCS loop 2 and 4 hot legs during normal ope ra tion. Test Requirement: Ex,: rcise for operability every 3 months. Basis for Relief: Failure of this valve in the open position would redirect low head safety injection flow from the safety injection flow path. Alternate Testing: This valve will be full stroic exercised for verification of operability during cold shutdown. 4.2.3.5 Valves: 8730A and 8730B Category: C (check) (( Class: 2 Function: Valves 8730A and 8730B are on the discharge of the RHRS pumps and prevent backflow through their respective pump. Test Requi.ement: Exercise for operability every 3 months. Basis for Relief: During power operation, the RHR pumps cannot overcome RCS pressure and the only flow path which can accommodate full flow is on recirculation to the RWST. This flow path is unacceptable because it would require repositioning of the RVST return isolation valve, 8735 (normally locked closed), which would render the RHI S injection system inoperable. Amendment 1 4.2-10 (December 1980)

Alternate Testing: Valver 8730A and 8730n will be partial stroke exercised on niniflow during power operation and full stroke exercised during cold shutdown. 4.2.3.6 Valves: M08804A and MO-8804B Category: B Class: 2 Function: These normally closed valves isolate the RHR pumps discharge from the safety injection and charging pump suctions. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Failure of either of these valves in the open position would result in redirection of g the safety analysis flow. Alternatt Testing: These valves will be full stroke exercised during cold shutdown. 4.2.3.7 valve: MO-8812 Category: B Class: 2 Function: This normally open valve is repositioned ! 2 isolate the RWST from the RHRS pump suction during the accident recirculation phase. Basis for Relief: Failure of this valve in the closed position would render the entire RHRS systen inoperable. 4.2-11 Amendment 1 (Decenber 1980) j l

l L i Alternate Testing: This valve will be full stroke exercised for verification of operability durit.g cold shutdown. 4.2.3.8 Valve 8958 Category: C Class: 2 Function: Valve prevents backflow from RHR suction header to the j refueling water storage tank. i Test Requirement: Exercise for operability every 3 months. C Basis for Relief: Exercising this valve requires the RHR pumps drawing suction on the RWST. Operating modes do not allow this because there is no place to store the water unless initiating large scale RVST recirculation (opening manual valve 8735). However, this is not l feasible due to the RHR system operating in a de-graded condition (see Relief 4.2.3.5). Cold shut-shutdown is not feasible because the RHR is in circu-lation to the RCS. The only feasible plant condition where this valve can be exercised is during refueling when the RHR system is utilized to fill the refueling l cavity. Alternate Testing: Valve 8958 will be full stroke exercised during refueling outages when the refueling cavity is filled. l l l l Amendment-1 4.2-12 (December 1980) i

i N 4.2.4 SAFETY INJECTION SYSTEM (SIS) i 4.2.4.1 Valves: MO-8808A, MO-8808B, MO-8808C, MO-8808D Catego ry: B (passive) Class: 1 Function: These normally open valves provide isolation for the SIS accumulators. The valves are designed to open on receipt of a Safety Injection Signal. Test Requirement: None Basis for Relief: These valves are categorized as B passive in that under normal operating conditions they are open and remain open in performance of their safety function. The valves have been included in the IST program for testing due to their critical location in a safety-related system and the imposed administrative require-ments which require plant shutdown for failure f of one of these valves in a closed position. O Alternate Testing: Exercise for verification of operability during cold shutdown. 4.2.4.2 Valve: 8815 Category: C (check) Class: 1 Function: This valve prevents backflow from the RCS cold legs into the baron injection tank during normal operation 4.2-13 Amendment 1 (Deccaber 1980)

and allows injection concentrated boric acid from ((l the boron injection ' e during a safety injection. Test Requirement: Exercise for operability every 3 months. Basis for Relief: Exercising of this valve would require injection of concentrated boric acid into the RCS causing a power transient that could result in a reactor trip. O Alternate Testing: This valve will be full stroke exercised for verification of operability during cold shutdown. 4.2.4.3 Valves: 8819A, 8819B, 8819C, 8819D 31 Category: AC (check) Class: 1 1 Function: Each of these valves prevents backflow from its respective RCS loop cold leg and allows flow from the discharge of the SIS pumps during shutdown. 4 Basis for-Relief: Exercising of these valves would require injection of concentrated beric acid into (( the RCS that could result in a reacect trip. During power operation the SIS pumps cannot overcome RCS pressure. Alternate Testing: These valves will be full stroke exercised for verification of operability during cold shutdown. 4 i' Acendnent 1 4.2-14 ) (De c embr.* 1980)

