Text

CFR 50.55a(f)(4)(iv) Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code for Inservice Testing
	ML040440424
Person / Time
Site:	Palo Verde
Issue date:	02/05/2004
From:	Mauldin D; Arizona Public Service Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	102-05046-CDM/SAB/RKR
	Download: ML040440424 (136)
	v • d • e

LAFS 10 CFR 50.55a David Mauldin Vice President Mail Station 7605 Palo Verde Nuclear Nuclear Engineering TEL (623) 393-5553 P.O. Box 52034 Generating Station and Support FAX (623) 393-6077 Phoenix, AZ 85072-2034 102-05046-CDM/SAB/RKR February 5, 2004 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-52815291530 10 CFR 50.55a(f)(4)(iv) Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME)

Section Xl Code for Inservice Testing Pursuant to 10 CFR 50.55a(f)(4)(iv), Arizona Public Service Company (APS) is proposing to update portions of the Palo Verde Nuclear Generating Station (PVNGS) inservice testing (IST) program second 10-year interval for Units 1, 2, and 3 to later editions and addenda of the ASME Code. APS requests Commission approval of these proposed changes in accordance with 10 CFR 50.55a(f)(4)(iv). The proposed subsequent editions and addenda are incorporated by reference in 10 CFR 50.55a(b),

and are described in the enclosure to this letter. Federal Register, Volume 67, Number 187, dated Thursday, September 26, 2002 (67 FR 60520), incorporate by reference the 1997 Addenda, 1998 Edition, 1999 Addenda, and 2000 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for IST programs in 10 CFR 50.55a(b).

The change would extend the exercise interval for manual valves within the scope of the PVNGS IST program from three months to two years. Currently, the PVNGS IST program is committed to the 1989 Edition of the ASME Section Xl Code that invokes the 1987 Edition and 1988 Addenda of the OM Code.

A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway

Comanche Peak

Diablo Canyon Palo Verde

South Texas Project

Wolf Creek 04 A (

U.S. Nuclear Regulatory Commission PVNGS Units 1, 2, and 3, Docket Nos. STN 50-528(529/530 Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME) Section Xl Code for Inservice Testing Page 2 This request is similar to a request previously approved by the NRC for Indian Point Unit 3, dated June 20, 2002 (TAC No. MB3865).

APS requests approval by August 31, 2004, in order to implement the change during the summer 2004.

No commitments are being made to the NRC in this letter. Enclosed for information only is the latest revision to the APS Pump and Valve Testing Program. The enclosure is revision 14 to PVNGS procedure 73DP-9XI01, "Pump and Valve Inservice Testing Program - Component Tables." Should you have any questions, please contact Thomas N.Weber at (623) 393-5764.

CDM/SAB/RKR/kg

Enclosures:

1. Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME) Code for Inservice Testing

2. Revision 14 to PVNGS procedure 73DP-9XI01, Pump and Valve Inservice Testing Program - Component Tables."

cc: B. S. Mallett NRC Region IV Regional Administrator M. B. Fields NRC NRR Project Manager N. L. Salgado NRC Senior Resident Inspector for PVNGS

ENCLOSURE Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME) Code for Inservice Testing

Request to Use Subsequent Editions and Addenda of American Society of Mechanical Engineers (ASME) Code for Inservice Testing

1. ASME Code Components Affected This Request affects all manually-operated valves in the Inservice Testing (ST)

Program at Palo Verde Nuclear Generating Station (PVNGS) units 1, 2, and 3.

2. Applicable Code Edition and Addenda

The current Code of record for the PVNGS IST Program is the 1989 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code. This Code invokes the 1987 Edition and 1988 Addenda of the ASME Code for Operation and Maintenance of Nuclear Power Plants (OM Code). This Code requires that the manual valves be exercised at a three month interval.

3. Proposed Subsequent Code Edition and Addenda (or Portion)

PVNGS requests approval to use the portions of the 2000 Addenda of the ASME OM Code related to inservice testing of manually-operated valves. Federal Register, Volume 67, Number 187, dated Thursday, September 26, 2002 (67 FR 60520),

incorporates by reference the 1997 Addenda, 1998 Edition, 1999 Addenda, and 2000 Addenda of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for Inservice Testing (IST) programs in 10 CFR 50.55a(b).

Specifically, PVNGS would apply the requirements of ISTC-3540, "Manual Valves",

and ISTC-5210, "Manually-Operated Valves", from the 2000 Addenda.

"ISTC-3540 Manual Valves. Manual valves shall be full-stroke exercised at least once every five years, except where adverse conditions may require the valve to be tested more frequently to ensure operational readiness. Any increased testing frequency shall be specified by the Owner. The valve shall exhibit the required change of obturator position.'

"ISTC-5210, Manually-Operated Valves. Valve testing shall be in accordance with ISTC-3500. If a valve fails to exhibit the required change of obturator position, the valve shall be immediately declared inoperable. Valves equipped with remote position indication shall be tested in accordance with ISTC-3700."

1

4. Limitations/Modifications and Related Requirements 10 CFR 50.55a(f)(4)(iv) states:

"Inservice tests of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b) of this section, subject to the limitations and modifications listed in paragraph (b) of this section, and subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions or addenda are met."

10 CFR 50.55a(b)(3) states:

"As used in this section, references to the OM Code refer to the ASME Code for Operation and Maintenance of Nuclear Power Plants, and include the 1995 Edition through the 2000 Addenda subject to the following limitations and modifications:"

Limitations and Modifications In accordance with the limitation imposed by 10 CFR 50.55a(b)(3)(vi), manual valves will be exercised on a 2-year interval rather than the 5-year interval specified in ISTC-3540 of the 2000 Addenda, provided that adverse conditions do not require more frequent testing.

Related Requirements The other requirements of the 2000 Addenda of the ASME OM Code that are related to the exercising of manual valves are essentially the same as those specified by the 1988 Addenda. Therefore the other requirements of the 1988 Addenda will continue to be applied to manual valves in the PVNGS ST Program.

5. Basis of Usinq Subsequent Code Editions and Addenda The ASME OM Code through the 2000 Addenda has been incorporated by reference in 10 CFR 50.55a(b)(3) per 67 FR 60520.

6. Duration of Proposed Request The duration of the proposed request is the remainder of the PVNGS second 10-year IST interval, which is scheduled to end January 15, 2008.

2

7. Precedents This request is similar to a request previously approved by the NRC for Indian Point Unit 3, dated June 20, 2002 (TAC No. MB3865).

3

ENCLOSURE 2 Revision 14 to PVNGS procedure 73DP-9XI01, "Pump and Valve Inservice Testing Program - Component Tables."

(For information Only)

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 1 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Procedure Intent This procedure identifies the pump and valve tests performed to meet the requirements of 10 CFR 50.55a, Section XI of the ASME Boiler and Pressure Vessel Code, and Technical Specification 5.5.8.

Revision 14 Changes

Updated the "Approval" section of all PRRs and VRRs to reflect approval status from the NRC SER dated July 8, 1999. Added a new PRR, CSJ, ROJ, and VRR summary table.

Deleted the PRRs, CSJs, ROJs, and VRRs that are no longer active.

Revision 13 Changes

Placed a note in the "Remarks" section of the valve table identifying MSIV and Economizer FWIV part-stroke exercise tests as "augmented" tests. Affected EQIDs are: MSIVs SGEUVO170, SGEUVO171, SGEUVOI80, SGEUV0181, and Economizer FWIVs SGBUVOI32, SGBUVOI37, SGAUV0174, and SGAUVO177. Also updated Cold Shutdown Justifications CSJ-18 and CSJ-19 accordingly. Basis: Part-stroke tests are not practical for ASME Section XI testing because of the risk of full closure. However, these part-strokes remain part of the IST Program as "augmented" tests at the request of System Engineering in order to confirm continued operability by periodically exercising the 4-way pilot valves.

This clarification in the IST Program was made to allow part-stroke testing to be waived in cases where the MSIVs or FWIVs were recently stoked for other reasons, such as a unit outage. For additional information, see the White Paper that accompanies 73DP-9XI0 I rev.

13.

Reformatted the valve tables to make them more compact.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 2 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Introduction This procedure identifies the pump and valve tests performed to meet the requirements of 10 CFR 50.55a, Section XI of the ASME Boiler and Pressure Vessel Code, and Technical Specification 5.5.8.

This program is applicable to PVNGS Units 1, 2, and 3. The pumps and valves within the scope of this program are identified in the component tables.

The second 10-year IST interval for all three units begins on January 15, 1998, and ends on January 15, 2008. During this interval, inservice testing is performed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition; and ASME/ANSI OM-1987, "Operation and Maintenance of Nuclear Power Plants", Part 1, Part 6 (with OMa-1988 Addenda), and Part 10 (with OMa-1988 Addenda). Deviations from the requirements of these codes are documented by relief requests.

Component Tables The Pump Table, Valve Table, and supporting documentation are provided on the following pages:

Pump Table ................................. 3 Valve Table ................................. 5 PRRs, CSJs, ROJs, and VRRs ................................ 47 Notes, Legends, Definitions, and Abbreviations ................................ 126 References Implementing References

73DP-9XI02, "Pump and Valve Inservice Testing Program - Administrative Requirements"

Surveillance test procedures as listed in the Pump Table and Valve Table Developmental References Developmental references for the Pump and Valve IST Program are listed in 73DP-9XI02.

In addition, recent IST Program changes are documented by the following:

LDCR 00-R003 and 10 CFR 50.59 Evaluation# 00-00033 (Change LTOP PSV testing interval from 18 months to 10 years)

LDCRs 00-RO05 (TRM), 00-F039 (UFSAR), and 10 CFR 50.59 Evaluation # 00-00069 (Delete Type C testing from shutdown cooling CIVs)

LDCRs 01-R003 (TRM), 01-F009 (UFSAR), and 10 CFR 50.59 Evaluation # 01-00019 rev. I (Delete Type C testing from HPSI hot leg injection CIVs)

CRDR 2410646 (Addition of valves SIEV500 and SIEV501 to the IST Program)

50.59 Screening S03-0045 (Delete Appendix J Type C testing on valves SIEV500 and SIEV501)

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 3 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Pump Table PumpID/ Code l Drawing j Flow Vibra- Test Description I Class i Coord.g Speed Press. i Rate tion IProcedure Remarks AFA-P01 3 AFP-001 QTR QTR NA QTR 73ST-9AF02 Minimum flow Essential Auxiliary Feedwater D06 PRR-01 recirc test Pump (Turbine-Driven)

CSD CSD CSD CSD 73ST-9AF02 Full-flow test per PRR-01 AFB-P01 3 AFP-001 NA QTR NA QTR 73ST-9AF03 Minimum flow Essential Auxiliary Feedwater B06 PRR-01 recirc test Pump (Motor-Driven)

NA CSD CSD CSD 73ST-9AF03 Full-flow test per PRR-01 AFN-P01 N AFP-001 NA QTR NA QTR 73ST-9AFO1 Augmented Non-Class Auxiliary H06 PRR-02 component, Feedwater Pump (Motor- tested pursuant Driven) to SR 3.7.5.2 CHA-P01 2 CHP-002 NA QTR QTR QTR 73ST-9CH06 Charging Pump B03 PRR-03 PRR-07 CHB-P01 2 CHP-002 NA QTR QTR QTR 73ST-9CH06 Charging Pump D03 PRR-03 PRR-07 CHE-P01 2 CHP-002 NA QTR QTR QTR 73ST-9CH06 Charging Pump G03 PRR-03 PRR-07 CTA-P01 3 CTP-001 NA QTR QTR QTR 73ST-9CTO Augmented Condensate Transfer Pump C05 component CTB-P01 3 CTP-001 NA QTR QTR QTR 73ST-9CT01 Augmented Condensate Transfer Pump B05 component DFA-P01 Diesel Generator Fuel Oil Transfer Pump 3 DFP-001 B06 NA QTR I QTR I NA*

I 73ST-9DFOI *Submerged pump - no accessible I I T lI i bearings.

QTR DFB-P01 Diesel Generator Fuel Oil 3 DFP-001 B02 NA II QTR II NA* II73ST-9DFOI *Submerged pump - no Transfer Pump I - - ________ I I ________ ________ I ______________

accessible bearings.

ECA-PO1 3 ECP-001 NA QTR QTR QTR 73ST-9ECOI Essential Chilled Water Circulation Pump / B08 ECB-PO1 3 ECP-001 NA QTR QTR QTR 73ST-9ECOI Essential Chilled Water B04 Circulation Pump EWA-P01 3 - EWP-001 - NA QTR - QTR QTR 73ST-9EW01 Essential Cooling Water E06 Pump EWB-PO1 3 EWP-001 NA QTR TR QTR 73ST-9EW01 Essential Cooling Water Pump I E02 I

/Qi R

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 4 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rcision COMPONENT TABLES 14 Pump ID l Code Drawing Flow Vibra- Test Description Class I Coord. I Seed Press. l Rate l tion l Procedure Remarks PCA-POI 3 PCP-OO1 NA QTR QTR QTR 73ST-9PCOI Augmented Spent Fuel Pool Cooling D15 component Pump PCB-POl 3 PCP-OOI NA QTR QTR QTR 73ST-9PCOI Augmented Spent Fuel Pool Cooling B15 component Pump SIA-POI 2 SIP-OOI NA QTR NA QTR 73ST-9SI I Minimum flow Low Pressure Safety Injection Fl 1 PRR-05 recirc test (LPSI) Pump NA CSD CSD CSD 73ST-9S114 Full-flow test per PRR-05 SIB-POI 2 SIP-OOI NA QTR NA QTR 73ST-9SII I Minimum flow Low Pressure Safety Injection Bl I PRR-05 recirc test (LPSI) Pump NA CSD CSD CSD 73ST-9S114 Full-flow test

_____ _____ _____ _____ __ _ _ _perPRR-05 SIA-P02 2 SIP-OOI NA i QTR i NA QTR j 73ST-9SI10 Minimum flow High Pressure Safety Injection Ell PRR-06 recirc test (HPSI) Pump NA RFO RFO RFO 73ST-9XI33 Full-flow test per PRR-06 SIB-P02 2 SIP-OO l NA QTR NA QTR 73ST-9SI10 Minimum flow High Pressure Safety Injection All PRR-06 recirc test (HPSI) Pump NA RFO RFO RFO 73ST-9XI33 Full-flow test

I I l l l ! l per PRR-06 SIA-P03 2 SIP-OOI NA QTR NA i QTR - 73ST-9Si06 Minimum flow Containment Spray Pump HI PRR-I recirc test NA CSD CSD CSD 73ST-9SI15 Full-flow test per PRR-I SIB-P03 2 SIP-OO l NA QTR NA QTR 73ST-9SI06 Minimum flow Containment Spray Pump CHl PRR-I recirc test NA CSD CSD CSD 73ST-9S115 Full-flow test l i i______ l______ l _______ l ______ l per PR R-II SPA-POI Essential Spray Pond Pump 3 SPP-OO Sh.

