Text

TMI-1 Pump & Valve IST Program
	ML20092M194
Person / Time
Site:	Three Mile Island
Issue date:	09/21/1995
From:	; GENERAL PUBLIC UTILITIES CORP.
To:	;
Shared Package
ML20092M191	List: ML20092M190; ML20092M194;
References
	PROC-950921, NUDOCS 9509290109
	Download: ML20092M194 (82)
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THREE MILE ISLAND NUCLEAR STATION. UNIT-1 1

-r PUMP AND VALVE INSERVICE TESTING PROGRAM i

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l PUMP AND VALVE INSERVICE TEST PROGRAM FOR THE l THREE MIIR ISLAND NUCLEAR STATION, UNIT-1 (TMI-1)

TABLE OF CONTENTS Page i

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1.0 INTRODUCTION

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2.0 S C OPE OF THE I ST PROGRAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l

l 3.0 APPLICABILITY.............................................................................................................................2

4. 0 - PUM P TEST PROG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 5.0 V ALV E TEST PROG RAM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 l 6.0 GENERIC CODE R EI IEF GRANTED BY GL 89-04 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 I

TABLE 1 DRAWING GUIDE - ISI DRAWINGS AFFECTED BY P& ids APPENDIX A - TMI-l INSERVICE PUMP 'GST PROGRAM EXPLANATION OF CODES AND SYMBOLS i

TABLE A-1 TMI-1 INSERVICE TEST PROGRAM PUMP TABULATION TABLE A-2 TMI-l IST PUMP RELIEF REQUESTS l TABLE A-3 TMI-l AUGMENTED IST PROGRAM PUMP TABULATION APPENDLX B - TMI-1 INSERVICE VALVE TEST PROGRAM EXPLANATION OF CODES AND SYMBOLS ,

TABLE B-1 TMI-1 INSERVICE TEST PROGRAM VALVE TABULATION TABLE B-2 TMI-l IST VALVE RELIEF REQUESTS TABLE B-3 TMI-l AUGMENTED IST PROGRAM VALVE TABULATION

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PUMP AND VALVE TEST PROGRAM FOR THE THREE MILE ISLAND NUCLEAR STATION ('IMI-1)

1.0 INTRODUCTION

The Pump and Valve Inservice Test (IST) Program along with the augmented IST for nree Mile Island Nuclear Station, Unit 1, (TMI-1) are described in Appendices A and B. TMI-l ISI Boundary Drawings and the associated Piping &

Instrumentation Diagrams (P& ids) are listed in Table 1. Four sets of drawings are being pmvided to the NRC Senior Project Manager to facilitate the NRC review of this submittal. He color coded ISI drawings are being pmvided in black and white for IST review purposes because the ASME Code Class and Category for each component within the scope of the IST pmgram is indicated on the pump / valve table as appropriate.

l The TMI-1 IST program is implemented by plant procedures which am contmlled in accordance with the GPU Nuclear Operational Quality Assurance Plan.

2.0 SCOPE OF THE IST PROGRAM TMI-1 was designed and licensed to operate with the Hot Shutdown condition defined as the " safe" shutdown condition'.

Therefore, components and systems necessary to achieve Cold Shutdown may not be safety-related or subject to quality assurance requirements. Such components are not credited to achieve " safe" shutdown in the plant's safety analyses.

The IST pump and valve programs were both developed with consideration given to boundary classification guidelines i contained in 10 CFR 50.2(v) for Quality Group A and Regulatory Guide 1.26 for Quality Groups B and C. (Quality l Group A is the same as ASME Class 1, Gmup B is Class 2 and Group C is Class 3). These programs have been reviewed with respect to NRC Generic Letter (GL) 89-04, " Guidance on Developing Acceptable la_ervice Testing Pmgrams" using many of the recommendations provided in NUREG-1482, " Guidance on Developing Acceptable Inservice Testing Programs."

NUREG-1482 states that licensees may elect to consolidate the testing of safety-related pumps and valves that are required to be tested (both Code ar.d non-Code), designating the non-Code components as such in the IST program. Components TMI-l Updated FSAR, Chapter 6B, Section 2.3.2.1.

that are either 1) non-Code or 2) Code Class I, 2, or 3 components with no required safety function are included in Tables j A-2 and B-2 as augmented IST pumps and valves.

i l NUREG-1482, Section 2.2 states that relief requests for non-Code components may be implemented without NRC evaluation and approval. However, as mquested by the NUREG, deviations from Code requirements are identified in Tables A-3 and B-3 for the non-Code pumps and valves. If relief from Code requirements is not needed, changes to the IST program will be made in accordance with 10 CFR 50.59 as appropriate, without prior NRC approval.

3.0 APPLICABILITY The Construction Permit (CP) for TMI-1 was issued on April 19, 1967; the Operating License (OL) was issued on April 19, 1974. Commercial operation began on September 2,1974.

This IST Program applies to the TMI-l third ten year interval (120-month period of operation from start of facility commercial operation) as defined by 10 CFR 50.55a(f) and the ASME Code Section XI. 10 CFR 50.55a(f)(4)(ii) requires that IST in each 120-month interval following the initial interval, which began on September 2,1974, be conducted in compliance with the requirements of the latest edition and addenda of the Code incorporated by mference in 10 CFR 50.55a(b), in effect 12 months befom the start of the interval. Themfore, GPU Nuclear is mquired to update IST to the Section XI 1989 Code Edition for the third IST interval.

ASME Code Section XI allows an extension of the 12 month interval up to twelve months, all of which can be taken during the current interval. In a letter dated June 29,1994 GPU Nuclear requested an extension of an additional 12 months for a total extension of 24 months. The NRC's letter dated September 22,1995 allowed for continuation of current testing for up to one year and further permitted continuation of current refueling interval tests through the Cycle 11 Refueling (llR)

Outage. Therefore, transition to the IST pmgram for the third 10-yr interval has begun and will be completed as allowed i by the NRC's letter dated September 22,1994.

I 4.0 PUMP TEST PROGRAM The pump test program shall be conducted in accordance with Part OM-6 of the ASME/ ANSI OMa-1988 Ad&nda to ASME/ ANSI OM-1987 Edition (OM-6) as required by Subsection IWP of Section XI of the 1989 Edition of the ASME Boiler and Pressure Vessel Code, except for relief requested under the provisions of 10 CFR 50.55a(f)(5)(iii).

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L Appendix A, Table A-1 includes the list of pumps which mquire operational testing under the guidelines of OM-6. Specific l requests for relief are noted in Appendix A. Test parameters which will be measured for each pump are indicated.

Appendix A, Table A-2 includes the list of pumps in the Augmented IST Program which are operationally tested under the guidelines of OM-6.

5.0 VALVE TEST PROGRAM

The valve test pmgram shall be conducted in accortlance with Part OM-10 of the ASMFJANSI OMa-1988 Addenda to l

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ASMFlANSI OM-1987 Edition (OM-10) as required by Subsection IWV of Section XI of the 1989 Edition of the ASME Boiler and Pressure Vessel Code, except for relief reque s ted under the provisions of 10 CFR 50.55a(f)(5)(iii). In addition, as required by 10 CFR 50.55a(b)(2)(vii), " Inservice Testing of Containment Isolation Valves," OM-10 paragraphs 4.2.2.3(e), " Analysis of Irakage Rates," and 4.2.2.3(f), " Corrective Action," apply to Containment Isolation Valves (CIVs) that do not provide a reactor coolant pressure isolation function.

Appendix B, Table B-1 includes the list of valves which require operational testing under the guidelines of OM-10.

Specific requests for relief are noted in Appendix B.

Appendix B, Table B-2 includes the list of valves in the Augmented IST Program which are operationally tested under the guidelines of OM-10.

6.0 CODE REIJEF WHERE NRC APPROVAL IS NOT REOUIRED OM-6 and OM-10 now provide relief from certain excessively restrictive requirements where NRC approval previously was needed. In addition, GL 89-04 and its Supplement 1, which includes NUREG-1482, grant generic relief from certain code requirements that have been demonstrated to be excessive. Tables A-1 and B-1 provide the justification to support such a reduction of test requirements as allowed by the code and appropriate application of relief granted by GL.

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TABLE 1 TMI-1 INSERVICE PUMP AND VALVE TESTING PROGRAM :

ISI DRAWINGS REFERENCED BY P&ID P&ID No. ISI DRAWING P&ID No. ISI DRAWING P&ID No. ISI DRAWING No.

No. No. ;

302-011 ID-ISI-FD-001 302-620 ID-ISI-FD-022 302-690 ID-ISI-FD-023 302-012 ID-ISI-FD-001 302-630 ID-ISI-FD-018 302-692 ID-ISI-FD-021 -

t 302-081 ID-ISI-FD-009 302-640 ID-ISI-FD-005 302-694 ID-ISI-FD-023 - ,

302-082 ID-ISI-FD-009 302-645 ID-ISI-FD4)03 302-706 ID-ISI-FD-023 ..

t 302-101 ID-ISI-FD-008 302-650 ID-ISI-FD-019 302-711 ID-ISI-FD-004 .

302-121 ID-ISI-FD-001 302-651 ID-ISI-FD-019 302-712 ID-ISI-FD-012 302-196 ID-ISI-FD-023 302-660 ID-ISI-FD-016 302-719 ID-ISI-FD-001 !

302-202 ID-ISI-FD-002 302-661 ID-ISI-FD-017 302-720 ID-ISI-FD-023 ,

302-203 ID-ISI-FD-002 302-669 ID-ISI-FD-005 302-721 ID-ISI-FD-023 302-231 ID-ISI-FD-023 302-670 ID-ISI-FD-021 302-722 ID-ISI-FD-015 !

302-271 ID-ISI-FD-023 302-671 ID-ISI-FD-020 302-725 ID-ISI-FD-015 f; 302-354 302-671 ID-ISI-FD-016 302-831 ID-ISI-FD-023 I 302-610 ID-ISI-FD-010 302-674 ID-ISI-FD-023 302-847 ID-ISI-FD-011 !

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4 APPENDIX A ,

TMI-l PUMP TEST PROGRAM

SUMMARY

OF APPENDIX A TABLE INFORMATION The TMI-1 Inservice Test Program Pump Tabulations (Tables A-1 and A-3) provide information under the following column headings:

o PUMP NUMBER: '

Individual pump identifier (e.g., MU-PI A identifies Makeup & Purification System Pump "A")

e TYPE:

Type of pump (Centrifugal or Positive Displacement).

e CLASS:

The ASME Code Class as Class 1, 2, or 3 for IST pumps. For pumps included under the Augmented IST Pump Program, "A" is shown in column under class.

e FLOWRATE: '

! Identifies whether flowrate testing applies for the component and gives the frequency of test (e.g., QUARTER = Quarterly Test Frequency,3RDREFL = Every third Refueling Outage, and REFUEL = Refueling Interval Test Frequency).

o DIFFERENTIAL PRESSURE: '

Identifies whether differential pressure testing applies for the component and gives the frequency of test (e.g., QUARTER =

Quarterly Test Frequency).

1 e DISCHARGE PRESSURE:

Identifies whether discharge pressure testing applies for the component and gives the frequency of test (e.g., QUARTER = '

Quarterly Test Frequency).

' TMI-l utilizes the 24 month fuel cycle.

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APPENDIX A TMI-1 PUMP TEST PROGRAM

SUMMARY

OF APPENDIX A TABLE INFORMATION (CONTINUED):

e VIBRATION:

Identifies whether vibration testing applies for the component and gives the frequency of test (e.g., QUARTER = Quarterly Test Frequency).

e SPEED:

Identifies whether rotative speed testing for variable speed pumps applies to the component and gives the frequency of test (e.g., QUARTER = Quarterly Test Frequency).

e REUEF NUMBER:

The pump relief request number from Appendix A, Table A-2, where applicable (e.g., P 1, P 2, etc. for relief that applies to specific components or PG 1, PG 2, etc. for relief that applies generically).

e DRAWING:

This column identifies the TMI-1 ISI Boundary Drawing Number on which the component is shown. For non-Code components the table shows the Piping and Instrumentation Drawing (P&ID) number, a "302" series drawing number. TMI-l ISI Boundary Drawings and the associated Piping & Instrumentation Diagrams (P& ids) are listed in Table 1.

09/19/95 Page 2 of 2

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! VABLE A-1 TMI1 INSERVICE TEST PROGRAM PUMP TABULATION DIFFERENTIAL DISCHARGE RELIEF l PUMP NL34BER TYPE CLASS FLOWRATE PRESSURE PRESSURE VIBRATION SPEED NtDIBER DRAWING AH-P3A CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-011

Description:

CONTROL BUILDING CHILLED WATER SUPPLY PUMP "A" AH-P3B CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-011

Description:

CONTROL BUILDING CHILLED WATER SUPPLY PUMP "B" SS-P1A CENTRIFUGAL 2 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-012

DH CLOSED COOLING WATER PUMP "A" DC-P1B CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-003

DECAY HEAT RIVER WATER PUMP "A" DR-P1B CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-002

Description:

DECAY HEAT RIVER WATER PUMP "B" EF-P1 CENTRIFUGAL 2 3RDREFL QUARTER QUARTER QUARTE;t QUARTER P 2 1D-ISI-FD-009

Description:

TURBINE DRIVEN EMERGENCY FEEDWATER PUMP Justification: The Emergency Feedwater Ptmps are tested on recirculation to the Condensate Storage Tanks. Installed restriction orifices limit the flow rate to a fixed value (approximately 190 gpm for EF-P1 and approximately 90 gpm for EF-P2A and B). Flowrote is not measured quarterly.

09/19/95 Page 1 of 4

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TABLE A-1 TM11 INSERVICE TEST PROGRAM PUMP TABULATION DIFFERENTIAL DISCHARGE RELIEF PUMP NUMBER TYPE CLASS FLOWRATE PRESSURE PRESSURE VIBRATION SPEED NL9eER DRAWING EF-P2A CENTRIFUGAL 2 3RDREFL QUARTER QUARTER QUARTER ---

P 2 1D-ISI-FD-009

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Description:==

MOTOR DRIVEN EMERGENCY FEEDWATER PUMP "A" Justification: The Emergency Feedwater Ptmps are tested on recirculation to the Condensate Storage Tanks. Instatted restriction orifices limit the flow rate to a fixed value (approximately 190 gpm for EF-Pi and approximately 90 wpm for EF-P2A and B). Flowrate is not measured quarterly.

EF-P2B CENTRIFUGAL 2 3RDREFL QUARTER QUARTER QUARTER ---

P 2 1D-ISI-FD-009

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Description:==

MOTOR DRIVEN EMERGENCY FEEDWATER PUMP "B" Justification: The Emergency Feedwater Pimps are tested on recirculation to the Condensate Storage Tanks. Installed restriction orifices timit the flow rate to a fixed value (approximately 190 gpm for EF-P1 and approximately 90 gpm for EF-P2A and B). Flowrate is not measured quarterly.

MU-P1A CENTRIFUGAL 2 REFUEL QUARTER QUARTER QUARTER ---

P 1 1D-ISI-FD-017

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Description:==

MAKEUP & PURIF1 CATION PUMP "A" Justification: The quarterly test uses the minimum flow recirculation (miniflow) line, where there is no flow instrumentation. As permitted by NUREG-1482 and NRC GL 89-04, Staff Position 9, flow rate will be measured thring the refueling outage test at full flow conditions.

MU-P1B CENTRIFUGAL 2 REFUEL QUARTER QUARTER QUARTER ---

P 1 1D-ISI-FD-017

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Description:==

MAKEUP & PURIFICATION PUMP "B" Justification: The quarterly test uses the minimum flow recirculation (miniflow) line, where there is no flow instrtmentation. As permitted by NUREG-1482 and NRC GL 89-04, Staf f Position 9, flow rate will be measured during the refueling outage test at full flow conditions.

MU-Plc CENTRIFUGAL 2 REFUEL QUARTER QUARTER QUARTER ---

P 1 1D-ISI-FD-017 1 MAKEUP & PURIFICATION PUMP "C"

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Description:==

Justification: The quarterly test uses the minimum flow recirculation (miniflow) Line, where there is no flow instrumentation. As permitted by NUREG-1482 and NRC GL 89-04, Staff Position 9, flow rate will be measured during the refueling outage test at full flow conditions.

NR-P1A CENTRIFUGAL 3 REFUEL QUARTER QUARTER QUARTER ---

P 3 1D-ISI-FD-002

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Description:==

NUCLEAR SERVICE RIVER WATER PUMP "A" NR-P1B CENTRIFUGAL 3 REFUEL QUARTER QUARTER QUARTER ---

P 3 10-ISI-FD-002

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Description:==

NUCLEAR SERVICE RIVER WATER PUMP "B" NR-P1C CENTRIFUGAL 3 REFUEL QUARTER QUARTER QUARTER ---

P 3 10-ISI-FD-002

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Description:==

NUCLEAR SERVICE RIVER WATER PUMP "C" NS-P1A CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

10-ISI-FD-010

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Description:==

NUCLEAR SERVICE CLOSED COOLING WATER PUMP "A" 09/19/95 Page 2 of 4 l

TABLE A-1 TMI1 INSERVICE TEST PROGRAM PUMP TABULATION l

SPENT FUEL COOLING PUMP "B" Justification: No pipe taps are present on the suction of the ptmp. Differential pressure will be determined by calculation using

indicated discharge pressure and suction pressure determined using fuel pool level as recomended in NUREG-1482 Section 5.5.3.

WDL-P13A CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

1D-ISI-FD-021

Description:

BORIC ACID RECYCLE PUMP "A" Justification: No pipe taps are present on the suction of the punp. Differential pressure will be determined by calculation using indicated discharge pressure and suction pressure determined using suction tank boric acid levet as recommended in NUREG-1482 Section 5.5.3.

WDL-P138 CENTRIFUGAL 3 QUARTER QUARTER QUARTER QUARTER ---

10-ISI-FD-021

Description:

BORIC ACID RECYCLE PUMP "B" Justification: No pipe taps are present on the suction of the pump. Differential pressure will be determined by calculation using 09/19/95 Page 3 of 4

TABLE A-1 TMI1 ICSERVICE TEST PROGRAM PUMP TAOULATION~

DIFFERENTIAL DISCHARGE RELIEF-PtsP IRDWER TYPE CLASS FL0bEATE PRESSURE PRESSURE VIBRATION SPEED IIIAGER DRAWIIIG indicated discharge pressure and suction pressure determined using suction tanit boric acid level'as rec 6 in - ,

NUREG-1482 Section 5.5.3.

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TABLE A-2 TMI-l IST PUMP RMN REQUESTS RMM REQUEST NO. P 1 Component Tar No. Component Description Tvoe MU-PIA Makeup & Purification Pump "A" Centrifugal MU-PIB Makeup & Purification Pump "B" Centrifugal MU-PIC Makeup & Purification Pump "C" Centrifugal Code Section from Which Relief is Reauested Relief is requested from the OM-6, 65.6, " Duration of Tests," requirement for a run time of at least two minutes after reaching stable pump conditions before obtaining data and the 55.2, " Test Procedure," requirement for testing at a single reference point.

