ML20094Q230

ASME ISI Valve Testing Program Basis Document, Rev 0

ML20094Q230
Person / Time
Site:	Sequoyah
Issue date:	10/30/1995
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20094P517	List: ML20094P514 ML20094Q176 ML20094Q184 ML20094Q193 ML20094Q197 ML20094Q211 ML20094Q230
References
PROC-951030-02, PROC-951030-2, NUDOCS 9512010098
Download: ML20094Q230 (188)

Text

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ATTACHMENT 2 B38 951031 802 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE1

< ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV0 l

TENNESSEE VALLEY AUTHORITY i

! SEQUOYAH NUCLEAR PLANT

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ASME INSERVICE VALVE TESTING l l

f PROGRAM BASIS DOCUMENT i

1 This document is to be used only for the second ten year inspection interval for ASME Section XI j

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REVISION NO. 0 SUBMITTED BY

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.P GRAM ER APPROVED BY M l v .w2n.c DATE/,-u pr.

ASME SE ON &S IAL PROGRAMS SUPV.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 2 l ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV O REVISION LOG i

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i REVISION DESCRIPTION OF REVISION DATE O Initial Issue 1

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 3 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV O TABLE OF CONTENTS PAGE I. CHARTER - MISSION - OBJECTIVES 4 II. PURPOSE - BASES - HISTORY 5 III. REFERENCES 6 IV. DEbINITIONS 8 V. PROGRAM SCOPE AND PLAN 9 VI. REGULATORY REQUIREMENTS 10 VII. DESCRIPTION 12 VII

I. PROCEDURE

S 18 IX. RESPONSIBILITIES 22 J

X. TRAINING 23 1

APPENDICES APPENDIX A ASME INSERVICE VALVE TEST PROGRAM APPENDIX B: EXPLANATION OF SYMBOLS USED APPENDIX C: DEFERRED TEST JUSTIFICATIONS APPEHDIX Dr RELIEF REQUESTS APPENDIX E; CATEGORY B PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION .

t ATTACHMENTS 1

ATTACHMENT 1: INDUSTRY CONTACTS

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 4 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 I. CHARTER Note: This document has been prepared for the Second Ten Year ASME Section MI Inspection Interval. Positions or commitments regarding the first ten year inspection interval should be based on existing i FSAR, SER, and other system documents. l A. MISSION STATEMENT The ASME Section XI section shall incorporate TVA policies and standards to support safe and reliable operation of Sequoyah Nuclear Plant through the following:

1. Establishing and maintaining a listing of all valves subject to the ASME Section XI Inservice Test Program.

2. Establishing and maintaining the ASME Section XI Inservice Valve test program to ensure the requirements of 10CFR50.55a and Technical Specifications are met.

3. For all cases where ASME valve test requirements are not met, provide a documented relief request with subsequent NRC approval.

4. Developing and implementing an Augmented Valve Test Program.

The Program Engineer and Program Test Engineer shall hold j responsibility, accountability, and authority for accomplishing this mission and maintaining the program. l B. OBJECTIVES The Objectives of the ASME Section XI Inservice Valve Test Program axe as follows:

1. Perform ASME valve tests in accordance with ASME Section XI,

, Subsection IWV, which involks OM-1 and OH-10.

2. Perform Augmented Valve Tests in accordance with 10CFR50, Generic Letter 89-04, and accepted industry standards.

3. Maintain OPERABILITY of applicable valves to support tech spec requirements.

4. Maintain clearly defined responsibilities of organizations involved with valve testing.

5. Maintain applicable procedures, test equipment, and methods to current industry standards or better.

6. No NRC violations due to the ASME or Augmented Valve Testing Program

7. No INPO findings due to the ASME or Augmented Valve Testing Program

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l TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE5 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 II. HISTORY - PURPOSE - BASES J l

ASME setup a committee in 1911 to establish standard rules for the fabrication of steam boilers and other pressure vessel. This committee, now called the Boiler and Pressure Vessel Committee, has also established suggested rules or good practices for inservice inspection / testing. The rules for the inservice inspection / testing for Nuclear Power Plant components are contained in the ASME Boiler and Pressure Vessel Code, Division 1,Section XI. 10CFR50.55a of the federal law and Sequoyah's technical specifications requires that ASME Section XI be met throughout the service life of the nuclear power plant and updated at each 10 year interval.

Under the provisions of 10 CFR 50.55a, inservice testing of safety-related valves will be performed in accordance with a specific edition of Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The interval dates applicable edition and addenda for the first 10 year interval was as follows" First Interval Start Unit 1: 7/1981 First Interval Start Unit 2: 6/1982 Unit 1: 1974 Edition through the Summer 1975 Addenda Unit 2: 1977 Edition through the Summer 1978 Addenda As required by 10 CFR 50.55a (b), the effective edition of Section XI with regard to the second ten year interval is as follows:

Second Interval Start Units 1 & 2: Estimated 12/15/1995 Unit 1 & 2: 1989 Edition (Must be verified to still be in effect 12 months prior to start of interval)

ASME valve tests will be performed in accordance with ASME/ ANSI OM-10 l (OMa-1988 Addenda to the OM-1987 Edition) and ASME/ ANSI OM-1 (OM-1987 Edition) using Generic Letter 89-04 as guidance. This' program identifies the valve inservice testing that will be performed at the Sequoyah Nuclear i Plant to comply with the requirements of 10 CFR 50.55a.

i The safety-related valves that are outside the scope of ASME Section XI, IWV (and therefore outside the scope of 10CFR50.55a) will be tested at a level commensurate with their intended function in the Augmented Test Program per Appendix B. Generic letter 89-04 will be used as guidance for the Augmented Valve Test Program.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 6 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV O III. REFERENCES

1. 10CFE50.55a codes and Standards.

2. NRC Documents

a. Inspection Manual, Temporary Instruction 2515/114, Inspection Requirements for Generic Letter 89-04, Acceptable Inservice Testing Programs.

b. NRC Generic Letter 89-04, Guidance on Developing Acceptable Inservice Testing Programs. April 3, 1989.

c. NRC letter on the " Minutes of the Public Meetings on Generic Letter 89-04 Oct 25, 1989.

d. NRC Draft NUREG 1482, Guidelines for Inservice Testing at Nuclear Power Plants, November 1993

3. Reserved t

4. Reserved

5. CODES and STANDARDS

a. ASME Boiler and Pressure Vessel Code, Division 1,Section XI, 1989 Edition.

b. ASME/ ANSI OM-1, Requirements for Inservice Performance Testing of Nuclear Power Plant Pressure Relief Devices, OM-1987 Edition.

c. ASME/ ANSI OH-10, Inservice Testing of Valves in Light-Water Reactor Power Plants, OMa-1988 Addenda to the OM-1987 Edition.

d. ANSI /ASME N45.2.6-1978, Qualification of Inspection Examination and Testing Personnel for Nuclear Power Plants.

6. TVA Calculation SQN-SQTP-001, ASME Section XI Inservice Code Class Boundaries for the Second 10 Year Interval.

7. TVA Calculation SQN-SQTP-003, ASME Section XI Valve and Augmented Valve Identification for the Second 10 Year Interval.

8. Sequoyah Site Standard Practice SSP-8.6, ASME Section XI Inservice Testing of Pumps and Valves.

9. Sequoyah Nuclear Plant Technical Specifications

10. Sequoyah Nuclear Plant FSAR 6.8

11. Sequoyah Nuclear Plant Design Criteria and Design Guides

a. SQ-DC-V-3.0 Classification of Piping, Pumps, Valves and Vessels.

b. SQ-DC-V-2.16 Single Failure Criteria

c. SQ-DC-V-3.2 Classification of HVAC Systems e

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 7 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0

12. TVA submittals to the NRC Reserved

13. NRC documents to TVA

a. Safety Evaluation Report NUREG-1232 Volume 2,

b. Safety Evaluation Report NUREG-1232 Volume 2, Supplement 1

c. Safety Evaluation Report NUREG-0011 and its Supplements ,

d. Safety Evaluation Report on Sequoyah Inservice Test Program for Pumps and Valves-(IST) April 5, 1985 (L44 850416 402).

4 e. Request for Relief from ASME Boiler and Pressure Vessel Code, Section 4 XI, Inservice Testing Program (TAC 61835, 61836), Oct 23, 1987 (A02 871029 014).

f. Request for Relief from ASME Boiler and Pressure Vessel Code,Section XI, Inservice Testing Program (TAC 61835, 61836), Jan 19, 1988.

g. Request for Relief from ASME Boiler and Pressure Vessel Code,Section XI, Inservice Testing Program - Ultrasonic Flow Measurement (TAC 61835, 61836) - Sequoyah Nuclear Plant, Units 1 & 2. Sept 15, 1988.

h. Request for Relief from ASME Boiler and Pressure Vessel Code,Section XI, Inservice Testing Program - Boric Acid Transfer Pump Flow Rate Measurement (TAC R00479/R00480) - Sequoyah Nuclear Plant, Units 1 & 2.

Mar 23, 1989 (A02 890327 014).

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 8 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 IV. DEFINITIONS

- OPERABLE - OPERABILITY: A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and all necessary attendant instrumentation, controls, a normal and emergency electrical power source, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device t perform its function (s) are also capable of performing their related support function (s).

ASME VALVE TEST PROGRAM: The valve test program required by 10CFR50.55a(f) which delineates the testing requirements of ASME Code Class 1, 2, and 3 valves by using the ASME Boiler and Pressure Vessel Code, Division 1,Section XI. This ASME VALVE TEST PROGRAM is further defined by ASME Section XI, Article IWV, and ASME/ ANSI OM Parts 1 and 10. Those valves that are required in shutting down the reactor to the safe shutdown condition, maintaining the safe shutdown condition, or mitigating the consequences of an accident are to be tested per OH-1 and 10.

AUGMENTED VALVE TEST PROGRAM: The valves that are outside the scope of ASME section XI, IWV (and therefore outside the scope of 10CFR50.55a) but will be testod at a level commensurate with their intended function. The intent of 10CFR50 Appendix A, GDC-1, and Appendix B, Criterion XI is that all components,such as valves, necessary for safe operation are to be tested to demonstrate that they will perform satisfactory in service. Therefore, while 10CFR50.55a delineates the testing requirements for ASME Code Class 1, 2, and 3 valves, the testing of valves is not to be limited to only those covered by 10CFR50.55a. (refer to item 11 of Generic Letter 89-04) 4 h

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l TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE9 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 V. PROGRAM SCOPE & PLAN l l

SCOPE- I ASME Section XI, Article IWA 1000 " Scope and Responsibility" paragraph IWA-1310 calls for the selection of components subject to the inservice ,

program. Article IWV invokes OH-1 and 10. oM-1 and 10 covers those valves 1 and pressure relief devices that are required in shutting down the reactor to the safe shutdown condition, maintaining the safe shutdown condition, or mitigating the consequences of an accident. OH-1 Section 9.0 and OM-10 Section 6.0 requires each valve that is to be tested to be identified and listed in the plants records. Valves subject to testing per 10CFR50.55a and ASME Section XI (OM-1 and 10) are identified in reference 7 and are included within the scope of this program.

PLAN A. The ASME Inservice Valves and Pressure Relief Devices subjected to testing shall be identified, documented, and the selection controlled by reference 7.

B. The ASME Inservice Valve and Pressure Relief Device Tests shall

( be performed in accordance with OM-1 and 10.

C. The ASME Inservice Valve and Pressure Relief Device Tests shall be reviewed and approved by the Program Engineer.

D. The ASME Inservice Valve and Pressure Relief Device Test records shall be maintained in accordance with SSP-8.6 and SSP-2.9.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 10 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV0 j VI. REGULATORY REQUIREMENTS Technical Specification 4.0.5 requires inservice testing of ASME Code Class 1, 2, and 3 components as required by 10CFR50.55a. 10CFR50.55a (f)  ;

requires the inservice testing of ASME Code Class 1, 2, and 3 valves per the 1989 Edition of ASME Section XI. 10CFR50.55a and ASME Section XI Subsection IWV involkes ASME/ ANSI OM-1 and 10 (OMa-1988 Addenda to the OM-1987 Edition). OM-1 requires the testing of pressure relief devices that l are needed for the safe shutdown of the reactor, maintaining safe shutdown, and mitigating the consequences of an accident. OM-10 requires the testing ,

of valves that are needed for the safe shutdown of the reactor, maintaining safe shutdown, and mitigating the consequences of an accident. Therefore ,

the valves and pressure relief devices identified in reference 7 subject to  ;

the OM-1 and 10 test program shall be tested to satisfy 10CFR50.55a I requirements unless specific relief is granted by the NRC.

The valves that are outside the scope of ASME Section XI, IWV (and therefore outside the scope of 10CFR50.55a) are to be tested at a level commensurate with their intended function. The intent of 10CFR50 Appendix l A, GDC-1, and Appendix B, Criterion XI is that all components,such as valves, necessary for safe operation are to be tested to demonstrate that '

they will perform satisfactory in service. Therefore, while 10CFR50.55a delineates the testing requirements for ASME Code Class 1, 2, and 3 valves,  ;

the testing of valves is not to be limited to only those covered by 1 10CFR50.55a. (refer to item 11 of Generic Letter 89-04). These valves will be tested per the Augmented Test Program per Appendix F. Relief is not required from the NRC if testing is not in accordance with OM-10. These pumps are to be tested at a level commensurate with their intended function.

The Type C Containment Isolation valves shall also be subject to the analysis and corrective action of ASME/ ANSI OM-10 (OMa-1988) as required by 10CFR50. 55a (b) (2) (vii) . Containment isolation valves or valve combination shall have a permissible leakage rate specified by the owner. This requirement is handled by the Appendix J containment isolation valve leak ]

test program.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE11 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 RELIEF REQUESTS -

IDENTIFICATION OF CODE NONCOMPLIANCE Technical Specification 4.0.5 (revision needed to reflect Standard Tech specs prior to start of second 10 year interval) and 10CFR50.55a reflect the position that relief requests from impractical code requirements do not have to be granted by the NRC before they are implemented. Relief Requests are to be identified in advance and submitted to the NRC well in advance of their implementation (minimum of 90 days suggested) where possible.

10CFR50.55a recognizes that it will not be possible in all cases to determine in advance that any particular ASME Code requirement is impractical and allows up to a full year after the beginning of an updated interval to inform the NRC and request relief. It is also recognized that, during the interval, certain ASME Code requirements may be identified as impractical due to unforeseen circumstances and relief may be requested at that time. Relief Requests identified during the interval should be submitted to the NRC within approximately two weeks of identification, after completion of the plants review / approval process. The

• review / approval process includes 1) preparation of the Relief Request and incorporation into this program basis document by approval of a revision

hereto, 2) the appropriate 10CFR50.59 reviews for this program basis document revision in accordance with the plants safety Assessment / Safety Evaluation process, and 3) review by PORC and approval of the Plant Manager of the change denote via the 10CFR50.59 evaluation. This methodology will avoid situations whete compliance with the technical specifications cannot be achieved for the period between the time of preparation / review / approval and submittal of a relief request until the NRC has granted the relief.

When noncompliance with a code requirement is identified and testing with technical specification allowable action times is not practical (e.g. test configuration / setup, cold shutdown or refueling required to test, etc.) it may be possible to reference other tests performed in justifying continued operation. A Relief Request or a deferred test justification (cold  ;

shutdown or refueling outage) may be required. The operability of the component could be assessed using the guidance provided in Generic Letter 91-18 which discusses the need for obtaining a Temporary Waiver of Compliance or exigent relief from the ASME Code requirements. Use of the guidance provided by the NRC within ref 2.d should help avoid denial by the NRC. Note that any alternate testing specified by the Relief Request is not to be implemented until authorized by the NRC.

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i TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE12 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 VII. DESCRIPTION Under the provisions of 10 CFR 50.55a, inservice testing of safety-related valves will be performed in accordance with Section XI of the ASME Boiler and Pressure vessel Code and applicable Addenda. As required by 10 CFR 50.55a (b), the effective edition of Section XI with regard to the second ten year interval is the 1989 Edition. ASME valve tests will be performed in accordance with ASME/ ANSI OM-1 (OM-1987 Edition) and OM-10 (OMa-1988 Addenda to the OH-1987 Edition). This program identifies the valve inservice testing that will be performed at the Sequoyah Nuclear Plant to comply with the requirements of 10 CFR 50.55a.  !

The valve test program shall be conducted in accordance with subsection IWV of Section XI of the ASME Boiler and Pressure Vessel Code (applicable Edition and Addenda) except for relief requested under the provisions of 10 CFR 50.55a. Subsection IWV as modified by 10CFR50.55a(b)(2)(viii) invokes OM-1 and 10 for the performance testing of valves and pressure relief devices. Appendix A details the inservice testing program for applicable ASME safety-related valves at Sequoyah Nuclear Plant. Appendix A lists each valve required to be tested and the actual testing to be

, performed in accordance with OH-1 and 10. ,

valve Testino Frecuency ASME Section XI inservice valve testing (in the as found condition where practical) shall be conducted quarterly (at least once every 92 days) except where reduced frequency testing is justified per Appendix C. ,

Specific tests that cannot be performed per Section XI are documented in I the Relief Requests contained in Appendix D. Valve testing shall continue through shutdown periods on operable equipment. Valves that are out of  ;

service are not required to be tested but will be tested prior to returning them to OPERABLE status. Valves in systems out of service for an  !

extended period of time shall be tested within the last 92 days of the l outage or prior to being returned to service. Valves tested during power I ascension due to maintenance performed during the outage shall be  ;

considered inoperable until the post maintenance tests are completed. j The start of the second interval will include all tests that are to be For performed during cold shutdowm and refueling prior to startup.

extended test programs, such as the check valve disassembly and inspection program, credit for similar inspections during the first interval may be taken.

Relief Recuests In the event specific test requirements of 10CFR50.55a and OH-1 and 10 are impractical and cannot be met, specific relief may be granted by the NRC.

Each relief request is identified as to whether it follows the guidance of Generic Letter 89-04, a relief request in the first interval, and/or if it is a new relief request. Relief Requests are to be submitted prior to the start of the second interval where possible, and in any case, by the end of 12 months following the new interval start date in accordance with j 10CFR50.55a(f)(5)(iv). l l

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE13 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 Deferred Test Justifications ]

OM-10 permits the delay of testing from a quarterly frequency to a cold shutdown or refueling frequency. Additionally, OM-10 allows the disassembly of check valves during refueling outages if flow testing cannot be performed. When valves are exercised anytime other than on a  !

quarterly frequency, or when check valve disassembly is performed in lieu of flow testing, justification shall be provided by a Deferred Test Justification. Appendix C contains all associated Deferred Test Justifications. The Valve Test Table contains "CSJ" and "ROJ" numbers for

' Cold shutdown Justifications and Refueling Outage Justifications that are contained within Appendix C. In addition, various tests require the Reactor Coolant Pumps to be removed from service. These tests will be performed similar to the cold shutdown tests and are coded "RCPJ" in Appendix C.

Category AC containment isolation check valves that cannot be verified closed quarterly or during cold shutdown due to lack of remote position indication, inaccessible containment locations or other inaccessible locations, no practical means of verifing check valve closure, possible extension of cold shutdown outages, and/or inability to remove the system from service for testing, will be verified closed during refueling outages via the seat leakage test. This position is in accordance with reference 2.d Section 4.1.3 and these valves have a ROJ in Appendix C. l Valve Exemotions The following types of valves are exempt from the requirements of the ASME inservice test program, as allowed by OM-10 paragraph 1.2, provided they do not perform a specific safety function.

valves used only for operating convenience such as vent, drain, l' instrument and test valves.

valves used only for system control, such as pressure regulating valves.

Valves used only for system or component maintenance. I Valves within external control and protection systems responsible  !

for sensing plant conditions and providing signals for valve operation.

I cold Shutdown Valve Testino For valves in which testing is deferred to cold shutdown, testing will commence within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after cold shutdown is reheived and will continue until all tests are complete or the plant is ready to return to power.

The unit will not be kept in cold shutdown solely to complete cold shutdown testing. Any testing not completed at one shutdown will be performed at subsequent cold shutdowns per the above schedule. For planned shutdowns in which suf ficient time exists to complete the testing of all the valves identified to be tested at cold shutdown, exception may be taken to the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> rule. As a minimum, all cold shutdown valves will be tested each refueling outage, however, valve testing will not be ,

performed at a frequency greater than quarterly for Category A, P, and C l valves. For outages greater than 92 days, all cold shutdown testing shall  ;

i be completed in the last 92 days of the outage. For valves that fail their associated acceptance criteria during cold shutdown testing and 1 which can only be tested at cold shutdown, corrective action shall be l' performed prior to restart.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE14 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 Valves associated with Reactor Coolant Pumo Operation Valves necessary for Reactor Coolant Pump (RCP) operation will be tested during Cold Shutdowns if the RCPs are stopped. The RCPs will not be stopped and then restarted solely to test valves that supply support services to the RCPs. The stopping and starting of RCPs solely to allow valve testing produces unnecessary challenges, wear, stress, and increases the number of cycles on plant equipment. The length of cold shutdown outages may also be extended resulting in undue burden. These valves are coded for a frequency of "RCP" in the valve Test Table on Appendix A. All the rules for Cold shutdown testing applies to the RCP frequency. When the plant is ready for RCP startup to support the plant's return to service, the remaining RCP associated tests need not be completed but will be completed in subsequent RCP out of service periods.

Check Valve Full / Partial Stroke In most cases, rystem design flow through a check valve requires less than full mechanical valve movement. As used in this program, the term full stroke refers to the ability of the valve to pass system design flow or a full mechanical stroke. Any test that verifies less than system design l flow capability or full mechanical movement is considered a partial stroke ,

test. j Safety Position and Testina Recuired The safety position and function of valves is contained within reference

7. The " Testing Required" column of the Valve Test Table in Appendix A denotes the safety position as part of the code for the testing required 4 (e.g. CVC, STO, etc.). These codes are explained in Appendix B. Valves

• with multiple safety positions are exercised to each position.