4.2.4.4 Valves: 8905A, 8905B, 8905C. 8905D Category: C (check) Class: 1 Function: Each of these valves prevents backflow from its respective RCS loop hot leg and all es flow from the discharge of the SIS pumps during shutdown. Test Requirement: Exercise for operability every 3 mot.ths. l Basis for Relief: Exercising of these valves would require injection of concentrated boric acid into the RCS causing a power transient that could result in a reactor trip. During power oper- [3 ation, the SIS pumps cannot overcome RCS pressure. Alternate Testing: These valves will be full stroke exercised for verification of operability during cold shutdown. 4.2.4.5 Valves: 8956A, 8956B, 8956C, and 8956D Category: C (check) Class: 2 I Function: These normally closed 4alves prevent backflow from the RCS into the accumulators during normal operation. Test Requirement: Exercise for operability every 3 months. Basis for Relief: During normal operation, the accumulator cannot overcome RCS pressure. Full stroke testing is not feasible due to limited plant

onditions for testing.

4.2-15 Amendment 1 (December 1980)

1 l Alternata Testing: These valves will be partial stroke exercised during cold shutdown. 4.2.4.6 Valve: 8968 Category: AC (check) Class: 2 Function: This internal isolation valve prevents backflow out of the Containment from the accumulators and is on the nitrogen overpressure supply line. Test Requirements: Exercise for operability ev'ery 3 months. Basis for Relief: There are no provisions for verifying the valve to be in the shut position during normal operation. ~~ 1 ~ Alternate Testing: This valve will be exercised and verified shut during leak rate testing at refueling outages. 4.2.4.7 Valves: MO-8806 and MO-8835 Category: B Class: 2 Function: These normally open valves isolate the RWST from the SIS pump suction (MO-8806) and the cold leg safety injection into the RCS (MO-6635). Test Requirement: Exercise for operability every 3 mont'.is. Amendment 1 4.2-16 (December 1980)

~. Alternate Testing: These valves will be partial stroke exercised during cold shutdown. 4.2.4.6 Valve: 8968 Category: AC (check) Class: 2 Function: This internal isolation valve prevents backflow out of the Containment from the accumulators and is on t the nitrogen overpressure supply line. Test Requirements: Exercise for operability every 3 months. i Basis for Relief: There are no provisions for verifying the valve to be in the shut position during normal operation. C; 3 Alternate Testing: This valve will be exercised and verified shut during leak rate testing at refueling outages. 4.2.4.7 Valves: MO-8806 and MO-8835 i Ca tegory: B i Class: 2 i Function: These normally open valves isolate the RWST Arom the SIS pump suction (Mu v806) and the cold leg safety injection into the RCS (MO-8835).. Test Requirement: Exercise for operability every 3 months. Amendment 1 4.2-16 (December 1980)

Basis for Relief: Failure of either valve in the closed position would render SIS inoperable. 4 Alternate Testing: These valves will be full stroke exercised for verification of operability during cold shutdown. 4.2.4.8 Valves: MO-8813 and MO-8814 Category: B l Class: 2 i Function? These normally open series valves isolate the SIS pump miniflow return flow path to the RWST. l Basis for Relief: Failure of either valve in a closed position would render the SIS pumps inoperable. A minimum flow rate through the pumps is required ] to ensure pump cooling. The miniflow l flow path guarantees this minimum flow during the Safety Injection initiation. Alternate Testing: These valves will be full stroke exerci ed for verification of operability during cold shutdown. 4.2.4.9 Valves: 8922A, 8922B, and 8926 J Category: C (check) l Class: 2 Function: Valves 8922A and 8922B are on the discharge of the SIS pumps and prevent backflow through the respective 4.2-17 Amendment 1 1 (Lecember 1980)