C04 i NA I

QTR QTR I QTR I

I 73ST-9SPOI I

Vertical line shaftpump SPB-POI 3 SPP-OO l NA QTR QTR QTR 73ST-9SP01 Vertical line Essential Spray Pond Pump Sh. I I I shaft pump

_ __ __ _ C07 _ _ I I _ _ __

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 5of 129 PUMP AND VALVE NSERVICE TESTING PROGRAM - 73DP9X101 I Revision 14 COMPONENT TABLES Drawing Size (in) Cat. CSJ/

Valve ID CoordlSht# Type A/P ROJI Description Code Class Act S.P. Test Freq Procedure VRR Remarks AFAV007 AFP-001 8 C FSO CSD 73ST-9AF02 CSJ-01 Notes 1, 2, 3 TURBINE-DRIVEN AFW PUMP SUCTION D07 CK A PSO QTR 73ST-9AF02 CSJ-01 CHECK VALVE FROM CONDENSATE 3 SA 0 STORAGE TANK AFAV015 AFP-001 6 C FSO CSD 73ST-9AF02 CSJ-03 Notes 1, 2 3 TURBINE-DRIVEN AUXILIARY FEEDWATER E05 CK A FSC CSD 73ST-9XI38 CSJ-03 PUMP DISCHARGE CHECK VALVE 3 SA OC AFBV022 AFP-001 8 C FSO CSD 73ST-9AF03 CSJ-01 Notes 1. 2 3 MOTOR-DRIVEN AFW PUMP SUCTION C07 CK A PSO 0TR 73ST-9AF03 CSJ-01 CHECK VALVE FROM CONDENSATE 3 SA 0 STORAGE TANK AFBV024 AFP-001 6 C FSO CSD 73ST-9AF03 CSJ-03 Notes 1, 2. 3 MOTOR-DRIVEN AUXILIARY FEEDWATER C05 CK A FSC CSD 73ST-9AF02 CSJ-03 PUMP DISCHARGE CHECK VALVE 3 SA OC AFBHV0030 AFP-001 6 B FSO OTR 73ST-9X105 VRR-12 Note 5 MOTOR-DRIVEN AFW PUMP TO SG #1 B04 GL A FSC QTR 73ST-9X105 VRR-12 QTR FS FOR PRAtRA FLOW CONTROL VALVE 3 MO OC STO 18M 73ST-9X105 VRR-12 18M ST FORTS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFBHV0031 AFP-001 6 B FSO QTR 73ST-9X105 VRR-12 Note 5 MOTOR-DRIVEN AFW PUMP TO SG #2 804 GL A FSC QTR 73ST-9XI05 VRR-12 QTR FS FOR PRAJRA FLOW CONTROL VALVE 3 MO OC STO 18M 73ST-9XI05 VRR-12 18M ST FORTS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFAHV0032 AFP-001 6 B FSO QTR 73ST-9XI05 VRR-12 Note 5 TURBINE-DRIVEN AFW PUMP TO SG #1 D04 GL A FSC 0TR 73ST-9X105 VRR-12 QTR FS FOR PRAJRA FLOW CONTROL VALVE 3 MO OC STO 18M 73ST-9X105 VRR-12 18M ST FORTS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFCHV0033 AFP-001 6 B FSO 0TR 73ST-9X105 VRR-12 Note 5 TURBINE-DRIVEN AFW PUMP TO SG #2 C04 GL A FSC QTR 73ST-9X105 VRR-12 QTR FS FOR PRAJRA FLOW CONTROL VALVE 3 MO OC STO 18M 73ST-9x105 VRR-12 18M ST FORTS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFBUVO034 AFP-001 6 B FSO QTR 73ST-9X105 VRR-12 Note 5 MOTOR-DRIVEN AFW PUMP TO SG #1 B03 GA A FSC QTR 73ST-9XI05 VRR-12 QTR FS FOR PRAtRA ISOLATION VALVE 2 MO OC STO 18M 73ST-9X105 VRR-12 18M ST FOR TS 3.3.5.4 STC 18M 73ST4XI05 VRR-12 AFBUVO035 AFP-01 6 B FSO 0TR 73ST-9X105 VRR-12 Note 5 MOTOR-DRIVEN AFW PUMP TO SG #2 C03 GA A FSC QTR 73ST-9XI05 VRR-12 QTR FS FOR PRAtRA ISOLATION VALVE 2 MC) OC STO 18M 73ST-9X105 VRR-12 18M ST FOR TS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFCUVO036 AFP-001 6 6 FSO QTR 73ST-9X105 VRR-12 Note 5 TURBINE-DRIVEN AFW PUMP TO SG #1 D03 GA A FSC QTR 73ST-9X105 VRR-12 QTR FS FOR PRAJRA ISOLATION VALVE 2 MO OC STO 18M 73ST-9X105 VRR-12 18M ST FOR TS 3.3.5A STC 18M 73ST-9X105 VRR-12 AFAUVO037 AFP-001 6 B FSO QTR 73ST-9X105 VRR-12 Note 5 TURBINE-DRIVEN AFW PUMP TO SG #2 D03 GA A FSC 0TR 73ST-9XI05 VRR-12 QTR FS FOR PRAJRA ISOLATION VALVE 2 MO OC STO 18M 73ST-9X105 VRR-12 18M ST FOR TS 3.3.5.4 STC 18M 73ST-9XI05 VRR-12 AFAHV0054 AFP-001 4 B FSO 0TR 73ST-9AF02 VRR-12 Note 5 TURBINE-DRIVEN AFW PUMP G04 GL A QTR FS FOR PRAARA TRIPJTHROTTLE VALVE 3 MO 0 PREVIOUSLY TESTED IN 73ST-9X105.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 6 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XJ01 l 14 COMPONENT TABLES Drawing SIze (In) CaL CSJI Valve ID Coord/Sht# Type AIP ROJ/

Description Code Class Ac. S.P. Test Freq Procedure VRR Remarks AFAV079 AFP-001 6 C FSO CSD 73ST-9AF02 CSJ-04 Notes 1, 2, 3. Also exercised open AFW TO SG #1 CHECK VALVE E02 CK A In 73ST9AF03.

2 SA 0 AFBV080 AFP-001 6 C FSO CSD 73ST-9AF02 CSJ-04 Notes 1, 2. 3. Also exercised open AFW TO SG #2 CHECK VALVE C02 CK A In 73ST9AF03.

2 SA 0 AFAV096 AFP-001 4 C FSC RFO 73ST-9XI36 ROJ-13 Notes 1. 2. 3 AUX STEAM SUPPLY CHECK VALVE TO G02 CK A AFW TURBINE 3 SA C AFBPSVO106 AFP-001 0.75 C SV 10Y 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR B03 SV A AFBUN0034 BONNET 2 SA OC AFBPSVO107 AFP-001 0.75 C SV 1 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR C03 SV A AFBUVO035 BONNET 2 SA OC AFAPSVO108 AFP-001 0.75 C SV 10Y 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR D03 SV A AFCUVO036 BONNET 2 SA OC AFAPSVO109 AFP-001 0.75 C SV 1OY 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR D03 SV A AFAUVO037 BONNET 2 SA OC AFAV137 AFP-001 6 C FSO CSD 73ST-9AF02 CSJ-02 Notes 1. 2, 3 TURBINE DRIVEN AFW PUMP DISCHARGE D06 CK A PSO QTR 73ST-9AF02 CHECK VALVE 3 SA 0 AFBV138 AFP-001 6 C FSO CSD 73ST-9AF03 CSJ-02 Notes 1. 2. 3 MOTOR DRIVEN AFW DISCHARGE CHECK C06 CK A PSO QTR 73ST-9AF03 VALVE 3 SA 0 CHEVM70 CHP-001 3 AC FSO OTR 73ST-9CH06 Notes 1. 2 3 CHARGING TO REGENERATIVE HEAT F15 CK A FSC RFO 73ST-9XI28 ROJ-09 EXCHANGER INLET INBOARD CIV (PEN. 41) 2 SA OC AJ CLR 73ST-9CLO1 CHNPSVO115 CHP-002 3 C SV 1OY 73ST-9ZZ20 VOLUME CONTROL TANK OUTLET C06 SV A PRESSURE RELIEF VALVE 2 SA OC CHNV118 CHP-002 4 C FSO OTR 73ST-9CH06 Notes 1 2 3 VOLUME CONTROL TANK OUTLET CHECK B07 CK A VALVE 2 SA 0 CHNVI31 CHP402 0.5 B FSO TR 73ST-9XI31 BORIC ACID FILTER DP GAUGE EXCESS C11 DI A FSC QTR 73ST9XI31 FLOW CHECK VALVE MANUAL ISOLATION 3 MA C CHNVI44 CHP-02 3 B FSO QTR 73ST-9XI31 MANUAL ISOLATION VALVE FROM RWT TO B14 DI A FSC QTR 73ST-9XI31 SPENT FUEL POOL CLEANUP PUMPS 3 MA OC CHNV154 CHP.002 3 C FSO RFO 4xST-xCH04 ROJ-03 Notes 1, 2, 3 BORIC ACID MAKEUP PUMP DISCHARGE B13 CK A PSO QTR 73ST-9XI06 ROJ-03 CHECK VALVE 3 SA 0 CHNV155 CHP-002 3 C FSO RFO 4xST-xCH04 ROJ-03 Notes 1. 2, 3 BORIC ACID MAKEUP PUMP DISCHARGE B13 CK A PSO aTR 73ST-9XI06 ROJ03 CHECK VALVE 3 SA 0

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 7 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 1v4 COMPONENT TABLES Drawing Size (In) Cat CSJ/

Valve ID CoordlSht# Type A/P ROJ/

Description Code Class Ac. S.P. Test Freq Procedure VRR Remarks CHNVI64 CHP-02 3 B FSO QTR 73ST-9XI31 BORIC ACID MAKEUP FILTER BYPASS LINE DI Di A FSC OTR 73ST-9XI31 ISOLATION VALVE 3 MA O CHNV165 CHP-002 0.5 B FSO QTR 73ST-9XI31 BORIC ACID FILTER DP GAUGE EXCESS Cli Di A FSC QTR 73ST-9XI31 FLOW CHECK VALVE MANUAL ISOLATION 3 MA C CHAV177 CHP-002 3 C FSO RFO 4xST-xCH04 ROJ-01 Notes 1. 2. 3 BORIC ACID MAKEUP CHECK VALVE TO B07 CK A PSO CSD 4xST-xCH04 ROJ-01 VCT OUTLET 2 SA O CHAV190 CHP-002 3 C FSO RFO 4xST-xCH04 ROJ-01 Notes 1. 2 3 RWT TO CHARGING PUMP SUCTION A07 CK A PSO CSD 4xST-xCH04 ROJ-01 CHECK VALVE 2 SA O CHNPSVO199 CHP-002 2 C SV 1Y 73ST-9ZZ20 RCP SEAL BLEEDOFF RELIEF VALVE HIS SV A 2 SA OC CHBHV0203 CHP-001 2 B FSO CSD 73ST-9XI22 CSJ-06 Cycled every 18 months per TRM AUXILIARY PRESSURIZER SPRAY VALVE H10 GL A FSC CSD 73ST9X122 CSJ-06 TSR 3.4.100.3 1 SO OC STO CSD 73ST9X122 CSJ-06 STC CSD 73ST-9XI22 CSJ-06 FTC CSD 73ST-9XI22 CSJ-06 VP 2YR 73ST-9XI27 CHAHV0205 CHP-001 2 B FSO CSD 73ST-9XI22 CSJ-06 Cycled every 18 months per TRM AUXILIARY PRESSURIZER SPRAY VALVE HIl GL A FSC CSD 73ST-9X122 CSJ46 TSR 3.4.100.3 1 SO OC STO CSD 73ST-9XI22 CSJ-06 STC CSD 73ST9XI22 CSJ-06 FTC CSD 73ST-9XI22 CSJ-06 VP 2YR 73ST-9X127 CHEHV0239 CHP-001 2 B FSC QTR 73ST-9XI06 NORMAL CHARGING FLOWPATH Gil GL A STC QTR 73ST-9X106 ISOLATION VALVE 2 AO C FTC QTR 73ST-9XI06 VP 2YR 73ST-9X106 CHEPDVO240 CHP-001 2 B FSC OTR 73ST9X106 NORMAL CHARGING FLOWPATH Gil GL A STC QTR 73ST-9XI06 ISOLATION VALVE 1 AO C FTC QTR 73ST-9X106 VP 2YR 73ST9X106 CHBHV0255 CHP-001 1.5 A FSC ICY 73ST-9X122 VRR-12 Note 5 RCP SEAL INJECTION OUTBOARD CIV G04 GL A AJ CLR 73ST-9CL01 (PEN. 72) 2 MO C CHBV305 CHP002 20 C FSO RFO 73ST-9X129 ROJ-02 Notes 1, 2. 3 REFUELING WATER TANK OUTLET CHECK B15 CK A FSC RFO 73ST-9XI39 ROJ-10 VALVE TO SI SUCTION HEADER 2 SA OC PSO QTR 73ST9S111 ROJ-02 CHAV306 CHP-002 20 C FSO RFO 73ST9XI29 ROJ-02 Notes 1, 2. 3 REFUELING WATER TANK OUTLET CHECK C13 CK A FSC RFO 73ST-9XI39 ROJ-10 VALVE TO SI SUCTION HEADER 2 SA OC PSO QTR 73ST-9S111 ROJ-02 CHAPSVO315 CHP-002 0.75 C SV I Y 73ST-9ZZ20 CHARGING PUMP SUCTION PRESSURE C05 SV A RELIEF VALVE 2 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 8 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 1v;4 COMPONENT TABLES Drawing Size (In) Cat. CSJI Valve ID Coord/Sht# Type A/P ROJI Description Code Class Ad. S.P. Test Freq Procedure VRR Remarks CHAV316 CHP-002 4 B FSO TR 73ST-9X131 CHARGING PUMP CHA-PO NORMAL B05 Di A FSC TR 73ST-9XI31 SUCTION FROM VCT MANUAL ISOLATION 2 PA OC VALVE CHBPSVO318 CHP-002 0.75 C SV lay 73ST-9ZZ20 CHARGING PUMP SUCTION PRESSURE F05 SV A RELIEF VALVE 2 SA OC CHBV319 CHP-002 4 B FSO QTR 73ST-9X131 CHARGING PUMP CHB-P01 NORMAL D05 Di A FSC TR 73ST-9XI31 SUCTION FROM VCT MANUAL ISOLATION 2 MA OC VALVE CHEPSVO321 CHP-002 0.75 C SV IY 73ST-9ZZ20 CHARGING PUMP SUCTION PRESSURE H05 SV A RELIEF VALVE 2 SA OC CHEV322 CHP-002 4 B FSO TR 735T9XI31 CHARGING PUMP CHE-PO NORMAL G05 Di A FSC TR 73ST-9XI31 SUCTION FROM VCT MANUAL ISOLATION 2 MA OC VALVE CHEPSVO324 CHP-002 0.75 C SV laY 73ST-9ZZ20 CHARGING PUMP DISCHARGE PRESSURE G02 SV A RELIEF VALVE 2 SA OC CHBPSVO325 CHP-002 0.75 C SV lay 73ST-9ZZ20 CHARGING PUMP DISCHARGE PRESSURE E02 SV A RELIEF VALVE 2 SA OC CHAPSVO326 CHP-002 0.75 C SV 10Y 73ST-9ZZ20 CHARGING PUMP DISCHARGE PRESSURE C02 SV A RELIEF VALVE 2 SA OC CHBV327 CHP-002 3 B FSO TR 73ST-9X131 CHARGING PUMP ALTERNATE SUCTION E05 DI A FSC TR 73ST-9XI31 COMMON ISOLATION VALVE 2 MA OC CHAV328 CHP-002 2 C FSO TR 73ST-9CH06 Notes 1, 2. 3 CHARGING PUMP CHA-PO DISCHARGE 602 CK A CHECK VALVE 2 SA 0 CHBV331 CHP-002 2 C FSO QTR 73ST-9CH06 Notes 1, 2, 3 CHARGING PUMP CHB-PO DISCHARGE E02 CK A CHECK VALVE 2 SA 0 CHEV334 CHP-002 2 C FSO QTR 73ST-9CH06 Notes 1, 2. 3 CHARGING PUMP CHE-PO DISCHARGE G02 CK A CHECK VALVE 2 SA 0 CHNPSVO345 CHP-001 2 C SV 10Y 73ST-9ZZ20 LETDOWN CONTROL VALVE OUTLET E12 SV A RELIEF VALVE 2 SA OC CHNPSVO354 CHP-001 2 C SV 1Y 73ST-9ZZ20 LETDOWN BACK PRESSURE CONTROL F9 SV A VALVE OUTLET REUEF VALVE 2 SA OC CHEV429 CHP-001 2 C FSO QTR 73ST-9CH06 Notes 1, 2, 3 COMMON CHARGING LINE TO D16 CK A REGENERATIVE HEAT EXCHANGER CHECK 2 SA 0 VALVE

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 9 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP9XI01 Re1iion COMPONENT TABLES 14 Drawing Size (in) Cat. cSi Valve ID CoordlSht# Type A/P ROJI Description Code Class At. S.P. Test Freq Procedure VRR Remarks CHEV431 CHP-001 2 C FSO CSD 73ST-9XI27 CSJ-06 Notes 1, 2, 3 PRESSURIZER AUXILIARY SPRAY CHECK G09 CK A VALVE I SA 0 CHEV433 CHP-001 2 C FSO TR 73ST-9CH06 Notes 1. 2. 3 CHARGING LINE CHECK VALVE TO RCS G09 CK A I SA 0 CHEV435 CHP-001 2 C FSO TR 73ST-9CH06 Notes 1. 2. 3 REGENERATIVE HEAT EXCHANGER F1i CK A OUTLET CHECK VALVE I SA 0 CHNV494 CHP-003 1.5 AC FSC CSD 73ST-9XI28 CSJ-29 Notes 1, 2 3 REACTOR MAKEUP WATER SUPPLY E15 CK A A) CLR 73ST-9CL01 CHECK VALVE TO RDT INBOARD CIV (PEN. 2 SA C 45)

CHNUVO501 CHP-002 4 8 FSC ICY 73ST-9X122 VRR-12 Note 5 VOLUME CONTROL TANK OUTLET C07 GA A ISOLATION VALVE 2 MO C CHBUVO505 CHP-002 1 A FSO CSD 73ST-9X122 CSJ-32 REACTOR COOLANT SEAL BLEED-OFF H13 GL A FSC CSD 73ST-9XI22 CSJ-32 OUTBOARD CIV (PEN. 43) 2 AO C STO CSD 73ST-9XI22 CSJ-32 STC CSD 73ST-9X122 CSJ-32 FTC CSD 73ST-9XI22 CSJ-32 Al CLR 73ST-9CLOI VP 2YR 73ST-9X122 CHAUVO506 CHP-002 1 A FSO CSD 73ST9X122 CSJ-32 REACTOR COOLANT SEAL BLEED-OFF H14 GL A FSC CSD 73ST-9X122 CSJ-32 INBOARD CIV (PEN. 43) 2 AO C STO CSD 73ST-9X122 CSJ-32 STC CSD 73ST9XI22 CSJ-32 FTC CSD 73ST-9X122 CSJ-32 A) CLR 73ST-9C-01 VP 2YR 73ST-9X122 CHNUVO514 CHP-002 3 B FSO ICY 73ST-9XI06 VRR-12 Note 5 BORIC ACID MAKEUP TO CHARGING PUMP B10 GL A SUCTION ISOLATION VALVE 3 MO 0 CHBUVO515 CHP-001 2 B FSC CSD 73ST-9X122 CSJ-09 LETDOWN ISOLATION VALVE H15 GL A STC CSD 73ST-9X122 CSJ-09 1 AO C FTC CSD 73ST-9X122 CSJ-09 VP 2YR 73ST9X122 CHAUVO516 CHP-001 2 A FSC CSD 73ST9X122 CSJ-09 LETDOWN INBOARD CIV (PEN. 40) G15 GL A STC CSD 73ST4X122 CSJ-09 1 AO C FTC CSD 73ST-9XI22 CSJ-09 Al CLR 73ST-9CLO1 VP 2YR 73ST-9XI22 CHBUVO523 CHP-001 2 A FSC CSD 73ST-9XI22 CSJ-09 LETDOWN FROM REGENERATIVE HEAT F13 GL A STC CSD 73ST9X122 CSJ-09 EXCHANGER OUTBOARD CIV (PEN. 40) 2 AO C FTC CSD 73ST-9XI22 CSJ-09 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9X122 CHAHV0524 CHP-001 2 B AJ CLR 73ST-9CLOI Note 5, NO EXERCISE REQ'T-CHARGING LINE OUTBOARD CIV (PEN. 41) D16 GL P PASSIVE VALVE (NO PRA OR TS 2 MO 0 3.3.5.4 REQ7S FOR THIS MOV).