Valve Position Indicator Verification ]

i Verification of proper remote position indication (OM-10 paragraph 4.1) will normally be accomplished by locally observing the position of the ,

valve and comparing it with the remote indication at least once every two years. Some valves are not equipped with a local means to verify position, therefore, position will be verified by the observation of system parameters such as flow and pressure during valve cycling or by other nonintrusive methods. The remote position indicator in the main control room and the remote position indicator used for valve exercising and stroke timing will be verified for accuracy. For valves having remote position indicator at multiple locations that include the main control room and the main control room indication is used for exercise testing and stroke timing, then only the main control room remote position indicator need be verified for accuracy.

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ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 Fail - Safe Testino l

For fail-safe valves, whereby placing the control switch in the open for j fail-open valves, and the closed position for fail-closed valve, results I in the loss of actuator power, the fail-safe testing requirements of OM-10 i paragraph 4.2.1.6 will be satisfied by the exercise testing required by paragraph 4.2.1.2. ,

1 Establishino Reference Stroke Time Values I For this second 10 year interval, power operated valves will have an initial reference stroke time established by averaging at least 3 stroke  !

times from previous tests to establish a baseline stroke time for comparison to subsequent testing as required by OM-10 paragraph 4.2.1.8.

Subsequent changes to this reference stroke time will be documented in the record of tests.

Stroke Time Tests Power operated valves shall have their stroke time measured while traveling to the position (s) denoted in Appendix A. This position is the automatic response direction or initial response direction for MOVs. MOVs are not stroked timed in both directions of travel (except for DC powered Mova). Other power operated valves are stroked timed to each safety position (open and/or close) as denoted by Appendix A.

The 480 volt three phase AC powered MOVs are exercised in both directions of travel but not stroked timed in both directions since the stroke time is essentially the same in both directions because AC motor actuator speed is mostly dependent on the line frequency. The same components operate within the valve with a phase change to change the direction of valve travel. The ASME valve testing is not performed with any pre-established fluid service conditions (flow, differential pressure, etc.) so the impact of these fluid service conditions on valve stroke time is not reflected in the allowable stroke times. The Generic Letter 89-10 MOV Program is a more comprehensive valve test methodology that considers valve operation and thrust in both directions. The scope of the Generic Letter 89-10 MOV Program includes all of the motor actuated valves that are required for safe operation or safe shutdown of the plant. Therefore, the ASME Inservice Valve Test Program will exercise MOVs in both directions and stroke time test MOVs in the direction most representive of the valve safety function.

Analysis of Valve Leakace Rates Valve leakage rates shall be subject to the analysis and corrective action of ASME/ ANSI OM-10 (OMa-1988). This is also required by 10CFR50. 55a (b) (2) (vii) for Containment Isolation Valves. Category A valves or valve combination shall have a permissible leakage rate specified by the owner. Valves or valve combinations with leakage rates exceeding the permissible rate shall be declared inoperable and either repaired or replaced. A retest demonstrating satisfactory performance shall be performed prior to declaring the valve operable. This requirement is satisfied within the Appendix J program for containment isolation valves.

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 16 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 Thermal Relief Valvag Thermal relief valves and thermal relief check valves of nominal size 1 inch or smaller are excluded from valve testing in so far as their opening function is concerned. The function of these valves to open is to avoid an overpressure condition in isolated components in the event the boundary 4

isolation valves are zero leakage. The likelyhood of zero leakage boundary valves and the failure of the thermal relief valve or thermal l relief check valve to pass any fluid does not warrent inclusion in the test program.

Data Analysis and Evaluation If a valve fails to exhibit the required change of disk position or exceeds the Maximun Allowable Stroke Time, the valve shall be declared inoperable immediately. Valves with measured stroke times which exceed the Calculated Maximun Allowable Stroke Time range (CMAST) shall be 4

immediately retested or declared inoperable. If the valve is ratested and the second set of data also exceeds the CHAST, the data shall be analyzed

! within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> to verify that the new stroke time represents acceptable I

operation, or the valve shall be declared inoperable. If the second set of test data does not exceed the CMAST, then the cause of the initial

deviation shall be analyzed and the results documented in the test record within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.

Subsequent to declaring a valve inoperable and entry into appropriate action statements of technical specifications, the test results may be reviewed and comparied to previous test data to decide if a condition has or has not developed that will further degrade the valve and exceed the safety analysis limit. If the valve is found not in danger of further degradation over an acceptable period of time, an analysis may be an acceptable alternative to valve repair or replacement until such time as

. repairs can be effected, as allowed by the code. If the analysis determines that the valve will soon degrade further, immediate action is required.

The first analysis may be a preliminary analysis (by the Program and/or System Engineers) until particular expertise is available (Vendors, Nuclear Engineering, etc.). The preliminary analysis must establish a basis for meeting the safety analysis limits / licensing basis and must assess the condition of the redundant train. The period the valve can be considered operable based on the preliminary analysis must be determined and limited in the event a more complete analysis determines the valve is inoperable. This period should allow adequate time to perform a thorough engineering analysis beginning without delay.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 17 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 I Check Valve Samole Disassembiv and Insoection Procram j Several check valves in this inservice test progran require disassembly l during refueling outages as an alternate method of verifying check valve '

full-stroke capabilities and operational readiness. To minimize the l

, number of check valves that are disassembled during refueling outages, a  !

check valve sample disassembly schedule and inspection program is implemented. This program complies with the requirements of Generic l Letter 89-04 Position 2 and meets the NRC guidelines set forth within the generic letter. These guidelines are summarized below.

Identical valves shall be grouped and one valve from each group shall be tested during each refueling outage.

Identical valve groups include those valves that are of the same design (i.e. same manufacturer, size, model number, and material ,

of construction); have the same service condition (i.e. water, conf.ensate, steam) and have the same valve orientation (i.e.

borizontially or vertically mounted).

Valve groupings shall not exceed more than four valves per group.

At each disassembly, the full stroke capability being tested shall be verified and the internals inspected to ensure the valve is structurally sound with no loose or corroded parts.

If the disassembled valve is unable to be full stroke exercised, or is binding, or failure of the valve internals is observed (loose or corroded parts), the valve shall be repaired as necessary and the remaining valves in the group shall be disassembled, inspected, and manually full stroked exercised.

i Each valve included in the scope of the sample disassembly and )

inspection program shall be disassembled at least once every eight i years. Any deviation from this interval shall require a revision l to this disassembly and inspection program and Generic Letter 89-  ;

04 Positions 2.a, 2.b, and 2.c shall be addressed and documented  ;

in the record of tests. l j

Aucmented Valve Testino The inservice operability testing of safety-related valves associated with non OH-1 and 10 valve systems are not tested per the ASME inservice test program. These valves as identified in ref 7 are tested per the Augmented valve test program. For example, the inservice operability testing of valves associated with the emergency diesels, are excluded from the ASME valve test program. The fuel oil transfer valves, and lube oil valves are tested per the augmented test program. These components are an integral part of the Emergency Diesel System and are functionally tested by the Diesel tests. Thus, the functional operability testing of these valves are performed at a frequency equal to that required by section XI for valves.

Additionally, the failure of a valve to perform its intended function will be identified by the failure of the associated Emergency Diesel to meet its functional requirements.

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 18 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 VII

I. PROCEDURE

S A. Administratives Sequoyah Site Standard Practice SSP-8.6, ASME Section XI Inservice Testing of Valves and Valves.

B. Summary Listing of Valve Tests - Refer to TVA Calculation SQN SQTP-003.

C. Listing of Valve Surveillance Instructions:

' 0-SI-SXV-001-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-003-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-026-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-030-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-31C-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-032-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-043-256.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-061-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-062-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-063-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-067-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-068-266.0 ASME SECTION XI VALVE TESTING i

l 0-SI-SXV-070-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-072-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-074-266.0 ASME SECTION XI VALVE TESTING 0-SI-SXV-077-266.0 ASME SECTION XI VALVE TESTING i

0-SI-SXV-081-266.0 ASME SECTION XI VALVE TESTING .

0-SI-SXV-090-266.0 ASME SECTION XI VALVE TESTING 1-SI-SXV-000-201.0 FULL STROKING OF CATEGORY A AND B VALVES DURING OPERATION 2-SI-SXV-000-201.0 FULL STROKING OF CATEGORY A AND B VALVES DURING OPERATION 1-SI-SXV-003-219.0 AUXILIARY FEEDWATER CHECK VALVE TEST DURING OPERATION 2-SI-SXV-003-219.0 AUXILIARY FEEDWATER CHECK VALVE TEST DURING OPERATION i l

1-SI-SXV-001-201.0 MAIN STEAM CHECK VALVE TEST DURING SHUTDOWN '

2-SI-SXV-001-201.0 MAIN STEAM CHECK VALVE TEST DURING SHUTDOWN 1-SI-SXV-003-231.0 FEEDWATER CHECK VALVE TEST DURING COLD SHUTDOWN 2-SI-SXV-003-231.0 FEEDWATER CHECK VALVE TEST DURING COLD SHUTDOWN 1-SI-SXV-000-201.1 FULL STROKING OF CATEGORY A AND B VALVES REQUIRED IN ALL MODES 2-SI-SXV-000-201.1 FULL STROKING OF CATEGORY A AND B VALVES REQUIRED IN ALL MODES 1-SI-SXV-000-203.0 FULL STROKING OF CATEGORY A AND B VALVES DURING COLD SHUTDOWN 2-SI-SXV-000-203.0 FULL STROKING OF CATEGORY A AND B VALVES DURING COLD SHUTDOWN

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 19 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 1-SI-SXV-000-203.1 FULL STROKING OF POWER OPERATED VALVES REQUIRED OPERABLE DURING ALL MODES 2-SI-SXV-000-203.1 FULL STROKING OF POWER OPERATED VALVES REQUIRED OPERABLE DURING ALL MODES 0-SI-SXV-000-221.0 FULL STROKING OF THE COMMON ERCW AND CCS CATEGORY A AND B VALVES DURING OPERATION 1-SI-SXV-074-203.2 FULL STROKING OF RHR VALVES 1-FCV-74-1 AND 1-FCV-74-2 2-SI-SXV-074-203.2 FULL STROKING OF RHR VALVES 2-FCV-74-1 AND 2-FCV-74-2 1-SI-SXV-001-202.0 PARTIAL STROKING OF MAIN STEAM ISOLATION VALVES DURING OPERATION 2-SI-SXV-001-202.0 PARTIAL STROKING OF MAIN STEAM ISOLATION VALVES DURING OPERATION i

1-SI-SXV-068-201.0 PRESSURIZER PORV OPERABILITY TEST 2-SI-SXV-068-201.0 PRESSURIZER PORV OPERABILITY TEST 0-SI-SXV-000-206.0 TESTING OF CATEGORY A AND B VALVES AFTER MAINTENANCE OR UPON RELEASE FROM A HOLD ORDER 1-ST-SXV-068-202.0 RCS HEAD VENT VALVE STROKE TEST DURING REFUELING 2-SI-SXV-068-202.0 RCS HEAD VENT VALVE STROKE TEST DURING REFUELING 1-SI-SXV-063-202.0 SAFETY INJECTION HOT LEG SECONDARY. CHECK VALVE INTEGRITY TEST '

2-SI-SXV-063-202.0 SAFETY INJECTION HOT LEG SECONDARY CHECK VALVE INTEGRITY TEST 1-SI-SXV-063-203.0 RESIDUAL HEAT REMOVAL HOT LEG SECONDARY CHECK VALVE INTEGRITY TEST 2-SI-SXV-063-203.0 RESIDUAL HEAT REMOVAL HOT LEG SECONDARY CHECK VALVE r INTEGRITY TEST l

1-SI-SXV-063-204.0 SI/RHR PRIMARY CHECK VALVE INTEGRITY TEST 2-SI-SXV-063-204.0 SI/RHR PRIMARY CHECK VALVE INTEGRITY TEST 1-SI-SXV-063-205.0 SAFETY INJECTION COLD LEG SECONDARY CHECK VALVE INTEGRITY TEST 2-SI-SXV-063-205.0 SAFETY INJECTION COLD LEG SECONDARY CHECK VALVE INTEGRITY TEST I l

1-SI-SXV-063-206.0 RESIDUAL HEAT REMOVAL COLD LEG PRIMARY AND SECONDARY l CHECK VALVE INTEGRITY TEST '

2-SI-SXV-063-206.0 RESIDUAL HEAT REMOVAL COLD LEG PRIMARY AND SECONDARY CHECK VALVE INTEGRITY TEST 1-SI-SXV-063-207.0 SAFETY INJECTION COLD LEG ACCUMULATOR SECONDARY CHECK VnLVE INTEGRITY TEST I l

l TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 20  ;

ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 l 2-SI-SXV-063-207.0 SAFETY INJECTION COLD LEG ACCUMULATOR SECONDARY CHECK '

VALVE INTEGRITY TEST 1-SI-SXV-062-246.0 NORMAL CHARGING LINE CHECK VALVE TEST DURING COLD SHUTDOWN 2-SI-SXV-062-246.0 NORMAL CHARGING LINE CHECK VALVE TEST DURING COLD SHUTDOWN 1-SI-SXV-070-216.0 COMPONENT COOLING SYSTEM CHECK VALVE TEST DURING COLD SHUTDOWN 2-SI-SXV-070-216.0 COMPONENT COOLING SYSTEM CHECK VALVE TEST DURING COLD SHUTDOWN 0-SI-SXV-070-226.0 COMPONENT COOLING SYSTEM CHECK VALVE TEST DURING OPERATION 1-SI-SXV-070-215.0 CONTAINMENT SPRAY CHECK VALVE TEST DURING OPERATION 2-SI-SXV-070-215.0 CONTAINMENT SPRAY CHECK VALVE TEST DURING OPERATION 0-SI-SXV-067-238.0 INSPECTION OF DG ERCW DISCHARGE CHECK VALVES 0-SI-SXV-067-245.0 FULL STROKING OF THE DG ERCW CHECK VALVES 0-SI-SXV-067-237.1 INSPECTION OF DG 1A-A ERCW SUPPLY CHECK VALVES 0-SI-SXV-067-237.2 INSPECTION OF DG 2A-A ERCW SUPPLY CHECK VALVES  !

0-SI-SXV-067-237.3 INSPECTION OF DG 1B-B ERCW SUPPLY CHECK VALVES 0-SI-SXV-067-237.4 INSPECTION OF DG 2B-B ERCW SUPPLY CHECK VALVES i

1-SI-SXV-074-201.0 RESIDUAL HEAT REMOVAL CHECK VALVE OPENING TEST l l

2-SI-SXV-074-201.0 RESIDUAL HEAT REMOVAL CHECK VALVE OPENING TEST j 1-SI-SXV-074-242.0 RHR PUMP CHECK VALVE OPENING TEST 2-SI-SXV-074-242.0 RHR PUMP CHECK VALVE OPENING TEST 1-SI-SXV-063-208.0 SAFETY INJECTION SYSTEM CHECK VALVE OPENING TEST 2-SI-SXV-063-208.0 SAFETY INJECTION SYSTEM CHECK VALVE OPENING TEST l

1-SI-SXV-063-210.0 CHARGING PUMP INJECTION CHECK VALVE OPENING TEST DURIP3 l COLD SHUTDOWN 2-SI-SXV-063-210.0 CHARGING PUMP INJECTION CHECK VALVE OPENING TEST DURING COLD SHUTDOWN 1-SI-SXV-081-227.0 PRIMARY WATER CHECK VALVE TEST DURING COLD SHUTDOWN 2-SI-SXV-081-227.0 PRIMARY WATER CHECK VALVE TEST DURING COLD SHUTDOWN 1

1-SI-SXV-000-204.0 REMOTE VALVE POSITION INDICATION VERIFICATION i 2-SI-SXV-000-204.0 REMOTE VALVE POSITION INDICATION VERIFICATION i

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TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 21 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 D. Listing of Pump Surveillance Instructions that Test Valves

• t SURVEILLANCE INSTRUCTION TRAIN PUMP TESTED 0-SI-SXP-067-201.J A ERCW PUMP J-A 0-SI-SXP-067-201.K A ERCW PUMP K-A 0-SI-SXP-067-201.L B ERCW PUMP L-B 0-SI-SXP-067-201.M B ERCW PUMP M-B 0-SI-SXP-067-201.N B ERCW PUMP N-B 0-SI-SXP-067-201.P B ERCW PUMP P-B 0-SI-SXP-067-201.Q A ERCW PJMP Q-A 0-SI-SXP-067-201.R A ERCW PUMP R-A >

0-SI-SXP-067-202.A A ERCW SCREEN WASH PUMP A-A 0-SI-SXP-067-202.B B ERCW SCREEN WASH PUMP B-B 0-SI-SXP-067-202.C B ERCW SCREEN WASH PUMP C-B 0-SI-SXP-067-202.D A ERCW SCREEN WASH PUMP D-A 0-SI-SXP-070-201.C S CCS PUMP C-S 1-SI-SXP-070-201.A A CCS PUMP 1A-A 1-SI-SXP-070-201.B B CCS PUMP IB-B 2-SI-SXP-070-201.A A CCS PUMP 2A-A 2-SI-SXP-070-201.B B CCS PUMP 2B-B 1-SI-SXP-003-201.A A AFW MD PUMP 1A-A 1-SI-SXP-003-201.B B AFW MD PUMP 1B-B 1-SI-SXP-003-201.S S AFW TD PUMP 1A-S 2-SI-SXP-003-201.A A AFW MD PUMP 2A-A i 2-SI-SXP-003-201.8 B AFW MD PUMP 2B-B i 2-SI-SXP-003-201.S S AFW TD PUMP 2A-S 0-SI-SXP-313-201.A A SDB RM CW PUMP A-A 0-SI-SXP-313-201.B B SDB RN CW PUMP B-B 1-SI-SXP-063-201.A A SIS PUMP 1A-A 1-SI-SXP-063-201.B B SIS PUMP 1B-B 2-SI-SXP-063-201.A A SIS PUMP 2A-A  ;

2-SI-SXP-063-201.B B SIS PUMP 2B-B l 1-SI-SXP-062-201.A A CCP PUMP 1A-A 1-SI-SXP-062-201.B B CCP PUMP IB-B 2-SI-SXP-062-201.A A CCP PUMP 2A-A  !

2-SI-SXP-062-201.B B CCP PUMP 2B-B  !

1 1-SI-SXP-062-202.A 1-SI-SXP-062-202.B A

B BAT PUMP 1A-A BAT PUMP IB-B kI 2-SI-SXP-062-202.A A BAT PUMP 2A-A 2-SI-SXP-062-202.B B BAT PUMP 2B-B 1-SI-SXP-072-201.A A CS PUMP 1A-A 1-SI-SXP-072-201.B B CS PUMP 1B-B 2-SI-SXP-072-201.A A CS PUMP 2A-A 2-SI-SXP-072-201.B B CS' PUMP 2B-B 1-SI-SXP-074-201.A A RHR PUMP 1A-A 1-SI-SXP-074-201.B B RHR PUMP IB-B 2-SI-SXP-074-201.A A RHR PUMP 2A-A 2-SI-SXP-074-201.B B RHR PUMP 28-B

4 TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 22 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV 0 RESPONSIBILITIES

1. Program Engineer (Nuclear Engineering)

Overall Program Ownership

Initiate Design Changes Ensure compliance with existing regulations and standards and update as required Maintenance of Design Basis Calculations, Program Basis Documents, and IST Drawings

2. Program Test Engineer (Technical Support)

Site Contact for all ASME and Augmented Valve testing Initiate maintenance requests based on test results end trends Maintaining state of the art technologies in the program

• Procure services and equipment necessary to perform the valve tests coordinate test schedules with Operating and Outage schedules ,

Coordinate valve tests Prepare appropriate Reports (PERs, Periodic Test Reports)

Review and approve test results i Maintain valve test procedures l Maintain tabulations and trends of valve test results  :

Ensuring periodic tests are performad on schedule Specifing post-maintenance test requirements l Establish and maintain a database of historical data and trend results Ensure compliance with existing regulations and standards and update as require Maintain instrumentation and test equipment necessary to perform valve tests 1

3. Corporate i Preparation and Maintenance of corporate standards {

Interpretation and coordination of ASME Code interpraatations l and application of generic programs Coordinate, review and assist in preparation of request for I

< relief and submittals Periodic assessments of site code programs  ;

4. Others operations shall support the valve tests with valve lineups and equipment operation as required Operations shall perform their portion of the valve test procedures Instrument Maintenance shall provide for calibration of necessary instrumentation The Maintenance organizations shall provide corrective maintenance as neessary i

TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT PAGE 23 ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT REV O X. TRAINING

1. Program Engineer & Program Test Engineer Understanding of valve operation and their application.

Understanding of 10CFR50.55a.

Knowledge of test instrumentation used to perform valve tests.

Knowledge of industry standards ASME Section XI and OM-1 & 10.

2. Test Performers Basic understanding of valve operation and their application.

Understanding of 10CFR50.55a.

Knowledge of test instrumentation used to perform valve tests.

Knowledge of industry standards ASME Section XI and OM-1 & 10.