4 {} pump. Valve 8926 is between the SIS pumps suction and the RHST and prevents backflow into the RUST. Test Requirement: Exercise for operability every 3 months. Basis for Relief: The SIS pumps cannot overcome RCS pressure during power operation and as a result full flow cannot be accommodated. Alternate Testing: These valves will be partial stroke exercised during power operation and full stroke i exercised for verification of operability during cold shutdown. 4.2.5 CONTAINMENT SPRAY SYSTEM 4.2.5.1 Valves: 10-HCB-CK (two) E Category: C 1 Class: 2 i i Function: These valves prevent backflow of air from the Containment atmosphere through the Containment spray i ring header. Test Requirement: Exercise for operability every 3 months. 1 j Basis for Relief: These valves do not have provision for testing under normal conditions. E:.ercising i the valves would require injection of the test medium into the Containment through the spray nozzles with no means available for verification of flow. Equipment damage n C and requirements for extensive cleanup of the Containment would result. d Amendment 1 4.2-18 -(December 1980).

Alternate Testing: These valves are partNal stroke exercised during Containment smoke testing at a maximum interval of 5 yr under Technical-I' Specification 4.6.2.1. i-4.2.5'.2 Valves: 14-HCB-CK (two) Category: .C Class: 2 j ? unction: These valves prevent backflow into the RWST from the Containment spray suction header. -s C i Test Requirement: Exercise for operability every 3 months. l Basis for Relief: Full stroke exercising of these valves would require injection of the test medium into the Containment. Equipment damage and I requirements for extensive cleanup of the Containment would result. Alternate Testing: These valves will be partial stroke exercised with flow through the Containment spray pump miniflow lines every 3 months. 4.2.6 MAIN STEAM SYSTEM 4.2.6.1 Valves: -CV-2216, CV-2236, CV-2256, CV-2276 Category: BC Class: 3 i i. I~ Functien: These valves provide main steam isolation in each of the. respective main steam headers. s 4.2-19 Amendment l' (December 1980) j i .... ~ .......,,,-_-,.~.,,m._-,_. ,,,. ~,., - - - ...,.,_,.--...-m._ ..,_.L.,

Basis for Relief: Shutting of one of these valves during opera-tion would result in three loop operation, thereby causing abnormal RCS flow. This results in unnecessary distortion of the reactor flux causing a decrease in the design thermal safety margins. Failure of a valve in the closed position would remove its respec-tive steam generator from operation. b Alternate Testing: These valves will be exercised for verifica-tion of operability during cold shutdown. 4.2.7 MAIN AND AUXILIARY FEED 4.2.7.1 Deleted 2.,2.7.2 Valves: 2-CCC-CK, 3-DBE-CK, and 3-EBE-CK, and 6-DBD-CK Category: C (check) Class: 2 and ANSI B31.1 Function: These valves prevent backflow from the main feed liras to the auxiliary feed system during normal operation. Test Requirement: Exercise for operability every 3 months. Basis for Relief: These valves cannot be exercised during power operation without thermal shocking of the feed system nozzles. Alternate Testing: These valves will be full stroke exercised during cold shutdown. Amendment 1 4.2-20 (December 1980)

4.2.7.3 Valves: 6-HBD-CK (two) Category: C (check) class: ANSI B31.1 Function: These valves are on the suction lines to the auxiliary feed pumps from the condensate storage tank and prevent backflow into the tank when the pumps are lined up to the Service Water System. Test Requirement: Exercise for operability every 3 months. Basis for Relief: The only flow path which will accommodate full flow is into the steam generators. Feeding the steam generators during power operation would result in thermal shocking of the feed system nozzles. O Alternate Testing: These valves will be partial stroke exercised every 3 months on recirculation and full strcke exercised at cold shutdown. 4.2.7.4 Valves: 6-HBD-CK (two) Category: C Class: ANSI B31.1 Function: These normally closed check valves are in the suction line to the auxiliary feed pumps from the Service Water System and prevent backflow into the SWS when the pumps are lined up to take suction from the condensate storage tank. 4.2-21 Amendment 1 (December 1980)