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 10 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES Drawing Size (in) Cat. CSJI Valve ID Coord/Sht# Type A/P ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks CHNUVO527 CHP-002 3 B FSC QTR 73ST9X106 MAKEUP TO CHARGING VCT BYPASS 608 GA A STC OTR 73ST9X106 ISOLATION VALVE 3 AO C FTC OTR 73ST-9XI06 VP 2YR 73ST9XI06 CHBHV0530 CHP-002 20 B FSO OTR 73ST9X106 VRR-12 Note 5 REFUEUNG WATER TANK OUTLET C15 GA A FSC OTR 73ST-9XI06 VRR-12 0TR FS FOR PRARA ISOLATION VALVE 2 MO OC CHAHV0531 CHP-002 20 B FSO 0TR 73ST-9X106 VRR-12 Note 5 REFUEUNG WATER TANK OUTLET C14 GA A FSC 0TR 73ST9XI06 VRR-12 0TR FS FOR PRAIRA ISOLATION VALVE 2 MD OC CHEHV0532 CHP-002 3 B FSO CSD 73ST9XI22 CSJ-07 ISOLATION FOR REFUELING WATER TANK E16 GL A FSC CSD 73ST9XI22 CSJ-07 TO BORIC ACID MAKEUP PUMPS 2 AO C STO CSD 73ST-9XI22 CSJ-07 STC CSD 73ST-9X122 CSJ-07 FTO CSD 735T9XI22 CSJ-07 VP 2YR 73ST-9XI22 CHEHV0536 CHP-002 3 B FSO 1CY 73ST-9X122 VRR-12 Note 5 REFUELING WATER TANK TO CHARGING A14 GL A PUMP SUCTION ISOLATION VALVE 3 MD O CHAUVO560 CHP-003 3 A FSC 0TR 73ST-9XI06 REACTOR DRAIN TANK OUTLET INBOARD B15 GL A STC QTR 73ST-9X106 CIV (PEN. 44) 2 AO C FTC 0TR 73ST-9XI06 AJ CLR 73ST-9CL01 VP 2YR 73ST-9XI06 CHBUVO561 CHP-003 3 A FSC 0TR 73ST-9XI06 REACTOR DRAIN TANK INBOARD CIV A15 GL A STC 0TR 73ST4X106 (PEN. 44) 2 AO C FTC CTR 735T9XI06 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI06 CHAUVO580 CHP-003 1.5 A FSC aTR 73ST-9XI06 REACTOR MAKEUP WATER TO RDT F14 GA A STC 0TR 73ST9X106 OUTBOARD CIV (PEN. 45) 2 AO C FTC 0TR 73ST-9XI06 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI06 CHAUVO715 CHP-003 0.5 A FSC OTR 73ST-9XI06 PASS TO RDT CIV (PEN. 45) E13 GL A STC QTR 73ST-9X106 2 SO C FTC CTR 73ST-9XI06 AJ CLR 73ST-9CL01 VP 2YR 73ST-9XI06 CHAV755 CHP-002 3 B FSO 0TR 73ST-9XI31 CHARGING PUMP CHA-PO1 ALTERNATE C05 DI A FSC 0TR 73ST-9XI31 SUCTION MANUAL ISOLATION VALVE 2 MA OC CHBV756 CHP-002 3 B FSO 0TR 73ST-9X131 CHARGING PUMP CHB-P01 ALTERNATE DO5 DI A FSC 0TR 73ST-9X131 SUCTION MANUAL ISOLATION VALVE 2 MA OC CHEV757 CHP-002 3 B FSO 0TR 73ST-9X131 CHARGING PUMP CHE-PO1 ALTERNATE F05 DI A FSC 0TR 73ST-9X131 SUCTION MANUAL ISOLATION VALVE 2 MA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 11 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 1 COMPONENT TABLES 14 Drawing Size (In) Cat. cSi Valve ID Coord/Sht# Type A/P ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks CHNV835 CHP-001 1.5 AC FSC CSD 73ST-9XI26 CSJ-1I Notes 1, 2, 3 RCP SEAL INJECTION SUPPLY LINE G03 CK A AJ CLR 73ST9CL01 CHECK VALVE 2 SA C CHEV854 CHP-001 0.75 A AJ CLR 73ST-9CL01 CHARGING LINE CHEMICAL ADDITION EIS GL P ISOLATION VALVE (PEN. 41) 2 MA C CHBUVO924 CHP-001 0.5 A FSC QTR 73ST-9X106 LETDOWN TO PASS CIV (PEN. 40) E14 GA A STC QTR 73ST-9X106 2 SO C FTC OTR 73ST-9XI06 AJ CLR 73ST-9CL01 VP 2YR 73ST-9XI06 CPAUVO002B CPP-001 42 A FSC CSD 73ST-9X123 VRR-12 Note 5 CONTAINMENT REFUELING PURGE E03 BF A STC 18M 73ST-9X123 VRR-12 18M STC REO'D FOR TS 3.3.5.4 EXHAUST INBOARD CIV (PEN. 57) 2 MO C AJ CLR 73ST-9CL10 DURING CSD (see CSJ-10).

CPAUVO002A CPP-001 42 A FSC CSD 73ST-9XI23 VRR-12 Note 5 CONTAINMENT REFUELING PURGE D06 BF A STC 18M 73ST-9X123 VRR-12 18M STC REQ'D FOR TS 3.3.5.4 SUPPLY OUTBOARD CIV (PEN. 56) 2 MO C Al CLR 73ST.9CL06 DURING CSD (see CSJ-10).

CPBUVO003A CPP-001 42 A FSC CSD 73ST-9X123 VRR-12 Note 5 CONTAINMENT REFUELING PURGE D05 BF A STC 18M 73ST-9X123 VRR-12 18M STC REQ'D FOR TS 3.3.5A SUPPLY INBOARD CIV (PEN. 56) 2 MO C AJ CLR 73ST-9CL06 DURING CSD (see CSJ-10).

CPBUVO003B CPP-001 42 A FSC CSD 73ST-9X123 VRR-12 Note 5 CONTAINMENT REFUELING PURGE E02 BF A STC 18M 73ST-9X123 VRR-12 18M STC REO'D FOR TS 3.3.5A EXHAUST OUTBOARD CIV (PEN. 57) 2 MO C AJ CLR 73ST-9CL10 DURING CSD (see CSJ-10).

CPAUVO004A CPP-001 8 A FSC QTR 73ST-9XI15 CONTAINMENT POWER ACCESS PURGE D06 BF A STC OTR 73ST-9X115 SUPPLY OUTBOARD CIV (PEN. 78) 2 AO C FTC QTR 73ST-9Xlt5 AJ CLR 73ST-9CL07 VP 2YR 735T-9XI15 CPAUVO004B CPP-001 8 A FSC QTR 73ST-9X115 CONTAINMENT POWER ACCESS PURGE D03 BF A STC OTR 73ST-9X115 EXHAUST INBOARD CIV (PEN. 79) 2 AO C FTC QTR 73ST-9X115 AJ CLR 73ST-9CL07 VP 2YR 73ST-9X115 CPBUVO005B CPP-001 8 A FSC QTR 73ST-9X115 CONTAINMENT POWER ACCESS PURGE C02 BF A STC OTR 73ST9X115 EXHAUST OUTBOARD CIV (PEN. 79) 2 AO C FTC QTR 73ST-9X115 AJ CLR 73ST-9CL07 VP 2YR 73ST-9X115 CPBUVOOO5A CPP-001 8 A FSC OTR 73ST-9X115 CONTAINMENT POWER ACCESS PURGE D05 BF A STC OTR 73ST9X115 SUPPLY INBOARD CIV (PEN. 78) 2 AO C FTC OTR 73ST-9X115 AJ CLR 73ST-9CL07 VP 2YR 73ST-9X115 CTAHVOOOI CTP-001 10 B FSO QTR 73ST-9XI05 VRR.12 The tests in the open direction ere AFN-P01 SUCTION ISOLATION VALVE E02 BF A FSC QTR 735T9X105 VRR-12 for an augmented function FROM CONDENSATE STORAGE TANK 3 MO C Note 5 QTR FS FOR PRARA.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 12 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 1s4 COMPONENT TABLES 1 Drawing Size (In) Cal. CSJ/

Valve ID Coord/Sht# Type A/P ROJ/

Description Code Class Act. S.P. Test Freq Procedure VRR Remarks CTAHV0004 CTP-001 10 8 FSO TR 73ST9XI05 VRR-12 The tests in the open direction are AFN-P01 SUCTION ISOLATION VALVE E03 BF A FSC TR 73ST-9XI05 VRR-12 for an augmented function FROM CONDENSATE STORAGE TANK 3 MO C Note 5 QTR FS FOR PRAIRA CTNPSV0008 CTP-001 10 C SV 10Y 73ST-9ZZ20 PressNacuum Relief COMBINED VACUUM AND PRESSURE H05 SV A RELIEF FOR THE CONDENSATE STORAGE 3 SA OC TANK CTAV016 CTP-001 3 C FSO TR 73ST-9CT01 Notes 1.2,3. Augmented test CONDENSATE TRANSFER PUMP C04 CK A requirement DISCHARGE CHECK VALVE 3 SA 0 CTAV018 CTP-001 3 B FSO TR 73ST-9CT01 Augmented testing CONDENSATE TRANSFER TO SPENT FUEL C03 GA P FSC TR 73ST-9CT01 POOL ISOLATION 3 MA C CTBV019 CTP-001 3 B FSO TR 73ST-9CT01 Augmented testing CONDENSATE TRANSFER TO SPENT FUEL 803 GA P FSC TR 73ST-9CT01 POOL ISOLATION 3 MA C CTBV020 CTP-001 3 C FSO TR 73ST-9CT01 Notes 1, 2. 3. Augmented test CONDENSATE TRANSFER PUMP B04 CK A requirement DISCHARGE CHECK VALVE 3 SA 0 CTNPSVO023 CTP-001 10 C SV 1Y 73ST-9ZZ20 PresstVacuum Relief COMBINED VACUUM AND PRESSURE H05 SV A RELIEF FOR THE CONDENSATE STORAGE 3 SA OC TANK CTAV037 CTP-001 3 C FSO TR 73ST-9CT01 Notes 1, 2. 3. Augmented test CONDENSATE TRANSFER TO SPENT FUEL C04 CK A requirement POOL CHECK VALVE 3 SA 0 CTBV038 CTP-001 3 C FSO TR 73ST-9CT01 Notes 1. 2, 3. Augmented test CONDENSATE TRANSFER TO SPENT FUEL B04 CK A requirement POOL CHECK VALVE 3 SA 0 DFAV012 DFP-001 2 C FSO TR 73ST-9DF01 Notes 1. 2 3 FUEL OIL TRANSFER PUMP DISCHARGE D06 CK A CHECK VALVE 3 SA 0 DFBV019 DFP-001 2 C FSO TR 73ST-9DF01 Notes 1. 2. 3 FUEL OIL TRANSFER PUMP DISCHARGE D02 CK A CHECK VALVE 3 SA 0 DFAV041 DFP-001 I B FSO TR 73ST-9XI31 DIESEL FUEL OIL FILTER DP GAUGE H07 GL A FSC 0TR 73ST-9XI31 MANUAL ISOLATION VALVE 3 MA C DFAV042 DFP-001 1 B FSO QTR 73ST-9X131 DIESEL FUEL OIL FILTER DP GAUGE G07 GL A FSC 0TR 73ST-9XI31 MANUAL ISOLATION VALVE 3 MA C DFBV051 DFP-001 1 B FSO 0TR 73ST-9XI31 DIESEL FUEL OIL FILTER DP GAUGE H03 GL A FSC 0TR 73ST-9XI31 MANUAL ISOLATION VALVE 3 MA C DFBV052 DFP-001 I B FSO 0TR 73ST9XI31 DIESEL FUEL OIL FILTER DP GAUGE G03 GL A FSC QTR 73ST-9XI31 MANUAL ISOLATION VALVE 3 MA C

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 13 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 14Rvlslon COMPONENT TABLES .

Drawing Size (in) Cat. CSJI Valve ID CoordlSht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks DGAPSVO005 DGP-001 1 C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY HO( SH9 SV A RELIEF VALVE 3 SA OC DGBPSVO006 DGP-001 1 C SV 10Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY DOESH9 SV A RELIEF VALVE 3 SA OC DGAPSVO007 DGP-001 1 C SV 1Y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY Foe SH9 SV A RELIEF VALVE 3 SA OC DGBPSVO008 DGP-001 I C SV y 73ST-9ZZ20 EDG START AIR RECEIVER SAFETY C0 SH9 SV A RELIEF VALVE 3 SA OC DGAV066 DGP-001 1 C FSC QTR 73ST-9XI17 Notes 1 2 3. Required In all EDG STARTING AIR DRYER OUTLET Foe SH9 CK A modes Icluding shutdown.

CHECK VALVE 3 SA C DGAV067 DGP-001 1 C FSC TR 73ST-9XI17 Notes 1, 2, 3. Required In all EDG STARTING AIR DRYER OUTLET GO SH9 CK A modes including shutdown.

CHECK VALVE 3 SA C DGBV068 DGP-001 1 C FSC TR 735T-9X118 Notes 1, 2. 3. Required in all EDG STARTING AIR DRYER OUTLET DOESH9 CK A modes Including shutdown.

CHECK VALVE 3 SA C DGBV069 DGP-001 1 C FSC TR 73ST-9XI18 Notes 1. 2, 3. Required in all EDG STARTING AIR DRYER OUTLET COESH9 CK A modes Including shutdown.