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. SEQuoYAH NUCLEAR PLANT ASNE INSERVICE TESTING PROGRAM RASIS DOCUMENT APPENDIZ A - ASME INSERVICE VALVE TESTING TABLES PAGE A-1 1

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ASME INSERVICE VALVE TEST TABLES a

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C:\ WINDOWS \JHSFILE\0VALMAS.WPF

sEguoYAE NUCLEAR PLANT AsME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDII A - ASME INSERVICE VALVE TESTING TABLES PAGE A-2 Summarv of Information Provided The following Tables use the format referenced in the 1978 "NRC Staff Guidance for Preparing Pump and Valve Test Program

• Descriptions and Associated Relief Requests Pursuant to 10 CFR 50.55a(g)", the non-mandatory Appendix F "Prreparation of Inspection Plans" of the 1989 Edition of ASME Section XI, and the Draft NUREG 1482 " Guidelines for Inservice Testing at Nuclear Power Plants" November 1993. The following information is provided:

1. System Name and Number

2. Drawing Number

3. Valve Number i

4.'ASME Section XI Classification

5. Drawing Coordinates of Valve

6. Valve Category

7. Valve Size

8. Valve Type

9. Actuator Type

10. Normal Position

11. Testing Required and Frequency per Section XI. Valves are tested to the Safety Position denoted by the applicable test code (e.g. CVO, STC, etc.)

4

12. Relief Request Required

. 13. Alternate Testing

14. Remarks (Including Relief Request Numbers, Specific Valve Data, etc.)

C:\ WINDOWS \JHSFILE\0VALMAS.WPF

SEQUOYAH NUCLEAR PLANT ASNE INSERVICE TESTING PROGRAN BASIS DOCUMENT APPENDIX A - ASNE INSERVICE VALVE TESTING TABLES PAGE A-3 SYSTEM: (1) MAIN STEAM DRAWING NO: 47W801-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AY I AY TT 0S EQ RS NUM8ER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E FSC/CSD **/RO CSJ-1 FCV-1-4 2 C-4 8-ACT 32 GL CYL 0 STC/CSD **lNDIVIDUAL TRAIN SOLENOID TEST PCV-1-5 2 C-2 BC-ACT 6 GA DIA C STC/CSD FSC/CSD CSJ-4 FSC/CSD **/R0 CSJ-1 FCV-t-11 2 E-4 8-ACT 32 GL CYL 0 STC/CSD " INDIVIDUAL TRAIN SOLEN 0!D TEST PCV-1-12 2 D-2 BC-ACT 6 GA DIA C STC/CSD FSC/CSD CSJ-4 FSC/CSD **/R0 CSJ-1 FCV-1-22 2 G-4 8-ACT 32 GL CYL o STC/CSD **lNDIVIDUAL TRAIN SOLENOID TEST PCV-1-23 2 F-2 BC-ACT 6 GA DIA C STC/CSD FSC/CSD CSJ-4 FSC/CSD **/R0 CSJ-1 FCV-1-29 2 A-4 8-ACT 32 GL CYL 0 STC/CSD **tNDIVIDUAL TRAIN SOLENotD TEST PCV-1-30 2 A-2 SC-ACT 6 GA DIA C STC/CSD FSC/CSD CSJ-4 FCV-1-147 2 C-4 8-ACT 2 GL DIA C STC/Q. FSC/Q FCV-1-148 2 E-4 B-ACT 2 GL DIA C STC/0. FSC/0 FCV-1 149 2 G-4 8-ACT 2 GL DIA C STC/0. FSC/0 FCV-1-150 2 A-4 8-ACT 2 GL DIA C STC/0. FSC/Q 1-619* 2 C-2 8-ACT 6 GL M o MSIRO ROJ-18 1-620* 2 E-2 8-ACT 6 CL M 0 MS/R0 ROJ-18 l 1-621* 2 F-2 5-ACT 6 GL M 0 MS/RC ROJ-18 t

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m - M SEQUOYAH NUCLEAR PIJutT ASME INSERVICE TESTING PROGRAM BASIS DOCUMIDIT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-6 SYSTEM: (1) STEAM GENERATOR BLOIOOWN DRAWING NO: 4? L J1-2 C A 0 L D0 C A P R TT VALVE AC RR VA 5 VT C NO TESTING RE EE 5L AD AT I AY TT OS EQ RS NUMBER MA UI LE Z LP UY RI REQUIRED- LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 L0 FT IG E Y R E V 5 E FCV-1-7 2 C-3 5-ACT 2 AN DIA 0 STC/0. FSC/o ,

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SEQUOYAE NUCLEAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDII A - ASME INSERVICE VALVE TESTING TABLES PAGE A-34 SYSTEM: (63) SAFETY INJECTION SYSTEM DRAWING MO: 47WB11-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EO RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E FCV-63 93 2 G-7 B-ACT 8 GA MO O STC/CSD CSJ-21 FCV-63-94 2 G-7 B-ACT 8 GA MO O STC/CSD CSJ-21 FCV-63-95

• 2 B-3 B-PAS 1 GL DIA C RPI FCV-63-96

• 2 C-2 B-PAS 3/4 GL DIA C RPI FCV-63-97

• 2 H-4 B-PAS 3/4 GL DIA C RPI FCV-63-98

• 2 B-2 B-ACT 10 GA MO O ST0/CSD CSJ-32 FSC/CSD FCV-63-107* 2 A-2 B-ACT 1 GL DIA C ST0/CSD CSJ-33 FCV-63-111* 2 H-6 B-PAS 3/4 GL DIA C RPI F CV-63-112* 2 H-6 B-PAS 3/4 GL DIA C RPI FCV-63-115* 2 B-2 B-PAS 1 GL DIA C RPI _

FCV-63-116* 2 C-1 B-PAS 3/4 GL DIA C RPI FCV-63-117* 2 H-1 B-PAS 3/4 GL DIA C RPI FCV-63-113

• 2 B-1 B-ACT 10 GA MO O ST0/CSD CSJ-32 FCV-63-121* 2 E-5 B-PAS 3/4 GL DIA C RPI FSC/CSD FCV-63-127* 2 A-2 B-ACT 1 GL DIA C ST0/CSD CSJ-33 C:\ WINDOWS \JHSFILE\0VALMAS.WPF

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SEQUOYAE NUCLEAR PLANT ASME. INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-37 SYSTEM: (63) SAFETY INJECTION SYSTEM DRAWING NO: 47W811-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT 05 EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI 5 NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E CVP0/CSD9 63-551 1 G-1 AC-ACT 2 CK SA -

CVF0/R0 SLTP/TS ROJ-5 CVP0/CSD9 63-553 1 H-3 AC-ACT 2 CK SA -

CVF0/RO SLTP/TS ROJ-5 CVP0/CSD9 63-555 1 G-3 AC-ACT 2 CK SA -

CVF0/R0 SLTP/TS ROJ-5 CVP0/CSD9 63-557 1 G-2 AC-ACT 2 CK SA -

CVFO/R0 SLTP/TS R0J-5 CVP0/CSD9 63-558 1 E-3 AC-ACT 6 CK SA -

CVFO/R0 SLTP/TS E0J-5 CVP0/CSD9 63-559 1 0-1 AC-ACT 6 CK SA -

CVF0/R0 SLTP/TS ROJ-5 CVP0/CSD9 63-560 1 E-1 AC-ACT 10 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-11 CSJ-23 CVP0/CSD9 63-561 1 0-2 AC-ACT to CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-11 CSJ-23 CVPO/CSD9 63-562 1 D-3 AC-ACT 10 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-11 CSJ-23 C:\ WINDOWS \JHSFILE\0VALMAS.WPF

SEQUOYAE NUCLEAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-38 SYSTEM: (63) SAFETY INJECTION SYSTEM DRAWING No: 47W811-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 L0 FT IG E Y R N V S E CVPC/CSD9 63-563 1 F-2 AC-ACT 10 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-11 CSJ-23 63-577 2 A-8 C 3/4 REL SA C RV/RVF CVP0/CSD 63-581 1 B-7 C 3 CK SA -

CVC/Q. CVF0/R0 ROJ-6 CVP0/CSD 63-586 1 E-1 C 1-1/2 CK SA -

CVC/Q. CVF0/R0 ROJ-6 CVP0/CSD 63-587 1 D-2 C 1-1/2 CK SA -

CVC/Q. CVF0/R0 ROJ-6 CVP0/CSD 63-588 1 0-3 C 1-1/2 CK SA -

CVC/Q. CVF0/R0 ROJ-6 CVP0/CSD 63-589 1 E-2 C 1-1/2 CK SA -

CVC/Q. CVF0/R0 ROJ-6 63-602 3 A-1 C 1 REL SA C RV/RVF l 63-603 3 A-3 C 1 REL SA C RV/RVF 63-604 3 A-4 C 1 REL SA C RV/RVF l 63-605 3 A-6 C 1 REL SA C RV/RVF i CVP0/CSD9 l 63-622 1 C-1 AC-ACT 10 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-7 CVP0/CSD9 j 63-623 1 C-2 AC-ACT 10 CK SA -

Df/DIF SLTP/TS X YES SEE RV-1 ROJ-7 CVPO/CSD9 63 624 1 C-3 AC-ACT 10 CK SA -

Ol/DIF SLTP/TS X YES SEE RV-1 ROJ-7 C:\ WINDOWS \JHSFILE\0VALMAS.WPF

_3 - - - c m .-  % "

SEQUOYAH NUCLEAR PIJutT ASME IN8ERVICE TESTING PROGRAM RASIS DOCUMENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-39 SYSTEM: (63) SAFETY INJECTION SYSTEM DRAWING NO: 47W811-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE A1 ES TN GT R 0 L0 FT IG E Y R N V S E ,

CVP0/CSD9 63-625 1 C-3 AC-ACT 10 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-7 63-626 2 G-7 C 2 REL SA C RV/RVF 63-627 2 G-7 C 2 REL SA C RV/RVF CVP0/CSO9 63-632 1 G-3 AC-ACT 6 CK SA - '

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVPO/CSD9 63-633 1 G-2 AC-ACT 6 CK SA -

Di/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVP0/CSO9 63-634 1 G-3 AC-ACT 6 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVPO/CSD9 63-635 1 G-2 AC-ACT 6 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 63 637 2 F-6 C 3/4 REL SA C RV/RVF CVP0/CSD9 63-640 1 F-4 AC-ACT 8 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVP0/CSD9 63-641 1 F-2 AC-ACT 6 CK SA -

DI/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVPO/CSD9 63-643 1 F-4 AC-ACT 8 CK SA -

Dl/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 CVP0/CSD9 63-644 1 D-2 AC-ACT 6 CK SA Dl/DIF SLTP/TS X YES SEE RV-1 ROJ-8 CSJ-23 C:\ WINDOWS \JHSFILE\DVALMAS.WPF

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SEQUOYAR NUCLEAR PLANT ASME INSERVICE TESTING PROGRAN BASIS DOCIBEENT APPEltDIX A - ASME INSERVICE VALVE TESTING TRRT.ma EWE A-41 ,

SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING No: 4ha65-1  ;

C A' O L D0 C A P R TT ,

VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EO RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE Al ES TN '

GT R 0 LO FT IG i E Y R N Y S E FCV-67-66 3 C-11 S-ACT 6 BUT M0 C ST0/0 FCV-67-67 3 C-7 B-ACT 6 8UT M0 C ST0/0 l

67-50BA 3 C-11 C-ACT 6 CK SA -

CVF0/0.

67-5088 3 C-8 C-ACT 6 CK SA -

CVF0/0.

67-512A 3 C-10 C-ACT 8 CK SA -

CVF0/0. DI/DIF X YES IEB 83-03. DG TEST. SEE RV-1 ROJ-16 67-5128 3 C-9 C-ACT 8 CK SA -

CVF0/0. DI/DIF X YES IE8 83-03. DG TEST. SEE RV-1 ROJ-16 67-517A 3 C-8 C-ACT 8 CK SA -

CVF0/0. DI/DIF X YES IEB 83-03. DG TEST. SEE RV-1 ROJ-16 67-517B 3 C-10 C-ACT 8 CK SA -

CVF0/0. DI/DIF X YES IEB 83-03. DG TEST. SEE RV-1 R0J-16 C:\ WINDOWS \JHSFILE\0VALMAS.WPF

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

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

SEQUOYAH NUCLEAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMEltT APPENDIX A - ASME INSERVICE VALVE TESTING TARYJtS PAGE A-42 STSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING MO: 47W845-2 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY -T T OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 Lo FT IG E Y R N V S E FCV-67-123 3 C-9 8-ACT 24 BUT Mo C ST0/** ROJ-15 FCV-67-124 3 E-8 8-ACT 18 BUT M0 C ST0/** ROJ-15 FCV-67-125 3 C-8 8-ACT 18 BUT M0 C ST0/** ROJ-15 FCV-67-126 3 D-7 8-ACT 18 BUT M0 C ST0/** ROJ-15 FCV-67-146 3 C-7 8-ACT 24 SUT MO O ST0/CSD CSJ-25 0-FCV-67-152 3 C-7 8-ACT 24 BUT MO C ST0/0

• • Full stroke exercise these valves at least once each refueling outage or each time the heat exchanger chemistry requires cleanup /layup operations, but at a frequency not to exceed once per quarter (92 days).

.C:\ WINDOWS \JHSFILE\0VALMAS.WPF

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SEQUOYAE NUCLEAR PIJutT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-47 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING No: 4hS45-4 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE

$L AD AT I AY TT 05 EQ RS NUMBER MA WI LE 2 LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA E0 E TE A1 ES TN GT R 0 L0 FT IG E Y R N V S E 2-FCV-67-176 3 D-7 B-ACT 1-1/2 GA DIA C ST0/0 FSofe No remote indicator 2-FCV-67-182 3 0-9 B-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote indicator 2-FCV-67-184 3 D-7 B-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote indicator 2-FCV 67-1% 3 D-9 B-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote indicator 2-FCV-67-217 3 B-2 B-ACT 2 GA DIA 0 ST0/Q FSO/0 No remote Indicator 2-FCV-67-219 3 B-4 B-ACT 2 GA DIA 0 ST0/0 FSO/0 No remote indicator 2-FCV-67-336 3 A-2 B-ACT 1 CA DIA 0 5T0/3 FSO/G No remote indicator 2-FCV-67-338 3 A-4 B-ACT 1 GA DIA 0 ST0/0 FSO/Q No remote indicator 2-FCV-67-342 3 G-7 B-ACT 2 GA DIA 0 ST0/0 FSO/Q No remote Indicator 2-FCV-67-344 3 G-9 B-ACT 2 GA DIA C ST0/0 FSO/Q No remote indicator C:\ WINDOWS \JMSFILE\0VALMAS.WPF

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SBgDOYAE BRFrm a FLANT ASIE INSEETIS TESTING FROGRAM BASIS DOCEMBET APPENDIX A - ASIE INSERTIG YALVE TESTING TRELES PAGE A-48 SYSTEM: (67) ESSENTIAL RAW COOLING WATER BRANING NO: 4Me65-4 C A + -

O L D0 C A P R TT l' VALVE AC RR VA 5 VT C NO TESTING RE EE SL AD AT I AY TT 05 EO RS .e-MLDSER MA WI LE Z LP UT RI REQUIRED LU NT REMARKS ES IN VG E. VE AP MT IE AI 5 NA EO E TE Al ES TN GT R 0 L0 FT IG E Y R N V

$ E 2-FCV-67-346 3 E-8 S-ACT 1-1/2 GA DIA 0 ST0/0 FSO/G Wo reente indicator 2-FCV-67-348 3 E-9 B-3,EL 1-1/2 CA DIA C ST0/0 FSO/0 No remote indicator - -

2-FCV-67-350 3 E-7 9-ACT 1-1/2 ' GA DIA 0~ ST0/0 PSO/0 No remote indicator' I

2-FCV-67-352 3 E-9 S-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote indicator 2-FCV-67-354 3 F-7 B-AL7 1-1/2 GA DIA 0 $T0/0 FSO/0 No remote indicator 2-FCV-67-356 3 F-9 5-ACT 1-1/2 GA DIA C ST0/0 FSO/G No remote Indicator FSV-32-87

• 3 5-7 B-ACT 1 GA SO C ST/G FSO/S RV-2 YES Wo remote indicator 2-67-1521 3 A-7 C 3/4 REL SA C RV/RVF T

C:\ WINDOWS \JNSFILE\0VALMAS.WPF

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-50 SYSTEM: (67) ESSENTIAL RAW COOLING WATEA DRAWING MO: 47U845-5 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE 2 LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP NT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R 4 V S E 67-743A 3 G-3 C 24 CK SA -

CVF0/Q. CVC/0 PutP TEST 67-7438 3 E-3 C 24 CK SA -

CVF0/Q. CVC/G PUMP TEST 67-744A 3 G-3 C 24 CK SA -

CVF0/0. CVC/0 PUMP TEST 67-7448 3 E-3 C 24 CK SA -

CVF0/Q. CVC/0 Ptpr TEST 67-719A

• 3 6-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES PUMP TEST 67-7198

• 3 C-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES PUMP TEST 67-720A

• 3 8-3 C 2 CK SA -

CVF0/O. CVC/0 RV-5 YES PU r TEST 67-7208

• 3 D-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES Ptsr TEST 67-739A

• 3 F-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES Pu r TEST 67-7398

• 3 D-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES PtstP TEST 67-740A

• 3 G-3 C 2 CK SA -

CVF0/Q. CVC/Q RV-5 YES PUMP TEST 67-7408

• 3 E-3 C 2 CK SA -

CVF0/Q. CVC/0 RV-5 YES PUMP TEST C:\ WINDOWS \JHSFILE\0VALMAS.WPF

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4 SEQUOYAH NUCLEAR PIANT ASME INSERVICE TESTING PROGRAM BASIS DOCINEENT APPENDIX A - ASME INSERVICE VALVE TESTING TABLES PAGE A-51 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO- 47WB45-6 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI 5 NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E 1-FCV-67-162 3 8-7 9-ACT 2 GA DIA O ST0/0 FSO/0 No remote (Micator 1-FCV-67-164 3 8-9 8-ACT 2 GA DIA C ST0/0 FSO/0 No remote IMicator 1-FCV-67-176 3 0-7 s-ACT 1-1/2 GA DIA C ST0/C FSO/0 No remote (Micator 1-FCV-67-182 3 0-9 8-ACT 1-1/2 GA DIA C ST0/Q FSO/0 lo remote (Micator 1-FCV-67-184 3 D-7 B-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote IMicator 1-FCV-67-1P6 3 D-9 s-ACT 1-1/2 GA DIA C ST0/0 FSO/Q No remote (Micator 1-FCV-67-213 3 B-7 B-ACT 1-1/2 GA DIA 0 ST0/0 FSO/0 No remote (Micator 1 - F CV-67-215 3 s-9 8-ACT 1-1/2 GA DIA C ST0/0 FSO/0 No remote IMicator 1-FCV-67-342 3 G-7 s-ACT 2 CA DIA 0 ST0/0 FSO/o No remote (Micator 1-FCV-67-344 3 G-9 B-ACT 2 CA DIA C ST0/0 FSO/0 No remote (Micator l

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S C

SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX B - E%PLANATION OF SYMBOLS USED PAGE B-1 1

APPENDIX B EXPLANATION OF SYMBOLS USED IN THE SEQUOYAH VALVE INSERVICE TESTING PROGRAM

. . This Appendix defines the meaning of all symbols used in the valve test program.. ,

4 1

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF

_.__ _ _ . _ ~ _ ._ . . _ . _ . _ _ .__ _ _ _ . . . . _ .

'SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT  ;

2 APPENDIX B - EXPLANATION OF SYMBOLS USED PAGE 2-2  !

^

i i

SYMBOLS USED TO DESIGNATE VALVE TYPE l

l l

' , VALVE TYPES :

SYMBOL Meaning

< BUT Butterfly BAL Bal!

CK Check DIA Diaphragm  ;

GA Gate -

I GL Globe .

ND Needle I AN Angle PLG Plug ,

RD Rupture Disk .

REL Relief  ;

1 SC_ Stop Check 4

SK Spring Check l 4 l l

Note: TRCV in the Remarks column indicates a Thermal Relief Check

. Valve in a Containment Penetration.

i

(

I 4

1 J -

f L

4 FILE C:\ WINDOWS \JHSFILETOVALSYM.WPF 8

SEQUOY H NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX B - EXPLANATION OF SYMBOLS USED PAGE B-3

\'

SYMBOLS USED TO DESIGNATE VALVE ACTUATOR TYPE 1

P VALVE ACTUATOR TYPES SYMBOL Meaning DIA Diaphragm Air Operator M Manual Operator l

MO Motor Operator i SA Self Actuated SO' Solenoid Operator l

CYL Cylinder / Hydraulic 1 Operator RD - Rupture Disc i.

1 i

)

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF'

SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX B EXPLANATION OF SYMBOLS USED PAGE B-4 SYMBOLS USED TO DESIGNATE VALVE POSITION VALVE POSITIONS SYMBOL Meaning O Own C Closed LO Locked Open LC Locked Closed TH Throttled Valve position determined by other system parameters as in the case of any check valve.

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF

. ~ . . - . - - . -

t 4 ,

i i

SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT l

APPENDIX B - EXPLANATION OF SYMBOLS USED PAGE B-o -

i SYMBOLS USED TO DESIGNATE TESTING REQUIREMENTS i

, i f

i

}t O CATEGORY A OR B VALVES f I l j MS Manual Stroke t j

! i

FSC Fail Safe close actuator test in accordance with OMa-1988, Part  ;

10, Paragraph 4.2.1.6.  !

l4 t*

l FSO Fail Safe open actuator test in accordance with OMa-1988, Part f 10, Paragraph 4.2.1.6.

PST Exercise valve (part stroke) for operability, in accordance with-OMa-1988, Part 10, Paragraph 4.2.1.

l

. RPl This symbol is used only to designate those B-Passive valves that  !

have a remote position indicator that is energized. These valves  !

will be verified that their remote position indicator agrees with the J actual valve position at least once every two years in accordance  !

! with OMa-1988, part 10, Table 1 and Paragraph 4.1. l

SLTJ Perform a Seat Leak Test per 10CFR50 Appendix J, but not less  !

than once every 2 years. Leak rate limits will be estabished by i the licensee in accordance with 10CFR50 Appendix J, and OMa-

l. 1988, Part 10, Paragraph 4.2.2.3(e), (Re: 10CFR50.55a(b)(2)(vii).

! SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications, and OMa 1988, Part 10, Paragraph 4.2.2.3.

ST Exercise valve (full stroke test and without timing) for operability,

in accordance with OMa 1988, Part 10, Paragraph 4.2.1.

STC Exercise valve (full stroke test and time to the close position) for

! operability, in accordance with OMa-1988, Part 10, Paragraph

! 4.2.1. Verified that their remote position indicator agrees with j the actual valve position at least once every two years in t accordance with OMa-1988, part 10, Table 1 and Paragraph 4.1.

i STO Exercise valve (full stroke test and time to the open position) for

operability, in accordance with OMa-1988, Part 10, Paragraph 4.2.1. Verified that their remote position indicator agrees with the actual valve position at least once every two years in accordance with OMa-1988, part 10, Table 1 and Paragraph 4.1 1

i, i

.l I

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF

SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDlX B - EXPLANATION OF SYMBOLS USED PAGE B-6 SYMBOLS USED TO DESIGNATE TESTING REQUIREMENTS (Continued)

CATEGORY C VALVES CVC Exercise check valve to the closed position for operability, in accordance with OMa-1988, Part 10, Paragraph 4.3.2.

CVPO Exercise check valve to the partial open position for operability, in accordance with OMa 1988, Part 10, Paragraph 4.3.2.

CVFO Exercise check valve to the full open position for operability, in accordance with OMa-1988, Part 10, Paragraph 4.3.2.

SLTJ Perform a Seat Leak Test per 10CFR50 Appendix J, but not less than once every 2 years. Leak rate limits will be estabished by the licensee in accordance with 10CFR50 Appendix J, and OMa-1988, Part 10, Paragraph 4.2.2.3(e), (Re: 10CFR50.55a(b)(2)(vii).

SLTP Perform a Seat Leak Test for pressure isolation function as required by Technical Specifications, and OMa-1988, Part 10, Paragraph 4.2.2.3.

RV Test safety and relief valves in accordance with OM-1987, Part 1.

(Re: OMa-1988, Part 10, Paragraph 4.3.1).

DI Disassembly and Inspection per Relief Request RV-1. This includes a full stroke open and close manual exercise test.

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF

SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX B - EXPLANATION OF SYMBOLS USED PAGE B-7 SYMBOLS USED TO DESIGNATE TESTING REQUIREMENTS (Continued)

CATEGORY D RDI Inspection of rupture discs shall be performed in accordance with OM-1987, Part 1. (Re: OMa-1988, Part 10, Paragraph 4.4.2)

RDR Replacement of rupture discs shall be performed in accordance with OM-1987, Part 1. (Re: OMa-1988, Part 10, Paragraph 4.4.2)

FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF 4

SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TtCVING PROGRAM BASIS EDCUMENT e APPENDIXC DEFERREDTESTJUSTIFICATIONS PAGE C-9 CSJ 22 i System: Safety Irdection System '

Valves: 63-510 Class: 2 ,

Category: C-ACT i Function:

Impractical Requirement: Verify closure quarterly. '

Basis for Deferred Test: Exercising (closing) this valve during operation isolates both SIS pump suction 6 t lines from the refueling water storage tank placing the unit in a condition outside the design and licensing basis. .

Alt Testing / Frequency: Verify check valve closure during cold shutdown. Partial stroke exercise ,

. quarterly during the SIP tests and full stroke each refueling outage.

e CSJ-23 l System: Safety Irdection System i Valves: 63-560, 0 -561,63-562, 0 -563, 0 432, 0 433, 0 434, 0 435, 0 440, 0 441, 63- .!

643, 63 4 44 .

Class: 2 Category: AC-ACT l Function: These valves open to allow for RHRP injection and close to pmvent an intersystem LOCA. .l Impractical Requirement: Full or partial stroke quarterly. l

- Basis for Deferred Test: These valves are in the residual heat removal pump injection lines, and RHR j pumps do not develop sufficient head to open the valves during operation. Injection through these lines  ;

using another pump would result in over pressurization of the RHR lines behind the check valves and 4 could cause an undesirable transient in the RCS which could cause a safety injection. In addition, i injection during operation results in thermal fatigue to the branch connections at the RCS. Technical Specifications require these valves to be leak tested following valve actuation or during cold shutdown .

but not more often than once every nine months. Full or partial stroke exercising these valves at a frequency more often than once every nine months would result in additional leak testing requirements without an increase in safety due to the potential for intersystem LOCAs.

Alt Testing / Frequency: Partial stroke exercise during cold shutdown but not more often than dnce every nine months. Leak rate test for pressure isolation function as required by technical specifications. .

Disassemble and inspect during refueling per Relief Request RV-1. j I

i CSJ-24 1 System: Essential Raw Cooling Water System Valves: FCV4743, FCV47-87, FCV47-88, FCV47-89, FCV47-90, FCV47-91, FCV47-95, FCV47-96, FCV47 99, FCV47-103, FCV-67104, FCV-67-105, FCV47106, FCV47-107, FCV-67-111, FCV47112 Class: 2 Category: A-ACT Function: These valves allow cooling flow to lower containment heat removal system and close for containment isolation.

Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: Exercising valve quarterly causes a loss of flow to lower compartment coolers, control rod system drive coolers and reactor coolant pump motor coolers leading to undesirable

' temperature transients inside the various compartments of the Sequoyah ice condenser containment. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke during cold shutdown.

CAWINWORDUHSFILE\VPBDAPPC. DOC

i 4

SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTD'O PRCDRAM BASIS DCCUMENT APPENDIX C DEFERRED TEST JUSTIFICATIONS PAGE C-10 i CSJ 25 System: Essential Raw Cooling Water System Valves: FCV 67-146 Class: 2 Category: B-ACT .

Function: This valve isolates and throttles the ERCW flow through the CCS plate heat exchangers for Train A and loads necessary for continued safe operation of the unit.

Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: Exercising valve quarterly causes a loss of cooling water flow to the CCS plate heat exchangers for Train A and all the loads necessary to support operation of the unit (e.g. RCP oil ,

coolers, RCP thermal barriers, letdown and seal return heat exchangers, and various pump seal coolers. l The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke during cold shutdown.

CSJ 26 System: Reactor Coolant System '

Valves: PCV-68-340A, PCV-68-334, FSV-68-394, FSV-68-395, FSV-68-3%, FSV-68-397 Class:1 Category: B-ACT Function: These valves open to allow for RCS venting /depressurization and close for RCPB isolation.

Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: NRC has requested that pressurizer PORVs and Reactor Vessel Head Vents be tested during cold shutdown rather than during power operation. Stroking these valves at power could result in depressurization of the RCS and resulting unit trip and safety injection. Failure of these valves i I

open could result in a LOCA.

Alt Testing / Frequency: Full stroke during cold shutdown.

CSJ-27 System: Containment Spray System Valves: FCV-72-40, FCV-72-41 Class: 2 Category: B ACT Function: These valves allow flow to the RHR spray headers inside upper containment.

Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: These valves are interlocked with the containment sump valves. Exercising these valves during operation could result in flooding of lower containment or would result in inoperability of both trains of low head safety injection since operation results in less than the required RHR cold leg injection flow capability; placing the unit in a condition outside the design and licensing basis. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

C:\WINWORDUHSFILE\VPBDAPPC. DOC

l

~ SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS IIDCUMENT  ;

APPENDIX C DEFERRED TEST JUSTillCATIONS PAGE C-Il ,

i

. CSJ 28 _

.j System: Residual Heat Removal System l Valves: FCV-74-1, FCV-74-2 )

Class: 2 Category: A-ACT  :

Function: These valves allow flow from the RCS to the RHR system for normal cooldown and during ' i shutdown for removal of decay heat. Dey are opened to provide suction from the RCS for the j Residual Heat Removal pumps when RCS pressure is below setpoint. ney are maintamed closed  :!

during operation to isolate the high press:.:re RCS from the low pressure RHR system.  ;

Impractical Requirement: Full or partial stroke quarterly. j Basis for Deferred Test: . Valves have interlocks to prevent opening them when RCS is above the RHR  ;

design temperature and pressure.. Exercising valve during operation results in over pressurizing RHR.- .i Full stroking of RHR return valves during shutdown isolates decay heat removal capacity, mixing j capacity needed to maintain uniform boron concentration within the RCS, and ability to produce gradual j reactivity changes during boron concentration reductions in the RCS. . It is generally not considered ; j prudent to remove a valve from its safety related position to perform a periodic code test when that .

testing places the unit in an LCO and an overall degraded condition. With respect to these specific jl valves, it is deemed additionally ill-advised in consideration of Unresolved Safety Issues (USI) A 31, i

" Residual Heat Removal Shutdown Requirements" and A-45, " Shutdown Decay Heat Removal l Requirements" which address concerns regarding loss of residual heat removal capability leading to core  !

damage. Reliability of performing beat removal functions is specifically identified as being dependent on i the frequency of events thatjeopardize decay heat removal operations. Alternative testing will provide ,

an acceptable level of quality and safety and the increase in the level of safety by normal testing is not t commensurate with the difficulties or risks involved. Extended outages of greater than 3 months are not  :

normally anticipated. The FCV valve control circuit is not designed for partial stroke capability. j Alt Testing / Frequency: These valves will be full stroke exercised while shutting down (when going on  ;

RHR) if not exercised in the last 3 months or the projected outage duration would cause valves to require  ;

testing prior to startup. If not stroked during shutdown, the surveillance interval expires during outage, i or if outage duration exceeds 3 months, valves need not be exercised until startup when coming off l RHR.

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, CSJ 29

! . System: Residual Heat Removal System  ;

l Valves: 74-514,74-515, 74-554,74-555 j

Class

2 a I

I Category: C Function: These valves open to allow flow from the RHRPs and close to prevent reverse flow through

an idle pump or miniflow competition (e.g. a stronger pump causing a parallel weaker pump to be

j. <leadheaded).

impractical Requirement

Full stroke quarterly.

Pasis for Deferred Test

These valves cannot be full stroked quarterly since the RHR pumps do not i develop enough pressure to overcome normal RCS pressure. The refueling' dewatering line cannot be used because opening HCV-74-34 would cause degradation of both trains of RHR and placing the unit outside the design and licensing basis.

Alt Testing / Frequency: These valves will be part stroked open quarterly during the pump test and full stroked open during cold shutdown, but not more often than once per three months. These valves will be

!- verified closed quarterly, h

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C DEFERRED TEST JUS 11FICATIONS PAGE C 12 CSJ 30 System: Primary Water System i Valves: 81-502  !

Class: 2 l Category: AC l Function: His valve closes for containment isolation. i Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: Exercising this valve results in loss of primary water to the RCP standpipes )

and PRT. Personnel radiation exposures and valve inaccessibility also prohibit exercising these valves )

quarterly. ]

Alt Testing / Frequency: nese valves will be verified closed during cold shutdown. j i

CSJ 31 System: Essential Raw Cooling Water System Valves: FCV47 489, FCV47-492 Class: 3 ,

Category: B-ACT ,

Function: These valves must operate to isolate header ruptures within the ERCW system or a loss of i CCS. I Impractical Requirement: Full or partial stroke quarterly.

Basis for Deferred Test: Exercising these valves results in loss of or diversion of ERCW to/from loads l essential to continued operation of the units. He FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: nese valves will be full stroke exercised during cold shutdown.

CSJ 32 System: Safety Injection System Valves: FCV4347, FCV43-80, FCV43-98, FCV43-118  ;

Class: 2 i Category: B-ACT I Function: nese valves are on the outlet of the SIS cold leg accumulators and are maintained open while l i

the RCS is above 1000 psig. In addition, they will auto open on increasing pressure and on an SI signal if closed. These valves are closed to isolate the accumulator after blowdown following a LOCA and on decreasing RCS pressure during shutdown following a non-LOCA event.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising (closing) this valve quarterly during operation isolates a passive cold leg accumulator placing the unit in a condition outside the design and licensing basis since all 4 accumulators are assumed available for the large break LOCA. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

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SEQUOYAH NUCLEAR PLANT ASME tNSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDDCC DEFERREDTESTNST!F1 CATIONS PAGE C.13 CSJ 33  !

System: Safety Irdection System Valves: FCV-63-63, FCV-63-87, FCV-63-107, FCV-63-127 Class: 2  !

Category: B-ACT Function: Normally closed valve that may be opened to vent nitrogen from the associated cold leg accumulator if unisolated following a LOCA or non-LOCA shutdown.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising this valve quarterly during operation connects an ASME Code Class 2 passive cold leg accumulator with non nuclear code class piping / components. This could cause a loss of the accumulator nitrogen pressure placing the unit in a condition outside the design and licensing basis since all 4 accumulators are assumed available for the large break LOCA. The FCV valve control circuit is not designed for partial stroke capability. i Alt Testing / Frequency: Full stroke exercise during cold shutdown.

I CSJ-34 System: Chemical and Volume Control System Valves: 62-928,62-930 Class: 3 i Category: C-ACT Function: These valves open to allow boric acid flow to the centrifugal charging pumps suction.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Stroking these valves during power operation would cause unacceptable boron transients leading to RCS temperature and power transients which could result in unit trip.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CSJ 35 System: Safety Irdection System Valves: FCV-63-47 Class: 2

. Category: B-ACT Function: Required to close for isolation of passive failure. Required to open for shutdown LOCA and loss of RHR.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising valve during operation results in the loss of two independent trains of {

ECCS and placing the unit in a condition outside the design and licensing basis. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

}

C:\WINWORD\IHSFILE\VPBDAPPC. DOC

SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C DEFERRED TEST JUST!FICATIONS PAGE C-14 APPENDIX C: DEFERRED TEST JUSTIFICATIONS Valves listed below are therein specifically identified by the Licensee as valves which cannot be exercised during power operation, per OM 10 Sections 4.2.1.2 and 4.3.2.2. The table lists the System, Valve Number, Code Class, Basis for Cold Shutdown Testing when the RCPs are stopped for each valve which is being tested on a reactor coolant pump shutdown frequency, and alternate testing / frequency.

He reactor coolant pump shutdown frequency is described in detail in the Description section of this document.

RCPJ 1 System: Chemical and Volume Control System Valves: FCV4241, FCV4243 Class: 2 Category: A-ACT Function: Here valves are in the RCP seal water return path and isolate on a containment isolation signal.

Impractical Requirement: Full or partial stroke exercise quarterly during Reactor Coolant Pump operation.

Basis for Deferred Test: Exercising these valves during RCP operation challenges a seal water return relief valve and could cause loss of seal water return and probable damage to the reactor coolant pump seals. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.

RCPJ-2 System: Chemical and Volume Control System Valves: FCV42-9, FCV42-22, FCV42-35, FCV42-48 Class: 2 Category: B-ACT Function: There valves are in the RCP #1 seal water leakoff return path.

Impractical Requirement: Full or partial stroke exercise quarterly during Reactor Coolant Pump operation. ,

Basis for Deferred Test: Exercising these valves during RCP operation isolates the leakoff from the #1 seal and challenges the #2 seal which could cause damage to the reactor coolant pump seals and a LOCA.

The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.

RCPJ-3 System: Component Cooling System Valves: FCV-70-133, FCV-70-134, FCV-70-87, FCV.?0-90 Class: 3 Category: B-ACT or A-ACT Function: These valves allow flow to the RCP thermal barriers and close for containment isolation and to isolate a thermal barrier flow mismatch (except FCV-70-133 which closes to isolate a thermal barrier flow mismatch only).

Impractical Requirement: Full or partial stroke quarterly during RCP operation.

Basis for Deferred Test: Exercising these valves during operation of the RCP results in loss of cooling water flow to all four reactor coolant pump thermal barrier coolers introducing the possibility of seal failure, loss of a RCP and a LOCA or a unit trip. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.

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- sEQUOYAH NUCLEAR PLANT A$.4E INSERVICE VALVE TESTING PROGRAM BASIS DCTUMENT

- APPENDIX C . DEFERRED TEST JUSTIFICATIONS PAGE C-14 l 1

APPENDIX C: DEFERRED TEST JUSTlFICATIONS Valves listed below are therein specifically identified by the Licensee as valves which cannat be exercised -  ;

during power operation, per OM-10 Sections 4.2.1.2 and 4.3.2.2. The ta' ole lists the System, Valve j Number, Code Class, Basis for Cold Shutdown Testing when the RCPs are stopped for each valve l which is being tested on a reactor coolant pump shutdown frequency, and alternate testing / frequency.

{ The reactor coolant pump shutdown frequency is described in detail in the Description section of this j, document. +

4 t l RCPJ 1  ;

System

' Chemical and Volume Control System  ;

i- Valves: FCV42-61, FCV4243 ,

Class: 2.  ;

Category: A-ACT i

, Function: There valves are in the RCP seal water return path and isolate e . a containment isolation l signal.  ;

Impractical Requirement: Full or partial stroke exercise quarterly during Reactor Coolant Pump l operation. .l*

Basis for Deferred Test: Exercising these valves during RCP operation challenges a seal water return relief valve and could cause loss of seal water return and probable damage to the reactor coolant pump l

seals. 'Ihe FCV valve control circuit is not designed for partial stroke capability. Stopping the RCP's i 2 for testing would increase the wear and stress on the RCP's, increase the number of cycles on other plant equipment, and would extol the length of cold shutdown outages.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped. i i

RCPJ-2 '

I Systan: Chemical and Volume Control System ,

- Valves

FCV42-9, FCV42 22, FCV42-35, FCV42-48 Class: '2  ;

{ Category: B-ACT

, Function: There valves are in the RCP #1 seal water lenkoff return path.

Impractical Requirement: Full or partial stroke exercise quarterly during Reactor Coolant Pump ,

operation.

. Basis for Deferred Test: Exercising these valves during RCP operation isolates the leakoff from the #1 seal and challenges the #2 seal which could cause damage to the reactor coolant pump seals and a LOCA.  ;

5 The FCV valve control circuit is not designed for partial stroke capability. Stopping the RCP's for .i testing would increase the wear and stress on the RCP's, increase the number of cycles on other plant i equipment, and would extend the length of cold shutdown outages.

Alt Testing / Frequency: Full stroke exercise Juring cold shutdown when the RCPs are stopped.  !

l  !

RCPJ 3 [

System: Component Cooling System  :

Valves: FCV-70-133, FCV-70134, FCV-70-87, FCV-70-90 Class: 3

Category: B-ACT or A-ACT ,

Function: 'Ihese valves allow flow to the RCP thermal barriers and close for containment isolation and to isolate a thermal barner flow mismatch (except FCV-70-133 which closes to isolate a thermal l I

barrier flow mismatch only).

l' Impractical Requirement: Full or partial stroke quarterly during RCP operation. j Basis for Deferred Test: - Exercising these valves during operation of the RCP results in loss of cooling l water flow to all four reactor coolant pump thermal barrier coolers introducing the possibility of thermal barrier failure. The FCV valve control circuit is not designed for partial stroke capability. Stopping the  ;

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1 SEQUOYAll NUCLEAR PLANT ASME INSERVICE t/ALVE TESTINO PROGRAM BASIS DOCUMENT ,

APPENDIX C . DEFERRED TEST JUSTIFICA'llONS PAGE C.15 RCP's for testing would increase the wear and stress on the RCP's, increase the number of cycles on other plant equipment, and would extend the length of cold shutdown outages.

' Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.  ;

RCPJ-4 System: Component Cooling Systan Valves: FCV-70140, FCV-70-141, FCV-70-89, FCV-70-92 Class: 3 Category: A-ACT Function: These valves allow flow to the RCP oil coolers and close for containment isolation.

Impractical Requirement: Full or partial stroke quarterly during RCP operation.

Basis for Deferred Test: Exercising these valves during operation of the RCPs results in loss of cooling ,

water flow to all eight reactor coolant pump oil coolers introducing the possibility ofloss of a RCP and a LOCA or a unit trip. The FCV valve control circuit is not designed for partial stroke capability.

Stopping the RCP's for testing would increase the wear and stress on the RCP's, increase the number of i 5

cycles on other plant equipment, and would extend the length of cold shutdown outages.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.

RCPJ 5 Systan: Component Cooling System Valve: 70-679 Class: 2 Category: C-ACT Function: 'Ihis valve allows flow to the RCP thermal barriers and closes for containment isolation.

Impractical Requirement: Full or panial stroke closed quarterly during RCP operation.

Basis for Deferred Test: Exercising this valve during operation of the RCPs results in loss of cooling +

water flow to the reactor coolant pump thermal barriers introducing the possibility ofloss of a RCP seal '

and a LOCA or a unit trip. Stopping the RCP's for testing would increase the wear and stress on the RCP's, increase the number of cycles on other plant equipment, and would extend the length of cold shutdown outages.

Alt Testing / Frequency: Full stroke exercise during cold shutdown when the RCPs are stopped.

)

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SEQUOYAll NUCt. EAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C. DEFERRED TEST JUSTIFICATIONS PAGE C-16 APPENDIX C: DEFERRED TEST JUSTIFICATIONS Valves listed below are therein specifically identified by the Licensee as valves which cannot be exercised during power operation, per OM-10 Sections 4.2.1.2 and 4.3.2.2. The table lists the System, Valve Number, Code Class, Basis for Refueling Ouage Testing for each valve which is being tested on a refueling outage frequency, and alternate testing / frequency.

ROJ 1 System: Chemical and Volume Control System Valve: 62-525,62-532 Class: 2 Category: C Function: These valves open to supply charging pump flow from RWST for safety injection.

Impractical Requirement: Exercise valve quarterly at full flow Basis for Deferred Test: The Centrifugal Charging Pumps cannot be run at full flow during normal operation due to the resulting undesirable temperature transients and boron concentration changes.

Operation of the CCPs during cold shutdown is undesirable due to the inability to letdown that full flow and the potential for cold over pressurization.

Alt Testing: These valves will be verified closed quarterly, part stroked open quanerly and full stroked open refueling.