Also, relief is requested from the vibration measurement requirements of OM-6, 64.6.4.

Alternate Test Descriotion As permitted by NRC GL 89-04, Position No. 9, the pumps will be full flow tested at a refueling outage frequency (seejustification).

The refueling outage test will include measurement of stable flow rate and DP. Pump testing will be performed with the system lined up to pump to the RCS through different flow path combinations to provide pump data at various flowrates. Run time through each flow configuration may be less than the two minutes required by OM-6. Due to the short duration of testing, a best effort will be used to take vibration data and all points may not be obtained.

Basis for Relief Request The amount of time that the Makeup Pump injects at full flow to the Reactor Coolant System (RCS) must be limited. Pumping to the RCS will raise the level in the pressurizer and a plant transient can occur. Run time, therefore, must be limited.

Pumping time is limited to a total of appruximately five minutes for all flow configurations. Because of the short time available for a test mn, throttling to a specific reference point can not be accomplished. The pump is run with several different valve lineups to verify that flowrate and head are equal to or higher than accident design requirements. Flow rate and pressure measurements for each lineup is compared to previous test data. Acceptance is based on meeting or exceeding accident flow and head requirements.

This meets the intent of the code. The test is similar to that described in NUREG 1482, f5.2 except for the following:

1) A manufacturers curve is not used. Comparison is with the FSAR Safety Analysis curve and previous full flow tests,

2) A five point curve is not used. The pump will operate at several different points, and 09/19/95 Page 1 of 2

TABLE A-2 TMI-l IST PUMP RFJJFF REQUESTS RFJJFF REQUEST NO. P 1 (Continued):

3) Vibration is taken during the quarterly test and to the extent time allows during the full flow test.

These tests demonstrate pump operability and meet the intent of the code.

08/28/95 Page . 2 of 2

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TABLE A-2 TMI-l IST PUMP RELIEF REQUESTS REIlEF REQUEST NO. P 2 Component Tar No. Component Description Tvoe EF-P1 Turbine Driven Emergency Feedwater Pump Centrifugal -

EF-P2A Motor Driven Emergency Feedwater Pump "A" Centrifugal EF-P2B Motor Driven Emergency Feedwater Pump "B" Centrifugal Code Section from Which Relief is Requested Regarding refueling interval tests, relief is requested from:

1. OM-6, f5.6, " Duration of Tests," requirement for a run time of at least two minutes after reaching stable pump conditions before obtaining data,

2. OM-6, f5.2.c, mquirement to compare flow rate and pressure to their mspective reference values, and

3. OM-6, 64.6.4.a, requirement to take vibration measurements on each accessible pump bearing.

Alternate Test Description TMI-I Tech Specs requires a test each refueling to demonstrate that the motor driven EFW pumps can pump water from the condensate storage tanks (CSTs) to the steam generators. Except for tests every third refueling outage, the pump will be stopped as soon as accident design flowrate is achieved.

Every third refueling starting with the 11R Outage in September 1995, the test will demonstrate full flow for each pump based on a reference value. During the full flow test, the pump will be stopped based on steam generator level when approximately 1000 gallons has been transferred. Run time while pumping to the steam generator in either case may be less than the two minutes required l by OM-6. A best effort will be used to take vibration data for each pump bearing, however because of the short duration of the refueling interval test, it may not be possible to obtain all of the data.

Basis for Relief Request l The EFW pumps are only for emergency use. They are not needed for startup, shutdown, or normal plant operation. Since the l pumps operate only for test, no significant degradation is expected if testing is performed as proposed.

Every refueling outage, accident design flow for each pump will be verified by starting the pump and running only long enough to take flow rate data. EFW flow to the steam generators is limited by the cavitating venturis.

09/19/95 Page 1 of 2

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TABLE A-2 TMI-l IST PUMP RELIEF REQUESTS RELIEF REQUEST NO. P 2 (Continued):

A full flow test of all three pumps will be performed every third refueling catage. The test pressure and flow will be measured and compared to the system design basis -alues as well as results of previous tests. This test verifies the acceptable flow rate of the 4

pumps. In between full flow tests, the refueling interval test will demonstrate accident design flowrate.

Since the refueling interval tests transfer lower quality water into the steam generators, the number and duration of tests must be limited to minimize the routine exposure of the steam generators to lower quality water. This will reduce chemistry challenges to the materials of the steam generator. Minimizing the duration of the test is necessary to limit the amount of CST water injected into the steam generators where coriosion damage promoted by oxygen contamination can occur. Because of the short duration of the refueling interval tests, it may not be possible to obtain all of the vibration data.

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'Ihe EFW pump quanerly tests verify that the pumps are operational, stan on demand, and can generate the required discharge pressure. During the quarterly test, vibration data will be taken on each bearing while pumping through the recirculation line.

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TABLE A-2 TMI-I IST PUMP RETJEF REQUESTS REIJEF REQUEST NO. P 3 Component Tae No. Component Description Tvoe NR-PIA Nuclear Service River Water Pump "A" Centrifugal NR-PIB Nuclear Service River Water Pump "B" Centrifugal NR-PIC Nuclear Service River Water Pump "C" Centrifugal Code Section from Which Relief is Requested Relief is requested from OM-6, @5.2, " Test Procedure," item (d) regarding the determination of flow rate.

Alternate Test Description Flowrate for individual pumps will be measured at refueling outages.

Basis for Relief Request The test flow instrumentation for this system is located in the common discharge from all three pumps. The piping configuration does not facilitate installation of individual pump flow measuring devices. GPU Nuclear has not been successful in attaining acceptable accuracy or mpeatability using individual annubar flow instmments.

During normal plant operation, at least two of the three pumps are in operation. Operation of only one Nuclear Service River Water Pump is not allowed because of reliability concerns and could jeopardize plant equipment due to heat loads for a large part of the year. Individual flow rate measumment is impractical during plant operation or during Cold Shutdowns of short duration.

09/19/95 Page 1 of1

TABLE A-2 ,

TMI-1 IST PUMP RELIEF REQUESTS RFJJEF REQUEST NO. PG 1 Code Section fmm which Relief is Requested Relief is requested fmm OM-6, 56.1, " Acceptance Criteria". This section requires doubling the test frequency until the cause is determined and corrected for vibration readings in the alert range (0.325 ips).

Alternate Test If vibration readings are in the alert range, vibration trends and spectrum data will be evaluated. If the evaluation concludes that the vibration amplitude is above the established average by a statistically significant amount or that a significant change in the spectrum has occurred, then test frequency will be doubled until the cause is determined and corrected. Otherwise nonnal monitoring will continue.

Basis for Relief OM-6 requires doubling test frequency whenever the overall vibration amplitude reaches 0.325 ips during quarterly testing. The ,

code assumes that the equipment has degraded to the point where more frequent monitoring and possibly a repair are warranted. l There is no consideration for test conditions, vibration history, or equipment maintenance history. !

Consideration of vibration amplitudes was not part of the original acceptance criteria for pumps pmcured for many of the earlier i nuclear plants. As a result, some of the pumps purchased in the late 60's and early 70's had inherently high vibrations. During low flow conditions, typical of IST testing, vibration amplitudes are at their highest. TMI plant data, shop testing by GPU Nuclear, and conversations with several pump vendors indicate that it is not unusual to experience vibrations in excess of 0.325 ips with these older pumps, especially at low flow conditions. Provided there is a successful long term operating history 3 and provided there is no significant change in vibration amplitude or spectra, there is no reason to suspect equipment degradation i at these vibration levels. TMI's Decay Heat Removal (DHR) pumps are one specific example and show the type of valuations that we perform for pumps that exceed the alert limit.

EXAMPLE:

TMI's DHR pumps are early edition American Petroleum Institute (API) 610 process pumps. They have operated with occasionally high but untrending vibration since 1974. This includes extensive operating time between 1979 and 1985 (TMI's extended shutdown). The pumps have not failed, there is no unusual degradation in hydraulic performance, and seal and bearing r life are normal. Vibration amplitudes average 0.293 ips (standard deviation of 0.1) with the highest vibration occurring at the [

lower flow IST conditions. Because of normal variation in vibration response and measurement, measured vibration exceeds 09/19/95 Page 1 of 2 r

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l TABLE A-2 TMI-l IST PUMP RELIEF REQUESTS RFIIEF REQUEST NO. PG 1 (Continued):

0.325 ips about once per year during low flow IST operation. However, there is no upward tmnd in the data and vibration has always been at vane pass frequency.

GPU has discussed these rtNtively high vibration readings with several vendors who manufactured API pumps. The vendors stated that high vibrations a ) expected with early edition API 610 pumps, particularly at the low flow rates encountend during inservice testing.

Additionally, GPU has shop tested TMI's spare DHR pump and found that its vibration readings wem almost identical to TMI's two inservice pumps. During the shop test, vibration data were recorded at many diffemnt flow rates. At flow rates equal to and below the IST flow rate, vibrations occasionally c:tceeded 0.325 ips. This pump was inspected prior to and after the shop test to assum no degradation had occurred. The spare pump is identical to the inservice pumps and had never been used.

Based on many years of successful operating history, no step changes or trends in vibration data, extensive vibratiornnalysis, shop testing, and vendor input, GPU Nuclear does not consider the vibration amplitudes of TMI's operating decay heat pumps unacceptable. Replacing or modifying the pumps to reduce vibrations only to assure they do not occasionally exceed 0.325 ips is unnecessary. Further, doubling the test frequency would result in running the pumps more often at low flow /high vibration conditions and would provide no useful information.

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TABLE A-2 TMI-1 IST PUMP RETJEF REQUESTS -

RFJJEF REQUEST NO. PG 2 Code Section fmm Which Relief is Requested r Additional clarification to OM-6, 66.1, " Acceptance Criteria," regarding mmnr.ing of a test is mquested.

! Alternate Test Description l If the test parameter values fall outside the acceptable range in OM-6 due to an identified systematic ermr, such as an impmper :

valve hne up or maccurate instmmentation, the test will be rerun after the correction of the ermr. ,

! Basis for Relief Request There can be instances where the data gathemd during a test appears to be in question. The clarification to OM-6, f6.1 will l permit the evaluation of the condition and the remnning of the test without declaring a pump to be either in the Alen Range or ,

inoperable. The evaluation will be included in the test records. This is permitted by OM Code ISTB-1995, 66.2.3.

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l-TABLE A-2 TMI-l IST PUMP REIJFF REQUESTS RETJFF REQUEST NO. PG 3 Code Section fium Which Relief is Requested Felief is requested from OM-6, 66.1, " Acceptance Criteria," regarding doubling of test frequency in the alert range, and declaring a pump inoperable if flow or differential pressure is in the alert or required action range.

Alternate Test Descrintion If measured pump parameters fall within the alert range the test frequency will be doubled until the cause of the deviation is j found and corrected or an analysis of the pump is performed and new reference values established. He frequency of test will not be changed if the evaluation concludes that the condition does not impair the ability of the pump to fulfill its safety function.

l If measured test parameters fall within the required action range the pump shall be declared inoperable until either the cause of the deviation is determined and the condition corrected, or an analysis of the pump is performed and new reference values established. ,

Basis for Relief Request An analysis of the pump condition can demonstrate that the pump can furnish its design function especially for those pumps with large margins above their design requirement. Doubling test frequency for pumps is intended to get more data. For pumps that are normally standby, the degrading mechanism will not be active when the pump is off. Doubling test frequency may not i establish any additional information.

l l The analysis will include an evaluation of previous data to establish a trend, an investigation into the itson for the parameter l change, and if necessary the collection of additional data. The analysis will include a comparison of the test results and the

! required design parameters. To be successful, the evaluation must conclude that the condition does not impair the ability of the l pump to perform its safety function. The evaluation will be maintained in the test records.

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' Dis option was permitted by earlier editions of ASME Section XI, Subsection IWP, and is also permitted by the ASME OM Code ISTB-1995, 66.2.2. !

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09/19/95 Page I of1

i; TABLE A-3 TMI1 AUGMENTED IST PROGRAM ptsP TAOULATION PRESSURE DISCMARGE RELIEF Pter IR5eER TYPE CLASS. FlohmATE . DIFFERENTIAL PRESSimE VIBRATION .M IMWER l DRAWIIIG DF-P1A POSITIVE DISPLACEMENT A QUARTER --- ---- --- --- C-302-351'

Description:

DIESEL "A" FUEL TRANSFER PtmP (AC) ~

Justification: These pumps will be tested as part of the test of the Emergency Diesel Generater Tech Spec Surveillance. The only code -

parameter evaluated is flow rate.and the test flow rate will be calculated for this pup.

DF-P1B- POSITIVE DISPLACEMENT A QUARTER --- --- -- - ---

C-302-351

Description:

. DIESEL "A" FUEL TRANSFER PLMP (DC)

Justification: These puups will be tested as part of the test of the Emergency Diesel Generator Tech Spec Surveillance. 'The'only code parameter evaluated is flow rate and the test flow rate will be calculated for this ptsp.

DF-P1C POSITIVE DISPLACEMENT A QUARTER --- --- --- --- C-302-351

Description:

DIESEL "B" FUEL TRANSFER PUMP (AC)

Justification: These pumps will be tested as part of the test of the Emergency Diesel Generator Tech Spec Surveillance. - The only code parameter evaluated is flow rate and the test flow rate will be calculated for this pump.

DF-P1D POSITIVE DISPLACEMENT A QUARTER --- --- --- -- . C-302-351

Description:

DIESEL "B" FUEL TRANSFER PUMP (DC)

Justification: TFeme pumps will be tested as part of the test of the Emergency Diesel Generator Tech spec Surveillance. The only code rarameter evaluated is flow rate and the test flow rate will be calculated for this pump.

09/19/95 Page 1 of 1 -

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_ _ . _ > . _ _ _ _ . .. ._ _ _ . ._ .. . . _ ..~ _ _ _ _ _ _ . _ - . _ _ _ _ . _ _ . . . _ . .__ _.

APPENDIX B 1

TMI-l VALVE TEST PROGRAM

SUMMARY

OF APPENDIX B TABLE INFORMATION ,

The TMI-1 Inservice Te.st Program Valve Tabulations (Table B-1 and B-3) provide information under the following column headings:

e VALVE NO: '

Individual valve identifier (e.g., MS-V9A identifies Main Steam System Valve 9A).

e TYPE:

This column lists the type of valve as follows: i BAIL Ball Valve BUITERFLY Butterfly Valve I CONTROL Control Valve DIAPHRAGM Diaphragm Valve GATE Gate Valve GLOBE Globe Valve ;

LIFT CHECK Lift Check Valve PLUG Plug Valve RELIEF Relief Valve i SOLENOID Solenoid Valve [

STOP CHECK Stop Check Valve SW7NGCHECK Swing Check Valve THREEWAY Three Way Valve l TILTDISCCK Tilting Disc Check Valve e SIZE:

Valve Size in inches.

09/19/95 Page 1 of 4 ,

I r - _ . , -_ _ _ _

APPENDIX B '

TMI-I VALVE TEST PROGRAM

SUMMARY

OF APPENDIX B TABLE INFORMATION (CONTINUED):

o gs: ,

The ASME Code Class as Class 1, 2, or 3 for IST valves. For valves included under the Augmented IST Valve Program, "A" is shown in column under class.

e gg: i The valve category (A, B, C, or D as defined in OM-10) or combination of categories (e.g., AC) when more than one distinguishing category characteristic is applicable and hence all mquirements of each of the individual categories applies.

Categories of valves are defined in OM-10, {1.4.

e ACTIVE / PASSIVE: !

Identifies whether the valve is active (requimd to change position to accomplish the required function) or passive (not required to change position to accomplish the requimd function). For active valves, information is given to indicate the direction the valve would travel in order to fulfill the required function (e.g. [from] " CLOSED TO OPEN" [ position] if the valve must actuate to the open position, [from] "OPEN TO CLOSE" if the valve must close to perform its required function, or "BOTH" if the valve has a requimd function which demands that the valve go open under some circumstances and also has a required function which demands that the valve go closed under other circumstances).

e ACTUATOR:

The type of actuator or " operator" (e.g., Piston, Motor, Diaphragm, Hand, Solenoid, Air or Not Applicable "NA" for check valves).

e NORM POS:

The position of the valve during normal full power plant operation.

e FAIL POS:

The fail safe position for valves which have fail safe actuators.

09/19/95 Page 2 of 4

APPENDIX B TMI-I VALVE TEST PROGRAM

SUMMARY

OF APPENDIX B TABLE INFORMATION (CONTINUED):

e TEST TYPE:

This column lists the applicable tests as follows:

CLOSE Close test OPEN Open test DISASFJIBLE Disassemble and exercise the valve disc FAIL SAFE Verify the valve will move to the fail safe position FULL FLOW Check valve test to the full open condition t LEAK Seat leakage test NONINTRUSV Full open test using non-intrusive techniques PART FLOW Verify partial opening of a check valve PARTIAL Partial valve stmke l POS WRIFY Verification of the required remote position indication l SET POINT Test to verify the setpoint of a relief or safety valve l TIME Full stroke exercise and timing of the valve TIME BOTH Full stroke exercise and timing of the valve both open and close l

l e FREOUENCY:

For ea-5 test listed in the Test Type column, the test frequency is provided in the column to the right. The test frequencies l am defined as follows:

QUARTER Quarterly or once per 92 days l COLD SD Cold Shutdown APP. J Frequency required by 10 CFR 50, Appendix J '

REFUEL Refueling Interval (Once per 24 months)

ALTREFU Every other (alternating) refueling outage ,

, 4REFUFL Every fourth refueling intenal 2 YEAR Once per 2 years 5 YEAR Once per 5 years 10 YEAR Once per 10 years 09/19/95 Page 3 of 4

APPENDIX B - [

TMI-l VALVE TEST PROGRAM I

SUMMARY

OF APPENDIX B TABLE INFORMATION (CONTINUED):

o DRAWING:

This column identifies the TMI-l ISI Boundary Drawing Number on which the component is shown. For non-Code [

components the table shows the Piping and Instrumentation Drawing (P&ID) number, a "302" series drawing number. TMI-l ISI Boundary Drawings and the associated Piping & Instrumentation Diagrams (P& ids) are listed in Table 1.

e REIIIW NO:

The Valve relief request number from Appendix A, Table A-2, where applicable (e.g., V 1, V 2, etc. for specific valves or VG 1, VG 2, etc. for relief that applies generically)

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I TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO AH-V 1A BUTTERFLY 48.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB PURGE OUTLET ISOL VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR s AH-U 18 BUTTERFLY 48.0 2 A ACTIVE OPEN TO CLOSE MOTOR CLOSE AS IS LEAK APP. J ID-IS!-FD-023

Description:

NA0H TANK - SUCTION ISOLATION VALVE POS VERIFY 2 YEAR 09/19/95 Page 1 of 40

CONTAINMENT ISOLATION - BS N0ZZLE INLET CHECK VLV PART FLOW QUARTER Justification: This valve cannot be full stroke exercised with flow because initiation of flow will spray down the containment.