CHECK VALVE 3 SA C DGAV317 DGP-001 6 C FSO TR 40ST-9DGO1 VRR-01 Notes 1 2 3 EDG ENGINE-DRIVEN JACKET WATER Foe SH4 CK A CIRC PUMP DISCHARGE CHECK VALVE 3 SA OC DGAV318 DGP-001 3 C FSO TR 40ST-9DG01 VRR-01 Notes 1. 2, 3 EDG MOTOR-DRIVEN JACKET WATER CIRC DO( SH4 CK A PUMP DISCHARGE CHECK VALVE 3 SA OC DGAV364 DGP-001 3 C FSO TR 40ST-9DG01 VRR-01 Notes 1. 2. 3 EDG PRE-LUBE PUMP AND HEATER COESH3 CK A CHECK VALVE 3 SA OC DGBV417 DGP-001 6 C FSO TR 40ST-9DG02 VRR-01 Notes 1, 2, 3 EDG ENGINE-DRIVEN JACKET WATER F02 SH4 CK A CIRC PUMP DISCHARGE CHECK VALVE 3 SA OC DGBV418 DGP-001 3 C FSO QTR 405T-9DG02 VRR-01 Notes 1, 2. 3 EDG MOTOR-DRIVEN JACKET WATER CIRC DO. SH4 CK A PUMP DISCHARGE CHECK VALVE 3 SA OC DGBV464 DGP001 3 C FSO TR 40ST-9DG02 VRR-01 Notes 1, 2 3 EDG PRE-LUBE PUMP AND HEATER CO. SH3 CK A CHECK VALVE 3 SA OC DWEV061 DWP-002 2 A A) CLR 735T9CLO1 DW SUPPLY HEADER OUTSIDE C03 GL P CONTAINMENT ISOLATION VALVE (PEN. 6) 2 MA C DWEV062 DWP-002 2 A AJ CLR 73ST-9CLO1 DW SUPPLY HEADER INSIDE C02 GL P CONTAINMENT ISOLATION VALVE (PEN. 6) 2 MA C

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 14 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rv14 COMPONENT TABLES 14 Drawing Size (In) Cat. CSJ/

Valve ID Coord/Sht# Type A/P ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks ECAV038 ECP-001 1.5 C CMI CMP 73ST-9ZZ25 VRR.13 Notes 1,3,4 MAKEUP LINE CHECK VALVE FROM DW D07 CK A 3 SA C ECAV041 ECP-001 1.5 C CMI CMP 73ST-9ZZ25 VRR-13 Notes 1.3,4 MAKEUP LINE CHECK VALVE FROM CT C07 CK A 3 SA C ECAV043 ECP-001 1 C CMI CMP 73ST-9ZZ25 VRR-13 Notes 1,3.4 NITROGEN SUPPLY CHECK VALVE TO EC C07 CK A EXPANSION TANK 3 SA C ECBV060 ECP-001 1.5 C CMI CMP 73ST-9ZZ25 VRR-13 Notes 1, 3. 4 MAKEUP LINE CHECK VALVE FROM DW D03 CK A 3 SA C ECBV064 ECP-001 1 C CMI CMP 73ST-9ZZ25 VRR-13 Notes 1, 3,4 NITROGEN SUPPLY CHECK VALVE TO EC C03 CK A EXPANSION TANK 3 SA C ECBV072 ECP-001 1.5 C CMI CMP 73ST-9ZZ25 VRR-13 Notes 1.3,4 MAKEUP LINE CHECK VALVE FROM CT D03 CK A 3 SA C ECAPSVO075 ECP-001 1.5 C SV 10y 73ST-9ZZ20 EC EXPANSION TANK RELIEF VALVE D06 SV A 3 SA OC ECBPSVO076 ECP-001 1.5 C SV 10Y 73ST-9ZZ20 EC EXPANSION TANK RELIEF VALVE D03 SV A 3 SA OC ECAPSVO095 ECP-001 1 C SV 10Y 73ST-9ZZ20 ESF SWITCHGEAR ROOM ESSENTIAL ACU E05 SV A RELIEF VALVE 3 SA OC ECBPSVO096 ECP-001 I C SV 10Y 73ST-9ZZ20 ESF SWITCHGEAR ROOM ESSENTIAL ACU E02 SV A RELIEF VALVE 3 SA OC ECAPSVO097 ECP-01 1 C SV 10Y 73ST-9ZZ20 CONTROL ROOM ESSENTIAL ACU RELIEF E07 SV A VALVE 3 SA OC ECBPSVO098 ECP-001 I C SV icY 73ST-9ZZ20 CONTROL ROOM ESSENTIAL ACU RELIEF E04 SV A VALVE 3 SA OC ECAPSVO099 ECP-001 1 C SV y 73ST-9ZZ20 WEST ELECTRICAL PENETRATION ROOM F07 SV A ESSENTIAL ACU RELIEF VALVE 3 SA OC ECBPSV0100 ECP-001 1 C SV 1ay 73ST-9ZZ20 EAST ELECTRICAL PENETRATION ROOM F03 SV A ESSENTIALACU RELIEF VALVE 3 SA OC ECAPSV0101 ECP-001 I C SV 10y 73ST-9ZZ20 EW PUMP ROOM ESSENTIAL ACU RELIEF F06 SV A VALVE 3 SA OC ECBPSVOI02 ECP001 I C SV 10Y 73ST-9ZZ20 EW PUMP ROOM ESSENTIAL ACU RELIEF F02 SV A VALVE 3 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 15 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 R COMPONENT TABLES 14 Drawing Size (in) CaL. CSJI Valve ID Coord/Sht# Type AJP ROJ/

Description Code Class Act. S.P. Test Freq Procedure VRR Remarks ECAPSVO103 ECP-001 1 C SV laY 73ST-9ZZ20 CS PUMP ROOM ESSENTIAL ACU RELIEF H07 SV A VALVE 3 SA OC ECBPSVO104 ECP-001 I C SV 10Y 73ST-9ZZ20 CS PUMP ROOM ESSENTIAL ACU RELIEF H04 SV A VALVE 3 SA OC ECAPSVOI05 ECP-001 I C SV 10Y 73ST-9ZZ20 HPSI PUMP ROOM ESSENTIAL ACU RELIEF H06 SV A VALVE 3 SA OC ECBPSVOI06 ECP-001 1 C SV 10Y 73ST-9ZZ20 HPSI PUMP ROOM ESSENTIAL ACU RELIEF H03 SV A VALVE 3 SA OC ECAPSVO107 ECP-001 I C SV laY 73ST-9ZZ20 LPSI PUMP ROOM ESSENTIAL ACU RELIEF H05 SV A VALVE 3 SA OC ECBPSVO108 ECP-001 I C SV laY 73ST-9ZZ20 LPSI PUMP ROOM ESSENTIAL ACU RELIEF H02 SV A VALVE 3 SA OC ECBPSVOI9 ECP-001 1 C SV 10Y 73ST-9ZZ20 AFW PUMP ROOM ESSENTIAL ACU RELIEF F04 SV A VALVE 3 SA OC ECAPSVO117 ECP-001 1 C SV 10Y 73ST-9ZZ20 AFW PUMP ROOM ESSENTIAL ACU RELIEF F05 SV A VALVE 3 SA OC ECBPSVOI20 ECP-001 1 C SV 10Y 73ST-9ZZ20 DC EQUIPMENT ROOM ESSENTIAL ACU E03 SV A RELIEF VALVE 3 SA OC ECAPSVOI21 ECP-001 I C SV 10Y 73ST-9ZZ20 DC EQUIPMENT ROOM ESSENTIAL ACU E06 SV A RELIEF VALVE 3 SA OC EWAPSVO47 EWP-001 1 C SV 10Y 73ST-9ZZ20 SHUTDOWN HEAT EXCHANGER RELIEF B07 SV A VALVE 3 SA OC EWBPSVO048 EWP-001 I C SV 1Y 73ST-9ZZ20 SHUTDOWN HEAT EXCHANGER B03 SV A PRESSURE RELIEF VALVE 3 SA OC EWAPSVO061 EWP-001 1 C SV 10Y 73ST-9ZZ20 ESSENTIAL CHILLER OUTLET LINE RELIEF D07 SV A VALVE 3 SA OC EWBPSVO062 EWP-001 1 C SV 10Y 73ST-9ZZ20 ESSENTIAL CHILLER OUTLET LINE RELIEF E03 SV A VALVE 3 SA OC EWAUVO065 EWP-001 12 B FSC ICY 73ST-9X123 VRR-12 Note 5 EW TO NUCLEAR COOLING WATER C08 BF A STC 18M 735T-9X123 VRR-12 IBM ST FOR TS 3.3.5A RETURN ISOLATION VALVE 3 MO C EWAHCV0067 EWP-001 10 B FSO QTR 73ST-9XI31 Passive closed valve, exercising Is FUEL POOL HEAT EXCHANGER RETURN E08 BF p FSC QTR 73ST-9XI31 augmented testing because of ISOLATION VALVE 3 MA C Important (but non-safety) function to open

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 16 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rision COMPONENT TABLES Drawing Size (in) Cat CSJI Valve ID Coord/Sht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks EWBHCV0068 EWP-001 10 B FSO OTR 73ST-9X131 Passive closed valve, exercising Is FUEL POOL HEAT EXCHANGER RETURN E04 BF P FSC QTR 73ST-9XI31 augmented testing because of ISOLATION VALVE 3 MA C Important (but non-safety) function to open EWAPSV079 EWP-001 1 C SV 10Y 73ST-9ZZ20 ESSENTIAL CHILLED WATER HEAT F07 SV A EXCHANGER A PRESSURE REUEF VALVE 3 SA OC EWBPSV0080 EWP-001 I C SV 1Y 73ST-9ZZ20 ESSENTIAL CHILLED WATER HEAT F03 SV A EXCHANGER B PRESSURE RELIEF VALVE 3 SA OC EWAPSVO103 EWP-001 2 C SV Y 73ST-9ZZ20 ESSENTIAL COOLING WATER SURGE TANK H06 SV A A PRESSURE RELIEF VALVE 3 SA OC EWBPSVOI04 EWPoo1 2 C SV 10Y 73ST-9ZZ20 ESSENTIAL COOLING WATER SURGE H02 SV A TANK B PRESSURE RELIEF VALVE 3 SA OC EWAPSVOI05 EWP-001 2 C SV 10Y 73ST-9ZZ20 EW SURGE TANK VACUUM RELIEF VALVE H06 SV A 3 SA 0C EWBPSVOI06 EWP-001 2 C SV laY 73ST-9ZZ20 EW SURGE TANK VACUUM RELIEF VALVE H02 SV A 3 SA 0C EWAHCV0133 EWP-001 10 B FSO QTR 73ST-9XI31 Passive closed valve, exercising Is FUEL POOL HEAT EXCHANGER SUPPLY D06 BF P FSC QTR 73ST-9XI31 augmented testing because of ISOLATION VALVE 3 MA C Important (but non-safety) function to open EWBHCV0134 EWP-001 10 B FSO QTR 73ST-9X131 Passive closed valve, exercising Is FUEL POOL HEAT EXCHANGER SUPPLY D02 BF P FSC QTR 73ST-9X131 augmented testing because of ISOLATION VALVE 3 MA C Important (but non-safety) function to open EWAUVO145 EWP-001 12 B FSC ICY 73ST-9X123 VRR-12 Note 5 EW TO NUCLEAR COOLING WATER C04 BF A STC 18M 73ST-X123 VRR-12 18M ST FOR TS 3.3.5.4 SUPPLY ISOLATION VALVE 3 MO C EWAV234 EWP-001 2 B FSO QTR 73ST-9Xt31 EW SURGE TANK INSTRUMENTATION G07 GL A FSC QTR 73ST-9X131 EXCESS FLOW CHECK VALVE MANUAL 3 MA C ISOLATION VALVE EWAV235 EWP-001 2 B FSO QTR 3ST-9X131 EW SURGE TANK INSTRUMENTATION F07 GL A FSC QTR 3ST-9)031 EXCESS FLOW CHECK VALVE MANUAL 3 MA C ISOLATION VALVE EWBV238 EWP-001 2 B FSO OTR 3ST-9X131 EW SURGE TANK INSTRUMENTATION G03 GL A FSC TR 3ST-9X131 EXCESS FLOW CHECK VALVE MANUAL 3 MA C ISOLATION VALVE EWBV239 EWP-001 2 B FSO OTR 3ST-9X131 EW SURGE TANK INSTRUMENTATION F03 GL A FSC QTR 3ST9X131 EXCESS FLOW CHECK VALVE MANUAL 3 MA C ISOLATION VALVE

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 17 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 I v14 COMPONENT TABLES 14 Drawing Size (in) Cat. CSJI Valve ID CoordlSht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks FPEV089 FPP-006 6 A A) CLR 73ST-9CLO1 FIRE WATER OUTSIDE CONTAINMENT E08 GL P ISOLATION VALVE (PEN. 7) 2 VA C FPEV090 FPP-006 6 AC Al CLR 73ST-9CLO1 Notes 1 2. 3 FIRE WATER INSIDE CONTAINMENT F09 CK P ISOLATION VALVE (PEN. 7) 2 SA C GAAUVO001 GAP-001 I A FSC QTR 735T-9XI07 HIGH PRESSURE NITROGEN SUPPLY E07 GA A STC QTR 73ST-9XI07 HEADER OUTSIDE CIV (PEN. 30) 2 SO C FTC QTR 73ST-9XI07 Al CLR 735T-9CLOI VP 2YR 73ST-9X107 GAAUVO002 GAP-001 1 A FSC QTR 735T-9X107 LOW PRESSURE NITROGEN SUPPLY F03 GA A STC QTR 73ST-9X107 HEADER OUTSIDE CIV (PEN. 29) 2 SO C FTC QTR 735T-9X107 AJ CLR 735T-9CLOI VP 2YR 73ST-9XI07 GAEV01 1 GAP-001 I AC FSC CSD 735T-9X128 Notes 1.2,3. Considered active HIGH PRESSURE NITROGEN SUPPLY D06 CK P AJ CLR 735T-9CLO1 during first IST Interval, re-INSIDE CONTAINMENT ISOLATION CHECK 2 SA C evaluated as passive during 10-VALVE (PEN. 30) year update, further reviews being performed before dis-continuing exercise testing.

GAEV015 GAP-001 I AC FSC CSD 735T-9X128 CSJ-23 Notes 1. 2 3 LOW PRESSURE NITROGEN SUPPLY E02 CK A AJ CLR 73ST-9CLO1 INSIDE CONTAINMENT ISOLATION CHECK 2 SA C VALVE (PEN. 29)

GRAUV0001 GRP-001 I A FSC QTR 735T-9Xi07 VRR-12 Note 5 CONTAINMENT ISOLATION BETWEEN RDT H07 GL A STC 18M 735T-9X107 VRR-12 QTR FS FOR PRA'RA AND GAS SURGE HEADER (PEN 52) 2 MO C AJ CLR 735T-9CLO1 18M ST FOR TS 3.3.5.4 GRBUVO002 GRP-001 I A FSC OTR 735T-9XI07 CONTAINMENT ISOLATION (SOV) BETWEEN H07 GL A STC QTR 735T9Xi07 RDT AND GAS SURGE HEADER (PEN 52) 2 SO C FTC QTR 735T-9XI07 AJ CLR 735T-9CLO1 VP 2YR 735T-9XI07 HCBUVO044 HCP-001 I A FSC QTR 735T-9XI40 CONTAINMENT ATMOSPHERE RADIATION E03 GA A STC QTR 73ST-9X140 MONITOR INLET CIV (PEN 25A) 2 SO C FTC QTR 73ST-9XI40 AJ CLR 73ST-9CLO1 VP 2YR 735T-9XI40 HCAUVO045 HCP-001 I A FSC QTR 735T-9XI40 CONTAINMENT ATMOSPHERE RADIATION E02 GA A STC QTR 735T-9X140 MONITOR INLET CIV (PEN. 25A) 2 SO C FTC QTR 735T-9XI40 Al CLR 735T-9CL01 VP 2YR 735T9XI40 HCAUVO046 HCP-001 1 A FSC OTR 735T-9Xi40 CONTAINMENT ATMOSPHERE RADIATION D02 GA A STC QTR 735T-9X140 MONITOR OUTLET CIV (PEN. 258) 2 SO C FTC QTR 735T-9X140 AJ CLR 73ST-9CLO1 VP 2YR 735T-9X140

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 18 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XIOl Revi ion COMPONENT TABLES Drawing Size (In) Cat. CSJI Valve ID CoordlSht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks HCBUV047 HCP-001 I A FSC QTR 73ST-9X140 CONTAINMENT ATMOSPHERE RADIATION D03 GA A STC QTR 735T4X140 MONITOR OUTLET CIV (PEN. 25B) 2 SO C FTC QTR 73ST-9XI40 A) CLR 73ST-9CLO1 VP 2YR 73ST-9XI40 HCAHV0074 HCP-001 0.75 B VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE TRANSMITTER D08 GL P CIV (PEN. 54A) 2 so O HCBHV0075 HCP-001 0.75 B VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE TRANSMITTER C02 GL P CIV (PEN. 55A) 2 so O HCCHV0076 HCP-001 0.75 B VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE TRANSMITTER C08 GL P CIV (PEN. 32A) 2 so O HCDHV0077 HCP-001 0.75 B VP 2YR 73ST-9XI40 CONTAINMENT PRESSURE TRANSMITTER C02 GL P CIV (PEN. 62A) 2 SO 0 HPAUV0001 HPP-001 2 A FSO ICY 73ST-9XI08 VRR.12 Note 5 H2 CONTROL SYSTEM SUPPLY FROM E15 GL A FSC ICY 73ST-9XI08 VRR-12 18M ST FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 35) 2 MO OC STO 18M 73ST-9XI08 VRR-12 STC 18M 73ST9X108 VRR-12 Al CLR 73ST-9CLO1 HPBUV002 HPP-001 2 A FSO iCY 73ST-9X108 VRR-12 Note 5 H2 CONTROL SYSTEM SUPPLY FROM C15 GL A FSC ICY 73ST-9X108 VRR-12 18M ST FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 36) 2 MO OC STO 18M 73ST-9X108 VRR-12 STC 18M 735T-9X108 VRR-12 AJ CLR 73ST-9CLO1 HPAV002 HPP-001 2 AC FSO QTR 735T-9XI09 Notes 1, 2. 3 H2 CONTROL SYSTEM RETURN LINE TO FIS CK A FSC CSD 73ST-9XI28 CSJ-24 CONTAINMENT INBOARD CIV (PEN. 38) 2 SA OC AJ CLR 73ST-9CLO1 HPAUV003 HPP-001 2 A FSO ICY 73ST-9XI08 VRR-12 Note 5 H2 CONTROL SYSTEM RETURN TO E14 GL A FSC ICY 735T-9XI08 VRR-12 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 35) 2 MO OC STO 18M 73ST-9X108 VRR-12 STC 18M 73ST-9X108 VRR-12 AJ CLR 73ST-9CLO1 HPBUV004 HPP-001 2 A FSO ICY 73ST-9X108 VRR-12 Note 5 H2 CONTROL SYSTEM RETURN TO C14 GL A FSC ICY 73ST-9X108 VRR-12 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 36) 2 MO OC STO 18M 735T-9XI08 VRR-12 STC 18M 735T9X108 VRR-12 Al CLR 73ST-9CLO1 HPBVO4 HPP-001 2 AC FSO QTR 735T-9X10 Notes 1. 2. 3 H2 CONTROL SYSTEM RETURN LINE TO C15 CK A FSC CSD 73ST-9XI28 CSJ-24 CONTAINMENT INBOARD CIV (PEN. 39) 2 SA OC Al CLR 73ST.9CLOI HPAUV0005 HPP-001 2 A FSO ICY 73ST-9XI08 VRR-12 Note 5 H2 CONTROL SYSTEM RETURN TO E14 GL A FSC ICY 73ST-9X108 VRR-12 18M ST FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN 33) 2 MO OC STO 18M 73ST-9X108 VRR-12 STC 18M 735T-9X108 VRR.12 AJ CLR 73ST.9CLO1