Frequency for Alt. Testing: These valves will be part stroked quarterly and full stroked refueling.

ROJ 2 System: Chemical and Volume Control System Valve: 62-504 Class: 2 Category: C Function: Opens to admit flow from refueling water storage tank to the centrifugal charging pumps and closes to prevent back flow to RWST during recirculation mode of ECCS.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly.

Basis for Deferred Test: Charging pumps cannot be run at full flow or reduced flow taking suction from the RWST without causing undesirable RCS temperature and/or boron concentration changes resulting in boration and power changes and could result in a plant trip. Full flow cannot be obtained during CSD with Reactor vessel head in place (See V-1) due to the inability to letdown full flow and the potential for cold over pressurization of the RCS.

Alt. Testing: Exercise at full flow at refueling during system performance tests and part stroke at reduced flow during cold shutdown. Exercise valve closed quarterly.

Frequency for Alt. Testing: Full stroke once per refueling and part stroke during cold shutdown (but not more often than once every three months). Exercise valve closed quarterly.

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SEQUOYAlI NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIXC DEFERREDTESTJUSTIFICATIONS PAGE C-17 ROJ-3 ,

System: Safety Injection System Valve: 63-502 Class: 2 Category: C Function: Opens to admit flow from RWST to the RHR pumps during safety injection. Closes to prevent flow to RWST during recirculation mode of ECCS.

Impractical Requirement: Exercise valve quarterly at full flow or partial stroke quarterly.

Basis for Deferred Test: The RHR pumps do not develop sufficient head to pump to the reactor at normal operating pressures. Part stroke exercising is not possible since the pump recirculation flow path does not include this check valve. 'Ibe refueling cavity dewatering line cannot be used because the valve alignment required to use it results in degrading both trains of RHR. Capabilities of the CVCS letdown system preclude use during cold shutdowns. Exercising 63-502 closed during power operations would require closure of FCV-63-1 and inoperability of both trains oflow head -

SIS. i

- Alternate Testing: Exercise at refueling outages during system performance tests. Exercise valve closed t during cold thutdowns.

a Frequency for Alt. Testing: Full stroke once per refueling outage. Exercise valve closed during cold shutdowns (but not more often than once every three months). i ROJ-4 System: Safety Injection System Valve: 63-510  ;

Class: B Category: C

• Function: Opens to admit flow from RWST to the SIS pumps during safety injection. Closes to prevent flow to RWST during recirculation mode of ECCS.

Impractical Requirement: Exercise valve quarterly at full flow.

Basis for Deferred Test: The intermediate head SIS pumps do not develop sufficient head to pump to the RCS at normal operating pressures, and the pump arcirculation line will not pass full pump flow.

RCS letdown capability will not allow pumps to be run at full flow during cold shutdown.

Exercising 63-510 closed during power operations would require closure of FCV-63-5 and inoperability of both trains of SIS, ,

Alternate Testing: Exercise valve at reduced flow once per quarter during SIS pump test and at full flow once per refueling during system performance test. Verify check valve closes during cold shutdowns.

Frequency for Alt. Testing: Part stroke quarterly, full stroke each refueling outage. Exercise valve clomi during cold shutdowns (but not more often than once every three months).

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMEMT APPENDIX C . DEFERRED TEST JUSTIFICATIONS PAGE C-18 ROJ5 System: Safety Injection System Valves: 63-543,63-545, 63-547,63-549, 63-551,63-553, 63-555,63-557, 63-558,63-559.

Class: 1 Category: AC Function: Opens to admit flow from SI pumps to RCS during LOCA and closes to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly. '

Basis for Deferred Test: SIS pumps do not develop sufficient head to overcome normal RCS pressure.

Use of another pump would result in an undesir '.L temperature transient on RCS components.

Letdown capability will not allow full flow testmg with reactor head on.

. Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. The first four '

valves are aligned in parallel in groups of two. Individual branch lines flow is only measured during refueling outage testing since plant instrumentation is not available to measure individual branch flows. Therefore, justification is provided to a!!ow partial stroking of these valves during

• cold shutdown (but not more often than once per nine months) and full stroke exercising during refueling outages.

Valve closure will be verified during cold shutdown, not to exceed once per nine months when the pressure isolation boundary leak test required by Technical Specification 4.4.6.2.2 is performed.

Alternate Testing: Part stroke valves during cold shutdown and full stroke exercise during refueling outages. Leak test as required by Technical Specification 4.4.6.2.2.

Frequency for Alt. Testing: Part stroke every cold shutdown not more often than once per nine months and full stroke each refueling outage. Leak test at the frequencies required by Technical Specification 4.4.6.2.2. ,

ROJ-6 System: Safety Injection System Valve: 63-581,63-586, 63-587,63-588, 63-589 Class: 1 Category: C Function: Open to admit flow from cent, charging pump (s) to the RCS cold legs during safety injection.

Closes for RCPB isolation. i impractical Requirement: Exercise valve on a quarterly basis at full flow or partial stroke quarterly.

Basis for Deferred Test: RCS letdown capacity will not allow full flow injection with the reactor vessel head on. Valve cannot be part stroked without discharging cold, borated water into the reactor.

This would cause an undesirable temperature and boron concentration transients which could result in a safety injection or unit trip. Cold water causes thermal stratification stresses at injection nozzles. The last 4 valves are in parallel and individual branch line flows are only measured during refueling testing since instrumentation is not available to measure the individual branch flows.

Alternate Testing: Part stroke valve (63-581) during cold shutdown and exercise valve at full finw during refueling during system performance tests. Part stroke the combination of parallel valves (63-586, 587,588,589) during CSD and full stroke them during refueling during system performance tests.

Verify check valves are closed quarterly.

i Frequency for Alt. Testing: Part stroke valve during cold shutdown (but not more often than every three months), full stroke once per refueling. Verify check valves are closed quarterly.

C:\WINWORDUHSFILE\VPBDAPPC. DOC

SEQUOYAH NUCLEAR PL. ANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT  !

APPENDIX C - DEFER RED TEST JUSTIFICATION S PAGE C 19  !

ROJ 7 System: Safety injection System' Valve: . 63422,63423,63424,63425

)'

Class: 1 Category: AC Function: Opens to admit flow from cold leg accumulators to the RCS during safety injection and closes l to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly. .

I Basis for Deferred Test: These valves cannot be cycled at full flow without removing the fuel from the core, removing the internals package and decreasing the RCS from above 650 psig to atmospheric pressure in a short period of time. This is an unreasonable burden and could cause damage to the . )

reactor vessel. 'the cold leg accumulators do not have sufficient head so overcome normal RCS  ;

pressure and the use of another pump would cause thermal fatigue to .(CS components.  ;

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation j and during cold shutdown if they have not been leak tested in the last nine months. Therefore, deferred testing is requested to allow partial stroking of these valves during cold shutdown (but not .l more often than once per nine months), so as not to impose additional leak testing requirements.  !

Valve closure will be verified during cold shutdown not to exceed once per nine months when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.

Alternate Testing: Disassemble and inspect one (1) valve each refueling outage on a rotating basis in ,

accordance with Relief Request RV-1.  !

Part stroke exercise using sis or RHR pump and CV test system during CSDs and after  !

i disassembly. l Verify valve closure when the pressure isolation boundary leak test required by SR 4.4.6.2.2 is performed, j Frequency for Alt. Testing: Disassemble and inspect one valve each refueling outage per RV-1. Part j i stroke during CSD (but not more often than once per nine months) and after disassembly. Leak ,

i test as required by SR 4.4.6.2.2.

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SEQUOYAlt NUCLEAR PLANT ASME INSERVICE VALVE TESTINO PROGRAM BASIS DOCUMENT APPENDtX C . DEFERRED TEST JUSTIFICATIONS PAGE C-20 j ROJ-8 System: Safety Injection System Valve: 63-632,63-633,63-634,63-635;63-640,63-641,63-643,63-644. ,

Class: 1 Category: AC Function: Opens to allow flow from RHRPs to RCS and closes to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly.

Basis for Deferred Test: RHR pumps do not develop sufficient head to overcome normal RCS pressure.

Use of another pump would result in an undesirable temperature transient in the RCS and possible reactor trip.

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation and during cold shutdown if they have not been leak tested in the last nine months. The eight i

valves are aligned and stroked in parallel in groups of two. Plant instrumentation is not available to measure individual branch flow rates. Verification of full flow (i.e., assumed flow rate) provides good assurance that both valves have stroked to perform their required safety function.

Therefore, deferred testing is requested to allow full stroking these valves during cold shutdown .l (but not more often than once per nine months). l Valve closure will be verified during cold shutdown (but not more often than once per nine 6 months) when the pressure isolation boundary leak test required by 4.4.6.2.2 is performed.

Disassemble and inspect (1) one RHR cold leg secondary and (1) one RHR hot leg valve each refueling outage in accordance with RV-1.

Altemate Testing: Partial stroke exercise the parallel combination during cold shutdown and after reassemble. Leak test as required by Technical Specification 4.4.6.2.2. Disassemble and inspect I

per RV-1.

Frequency for Alt. Testing: Partial stroke exercise during cold shutdown (but not more often than once ,

per nine months) and after disassembly. Leak test at the frequencies required by Technical l Specification 4.4.6.2.2. Disassemble and inspect one valve from each group every refueling  ;

outage per RV-1. J i

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SEQUOYAff NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C DEFERRED TEST JUSTIFICATIONS PAGE C-21 ROJ-9 Systern: Containment Spray -

Valve: 72-547, 72-548, 72-555, 72-556 Class: 2 t

- Category: C Function: Opens to admit flow from the containment spray and RHR pumps to the spray headers.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly. -

Basis for Deferred Test: Testing these valves with water (full or panial stroke) will deluge the containment. Testing with air could cause an SI, unit trip, and containment isolation signal from high containment pressure.

l Alternate Testing: Disassemble and inspect one (1) valve each refueling outage on a rotating basis per -

RV-1. These valves cannot be partial stroked after disassembly.

Frequency for Alt. Testing: Disassemble and inspect one valve each refueling outage per RV-1 l

- ROJ System: Safety hdection System j Valve: 0 -524,63-526 .,

Class: 2 6

Category: C Function: Opens to admit flow from SIS pumps to RCS during LOCA. Closes to prevent flow through idle pump. t Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly.  ;

Basis for Deferred Test: SIS pumps do not develop sufficient head to pump to the RCS during normal operation. i Alt. Testing: Part stroke valves during cold shutdown and full stroke exercise valves during refueling. ,

Verify valve closed quarterly during pump test.

Frequency for Alt. Testing: Verify closed quarterly, part stroke during cold shutdown (but not more often than once per nine months) and full stroke during refueling.

ROJ 11 j System: Safety Irdection System  ;

Valve: 63-560,63-561, 63 562,63-563 Class: 1 i

. Category: AC

. Function

Opens to admit flow from cold leg accumulators, safety injection pumps, and RHR pumps to  !

l the RCS cold legs during safety injection and close to prevent intersystem LOCA.

Impractical Requirement: Exercise quarterly at full flow or partial stroke quarterly. ,

Basis for Deferred Test: 'Ihese valves cannot be exercised at full flow without removing the fuel from the core, removing the internals package, and decreasing the RCS from above 650 psig to atmospheric pressure in a short period of time. This is an unreasonable burden and could cause damage to the  :

reactor vessel. These valves cannot be partial stroked during operation since the RHRPs/ SIPS / Cold

[

j Leg Accumulators do not have sufficient head to overcome RCS pressure. "

Technical Specification 4.4.6.2.2 requires these valves to be leak tested following valve actuation l i and during CSD if they have not been leak tested in the last nine months. Therefore, relief is requested to allow partial stroking of these valves during CSD not to exceed once per nine months i- so as not to impose additional leak testing requirements.  :

Alt. Testing

Disassemble and inspect one valve each refueling outage on a rotating basis per RV-1. [

Part stroke exercise using RHR pump during CSDs and after disassembly. ['

Verify valve closure when the pressure isolation boundary leak test required by SR 4.4.6.2.2 is I

performed.

Frequency for Alt. Testing: Disassemble and inspect one valve each refueling outage per RV-1. Parts  ;

stroke during CSD not to exceed once per nine months and after disassembly. Leak test at the frequencies required by Technical Specification 4.4.6.2.2.

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. sEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESUNO PROGRAM BASIS DOCUMENT APPENDIX C DEFERRED TEST JU5HFICATIONS PAGE C-22 i

J- 5

~

ROJ 12 Systesn: Reactor Coolant System Valve: '68-559 '

- Class: 2

Category

C Function: Opens to admit SIS and CS relief valve discharge to the PRT. _

. Impractical Requirement: Exercise quarterly at full flow, partial stroke quarterly, or exercise during cold shutdown.

1 Basis for Deferred Test: Full flow exercising, by definition, is not possible due to the nature of the system. Partial stroke exercising would present unacceptable hazards unless all interacting systems ,

were removed from service; these systems include RCS, CVCS charging / seal flow / letdown, RHR, SIS, and CS systems. Removal from service of both trains of the affected systems would require entry into LCOs and an overall degraded plant condition beyond the design /licenamg basis,

! regardless of operating mode. Plant operating experience has shown that this CV does function to

provide release to the PRT as indicated by PRT temperature, pressure, and level increases.

Alt. Testing: Disassemble and inspect per RV-1. This valve cannot be part stroke exercised after .t disassembly.

Frequency for Alt. Testing: Every third refueling outage. In the event of unacceptable indications, test at l the next refueling outage.

ROJ-13 System: Reactor Coolant System Valve: FSV-68-394, FSV-68-395, FSV-68-3%, FSV-68-397 i Class: 2.

Category: B j Function: Operates to provide a reactor vessel head vent path; to vent non-condensable from head during an accident to promote natural circulation and prevent gases from impeding reactor coolant circulation flow through the core.

4 Impractical Requirement: Exercise valve quarterly and during cold shutdown (full or partial). Refer to RV 2 also. [

Basis for Deferred Test: These valves are Target Rock valves (similar to the pressurizer PORVs)  !

< and have a probability of sticking open. Inappropriate or inadvertent operation of this system 1 (resulting from valves sticking open) could create an unanalyzed condition or worsen the severity 1 of an analyzed faulted condition. Due to the risk of stroking these valves, the licensee requests relief to exercise these valves at refueling outages only. (

l Alt. Testing: Full stroke exercise at refueling outages. See RV-6 for additional details on FSV-68-396 l

and -397.

5 Frequency for Alt. Testing: Every refueling outage.

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4 SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTINO PRCT., RAM BASIS DOCUMENT

- APPENDIXC DEFERREDTESTJUST1FICAT10NS PAGE C-23 ROJ 14 Systan: CVCS

. Valves: 62-560,62-561, 62-562,62-563, 62-576,62-577, 62-578,62-579 i

, Class: 1 i Category: C Function: Opens to admit flow to RCP seals and closes to prevent RCS back flow (intersystem LOCA) and containment integrity (62-560,62-561, 62-562,62-563).

4 Impractical Requirement: Verify closure quarterly or during cold shutdown (full or partial stroke).

Basis for Defened Test: 'Ibese valves cannot be exercised closed without terminating seal flow to the 4

RCPs, depressurizing and draining down the RCS. This is not normally done unless the plant is in 4 mode 6 and testing the valves during operation results in ' hardship and unusual difficulty without a co-- ;-- -Hag increase in the level of quality and safety " For these reasons, justification is provided to allow stroking of these valves to the closed position during refueling.

. Alternate Testing: Verify valves full open quarterly and full stroke exercise to the closed position during  ;

4 mfueling outages.

]- ' Frequency for Alt. Testing: Each Refueling Outage. ,

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5 ROJ 15 System: Essential Raw Cooling Water System (ERCW) j Valves: FCV47123, FCV47-124, FCV47-125, FCV47126 Class: 3

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Category: B-Active Function: Open to provide ERCW cooling water flow to the containment spray heat exchanger shell side.

Impractical Requirement

Exercise valve on a quarterly basis (full or partial stroke).

i Basis for Deferred Test: The raw water of the ERCW system contains chlorides which cm cause heat

. exchanger tube pitting, and organisms which can produce micro biologically induced -orrosion in l the heat exchanger piping and shell. To preserve their integrity, these heat exchangers are placed

! in wet lay-up with demineralized water and corrosion inhibitors, and their chemistry is monitored.

Whenever the chemistry specifications are exceeded, the heat exchangers are drained, flushed, and again placed in lay-up.

i During modes 1, 2, 3, and 4, Technical Specification 3.6.2.1 requires that the plant maintain two independent Containment Spray Systems operable or enter an LCO. When a containment spray heat exchanger is drained during the cleanup / lay-up operation, that containment spray loop is declared inoperable placing the urat in an LCO.

Chemistry data demonstrates that the quarterly cycling of the inlet and outlet heat exchanger valves .

increases the intrusion of raw water, thus forcing the plant to enter the LCO more often to preserve ,

j the integrity of the heat exchangers.

Alt Testing: Full stroke exercise these valves as required on an alternate frequency.

. Frequency for Alt. Testing: Full stroke exercise these valves:

1. at least once each refueling outage

2. each time the heat exchanger chemistry requires cleanup / lay-up operations, but at a frequency not to exceed once per quarter.

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I SEQUoYAll NUCLEAR PIANT ASME INSERVICE VALVETESTINO PROGRAM BASIS DCCUMENT APPENDIX C DEFERRED TEST JUSTIFICATIONS PAGE C-24 ROJ 16 System: Essential Raw Cooling Water System (ERCW)

Valves: 67-512A,67-512B,67-517A,67 517B Class: 3 Category: C-Active Function: Open to provide ERCW cooling water discharge form the DG coolers and closes to prevent flooding of the DG building in the event of a break upstream of the check valve.

Impractical Requirement: Exercise valve closed on a quarterly or cold shutdown basis (full or partial stroke).

Basis for Deferred Test: These valves are part of the IE Bulletin 83-03 program for disassembly and inspection. A meaningful closure test is not possible on a quarterly basis due to the inability to provide sufficient back pressure for check valve closure.

Alt Testing: Disassemble and inspect per RV-1 Frequency for Alt. Testing: Each refueling outage per RV-1 ROJ 17

. System: Auxiliary Feedwater System Valves: 3 891, 3-892 Class: 2 Category: C-ACT Function: These check valves are located in the individual steam lines supplying the AFWP turbine.

The safety function in the open position is to allow steam flow to the pump turbine. Additionally, the valves must be capable of closure to prevent blowdown of the adjacent steam generator due to a line fault occurring upstream of the valve.

Impractical Requirement: Full stroke exercise quarterly.

Basis for Deferred Test: Full stroke exercising these valves during power operation could result in severe thermal shock to the auxiliary feedwater nozzles and cause SG level transients and a unit trip. Full exercising these valves to the closed position during normal plant operation would require closing the upstream motor operated valve and depressurizing between the closed valve and the check valve being tested. This is not possible because of the inability to depressurize due to the lack of vents or drains located within the isolated boundary. The use of an outside pressure source to overcome the SG pressure l is not practical due to the high pressure involved. Additionally, isolation of both the SG 1 and 4 steam l supply lines will result in the loss of all AFW for the loss of all AC power event. Exercising during cold )

shutdown would require the use of an outside air or nitrogen pressure source to exceed the SG pressure. j This method is undesirable due to the energy involved and the personnel hazards. Also, this method 1

provides minimal assurance of valve reliability and operational readiness.

Alt Testing / Frequency: These valves will be part stroked during the associated pump test and full l i

stroked during hot shutdown or hot standby (but not more often than once per three months). These valves are in the check valve disassembly program to satisfy the recommendations of SOER 86-03. 3-891, 3-892 will be disassembled and inspected per the disassembly and inspection program (one valve each refueling outage per RV 1) to satisfy the check valve closing test. ,

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE tfALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C . DEFER RED TEST JUSTIFICATIONS PAGE C-25 -

ROJ 18 System: Various Systems Valves: All "B-ACT" Valves with an " Actuator Type" of "M' in Appendix A - ASME Inservice Valve Testing Tables (approximately 32 valves per unit and 9 common valves) 1 619, 1-620, 1-621, 1-622 62-929,62-932, 62 944 l 67-543A, 67-543B, 67 544,

'70-531,70-540, 70-542, HCV 74-36, HCV-74-37,74-520, 74-521,74-530, 74-531 78-513 Class: 2 or 3 Category: B-ACT Function: These valves are manual valves subject to local handwheel operation only.

Impractical Requirement: Full or partial stroke exercise quarterly or cold shutdown.

Basis for Deferred Test: These valves are only operated locally in the plant via the manual handwheel. '

Access to the valve requires entry into remote areas of the plant where 1) extreme environmental conditions exist (e.g. main steam valve vault upper elevations where the ambient temperature is excessive), 2) nreas where personnel radiation exposure challenges the ALARA approach (e.g. CVCS blender arc 4 on elevation 690), 3) valve operation causes a change in the system flow path that cannot be tolerp ed due to the lengt!' -f time required for the manual handwheel stroke exercise (e.g. CCS pump ,

isoLtion valves and ERC ' > det of the CCS heat exchangers), 4) valve operation causes an alignment that places the system in a configuration that is outside the design / licensing basis (e.g. RHR heat exchanger bypass valves and letdown to CVCS path), and 5) administrative controls such as unlocking a normally locked valve must be bypassed in order to exercise the valve (e.g. RHR pump discharge).

Exercising these valves during cold shutdown is not practical due to the length of time necessary to stroke the valves may extend the outage creating undue burden. Since these valves are simple manual valves without the complex power operators and are used infrequently in the course of operation, quarterly or cold shutdown exercising is not necessary to ensure a degree of operational readiness commensurate with their safety ftmetion. Quarterly exercising would, in essence, result in over testing the valve and causing unwarranted degradation, above that normally expected, due to the infrequency of use. t Alt Testing / Frequency: These manual valves will be full stroke exercised during refueling.