BS-V30B SWINGCHECK 8.0 2 C ACTIVE CLOSE TO OPEN NA CLOSE NONE DISASEMBLE 4 REFUEL 1D-ISI-FD-012 V 4

Description:

CONTAINMENT ISOLATION - BS N0ZZLE INLET CHECK VLV PART FLOW QUARTER Justification: This valve cannot be full stroke exercised with flow because initiation of flow will spray down the containment.

BS-V52A SWINGCHECK 4.0 2 C ACTIVE CLOSE TO OPEN NA CLOSE NONE DISASEMBLE 4 REFUEL 10-ISI-FD-012 V 3

Description:

NADH TANK TO LPI/BS SUCTION HEADER CHECK VALVE Justification: This valve cannot be exercised with flow because it will inject Sodiun Hydroxide into the Decay Heat Removal system.

BS-VS2B SWINGCHECK 4.0 2 C ACTIVE CLOSE TO OPEN NA CLOSE NONE DISASEMBLE 4 REFUEL 10-ISI-FD-012 V 3

Description:

NADH TANK TO LPI/BS SUCTION HEADER CHECK VALVE

, Justification: This valve cannot be eurcised with flow Lecause it will inject Sodiun Hydroxide into the Decay Heat Removal system.

i BS-V59 GATE 6.0 2 A PASSIVE HAND CLOSE AS IS LEAK REFUEL 1D-ISI-FD-012

Description:

TEST LINE ISOLATION VALVE To BWST l CA-V 2 GATE 1.0 1 A ACTIVE BOTH PISTON CLOSE CLOSE LEAK APP. J 1D-ISI-FD-020 l

Description:

CONTAINMENT ISOLATION - RC SAMPLE ISOLATION VALVE TIME BOTH QUARTER I

FAIL SAFE QUARTER POS VERIFY 2 YEAR 09/19/95 Page 2 of 40

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TOBLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TA8ULATION VALVE NO TYPE S!ZE CL_1 CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO

' CA-V 3 GLOBE 1.0 1 A ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER TD-ISI-FD-020

Description:

CONTAINMENT ISOLATION - PRZ WATER SAMPLE ISOL VLV POS VERIFY 2 YEAR l

CA-V 4A GLOBE 1.0 2 A ACTIVE OPEN TO CLOSE MOTOR CLOSE AS IS LEAK APP. J 1D-ISI-FD-020

Description:

CONTAINMENT ISOLATION - OTSG "A" FW SAMPLE VALVE TIME QUARTER POS VERIFY Z YEAR CA-V 48 GLOBE 1.0 2 A ACTIVE OPEN TO CLOSE MOTOR CLOSE AS IS LEAK APP. J 1D-ISI-FD-020 ,

Description:

CONTAINMENT ISOLATION - OTSG "B" FW SAMPLE VALVE TIME QUARTER POS VERIFY 2 YEAR CA-V SA GATE 1.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAK APP. J 1D-ISI-FD-020

Description:

CONTAINMENT ISOLATION - OTSG "A" FW SAMPLE VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CA-t15B GATE 1.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAK APP. J 1D-ISI-FD-020

Description:

CONTAINMENT ISOLATION - OTSG "B" FW SAMPLE VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CA-013 GLOBE 0.5 1 A ACTIVE BOTH MOTOR CLOSE AS IS LEAK APP. J 1D-ISI-FD-020 .

i

Description:

CONTAINMENT ISOLATION - RCS LETDOWN SAMPLE VALVE TIME BOTH QUARTER POS VERIFY 2 YEAR CA-01TT LIFT CHECK 1.0 3 C ACTIVE CLOSE TO OPEN NA CLOSE ---

PART FLOW COLD SD 10-ISI-FD-021

Description:

CA-T1 TO MAKEUP SYSTEM CHECK VALVE FULL FLOW REFUEL s Jus 2ification: Initiation of flow through this valve will inject concentrated boric acid into the Reactor Coolant System. This will adversely affect plant operation due to a reactivity change and potential control transient. Returning the concentration to the operating band will create additional radwaste to be processed. For these reasons, exercising during operation is considered to be inpractical. This is one of two alternative Tech Spec paths that may be used to bring the plant to cold shutdown. This path will not be used for a shutdown when the flow peth from the Soric ,

Acid Mix Tank is out of service. Partial stroke testing will occur during shutdowns when this flow path is used. Per OM-10, 54.3.2.2 (e), the valve will be exercised at refueling outages.

CA-V189 GATE 2.0 2 A ACTIVE OPEN TO CLOSE DIAPHRAGM OPEN CLOSE LEAK APP. J 1D-ISI-FD-021 i

Description:

CONTAINMENT INTEGRITY - RECLAIMED WATER TO RB VLV POS VERIFY 2 YEAR ,

TIME QUARTER FAIL SAFE QUARTER b

09/19/95 Page 3 of 40

_ _____ _ _ _ ____ . .~ _ .

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TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TAButATION VALVE NO TYPE SIZE ES. MT, ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO CA-V192 LIFT CHECK 2.0 2 A/C ACTIVE OPEN TO CLOSE NA CLOSE ---

LEAK APP. J 1D-ISI-FD-021 ,

Description:

CONTAIISENT ISOLATION - RECLAIMED FEED TO RB CHK Justification: Following the completion of Reactor Co)lant Pump Seal Modifications during the 11R Refueling Outage, there will be no flow through this valve ;

during normat operation. The only practical method of verifying the closed position of the valve is Appendix J testing. In accordance with the NRC's reconumendation in NUREG-1482, f4.1.4, these closed passive valves will be tested in accordance with Appendix J and extension of the test frequency is acceptable in accordance with 10 CFR 50.55atf)(4)(iv). ,

.. .....................................__....___...........................................__.......................s..................__......................

CF-U 1A GATE 14.0 2 B PASSIVE MOTOR OPEN AS IS POS VERIFY 2 YEAR 1D-ISI-FD-004

Description:

CORE FLOW TANK "A" - DISCHARGE ISOLATION VALVE r Justification: This valve is passive for its open safety fmetion and must be open during operation as required by Tech Spec 3.3.1.2 c. GPUN also performs a j stroke time test of this valve each refueling outage which is not required by the code. !

CORE FLOOD TANK "A" OUTLET CHECK VALVE PART FLOW COLD SD ;

NOMINTRUSV ALTREFU r

Justification: This valve cannot be exercised during power operations. The pressure of this system (600 psi) during power operation is significantly tower than [

+

the RCS pressure (2155 psi) and the valve cannot be opened. As permitted by OM-10, 54.3.2.2(d) the valve witt be partial stroke exercised during j cold shutdowns. This valve (CF-V4A) along with CF-V48 forms a group es defined by GL 89-04, Position 2 and NUREG 1482, Section 4.1.2. One of ;

the valves in the gro @ will be full stroke exercised every refueling outage (alternating between A & B) using nonintrusive techniques or, as an I alternative, one of the valves will be disassenbled and inspected. ,

CF-V 43 TILTDISCCK 14.0 1 A/C ACTIVE CLOSE TO OPEN NA CLOSE ---

LEAK REFUEL 1D-ISI-FD-004 Doacription: CORE FLOOD TANK "B" OUTLET CHECK VALVE PART FLOW COLD SD

[

NONINTRUSV ALTREFU ';

Justification: This valve cannot be exercised during power operations. The pressure of this system (600 psi) during power operation is significantly tower than [

the RCS pressure (2155 psi) and the valve cannot be opened. As permitted by OM-10, 64.3.2.2(d) the valve will be partial stroke exercised during '

cold shutdowns. This valve (CF-V4B) along with CF-V4A forms a gro @ as defined by GL 89-04, Position 2 and NUREG 1482, 54.1.2. One valve of the :

i group will be full stroke exercised every refueling outage (alternating between A & B) using nonintrusive techniques or, as an alternative, one valve in the group will be disassenbled and inspected. f t

I 09/19/95 Page 4 of 40

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1 VABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS_ MT ACT!YE/ PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO CF-U SA SWINGCHECK 14.0 1 A/C ACTIVE NA CLOSE ---

LEAK REFUEL 1D-ISI-FD-004

Description:

CF-T1A & DH PUMP DISCH CHECK VALVE PART FLOW COLD SD FULL FLOW REFUEL NONINTRUSV ALTREFU Justification: Leak Testing Required to fulfill T.S. 4.2.7.1. This valve camot be exercised during power operations. The pressure of this system during power operation is significantly lower than the RCS pressure and the valve cannot be opened. This valve (CF-V5A) along with CF-V5B form a grote as defined by GL 89-04, Position 2 and NUREG *402, 1S.1.2. One valve in the group will be full stroke exercised every refueling outage (alterneting l

between A & B) using nonintrusive techniques or, as an alternative, one of these valves will be disassenbled and inspected. Both valves (CF-VSA ^

and CF-V5B) will be open tested with flow every refueling outage.

CF-V 5B SWINGCHECK 14.0 1 A/C ACTIVE NA CLOSE ---

LEAK REFUEL 1D-ISI-FD-004

Description:

CF-T1B & DH PUMP DISCH CHECK VALVE PART FLOW COLD SD FULL FLOW REFUEL NONINTRUSV ALTREFU Justification: Leak Testing Required to fulfill T S. 4.2.7.1. This valve cannot be exercised during power operations. The pressure of this system dJring power operation is significantly lower than the RCS pressure and the valve cannot be opened. This valve (CF-V5B) along with CF-V5A form a gret ,as defined by GL 89-04, Position 2 and NUREG-1482, 14.1.2. One valve in the group will be full stroke exercised every refueling outage (etternating l between A & B) using nonintrusive techniques or, as an alternative, one of these valves will be disassenbled and inspected. Both valves (CF-VSA i

and CF-V5B) will be open tested with flow every refueling outage, f

CF-V12A LIFT CHECK 1.0 2 A/C ACTIVE OPEN TO CLOSE NA CLOSE ---

CONTAINMENT ISOLATION - CF-T1B SAMPLE ISOL VLV TIME QUARTER l FAIL SAFE QUARTER POS VERIFY 2 YEAR l _.___....................... ............................____...................._____._____................ ..__.................__.___....___.___.............

[ CH-V22A SWINGCHECK 4.0 3 C ACTIVE BOTH NA --- ---

FULL FLOW QUARTER 10-ISI-FD-011

Description:

AH-C3B CHILLED WATER DISCHARGE CHECK VALVE CLOSE QUARTER CH-V22B SWINGCHECK 4.0 3 C ACTIVE BOTH NA --- ---

FULL FLOW QUARTER TD-ISI-FD-011 i

Description:

AH-C3B CHILLED WATER DISCHARGE CHECK VALVE CLOSE QUARTER CM-V1 BALL 1.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAIMMENT ISOLATION - RB ATMOSPHERE SAMPLE VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CM-V2 BALL 1.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-023 Drscription: CONTAINMENT ISOLATION - RB ATMOS SAMPLE RETURN VLV TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CM-V3 BALL 1.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB ATMOSPHERE SAMPLE VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CM-V4 BALL 1.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB ATMOS SAMPLE ISOL VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR CO-V 14A GATE 12.0 3 B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-008 D:scription: CONDENSATE STORAGE TANK "A" ISOLATION VALVE POS VERIFY 2 YEAR Justification:

CD-V 14B GATE 12.0 3 B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-008

Description:

CONDENSATE STORAGE TANK "B" ISOLATION VALVE POS VERIFY 2 YEAR CO-V 16A SWINGCHECK 10.0 3 C ACTIVE NA --- .--

PART FLOW QUARTER 1D-ISI-FD-009

Description:

CONDENSATE CHECK VALVE - SUPPLY TO EFW PUMPS FULL FLOW REFUEL Justification: Initiating flow through this valve requires that the Emergency Feedwater Pump be operating. These ptaps are operated quarterly on minista flow recirculation. This flowrate is insufficient to open the valve fully. Full flow requires injection into the OTSG. This is impractical because injecting unheated water from the Condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the auxiliary feedwater nozzles and OTSG tubes. Further, injection from the Condensate Storage Tank will introduce oxygenated water into the Steam Generators.

09/19/95 Page 6 of 40

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l TABLE B-1 TMil INSERVICE TEST PROGRAM VALVE TABULATION l

VALVE NO TYPE S!ZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO l

j The exposure of the Steam Generator tubes to oxygenated water must be minimized. While performance of the test at cold shutdown is not strictly !

impracticable, it is not prudent to change water chemistry solely for this test. As permitted by OM-10 54.3.2.2 (e) the valve will be fuit stroked at refueling outages.

l i CD-U 168 SWINGCHECK 10.0 3 C ACTIVE NA --- ---

DECAY HEAT SUCTION ISOLATION FROM "B" HOT LEG POS VERIFY 2 YEAR Justification: DH-V1 is a high pressure valve in the Decay Heat drop line (suction to LPI pumps). During normat plant operation, DH-V1 cannot be cycled because it would reduce redmdancy by providing only one high pressure valve between the RCS and the low pressure Decay Heat Removat System. In addition, the valves are interlocked with RCS pressure such that they cannot be opened unless RCS pressure is less than 400 psig. Per OM-10, !

E4.2.1.2 c, these valves will be tested at cold shutdowns.

DH-U 2 GATE 12.0 1 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME COLD SD 1D-ISI-FD-005

Description:

CONTA!NMENT ISOLATION - DH DROP LINE/ PUMP SUCTION POS VERIFY 2 YEAR Justification: During normal plant operation, DH-V2 cannot be cycled because it would reduce redundancy by providing only one high pressure valve between the ;

RCS and the low pressure Decay Heat Removal System. In addition, the valves are interlocked with RCS pressure such that they cannot be opened t unless RCS pressure is less than 400 psig. Per OM-10, 64.2.1.2 c, these valves will be tested at cold shutdowns.

09/19/95 Page 7 of 40

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TABLE B-1 TC11 ICSERVICE TEST PQ0 GRAM VALVE VABULATI C VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR WORM POS Fall POS TEST TYPE FREQUENCY DRAWING REllEF NO DH-V 3 GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE As IS TIME QUARTER 10-ISI-FD-005

Description:

CONTAINMENT ISOLATION - DH DROP LINE VLV POS VERIFY 2 YEAR DH-V 4A GATE 10.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME COLD SD 1D-ISI-FD-005

Description:

CONTAINMENT ISOLATION - DH-P1A DISCHARGE ISOL VLV POS VERIFY 2 YEAR Justification: This valve is in series with valves DH-V22A and CF-VSA. If there is leakage past DM-V22A and CF-V5A, opening DM-V4A during operation could subject the DH sytem to a pressure in excess of its design pressure. For this reason, the stroke test will be performed at cold shutdowns. This is as described in NUREG 1482, 63.1.1, (3).

DM-V 4B GATE 10.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME COLD SD 1D-ISI-FD-005

Description:

CONTAINMENT ISOLATION - DH-P1B DISCH ISOL VALVE POS VERIFY 2 YEAR Jus 2ification: This valve is in series with valves DH-V22B and CF-V5B. If there is leakage past DH-V228 and CF-V5B, opening of DM-V4B during operation could subject the DH sytem to a pressure in excess of its design pressure. For this reason, the stroke test will be performed at cold shutdowns. This is as described in NUREG 1482, 13.1.1, (3).

DH-C1A DISCHARGE VALVE TO MAKEUP SYSTEM POS VERIFY 2 YEAR '

CLOSE QUARTER DH-V 7B GATE 4.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS .3 TIME QUARTER 1D-ISI-FD-005

DH-P1A DISCHARGE CHECK VALVE FULL FLOW REFUEL Justification: Full flow testing of this valve requires that the DH system inject into the Reactor Coolant System. This cannot be done during power operation because the RCS pressure is higher than the design pressure of the DH system and exceeds the capability of the DH ptmps. The valves can be exercised quarterly with partial flow through a test line. Both valves will be tested charing each refueling. Full flow testing of both valves is considered to be inpractical for short duration cold shutdowns since only one DH train is normally utilized.

DH-V168 SWINGCHECK 10.0 2 C ACTIVE CLOSE TO OPEN NA --- ---

PART FLOW QUARTER 1D-IS!-FD-005

Description:

DECAY HEAT PUMP "B" DISCHARGE CHECK VALVE FULL FLOW REFUEL Justification: Full flow testing of this valve requires that the DH system inject into the Reactor Coolant System. This cannot be done during power operation because the RCS pressure is higher than the design pressure of the DH system and exceeds the capability of the DH ptmps. The valves can be exercised quarterly with partial flow through a test line. Both valves will be tested during each refueling. Full flow testing of both valves is considered to be inpractical for short duration cold shutdowns since only one DH train is normally utilized.

09/19/95 Page 9 of 40

TABLE B-1 TM11 INSERVICE TEST PROGRAM VALVE TABULAT!ON VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM rOS FAIL POS TEST TYPE FREQUENCY DRAWING REllEF NO DM-V21 GLOBE 3.0 3 A PASSIVE MAND CLOSE ---

LEAK REFUEL 1D-ISI-FD-005

==

Description:==

DH PUMPS DISCHADGE TEST ISOLATION VALVE DM-V22A TILTDISCCK 10.0 1 A/C ACTIVE NA CLOSE ---

LEAK REFUEL 1D-ISI-FD-005

==

Description:==

CONTAINMENT ISOLATION - DH-P1A DISCHARGE CHK TO CF PART FLOW COLD SD FULL FLOW REFUEL Justification: Leak testing is required to fulfill T.S. 4.2.7.1. This valve cennot be exercised during power operations. The pressure of this system & ring power operation is significantly lower than the RCS pressure and the valve cannot be opened. At a mininua, one of the DH-V22 valves will will be exercised during cold shutdowns. Botn valves will be tested each refueling. Full flow testing of both valves is considered to be inpractical for short duration cold shutdowns since only one DH train ic normally utilized.

DM-V228 TILTDISCCK 10.0 1 A/C ACTIVE NA CLOSE ---

LEAK REFUEL 1D-ISI-FD-005

==

Description:==

CONTA! M i ISOLATION - DH-P1B DISCH CHK TO CF PART FLOW COLD SD FULL FLOW REFUEL Justification: Leak testing is required to fulfitt T.S. 4.2.7.1. This valve cannot be exercised during power operations. The pressure of this system & ring power operation is significantly lower than the RCS pressure and the valve cannot be opened. At a minimum one of the DM-V22 valves will be exercised during cold shutdowns. Both valves will be tested each refueling. Futt flow testing of both valves is considered to be impractical for short duration cold shutdowns since only one DH train is normally utilized.