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 19 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rv14 COMPONENT TABLES 14 Drawing Size (in) CaL CSJ Valve ID CoordlSht# Type AtP ROJI DescrIptIon Code Class Act. S.P. Test Freq Procedure VRR Remarks HPBUVO006 HPP-001 2 A FSO ICY 73ST-9XI08 VRR-12 Note 5 H2 CONTROL SYSTEM RETURN TO C14 GL A FSC ICY 73ST-9XI08 VRR-12 18M ST FORTS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 39) 2 MO OC STO 18M 73ST-9XI08 VRR-12 STC 18M 73ST-X108 VRR-12 A) CLR 73ST-9CLOI HPAHV0007B HPP-001 I A FSO QTR 73ST-9XI08 POST-LOCA H2 MONITOR OUTLET CIV G14 GL A FSC QTR 73ST-9XI08 (PEN. 38) 2 SO OC STO OTR 73ST-9XI08 STC QTR 73ST4X108 FTC OTR 73ST-9XI08 AJ CLR 73ST-9CLI01 VP 2YR 73ST-9XI08 HPAHV0007A HPP-001 1 A FSO 0TR 73ST-9X108 POST-LOCA H2 MONITOR INLET CIV (PEN. F14 GL A FSC qTR 73ST-9XI08

35) 2 SO OC STO 0TR 73ST-9XI08 STC 0TR 73ST-9X108 FTC 0TR 73ST-9XI08 AJ CLR 73ST-9CLOI VP 2YR 73ST-9XI08 HPBHV0008A HPP-001 1 A FSO QTR 73ST-9XI08 POST-LOCA H2 MONITOR INLET CIV (PEN. C13 GL A FSC qTR 73ST-9XI08

36) . 2 SO OC STO QTR 73ST-9XI08 STC QTR 73ST-9X108 FTC QTR 73ST-9XI08 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI08 HPBHV0008B HPP-001 I A FSO QTR 73ST-9XI08 POST-LOCA H2 MONITOR OUTLET CIV B14 GL A FSC qTR 73ST-9XI08 (PEN. 39) 2 SO OC STO 0TR 73ST-9XI08 STC 0TR 73ST-9X108 FTC 0TR 73ST-9XI08 Al CLR 73ST-9CLO1 VP 2YR 73ST-9XI08 HPAUVO023 HPP-001 0.5 A FSC 0TR 73ST-9XI08 Valve size Is 1- in Units 2 and 3.

CONTAINMENT H2 MONITORING SYSTEM G14 GL A STC 0TR 73ST-9X108 RETURN FROM PASS OUTBOARD CIV 2 SO C FTC qTR 73ST-9XI08 (PEN. 38) A) CLR 73ST-9CLO1 VP 2YR 73ST-9XI08 HPAUVO024 HPP-001 0.5 A FSC 0TR 73ST-9XI08 Valve sze Is in Units 2 and 3.

CONTAINMENT H2 MONITORING SYSTEM F12 GL A STC qTR 73ST4X108 TO PASS ISOLATION VALVE 2 SO C FTC 0TR 73ST-9XI08 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI08 IAAUV0002 IAP-003 2 A FSC CSD 73ST-9XI23 CSJ-13 INSTRUMENTAIRSUPPLYOUTSIDE G07 GA A STC CSD 73ST-9X123 CSJ-13 CONTAINMENT ISOLATION VALVE (PEN. 31) 2 SO C FTC CSD 73ST-9XI23 CSJ-13 AJ CLR 73ST-9CLI01 VP 2YR 73ST-9XI23 IAEV021 IAP-003 2 AC FSC CSD 73ST-9XI28 CSJ-13 Notes 1, 2, 3 INSTRUMENT AIR SUPPLY INSIDE G05 CK A AJ CLR 73ST-9CL01 CONTAINMENT ISOLATION VALVE (PEN. 31) 2 SA C

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 20 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES T 1 Drawing Size (in) Cat. CSJ/

Vaive ID Coord/Sht# Type AIP ROJI Description Code Class AcL S.P. Test Freq Procedure VRR Remarks IAEV072 AP-002 3 A At CLR 73ST-9CLOI BREATHING AIR CONTAINMENT ISOLATION G09 GL P VALVE (PEN. 59) 2 MA C IAEV073 IAP-002 3 AC AJ CLR 73ST-9CLO1 Notes 1, 2, 3 BREATHING AIR SUPPLY INSIDE H07 CK P CONTAINMENT ISOLATION VALVE (PEN. 59) 2 SA C NCEV118 NCP-003 10 AC FSC CSD 73ST-9X126 CSJ-30 Notes 1, 2, 3 NUCLEAR COOLING WATER SUPPLY TO E06 CK A A) CLR 73ST-9CLO1 RCP COOLER INBOARD CIV (PEN. 33) 2 SA C NCAHCV0244 NCP-002 10 B FSC OTR 73ST-9XI31 Augmented NUCLEAR COOLING WATER TO SPENT B04 BF A FUEL POOL HEAT EXCHANGER ISOLATION 3 MA C VALVE NCBHCV0245 NCP-002 10 B FSC TR 73ST-9XI31 Augmented NUCLEAR COOLING WATER TO SPENT B04 BF A FUEL POOL HEAT EXCHANGER ISOLATION 3 MA C VALVE NCAPSVO250 NCP-002 1 C SV 10Y 73ST-9ZZ20 Augmented FUEL POOL COOLING HEAT EXCHANGER E02 SV A RELIEF VALVE 3 SA OC NCBPSVO251 NCP402 I C SV 10Y 73ST-9ZZ20 Augmented FUEL POOL COOLING HEAT EXCHANGER D02 SV A RELIEF VALVE 3 SA OC NCAHCV0258 NCP-002 10 B FSC TR 73ST-9XI31 Augmented NUCLEAR COOLING WATER TO SPENT C04 BF A FUEL POOL HEAT EXCHANGER ISOLATION 3 MA C VALVE NCBHCV0259 NCP-002 10 B FSC TR 73ST-9X131 Augmented NUCLEAR COOUNG WATER TO SPENT B04 BF A FUEL POOL HEAT EXCHANGER ISOLATION 3 MA C VALVE NCBUVO401 NCP-003 10 A FSC ICY 73ST-9X123 VRR-12 Note 5 NUCLEAR COOLING WATER SUPPLY TO E07 BF A STC 18M 73ST9X123 VRR-12 IBM ST FOR TS 3.3.5.4 RCP COOLER OUTBOARD CIV (PEN. 33) 2 MO C AJ CLR 73ST-9CL01 NCAUVO402 NCP-003 10 A FSC ICY 73ST-9X123 VRR-12 Note 5 NUCLEAR COOLING WATER SUPPLY TO F07 BF A STC 18M 73ST9X123 VRR-12 18M ST FOR TS 3.3.5.4 RCP COOLER OUTBOARD CIV (PEN. 34) 2 MO C AJ CLR 73ST-9CL01 NCBUVO403 NCP-003 10 A FSC ICY 73ST-9X123 VRR-12 Note 5 NUCLEAR COOLING WATER SUPPLY TO F06 BF A STC 18M 73ST9X123 VRR-12 IBM ST FORTS 3.3.5A RCP COOLER INBOARD CIV (PEN. 34) 2 MO C AJ CLR 73ST-9CL01 NCEPSVO614 NCP-003 6 C SV iaY 73ST-9ZZ20 Augmented NC CONTAINMENT ISOLATION VALVE E05 SV A RELIEF VALVE 2 SA 0 NCEPSVO615 NCP-003 6 C SV I0Y 73ST-9ZZ20 Augmented NC CONTAINMENT ISOLATION VALVE E05 SV A RELIEF VALVE 2 SA 0 NCEPSVO617 NCP-003 0.75 AC AJ CLR 735T-9CLO1 NC CONTAINMENT PENETRATION RELIEF E07 SV A SV IY 73ST-9ZZ20 VALVE (PEN 34) 2 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 21 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Rv14 COMPONENT TABLES 1 4 Drawing Size (In) Cat CsJI Valve ID CoordlSht# Type AIP ROJI Description Code Class Act. SP. Test Freq Procedure VRR Remarks PCAV013 PCP-001 8 C FSO QTR 73ST9PCO1 Notes 1, 2, 3. Augmented.

SPENT FUEL POOL COOLING PUMP D15 CK A FSC TR 73ST-9PC01 DISCHARGE CHECK VALVE 3 SA OC PCBV017 PCP-001 8 C FSO TR 73ST-9PC01 Notes 1.2.3. Augmented.

SPENT FUEL POOL COOLING PUMP B15 CK A FSC QTR 73ST-9PC01 DISCHARGE CHECK VALVE 3 SA OC PCAPSVO035 PCP-401 I C SV oY 73ST-9ZZ20 Augmented SPENT FUEL POOL COOLING HEAT E13 SV A EXCHANGER PRESSURE RELIEF VALVE 3 SA OC PCBPSVO036 PCP-001 I C SV 10Y 73ST-9ZZ20 Augmented SPENT FUEL POOL COOLING HEAT B13 SV A EXCHANGER PRESSURE RELIEF VALVE 3 SA OC PCEV070 PCP-a01 4 A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION RETURN E10 GA P CONTAINMENT ISOLATION VALVE (PEN 51) 2 MA C PCEV071 PCP-401 4 A AJ CLR 73ST-9CLO1 REFUELING POOL PURIFICATION RETURN E09 GA P CONTAINMENT ISOLATION VALVE (PEN 51) 2 MA C PCEV075 PCP-01 4 A A) CLR 73ST-9CL01 REFUELING POOL PURIFICATION SUPPLY G06 GA P CONTAINMENT ISOLATION VALVE (PEN 50) 2 MA C PCEV076 PCP-a01 4 A AJ CLR 73ST-9CL01 REFUELING POOL PURIFICATION SUPPLY G05 GA P CONTAINMENT ISOLATION VALVE (PEN 50) 2 MA C PCNV215 CHP-002 3 B FSO QTR 73ST-9XI31 RWT TO SPENT FUEL POOL MANUAL All Dl A FSC QTR 73ST-9X131 ISOLATION VALVE 3 MA OC RCAHV0101 RCP-001 1 B FSO CSD 73ST-9XI24 CSJ-15 REACTOR VESSEL HEAD VENT VALVE G15 GL A FSC CSD 73ST-9XI24 CSJ-15 2 SO OC STO CSD 73ST9XI24 CSJ-15 STC CSD 735T-9X124 CSJ-15 FTC CSD 73ST-9XI24 CSJ-15 VP 2YR 73ST-9X124 RCBHV0102 RCP-001 1 B FSO CSD 73ST-9XI24 CSJ-15 REACTOR VESSEL HEAD VENT VALVE G15 GL A FSC CSD 73ST-9XI24 CSJ-15 2 SO OC STO CSD 73ST-9X124 CSJ-15 STC CSD 735T-X124 CSJ-15 FTC CSD 73ST-9XI24 CSJ-15 VP 2YR 73ST-9XI24 RCAHV0103 RCP-001 I B FSO CSD 73ST-9X124 CSJ-15 PRESSURIZER VENT VALVE G14 GL A FSC CSD 73ST-9XI24 CSJ-15 2 SO OC STO CSD 735T-9X124 CSJ-15 STC CSD 735T-9X124 CSJ-15 FTC CSD 73ST-9XI24 CSJ-15 VP 2YR 735T-9XI24

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 22 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 l v14 COMPONENT TABLES 14 Drawing Size (In) Cat CSJI Valve ID CoordlShtW Type A/P ROJ/

Description Code Class Act. S.P. Test Freq Procedure VRR Remarks RCBHV0105 RCP-001 1 B FSO CSD 73ST-9X124 CSJ-15 PRESSURIZERIREACTOR VESSEL HEAD G13 GL A FSC CSD 73ST-9XI24 CSJ-15 VENT VALVE TO REACTOR DRAIN TANK 2 SO OC STO CSD 73ST-9XI24 CSJ-15 STC CSD 73ST-9X124 CSJ-15 FTC CSD 73ST-9XI24 CSJ-15 VP 2YR 73ST-9XI24 RCAHV0106 RCP-001 1 B FSO CSD 73ST-9X124 CSJ-15 PRESSURIZERIREACTOR VESSEL HEAD G13 GL A FSC CSD 73ST-9XI24 CSJ-15 VENT VALVE TO CONTAINMENT 2 SO OC STO CSD 73ST-9XI24 CSJ-15 STC CSD 73ST-Xi24 CSJ-15 FTC CSD 73ST-9X124 CSJ-15 VP 2YR 73ST-9XI24 RCBHV0108 RCP-001 1 B FSO CSD 73ST-9X124 CSJ-15 PRESSURIZER VENT VALVE G13 GL A FSC CSD 73ST9X124 CSJ-15 1 SO OC STO CSD 73ST-9XI24 CSJ-15 STC CSD 73ST-9X124 CSJ-15 FTC CSD 73ST-9X124 CSJ-15 VP 2YR 73ST-9X124 RCBHV0109 RCP-001 1 B FSO CSD 73ST-9Xt24 CSJ-15 PRESSURIZER VENT VALVE G13 GL A FSC CSD 73ST-9X124 CSJ-15 1 SO OC STO CSD 73ST-9X124 CSJ-15 STC CSD 73ST-9X1241 CSJ-15 FTC CSD 73ST-9XI24 CSJ-15 VP 2YR 73ST-9XI24 RCEPSVO200 RCP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV A 040634) 1 SA OC RCEPSVO201 RCP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV A 040634) 1 SA OC RCEPSVO202 RCP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV A 040634) 1 SA OC RCEPSVO203 RCP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS PRESSURIZER SAFETY VALVE F12 SV A 040634) 1 SA OC RDAV020 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1 3. Disassembled on a CONTAINMENT SPRAY PUMP ROOM B14 SH2 CK A FSC STF 73ST-9ZZ25 VRR-04 sampling basis.

FLOOR DRAIN CHECK VALVE TO ESF SUMP 3 SA OC RDAV021 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1. 3. Disassembled on a HPSI PUMP ROOM FLOOR DRAIN CHECK BOE SH2 CK A FSC STF 73ST-9ZZ25 VRR-04 sampring basis.

VALVE TO ESF SUMP 3 SA OC RDAV022 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1 3. Disassembled on a LPSI PUMP ROOM FLOOR DRAIN CHECK B14 SH2 CK A FSC STF 73ST-9ZZ25 VRR-04 sampong basis.

VALVE TO ESF SUMP 3 SA OC RDAUVO023 RDP-001 3 A FSC OTR 73ST9X107 VRR-12 Note 5 CONTAINMENT RADWASTE SUMP OUTLET G04 GA A STC 18M 73ST-9X07 VRR-12 QTR FS FOR PRAIRA INBOARD CIV (PEN. 9) 2 MO C Al CLR 73ST-9CLO1 18M ST FOR TS 3.3.5.4

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Valve ID Coord/Sht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks RDBVO024 ROP-001 3 A FSC QTR 73ST-9XI07 CONTAINMENT RADWASTE SUMP OUTLET G04 GA A STC QTR 73ST-9X107 OUTBOARD CIV (PEN. 9) 2 AO C FTC QTR 73ST-9XI07 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI07 RDBV040 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1. 3. Disassembled on a CONTAINMENT SPRAY PUMP ROOM BOSSH3 CK A FSC STF 73ST-9ZZ25 VRR-04 sampling basis.

FLOOR DRAIN CHECK VALVE TO ESF SUMP 3 SA OC RDBV041 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1, 3. Disassembled on a HPSI PUMP ROOM FLOOR DRAIN CHECK BO! SH3 CK A FSC STF 73ST-9ZZ25 VRR-04 sampling basis.