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l SEQUOYAll NUC1. EAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS EDCUMENT ,

APPENDIX C DEFERRED TEST JUSTIFICATIOidS PAGE C-36  !

ROJ 19 System: Chemical and Volume Control System l Vaives: 62-523,62-530 Class: 2 Category: C-ACT Function: Opens for miniflow path for its associated CCP and closes to prevent reverse flow through its idle CCP.

Impractical Requirement: Full stroke exercise quarterly.

Basis for Deferred Test: Verification that this valve strokes full open quarterly is not possible because flow instrumentation is not available on the CCP miniflow lines. The installation of extemal flow t measurement devices quarterly or during cold shutdown is an excessive burden and increases personnel radiation exposure. 'Ihese valves are tested quarterly in the CCP tests and an acceptable quarterly CCP miniflow test in accordance with OM-6 provides confidence that these check valves have been exercised to the extent necessary for them to perform their safety function.

Alt Testing / Frequency: Partial stroke open quarterly and verify closure quarterly during the associated CCP tests. Full stroke open during refueling with the miniflow line instrumented with an extemal flow ,

measurement device. i 6

t ROJ 20 System: Auxiliary Feedwater System ,

Valves: 3-861, 3-862, 3-921, 3-922 Class: 2 Category: C-ACT Function: These check valves are located in the AFW lines supplying SGs 2 and 3. The safety function in the open position is to allow AFW flow to the SGs. Additionally, the valves must be i capable of closure to prevent blowdown a steam generator into the Reactor Building annnulus due j to a line fault occurring upstream of the check valves in the annulus.

- Impractical Requirement: Full stroke exercise quarterly. ,

Basis for Deferred Test: Full stroke exercising these valves during power operation could result in severe thermal shock to the auxiliary feedwater nozzles and cause SG level transients and a unit trip. Full 4

exercising these valves to the closed position during normal plant operation would require entry into containment, operation of manual containment isolation valves violating containment integrity, and depressurizing upstream of the closed valve. The test of the outboard check valve requires an outside  !

pressure source to pressurize between the series check valves. This pressure source would have to be  :

qualified for SG pressure conditions. The use of an outside pressure source to overcome the SG pressure '

is not practical due to the high pressure involved and the resulting personnel hazards involved.

Alt Testing / Frequency: These valves will be full stroked during hot shutdown or hot standby (but not more often than once per three months). These valves are in the check valve disassembly program to satisfy the recommendations of SOER 86-03, 3-891, 3-892 will be disassembled and inspected per the disassembly and inspection program (one valve each refueling outage per RV-1) to satisfy the check valve closing test.

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALifE TESTING PROGRAM BASIS DOCUMENT l APPENDDC C . DEFERRED TEST JUSTIFICATIONS PAGE C 27 -l

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ROJ-21 )

System: Auxiliary Feedwater System ,

Valves: 3-830, 3 4 31, 3-871, 3-872  ;

Class: 2 l Category: C-ACT Function: - Dese check valves are located in the AFW lines supplying SGs 2 and 3. The safety )

function in the open position is to allow AFW flow to the SGs. Additionally, the valves must be  !

capable of closure to prevent reverse flow through an idle pump.

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- Impractical Requirement: Full stroke exercise quarterly.

Basis for Deferred Test: Full stroke exercising these valves during power operation could result in severe i thermal shock to the auxiliary feedwater noules and cause SG level transients and a unit trip. Full ,

exercising these valves to the closed position during normal plant operation would require an outside 1

- pressem source to pressurias between the series check valves and the check valve being tested. This l pressure source would have to be qualified for SG pressure conditions. He use of an outside pressure source to overcome the SG pressure is not practical due to the high pressure involved and the resultag j personnel hazards involved.  ;

Alt Testing / Frequency:. These valves will be full stroked during hot shutdown or hot standby (but not j more often than once per three months). Dese valves are in the check valve disassembly program to  !

satisfy the recommendations of SOER 86-03 and will be disassembled and inspected per the disassembly  !

and inspection program (one valve each refueling outage per RV-1) to satisfy the check valve closing .

test. j ROJ-22 l System: Component Cooling Systesa l Valves: 70-681 A, 70-681B, 70481C, 70-681D, 70-682A, 70-682B, 70-682C, 70-682D  ;

- Class: 3 Category: C i Function: These valves allow flow to the RCP thermal barriers and close for isolation of a thermal barrier breach. [

Impractical Requirement: Full or partial stroke closed quarterly. ,

Basis for Deferred Test: Exercising these valves during operation of the RCPs results in loss of cooling .;

water flow to the reactor coolant pump thermal barriers introducing the possibility ofloss of a RCP t thermal barrier. Stopping the RCP's for testing would increase the wear and stress on the RCP's, increase the number of cycles on other plant equipment, and would extend the length of cold shutdown j outages.

Alt Testing / Frequency: Verify full open capability quarterly. These valves will be disassembled and  !

inspected per the disassembly and inspection program (one valve each refueling outage per RV-1) to i satisfy the check vA:' closing test. i i

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-1 SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDDC D.REUEF REQUESTS PAGE D 1 )

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APPENDIX D: RELIEF REQUESTS i

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VAUIE TESTINO PROGRAM BASIS DOCUMENT APPENDIX D. REUEF REQUESTS PAGE D-2 RELIEF REQUEST RV-1 CHECK VALVE DISASSEMBLY AND INSPECTION Systan: Safety IWection Systen Valve Group # 1: 0422,0423,63424,63425 Class: 1 Category: AC Function: Opens to admit flow from cold leg accumulators to the RCS during safety injection and closes to prevent intersystem LOCA.

System: Safety IWection System Valve Group #2: 0 -560,63-561, 63-562,63-563 Class: 1 Category: AC Function: Opens to admit flow from cold leg accumulators, safety injection pumps, and RHR pumps to the RCS cold legs during safety injection and close to prevent intersystem LOCA.

System: Containment Spray Valve Group # 3: 72-547,72-548,72-555,72-556 NOTE: This valve group consists of two pairs of identical valves. 'Ihe two pairs are not all the same size but constituted an approved Relief Request (PV-

10) in the first 10 interval. Thisjustification remains valid since these valve are in the same inaccessible location (upper contamment dome) and remain passive through out the fuel cycle.

Class: 2 Category: C Function: Opens to admit flow fron *he containment spray and RHR pumps to the spray headers. Close for containnunt isolation.

Systan: Upper Head IWection System Valve Group # 4: SYSTEM DELETED - NOT USED System: Safety Idection System Valve Group # 5: 63432,0433,0434,0435; Valve Group # 6: 0440,63441,63443,63444.

Class: 1 Category: AC Function: Opens to al'.ow flow from RHRPs to RCS and closes to prevent intersystem LOCA.

System: Reactor Ccolant System Valve Group 7: 68<iS9 NOTE: This valve is grouped by itself and will be disassembled and mspected every third refueling outage. This was an approved relief request (PV-17) in the first 10 year interval. Additionally, in the event of unacceptable indications, the valve will be restored to an acceptable condition and retested at the next refueling outage.

Class: 2 Category: C Function: Opens to admit SIS and CS relief valve discharge to the PRT.

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX D. RELIEF REQUESTS PAGE D 3 System: ERCW Valves Group #8: 67-512A,67-512B,67-517A,67 517B Class: -3 Category: C-Active  ;

Function: Open to allow ERCW discharge from the DG and close t i prevent flooding of the DGB on a line break.

System: Auxiliary Feedwater System Valve Group #9: 3491, 3492 Class:2 ,

Category: C-ACT Function: nese check valves are located in the individual steam lines supplying the AFWP turbine.

The safety function in the open position is to allow steam flow to the pump turbine. Additionally, the valves must be capable of closure to prevent blowdown of the adjacent steam generator due to a line fault occurring upstream of the valve.

System: Component Cooling System Valve Group #10: 70 681A, 70-681B, 70-681C, 70481D, Valve Group #11: 70-682A, 70482B, 70482C, 70482D l Class: 3 Category: C Function: These valves allow flow to the RCP thermal barriers and close for isolation of a thermal barrier breach.

System: Auxiliary Feedwater System Valve Group #12: 3 461, 3 462, 3-921, 3-922 Class: 2 Category: C-ACT Function: nese check valves are located in the AFW lines supplying SGs 2 and 3. The safety function in the open position is to allow AFW flow to the SGs. Additionally, the valves must be capable of closure to prevent blowdown a steam generator into the Reactor Building annulus due to i a line fault occurring upstream of the check valves in the annulus. j System: Auxiliary Feedwater System .

Valve Group #13: 3-830, 3431, 3471, 3472 l Class: 2 Category: C-ACT Function: These check valves are located in the AFW lines supplying SGs 2 and 3. The safety function in the open position is to a!!ow AFW flow to the SGs. Additionally, the valves must be capable of closure to prevent reverse flow through an idle pump.

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT

!- APPENDDCD RELIEFREQUESTS PAGE D-4 l l

i Impractical Requirement: OM-1, Section 4.3.2.l; Exercising Test Frequency - Exercise every 3 months f Basis for Relief: In Generic Ietter 89-04 Position 2, the NRC staff established a position reguarding valve disassembly and inspection as an approved alternate method to be used as a means of determming that a valve disc will full stroke exercise open or of verifying closure capability. When direct or indirect methods of exercising check valves are not available or when it is impractical to demonstrate opemog or closing capabilities by other means, the disassembly and inspection method will be used to fulfill the msorvice testing requirements. Several check valves in this inservice test program require disassembly during refueling outages as an alternate method of verifying check valve full-stroke capabilities and j l'

operational readiness. To minimize the number of check valves that are diseasembled during refueling .

outages, a check valve sample disassembly schedule and inspection program is implemented. This

program complies with the requirements of Generic letter 89-04 Position 2 and meets the NRC guidelines set forth within the generic letter. These guidelines are summarized below. i 4

e Identical valves shall be grouped and one valve from each group shall be tested' f during each refueling outage.

J e . Identical valve groups include those valves that are of the same design (i.e. same j i

manufacturer, size, model number, and material of construction); have the same service condition (i.e. water, condensate, steam) and have the same valve {

i orientation (i.e. horizontally or vertically mounted). l 1

4 Valve groupings shall not exceed more than four valves per group. l

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F e At each disassembly, the full stroke capability shall be manually verified and the ]

internals inspected to ensure the valve is structurally sound with no loose or corroded parts, i I .

l 4 If the disassembled valve is unable to be full stroke exercised, or is binding, or l I

failure of the va!ve internals is observed (loose or corroded parts), the valve shall be repaired as necessary and the remaming valves in the group shall be disassembled,

_ inspected, and manually full stroked exercised.

4 e Each valve included in the scope of the sample disassembly and inspection program j

!' shall be disassembled at least once every eight years. Any deviation from this +

l interval shall require a revision to this disassembly and inspection program and Generic letter 89-04 Positions 2.a,2.b, and 2.c shall be addressed and documented 1 l

in the record of tests.

Alt Testing: When practical, partial valve stroking quarterly or during cold shutdown will be performed.

2 Valves will be disassembled during refueling outages on a rotating basis. Additioually, partial 4 exercising shall be performed upon reassembly when practical.

Frequency for Alt. Testing: When practical, partial valve stroking quarterly or during cold shutdown will be performed. Valves will be disassembled during refueling outages on a rotating basis.

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SEQUOYAH NUCLEAR PLANT ASME INSERVV;E VALVE TESTING PROGRAM BASIS DOCL7(ENT l APPENDIXD RELIEFREQUESTS PAGE P,-5 .

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RELIEF REQUEST RV-2  !

ALTERNATE TO AUXILIARY AIR COMPRESSOR ERCW VALVE STROKE TIMING ]

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System: ERCW to Compressed Air System Valve: FSV-3241, FSV-32-87 Class: 3 i

, Category: . B ACT L Function: Opens to provide ERCW to the auxiliary control air compressors.

• I Impractical Requirement: Stroke time test. l l

Basis for Relief: 'Ibese solenoid valves are part of the ausiliary air compressor package, have no position *mdication and are totally enclosed, preventing vimal confirmation of valve position.  !

Satisfactory operation of the aux.iliary air compressors vedfies that FSV-3241 and 87 operates. l Alternative testing will provide an acceptable level of safety. j Alt. Testing: Exercise by observing the auxiliary air compressors to ensure the solenoid valve opens to ,

supply ERCW cooling by ensuring auxiliary air compressor temperature is acceptable.  ;

Frequency for Alt. Testing: Quarterly  ;

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sEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIXD RELIEFREQUESTS PAGE D-6 RELIEF REQUEST RV-3 RHR VALVE EXERCISING DURING COLD SHUTDOWN System: Residual Heat Removal (RHR)

Valve: FCV-74-1. FCV-74-2 Class: 1 Category: A Active Function: Open to provide emnon from the RCS for the Residual Heat Removal pumps when RCS pressure is below setpoint.

Close to ed as pressure isolation valves to prevent overpressurization of the RHR system.

Inspmetical Requirement: Full stroke exercise every 3 months while in cold shutdown or refueling when RHR is required to be operable.

Basis for Relief: Full stroking of RHR return valves during shutdown isolates decay heat removal capacity, mixing capacity needed to maintain uniform boron concentration within the RCS, and ability to produce gradual reactivity changes during boron concentration reductions in the RCS. It is generally not considered prudent to remove a valve from its safety related position to perform a

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periodic code test when that testing places the unit in an overall degraded condition. With respect to these specific valves, it is deemed additionally ill-advised in consMeration of Unresolved Safety Issues (USI) A-31, " Residual Heat Removal Shutdown Requirements" and A-45, "Shutdon Decay Heat Removal Requirements" which address concerns regarding loss of residual heat removal capability leading to core damage. Reliability of performing heat removal functions is specifically identified as being dependent on the frequency of events that jeopardize decay heat removal operations.

). Alternative testing will provide an acceptable level of quality and safety and the increase in the j level of safety by normal testing is not commensurate with the difficulties or risks involved.

F Extended outages of greater than 3 months are not normally anticipated.

Alt. Testing: Full stroke exercise while shutting down when going on RHR as required. Full stroke exercise during startup when coming off RHR as required.

Frequency for Alt. Testing

Full stroke exercise while shutting down (when going on RHR) if not

! exercised in the last 3 months or the projected outage duration would cause valves to require testing j prior to startup. If not stroked during shutdown the surveillance interval expires during outage, or if outage duration exceeds 3 months, valves need not be exercised until startup when coming off 6

RHR.

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SEQUOYAH NLCLEAR PLANT ASME INSERVICE VALVE TES11NG PROGRAM BASIS DOCUMENT APPENDIX D.pF11FF REQUESTS PAGE D-7 RELIEF REQUEST RV-4 This relief request has been deleted.

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDDCD REllEFREQUESTS PAGE D-8 j RELIEF REQUEST RV 5 '

ERCW PUMP AIR RELEASE CHECK VALVE EXERCISING DURING PUMP TEST System: Essential Raw Cooling Water Valves: 67-719A, 67-719B, 67-720A, 67-720B, 67-739A, 67-739B, 67-740A, 67-740B  ;

Class: 3'

' Category: C-Active Function: Valves open to admit air to pump column to allow the water in the pump column to drain l back to the pump pit upon stopping the pump. These valves also remain open for a period of time upon starting the pump to provide a vent path for the air in the pump columns and discharge head. ,

Den the valves close to provide a flow boundary after the pump starts and water reaches the pump discharge head and the check valve h valves are located in a horizontal run of pipe and are  !

installed upside down (i.e., the valve bonnets face downward) so that gravity will assist m opemog .

the valve.

Impractical Requirement: Verify that valves full stroke open.

Basis for Relief: There is no required flow rate for these valves and no practical way to determine the j flow rate through these small diameter valves. The rules of OM Part 10 and NUREG-1482 were  !

developed with liquid flow in mind and not compressible gaseous flow. Attempting to measure an j air flow rate this small will result in very inaccurate and unrepeatable results. Additionally, the nature of the flow through these valves is such that it will not be at a steady state long enough to j quantify. He flow will rapidly accelerate to a maximum and then steadily decrease as the driving i l

force of the water column level above the river elevation decreases.

Alternate Testing: Verify that the valves open after stopping the pumps by use of a smoke test to verify that the valves at least partially stroke open. This will be indicated by the smoke being drawn into the piping by the vacuum caused by the water in the pump column when it starts to drain back to the pump pit. He closing function of the valves will be demonstrated during each pump test.

Frequency for Alternate Testing: Once per quarter.

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDDCD RELIEFREQUESTS PAGE D-9 RELIEF REQUEST RV4 -

ALTERNATE TO REACTOR HEAD VENT VALVE STROKE TIMING I

System: Reactor Coolant System Valve: FSV48-3%, FSV48-397 I

Class: 1.

Category: B-Active Function: Valves are opened manually to provide a rewor vessel head vent path; to vent non-cnndannahles from the head during an accident so promote natural circulation; and to prevent gases from impedag reactor coolant circulation flow through the core.

Impractical Requirement: Quarterly stroke time test.

Bacis for Relief: These solenoid valves have no position indication and are totally enclosed which prevents visual confirmation of the valve position and therefore the inability to measure the time q that it takes the valve to stroke.

Alternate Testing: Verify that the valve operate properly through the use of acoustic monitoring. f Frequency: Every refueling outage. .

Note: His is similar to relief which was approved for the first interval testing program.

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SEQUOYAH NUCI. EAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT i APPENDIX Et B-PASSIVE VALVES.NITHOUT REMOTE POSITION INDICATION PAGE E-1 '

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CATEGORY B - PASSIVE VALVES  ;

WITHOUT REMOTE POSITION .

INDICATION  ;

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4 i C:\ WINDOWS \JHSFILE\0BPASVLV.WPF

4 --d am.ze,J--4 a.k .A a J p.d. J a,a4- 4 -+- 4 -+: a,s.ie a e- r_ wp --vuir SEQUOYAE NUCLEAR FIANT ASNE INSERVICE TESTING PROGRAN BASIS DOCUMENT APPENDIE Et B-PASSIVE VALVES WITEOUT REMOTE POSITION INDICATION PAGE E-2

• 5 Stmmary of Information Provided The following Tables use the format referenced in the 1978 "NRC Staff Guidance for Preparing Pump and Valve Test Program. 1 Descriptions and Associated Relief Requests Pursuant to 10 CFR j 50.55a(g)" to give valve descriptions. The following information j is provided: ,

l

1. System Name and Number s

2. Drawing Number l 3.--Valve Number i j

4. ASME Section.XI Classification

5. Drawing Coordinates of Valve

6. Valve Category Per Section XI, Article IWV-2100

7. Valve Size

8. Valve Type

9. Actuator Type

10. Normal Position l

11. Testing Required Per Section XI l

12. Relief Request Required

13. Alternate Testing

14. Remarks (Including Relief Request Numbers, Specific Valve Data, etc.)

l C:\ WINDOWS \JHSFILE\0BPASVLV.WPF i

4

w. -

S K

1 R

- A 1 M 0 E B R W

7

_ 4 .

. O N -

G N

I W

A R

3 D

- TESTING E ALYERNATIVE T

N EE REQUEST NG RELIEF UA CP O

DN O G D SI N E IT I R SA T S

I U

AC E Q .

BI T E R e e e e e e e e D n n n n n n n n NN o o o o o o o o M M N N M W N N AI R

GN POSIi I 0N OO C C C C C C C C RI NORMAL L L L L L L L L PTI GS TYPE NO ACTUAT0R M M M M M M M M IP T

SE TYPE ET L L L G

L G

L G

L G

L G

L G

TO VALVE G G N

EE CR 2 2 I SIIE 2 2 2 2 2 2 VT RU F EO SH P NT II CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A W .

P P P P P P P P W VALVE - - - - - - - -

V E 8 B 5 B 5 B B B L

NS SE V AV C00RDI NATES 4 4 4 4 4 4 4 4 S TA L DRAWING G G

E E

C C

A A

A fV P u B J 0 IE CLASS PV ASME \

RS I 2 2 2 2 2 2 2 2 E AS L EA I LP F C- M _ S UB E A

H N T J S

Ht \

N S AE I E R Y

OX A

M V

L E

B W UI ) V A M O U D QD 1

(

N N

EN 2 2 4 4 6 6 8 8 SE 3 3 3 3 3 3 3 3 I

5 5 5 5 5 5 P

P M E

5 1

5 1

1 1

1 1

1 1

- W

\

A T - - - - - - - -

S 1 2 1 2 1 2 1 2  :

Y S C

1 ,'

S 1

K -

R 4 A 0 M 8 E W R 7

4 .

O M

G N

I W

A R

4 D

- TESTING .

E ALTERNATIVE T

N EE REeUEST I

G BA t

RELIEF cP O

DN O G D SI N E IT I R _

SA T S

I U

AC E Q BI T E R e e D n n _

NN N o

M o _

AI R .

GN P0SITI ON OO o O _

RI WORMAL L L _

PT _

I _

GS TYPE NO ACTUAT0R N M IP T

SE TYPE ET A A G

TG VALVE G N

EE CR _

I SI2E 2" 2" _

VT 1 1 RU F _

EO SH P NT II CATEGORY S

A S

A W .

P P W VALVE - -

V E 8 8 L

NS SE V AV C00RDI NATES 2 3 S

L DRAWING - - A TA G G P tV u B J O IE CLASS C C

C C

PV ASME N N \

RS I N N E AS L .

EA I _

LP E T

F _

C- A S .

UB S N H N E J D

Et N \

AE O S _

C E R _

Y OX V

L E

B W UI

) A V

M U

O QD 2

( N D _

N EN _.

SE I .

4 P M 0 5

0 W _

, P E 5 5 \ _

A T S 2 2

Y S c _

~ _

S 1 K -

- R 3 A 0 M 8 E W R 7

4 O

N G

N I

W A

R 5 D

- TESTI NC -

E ALTERNATIVE T

f -

nE nG REQUEST a A RELIEF mP o .