DH-V38A GATE 6.0 2 B ACTIVE CLOSE TO OPEN HAND CLOSE ---

OPEN QUARTER 1D-ISI-FD-005

==

Description:==

DECAY HEAT CROSSOVER VALVE CLOSE QUARTER DM-U388 GATE 6.0 2 B ACTIVE CLOSE TO OPEN HAND CLOSE ---

OPEN QUARTER 1D-ISI-FD-005

==

Description:==

DECAY HEAT CROSSOVER VALVE CLOSE QUARTER DH-V50 SWINGCHECK 4.0 2 C PASSIVE NA CLOSE ---

ID-ISI-FD-005 V 2

==

Description:==

SPENT FUEL RETURN CLEANUP CHECK VALVE DH-V64 GLOBE 2.0 2 A ACTIVE BOTH HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-005

==

Description:==

CONTAINMENT ISOLATICN - DH 10 PZR SPRAY ISOL VLV OPEN QUARTER -

DM-V69 SWINGCHECK 1.5 2 A/C ACTIVE BOTH NA ODEN ---

LEAK APP. J 1D-ISI-FD-005

==

Description:==

CONTAINMENT ISOLATION - DH TO PZR AUX SPRAY LINE FULL FLOW COLD SD Justification: This valve is in the discharge of the Decay Heat Removal pwps. The valve open safety function is to provide long term core circulation to prevent boron concentration. The open function of the check valve cannot be tested quarterly. Decay Heat (LPI) pW ps have a discharge pressure in the order of 200 psig. During normal plant operation, these valves cannot be opened because the RCS pressure is approximately 2155 psig. The valve will be flow tested during cold shutdown as permitted by OM 10, 64.3.2.2 (c). t DR-V1A BUTTERFLY 20.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-002

==

Description:==

DR-P1A DISCHARGE VALVE POS VERIFY 2 YEAR h

09/19/95 Page 10 of 40

TABLE B-1 TM11 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CL_S, EAT, ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO DR-V1B BUTTERFLY 20.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 10-ISI-FD-002

==

Description:==

DR-P1B DISCHARGE VALVE POS VERIFY 2 YEAR DR-V7A SWINGCHECK 2.0 3 C ACTIVE OPEN TO CLOSE NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-002

==

Description:==

DR-P1A COLUMN VACUUM BREAKER CLOSE QUARTER DR-V7B SWINGCHECK 2.0 3 C ACTIVE OPEN TO CLOSE NA --- ---

FULL FLOW QUARTER 10-ISI-FD-002

==

Description:==

DR-P1B COLUMN VACUUM BREAKER CLOSE QUARTER EF-V 2A GATE 6.0 3 8 ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-009

==

Description:==

EFW PUMP DISCHARGE HEADER CROSS CONNECT VALVE POS VERIFY REFUEL EF-V 28 GATE 6.0 3 B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-009

==

Description:==

EFW PUMP DISCHARGE HEADER CROSS CONNECT VALVE POS VERIFY REFUEL EF-V 4 GATE 6.0 3 8 ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-010 D acription: EMERGENCY RIVER WATER SUPPLY TO EFW PUMPS TIME REFUEL POS VERIFY 2 YEAR EF-v 5 GATE 6.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-010

==

Description:==

EMERGENCY RIVER WATER SUPPLY TO EFW PUMPS TIME REFUEL POS VERIFY 2 YEAR EF-V11A TILTDISCCK 4.0 3 C ACTIVE NA --- ---

FULL FLOW REFUEL 1D-ISI-FD-009

==

Description:==

EF-P2A DISCHARGE CHECK VALVE CLOSE REFUEL Justification: These check valves are on the discharge of peps EF-P2A/B. The EF pumps are tested quarterly on recirculation with the stean generators isolated. Since the recirculation line is upstream of these valves there is no flow to open them. Initiation of flow through the valves during power operation would inject cold water into a hot steam generator. This is impractical because injecting cold water from the Condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the tubes and Emergency Feedwater nozzles. Further, injection from the Condensate Storage Tank will introduce oxygenated water into the Steam Generators. The exposure of the Steam Generator tubes to oxygenated water, especially during short shutdowns, must be minimized. The closed test requires the closing of one injection line to the OTSG and the cross connecting of two of the three Emergency Feedwater Ptaps. This effectively removes two pugs from service. This is not desirable nor permitted by the Tech Specs when the plant is operating. During short duration or unplanned Cold Shutdowns, the test could extend the outage.

As permitted by OM-10, 54.3.2.2 te), flow testing and closed testing of the valves will be performed at a refueling outage frequency.

EF-V118 TILTDISCCK 4.0 3 C ACTIVE NA --- ---

FULL FLOW REFUEL 1D-ISI-FD-009

==

Description:==

EF-P2B DISCHARGE CHECK VALVE CLOSE REFUEL Justification: These check valves are on the discharge of pe ps EF-P2A/B. The EF pumps are tested quarterly on recirculation with the steam generators isolated. Since the recirculation line is upstream of these valves there is no flow to open them. Initiation of flow through the valves during power operation would inject cold water into a hot steam generator. This is impractical because injecting cold water from the condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the tubes and the Emergency Feedwater nozzles. Further, injection from the Condensate Storage Tank will introduce oxygenated water into the Steam Generators. The exposure of the Steam Generator tubes to oxygenated water, especially during short shutdowns, must be minimized. The closed test requires tt>e closing of one injection line to the OTSG and the cross connecting of two of the three Emergency Feedwater Pu gs. This effectively removes two ptmps from service. This is not desirable nor 09/S9/95 Page 11 of 40

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' BLE B-1 TM11 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO permitted by the Tech Specs when the plaat is operating. During short duration or ts1 planned Cold Shutdowns, the test could extend the outage.

As permitted by OM-10, 14.3.2.2 (e), flow testing and closed testing of the valves will be a: a refueling outage frequency.

EF-V12A TILTDISCCK 6.0 2 C ACTIVE NA CLOSE ---

FULL FLOW REFUEL 1D-ISI-FD-009

Description:

CONTAINMENT ISOLATION - EFW TO OTSG "A" CHECK VLV CLOSE REFUEL Justification: This is the last valve in the flowpath before feedwater reaches the steam generator. Initiation of flow through these valves during power operation would inject cold water into a hot steam generator. This is considered to be impractical because injecting cold water from the i Condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the Emergency Feedwater nozzles and tubes. Further, injection f rom the Condensate Storage Tank will introduce oxygenated water into the Steam Generators. The exposure of the Steam Generator tubes to oxygenated water, especially during short cold shutdowns, must be minimized. The closed test cannot be performed at power because it would >

drain the injection pipe. The pipe would need to be refilled. The refill operation may cause injection into the OTSG. This is not desirable for the reasons stated above. The closed test requires that the OTSG be isolated and pressurized with Nitrogen. This is not practical for short ts1 planned Cold Shutdowns. The valve will be tested at refueling outages as permitted by OM-10, 64.3.E.2 (e).

EF-V128 TILTDISCCK 6.0 2 C ACTIVE NA CLOSE ---

FULL FLOW REFUEL 1D-ISI-FD-009

Description:

CONTAINMENT ISOLATION - EFW TO OTSG "B" CHECK VLV CLOSE REFUEL

! Justification: This is the last valve in the flowpath before feedwater reaches the steam generator. Initiation of flow through these valves during power j operation would inject cold water into a hot steam generator. This is considered to be igractical because injecting cold water from the l Condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the Emergency Feedwater nozzles and tubes. Further, I

injection from the Condensate Storage Tank will introduce oxygenated water into the Steam Generators. The exposure of the Steam Generator tubes to oxygenated water, especially during short cold shutdowns, must be minimized. The closed test cannot be performed at power because it would drain the injection pipe. The pipe would need to be refilled. The refill operation may cause injection into the OTSG. This is not desirable for the reasons stated above. The closed test requires that the OTSG be isolated and pressurized with nitrogen. This is not practical for short unplanned Cold Shutdowns. The valve will be tested at a refueling outage frequency as permitted by OM-10, 14.3.2.2 (e).

EF-V13 TILTDISCCK 6.0 3 C ACTIVE NA --- ---

PART FLOW QUARTER 10-Ist-FD-009

Description:

EF-P1 DISCHARGE CHECK VALVE FULL FLOW REFUEL CLOSE REFUEL Justification: This check valve is on the discharge of the turbine driven Emergency Feedwater Ptmp (EF-P1). The EF pu g s are tested quarterly on recirculation with the steam generators isolated. Since the recirculation line is upstream of these valves, there is no flow to open them. Initiation of flow through the valves during power operation would inject unheated water into a hot steam generator. This is considered to be igractical because injecting unheated water from the Condensate Storage Tank into the hot Steam Generator during operation would thermally cycle the Emergency Feedwater nozzles and the Steam Generator tubes. Further, injection from the Condensate Storage Tank will introduce oxygenated water into the Steam Generators. The exposure of the steam Generator tubes to oxygenated water, especially during short shutdowns, must be minimized. A partial stroke is performed quarterly by flowing water through a drain valve. The closed test will not be performed at power because it would render part of the system inoperable and remove redundancy for providing Emergency Feedwater to each Steam Generator. The closed test requires that the OTSG be isolated and pressurized with nitrogen. This is not practical for short triplanned Cold shutdowns. As permitted by OM-10, 54.3.2.2 (e), flow testing of the valves will be performed at a refueling outage frequency.

09/19/95 Page 12 of 40

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TABLE B-9 TMll INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CL_S C E ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO EF-V19A LIFT CHECK 1.5 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-009

Description:

EF-P2A RECIRC LINE CHECK VALVE CLOSE QUARTER EF-V19B LIFT CHECK 1.5 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-009

Description:

EF-P2B RECIRC LINE CHECK VALVE CLOSE QLfJtTER EF-V21 LIFT CHECK 2.0 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 10-ISI-FD-009

Description:

EF-P1 RECIRCULATION CHECK VALVE CLOSE QUARTER EF-V30A CONTROL 3.0 2 B ACTIVE BOTH DIAPHRAGM CLOSE CLOSE TIME BOTH QUARTER 10-ISI-FD-009

Description:

EFW TO OTSG "A" FLOW CONTROL VALVE Fall SAFE QUARTER POS VERIFY 2 YEAR OPEN REFUEL CLOSE REFUEL Justification: 7"r open and close tests are not required by Code, this testing is part of the augmented testing of 2-Hr Backup Air switching valves (IA-V1625 and IA-V1626).

t EF-v30B CONTROL 3.0 2 B ACTIVE BOTH DIAPHRAGM CLOSE CLOSE TIME BOTH QUARTER 1D-ISI-FD-009 1

Description:

EFW TO OTSG "B" FLOW CONTROL VALVE FULL QUARTER l POS VERIFY 2 YEAR OPEN REFUEL CLOSE REFUEL Justification: The open and close tests are not required by Code, this testing is part of the augmented testing of 2-Hr Backtp Air switching valves (IA-V1625 and IA-V1626).

EF-V30C CONTROL 3.0 2 B ACTIVE BOTH DIAPHRAGM CLOSE CLOSE TIME BOTH QUARTER 1D-ISI-FD-009 IK;Ocription: EFW TO OTSG "A" FLOW CONTROL VALVE Fall SAFE QUARTER POS VERIFY 2 YEAR OPEN REFUEL CLOSE REFUEL Justification: The open and close tests are not required by Code, this testing is part of the augmented testing of 2-Hr Backup Air switching valves (IA-V1625 and IA-V1626).

EF-V30D CONTROL 3.0 2 B ACTIVE BOTH DIAPHRAGM CLOSE CLOSE TIME BOTH QUARTER 1D-ISI-FD-009

Description:

EFW TO OTSG "B" FLOW CONTROL VALVE FAIL SAFE QUARTER l

POS VERIFY 2 YEAR OPEN REFUEL

( CLOSE REFUEL

( Justification: The open and close tests are not required by Code, this testing is part of the augmented testing of 2-Hr Backup Air switching valves (IA-V1625 i and IA-V1626).

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09/19/95 Page. 13 of 40 r- as :e-

TABLE B-1 TMit INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CL_S [AT, ACTIVE / PASSIVE ACTUATOR NORM POS Fall POS TEST TYPE FREQUENCY DRAWING REllEF NO FW-V12A TILTDISCCK 20.0 2 C ACTIVE OPEN To CLOSE NA OPEN ---

CLOSE REFUEL 10-ISI-FD-009

==

Description:==

CONTAINMENT ISOLATION - OTSG "A" INLET CHECK VALVE Justification: This valve supplies feedwater to the Steam Generator during plant operation. Any stroke testing dJring operation is lupossible. To perform the closed portion of the cycle test, condenser vacuun must be broken and the Steam Generator pressurized with nitrogen. This evolution requires significant resources and is considered to be inpractical for cold shutdowns. Per CM-10, 54.3.2.2(e) this valve will be tested on a refueling outage frequency.

FW-V128 TILTDISCCK 20.0 2 C ACTIVE OPEN TO CLOSE NA OPEN ---

CLOSE REFUEL 1D-ISI-FD-009

==

Description:==

CONTAINMENT ISOLATION - OTSG "B" INLET CHECK VALVE Justification: This valve stypties feedwater to the Steam Generator during plant operation. Any stroke testing during operation is impossible. To perform the closed portion of the cycle test, condenser vacuun must be broken and the Steam Generator pressurized with nitrogen. This evolution requires significant resources and is considered to be inpractical for cold shutdowns. Per OM-10, 54.3.2.2(e) this valve will be tested on a refueling outege frequency.

MM-V1A GLOBE 1.0 2 A ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

==

Description:==

CONTAINMENT ISOLATION - H2 MONITOR "A" OUTLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR HM-V1B GLOBE 1.0 2 A ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

==

Description:==

CONTAINMENT ISOLATION - H8 MONITOR "B" OUTLET ISOL TIME QUARTER Fall SAFE QUARTER POS VERIFY 2 YEAR HM-V2A GLOBE 1.0 2 A ACTIVE CLOSE To OPEN SOLEN 0!D CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

==

Description:==

CONTAINMENT ISOLATION "A" H' MONITOR INLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR HM-V2B GLOBE 1.0 2 A ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

==

Description:==

CONTAINMENT ISOLATION "B" M' MONITOR INLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR HM-V3A SOLEN 0!D 1.0 2 A ACTIVE CLOSE To OPEN SOLEN 010 CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023 DGscription: CONTAINMENT ISOLATION "A" H8 MONITOR OUTLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR 09/19/95 Page 14 of 40

TABLE B-9 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE g 4 M J, ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO HM-V3B SOLENCID 1.0 2 A ACTIVE CLOSE TO OFEN SOLENOID CLOSE ClosE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION *B" H8 MONITOR OUTLET ISOL TIME QUARTER Fall SAFE QUARTER POS VERIFY 2 YEAR HM-V4A SOLENOID 1.0 2 A ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION "A" H8 MONITOR OUTLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR HM-V4B SOLENOID 1.0 2 A ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION "B" N' MONITOR OUTLET ISOL TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR HP-Vi GATE 6.0 2 A PASSIVE HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-023 DGscription: CONTAINMENT ISOLATION - H8 PURGE ISOLATION VALVE HP-V6 GATE 6.0 2 A PASSIVE HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-023 DGscription: CONTAINMENT ISOLATION - N' PURGE RB ISOL VALVE HR-V 2A GLOBE 2.0 2 A ACTIVE CLOSE TO OPEN HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-015

Description:

CONTAINMENT ISOLATION - HR-R1A/B RB SUPPLY VALVE OPEN QUARTER CLOSE QUARTER HR-V 2B GLOBE 2.0 2 A ACTIVE CLOSE TO OPEN HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-015

Description:

CONTAIRMENT ISOLATION - HR-R1A/B RB SUPPLY OPEN QUARTER CLOSE QUARTER HR-V 4A GLOBE 2.0 2 A ACTIVE CLOSE TO OPEN HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-015

Description:

CONTAINMENT ISOLATION - HR-R1A/9 RB RETURN VALVE OPEN QUARTER CLOSE QUARTER HR-U 48 GLOBE 2.0 2 A ACTIVE CLOSE TO OPEN HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-015 OGstription: CONTAINMENT ISOLATION - HR-R1A/B RB RETURN VALVE OPEN QUARTER CLOSE QUARTER HR-V22A GLOBE 2.0 2 A ACTIVE BOTH SOLENOID CLOSE CLOSE LEAK APP. J 1D-IS!-FD-015

Description:

CONTAINMENT ISOLATION - RB EXHAUST TO H2 RECOMB TIME BOTH QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR 09/19/95 Page 15 of 40

CONTAINMENT ISOLATION - IA INNER RB ISOL VALVE Jus 2ification: The valve is a passive component. Per OM-10, Table 1, no valve exercise will be performed.

IC-V 2 GATE 6.0 3 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 1D-ISI-FD-022 DGscription: CONTAINMENT ISOLATION - ICCW COOLANT RETURN VALVE PARTIAL QUARTER TIME COLD SD POS VERIFY 2 YEAR

! Justification: Full Stroke Exercise of this valve during power operation will isolate cooling water returning from the Primary Letdown Coolers, Control Rod l Drive Cooling coils, and the Reactor Coolant Ptsnp Heat Exchangers. Operation of this valve during power operation will jepordize Control Rod Drive Stators and cause thermal cycling of the Letdown Coolers. As per OM-10, 54.2.1.2(d), this valve will be full stroke exercised at the Cold shutdown frequency.

IC-V 3 PLUG 6.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-022 l

Description:

CONTAINMENT ISOLATION - ICCW COOLANT RETURN VALVE PARTIAL QUARTER TIME COLD SD FAIL SAFE COLD SD POS VERIFY 2 YEAR Justification: Full Stroke Exercise of this valve during power operation will isolate cooling water returning from the primary Letdown Coolers, Control Rod Drive Cooling Coils, and the Reactor Coolant Ptsnp Heat Exchangers. Operation of this valve during power operation will cause thermal cycling cf the Letdown Cooler. This is not tolerable. As per OM-10, 64.2.1.2(d), this valve will be full stroke exercised at the Cold Shutdown frequency.

09/19/95 Page 16 of 40

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TABLE B-1 TMIT INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL PCS TEST TYPE FREQUENCY DRAWING REllEF NO l

CONTAINMENT ISOLATION - LETDOWN SUPPLY CHECK VLV Justification: Stopping flow through this valve to cycle it closed will stop all cooling to the RC Pump Coolers, Letdown Coolers, and the Reactor Coolant Drain Tank Heat Exchanger. This would cause a thermal cycle on the above equipment. Since the only practical means available to test this valve is setting up test equipment and performing leak rate testing as required by Appendix J, the test frequency has been extended to refueling as permitted by NUREG 1482, 54 1.4 (NRC Recorsnendation).