VALVETO ESF SUMP 3 SA OC RDBV042 RDP-002 4 C FSO STF 73ST-9ZZ25 VRR-04 Notes 1. 3. Disassembled on a LPSI PUMP ROOM FLOOR DRAIN CHECK B0_ SH3 CK A FSC STF 73ST-9ZZ25 VRR-04 sampling basis.

VALVETO ESFSUMP 3 SA OC RDBUVO407 RDP-001 0.5 A FSC QTR 73ST-9XI07 CONTAINMENT RADWASTE SUMP OUTLET G04 GL A STC QTR 73ST-9XI07 TO POST ACCIDENT SAMPLING CIV (PEN. 9) 2 SO C FTC QTR 73ST-9XI07 Al CLR 735T-9CL01 VP 2YR 73ST-9XI07 SGEV003 SGP-002 24 C CM CMP 73ST-9X132 VRR-13 Notes 1,2, 3,4 ECONOMIZER FEEDWATER LINE CHECK E10 CK A VALVE 2 SA C SGEV005 SGP-002 24 C CM CMP 73ST-9X132 VRR-13 Notes 1. 2, 3. 4 ECONOMIZER FEEDWATER LINE CHECK A10 CK A VALVE 2 SA C SGEV006 SGP-002 24 C CM CMP 73ST-9X132 VRR-13 Notes 1. 2.3,4 ECONOMIZER FEEDWATER LINE CHECK A10 CK A VALVE 2 SA C SGEV007 SGP-002 24 C CM CMP 73ST-9XI32 VRR-13 Notes 1. 2. 3. 4 ECONOMIZER FEEDWATER LINE CHECK E10 CK A VALVE 2 SA C SGEVA19 VM M234A- 0.5 AC FSC QTR 73ST-95G01 Notes 1, 2, 3 NA CK A LT 2YR 735T-9SG01 MSIV 170 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA20 VM M234A- 0.5 AC FSC QTR 73ST-9SGOI Notes 1. 2. 3 NA CK A LT 2YR 73ST-9SG01 MSIV 170 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA21 VM M234A- 0.5 AC FSC QTR 73ST-95G01 Notes 1. 2. 3 NA CK A LT 2YR 73ST-9SGO1 MSIV 180 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA22 VM M234A- 0.5 AC FSC QTR 73ST-9SG01 Notes 1, 2. 3 NA CK A LT 2YR 735T-9SG01 MSIV 180 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA23 VM M234A- 0.5 AC FSC QTR 735T-9SGO1 Notes 1, 2. 3 NA CK A LT 2YR 735T-9SG01 MSIV 171 INSTRUMENT AIR CHECK VALVE 2 SA C

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Valve ID Coord/Sht# Type A/P ROJ/

Description Code Class Act S.P.. Test Freq Procedure VRR Remarks SGEVA24 VM M234A- 0.5 AC FSC OTR 73ST-9SGO1 Notes 1. 2 3 NA CK A LT 2YR 73ST-9SG01 MSIV 171 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA25 VM M234A- 0.5 AC FSC OTR 73ST-9SG01 Notes 1. 2 3 NA CK A LT 2YR 73ST-9SG01 MSIV 181 INSTRUMENT AIR CHECK VALVE 2 SA C SGEVA26 VM M234A- 0.5 AC FSC 0TR 73ST-9SGO1 Notes 1. 2, 3 NA CK A LT 2YR 73ST-9SG01 MSIV 181 INSTRUMENT AIR CHECK VALVE 2 SA C SGAVA27 VM M234A- 0.5 AC FSC ITR 73ST-9X116 Notes 1, 2. 3 NA CK A LT 2YR 73ST-9X116 ECONOMIZER FWIV 174 INSTRUMENT AIR CHECK VALVE 2 SA C SGAVA28 VM M234A- 0.5 AC FSC QTR 73ST-9X116 Notes 1. 2, 3 NA CK A LT 2YR 73ST-9X116 ECONOMIZER FWIV 177 INSTRUMENT AIR CHECK VALVE 2 SA C SGBVA29 VM M234A- 0.5 AC FSC OTR73ST-9X116 Notes 1, 2, 3 NA CK A LT 2YR 73ST-9X116 ECONOMIZER FWIV 132 INSTRUMENT AIR CHECK VALVE 2 SA C SGBVA30 VM M234A- 0.5 AC FSC aTR 73ST-9X116 Notes 1. 2, 3 NA CK A LT 2YR 73ST-9XI16 ECONOMIZER FWIV 137 INSTRUMENT AIR CHECK VALVE SA C SGAV043 SGP-001 6 C FSO CSD 73ST-9AF02 CSJ-17 Notes 1,2. 3 STEAM SUPPLY CHECK VALVE TO E12 SHI CK A FSC QTR 73ST-9AF02 TURBINE-DRIVEN AFW PUMP 3 SA OC PSO QTR 735T-9AF02 CSJ-17 SGAV044 SGP-001 6 C FSO CSD 73ST-9AF02 CSJ-17 Notes 1, 2 3 STEAM SUPPLY CHECK VALVE TO C1. SHI CK A FSC aTR 73ST-9AF02 TURBINE-DRIVEN AFW PUMP 3 SA OC PSO OTR 73ST-9AF02 CSJ-17 SGBUVO130 SGP-002 8 B FSC CSD 73ST-9X119 CSJ-18 Fails closed on loss of air only SG 1 DOWNCOMER FEEDWATER G11 GA A STC CSD 73ST9X119 CSJ-18 DOWNSTREAM ISOLATION VALVE 2 AO C FTC CSD 73ST-9X119 CSJ-18 VP 2YR 73ST-9X119 SGBUVO132 SGP-002 24 8 FSC CSD 73ST-9X116 CSJ-18 PSC Isan Augmented Test (see SG 1 ECONOMIZER FEEDWATER E12 GA A PSC OTR 73ST-9X16 CSJ-18)

DOWNSTREAM ISOLATION VALVE 2 HY C STC CSD 73ST-9X116 CSJ-18 FTC CSD 73ST-9X116 CSJ-18 VP 2YR 73ST-9XI16 SGAUVOI34A SGP-001 I B FSO OTR 735T-9AF02 TDAFW PUMP STEAM SUPPLY WARM-UP E13 SHI GL A FSC QTR 73ST-9AF02 LINE ISOLATION VALVE 2 SO OC STO QTR 73ST-9AF02 STC 0TR 73ST-9AF02 FTC 0TR 73ST-9AF02 LT RFO 73ST-9X134 VP 2YR 73ST9AF02

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Valve ID Coord/Sht# Type A/P ROJ/

Descriptlon Code Class Act. S.P. Test Freq Procedure VRR Remarks SGAUVO134 SGP-001 6 B FSO QTR 73ST-9AF02 VRR-12 Note 5 SG 1 STEAM SUPPLY TO AUX FEED PUMP E14 SHI GA A FSC QTR 73ST-9AF02 VRR-12 QTR FS FOR PRA/RA TURBINE ISOLATION VALVE 2 MO OC STO 18M 73ST-9AF02 VRR-12 18M ST FOR TS 3.3.5.4 STC 18M 73ST-9AF02 VRR-12 LT RFO 73ST-9X134 SGBUVO135 SGP-02 8 B FSC CSD 73ST-9X119 CSJ-18 Fails closed on loss of air only SG 2 DOWNCOMER FEEDWATER C11 GA A STC CSD 73ST-4X119 CSJ-18 DOWNSTREAM ISOLATION VALVE 2 AO C FTC CSD 73ST9XI19 CSJ-18 VP 2YR 73ST-9XI19 SGBUVO137 SGP-002 24 B FSC CSD 73ST-9XI16 CSJ-18 PSC an Augmented Test (see SG 2 ECONOMIZER FEEDWATER A12 GA A PSC QTR 73ST-9X16 CSJ-18)

DOWNSTREAM ISOLATION VALVE 2 HY C STC CSD 73ST-9X116 CSJ-18 FTC CSD 73ST-9X16 CSJ-18 VP 2YR 73ST-9XI16 SGAUVO138 SGP-001 6 B FSO OTR 735T-9AF02 VRR-12 Note 5 SG2 STEAM SUPPLY TO AUX FEED PUMP C1V SHI GA A FSC OTR 735T-9AF02 VRR-12 QTR FS FOR PRARA TURBINE ISOLATION VALVE 2 MO OC STO 18M 73ST-9AF02 VRR-12 IBM ST FOR TS 3.3.5.4 STC 18M 73ST-9AF02 VRR-12 LT RFO 73ST-9XI34 SGAUVOI38A SGP-001 1 B FSO QTR 73ST-9AF02 TDAFW PUMP STEAM SUPPLY WARM-UP C11 SHI GL A FSC QTR 73ST-9AF02 LINE ISOLATION VALVE 2 SO OC STO OTR 73ST-9AF02 STC OTR 73ST-9AF02 FTC QTR 73ST-9AF02 LT RFO 73ST-9XI34 VP 2YR 73ST-9AF02 SGEUVOI69 SGP-001 4 B FSC QTR 73ST9XI01 MSIV BYPASS VALVE D11 SH1 GA A STC QTR 73ST-9X101 2 AO C FTC QTR 73ST-9XI01 VP 2YR 73ST-9XI01 SGEUVOI70 SGP-001 28 B FSC CSD 73ST-9SG01 CSJ-19 PSC Is an Augmented Test (see MAIN STEAM ISOLATION VALVE Gi( SHI GA A PSC OTR 73ST-9SG01 CSJ-19) 2 HY C STC CSD 73ST-9SG01 CSJ-19 FTC CSD 73ST-9SG01 CSJ-19 VP 2YR 73ST-9SGOI, SGEUVO171 SGP-001 28 B FSC CSD 73ST9SG01 CSJ-19 PSC Is an Augmented Test (see MAIN STEAM ISOLATION VALVE D1( SHI GA A PSC QTR 73ST-9SG01 CSJ-19) 2 HY C STC CSD 73ST-9SG01 CSJ-19 FTC CSD 73ST-9SG01 CSJ-19 VP 2YR 73ST9SG01 SGAUVO172 SGP-002 8 B FSC CSD 73ST-9XI19 GSJ-18 Fails closed on loss of air only SG I DOWNCOMER FEEDWATER G12 GA A STC CSD 73ST-9X119 CSJ-18 UPSTREAM ISOLATION VALVE 2 AO C FTC CSD 73ST-9XI19 CSJ-18 VP 2YR 73ST-9XI19 SGAUVOI74 SGP-002 24 B FSC CSD 73ST9XI16' CSJ-18 PSC Is an Augmented Test (see SG 1 ECONOMIZER FEEDWATER E12 GA A PSC QTR 73ST-9X16 . CSJ-18)

UPSTREAM ISOLATION VALVE 2 HY C STC CSD 73ST-9X116 CSJ-18 FTC CSD 73ST-9XI16 CSJ-18 VP 2YR 73ST-9XI16

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Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SGAUVOI75 SGP-002 8 B FSC CSD 73ST-9X119 CSJ-18 Fails closed on loss of air only SG 2 DOWNCOMER FEEDWATER C12 GA A STC CSD 73ST-9X119 CSJ-18 UPSTREAM ISOLATION VALVE 2 AO C FTC CSD 73ST-9XI19 CSJ-18 VP 2YR 73ST-9XI19 SGAUVO177 SGP-002 24 B FSC CSD 73ST9XI16 CSJ-18 PSC Is an Augmented Test (see SG 2 ECONOMIZER FEEDWATER A12 GA A PSC qTR 73ST-9XI16 CSJ-18)

UPSTREAM ISOLATION VALVE 2 HY C STC CSD 73ST-9X116 CSJ-18 FTC CSD 73ST9XI16 CSJ-18 VP 2YR 73ST-9XI16 SGBHV0178 SGP-001 12 B FSO 0TR 73ST-9XI20 STEAM GENERATOR ATMOSPHERIC DUMP E02 SH2 GL A FSC QTR 73ST-9XI20 VALVE (ADV) 2 AO OC STO 0TR 73ST-9XI20 STC GTM 73ST-4X120 FTC QTR 73ST-9XI20 VP 2YR 73ST-9X120 SGAHV0179 SGP-001 12 B FSO QTR 73ST-9X120 STEAM GENERATOR ATMOSPHERIC DUMP B02 SH2 GL A FSC qTR 73ST-9XI20 VALVE (ADV) 2 AO OC STO 0TR 73ST9X120 STC 0TR 73ST-9X120 FTC 0TR 73ST-9X120 VP 2YR 73ST9X120 SGEUV0180 SGP-001 28 B FSC CSD 73ST-9SGO1 CSJ-19 PSC isan Augmented Test (see MAIN STEAM ISOLATION VALVE F1C SH1 GA A PSC QTR 73ST-9SGOI CSJ-19) 2 HY C STC CSD 735T-9SG01 CSJ-19 FTC CSD 73ST9SG01 CSJ-19 VP 2YR 73ST-9SGO1 SGEUV181 SGP-001 28 B FSC CSD 73ST-9SGO1 CSJ-19 PSC isan Augmented Test (see MAIN STEAM ISOLATION VALVE B1C SHI GA A PSC QTR 73ST-9SGO1 CSJ-19) 2 HY C STC CSD 73ST-9SGO1 CSJ-19 FTC CSD 73ST-9SGO1 CSJ-19 VP 2YR 73ST-9SGO1 SGEUVO183 SGP-001 4 B FSC QTR 73ST-9XI02 MSIV BYPASS VALVE C11 SH1 GA A STC QTR 73ST-X102 2 AO C FTC QTR 73ST-9XI02 VP 2YR 735T-9X102 SGAHV0184 SGP-001 12 B FSO QTR 73ST-9X120 STEAM GENERATOR ATMOSPHERIC DUMP GO. SH2 GL A FSC QTR 73ST-9X120 VALVE (ADV) 2 AO 00 STO 0TR 73ST-9X120 STC QTR 73ST-4)20 FTC QTR 73ST-9X120 VP 2YR 73ST-9X120 SGBHV0185 SGP-001 12 B FSO 0TR 73ST-9X120 STEAM GENERATOR ATMOSPHERIC DUMP DO' SH2 GL A FSC QTR 73ST-9X120 VALVE (ADV) 2 AO OC STO 0Th 73ST-9X120 STC 0TR 73ST-9X120 FTC QTR 73ST-9X120 VP 2YR 73ST-9X120 SGBHV0200 SGP-002 0.38 B FSC QTR 73ST-9X101 CHEMICAL INJECTION ISOLATION VALVE F11 GA A STC 0TR 73ST-9X101 (PEN. 11) 2 SO C FTC 0TR 73ST-9X101 VP 2YR 73ST-9X101

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 27 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 .14 COMPONENT TABLES 1 14 Drawing Size (In) Cat CSJI Valve ID Coord/Sht# Type AIP ROJ Description Code Class Act SP. Test Freq Procedure VRR Remarks SGBHV0201 SGP-002 0.38 B FSC QTR 73ST-9X102 CHEMICAL INJECTION ISOLATION VALVE B11 GA A STC CTR 73ST-9X102 (PEN. 12) 2 SO C FTC OTR 73ST-9XI02 VP 2YR 73ST49XI02 SGAUVO204 . SGP-002 0.5 B FSC QTR 73ST-9XI01 SG I HOT LEG BLOWDOWN SAMPLE LINE F03 GL A STC aTR 73ST9XI01 ISOLATION VALVE (PEN. 37B) 2 SO C FTC 0TR 73ST-9X101 VP 2YR 73ST-9X101 SGAUVO211 SGP-002 0.5 B FSC OTR 73ST9X101 SG 1 COLD LEG BLOWDOWN SAMPLE LINE G03 GL A STC OTR 73ST4XI01 ISOLATION VALVE (PEN. 37A) 2 SO C FTC OTR 73ST-9X101 VP 2YR 73ST-9X101 SGBUVO219 SGP-002 0.5 B FSC QTR 73ST9X101 SG I HOT LEG BLOWDOWN SAMPLE LINE G03 GL A STC QTR 73ST-9XI01 ISOLATION VALVE (PEN. 37B) 2 SO C FTC QTR 73ST-9XI01 VP 2YR 73ST-9XI01 SGAUVO220 SGP-002 0.5 B FSC QTR 73ST-9X101 SG 1 DOWNCOMER BLOWDOWN SAMPLE G06 GL A STC QTR 73ST-XIO1 LINE ISOLATION VALVE (PEN. 49) 2 SO C FTC QTR 73ST-9XI01 VP 2YR 73ST-9X101 SGBVO221 SGP-002 0.5 B FSC OTR 73ST-9XI01 SG I DOWNCOMER BLOWDOWN SAMPLE G05 GL A STC OTR 73ST9X101 LINE ISOLATION VALVE PEN. 49) 2 SO C FTC 0TR 73ST9XI01 VP 2YR 73ST-9XI01 SGBUVO222 SGP-002 0.5 B FSC OTR 73ST-9XI02 SG 2 COLD LEG BLOWDOWN SAMPLE LINE C04 GL A STC OTR 73ST9X102 ISOLATION VALVE (PEN. 638) 2 SO C FTC 0TR 73ST49XIO2 VP 2YR 73ST9XI02 SGAUVO223 SGP002 0.5 B FSC 0TR 73ST-9X102 SG 2 COLD LEG BLOWDOWN SAMPLE LINE C03 GL A STC 0TR 73ST-9X102 ISOLATION VALVE (PEN. 638) 2 SO C FTC 0TR 73ST-9XI02 VP 2YR 73ST9XI02 SGBUVO224 SGP-002 0.5 B FSC 0TR 73ST-9XI02 SG 2 HOT LEG BLOWDOWN SAMPLE UNE D04 GL A STC aTR 73ST-9X102 ISOLATION VALVE (PEN. 63A) 2 SO C FTC QTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAUVO225 SGP-002 0.5 B FSC 0TR 73ST-9XI02 SG 2 HOT LEG BLOWDOWN SAMPLE UNE D02 GL A STC 0TR 73ST9X102 ISOLATION VALVE (PEN. 63A) 2 SO C FTC 0TR 73ST9XI02 VP 2YR 73ST-9XI02 SGBUVO226 SGP-002 0.5 B FSC OTR 73ST-9XI02 SG 2 DOWNCOMER BLOWDOWN SAMPLE C05 GL A STC QTR 73ST-9X102 LINE ISOLATION VALVE (PEN. 48) 2 SO C FTC aTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAUVO227 SGP-002 0.5 B FSC 0TR 73ST-9XI02 SG 2 DOWNCOMER BLOWDOWN SAMPLE C05 GL A STC 0TR 73ST-9X102 LINE ISOLATION VALVE (PEN. 48) 2 SO C FTC 0TR 73ST-9XI02 VP 2YR 73ST9XI02