DN O G D SI N E _

IT I R SA T S

I U

AC E Q BI T E R e e e e e e e e D n no n n n n n n o o o -

NN o o o M o

N N M W N N N AI _

R -

GN POSITI0N OO C C C C C C C C RI NORMAL L L L L L L L L PTI GS TYPE NO ACTUAT0R M M M M M M M M IP T

SE TYPE ET VALVE L

G L

G L

G L

G L

G L

G L

G L

G TO M

EE CR I SIZE VT 2 2 2 2 2 2 2 2 RU F EO P SE NT S S S A

S A

S A

S A

S A

S A

W II CATEGORY A P

A P P P P P P P E

W VALVE 5 8

B B

8 8

8 B

V MS L SE V AV C00RDI NATES 3 3 3 3 3 3 S

L DRAWI NG 3

3

- - - - - - - A TA C C E E G G B B P uV l

B J

IE CLA5S O PV \

I ASME 2 2 2 2 2 2 2 2 E RS L AS I EA F LP R S C- E UB T A

H N W J D \

Et E AE E F E R S

Y V E B

W OX )

L A M O UI 3 V L D QD ( N N

EN 9 9 0 0 1 1 2 2 I

SE 0 0 1 1 1 1 1 1 P M

6 6

6 6

6 6

6 6

- W P E 3 3

3 3

3 3

3 3

\

A T S 1 2 1 2 1 2 1 2  :

Y S

C

S 2 K

- R 3 A 0 M 8 E W R 7

4 o

N G

N I

W A

R 6 D

- TESTING E ALTERpATIVE T

N EE REQUEST MG RELIEF UA CP O

DN O G D SI N E IT I R SA T S

I U

AC E Q RI T E R e e e e e e e e e e e e e e D n n n n n n n n n n n n n n MN o o o o o o o o o o o o o o M N W N N N N N N N N N N N AI R

GN POSI T1 0N OO O O O O O O O O o O L

O L

O L

O L

O L

RI NORMAL L L L L L L L L t PT I

GS TYPE NO ACTUAT0R M M M M M M M M M M M M M M IP T

SE TYPE A A L A ET A G

A G

A G

A G

A G G G L

G L

G L

G L

G L

G G G TO VALVE M

EE 2 2 2 2 2 2 CR 6" 8" 8" 8" 8" 0" 0" /

1

/

1

/

1

/

1

/

1

/

1 I SIZE 1 1 1 VT 1 1 1 1 1 1 4 RU F

. EO P SE

. NT CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A W -

II P P P P P P P P P P P P P P .

E W VALVE B 5

B 5

B B

B B

5 5

B B

B B

V MS L SE V AV C00RDI NATES 5 6 6 4 4 5 5 6 6 7 7 3 S L DRAWI NG 4

5

- - - - - - - - - - - - - A TA B E D F D F B F F F F B B F P

uV t

B J C C C C C C C C C C C C C 0 IE R E

CLASS C C C C C C C C C C C C C \

PV T ASME N M M N N N N N M N M N N I A N N N N W N N N N W N N N 3 E RS W D L AS E I EA E F

LP F C- Y S UB R A H N I J L \

Et I X S AE U E R Y A V E B

W OX )

L A M O UI 3 V U D QD ( N N

EN 3 3 4 4 9 9 0

6 6 7 7 9 9 6 2 I SE 0 0 0 0 0 1 1 1 1 1 8

1 8 8 P

P M

0 0

8 8

5 8

3 8

3 8

3 8

3 8

3 8

3 8

3 8

3 8

3 3

3 3

- W

\

E - - - - - - - - - -

A T S 3 1

2 1 2 1 2 1 2 1 2 1 2 1  :

Y S C 1

S 2 K

- R _

3 A 0 M B E W R 7

4 O

N G

N I

W A

R 7 D

- TESTI NG E ALTERNATI VE T

N EE REQUEST MG RELIEF UA CP O

DN O G D SI N E IT I R SA T S

I U

AC E Q BI T E R e e e e e e e e e e e e e e D n n n n n n n n n n n n n n NN o o o o o o o o o o c o o o N

W N M W N N N N N N N N N AI _

R Il GN PO5ITI0N OO O O O O O C O O O O O O O O RI N0RMAL L L L L L L L L L L L L L L _

PT I _

GS TYPE _

NO ACTUATOR M N M M M M M M M M M M M M _

IP T

SE TYPE A A A _

ET VALVE A

G A

G A

G A

G A

G A

G A

G A

G A

G A

G A

G G G G TO

- M _

EE 4 4 4 4 4 4 4 4 4 4 4 CR I SI ZE VT 4 4 4 RU F EO P SE NT II CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A W .

P P P P P P P P P P P P P P _

W VALVE - - - - - - - - - - - - - -

V -

E 8 B 8 B 9 B B B 8 8 8 8 B 8 L .

MS SE V _

AV CO0RDI NATES 3 3 3 3 3 3 3 3 3 3 3 3 3 3 S TA L DRAWI NG -

E E

C C

B F

E E

C C

9 A _

NV F 8 F P _

L J

B IE R CLASS 0 PV E T ASME \

RS I A W

3 3 3 3 3 3 3 2 2 2 2 2 2 2 E AS D E

L EA E I LP F F -

C- Y S UB R A H _

N I J L

Et  ! \

AE X U E R S Y

OX A V L

E B W

) A M O UI 3 V U D QD ( N N

EN 6 7 7 8 8 9 9 4 4 5 5 6 6 7 I

SE 2 8

2 8

2 8

2 8

2 8

2 8

2 8

3 8

3 8

3 8

3 8

3 8

3 8

3 8

P P E M

3 3

3 3

3 3

3 3

3 3

3 3

3 3

- W

\

A T S 2 1 2 1

2 1

2 1

2 1

2 1

2 1 Y

S C

o S

2 E

- R 3 A 0 M S E R

M 4

O N

G N -

I h'

R S D

- TESTI NG E ALTERNATIVE T -

N EE REQUEST MG RELIEF UA CP O

DN O G D SI N E IT I R SA T S

u -

AC E c BI T E R e e e e e e e e e D n n n n n n n n n NN o o o o o o o o o M M N N N N N N N AI R

GN POSI TI ON OO O O O O O O O O O RI NORMAL L L L L L L L L L PT I

GS TYPE NO ACTUAT0R M M M M M M M M M IP T

SE TYPE ET A G

L G

L G

L G

L G

L G

L G

A G

A G

TO VALVE M

EE 4 4 4 4 4 4 4 4 4 CR I SIZE VT RU F E0 P S5 NT II CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A W .

P P P P P P P P P W VALVE - - - - - - - - -

V E 3 B 8 B 8 5 8 8 B L

MS V SE AV C00RDI NATES 3 3 3 3 3 3 3 3 S L DRAWI NG 3

- - - - - - - - - A TA s F F D D C C A A P NV B A O LE R E

CLASS

\

PV T ASME I A W

2 3 3 3 3 3 3 3 3 E RS D L AS E I EA E F

LP F C- Y S UB R A H N I J L \

Et I X S AE U E R Y A V E B

W OX )

L A M O UI 3 V U D QD ( N N

EN 7 7 7 8 8 9 9 0 7

0 7 I SE 3 6 6 6 6 6 6 P M

8 8

8 8

8 8

8 8

8

- W P E 3 3 3 3

3 3

3 3

3

\

A T S 2 1

2 1 2 1 2 1 2  :

Y S c

S 2 K

- R 3 A 0 M 8 E W R 7

4 O

N G

N I

W A

R 9 D

- TESTI NG E ALTERNATIVE T

N EE REQUEST MG RELIEF UA CP O

DN O G D SI N E IT I R SA T S

I U

AC E Q BI T E R e e e e e e e e e e D n n n n n n n n n n MN o o o o o o o o o o N M N M N M N M N N AI R

GN POSITI ON OO O O O O O O O O O O RI NORMAL L L L L L L L L L L PT I

GS TYPE NO ACTUAT0R M M M M M M M M M M IP T

SE TYPE ET VALVE A

G A

G A

G A

G L

G L

G L

C L

G A

G A

G TO _

M EE 4 4 4 4 4 4 4 4 CR 3" 3" _

I 5I 2E _

VT _

RU F EO P SH -

NT II CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A W .

P P P P P P P P P P E

W VALVE 8 8

8 8

B 8

8 B

B 8

V _

MS L SE V AV C00RDI NATES 3 3 3 3 3 3 3 7 6 S L DRAWI NG 3

- - = - - - - - - - A TA F F D 0 C C A A 8 B P

f u V B J C C 0 IE R CLAS$ C C PV E T ASME N W \ _

I A 3 2 2 2 2 2 2 2 W N E _

RS W D L AS E I _

EA E F

LP F C- Y S UB R A H N I J L \

Et I X S AE U E R Y A V E B

W

. OX )

L A M O UI 3 V U D QD ( N N

EN 5 5 6 6 7 7 7

8 8 3 7 I

SE 7 7 7 7 7 7 7 2 2 P

P M

8 8

8 8

8 8

3 8

3 8

3 9

3 9

3

- W E 3 3 3 3 3

\

- A T S 1 2

1 2 1 2

1 2 0 0

Y S C

l i

I <

S 1 K

- R 9 A 0 M .

B E W

7 R

4 D F

F

G O E N T G A N L I O W S I

A R

0 D 1 TESTING ALTERNATIVE

_ T E N

E E REQUEST NG RELIEF

_ O C A -

O P DN S O G D N E I I R T I T t SA S u A C B I E

T e

E e e e e e R e e e e e e e e -

D n n n n n n n n n n n n n o o o o o o o o o o o o o N

A N N N N N N N N M N N N N M R I GN PO5I TI ON OO R - N0RMAL O O 0 0 0 O 0 O 0 0 0 C C

. I .

P IT .

G S TYPE O O N O ACTUAT0R M M M M M M M N M N M M M I

T P SE TYPE A A A A A A A A A A A L L ET VALVE G G G G G G G G G G G G G TO E M C E 2" 2" 6" 6" 4" 4" 3" 3" 3" 3" 2" 4" I R SIZE

/

3 1" VT R

EU F S BO P _

N I T M CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A W .

I E P P P P P P P P P P P P P _

E W T S

VALVE B 3

5 5

8 B

B B

8 B

B 5

8 V .

L Y

MS S V SE L COORDI NATES 0 0 0 0 S AV O DRAUI MG 9

9- 1 1 8 8- 8 8

8 8

1 1

7 A

L R D D G G G

G F F D D E A 8 P

T f A T N

uV O C

B J C C C O IE CLASS C C C -

P V E ASME N N N 2 \

I L 5 3 3 2 2 2 2 2 2 2 N N N E R S L O L AS V I E

L A & F C P L S U-B A C H N I J N \

E t E

N S A

Y E C E V

R E W

) L B O O -

U X 2 A M 7 6 7 9 I 6

(

V U N 8 9 9

0 0

1 2 3

3 5

3 3 3 3  % 3 9 D .

QD 9 9 5 5 5 5 5

5 5

5 6

1 7

0 7 N EN 2 2

2 2

2 2 2 2 2 2 2 - - I SE  : 6 6 6 6 6 6 6 6 6 6 6 2 2 6 W P M E V V

- 6

\

P T C C _

A S F F  :

Y S c -

S 2 K

- R 9 A D M 8 E W R 7

4 O

N G

N I

W A

R 1 D 1 TESTI NG ALTERNATIVE T E N

EE REQUEST MG U RELIEF C A O P DN S OI G

N D

E I R T I T I S

A A S U Q

B C E T E I R e e D n n M o o A N N N I

R GN POSI TIOM OO R NORMAL 0 C I

P IT G S TYPE N

I O ACTUAY0R M M T P SE TYPE A A ET VALVE G G TO E EM C R 1" 2" I SIZE V

R TU F E

S O P E M S S W N IT I

E T CATEGORY A A .

S P P E M Y

S VALVE 8 8

V M S L S E L O V AV R C00RDI NATES 3 2 S

T L T

N DRAWING -

C

- A f A O

C A P uV J E B

M CLASS C 0 IE U C \

PV L O

ASME 2

N N E R IS V L

A S D I E N LA A F C P L S U-B A C H N I J

M \

R E A:E H C E R S Y

O X )

V L

E B

W 2 A M O U I 6 V U D

( N QD Ef N SlE 7 6 I 3

P M

2 9

9 W

P E T 2 2

\

A S 6 6  :

Y S C

l SEgDOYAE NUCLEAR PIJutT ASME INSERVICE TESTING PROGRAN BASIS DOCUDENT APPENDIX Et B-PASSIVE VALVES NITHOUT REMOTE POSITION INDICATION PAGE E-12 SYSTEM: (62) CHEMICAL & VOLUME CONTROL SYSTEM DRAWING NO: 47W809-5 C A O L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT 05 EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E iE AI E5 TN GT R O LO FT IG E Y R N V S E 1-62-1047 NNCC H-6 8-PAS 2" GA M C Mone 2-62-1047 NNCC H-5 8-PAS 2" GA M C None 1-62-10484 2 H-7 8-PAS 3" GA M C None 2-62-1048A 2 H-4 8-PAS 3" GA N C None 1-62-10488 2 H-6 8-PAS 3" GA M O Wone 2-62-10488 2 H-5 8-PAS 3" GA M O Wone 1-62-1049 2 H-8 B-PAS 3" GA M O None 2-62-1049 2 H-3 8-PAS 3" GA M O None 0-62-1040 2 H-5 8-PAS 3" GA M O None 1-62-1050A 2 H-7 8-PAS 3" GA M O None 2-62-1050A 2 H-4 8-PAS 3" GA M O None 1-62-10508 2 G-6 8-PAS 3" GA M O None 2-62-10508 2 G-4 8-PAS 3" GA M O Mone C:\ WINDOWS \JHSFILE\0BPASVLV.WPF

. i l

S 5 K

- R 9 A 0 M 8 E W

7 R

4 O

M .

G N

I W

A R

3 D 1 TESTING ALTERNATIVE TE N

EE REeUE$T M

U G RELIEF C AP O

DN S O G D N E I I I R T T I SA S U .

A BI C E T

Q E e e e e e e e e R e e e e n n n n n n n D n n n n n o o o o o o o o o o o o M

A N N N M M M N M M N N N N I

R G

O N POSITI0W C C C C O 0 C C 0 0 0 O RO I NORMAL P IT G S TYPE ACTUAT0R M M M M M M M M M M M N N

I O T P SE TTPE A A A A A A A A A A A A ET VALVE G G G G G G G G G G G G TO E EM a

2" 2" 2" 2" 2" 2" 2" 2" 2 2" 2" 2" C

I R SIZE VT F RU E

S O P N

E T S S A

S A

S A

S A

S A

S A

S A

S A

S A

S A

S A

W I I M CATEGORY A P P P P P P P P P P P P .

EW E

T VALVE 8 8

8 8

8 8

8 8

8 8

8 8

V S

Y L MS S V -

SE L C00RDI NATES S AV O DRAWI NG 7

4 6

4 7

4 6

4 7

4 6

5

- A -

L R G G G G F F F F F F F F P

T f A T

N B

uV O C

J CLAS$ C C 0 IE F E C N

C N \

V M U

ASME 2 2 2 2 N N 2 2 2 2 2 2 E R IS L O L AS V I E

L A & F C P S U-NB L

A C

H I

M J

\

R t E H S A

Y E C E V

R E W O X 2

) L A e p

A A O

U I 6

(

V U M

A 1

A 1

8 1

8 1

A 3

A 3

8 3

8 3 4 4 8

4 8

4 D QD E N 5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0 N 1 1 1 1 1 1 1 1 1 1 1 1 I SE  : - - - - -

2 2

2 2

2 2

2 W

P M E

2 6

2 6

2 6

2 6

2 6 6 6 6 6 6 6 6 \

P T - - - - - - - - - - - -

A S 1 2 1 2 1 2 1 2 1 2 1 2 T

S c

1 i S

5 K

- R 9 A 0 M 8 E

- W R 7

4 O

N G

N I

W A

R 4 D 1 TESTI NG T E ALTERNATI VE .

t l

EE REQUEST MG RELIEF U

C A O P DN .

S O I G

N D

E I R S T I .

T I A A S U _

Q B C E _

T E I R e e e e e e e e e e e e e _

D n n n n n n n n n n n n n _

o o o o o o o o o o o o o _

MN A N N N N N N N N N N N N N I _

R .

GN POSITI 0N -

OO 0 o C C 0 O o 0 0 0 0 0 0 R I NORMAL P IT GS TYPE N O ACTUAT0R M M M M M M M M M M M M M I

T P S E TYPE A A A A A A A A A A A A A ET VALVE G G G G G G G G G G G G G TO E M _

C E 2" 2" 2" 4" 4" 1" 1" 2" 2" 2" 2" _

I R 2" 4" _

SIZE / / / _

3 3 3 VR T E U F S OH P

N IT I M CATEGORY S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A S

A W .

E P P P P P P P P P P P P P _

V VALVE - - - - - - - -

E W T - - - - -

- S 8 8 8 8 8 8 8 B 8 8 8 8 5 MS Y L _

S E S V _

AV L O

C00RDI NATES 7- 4 7 4 6 3 5 0

1 1 9- 2 9 2 S A

DRAWI NG - - - - - - _

T L R = - - - -

E D D E F F A T N

E E F 0 E F F P _

N A V O C

B LE CLASS O E \

PV I M

U ASME 2 2 2 2 2 2 2 2 2 2 2 2 2 E RS L O L A S V I E

L A & F CP L S U-B A C H N I J

M \

E t E H

A S Y E C E R

)

V E B W OII U

2 L

A V M A A 8 O

6

(

L N 5 5 8

5 5 7 7 7 9 9 0 0 1 1 D QD E N 5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

5 0

6 0

6 0

6 0

6 0 N S E  :

1 1

1 1

1 1

1 1

1 1

1 1

1 I

P M E

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

2 6

W P T - - - - - - - - - - - - -

\

A S Y

1 2 1 2 1 2 0 1 2 1 2 1 2  :

S C

i  !

' i S

K R

1 A

- M

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i SEQUOYAE'WUCLEAR PLANT ASME INSERVICE TESTING PROGRAN BASIE DOCUMENT APPENDIX E B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-16 l

SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 47W845-1 '(R10)'

C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S MA EO E TE AI ES TN GT R 0 LO FT IC E Y R N V S E RPI Unavailable FCV-67-12 3 E-1 B-PAS 36 90T MO O Mone AERCW Deleted - Accendix R Denereired RPI Unevaltable FCV-67-14 3 0-1 B-PAS 36 80T MO O Mone AERCW Deleted - Annendia R Denerefred RPI Unavaltable FCV-67-22 3 F-10 B-PAS 30 BUT No o None AERCW Deleted - Accendix R Denereired RPI Unavettable i

FCV-67-24 3 E-10 B-PAS 30 BUT M0 0 Mone AERCW Deleted - Anoendix R Denerefred RPI Unavailable FCV-67-364 3 E-1 8-PAS 36 9UT MO O None AERCW Deleted - Anoendin R Denerefred RPI Unavaltable FCV-67-365 3 D-1 8-PAS 36 BCT MO O None AERCW Deleted - Accendix R Denerefred RPI Unavailable FCV-67-366 NNCC E-3 8-PAS 24 SUT MO O Mone AERCW Deleted - Accendix R Denereired RPI Unavaliable-E-3 B-PAS 24 BUT MO O None AERCW Deleted - Anoendix R Denergized FCV-67-367 NNCC C:\ WINDOWS \JHSFILE\OBPASVLV.WPF

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BEQUOYAE NUCLEAR PIJUfT ASME INSERVICE TESTING PROGRAN BASIS DOCUMENT APPENDIX E: B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-18 SYSTEM: (67) ESSENTI AL RAW COOLING WATER DRAWING NO: 4h845-1 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NLMBER MA U1 LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E 1-67-510A 3 C-11 8-PAS 6" SUT M 0 None 2-67-510A 3 C-9 8-PAS 6" BUT M 0 None 1-67-5108 3 C-8 B-PAS 6" BUT M 0 None 2-67-5108 3 C-6 8-PAS 6" BUT M 0 None 1-67-511A 3 8-11 8-PAS 8" BUT M 0 None 2-67-511A 3 8-9 8-PAS 8" BUT M 0 None 1-67-5118 3 8-9 8-PAS 8" BUT M 0 None 2-67-5118 3 8-7 8-PAS 8" BUT M 0 None 1-67-515A 3 C-11 8-PAS 6" BUT M 0 None 2-67-515A 3 C-11 8-PAS 6" BUT M O None 1-67-5158 3 C-8 8-PAS 6" BUT M 0 None 2-67-5158 3 C-8 B-PAS 6" BUT M 0 None C:\ WINDOWS \JHSFILE\0BPASVLV.WPF

SEQUOYAE NUCLEAR PIJulT ASME INSERVICE TESTING PROGRAN BASIS DOCUMENT APPENDIZ Et B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-19 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 47WB45-1 C A 0 L 00 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EG RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E 1-67-516A 3 B-9 B-PAS 8" BUT M O Mone 2-67-516A 3 B-7 B-PAS 8" BUT M 0 None 1-67-516B 3 B-11 B PAS 8" BUT M 0 None 2-67-516B 3 B-9 B-PAS 8" BUT M O None 1-67-518A 3 F- 12 B-PAS 30" BUT M 0 None 2-67-518A 3 F-6 B-PAS 30" BUT M 0 None 1-67-518B 3 E-12 B-PAS 30" BUT M 0 None 2-67-518B 3 E-6 B-PAS 30" BUT M O Mone 0-67-672A 3 H-3 B-PAS 24" BUT M C None AERCEDeleted 0-67-672B 3 H-4 B-PAS 24" BUT M C None AERCW Deleted C:\ WINDOWS \JHSFILE\OBPASVLV.WPF