MS-V 1A STOP CHECK 24.0 2 B/C ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS PARTIAL QUARTER 1D-ISI-FD-001

Description:

CONTAINMENT ISOLATION - OTSG "A" MS ISOL VALVE TIME COLD SD POS VERIFY 2 YEAR CLOSE REFUEL Justification: Full stroke testing of this valve during power operation would cause turbine pressure instabilities and may cause possible chalenges to safety valves upstream. This valve will be partial stroke tested quarterly and full stroke exercised at Cold Shutdown as permitted by OM-10, 14.2.1.2(b). The close test of the check function requires that one OTSG be depressurized while pressure on the other is monitored.

Effectively, the closed function is verified by leak test. This test can only be done during normal shutdowns (not turbine trip). The test is performed when the generator is taken off line but before the turbine is tripped. The test lengthens the shutdown process ard does intait some risk. As permitted by OM-10 94.3.2.2(e) the close test is performed during refueling.

09/19/95 Page 17 of 40

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! i TABLE B-1 TMll INSERVICE TEST PROGRAM VALVE TA8ULATION I

VALVE NO TYPE SIZE C S, _C M ACTIVE / PASSIVE ACTUATOR NORM POS F_AR,f A _0S TEST TYPE FREQUENCY DRAWING RELIEF NO l

MS-V 18 STOP CHECK 24.0 2 B/C ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS PARTIAL QUARTER 10-ISI-FD-001 1

Description:

CONTAINMENT ISOLATION - OTSG "A" MS ISOL STOP CHK TIME COLD SD POS VERIFY 2 YEAR

! CLOSE REFUEL Justification: Full stroke testing of this valve during power operation would cause turbine pressure instabilities and may cause possible chalenges to safety valves upstream. This valve wi*l be partial stroke tested quarterly and full stroke exercised at cold shutdown as permitted by OM-10, 14.2.1.2(b). The close test of the check function requires that one OTSG be depressurized while pressure on the other is monitored.

Effectively, the closed function is verified by teak test. This test can only be done during normal shutdowns (not turbine trip). The test is perfonned when the generator is taken off line but before the turbine is tripped. The test lengthens the shutdown process and does intait some risk. As permitted by OM-10 14.3.2.2(e) the close test is performed during refueling.

CS-V 1C STOP CHECK 24.0 2 B/C ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS PARTIAL QUARTER 10-ISI-FD-001 DGscription: CONTAINMENT ISOLATION - OTSG "B" MS ISOL STOP CHK TIME COLD SD POS VERIFY 2 YEAR

CLOSE REFUEL Justification: Full stroke testing of this valve during power operation would cause turbine pressure instabilities and may cause possible chalenges to safety valves upstream. This valve will be partial stroke tested quarterly and full stroke exercised at cold shutdown as permitted by OM-10, 14.2.1.2(b). The close test of the check function recpires that one OTSG be depressurized while pressure on the other is monitored.

Effectively, the closed function is verified by leak test. This test can only be done during normat shutdowns (not turbine trip). The test is performed when the generator is taken off line but before the turbine is tripped. The test lengthens the shutdown process and does intait some risk. As permitted by oM-10, 54.3.2.2(e) the close test is performed during refueling.

MS-U 1D STOP CHECK 24.0 2 B/C ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS PARTIAL QUARTER 1D-ISI-FD-001

Description:

CONTAINMENT ISOLATION - OTSG "B" MS ISOL STOP CHK TIME COLD SD POS VERIFY 2 YEAR CLOSE REFUEL Justification: Full stroke testing of this valve during power operation would cause turbine pressure instabilities and may cause possible chalenges to safety valves upstream. This valve will be partial stroke tested quarterly and full stroke exercised at cold shutdown as permitted by OM-10, 54.2.1.2(b). The close test of the check function requires that one OTSG be depressurized while pressure on the other is monitored. l Effectively, the closed function is verified by leak test. This test can only be done during normal shutdowns (not turbine trip). The test is i performed when the generator is taken off line but before the turbine is tripped. The test lengthens the shutdown process and does intait some risk. As permitted by OM-10, 54.3.2.2(e) the close test is performed during refueling.

MS-U 2A GATE 12.0 2 B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME QUARTER 10-Ist-FD-001

Description:

OTSG "A" MS TO EF-P1 & TURBINE BYPASS VALVES POS VERIFY 2 YEAR MS-V 2B GATE 12.0 2 B ACTIVE OPEN TO CLCSE MOTOR OPEN AS IS TIME QUARTER 10-ISI-FD-001

Description:

OTSG "B" TO EF-P1 & TURBINE BYPASS VALVES POS VERIFY 2 YEAR ,

t b

i 09/19/95 Page 18 of 40

. . . .._ _________ -_ - ______m__ m

TABLE B-1 TM11 INSERVICE TEST PROGRAM VALVE TABULATION VALVE No ' TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO MS-V 4A CONTROL 6.0 3 B ACTIVE CLOSE TO OPEN PISTON CLOSE CLOSE TIME QUARTER 1D-ISI-FD-001

Description:

ATMOSPHERIC DUMP VALVE FOR OTSG "A" FAIL SAFE QUARTER POS VERIFY QUARTER Justification: Position Verification required quarterly per NRC Conunittment.

MS-V 48 CONTROL 6.0 3 B ACTIVE CLOSE TO OPEN PISTON CLOSE CLOSE TIME QUARTER 1D-ISI-FD-001

Description:

ATMOSPHERIC DUMP VALVE FOR OTSG "B" FAIL SAFE QUARTER POS VERIFY QUARTER Jus 2ification: Position verify required each quarter per NRC conunittment.

MS-V 6 GLOBE 4.0 3 B ACTIVE DIAPHRAGM OPEN OPEN TIME QUARTER 1D-ISI-FD-001 DGscription: EF-P1 MS PRESSURE REGULATOR CONTROL VALVE FAIL SAFE QUARTER Justification: This valve will be tested with the Emergency Feed Ptap Turbine. The valve is considered to be a "Skiri Mounted Component" as defined in NUREG 1482, 53.4. The only m?thod available to open this valve is to change the setpoint of its pressure controtter. This is a precise setpoint that is relied upon to prevent opening of the turbine driver safety valves. The setpoint should not be routinely changed. The controller must then be returned to the pretest setpoint. Since, the valve stroke cannot be directly measured, obturator movement will be monitoring by the startup time of the Emergency Feedwater Ptsp Turbine to verify the proper functioning of MS-V6. This is as permitted by OM-10, 54.2.1.3. The valve stroke will be that required to accelerate the turbine.

MS-V 8A GATE 12.0 3 B PASS!VE MOTOR OPEN AS IS POS VERIFY 2 YEAR 1D-ISI-FD-001 DGscription: OTSG "A" TO MS-V3D, 3E & 3F ISOLATION VALVE Justification: Normal Decay Heat Removat is by the steam generator to the condenser via this valve and the turbine bypass valves. This valve is passive in that it is open as required per T.S. 3.4.1.1.b. during operation. Per OM-10, Table 1 the only test required is position verification.

MS-V 8B GATE 12.0 3 B PASSIVE MOTOR OPEN AS IS POS VERIFY 2 YEAR 10-ISI-FD-001

Description:

OTSG "B" TO MS-V3A, 3B & 3C ISOL VALVE Jus 2ification: Normal decay heat removat is by the steam generator to the condenser via this valve and the turbine bypass valves. This valve is passive in that it is open as required per T.S. 3.4.1.1.b. during operation. Per OM-10, Table 1 the only test required is position verification.

MS-U 9A SWINGCHECK 6.0 3 C ACTIVE NA --- ---

PART FLOW QUARTER 1D-ISI-FD-001

Description:

MAIN STEAM SUPPLY CHECK VALVE TO EF-U1 DISASEMBLE ALTREFU Justification: Thie valve supplies steam from the OTSG to the Turbine Driven Emergency Feedwater Punp. This valve cannot be full stroke exercised during operation because such an evolution would require injecting low tenperature condensate into the operating OTSG. Injecting cold water into the OTSG will thermally cycle the tubes and Emergency Feedwater nozzles, which should be avoided. A partial stroke is possible through the testing of the punp on recirculation. As permitted by OM-10, 14.3.2.2(b) a partial stroke test will be conducted quarterly. This valve (MS-V9A) along with MS-V98 forms a group as described in Generic Letter 89-04, Positon No. 2 and NUREG-1482 in that they are identical, mounted the same manner, and see the same service. One valve in the group will be disassenbled and inspected and the disc manually exercised every refueling outage alternating between A and B (the interval for each valve is every other refueling outage). If the inspected valve is found to be unacceptable, the other valve in the group will be inspected during the same outage.

09/19/95 Page 19 of 40

TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE ES CAT. ACTIVE / PASSIVE ACTUATOR NORM POS Fall POS TEST TYPE FREQUENCY DRAWING RELIEF No MS-V 9B SWINGCHECK 6.0 3 C ACTIVE NA --- ---

PART FLOW QUARTER 1D-ISI-FD-001 Dcscription: MAIN STEAM SUPPLY CHECK VALVE TO EF-U1 DISASEMBLE ALTREFU Justification: This valve supplies steam from the OTSG to the Turbine Driven Emergency Feedwater Ptmp. This valve cannot be full stroke exercised during operation because such an evolution would require injecting low tenperature condensate into the operating OTSG. Injecting cold water into the OTSG will thermally cycle the tubes and Emergency Feedwater nozzles, which should be avoided. A partial stroke is possible through the testing of the ptmp on recirculation. As permitted by OM-10, 54.3.2.2(b) a partial strcke test will be conducted quarterly. This valve (MS-V98) along with MS-V9A forms a group as described in Generic Letter 89-04, Positon No. 2 ard NUREG-1482 in that they are identical, mounted the same manner, and see the same service. One valve in the group will be disassembled and inspected and the disc manually exercised every refueling outage alternating between A and B (the interval for each valve is every other refueling outage). If the inspected valve is found to be unacceptable, the other valve in the grotp will be inspected during the same outage.

MS-V13A GLOBE 2.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE OPEN TIME QUARTER 1D-ISI-FD-001

Description:

SETPOINT 5 YEAR 10-ISI-FD-001 DGscription: OTSG "A" MS RELIEF VALVE MS-V20C RELIEF 6.0x10.0 2 C ACTIVE NA CLOSE ---

SETPOINT 5 YEAR 1D-ISI-FD-001. !

Description:

OTSG "B" MS RELIEF VALVE MS-V20D RELIEF 6.0x10.0 2 C ACTIVE NA CLOSE ---

SETPOINT 5 YEAR 1D-ISI-FD-001

Description:

OTSG "B" MS RELIEF VALVE MS-v21A RELIEF 3.0x6.0 2 C ACTIVE NA CLOSE ---

SETPOINT 5 YEAR 1D !SI-FD-001

Description:

OTSG "A" MS SAFETY VALVE MS-V218 RELIEF 3.0x6.0 2 C ACTIVE NA CLOSE ---

SETPOINT 5 YEAR 1D-Isi-FD-001 DGscription: OTSG "B" MS SAFETY VALVE MU-V 2A GLOBE 2.5 1 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 10-ISI-FD-016

Description:

CONTAINMENT ISOLATION - LETDOWN CLR "A" OUTLET VLV PARTIAL QUARTER TIME COLD SD POS VERIFY 2 YEAR Justification: Fully closing this valve will isolate letdown flow through one cooler. This will cause a thermal cycle on that Letdown Cooler. A thermat cycle i must be avoided if possible. Per OM-10, 64.2.1.2(b), a partial stroke test will be performed quarterly with a futt stroke test at the Cold r

Shutdown frequency.

l .....................___._____._____.. ................__.___..........................__....-...................................__.......................__.... ,

l l

09/19/95 Page 21 of 40

I TABLE B-1 TMI'2 INSERVICE TESV PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO MU-V 2B GLOBE 2.5 1 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 1D-ISI-FD-016

Description:

CONTAINMENT ISOLATION - LETDOWN CLR "B" OUTLET VLV PARTIAL QUARTER TIME COLD SD POS VERIFY 2 YEAR Justification: Fully closing this valve will isolate letdown flow through one cooler. This will cause a thermal cycle on that Letdown Cooler. A thermal cycle must be avoided if possible. Per CM-10, 54.2.1.2(b), a partial stroke test will be performed quarterly with a futt stroke test at the Cold shutdown frequency.

+ _. . . . - - -. - . . .

Description:

CONTAINMENT ISOLATION - RCP SEAL WATER ISOL VLV TIME COLD SD I

FAIL SAFE COLD SD POS VERIFY 2 YEAR Justification: Closure of this valve at power operation risks permanent damage to the Reactor Coolant Ptnp seats and subsequent Reactor Coolant leakage. The valve will be full stroked at the Cold Shutdown frequency.

MU-V 25 GLOBE 4.0 2 A ACTIVE OPEN TC CLCSE MOTOR OPEN AS IS LEAK APP. J ID-ISI-FD-016

Description:

CONTAINNENT ISOLATION RCP SEAL RETURN ISOL VALVE PARTIAL QUARTER TIME COLD SD ,

POS VERIFY 2 YEAR Justification: Closure of this valve at power operation risks permanent damage to the Reactor Coolant Punp seats and subsequent Reactor Coolant leakage. Per ,

CM-10, 14.2.1.2(b), this valve will be part stroke exercised quarterly and full stroke tested at the Cold Shutdown frequency.

MU-V 26 GATE 4.0 2 A ACTIVE OPEN TO CLOSE PISTON OPEN CLOSE LEAK APP. J 1D-ISI-FD-016 l

Description:

CONTAINMENT ISOLATION RCP SEAL RETURN LETDOWN ISOL PARTIAL QUARTER TIE mm 2 l '

FAIL SAFE COLD SD POS VERIFY 2 YEAR Justification: Closure of this valve at power operation risks permanent damage to the Reactor Coolant Punip seats and stbsequent Reactor Coolant leakage. Per i OM-10, 54.2.1.2(b), this valve will be part stroke exercised quarterly and full strok tested at the Cold Shutdown frequenc.

09/19/95 Page 23 of 40 ,

1 i _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

3 .J L m- g.

TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION

VALVE NO TYPE SIZE _C1S_ CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO MU-V 36 GATE 2.0 2 B ACTIVE BOTH MOTOR OPEN AS IS TIME BOTH QUARTER 1D-ISI-FD-017

==

Description:==

MU TANK AND PUMPS BYPASS FOR RCS FILL ISOLATION MU-V 79 SWINGCHECK 2.5" 2 C PASSIVE NA CLOSE --- --- ---

ID-ISI-FD-017 V 1

==

Description:==

MU TANK AND P'JMPS BYPASS FOR RCS FILL CHECK VALVE MU-V 86A TILTDISCCK 2.5 1 C ACTIVE CLOSE TO OPEN NA CLOSE ---

NONINTRUSV ALTREFU 1D-ISI-FD-017

==

Description:==

LOOP "D" RCS HPI INLET CHECK VALVE PART FLOW REFUEL Justification: Full flow testing of this valve is not possible during power operation. Initiating flow through this valve requires opening an additional flow path to the Reactor Coolant System (RCS) or switching from the normal makeup path. Injection of flowrates higher than normal makeup will cause a significant transient to the RCS and could cause a plant trip. Aditionally, injection at higher flowrates can cause a thermal cycle to the pressurizer surge line. Partial flow testing requires switching from the normal makeup nozzle. Switching the normal makeup path to close and then reopening the normal makeup valve will cause an additional thermal cycle on the injection nozzle as well as that of the tested valve (MU-V86A). This not considered to be predent and, therefore, part flow testing is not possible quarterly. Tech Spec 3.1.12.3 wilt not permit opening of the injection valves (MU-V16 A,B,C,D) when RCS temperature is below 275 degrees F with the Reactor head in place. The reactor head is normally not removed for Cold shutdown other than refueling. This makes testing at the Cold shutdown frequency impractical. These valves (MU-V86A/B, MU-V94, MU-V95, and MU-V220) are in parallel flow paths that are cross connected. White flow instrtsnentation is available, it is upstream of the cross connection. Because the cross connection has no means for isolating flow, there is no way to quantify flowrate through each of the parattet valves. This valve (MU-V86A) along with MU-V868 and MU-V95 form a group as per Generic Letter 89-04, Position 2. One valve in the group will be tested each refueling outage using nonintrusive equipment as permitted by NUREG-1482, 54.1.2 or, as an alternative, one of the valves in the group will be disassembled and inspected. A different valve in the group will be tested using nonintrusive techniques or disassenbled each subsequent refueling outage.

O-V 86B TILTDISCCK 2.5 1 C ACTIVE CLOSE TO OPEN NA CLOSE ---

NONINTRUSV ALTREFU 1D-ISI-FD-017 DQscription: LOOP "C" RCS HPI INLET CHECK VALVE PART FLOW REFUEL Justification: Full flow testing of this valve is not possible during power operation. Initiating flow through this valve requires opening an additional flow path to the Reactor Coolant System (RCS) or switching from the normal makeup path. Injection of flourates higher than normal makeup will cause a significant transient to the RCS and could cause a plant trip. Partial flow testing requires switching from the normal make up nozzle.

Switching the normal makeup path to close and then reopening the normal makeup valve will cause an additional thermal cycle on the normat injection nozzle as well as that of the tested valves (MU-V86B & MU-V95). This not considered to be prudent and, therefore, part flow testing is not possible quarterly. Tech Spec 3.1.12.3 will not permit opening of the injection valves (MU-V16 A,B,C,D) when RCS tenperature is below 275 degrees F with the Reactor head in place. The reactor head is normally not removed for Cold shutdown other than refueling. This makes testing at a Cold shutdown frequency impractical. These valves (MU-V86A/B, MU-V94, MU-V95, and MU-V220) are in parallel flow paths that are cross connected. While flow instrumentation is available, it is upstream of the cross connection. Because the cross connection has no means for isolating flow, there is no way to quantify flowrate through each of the parattet valves. This valve (MU-V868) along with MU-V 86A and MU-V95 form a group as per Generic Letter 89-04, Position 2. One valve of the group will be tested each refueling outage using nonintrusive equipnent as permitted by NUREG-1482, 64.1.2 or, as an alternative, one valve in the group will be disassembled and inspected. A different valve in the group will be tested using nonintrusive techniques or disassenbled each subsequent refueling outage.

09/19/95 Page 25 of 40

TABLE B-1 YM11 INSERVICE VEST PROGRAM VALVE TABULATION VALVE NO TYPE S!ZE RS MT ACTIVE / PASSIVE ACTUATOR WORM POS FAIL POS TEST TYPE FREQUENCY DRAWING REllEF NO MJ-U 94 TILTDISCCK 2.5 1 C ACTIVE CLOSE TO OPEN NA OPEN ~-

PART FLOW QUARTER 10-ISI-FD-017

Description:

LOOP "B" RCS HP1 INLET CHECK VALVE NONINTRUSV. REFUEL Justification: Normal makeup flow through this valve is significantly tower than the accident design flowrate. Full flow testing of this valve is not possible during power operation. Injection at higher than normal makeup will cause a significant perturbation and could cause a plant trip.