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Valve ID Coord/Sht# Type AJP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SGBUVO228 SGP-002 0.5 B FSC QTR 73ST-9XI01 SG 1 COLD LEG BLOWDOWN SAMPLE LINE G03 GL A STC QTR 73ST-9XI01 ISOLATION VALVE (PEN. 37A) 2 SO C FTC 0TR 73ST-9XI01 VP 2YR 73ST-9XI01 SGBPSVO302 SGP-001 1 AC LT 2YR 73ST-9SG05 ADV SGBHV178 NITROGEN ACCUMULATOR F06 SH2 SV A SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3 SA Oc SGBPSVO305 SGP-001 1 AC LT 2YR 73ST-9SG05 ADV SGBV178 NITROGEN SUPPLY F05 SH2 SV A SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGBPV0306A SGP-001 1 B FSO TR 73ST-9X120 VRR02 ADV NITROGEN SOLENOID VALVE F05 SH2 GA A 3 SO 0 SGBPV0306B SGP-001 1 B FSO TR 73ST-9XI20 VRR-02 ADV NITROGEN SOLENOID VALVE E05 SH2 GA A 3 SO 0 SGAPSVO309 SGP-001 1 AC LT 2YR 735T-95G05 ADV SGAV179 NITROGEN ACCUMULATOR CO( SH2 SV A SV 10Y 73ST9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGAPSVO312 SGP-001 I AC LT 2YR 73ST9SGO5 ADV SGAHV179 NITROGEN SUPPLY CO! SH2 SV A SV 10Y 73ST9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGAPV031 3A SGP-001 I B FSO QTR 73ST-9XI20 VRR-02 ADV NITROGEN SOLENOID VALVE CO! SH2 GA A 3 SO 0 SGAPV031 3B SGP-001 1 B FSO QTR 73ST-9XI20 VRR-02 ADV NITROGEN SOLENOID VALVE H0 SH2 GA A 3 so O SGAPSVO316 SGP-001 1 AC LT 2YR 735T-95G05 ADV SGAV184 NITROGEN ACCUMULATOR HO( SH2 SV A SV laY 73ST-9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGAPSVO319 SGP-001 1 AC LT 2YR 735T-95G05 ADV SGAHVI84 NITROGEN SUPPLY HO! SH2 SV A SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGBPSVO322 SGP-001 1 AC LT 2YR 73ST-95G05 ADV SGBHV185 NITROGEN ACCUMULATOR EOCSH2 SV A SV 10Y 73ST9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGBPSVO325 SGP-001 1 AC LT 2YR 735T-95G05 ADV SGBHV185 NITROGEN SUPPLY EQESH2 SV A SV IOY 73ST-9ZZ20 PRESSURE RELIEF VALVE 3 SA OC SGEV334 SGP-001 1 C FSO TR 73ST-9XI20 Notes 1 2 3 NITROGEN CHECK VALVE TO ADV 179 C04 SH2 CK A 3 SA 0 SGEV339 SGP001 1 C FSO QTR 73ST-9X120 Notes 1, 2. 3 NITROGEN CHECK VALVE TO ADV 184 HOESH2 CK A 3 SA 0

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Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SGEV346 SGP-001 I AC FSC aTR 73ST-9SG05 Notes 1.2. 3 INSTRUMENT AIR CHECK VALVE TO ADV B04 SH2 CK A LT 2YR 73ST-9SG05 184 3 SA C SGEV348 SGP-001 1 AC FSC QTR 73ST-9SG05 Notes 1, 2, 3 INSTRUMENT AIR CHECK VALVE TO ADV GO' SH2 CK A LT 2YR 73ST-9SG05 179 3 SA C SGEV350 SGP-001 I C FSO OTR 73ST-9XI20 Notes 1. 2, 3 NITROGEN CHECK VALVE TO ADV 178 F04 SH2 CK A 3 SA 0 SGEV357 SGP-001 I AC FSC OTR 73ST-9SG05 Notes 1. 2. 3 INSTRUMENT AIR CHECK VALVE TO ADV F04 SH2 CK A LT 2YR 73ST-9SG05 178 3 SA C SGEV358 SGP-001 1 AC' FSC CTR 73ST-9SG05 Notes 1, 2 3 INSTRUMENT AIR CHECK VALVE TO ADV D04 SH2 CK A LT 2YR 73ST-9SG05 185 3 SA C SGEV360 SGP-001 I C FSO OTR 73ST-9X120 Notes 1. 2. 3 NITROGEN CHECK VALVE TO ADV 185 Ec SH2 CK A 3 SA 0 SGBUVO500Q SGP-002 6 B FSC QTR 73ST-9XI01 STEAM GENERATOR BLOWDOWN SAMPLE E02 GA A STC QTR 73ST-9X101 CIV (PEN. 46) 2 AO C FTC aTR 73ST-9XI01 VP 2YR 73ST-9XI01 SGAUVO500P SGP-002 6 B FSC CTR 73ST-9XI01 STEAM GENERATOR BLOWDOWN SAMPLE E03 GA A STC OTR 73ST-9X101 CIV (PEN. 46) 2 AO C FTC CTR 73ST-9XI01 VP 2YR 73ST-9XI01 SGBUVO50OR SGP-002 6 B FSC CTR 73ST-9XI02 STEAM GENERATOR BLOWDOWN SAMPLE A03 GA A STC OTR 73ST-9X102 CIV (PEN. 47) 2 AO C FTC OTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGAUVO500S SGP-002 6 B FSC OTR 73ST-9XI02 STEAM GENERATOR BLOWDOWN SAMPLE A02 GA A STC GTR 73ST-9X102 CIV (PEN. 47) 2 AO C FTC OTR 73ST-9XI02 VP 2YR 73ST-9XI02 SGEPSVO554 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D1; SHI SV A 038788)

LINE 1 2 SA OC SGEPSVO555 SGP-001 6 C SV RFO 73ST.9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D1 SH1 SV A 038788)

LINE 1 2 SA OC SGEPSVO556 SGP-001 6 C SV RFO 73ST.9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM D14 SHI SV A 038788)

LINE 1 2 SA OC SGEPSVO557 SGP-001 6 C SV RFO 73ST.9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM . DI! SHI SV A 038788)

LINE 1 2 SA OC

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Valve ID Coord/Sht# Type AP ROJI Description Code Class Act. SP. Test Freq Procedure VRR Rernars SGEPSVO558 SGP001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM Al SHI SV A 038788)

LINE2 2 SA OC SGEPSVO559 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A14 SH1 SV A 038788)

LINE 2 2 SA OC SGEPSVO560 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A13 SH1 SV A 038788)

LINE2 2 SA 0C SGEPSVO561 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A12 SHI SV A 038788)

LINE2 2 SA OCi SGEPSVO572 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM H1; SHI SV A 038788)

LINE 1 2 SA 0C SGEPSVO573 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG15TEAM H1 SHI SV A 038788)

LINE 1 2 SA DC SGEPSVO574 SGP001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG STEAM H14 SH1 SV A 038788)

LINE 1 2 SA 0C SGEPSVO575 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SGI STEAM H14 SHI SV A 038788)

LINE 1 2 SA 0C SGEPSVO576 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM FIS SH1 SV A 038788)

LINE 2 2 SA OC SGEPSV0577 SGP001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F14 SH1 SV A 038788)

LINE 2 2 SA 0C SGEPSVO578 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F13 SH1 SV A 038788)

LINE 2 2 SA OC SGEPSVO579 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F12 SHI SV A 038788)

LINE2 2 SA 0C SGEV642 SGP-002 8 C CM CMP 73ST-9XI32 VRR-13 Notes 1. 2, 3 4 DOWNCOMER FEEDWATER LINE CHECK G11 CK A VALVE 2 SA C SGEV652 SGP002 8 C CM CMP 73ST-9X132 VRR-13 Notes 1, 2, 3 4 DOWNCOMER FEEDWATER LINE CHECK 010 CK A VALVE 2 SA C SGEV653 SGP-002 8 C CM CMP 73ST-9X132 VRR-13 Notes 1, 2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK C10 CK A VALVE 2 SA C SGEPSVO691 SGP-01 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM F15 SH1 SV A 038788)

LINE 2 2 SA 0C

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 31 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 14 COMPONENT TABLES Drawing Size (In) Cat. CSJI Valve ID CoordlSht# Type AIP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SGEPSVO692 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG1 STEAM HI SHI SV A 038788)

LINE 1 2 SA OC SGEV693 SGP-002 8 C CM CMP 73ST-9XI32 VRR-13 Notes 1. 2, 3, 4 DOWNCOMER FEEDWATER LINE CHECK C11 CK A VALVE 2 SA C SGEPSVO694 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAIN STEAM SAFETY VALVE SG2 STEAM A1E SH1 SV A 038788)

LINE2 2 SA OC SGEPSVO695 SGP-001 6 C SV RFO 73ST-9ZZ18 Tested each refueling (ref. RCTS MAINSTEAMSAFETYVALVESG2STEAM DI' SHI SV A 038788)

LINE 1 2 SA OC SGEV887 SGP-001 2 C FSO QTR 73ST-9AF02 Notes 1,2. 3 WARM-UP LINE CHECK VALVE TO TURBINE- D1; SHI CK A FSC RFO 73ST-9XI36 ROJ-13 DRIVEN AFW PUMP 3 SA OC SGEV888 SGP-001 2 C FSO QTR 73ST-9AF02 Notes 1, 2, 3 WARM-UP LINE CHECK VALVE TO TURBINE- C1. SH1 CK A FSC RFO 73ST-9X136 ROJ-13 DRIVEN AFW PUMP 3 SA OC SGEV982 SGP-001 1 AC FSC QTR 73ST-9SG05 Notes 1 2 3 ADV NITROGEN SUPPLY CHECK VALVE BOE SH2 CK A LT 2YR 73ST-9SG05 3 SA C SGEV985 SGP-001 1 AC FSC QTR 73ST.9SG05 Notes 1, 2. 3 ADV NITROGEN SUPPLY CHECK VALVE GOf SH2 CK A LT 2YR 73ST-9SGO5 3 SA C SGEV988 SGP-001 I AC FSC QTR 73ST.9SG05 Notes 1, 2, 3 ADV NITROGEN SUPPLY CHECK VALVE DOESH2 CK A LT 2YR 73ST.9SG05 3 SA C SGEV991 SGP-001 1 AC FSC qTR 73ST-9SG05 Notes 1, 2, 3 ADV NITROGEN SUPPLY CHECK VALVE FOGSH2 CK A LT 2YR 73ST-9SG05 3 SA C SGAUVI133 SGP-001 1 B FSC OTR 73ST9XI01 STEAM TRAP SGN-M23 ISOLATION VALVE ElE SHI GL A STC QTR 73ST-9X101 2 SO C FTC QTR 73ST9XI01 VP 2YR 73ST-9XI32 SGAUV1I34 SGP-001 I B FSC QTR 73ST-9X102 STEAM TRAP SGN-M24 ISOLATION VALVE C14 SH1 GL A STC OTR 73ST-9X102 2 SO C FTC QTR 73ST-9XI02 VP 2YR 73ST-9XI32 SGBUV135A SGP-01 I B FSC QTR 73ST-9XI01 STEAM TRAP SGN-MOI ISOLATION VALVE Hi SHI GL A STC QTR 73ST9X101 2 SO C FTC QTR 73ST-9XI01 VP 2YR 73ST-9XI32 SGBUV1I35B SGP-Ca 1 B FSC QTR 73ST-9XI01 STEAM TRAP SGN-M02 ISOLATION VALVE F1 SH1 GL A STC QTR 73ST-X101 2 SO C FTC QTR 73ST-9X101 VP 2YR 73ST-9X132

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Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SGBUV1I36B SGP-001 I B FSC QTR 73ST9XI02 STEAM TRAP SGN-M04 ISOLATION VALVE All SHI GL A STC QTR 735T-9X102 2 SO C FTC QTR 73ST-9XI02 VP 2YR 73ST-9XI32 SGBUVII36A SGP-001 1 B FSC QTR 73ST-9XI02 STEAM TRAP SGN-M03 ISOLATION VALVE D11 GL A STC QTR 73ST-9X102 2 SO C FTC QTR 73ST-9XI02 VP 2YR 73ST-9X132 SGEPSE1183 SGP-001 I AC LT 2YR 73ST-9SG05 Replaced every 5 years perOM-1 ADV NITROGEN SUPPLY RUPTURE DISK F05 2 RD A 1.3.4.2 3 SA OC SGEPSE1184 SGP-001 I AC LT 2YR 73ST-9SGO5 Replaced every 5 years per OM-1 ADV NITROGEN SUPPLY RUPTURE DISK D0. 2 RD A 1.3.4.2 3 SA OC SGEPSE1185 SGP-001 1 AC LT 2YR 73ST-9SG05 Replaced every 5 years per OM-1 ADV NITROGEN SUPPLY RUPTURE DISK B05 2 RD A 1.3.4.2 3 SA OC SGEPSE1186 SGP-001 1 AC LT 2YR 735T-9SG05 Replaced every 5 years perOM-1 ADV NITROGEN SUPPLY RUPTURE DISK GO 2 RD A 1.3.4.2 3 SA OC SIAVA10 SIP-002 1 C FSO RFO 73ST9X121 ROJ-12 Notes 1, 2, 3 PRESSURE LOCKING CHECK VALVE FOR G03 CK A FSC RFO 73ST-9XI21 ROJ-12 SIAUV0655 BONNET 2 SA OC SIBVA15 SIP-002 I C FSO RFO 73ST-9X121 ROJ-12 Notes 1, 2. 3 PRESSURE LOCKING CHECK VALVE FOR G10 CK A FSC RFO 73ST-9X121 ROJ-12 SIBUV0656 BONNET 2 SA OC SIEV113 SIP-002 3 C FSO RFO 73ST-9X133 ROJ-04 Notes 1, 2, 3 HPSI CHECK VALVE TO RCS COLD LEG F14 CK A FSC CSD 73ST-9SI05 CSJ-20 INJECTION HEADER 2 SA OC SIEV114 SIP-002 12 C FSO CSD 73ST9X127 CSJ-21 Notes 1, 2, 3 LPSI CHECK VALVE TO RCS COLD LEG F13 CK A FSC CSD 73ST-9S105 CSJ-21 INJECTION HEADER 2 SA OC SIEV123 SIP-002 3 C FSO RFO 73ST-9X133 ROJ-04 Notes 1, 2. 3 HPSI CHECK VALVE TO RCS COLD LEG F12 CK A FSC CSD 73ST-9S105 CSJ-20 INJECTION HEADER 2 SA OC SIEV124 SIP-002 12 C FSO CSD 73ST9X127 CSJ-21 Notes 1, 2. 3 LPSI CHECK VALVE TO RCS COLD LEG Fl1 CK A FSC CSD 73ST-9S105 CSJ-21 INJECTION HEADER 2 SA OC SIEV133 SIP-002 3 C FSO RFO 73ST-9X133 ROJ-04 Notes 1, 2. 3 HPSI CHECK VALVE TO RCS COLD LEG F07 CK A FSC CSD 73ST-9S105 CSJ-20 INJECTION HEADER 2 SA OC SIEV134 SIP-002 12 C FSO CSD 73ST-9XI26 CSJ-21 Notes 1. 2. 3 LPSI CHECK VALVE TO RCS COLD LEG F06 CK A FSC CSD 73ST-9S105 CSJ-21 INJECTION HEADER 2 SA OC SIBPSVOI40 SIP-001 0.75 C SV 10Y 73ST-9ZZ20 SI PUMP SUCTION LINE FROM B15 SV A CONTAINMENT SUMP PRESSURE RELIEF 2 SA OC VALVE (PEN. 24)