SEQUOYAH NUCLEAR PLMIT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDII Et B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-20 SYSTEM: (67) ESSENTI AL RAW COOLING WATER DRAWING No: 47W845-2 (R15)

C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES I fl VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E FCV-67-127 3 8-10 B-PAS 8" 8UT MO O Wone Accendix R Denerefred/RPI Unavailable FCV-67-128 3 8-10 8-PAS 8" BUT MO O Mone Accendix R Denernized/RPI Unavailable FCV-67-47P 3 8-7 8-PAS 6" BUT MO O None Accendix R Denerained/RPI Unevallable 1-67-520A 3 G-9 8-PAS 6" BUT M LO None 2-67-520A 3 G-2 8-PAS 6" BUT M LO None 1-67-5208 3 H-9 B-PAS 6" BUT M LO None 2-67-5208 3 H-2 B-PAS 1-1/2 BUT M LO None C:\ WINDOWS \JHSFILE\OBPASVLV.WPF

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE TESTING PROGRAM BASIS DOCUMEMIT APPENDIZ Et B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-22 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING No: 47W845-2 C A 0 L DO C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT OS EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP Mi !E AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V S E 0-67-552 3 C-6 B-PAS 24" BUT M O None 0-67-553 3 C-6 B-PAS 24" BUT M o None 0-67-555A 3 G-6 B-PAS 6" BUT M 0 None 0-67-555B 3 H-5 B-PAS 6" BUT M 0 None 1-67-718A 3 G-6 B-PAS 6" BUT M 0 Mone ,

2-67-718A 3 G-5 B-PAS 6" BUT M O None 1-67-7188 3 M-6 B-PAS 6" BUT M 0 None 2-67-7188 3 H-5 B-PAS 6" BUT M 0 None C:\ WINDOWS \JHSFILE\0BPASVLV.WPF ,

~1 l SEQUOYAE NUCLEAR PLAIST ASME INSERVICE TESTING PROGRAN BASIS DOCUMENT APPENDIX Et B-PASSIVE VALVES WITHOUT REMOTE POSITION INDICATION PAGE E-23 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING NO: 47Wl45-3 C A 0 L D0 C A P R TT VALVE AC RR VA S VT C NO TESTING RE EE SL AD AT I AY TT 05 EQ RS NUMBER MA WI LE Z LP UY RI REQUIRED LU NT REMARKS ES IN VG E VE AP MT IE AI S NA EO E TE AI ES TN GT R 0 LO FT IG E Y R N V 5 E 1-67-564A 3 N-4 6-PAS 4" BUT M O None 2-67-564A 3 M-4 8-PAS 4" BUT M 0 None 1-67-5648 3 E-4 8-PAS 4" BUT M 0 None 2-67 5648 3 E-4 B-PAS 4" BUT M 0 None 1-67-564C 3 F-4 B-PAS 4" BUT M O None 2-67-564C 3 F-4 8-PAS 4" BUT M 0 None 1-67-564D 3 D-4 B-PAS 4" BUT M 0 None 2-67-564D 3 D-4 B-PAS 4" BUT M 0 None j

C:\ WINDOWS \JHSFILE\0BPASVLV.WPF

SEQUOYAE NUCLEAR PIJutT ASME INSERVICE TESTING PROGRAM BASIS DOCUMENT APPENDII Et B-PASSIVE VALVES WITHOUT RD00TE POSITION INDICATICBI PAGE E-24 SYSTEM: (67) ESSENTIAL RAW COOLING WATER DRAWING No: 4M45-3 C A 0 L D0 C A P R 1Y VALVE AC RR VA S VT C W0 TESTING RE EE SL AD AT I AY TT 05 EQ RS NUMBER MA WI LE Z LP UT RI REQUIRED LU NT REMARKS ES 1N VG E VE AP MT IE AI S NA EO E TE AI ES TW GT R 0 LO FT IG E Y R N V S E 1-67-567A 3 M-2 B-PAS 3" GA M 0 None 2-67-567A 3 G-2 B-PAS 3" GA M 0 None 1-67-5678 3 F-2 8-PAS 3" GA M 0 None 2-67-5678 3 .F-2 B-PAS 3" GA N O None 1-67-567c 3 G-2 0-PAS 3" GA M 0 None _

2-67-567C 3 G-2 B-PAS 3" GA M 0 None 1-67-567D 3 E-2 8-PAS 3" GA M 0 Wone 2-67-567D 3 E-2 B-PAS 3" GA N O None 1-67-572A 3 G-3 8-PAS 3" GA N O Wone 2-67-572A 3 G-3 8-PAS 3" GA N O None 1-67-5728 3 E-3 8-PAS 3" GA N O None i

2-67-5728 3 E-3 8-PAS 3" GA M 0 None .

i C:\ WINDOWS \JHSFILE\0BPASVLV.WPF i

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT .

APPENDlX B - EXPLANATION OF SYMBOLS USED PAGE B-8 i 4

SYMBOLS USED TO DESIGNATE TESTING FREQUENCY REQUIREMENTS 5

j

. FREQUENCY CODES [

t  ;

i CSD These valves have been specifically identified as valves which cannot be tested during power operation. These valves shall be j l

full stroke tested during cold shutdowns according to the CSD  !

rules (but not more often than once every three months). Note: 3 .

{

months equals 92 days. i CSD9 These valves have been specifically identified as valves which  !

- cannot be tested during power operation. These valves shall be .

full stroke tested during cold shutdowns (but not more often than .

once every nine months). Note: 9 months equals 276 days. .

DIF At the disassembly and inspection program frequency I J As required by 10CFR50 Appendix J.  !

I i O Quarterly (at least once per 92 days) i l RCP These valves have been specifically identified as valves which  !

p cannot be tested during operation of the Reactor Coolant Pumps (RCPs). These valves shall be full stroke tested during cold I l

shutdowns according to the CSD and RCP rules only of the RCPs

are stopped (but not more often than once every three months).

Note: 3 months equais 92 days. ,

1 l RO Exercise full stroke at refueling only. These valves are identified as i valves which cannot be full staroke tested during power operation i 2 or cold shutdown or relief is requested for an alternate frequency.

3 These valves shall be full stroke tested during refueling. 3

)

RVF At the relief' valve test plan frequency per OM 1987, Part 1. (Re: )

OMa-1988, Part 10, Paragraph 4.3.1).

TS Technical Specification Frequency

}

Y Yearly (at least once per 366 days) 2Y Two Years (at least once per 24 months) 4 xY x Years where x is the number of years i

18- 18 months NOTE: Some frequencies are defiried by Technical Specification 4.0.5. A 25%

l extension can be applied to these intervals as allowed by Technical Specifications.

FILt* C

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f SYMBOLS USED TO DESIGNATE TESTING FREQUENCY REQUIREMENTS j l

FREQUENCY CODES i i

i HSB Testing is to be performed while the unit is at Hot Shutdown.

See Technical Specifications for definition.

HSD Testing is to be performed while the unit is at Hot Standby. See Technical Specifications for definition.

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1 FILE C:\ WINDOWS \JHSFILE\0VALSYM.WPF

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SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTINO PROGRAM BASIS DOCUMENT

• s APPENDIX C . DEFERRED TEST JUSTIFICATIONS ' PAGE C i l

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APPENDIX C: DEFERRED TEST JUSTIFICATIONS Valves listed below are therein specifically identified by the Licensee as valves which cannot be exercised during power operation, per OM-10 Sections 4.2.1.2 and 4.3.2.2. The table lists the System, Valve i Number, Code Class, Basis for Cold Shutdown Testing for each valve which is being tested on a cold l shutdown frequency, and alternate testing / frequency. 'Ihe cold shutdown frequency is described in detail .

in the Description section of this document.

l CSJ-1 System: Main Steam System Valves: FCV-1-4, FCV-1-11, FCV-1-22, FCV-1-29 .

Class: 2 Category: B-ACT ' l Function: Isolate the Main Steam Line  ;

Impractical Requirement: Full Stroke and Part Stroke exercise quarterly

• Basis for Deferred Test: Full stroke exercising of these valves during operation could cause SG level  ;

transients which could result in a plant trip. Part stroke excercising of the these valves also can l cause SG transients. Additionally, the revised standard technical specifications state that 'MSIV's l l '

L should not be tested at power, since even a part-stroke exercise increases the risk of a valve closure i when the unit is generating power."  ;

, Alt Testing / Frequency: These valves will be full stroke exercised during cold shutdown.

2 CSJ-2 System: Main Steam System i Valves: 2-1423,2 1424,2-1425,21426

Class

2 j Category: C-ACT .

i 1 Function: Isolate the Main Steam Line on reverse flow in the event of failure of a MSIV to close. }

Impractical Requirement: Full Stroke or part stroke exercise quarterly ';

Basis for Deferred Test

Full or part stroke exercising of these valves during operation could cause SG  :

level transients, which could result in a plant trip. In addition, it is not possible to manually full or part stroke these large check valves using the external arm under steam flow conditions.  :

Alt Testing / Frequency: These valves will be full stroke exercised by manual manipulation during cold shutdown. ,

' t

[ CSI-3 1 System: Main Steam System  ;

. . Valves: FCV-117. FCV-1-18 i Class: 3, 2 4 .-

Category: B-ACT .

Function: Isolate on terry turbine steam line break via high temperature signal from TD AFW Pump Room.

Impractical Requirement: Full ar partial stroke exercise quarterly  ;

Basis for Deferred Test: Cic;ing either of these valves during power causes loss of steam to the steam l driven auxiliary feedwater pump. Failure of either of these two normally open valves in the closed position will result in no heat sink for the loss of all AC power accident. The valve control circuit is not designed for partial stroke capability.  !

Alt Testing / Frequency: Full stroke exercise during cold shutdown.  ;

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SEQUOY All NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS IX:CUMENT APPENDIX C DEFERRED TEST NSTIFICATIONS PAGE C-3 CSJ 4 System: Main Steam Systan Valves: PCV-1-5, PCV 1-12, PCV-1-23, PCV-1-30 Class: 2 Category: BC-ACT -

Function: Must isolate for Steam Generator isolation and for containment isolation. Must operate for

. RCS temperature control and cooldown to cold shutdown.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Opening valve during power operation (full or partial stroke) will cause steam -

blowdown to the atmosphere and a steam generator level transient which could result in an inadvertent safety injection signal and/or plant trip. Closure of the manual isolation valve in series with the PCV is not practical during operation due to high temperatures inside the main steam valve room.

Alt Testing / Frequency: Full Stroke exercise during cold shutdown.

CSJ-5 System: Feedwater System Valves: FCV-3-33, FCV-3-47, FCV-3-87, FCV-3-100, 3-508, 3-509, 3-510, 3-511 Class: 2

Category: B ACT and C Function: The FCVs must close for feedwater isolation, containment isolation and Steam Generator (SG) isolation. The check valves must close to prevent reverse AFW flow or SG blowdown.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising these valves during power operation (full or partial) causes a loss of ,

feedwater to the loop they supply. When feedwater flow is restored, the resulting SG level shrmk could cause a reactor trip. He FCV valve control cin:uit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke the FCVs during cold shutdown and verify the checks closed during ,

cold shutdown.

I CSJ-6  ;

System: Auxiliary Feedwater System Valves: 3-805, 3 806, 3-810 i Class: 3 j Category: C-ACT 1 Function: 3-805,3-806, and 3-810 open to admit auxiliary feedwater flow from the condensate storage l i

tank to the auxiliary feedwater pump's suction; they also close when the ERCW is aligned to auxiliary feedwater pump suction.

Impractical Requirement: Full stroke exercise quarterly.

Basis for Defernd Test: Full stroke exercising these valves during power operation could result in severe thermal shock to the auxiliary feedwater nozzles and cause SG level transients and a unit trip. J

. Alt Testing / Frequency: These valves will be part stroked quarterly during the associated pump test and full stroked during hot shutdown or hot standby (but not more often than once per three months). 3-805, 3-806, and 3-810 will be verified closed quarterly.

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SEQUOYA!! NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDIX C DEFERRED TEST JUSTiflCATIONS PAGE C 4 CSJ 7 System: Auxiliary Feedwater System Valves: 3-820, 3-821, 3-864 Class: 3 Category: C Function: Open to allow AFW Pump discharge flow. .

Impractical Requirement: Full stroke exercise quarterly. In addition,3-864 cannot be partial stroke exercised.

Basis for Deferred Test: Full stroke exercising these valves (and partial stroke of 3-864) during power operation would result in severe thermal shock to the auxiliary feedwater nozzles and a unit trip.

Alt Testing / Frequency: Partial stroke exercise 3-820 and 3-821 during the quarterly pump test and full stroke exercise during operation of the auxiliary feedwater system during hot standby. Full stroke exercise 3-864 during operation of the auxiliary feedwater system during hot standby.

' CSJ-8 ,

System: Auxiliary Feedwater System Valves: 3-832, 3-833, 3-873, 3-874 Class: 2 Category: C Function: Open to allow AFW Pump discharge tiow to SG and closes to prevent reverse AFW flow through idle pump.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Full or partial stroke exercising these valves during power operation would result in severe thermal shock to the auxiliary feedwater nozzles and a unit trip.

Alt Testing / Frequency: Full stroke exercise during operation of the auxiliary feedwater system during hot standby. Verify closure quarterly.

CSJ-9 l System: Auxiliary Feedwater System Vnives: 3-861, 3-862, 3-921, 3-922 )

Class: 2 Category: C Function: Open to allow AFW Pump discharge flow to SG and closes to prevent blowdown of SG into annulus for an AFW line break in the annulus.  !

Impractical Requirement: Full stroke exercise quarterly.

Basis for Deferred Test: Full stroke exercising these valves during power operation would result in severe thermal shock to the auxiliary feedwater nozzles and a unit trip.

. Alt Testing / Frequency: Full stroke exercise during operation of the auxiliary feedwater system during hot standby. Verify closure quarterly.  !

i CSJ 10 System: Compressed Air System Valves: 1.FCV-32-80,2-FCV-32-81,1 FCV 32-102,2-FCV-32-103,1-FCV-32-110,2-FCV-32111 Class: 2 ,

i Category: C Function: Close on a phase B containment isolation signal. Open to supply control air to valves inside containment impractical Requirement: Full or partial stroke exercise quarterly. l Basis for Deferred Test: Exercising these valves during operations results in a loss of control air to control valves inside containment and could result in valves going to their failed position and resulting in a possible unit trip. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown. l I

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCtMENT APPENDIX C DEFERRED TEST JUSTIFICATIONS PAGE C-5 l

i CSJ-11

. System: Post Accident Sampling System Valves: FSV-43-250, FSV 43 251, FSV-43-309, FSV-43-310, FSV-43-317, FSV-43-341,43-461 Class: 2 Category: B-ACT and C. f Function: Must close or remain closed for containment isolation.

Impractical Requirement: Full or pa tial stroke exercise quarterly. i Basis for Deferred Test: These FSVs are containment isolation valves that do not receive a containment isolation signal. Testing during operation would require a violation of Containment Integrity. The FCV valve control circuit is not designed for partial stroke capability. Testing 43-461 at power would also require entry into a high radiation area.

Alt Testing / Frequency: Full stroke exercise during cold shutdown and leak test per Appendix L CSJ 12 l System: Chemical and Volume Control System  ;

Valves: LCV42132, LCV42133, LCV-62-135, LCV42136 Class: 2 j Category: B-ACT  !

Function: These valves operate to switch the centrifugal charging pumps suction from the VCT to the l RWST on a safety injection or low VCT level sigr.al. l Impractical Requirement: Full or partial stroke exercise quarterly. {

Basis for Deferred Test: Stroking these valves during power operation would cause unacceptable boron i transients leading to RCS temperature and power transients which could result in unit trip. The FCV valve control circuit is not designed for partial stroke capability. 3 Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CSJ 13  :

System: Chemical and Volume Control System Valves: 62-543, 6346t, FCV4244 l Class: 2 and 1 Category: C and B-ACT Function: 62-543 must open to allow charging flow and close for containment isolation. FCV-62-84 and 62-661 must close for RCPB isolation.

Impractical Requirement: Exercise full or partial closed quarterly. '

Basis for Deferred Test: Full or partial stroking of these valves causes thermal cyclic fatigue to the letdown heat exchanger, charging connections to the RCS and. ic the case of 62-661 and FCV-62-84, thermal cyclic fatigue to the Pressurizer spray nozzle. Is additien, stroking of the check valves closed during power operation is not practical since performance of the cbsure test requires isoli. tion of the normal charging path for a prolonged period of time. The FCV valve centrol circuit i not designed for partial stroke capability.

Alt Testing / Frequency: Verify 62-543 full stroke open quarterly. Verify closure of 62-543 and 62-661 during cold shutdown. Full stroke exercise FCV-62-84 during cold shutdown.

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I SEQUOYAH NUCLEAR PLANT ASME INSERVICE VALVE TESTING PROGRAM BASIS DOCUMENT APPENDDCC DEFERREDTESTJUSTIF] CATIONS PAGE C4 i

CSJ-14 System: Chemical and Volume Control System Valves: FCV4249, FCV42-70, FCV42-72, FCV42-73, FCV42-74, FCV42-77, FCV4245, FCV4246 FCV42 90, FCV42-91 Class: 1 and -2 Category: B-ACT Function: 'lliese valves allow for charging and letdown flow from the CVCS to/from the RCS. FCV-62-72 FCV42-73, FCV42-74, FCV42-77 and FCV42-90 must close or be capable of closing -

for contammant isolation. FCV4249 and 70 must close for RCPB isolation. -

Impractical Requirement: Full stroke exercise quarterly.

Basis for Deferred Test: Full or partial stroking of these valves causes thermal cyclic fatigue to the letdown heat exchanger, letdown and charging connections to the RCS. The FCV valve control circuit is not designed for partial stroke capability.

- Alt Testing / Frequency: Full stroke during cold shutdown.

CSJ 15 System: Chemical and Volume Control System l Valves: 62 4 59, 62 4 60,62-716, 62-717 Class: 2 Category: C-Active j Function: Open to provide normal or auxiliary charging flow to the RCS.

Impractical Requirement: Exercise open (full or partial stroke)

Basis for Deferred Test: Full stroke openmg of these valves is verified by establishment of normal charging flow or alternate charging flow. One path (either normal or alternate charging) is normally in service at all times during operation. Valve realignment to verify full stroking of the .

opposite path causes thermal cyclic fatigue to the letdown heat exchanger, letdown and charging connections to the RCS.

Alt. Testing / Frequency: Exercise full open during cold shutdown.

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SEQUOYAll NUCLEAR PLANT ASME INSERVICE VAU!E TESTING PROGRAM BASIS DOCUMENT APPENDIX C - DEFERRED TEST NSTIFICATIONS PAGE C-7 CSJ-16 System: Safety Injection System Valves: FCV-631 Class: 2 Category: B-ACT Function: Allows flow from the RWST to both trains of RHRPs. Closes during recirculation mode of ECCS Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising valve during operation results in losing suction from RWST to both trains of residual heat removal and placing the unit in a condition outside the design and licensing basis.

The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CSJ 17 S; stem: Safety Injection System Valves: FCV-63-3 Class: 2 Category: B-ACT Function: Allows recirculatica of both SIPS miniflow back to the RWST. Closes during recirculation mode of ECCS Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising valve during operation results in losing the miniflow recirculation flow path for both trains of safety injection pumps and placing the unit in a condition outside the design and licensing basis. If the pumps started without recirculation, severe damage to both pumps could occur. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CSJ-18 System: Safety Injection System Valves: FCV-63-5 Class: 2 Category: B-ACT Function: Allows flow from the RWST to both trains of SIPS. Closes during recirculation mode of ECCS Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising valve during operation results in losing suction from RWST to both train of safety injection pumps and placing the unit in a condition outside the design and licensing basis.

The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

C:\WINWORDUHSFILE\VPBDAPPC. DOC A

SEQUOYAH NUCLEAR PLANT ASME tNSERVICE VALVE TESTINO PROGRAM BASIS DOCUMENT APPENDIX C - DEFERRED TEST JUSTIFICATIONS PAGE C-8 CSJ-19 System: Safety Injection System Valves: FCV43-22 Class: 2 Category: B-ACT Function: This valve is normally open and its closure isolates both trains of safety injection from their normal flow path to the cold legs.

Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: Exercising valve quarterly isolates both trains of safety injection from their normal flow path to the cold legs and places the unit in a condition outside the design and licensing basis.

The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CSJ-20 Systenu Safety Injection System ,

Valves: FCV-63-8, FCV-63-11, FCV43-72, FCV43-73 Class: 2 Category: B-ACT Function: FCV-63-8 and 11 connect the discharge of the low head RHRPs to the suction of the higher head CCPs and SIPS during the recirculation mode of ECCS. FCV-63-72 and 73 are the containment ECCS sump isolation valves that open to provide the supply to the RHRP's suction during the recirculation mode of ECCS Impractical Requirement: Full or partial stroke exercise quarterly.

Basis for Deferred Test: These valves are associated with the containment sump and their operation during power operation could cause loss of the RWST inventory and flooding oflower containment which would result in inoperability of both trains of safety injection; placing the unit in a condition outside the design and licensing basis. FCV-63-8 and -11 are interlocked with FCV-63-72 and -73. The FCV val've control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

CM-21 Sys em: Safety Injection and Residual IIcat Removal System .

Val res: FCV-63-93, FCV-63 94, FCV-63-172, FCV-74-33, FCV-74-35 l Cira: 2 category: B-ACT ,

Function: These valves are associated with the RHR flowpaths to the RCS hot and cold legs. j Impractical Requirement: Full or partial stroke exercise quarterly, i Basis for Deferred Test: Closing the norinally open valves or opening the normally closed hot leg l injection valve FCV-63-172 during operation results in less than the required RHR cold leg injection j flow capability placing the unit in a condition outside the design and licensing basis. The FCV valve control circuit is not designed for partial stroke capability.

Alt Testing / Frequency: Full stroke exercise during cold shutdown.

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