Additionally, injection at higher flowrates can cause a thermal cycle to the pressurizer surge line. Tech Spec 3.1.12.3 will not permit opening of the injection valves (MU-V16A,B,C,D) when RCS temperature is below 275 degrees F with the Reactor head in place. The reactor head is normally not removed for Cold shutdown other than refueling. This makes testing at Cold shutdown frequency impractical. The valves (MU-V86A/S, MU-V94, MU-V95, and MU-V220) are in parallel flow paths that are cross connected. White flow instrunentation is available, it is upstream of the cross connection. Because the cross connection has no means for isolating flow, there is no way to quantify flowrate through each of the parattet valves. This valve (MU-V94) will be partial flow tested quarterly then tested using nonintrusive equipment as permitted by NUREG-1482, 14.1..

or, as an alternative, disassent> led and inspected.

CONTAINMENT ISOLATION - HPI TO RC "D" SUPPLY CHK i Justification: Full flow testing of this valve is not possible during power operation because the accident design flow rate exceeds, by far, the normal RCS makeup flow. Futt design flow rate will cause a significant perturbation and could cause a plant trip. Aditionally, the use of injection nozzles that are not part of the normal maketp path will add a thermal cycle to the nozzle and, at design flow, cause a thermet cycle to the pressurizer surge line. For all those valves that are not part of the normal makeup path, a thermal cycle will be experienced by the nozzle.

Taking the additional thermal cycle for a check valve test is not considered to be prudent. Tech Spec 3.1.12.3 will not permit opening of the injection valves (MU-V16A,B,C,D) when RCS te m erature is below 275 degrees F with the Reactor head in place. The Reactor head is not normatty removed for Cold shutdown other than refueling. This makes testing at Cold Shutdown i gractical. Per OM-10, 54.3.2.2(e), this valve will be tested during refueling outages.

MU-V112 SWINGCHECK 4.0 2 AC ACTIVE NA OPEN ---

FULL FLOW QUARTER 1D-ISI-FD-017

Description:

MAKEUP TANK OUTLET CHECK VALVE CLOSE REFUEL

.bstification: To test the closed function, the HPI Ptenps must be secured and the MU Tank depressurized. This cannot be done quarterly and could significantly add to the r ope of a unplanned or short duration Cold shutdown. As permited by OM-10, 5.3.2.2(e), the check valve portion of the test will be done at a refueling interval frequency.

09/19/95 Page 27 of 40 i

=_ _ _ _ . . _ - . _ ._ m _ _ . .. . . _ _ _ _ _ . .

TABLE B-1 TM!1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF WO MU-V116 LIFT CHECK 1.5 1 A/C ACTIVE OPEN TO CLOSE NA OPEN ---

LEAK APP. J 10-ISI-FD-017

Description:

CONTAINMENT ISOLATION - SEAL INJ SPRY /RC CHK Justification: The normat operating position of this valve is open to provide a seat water flow to the Reactor Coolant Puup seats. Flow cannot be interupted to exercise this valve to the closed position during periods when any of the RC puips are operating. The open position is not the Nuclear Safety Related position. The only practical way to close test this valve is to setup equipment and perform a leakage test per Appendix J. The j frequency will be extended to the Appendix J required test frequency as permited by NUREG-1482, 54.1.4 (NRC Reconenendation).

MU-v193A STOP CHECK 2.0 2 C ACTIVE HAND --- ---

FULL FLOW QUARTER 1D-ISI-FD-017

(

Description:

MU-P1A RECIRC STOP CHECK VALVE CLOSE QUARTER

Description:

CONTAINMENT ISOLATION - 650# N' SUPPLY TO RB Justification: This valve is a passive component. Per OM-10, Table 1, no exercise test will be performed.

CR-V 1A BUTTERFLY 16.0 3 B ACTIVE CLOSE TO OPEN MOTOR ---

AS IS TIME QUARTER 1D-ISt-FD-002 Discription: NUC RIVER PUMP "A" DISCH VALVE POS VERIFY 2 YEAR TIME REFUEL 09/19/95 Page 28 of 40

m ..m.___._._m__.m . . . _ .- .- _

, i l

l TABLE B-1.

t TMI1 INSERVICE TEST PROGRAM VALVE TABULATION

+

VALVE NO TYPE SIZE RS CA_T ACTIVE / PASSIVE ACTUATOR NORM POS Fall'POS' TEST TYPE FREQUENCY DRAWING RELIEF NO' -.

NR-V 1B BUTTERFLY 16.0 3 B ACTIVE CLOSE TO OPEN MOTOR ---

AS IS TIME QUARTER 1D-ISI-FD-002

Description:

NUC RIVER PUMP "B" DISCH VALVE POC VERIFY 2 YEAR r TIME REFUEL NR-V 1C BUTTERFLY 16.0 3 B ACTIVE CLOSE TO OPEN MOTOR ---

AS IS TIME QUARTER 10-ISI-FD-002

Description:

I NR-V20C SWINGCHECK 16.0 3 C ACTIVE NA --- ---

PART FLOW QUARTER 1D-ISI-FD-002

Description:

NR-P1C DISCHARGE CHECK VALVE CLOSE QUARTER FULL FLOW REFUEL Justification: To verify full flow through this valve, only one of three Nuclear River Ptaps can be operating. Usually, plant heat loads will not permit the j operation of only one Nuclear River Ptmp. This applies to Power Operation, Hot Shutdown and most Cold Shutdown conditions. As permitted by OR-10, 14.3.2.2(d), this valve will be full stroke tested during refueling outages.

09/19/95 Page 29 of 40

TABLE B-1 TMIT INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CL_S. CA_T ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO NR-V22A SWINGCHECK 2.0 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 10-ISI-FD-002

Description:

NR-P1A VACUUM BREAKER CLOSE QUARTER NR-V228 SWINGCHECK 2.0 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 10-ISI-FD-002

Description:

Description:

RCP MOTOR COOLER SUPPLY VALVE t

l Justification: The normal operating position of this valve is open to provide cooling water to the Reactor Coolant Ptap motor coolers. Flow cannot be interupted to exercise this valve to the closed position during periods when any of the RC punps are operating. The open position is not the Nuclear Safety Related position. The only practical way to test the closed position is by seting up ecpipment and performing the Appendix J leakage test. The frequency will be extended to refueling outages as permited by NUREG-1482, 54.1.4 (NRC Recomendation).

CS-V 15 GATE 8.0 2 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 1D-ISI-FD-010

Description:

RCP MOTOR COOLER RETURN VALVE PARTIAL QUARTER TIME COLD SD POS VERIFY 2 YEAR l Justification: This valve cannot be closed during power operations bet.ause it would isolate cooling water for the Reactor Coolant Punp Motors. Per GM-10,

$4.2.1.2(b), this valve will be part stroke tested quarterly and full stroke tested at the Cold Shutdowns frequency.

i .............................................._.__..__...__......-_.......___...................................................................................

09/19/95 Page 30 of 40

__ < _- . <____m .. _ _ _ - - - . , . -m ._- . _ _ . - . . ___ . ---.---._ _. . - . - . _

b TA8LE B-1 p TMil INSERVICE TEST PROGRAM VALVE TAOULATION i

VALVE NO ' TYPE SIZE CLS cal ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO i

NS-V 35 GATE 8.0 3 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 1D-ISI-FD-010

Description:

RCP MOTOR COOLER RETURN VALVE PARTIAL QUARTER l TIME COLD SD !

i POS VERIFY 2 YEAR Justification: This valve cannot be closed during power operations because it would isolate cooling water for the Reactor Coolant Pu g Motors. Per OM-10, H.2.1.2(b), this valve will be part stroke tested quarterly and full stroke tested at the Cold shutdown frequency.

NS-V 52A GATE 1.0 2 B PASSIVE PISTON OPEN OPEN POS VERIFY 2 YEAR 1D-ISI-FD-010

Description:

CONTAINMENT ISOLATION - AH-E1A MOTOR COOLER SUPPLY Justification: This valve is also positiun verified Open in Auxiliary Operator Logs which require the reading of cooling water flow to the fan motor coolers each shift.

NS-V 52B GATE 1.0 2 B PASSIVE PISTON OPEN OPEN POS VERIFY 2 YEAR 1D-ISI-FD-010 ,

I

Description:

CONTAINMENT ISOLATION - AH-E18 MTR COOLER SUPPLY Justification: This valve is also position verified Open in Auxiliary Operator Logs which require the reading of cooling water flow to the fan motor coolers each shift.

4 .........__.............................................___.............................................................___.___.................................

NS-V 52C GATE 1.0 2 B PASSIVE PISTON OPEN OPEN POS VERIFY 2 YEAR 10-ISI-FD-010-Drscription: CONTAINMENT ISOLATION - AH-E1C MTR COOLER SUPPLY Justification: This valve is also position verified Open in Auxiliary Operator Logs which require the reading of cooling water flow to the fan motor coolers each shift.

1) Actuate during shutdown conditions, or

2) Remove and bench test, or

3) Remove and replace with a spare valve that had been bench tested within the last three years.

In addition, an as-found and as-left visual examination will be performed. For in-place testing the stroke time will be determined by acoustic monitors. For bench testing, the stroke time will be determined by observation. Fait Safe testing will be acconplished by observing valve closure upon the removat of the open actuation signal.

RC-V 2 GATE 2.50 1 B ACTIVE MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-019

Description:

PORV (RC-RV2) ISOLATION VALVE POS VERIFY 2 YEAR RC-V 4 GLOBE 1.5 1 B ACTIVE MOTOR CLOSE AS IS TIME COLD SD 1D-ISI-FD-019 DQscription: DECAY HEAT PRESSURIZER SPRAY LINE ISOLATION VALVE POS VERIFY 2 YEAR Justification: This valve is one of two isolation valves in series that isolate the RCS from a tower design pressure system, the Decay Heat System. Exercising this valve at power would reduce the margin of safety for the RCS pressure barrier. Per OM-10, 14.2.1.2(c), this valve will be exercised at the Cold shutdown frequency.

RC-U23 LIFT CHECK 1.5 1 C ACTIVE NA CLOSE ---

FULL FLOW COLD SD 1D-ISI-FD-019

Description:

DH PRESSURIZER SPRAY LINE CHECK VALVE Jus 2ification: This valve is in the discharge of the Decay Heat Ptsups and the Auxiliary Pressurizer Spray line. The punps have a discharge pressure in the order of 200 psig. During normal plant operation, these valves cannot be opened because the RCS pressure is approximately 2155 psig. Per OM-10, 14.2.1.2(c), this valve will be exercised at the Cold Shutdown frequency.

09/19/95 Page 33 of 40

__. . _ _ _ . . . . - -. --- -~. - - - - . - _ . . --+ ._ - .. .

! TABLE B-1 i T;til INSERVICE TEST PROGRAM VALVE TABULATION i

l VALVE NO TYPE SIZE ES CAT ACTIVE / PASSIVE ACTUATOR _ NORM POS Fall POS TEST TYPE FREQUENCY DRAWING RELIEF NO l

l RC-V28 GLOBE 1.0 1 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME COLD SD 1D-ISI-FD-019 l

Description:

PZR VENT TO RCDT ISOLATION VALVE POS VERIFY 2 YEAR Justification: This valve is one of two isolation valves in series. The valves isolate the Reactor Coolant System f rom the lower design pressure Reactor Coolant Drain Tank. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Per OM-10, 54.2.1.2(c), this valve will be exercised at the Cold shutdown frequency.

[C-v40A GLOBE 0.5 1 B ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

"A" HOT LEG HIGH POINT VENT TO RCDT AND ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 14.2.1.2(c), this valve will be exercised at the Cold Shutdown frequency.

RC-V408 GLOBE C.5 1 B ACTIVE CLOSE TO OPEN SOLEN 0!D CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

"B" HOT LEG VENT TO RCDT AND ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 54.2.1.2(c), this valve will be exercised at

-the Cold shutdown frequency.

RC-V41A GLOBE 0.5 1 B ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

"A" HOT LEG VENT TO RCDT AND ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve it is not possible to part stroke it. Per OM-10, 54.2.1.2(c), this valve will be exercised at the Cold Shutdown frequency.

[C-V418 GLOBE 0.5 1 B ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

"B" HOT LEG VENT TO RCDT AND ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 14.2.1.2(c), this valve will be exercised at Cold Shutdown frequency.

RC-V42 GLOBE 0.5 1 B ACTIVE CLOS 5 TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

REACTOR VESSEL VENT TO REACTOR BLDG ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 14.2.1.2(c), this valve will be exercised at Cold Shutdown frequency.

RC-V43 GLOBE 0.5 1 B ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 1D-ISI-FD-019

Description:

REACTOR VESSEL VENT TO REACTOR BLDG ATMOSPHERE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 54.2.1.2(c), this valve will be exercised at the Cold Shutdown frequency.

09/19/95 Page 34 of 40

TABLE S-1 TMI1 INSERVICE TEST PROGRAM VALVE VA8ULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR WORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO' RC-V44 GLOBE 1.0 1 B ACTIVE CLOSE TO OPEN SOLENOID CLOSE CLOSE TIME COLD SD 10-ISI-FD-019

==

Description:==

PRESSURIZER HI POINT VENT ISOLATION VALVE POS VERIFY 2 YEAR Justification: This valve is one of two high pressure isolation valves in series. Exercising this valve at power will reduce the margin of safety for the RCS barrier. Since this is a solenoid operated valve, it is not possible to part stroke it. Per OM-10, 54.2.1.2(c), this valve will be exercised at the Cold Shutdown frequency.

RR-V 1A BUTTERFLY 16.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-002

==

Description:==

RR-P1A DISCHARGE VALVE POS VERIFY 2 YEAR RR-V 1B BUTTERFLY 16.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 10-ISI-FD-002

==

Description:==

RR-P16 DISCHARGE VALVE POS VERIFY 2 YEAR RR-v 3A GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR OPEN AS IS TIME QUARTER 1D-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION - RBEC COIL "A" INLET VALVE POS VERIFY 2 YEAR RR-V 3B GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR OPEN AS IS TIME QUARTER 10-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION - RBEC COIL "B" INLET VALVE POS VERIFY 2 YEAR RR-V 3C GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR OPEN AS IS TIME QUARTER' 10-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION - RBEC COIL "C" INLET VALVE POS VERIFY 2 YEAR RR-V 4A GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 10-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION - RBEC COIL "1A OUTLET VLV POS VERIFY 2 YEAR RR-V 48 GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION RBEC COIL "18" OUTLET VALVE POS VERIFY 2 YEAR RR-V 4C GATE 12.0 2 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-010

==

Description:==

CONTAINMENT ISOLA!!ON - RBEC COIL "1C" OUTLET VLV POS VERIFY 2 YEAR RR-V 4D GATE 12.0 2 B ACTIVE CLOSE TO OPEN MCTOR CLOSE AS IS TIME QUARTER 1D-ISI-FD-010

==

Description:==

CONTAINMENT ISOLATION - RBEC COIL "1D" OUTLET VLV POS VERIFY 2 YEAR RR-V 5 BUTTERFLY 10.0 3 B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME QUARTER 10-ISI-FD-010 D mcription: RR-V6 RB COOLING COIL DISCHARGE BYPASS VALVE POS VERIFY 2 YEAR RR-V 6 BUTTERFLY 10.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM THROT OPEN TIME QUARTER 10-ISI-FD-010

==

Description:==

RB EMEPG COOLING COIL BACK PRESSURE REGULATOR FAIL SAFE QUARTER 09/19/95 Page 35 of 40

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TABLE B-1 TQIl INSERUICE VEST PRCT, RAM VALUE TABULATIC'3 VALVE NO TYPE SIZE CLS CAT, ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWINC RELIEF NO RR-V 7A SWINGCHECK 16.0 3 C ACTIVE CLOSE TO OPEN NA --- ---

PART FLOW- QUARTER 1D-ISI-FD-002 _

Deecription: RB EMERG COOL PUMP "A" DISCHARGE CHECK VALVE FULL FLOW REFUEL Justification: Quarterly testing will be performed by flowing through the plup minimum flow I.ine. This flow is less than the design flow rate. Initiating full flow through these valves would introduce river water into the Reactor Building Emergency Cooling Coits. Since river water contains sitt and microorganisms, the system must be drained to the Reactor Building su m and refilled with Nuclear Services Closed Cooling Water. Approximately 5,000 gallons of water must be processed through the Liquid Waste Disposal System. This is not pratical for a quarterly or cold shutdown I f regaency. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, an envirormiental release that should be l held to a minimum. As permitted by OM-10, 54.3.2.2(e), this valve will be futt stroke tested at a refueling outage frequency.

RR-V 78 SWINGCHECK 16.0 3 C ACTIVE CLOSE TO OPEN NA --- ---

PART FLOW QUARTER 10-ISI-FD-002 DCscription: RB EMERG COOL PUMP "B" DISCARGE CHECK VALVE FULL FLOL' REFUEL Justification: Quarterly testing will be performed by flowing through the pum minimten flow line. This flow is less than the design flow rate. Initiating full flow through these valves will introduce river water into the Reactor Building Emergency Cooling Colts. Since the river water contains sitt and microorganisms, the system must be drained to the Reactor Building step and refilled with Nuclear Services Closed Cooling Water. Approximately 5,000 gattons of water must be processed through the Liquid Weste Disposat System. This is not pratical for a quarterly or cold shutdown frequency. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, an environmental release that should be held to a minimum. As permitted by OM-10, 54.3.2.2(e), this valve will be futt stroke tested at a refueling outage frequency.

l CR-U 8A SWINGCHECK 20.0 3 C ACTIVE NA CLOSE ---

FULL FLOW REFUEL 1D-ISI-FD-010

Description:

RIVER WATER TO RB COOL UNITS CHECK VALVE CLOSE QUARTER i Justification: Initiating flow through these valves will introduce river water into the Reactor Building Emergency Cooling coils. Since the river water may be sitt laden and is untreated, the system must be drained to the Reactor Building sump and refitted with Nuclear Services Closed Cooling Water _ +

This produces quantities of water that must be processed through the Liquid Waste Disposat System. This is not pratical for quarterly or cold shutdown testing. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, a condition that should be held to a mininun. As permitted by OM-10, 54.3.2.2(e), this valve will be tested at a refueling outage frequency.