1 Test Requirements: Exercise for operability every 3 months. 1 Basis for Relief: The only flow path which will accommodate -full flow is into the steam generators. Taking suction on the SWS teould result in injecting contaminants in the Steam Generators and/or condensate storage tanks. 4 Alternate Testing: No testing of these valves will be done. 4.2.7.5 Valves: 14-EBE-CK (four) Category: C i Class: 2 ? v Function: These valves prevent backflow from the steam generators into the main feed systes. Test Regnirement: Exercise for operability every 3 months. Basis for Relief: Shutting this valve during power operation would secure feed to the respective steam generator causing the associated MSIV to be shut and resulting in a reactor trip. Alternate Testing: This valve will be full stroke exercised during cold shutdown. 1 4.2.8 COMPONENT COOLING WATER (CCW) 4.2.8.1 Valves: MO-3290, M0-3291, M0-3292,MO-3294, MO-3296, M0-3300, MO-3320, MO-3346 i Category: B Amendment 1 4.2-22 (December 1980) I .. _... _. _ _ _...... ~.. ~.

f ~. Class: 2 (M0-3290, MO-3291, MO-3292, MO-3346, and ANSI B31.1 (MO-3294, MO-3296, M i-3300, M0-3320). Function: These normally open valves are on the supply and return lines of the component cooling water supply to the reactor coolant pumps. Test Requirement: Exercise for operability every 3 months. i Basis for Relief: Failure of one of these valves in the closed position would result in loss of cooling water to the reactor coolant pumps. } C2 J j Alternate Testing: These valves will be~ exercised for verifica-tion of operability at cold shutdown. I 4.2.8.2 -Valves: M0-3295 and MC-3319 Category: B 1 ) Class: ANSI B31.1 J j Function: These are the inlet and outlet isolation valves on the letdown and seal water heat exchangers. The valves are normally open and close on receipt of a Containment isolation signal. 4 Test Requirement: Exercise for operability every 3 months. 4 Basis for Relief: Failure of either of these valves in the closed position would result in loss of cooling water to the _ RCS letdown and the RCS pump seal water heat exchangers requiring reactor shutdown. O Alternate Testing: These valves will be exercised for verifica-tion of operability during cold shutdown. '4.2-23 Amendment 1 (December 1980)

~.. - r 4.2.9 OTHER SYSTEMS l 4.2.9.1. Valve: 1-GBB-CK a J { Category: C Class: 2 i Function: This valve is a Contair. ment isolation valve for (( the N2 supply line to the Reactor Coolant Drain ) Tank and prevents back flow out of Containment. Test Requirement: Exercise for operability every 3 months. i Basis for Relief: The valve can only be verified in uha + 1 closed position during leak rate testing at refueling outage. t Alternate Testing: Exercise for operability at each refueling outage. 4.2.9.2 Valves: 'CV-4471 and 2-HBE-CK (two) Category: A and C, respectively l 1 1 Class: '2 4 i j Function: These normally open series valves are Containment 1 isolation valves for the instrument air supply to j pneumatic valves and instrumentation inside the Containment. The valves close on receipt of a Containment isolation signal. 4 1 Test Requirement: Exercise for operability every 3 months. 4 i f Amendment l' 4.2-24 j (December'1980)

Basis for Relief: Failure of either of these valves in a closed position removes the air supply to the Containment air,eerated valves and pneumatic instrumentvtion. 2-HEE-CK can only be verified shut. during leak testing at refueling outages. Alternate Testing: These valves will be full stroke exercised for verification of operability during leak rate testing at refueling. 4.2.9.3 Valves: CV-10001, MO-10002, M0-10003, CV-10004 i Category: A Function: These valves are the Containment isolation valve. for the Main Containment Purge System. Test Requirement: Exercise for operability every 3 months. Basis for Relief: PGE has committed to maintaining these valves in {} the closed position during Modes 1, 2, 3, and 4 f-response to an NRC concern over Containment purging during normal operation. l 1 Alternate Testind: These valves will be full stroke exercised during i cold shutdown. 4.2.9.4 Valves: MO-10005, M0-10006, M0-10007, M0-10008, MO-10009, hu-10010, MO-10011, M0-10012 i i Category: A 4 1 Function: These valves are the Containment isolation valves for the Hydrogen Vent System. Test Requirement: Exercise for operability every 3 months. 4.2-25 Amendment 1 (December 1980) i 1 r --,-o ,,.5-- -r y ,.w.w,-- ,e, m- ,, -,.w.

i 4 Basis for Relief: PGE has committed to limiting the opening of these valves to'50' to ensure closure under the most severe design basis flow conditions. 0; Alternate Testing: These valves will be-partial stroke exercised every 3 months. 4.2.10 GENERIC RELIEF REQUESTS 4.2.10.1 Valves: Containment Isolation Valves Catego ry: A Class: 1 and 2 Function: These valves provide Containment isolatiot uring reactor operation and/or isclate the Containment to prevent the release of radioactive products following a J design accident. i Test Requirement: Test for seat leakage rate at each refueling. Basis for Relief: The Containment isolation valves are tested for seat leakage under the criteria of Appendix J to 10 CFR 50. These valves are tested and analyzed for seat tightness in accordance with the Trojan Nuclear Plant " Containment Local Leak Rate Test". This t n C, procedure provides for local leak rate testing of valves. The acceptance criteria I for allowable leakage rate under. Appendix J i to 10 CFR 50 varies from the acceptance criteria of Subsection IWV of ASME, Section XI, in that the allowed leakage is based on the total Containment leakage rate rather than Amendment 1 4.2-26 (December 1980) i

o o on individual. valve seat leakage criteria. This test program provides adequate document-ation and individual analysis for valves to verify maintenance of Containment integrity. Failure of any valve to provide adequate seat tightness in maintaining Containment integrity will require the same corrective action for repair and replacement of the valve. Therefore, based on provisions'in Section XI which allow the owner to specify the valve seat leakage criteria, testing under the Section XI requirements would only require duplication of documentation without any added benefit as far as testing or analyzing of test data for assurance of leakage integrity. kh Alternate Testing: These valves are tested for seat leakage rate during local leakage rate testing in accordance with Appendix J to 10 CFR 50 and will not be tested under this program. 4.2.10.2 Valves: WASH-1400, Event V Configuation Valves Category: A Class: 1 Panction: These valves are designated from a configuration of inseries check valves which provide a boundary kb between a high pressure system and a system with a design pressure below that of the normal operating pressure of the high pressure system. Test Requirement: Test for seat leakage rate at each cold shutdown. 4.2-27 Amendment 1 (December 1980) J

m Basis for Relief: The present system at Trojan for testing inseries check valves is designed for testing the second inseries check valve at normal operating pressure only in the event that the first valve demonstrates leakage. The WASH-1400 report does not consider added assurance of protection from periodic testing of the first valve. Alternate Testing: The second valve will be leak tested at reduced pressures at cold shutdown except for check Valves 89053 and 8905D, which will be tested with the in-series check valve to determine the combined leakage across the two valves. 4.2.10.3 Valves: Valves Designated Category E Ca tego ry: E ,s O Class: 1, 2, and 3 Function: The valves under this category are those which are normally locked open or' locked closed to fulfill their function. Test Requirement: Operational checks, with appropriate record entries, shall record the position of these valves before operations are performed and af ter operations are completed and shall verify that each valve is locked or sealed. Basis for Relief: Under 10 CFR 50.55a(b)(2), the most recently approved edition of ASME, Section XI, is 1977 with addenda through the summer of 1978. Category E was deleted from this edition. Valves at Trojan which are locked Amendment 1 4.2-28 (December 1980)

or sealed in position are covered by appro-priate administrative procedures and docu-mentation. The IST program would only duplicate existing requirements. In an effort to prevent conflicting and confusing reports which would not provide any safety margin over the existing administrative procedures, these valves have been listed for convenience but will not be separately documented under this program. O Alternate Testing: Existing administrative procedures. 4.2.10.4 Valves: Valves Designated for review Under the Criteria for Appendix J to 10 CFR 50 These valves were identified by NRC staff during the preliminary meeting for resolving IST comments and are being reviewed by the NRC for applicability to Appendix J Containment boundary criteria. The valves have been included within this program for administrative documentation only. Testing of these valves will be reevaluated upon completion of the NRC review. t I l 4.2-29 Amendment 1 l (December 1980) )}}