RR-U 88 SWINGCHECK 20.0 3 C ACTIVE NA CLOSE ---

FULL FLOW REFUEL 1D-ISI-FD-010 [

Description:

RIVER WATER TO RB COOL UNITS CHECK VA. 1 CLOSE QUARTER ;

l Justification: Initiating flow through these valves will introduce river water into the Reactor Building Emergency Cooling Coils. Since the river water may be sitt laden and is untreated, the system must be drained to the Reactor Building simp and refilled with Nuclear Services Closed Cooling Water _

This produces quantities of water that must be processed through the Liquid Waste Disposat System. This is not pratical for quarterly or cold shutdown testing. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, a condition that should be held to a minimum. As permitted by OM-10, 14.3.2.2(e), this valve will be tested at a refueling outage frequency. ;

RR-U 9A SWINGCHECK 12.0 3 C ACTIVE NA --- ---

FULL FLOW REFUEL 1D-ISI-FD-010

Description:

CONTAINMENT ISOLATION - AH-E1A EMERG COOL OUTLET Justification: Initiating flow through these valves will introduce river water into the Reactor Building Emergency Cooling coils. Since the river water may be sitt laden and is untreated, the system must be drained to the Reactor Building stnp and refitted with Nuclear Services Closed Cooling Water. !

This produces quantities of water that must be processed through the Liquid Waste Disposat System. This is not pratical for quarterly or cold shutdowns. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, a condition that should be held to a mininun. As permitted by OM-10, 54.3.2.2(e), this valve will be tested at a refueling outage frequency. t I-09/19/95 Page 36 of 40 i

TABLE B-1 TMll INSE0VICE VEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS. cal ACTIVE / PASSIVE - ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO RR-V 98 SWINGCHECK 12.0 3 C ACTIVE WA --- ---

' FULL FLOW REFUEL- 1D-ISI-FD-010 ,

Description:

CONTAINMENT ISOLATION - AH-E1B EMERG COOL OUTLET Justification: Initiating flow through these valves will introduce river water into the Reactor Building Emergency Cooling Colts. Since the river water may be-sitt laden and is tntreated, the system must be drained to the Reactor Building stap and refitted with Nuclear Services Closed Cooling Water.

This prcduces quantities of water that must be processed through the Liquid Weste Disposat System. This is not pratical for quarterly or cold shutdown testing. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, a condition that should be held to a minimum. As permitted by OM-10, $4.3.2.2, this valve will be tested at a refueling outage frequency.

RR-V 9C SWINGCHECK 12.0 3 C ACTIVE NA --- ---

FULL FLOW REFUEL 1D-ISI-FD-010

Description:

CONTAINMENT ISOLATION - AH-E1C EMERG COOL OUTLET

- Justification: Initiating flow through these valves will introduce river water into the Reactor Building Emergency Cooling Coils. Since the river water may be sitt laden and is untreated, the system must be drained to the Reactor Building simp and refilled with Nuclear Services Closed Cooling Water.

This produces w antitles of water that must be processed through the Liquid Waste Disposat System. This is not pratical for quarterly or cold shutdown testing. Additionally, test operation will discharge a quantity of corrosion inhibiter to the river, a condition that should be held to-a mininun. As permitted by OM-10, 14.3.2.2(e), this valve will be tested at a refueling outate frequency.

RR-V10A GLOBE 2.0 3 B ACTIVE BOTH DIAPHRAGM TIME BOTH QUARTER 1D-ISI-FD-002

Description:

RR-P1A RECIRCULATION MINIMUM FLOW BYPASS VALVE FAIL SAFE QUARTER POS VERIFY 2 YEAR RR-V108 GLOBE 2.0 3 8 ACTIVE BOTH DIAPHRAGM TIME BOTH QUARTER 1D-ISI-FD-002

Description:

RR-P1B RECIRCULATION MINIMUM FLOW BYPASS VALVE FAIL SAFE QUARTER' POS VERIFY 2 YEAR RR-V12A SWINGCHECK 2.0 3 C ACTIVE BOTH NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-002

Description:

RIVER WATER PUMP "A" VACUUM BREAKER CLOSE QUARTER RR-V128 SWINGCHECK 2.0 3 C ACTIVE BOTH NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-002

Description:

RIVER WATER PUMP "B" VACUUM BREAKER CLOSE QUARTER SA-V 2 GLOBE 2.0 2 A PASSIVE HAND CLOSE ---

LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - SERVICE AIR TURB BLDG

.tustification: The valve is a passive component. Per OM-10, Table 1, no valve exercise will be performed.

SA-V 3 GLOBE 2.0 2 A PASSIVE HAND CLOSE ---

LEAK APP. J 10-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB 1ST FL SVC AIR ISOL Justification: The valve is a passive component. Per OM-10, Table 1, no valve exercise will be performed.

SF-V 7 SWINGCHECK 8.0 3 ACTIVE NA --- ---

FULL FLOW . QUARTER 1D-SIS-FD-013 ,

Description:

SF-P1A DISCHARGE CHECK VALVE

?

09/19/95 Page 37 of 40

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VABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE ELS M ACTIVE #ASSIVE ACTUATOR NORM POS FAIL' DOS . TEST TYPE FREQUENCY DRAWING RELIEF NO SF-V 8 SWINGCHECK 8.0 3 ACTIVE NA --- ---

FULL FLOW QUARTER 1D-SIS-FD-018 .

Description:

SF-P1B DISCHARGE CHECK VALVE SF-V23 GATE 8.0 2 A PASSIVE HAND CLOSE CLOSE LEAK REFUEL 1D-SIS-FD-018

Description:

FUEL TRANSFER CANAL FILL & DRAIN LINE VALVE Justification: This valve is a passive component as defined by OM-10. Per CM-10, Table 1, no exercise test will be performed.

SF-V50 SWINGCHECK 8.0 3 ACTIVE NA OPEN ---

FULL FLOW QUARTER 1D-ISI-FD-018

Description:

SF W OL "A" COOLING RETURN CHECK VALVE SF-V51 SWINGCHECK 8.0 3 ACTIVE NA OPEN ---

FULL FLOW QUARTER 1D-SIS-FD-018

Description:

SF POOL "B" COOLING RETURN CHECK VALVE W G-V3 GLOBE 2.0 2 A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB VENT HEADER VALVE TIME QUARTER POS VERIFY 2 YEAR W G-V4 GATE 2.0 2 A ACTIVE OPEN TO CLOSE SOLENOID OPEN CLOSE LEAK APP. J 1D-ISI-FD-023

Description:

CONTAINMENT ISOLATION - RB VENT HEADER VALVE TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR WDL-V 49 DIAPHRAGM 1.5 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 1D-ISI-FD-021

Description:

WDL-P13A OUTLET SUPPLY TO RCBT POS VERIFY 2 YEAR I

W L-V 50 DIAPHRAGM 1.5 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 10-ISI-FD-021

Description:

WDL-P138 OUTLET SUPPLY TO RCBT POS VERIFY 2 YEAR WDL-V 61 DIAPHRAGM 1.0 3 8 ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER" 1D-ISI-FD-021

Description:

BORIC ACID MIX TANK OUTLET TO PRIMARY SYSTEM POS VERIFY 2 YEAR I WDL-V 62 DIAPHRAGM 1.0 3 B ACTIVE OPEN TO CLOSE DIAPHRAGM CLOSE CLOSE TIME QUARTER 1D-ISI-FD-021 l

DGscription: OUTLET BORIC ACID MIX TANK TO RCBT POS VERIFY 2 YEAR WDL-V 89 DIAPHRAGM 2.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 1D-ISI-FD-021

Description:

OUTLET RBAT (WL-T7A) TO WDL-P13A r

i WDL-V 90 DIAPHRAGM 2.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 1D-ISI-FD-021

Description:

OUTLET RSAT (WDL-T7A) TO WDL-P138 i

09/19/95 Page 38 of 40

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_ _ - _ _ _ - _ _ _ .

TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TARULATION ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO VALVE NO TYPE SIZE ,CAS CA_T ACTIVE / PASSIVE DIAPHRAGM 2.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 1D-ISI-FD-021 WDL-V 91

==

Description:==

OUTLET RBAT (WL-T7B) TO WL-P13A DIAPHRAGM 2.0 3 B ACTIVE CLOSE TO OPEN DIAPHRAGM CLOSE CLOSE TIME QUARTER 10-ISI-FD-021 WDL-V 92 DGscription: OUTLET WL-T7B TO WL-P138 3.0 2 A ACTIVE OPEN TO CLOSE MOTOR CLOSE AS IS LEAK APP. J 1D-ISI-FD-023 W L-V303 GATE

==

Description:==

CONTAINMENT ISOLATION - RC DRAIN PUMP DISCH VALVE TIME QUARTER P03 VERIFY 2 YEAR WL-V304 GATE 3.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAK APP. J 10-ISI-FD-023 Deacription: CONTAINMENT ISOLATION - RC DRAIN PLMP DISCH ISOL TIME QUARTER 3 FAIL SAFE QUARTER POS VERIFY 2 YEAR WDL-V353 LIFT CHECK 1.5 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-021

DGscription: BA RECYCLE PUMP "A" DISCHARGE CHECK VALVE WDL-V354 LIFT CHECK 1.5 3 C ACTIVE NA --- ---

FULL FLOW QUARTER 1D-ISI-FD-021

==

Description:==

BA RECYCLE PUMP "B" DISCHARGE CHECK VALVE WDL-V361 LIFT CHECK 1.0 3 C ACTIVE NA --- ---

PART FLOW COLD SD 1D-ISI-FD-021 DQseription: FEED INJ CHECK BK4T TO MU&P SYSTEM FULL FLOW REFUEL Justification: Initiation of flcd through this valve will inject concentrated boric acid into the Reactor Coolaat Makeup and Purification System. This would adversely affect plant operation due to reactivity changes. Returning the concentration to the operating band would create additional radwaste to be processed. For these reasons, exercising during operation is considered to be inpractical. Partial stroke testing will occur at the Cold Shutdown frequency. Per OM-10, 14.3.2.2 (c), the valve will be exercised at a refueling outage frequency.

WDL-V362 SWINGCHECK 2.5 3 C ACTIVE NA --- ---

CLO*E REFUEL 1D-ISI-FD-021

==

Description:==

FEED INJ DEBORATING DEMIN TO MU&P SYS CHECK VALVE Justification: Initiation of flow through this line will inject concentrated boric acid into the Reactor Coolant Makeup and Purification System. This would adversely affect plant operation due to reactivity changes. Returning the concentration to the operating band would create additional radwaste to be processed. For these reasons close testing during operation is considered to be impractical. Per OM-10, 14.3.2.2(c), this valve will be exercised at the refueling outage frequency.

WL-V534 GATE 6.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAK APP. J 1D-ISI-FD-021 Doscription: CONTAINMENT ISOLATION - RB SUMP DRAIN TO AUX BLDG TIME QUARTER FAIL SAFE QUARTER POS VERIFY 2 YEAR 09/19/95 Page 39 of 40

s . . .m . _ - _ . _ _ .. _ . . _ _ _. _. ,_

TABLE B-1 TMI1 INSERVICE TEST PROGRAM VALVE TAOULATION VALVE NO TYPE SIZE _CLS CA_T ACTIVE / PASSIVE ACTUATOR NORM POS FA!( P _OS JEST TYPE FREQUERICY DRAWING ' RELIEF 110 m L-V535 GATE 6.0 2 A ACTIVE OPEN TO CLOSE PISTON CLOSE CLOSE LEAL ( .. APP. J 10-ISI-FD-021'

Description:

CONTAIMMEWT ISOLATION - RS SUMP DRAIN TO AUX BLDG TIME QUARTER FAIL SAFE QUARTER POS VERIFY' 2 YEAR 09/19/95 Page 40 of 40

TABLE B-2 TMI-l IST VALVE RELIEF REQUESTS RETJEF REQUEST NO. V 1 Comoonent Tar No. Component Description Cateeory Tvoe Actuator MU-V78 Makeup Tank and Pumps Bypass for RCS Fill Isolation Valve C Globe Hand MU-V79 Makeup Tank and Pumps Bypass for RCS Fill Check Valve C Swing Check NA Code Section from Which Reliefis Requested Relief is requested from the exercising requirements of OM-10, 64.3.2.2. .

Alternate Test Descriotion The valve pair (MU-V78 in series with MU-V79) is verified closed by normal operating procedures. No specific test procedures will be implemented. MU-V78 is a locked closed hand operated globe valve. Irakage will be noted by observing Makeup Tank level and pn:ssure as part of normal operating procedures.

Basis for Relief Request Relief is requested from the requirement to perform a quarterly exercise test for MU-V79. MU-V79, a 2%" swing check valve, has no nuclear safety function in the open position. During normal plant operation, MU-V79 is isolated by a hand operated locked closed valve, MU-V78. Either of these valves fulfills the nuclear safety function. MU-V78 is maintained locked closed during operation in accordance with the normal system valve lineup. Both of these valves are Seismic Category I and capable of seating against the shutoff head of the Makeup Pumps.

A small amount of leakage past MU-V78 and MU-V79 into the 2%" fill line is of no consequence since any leakage water would ,

return to the Makeup Tank and remain available for makeup to the primary system. The Makeup Tank is alarmed for both pressure and level. ;

Significant leakage such as would be seen if both valves were open would be identified by significant changes in Makeup Tank pressure and level. Significant leakage would also be identified by a refueling surveillance 1303-11.8, "HPI Test," since this procedure verifies HPI accident design flow rate.

NUREG-1482, f4.1.1 discusses the situation of two check valves in series and the acceptability of testing them together.

Although MU-V73 is not a check valve, a similar argument can be made. There is no pressure tap between these two redundant 09/19/95 Page 1 of 2

i l

TABLE B-2 TMI-l IST VALVE RMJFF REQUESTS -

l' RMJFF REQUEST NO. V 1 (Continued):

l l valves and testing would only be capable of verifying the seat tightness of one valve. Both of these. valves are capable seating against accident design pressure. The valve pair (MU-V78 and MU-V79) are under cons: ant test for significant leakage since Makeup Tank high level and high pressure are both alarmed conditions. Therefore, specific tests to exercise these valves or -

l disassemble and inspect them are not needed.

1 1

l l

l 09/19/95 Page 2 of 2 l

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TABLE B-2 TMI-I IST VALVE RHJEF REQUESTS .

RFJIEF REQUEST NO. V 2 Comoonent Tae No. Component Description Cateeory Tvoe Actuator !

DH-V50 Spent Fuel Return Cleanup Check Valve C Swing Check NA Code Section from Which Relief is Requested ;

Relief is requested from the exercising requirements of OM-10, 64.3.2.2.

Alternate Test Description

'Ihe valve pair (DH-V50 in series with SF-V44) is verified closed by means of Borated Water Storage Tank (BWST) level as part of normal operating and alarm response procedums. No specific test procedure will be implemented. l Basis for Relief Request DH-V50 has no nuclear safety function in the open position. The nuclear safety function is to prevent fluid from the BWST and Reactor Building Sump from entering the non seismic portion of the Spent Fuel Pool Cooling System (SF) after a LOCA when the ,

Decay Heat Removal System is in Low Pressure Injection (LPI) mode and suction is from the BWST and later from the Reactor Building sump. The valve is in series with a hand-operated normally closed valve (SF-V44).

'Ihe leak tightness of these valves (DH-V50 and SF-V44) is under constant test by surveillance of BWST level. Maintaining BWST level, which is also alarmed, verifies that (either DH-V50 or SF-V44) is in the closed position. Any appreciable leakage would be '

detected through use of the curmnt procedures (e.g., Surveillance Procedure 1301-1, " Shift and Daily Checks"). In addition, t l refuehng surveillance 1303-11.54, "LPI Test," verifies that these valves do not have significant seat leakage since this procedure !

verifies LPI accident design flow rate.

c DH-V50 is only used when the DH system is to be filled from the spent fuel pool which is rarely done. SF-V44 is included in the :

Augmented IST program because it is a non-Code valve. Both of these valves are Seismic Category I and capable of seating against accident design pmssure. Either of these valves fulfills the nuclear safety function.

NUREG-1482, 64.1.1 discusses the situation of two check valves in series and the acceptability of testing them together. Although SF-V44 is not a check valve, a similar argument can be made. Them is no pressum tap between these two redundant valves and

, testing would only be capable of verifying the seat tightness of the first valve, DH-V50. The valve pair (DH-V50 and SF-V44) are ,

09/19/95 Page 1 of 2

- = - _ - . - . .- . _ _

TABLE B-2 TMI-1 IST VALVE REIJEF REQUESTS l REIJEF REQUEST NO. V 2 (Continued):

i l

i

! under constant test for significant leakage since BWST level is alarmed and is surveilled. Therefom, opening SF-V44 to test the leak tightness of DH-V50, or other specific tests to exemise these valves or disassemble and inspect them am not needed.

l l

l t

l 09/19/95 Page 2 of 2

TABLE B-2 TMI-l IST VALVE RETIFF REQUES*IS REUEF REQUEST NO. V 3 Component Tae No. Component Description Cateeory Tygg Actuator BS-V52A NAOH Tank LPIIBS Suction Header Check Valve C Swing Check NA BS-V52B NAOH Tank LPI/BS Suction Header Check Valve C Swing Check NA r

^

Code Section from Which Relief is Requested Relief is requested from OM-10, 64.3.2.4(c) regartling the frequency of disassembly for inspection purposes. This valve cannot be .

exercised with flow.

Alternate Test Description These valves form a group as described in Generic letter 89-04, Position 2 and NUREG-1482 in that they are identical, mounted the same manner, and see the same service. As approved for the last 10-year interval, one valve in the group will be disassembled ar.d inspected and the disc manually exercised every other refueling outage alternating between A and B, such that each valve is ,

disassembled every fourth outage. This msults in a disassembly frequency of appmximately every 8 years for a specific valve. If t the inspected valve is found to be unacceptable, the other valve in the group will be inspected during the same outage. !

t Basis for Relief Request !

Flow testing of these valves requires the injection of sodium hydroxide into the Decay Heat Removal and Building Spray Systems.

Such operation is impractical in that the sodium hydroxide must be removed from the Decay Heat System. Therefore, flow testing i is not considered to be practical. Except for accident conditions, these valves would never see flow. The valves are stainless steel and are subject to conditions (clean, low temperatum fluid) that would minimize the possibility of their sticking closed. ;

i Both valves were disassembled and inspected in 1984. BS-V52A was again disassembled during the 6R (1986) and 9R (1991)

Outages. BS-V52B was disassembled during the 7R (1988) Outage and in July,1995. All inspections have shown the valves to be in excellent condition.

Given the valves' materials of construction, lack of service, and the results of previous disassembly inspections, this relief is justified. Similar relief was approved by the NRC for the previous IST interval in a letter dated December 27,1989. The NRC <

granted relief based on GPU Nuclear letters dated June 7,1988 and April 17, 1989. Inspection msults fmm disassembly subsequent to our previous correspondence provide even greater justification for reducing the fmquency of inspection.

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t i TABLE B-2 TMI-l IST VALVE RFJ JEF REQUES'I3 RELIEF REQUEST NO. V 4 Component Tar No. Component Description Category Type Actuator BS-V30A Containment Isolation - BS Nozzle Inlet Check Valve C Swing Check NA BS-V30B Containment Isolation - BS Nozzle Inlet Check Valve C Swing Check NA Code Section from Which Reliefis Requested Relief is requested fmm OM-10, 64.3.2.4(c), reganling disassembly frequency. His valve cannot be full stroke exercised with flow.

Alternate Test Description Rese valves form a gmup as described in Generic letter 89-04, Position 2 and NUREG-1482 in that they are identical, mounted the same manner, and see the same service. As approved for the last submittal, each valve in the group will be disassembled and inspected and the disc manually exercised every other refueling outage alternating between A and B, such that each valve is disassembled every fourth outage. This equates to disassembly frequency of approximately 8 years for a specific valve. If the inspected valve is found to be unacceptable, the other valve. in the gmup will be inspected during the same outage. Both valves are I partial flow tested every quarter using nitrogen.

Basis for Relief Request Operation of this system would requim spraying the containment. Therefore flow testing is not considered to be practical. These valves effectively never see service and are subiect to conditions (clean, low temperature water) that would minimize their sticking . !

l closed. Both valves are stainless steel.

BS-V30A was opened and inspected for the first time in 1984. It was opened again during the 7R (1988) Outage. It is scheduled to '

be opened during the llR Outage (9/95). BS-V30B was disassembled during the 6R (1986) and 9R (1991) Outages. All inspections have shown the valves to be in excellent condition.

Given the valves' materials of constmetion, lack of service, and the results of previous disassembly inspections, this relief is justified. Similar relief was approved by the NRC for the previous IST interval in a letter dated December 27,1989. The NRC

! granted relief based on GPU Nuclear letters dated June 7,1988 and April 17, 1989. Inspection results from disassembly subsequent l to our previous correspondence provide even greater justification for reducing the frequency of inspection. ,

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TABLE B-2 TMI-l IST VALVE RETJEF REQUESTS REIlEF REQUEST NO. V 5 Component Tar No. Component Descriotion Category Tvoe Actuator a CO-V175A EFW Pump Bearing Cooling Return Check Valve C Lift Check NA CO-V175B EFW Pump Bearing Cooling Return Check Valve C Lift Check NA Code Section fmm Which Relief is Requested Specific relief is requested from the full flow test requirement of NRC Generic Ixtter 89-04, Position 1. While the system is tested '

quarterly, it is not possible to determine that both valves open.

Alternate Test Description These valves form a gmup as described in Generic letter 89-04, Position 2 and NUREG-1482 in that they are identical, mounted i the same manner, and see the same service. One valve in the gmup will be disassembled and inspected and the disc manually exercised every other refueling outage alternating between A and B, such that each valve is disassembled every fourth outage. This results in a disassembly frequency of approximately every 8 years for a specific valve. If the inspected valve is found to be unacceptable, the other valve in the group will be inspected during the same outage.

Basis for Relief Reauest :

These stop check valves direct flow fmm the EFW Pump seal supply back to the EFW Pump Suction header. The return flow from all three EFW Pumps is combined and then flow is directed through these parallel valves. The closed function is required to prevent draining one Condensate Storage Tank (CST) through the other CST if a failure of one tank is postulated. Full flow testing ,

would require that two of three EFW Pumps (one motor driven and the turbine driven) operate simultaneously with one Condensate Storage Tank /EFW Suction Header isolated (to the opposite motor driven EFW Pump). 'Ihis test is not practical because isolation of a header and Condensate s'orage tank with two pumps operating is undesirable. .

Both valves were disassembled and inspected during Refueling Outages 8R (January 1990) and 9R (October 1991); both were found ,

to be in good condition. CO-V175A was again disassembled and inspected during 10R (September 1993) and found in good i condition. CO-V175B is scheduled to be disassembled and inspected ir, llR (September 1995). These valves operate in clean ,

water and are of a simple design. Disassembly and inspection every other outage is sufficient to demonstrate the operational readiness of these valves.

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TABLE B-2 TMI-l IST VALVE RETIEF REQUESTS l

l RELIEF REQUEST NO. VG 1 l

Code Section from Which Relief is Requested l

l Generic relief is requested from OM-10, 664.2.2.3(a) and 4.1 regarding test fmquency.

l l Alternate Test Descriotion l These tests will be performed each refueling outage instead of the Code specified frequency "at least once every two years."

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Basis for Relief Request The refuel cycle for TMI-I is nominally two years. Several of the valves requiring leak testing cannot be tested with the plant operatieg. If, due to an intermediate outage, the refueling cycle exceeds two years, the code requirement could require a shutdown simply to test the certain valver. This is impractical. Testing each refueling is a reasonable alternative.

l Typically, valve position verification is done more frequently than once every two years. Some valves must be stroked to verify l position. Of these, several cannot be stroked with the plant operating. As delineated above, the refuel cycle may extend beyond two years. Position verification using the code specified frequency, could cause the plant to be shut down. Position verification I at least every refueling is a reasonable alternative to at least every two years.

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EG-71B-2 AIR START RECEIVER INLET CHECK EG-V16AA DIAPHRAGM 1.5 A B ACTIVE CLOSE TO OPEN SOLENOID CLOSE OPEN TIME QUARTER C-302-351 D:scription: AIR START FOR DIESEL GENERATOR 1A EG-V16AB DIAPHRAGM 1.5 A B ACTIVE CLOSE TO OPEN SOLENOID CLOSE OPEN TIME QUARTER C-302-351 Drscription: AIR START FOR DIESEL GENERATOR 18 l

EG-V16BA DIAPHRAGM 1.5 A B ACTIVE CLOSE TO OPEN SOLENOID CLOSE OPEN TIME QUARTER C-302-351 l D acription: AIR START FOR EG-Y1A i .-_....................__.... --__.----- ...__.__.--.-__.--..------- ...--..............-.----..-....-_..................--__.....-................-....---.....

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l TABLE B-3 TMIT AUGMENTED IST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE BLS CAT, ACTIVE / PASSIVE ACTUATOR WORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO EG-V16BB DIAPHRAGM 1.5 A B ACTIVE CLOSE TO OPEN SOLENGID CLOSE OPEN TIME QUARTER C-302-351

Description:

AIR START FOR DIESEL EG-Y18 EG-V31A THREE WAY 5.0 A C ACTIVE CLOSE TO OPEN EXPANSION --- ---

FULL FLOW QUARTER C-302-354 1 DGscription: EDG "A" JACKET COOLANT TEMP CONTROL VALVE DISASEMBLE 10 YEAR Justification: These are self contained thermostatic valves that use an expanding wax type of temperature sensing element. There are no external actuators.

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The valves have four internal elements that start to open at 100 degrees F and are fully open at 115 degrees F. These volves are self actuating in response to some system characteristic (temperature) therefore, they are clasified as category C per the definition of OM-10, $1.4.c. There t are no rules in OM-10 for the testing of these valves (rules exist for check and relief valves only). Further, these valves are an integral part of the Diesel Generator skid. The proper functioning of these valves will be indicated during the performance of the Diesel Genrator test.

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EG-V31B THREE WAY 5.0 A C ACTIVE CLOSE TO OPEN EXPAMSION --- ---

FULL FLOW QUARTER C-302-354 l

Description:

EDG "B" JACKET COOLANT TEMPERATURE CONTROL VALVE DISASEMBLE 10 YEAR Justification: These are self contained thermostatic valves that use an expanding wax type of tegerature sensing element. There are no external actuators.

The valves have four internal elements that start to open at 100 degrees F and are fully open at 115 degrees F. These valves are self actuating in response to some system characteristic (teg erature) therefore, they are clasified as category C per the definition of OM-10, $1.4.c. There are no rules in OM-10 for the testing of these valves (rules exist for check and relief valves only). Further, these valves are an integral part of the Diesel Generator skid. The proper functioning of these valves will be indicated during the performance of the Diesel Genrator test.

EG-tf32AA SWINGCHECK 4.0 A C ACTIVE CLOSE TO OPEN NA --- ---

FULL FLOW QUARTER C-302-354

Description:

EG-C3A/A COOL RADIATOR OUTLET CHECK VALVE DISASEMBLE 10 YEAR Justification: These valves are located downstream of the Diesel Generator and must open to allow to be pu med out of the two 50% capacity each radiators and are an integral part of the Diesel Generator skid. Their function is verified open during the performance of testing of the Diesel Gemerator by observation of acceptable engine coolant temperatures. If one of the valves did not open, acceptable coolant temperatures could not be attained.

This is considered to be an indirect indicator of valve function as permitted by OM-10, 64.3.2.4(a).

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f EG-V32AB SWINGCHECK 4.0 A C ACTIVE CLOSE TO OPEN NA --- ---

FULL FLOW QUARTER C-302-354

Description:

EG-C3A/B COOL RADIATOR OUTLET CHECK VALVE DISASEMBLE 10 TEAR

( Justification: These valves are located downstream of the Diesel Generator and must open to allow to be p m ped out of the two 50% capacity each radiatcrs and

! are an integral part of the Diesel Generator skid. Their function is verified open during the performance of testing of the Diesel Gemerator by l observation of acceptable engine coolant tem eratures. If one of the valves did not open, acceptable coolant temperatures could not be attained.

This is considered to be an indirect indicator of valve function as permitted by OM-10, $4.3.2.4(a).

EG-V32BA SWINGCHECK 4.0 A C ACTIVE CLOSE TO OPEN NA --- ---

FULL FLOW QUARTER C-302-354

Description:

EG-C38/A COOL RADIATOR OUTLET CHECK VALVE DISASEMELE 10 YEAR Jus 2ification: These valves are located downstream of the Diesel Generator and must open to allow to be peped out of the two 50% capacity each radiators and are an integral part of the Diesel Generator skid. Their function is verified open during the performance of testing of the Dieeel Gemerator by observation of acceptable engine coolant temeratures. If one of the valves did not open, acceptable coolant temperatures could not be attained.

This is considered to be an interect indicator of valve function as permitted by OM-10, 54.3.2.4(a).

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I TABLE B-3 TMI1 AUGMENTED IST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE CLS CAT ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING REttEF NO EG-V32BB SWINGCHECK 4.0 A C ACTIVE CLOSE TO OPEN NA --- ---

FULL FLOW QUARTER C-302-354 Deocription: EG-C-3B/B COOL RADIATOR OUTLET CHECK VALVE DISASEMBLE 10 YEAR Jus 2ification: These valves are located downstream of the Diesel Generator and must open to allow to be pumed out of the two 50% capacity each radiators and are an integral part of the Diesel Generator skid. Their fmction is verified open during the performance of testing of the Diesel Gemerator by observation of acceptabte engine coolant temperatures. If one of the valves did not open, acceptable coolant temeratures could not be attained.

This is considered to be an interect indicator of valve function as permitted by OM-10, 64.3.2.4(a).

EG-V34A SWINGCHECK 5.0 A C ACTIVE OPEN TO CLOSE NA --- ---

CLOSE QUARTER C-302-354

Description:

JACKET COOLANT RADIATOR BYPASS CHECK VALVE DISASEMBLE 10 YEAR Justification: This valve will be tested as part of the test of the Dieset Generator. The valve is an integral part of the Diesel skid. Maintaining the Diesel Jacket water tem erature within its perating range will be considered as an acceptable test of the valve and is considered an indirect observation of valve fmetion as permitted by OM-10,14.3.2.4(a).

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EG-V34B SWINGCHECK 5.0 A C ACTIVE OPEN TO CLOSE NA --- ---

CLOSE QUARTER C-302-354

Description:

JACKET COOLANT RADIATOR BYPASS CHECK VALVE DISASEMBLE 10 YEAR Justification: This valve will be tested as part of the test of the Diesel Generator. The valve is an integral part of the Diesel skid. Maintaining the Diesel Jacket water temperature within its operating range will be considered as an acceptable test of the valve and is considered an indirect observation of valve function as permitted by OM-10, 64.3.2.4(a).

EG-V47A THREE WAY 4.0 A C ACTIVE CLOSE TO OPEN NA --- ---

MAIN FEEDWATER STARTUP FLOW CONTROL VALVE FAIL SAFE COLD SD POS VERIFY 2 YEAR FW-V16B CONTROL 6.0 A B ACTIVE OPEN TO CLOSE AIR OPEN AS IS TIME COLD SD C-302-081

Description:

MAIN FEEDWATER STARTUP FLOW CONTROL VALVE FAIL SAFE COLD SD POS VERIFY 2 YEAR FW-V17A CONTROL 20.0 A B ACTIVE OPEN TO CLOSE AIR THROT AS 15 TIME COLD SD C-302-081 DGscription: MAIN FEEDWATER CONTROL VALVES FAIL SAFE COLD SD POS VERIFY 2 YEAR FW-U17B CONTROL 20.0 A B ACTIVE OPEN TO CLOSE AIR THROT AS IS TIME COLD SD C-302-081 l

Description:

MAIN FEEDWATER CONTROL VALVE FAIL SAFE COLD SD POS VERIFY 2 YEAR FW-V92A GATE 6.0 A B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME COLD SD C-302-081 DGscription: OTSG "A" STARTUP FEEDWATER BLOCK VALVE POS VERIFY 2 YEAR Justification: This valves do not have jog control a cannot be part stroked. This valve is in the main feedwater line and cannot be closed during operation.

Per OM-10, 54.2.12(c), it will be exercised at the Cold Shutdown frequency.

FW-V928 GATE 6.0 A B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME COLD SD C-302-081 DGscription: OTSG "B" STARTUP FEEDWATER BLOCK VALVE POS VERIFY 2 YEAR Justification: This valves do not have jog control a cannot be part stroked. This valve is in the main feedwater line and cannot be closed during operation.

Per OM-10, 54.2.12(c), it will be exercised at the Cold Shutdown frequency.

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TABLE B-3 TMI1 AUGMENTED IST PROGRAM VALVE TABULATION VALVE NO TYPE SIZE .CL.S g l ACTIVE / PASS!VE ACTUATOR NORM POS FAIL POS TEST TYPE FREQUENCY DRAWING RELIEF NO IA-V1625A THREE WAY 1.0 A ACTIVE AIR OPEN OPEN FUNCTION REFUEL 302-273

Description:

2-HR BACKUP AIR SYSTEM "A" HEADER VENT VALVE IA-V16258 THREE WAY 1.0 A ACTIVE AIR OPEN OPEN FUNCTION REFUEL 302-273 DTeription: 2-HR BACKUP AIR SYSTEM "B" HEADER VENT VALVE IA-V1626A THREE WAY 1.0 A ACTIVE AIR OPEN OPEN FUNCTION REFUEL- 302-273

Description:

2*HR BACKUP AIR SYSTEM HEADER SUPPLY VALVE i Justification: There is no practical way to stroke time these valves. The test includes stroking the Emergency Feedwater and Mainsteam valves supplied by the 2-hr Back @ Air Bottles to demonstrate this component will perform its intended f metion.

IA-V1626B THREE WAY 1.0 A ACTIVE AIR OPEN OPEN FUNCTION REFUEL 302-273

Description:

2-HR BACKUP AIR SYSTEM HEADER SUPPLY VALVE Jus 2ification: There is no practical way to stroke time these valves. The test includes stroking the Emergency Feedwater and Mainsteam valves supplied by the 2-Hr Backup Air Bottles to demonstrate this component will perform its intended fmetion.

IC-U 1A GATE 4.0 A B ACTIVE MOTOR ---

AS IS TIME COLD SD 1D-ISI-FD-022

Description:

LETDOWN COOLER "A" SUPPLY ISOLATION VALVE Justification: This valve has no Nuclear Safety Function.

IC-U 1B GATE 4.0 A B ACTIVE MOTOR ---

As IS TIME COLD SD 1D-ISI-FD-022 DGscription: LETDOWN COOLER "B" SUPPLY ISCLATION VALVE Justification: The valve has no Nuclear Safety Function.

CS-v10A GATE 6.0 A B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME REFUEL 10-ISI-FD-001

Description:

OTSG "A" TO EF-P1 J0G/ THROTTLE VALVE POS VERIFY 2 YEAR Justification: Valve is not required to perfors: a safety function or midigate the censequences of an accident. GPUN has chosen to test this valve at a refueling interval frequency. ;

MS-V10B GATE 6.0 A B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS TIME REFUEL ID-ISI-FD-001

Description:

OTSG "B" TO EF-P1 J0G/ THROTTLE VALVE POS VEEIFY 2 YEAR Justification: Valve is not required to perform a safety function or mitigate the consequences of an accident. GPUN has chosen to test the valve at a refueling ;

interval frequency. !

l MU-V217 GLOBE 2.5 A B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS PARTIAL QUARTER 1D-ISI-FD-017

Description:

HIGH CAPACITY NORMAL MAKEUP VALVE TIME COLD SD l POS VERIFY 2 YEAR l Justification: This valve has no Nuclear Safety Related function. It is used to avoid chalanges to the High Pressure Injection system in that it is manually l

opened to increase make @ flow during some abnormal conditions and during reactor trip.

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I I TABLE 8-3 t

t TMil AUGIENTED IST PROGRAM VALVE TABULATION 1

t I' . VALVE NO- TYPE SIZE CLS CA.T ACTIVE / PASSIVE ACTUATOR NORM POS FAIL POS TEST TYPE' FREQUENCY DRAWING RELIEF NO NS-V 32 GATE 8.0 ' A ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS TIME COLD SD ID-ISI-FD-010

Description:

INLET HEADER 70 EVAP CONDENSER & WG COMP VALVE l ................................................................................................................................................................

l RC-V 1 GLOBE 2.5 A B ACTIVE CLOSE TO OPEN MOTOR CLOSE AS IS PARTIAL QUARTER 1D-ISI-FD-019

Description:

PRESSURIZER SPRAY CONTROL VALVE POS VERIFY 2 YEAR l Justificaticn: This valve has no nuclear safety fmetion, but it is inportant to plant operation. It is one of two valves in series used as a method of redJcing RCS pressure during a transient.

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l RC-V 3 GLOBE 2.5 A B ACTIVE OPEN TO CLOSE MOTOR OPEN AS IS T!ME COLD SD 1D-ISI-FD-019 l_

Description:

PRESSURIZER SPRAY LINE ISOLATION VALVE POS VERIFY 2 YEAR

'- Justification: This valve has no nuclear safety fmetion, but it is important to plant operation. RC-V3 is one of two valves in series used as a method of i reducing RCS pressure during a transient. One of the two vilves must reclose to avoid lowering pressure below the normal operating point.

l SF-V44 DIAPHRAGM 4.0 A B PASSIVE MAND CLOSE --- --- ---

C302-630

Description:

ISOLATION VALVE FROM SPENT FUEL TO DH-P1A Jus 2ification: See relief request V 2 for discussion of relief regarding DH-V50.

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ML20092M194

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