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Valve ID Coord/Sht# Type AIP ROJ/

Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SIBPSVO141 SIP-001 1 C SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE BETWEEN B15 SV A ISOLATION VALVES TO FUEL POOL 3 SA 0C COOLING SIEV143 SIP-002 3 C FSO RFO 73ST-9X133 ROJ-04 Notes 1, 2, 3 HPSI CHECK VALVE TO RCS COLD LEG F04 CK A FSC CSD 73ST-9SI05 CSJ-20 INJECTION HEADER 2 SA OC SIEV144 SIP-002 12 C FSO CSD 73ST-9X126 CSJ-21 Notes 1, 2, 3 LPSI CHECK VALVE TO RCS COLD LEG F04 CK A FSC CSD 73ST-9SI05 CSJ-21 INJECTION HEADER 2 SA OC SIAPSVO150 SIP-001 I C SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE BETWEEN H15 SV A ISOLATION VALVES TO FUEL POOL 3 SA OC COOLING SIAPSVOI51 SIP-001 0.75 C SV 10y 73ST-9ZZ20 SI PUMP SUCTION LINE FROM CONTMT G15 SV A SUMP PRESSURE RELIEF VALVE (PEN. 23) 2 SA OC SIAV157 SIP-001 18 C FSO RFO 73ST-9X129 ROJ-11 Notes 1, 2, 3 CONTAINMENT SPRAY PUMP SUCTION G13 CK A PSO QTR 73ST-9S106 ROJ-11 LINE CHECK VALVE 2 SA 0 SIBV158 SIP-001 18 C FSO RFO 73ST-9XI29 ROJ-11 Notes 1. 2 3 CONTAINMENT SPRAY PUMP SUCTION B13 CK A PSO TR 73ST-9SI06 ROJ-11 LINE CHECK VALVE 2 SA 0 SIAPSVO161 SIP-001 0.75 C SV 10Y 73ST-9ZZ20 LPSIISDC LINE PRESSURE RELIEF VALVE H06 SV A 2 SA OC SIAPSVO162 SIP-001 1 C SV laY 73ST-9ZZ20 PRESSURE RELIEF VALVE BETWEEN G05 SV A ISOLATION VALVES TO FUEL POOL 3 SA OC COOLING SIAV164 SIP-002 10 AC CM CMP 735T-9CL01 VRR-13 Notes 1, 3,4 CONTAINMENT SPRAY HEADER CHECK F08 CK A AJ CLR 73ST-9CLOI VALVE AND INBOARD CIV (PEN. 21) 2 SA OC SIBVI65 SIP-002 10 AC CM CMP 73ST-9CLOI VRR-13 Notes 1. 3.4 CONTAINMENT SPRAY HEADER CHECK F06 CK A AJ CLR 73ST-9CLOI VALVE AND INBOARD CIV (PEN. 22) 2 SA OC SIBPSVO166 SIP-002 0.75 C SV I Y 73ST-9ZZ20 HPSI LONG TERM RECIRC PRESSURE G09 SV A RELIEF VALVE 2 SA OC SIBPSVOI69 SIP-002 0.75 C SV SYR 73ST-9ZZ20 SHUTDOWN COOLING LINE PRESSURE D10 SV A RELIEF VALVE 1 SA OC SIAPSVO79 SIP-002 6 C SV lY 73ST-9ZZ19 SHUTDOWN COOLING RETURN LINE LTOP G0,3 SV A RELIEF VALVE 2 SA OC SIBPSV0189 SIP-002 6 C SV 10Y 73ST-9ZZ19 SHUTDOWN COOLING RETURN LINE LTOP F11 SV A RELIEF VALVE 2 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 34 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rev1ion COMPONENT TABLES DrawIng SIze (In) Cat CSJI Valve ID CoordUSht# Type AIP ROJI Description Code Class Act S.P. Test Freq Procedure VRR Remarks SIBPSVO191 SIP-001 1.5 C SV l0Y 73ST-9ZZ20 SHUTDOWN COOLING HEAT EXCHANGER D07 SV A OUTLET PRESSURE RELIEF VALVE 2 SA OC SIBPSVO92 SIP-001 1 C SV lay 73ST-9ZZ20 PRESSURE RELIEF VALVE BETWEEN C05 SV A ISOLATION VALVES TO FUEL POOL 3 SA OC COOLING SIBPSVOI93 SIP-001 0.75 C SV 1y 73ST-9ZZ20 LPSUSDC LINE PRESSURE RELIEF VALVE D06 SV A 2 SA OC SIAPSVO194 SIP-001 1.5 C SV 10Y 73ST-9ZZ20 SHUTDOWN COOLING HEAT EXCHANGER H07 SV A OUTLET PRESSURE RELIEF VALVE 2 SA OC SIBV200 SIP-01 20 C FSO RFO 73ST-9X129 ROJ-1 LPSI PUMP SUCTION LINE CHECK VALVE 812 CK A PSO QTR 73ST-9X110 ROJ-1 2 SA 0 SIAV201 SIP-001 20 C FSO RFO 73ST-9XI29 ROJ-11 LPSI PUMP SUCTION LINE CHECK VALVE F13 CK A PSO QTR 73ST-9XI09 ROJ-11 2 SA 0 SIAV205 SIP-001 24 C CMO CMP 73ST-9ZZ25 VRR-13 Notes 1. 3, 4 CONTAINMENT RECIRCULATION SUMP F14 CK A CMC CMP 73ST-9X139 VRR-13 CHECK VALVE TO SI SUPPLY HEADER 2 SA 0 SIBV206 SIP-001 24 C CMO CMP 73ST-9ZZ25 VRR-13 Notes 1,3.4 CONTAINMENT RECIRCULATION SUMP A14 CK A CMC CMP 73ST-9X139 VRR-13 CHECK VALVE TO SI SUPPLY HEADER 2 SA 0 SIEPSVO211 SIP-002 2 C SV laY 73ST-9ZZ20 SAFETY INJECTION TANK 2A PRESSURE E15 SV A RELIEF VALVE 2 SA OC SIEV215 SIP-002 14 AC CMO CMP 73ST-9XI25 VRR-13 Notes 1, 2, 3,4 SAFETY INJECTION TANK DISCHARGE A15 CK A CMC CMP 73ST-9SI03 VRR-13 Leak test frequency Is 18 months CHECK VALVE I SA OC LT 18M 73ST-9SI03 per TS SR 3.4.15.1.

SIEV217 SIP-002 14 AC CMO CMP 73ST-9X127 VRR-13 Notes 1. 2. 3. 4 COLD LEG SAFETY INJECTION LOOP A13 CK A CMC CMP 73ST9S103 VRR-13 Leak test frequency Is 18 months CHECK VALVE 1 SA OC LT 18M 73ST-9S103 per TS SR 3.4.15.1.

SIEPSVO221 SIP-002 2 C SV 10y 73ST-9ZZ20 SAFETY INJECTION TANK 2B PRESSURE E12 SV A RELIEF VALVE 2 SA OC SIEV225 SIP-002 14 AC CMO CMP 73ST-9X125 VRR-13 Notes 1, 2. 3. 4 SAFETY INJECTION TANK DISCHARGE A12 CK A CMC CMP 73ST-9SI03 VRR-13 Leak test frequency Is 18 months CHECKVALVE 1 SA OC LT 18M 73ST-9S103 perTS SR 3.4.15.1.

SIEV227 SIP-002 14 AC CMO CMP 73ST-9X127 VRR-13 Notes 1. 2, 3. 4 COLD LEG SAFETY INJECTION LOOP A1O CK A CMC CMP 73ST-9SI03 VRR-13 Leak test frequency Is 18 months CHECK VALVE 1 SA OC LT IBM 735T-95103 perTS SR 3.4.15.1.

SIEPSVO231 SIP-002 2 C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 1A PRESSURE E08 SV A RELIEF VALVE 2 SA OC SIEV235 SIP-002 14 AC CMO CMP 73ST-9X125 VRR-13 Notes 1,2,3,4 SAFETY INJECTION TANK DISCHARGE A07 CK A CMC CMP 73ST-9SI03 VRR-13 Leak test frequency si 8months CHECK VALVE 1 SA OC LT 18M 73ST-9SI03 per TS SR 3.4.1 5.1.

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Vaive ID CoordlSht# Type A/P ROJ/

Description Code Class Ad. S.P. Test Freq Procedure VRR Remarks SIEV237 SIP-002 14 AC CMO CMP 73ST-9XI26 VRR-13 Notes 1.2.3,4 COLD LEG SAFETY INJECTION LOOP A06 CK A CMC CMP 73ST-9S103 VRR-13 Leak test frequency Is 18 months CHECK VALVE 1 SA OC LT 18M 73ST-9SI03 per TS SR 3.4.15.1.

SIEPSVO241 SIP-002 2 C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK 1B PRESSURE E05 SV A RELIEF VALVE 2 SA OC SIEV245 SIP-002 14 AC CMO CMP 73ST-9Xi25 VRR-13 Notes 1, 2, 3, 4 SAFETY INJECTION TANK DISCHARGE A05 CK A CMC CMP 73ST-9S103 VRR-13 Leak test frequency Is 18 months CHECK VALVE I SA OC LT 18M 73ST-9SI03 perTS SR 3.4.15.1.

SIEV247 SIP-002 14 AC CMO CMP 73ST-9XI26 VRR-13 Notes 1, 2 3. 4 COLD LEG SAFETY INJECTION LOOP A04 CK A CtIC CMP 73ST-9SI03 VRR-13 Leak test frequency Is 18 months CHECK VALVE I SA OC LT 18M 73ST-9SI03 perTS SR 3.4.15.1.

SIAPSV0285 SIP-001 0.75 C SV ICY 73ST-9ZZ20 Si PUMP COMBINED RECIRC PRESSURE F09 SV A RELIEF VALVE 2 SA OC SIBPSVO286 SIP-001 0.75 C SV 10Y 73ST-9ZZ20 Si PUMP COMBINED RECIRC PRESSURE B09 SV A RELIEF VALVE 2 SA OC SIBPSVO287 SIP-001 0.75 C SV lay 73ST-9ZZ20 CONTAINMENT SPRAY LINE PRESSURE C09 SV A RELIEF VALVE 2 SA OC SIEPSVO288 SIP-001 I C SV 1Y 73ST-9ZZ20 SI MAXIFLOW RECIRC LINE RELIEF VALVE E05 SV A 3 SA OC SIAPSVO289 SIP-001 0.75 C SV 1Y 73ST-9ZZ20 CONTAINMENT SPRAY LINE PRESSURE G09 SV A RELIEF VALVE 2 SA OC SIAHV0306 SIP-001 10 B FSO ICY 73ST-xX1 VRR-12 FSO Includes position stop LPSI DISCHARGE HEADER ISOLATION G05 GL A FSC iCY 73ST-xX111 VRR-12 verification perTS SR 3.5.3.7 VALVE 2 MOZ 00 Note 5 SIBHV0307 SIP-001 10 B FSO iCY 73ST-xX112 VRR-12 FSO Includes position stop LPSI HEADER DISCHARGE ISOLATION B04 GL A FSC ICY 73ST-xX112 VRR-12 verification perTS SR 3.5.3.7 VALVE 2 MO 00 Note 5 SICHV0321 SIP-002 3 B FSO OTR 73ST-xXI11 VRR-12 FSO Includes position stop HPSI LONG TERM RECIRCULATION CIV G02 GL A FSC OTR 73ST-xX111 VRR-12 verification per TS SR 3.5.3.7 (PEN. 77) 2 iMO OC Note 5 OTR FS FOR PRANRA.

SIBUVO322 SIP-002 1 B FSC OTR 73ST-9X113 HOT LEG INJECTION CHECK VALVE LEAK E02 GL A STC OTR 73ST-9X113 ISOLATION VALVE 1 AO C FTC OTR 73ST-9XI13 VP 2YR 73ST-9XI13 SIDHV0331 SIP-002 3 8 FSO OTR 73ST-xXI12 VRR-12 FSO Includes position stop HPSI LONG TERM RECIRCULATION CIV G09 GL A FSC QTR 73ST-xXI2 VRR-12 verification per TS SR 3.5.3.7 (PEN. 67) 2 iMO OC Note 5 QTR FS FOR PRAJRA.

SIBUVO332 SIP-002 1 B FSC QTR 73ST-9XI14 HOT LEG INJECTION CHECK VALVE LEAK E10 GL A STC QTR 73ST-9X114 ISOLATION VALVE 1 AO C FTC 0TR 73ST-9XI14 VP 2YR 73ST-9XI14

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 36 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 , 14 COMPONENT TABLES Drawing Size (in) CaL CSJ/

Valve ID CoordJSht# Type AtP ROJI/

Description Code Class Ad. S.P. Test Freq Procedure VRR Remarks SIAV404 SIP-001 4 C FSO RFO 73ST-9X133 ROJ-05 Notes 1. 2. 3 HPSI PMP DISCHARGE CHECK VALVE F06 CK A FSC RFO 73ST-9X133 ROJ-05 FSC also performed in 73ST-9X135 2 SA OC SIBV405 SIP-001 4 C FSO RFO 73ST-9X133 ROJ-05 Notes 1, 2, 3 HPSI PMP DISCHARGE CHECK VALVE B04 CK A FSC RFO 73ST-9X133 ROJ-05 FSC also performed In73ST-9X135 2 SA OC SIEPSVO407 SIP-001 1 C SV 10Y 73ST-9ZZ20 SAFETY INJECTION TANK FILL LINE E08 SV A RELIEF VALVE 3 SA OC SIBPSV0409 SIP-001 1.5 C SV 10Y 73ST-9ZZ20 HPSI LINE PRESSURE RELIEF VALVE B02 SV A 2 SA OC SIAPSV0417 SIP-001 1.5 C SV 10Y 73ST-9ZZ20 HPSI LINE PRESSURE RELIEF VALVE F02 SV A 2 SA OC SIAV424 SIP-001 2 C FSO TR 73ST-9S1l0 Notes 1, 2, 3 HPSI PUMP RECIRC LINE CHECK VALVE F10 CK A 2 SA 0 SIBV426 SIP-001 2 C FSO TR 73ST-9S1l0 Notes 1. 2, 3 HPSI PUMP RECIRC LINE CHECK VALVE A10 CK A 2 SA 0 SIAV434 SIP-001 10 C FSO CSD 73ST-9X126 CSJ-05 Notes 1. 2, 3 LPSI PUMP DISCHARGE CHECK VALVE F09 CK A PSO TR 73ST-9X109 CSJ-05 2 SA 0 SIAPSV0439 SIP-001 0.75 C SV 10Y 73ST-9ZZ20 LPSI LINE PRESSURE RELIEF VALVE H02 SV A 2 SA OC SIBV446 SIP-001 10 C FSO CSD 73ST-9XI27 CSJ-05 Notes 1. 2. 3 LPSI PUMP DISCHARGE CHECK VALVE B09 CK A PSO TR 73ST-9X110 CSJ-05 2 SA 0 SIBV448 SIP-001 2 C FSO TR 73ST-9Si11 Notes 1, 2, 3 LPSI PMP RECIRC LINE CHECK VALVE B10 CK A 2 SA 0 SIBPSV0449 SIP-01 0.75 C SV 10Y 73ST-9ZZ20 LPSI LINE PRESSURE RELIEF VALVE D02 SV A 2 SA OC SIAV451 SIP-001 2 C FSO TR 73ST-9S111 Notes 1, 2, 3 LPSI PMP RECIRC LINE CHECK VALVE G11 CK A 2 SA O SIEV463 SIP-001 2 A AJ CLR 73ST-9CL01 SAFETY INJECTION TANK FILUDRAIN D08 GL p HEADER OUTBOARD CIV (PEN. 28) 2 MA C SIAPSV0468 SIP-002 0.75 C SV 1Y 73ST-9ZZ20 HPSI LONG TERM RECIRC PRESSURE G02 SV A RELIEF VALVE 2 SA OC SIAPSV0469 SIP-002 0.75 C SV 5YR 73ST-9ZZ20 SHUTDOWN COOLING LINE PRESSURE D03 SV A RELIEF VALVE 1 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 37 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 1v4 COMPONENT TABLES Drawing Size (In) Cat. CSJJ Valve ID CoordlSht# Type AtP ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SIEPSVD473 SIP-001 I C SV lay 73ST-9ZZ20 SAFETY INJECTION TANK FILL/DRAIN LINE E10 SV A PRESSURE RELIEF VALVE 2 SA OC SIEPSV474 SIP-001 0.75 AC AJ CLR 73ST-9CLO1 SAFETY INJECTION TANK FILLIDRAIN LINE D09 SV A SV 10Y 73ST-9ZZ20 PRESSURE RELIEF VALVE 2 SA OC SIBV484 SIP-001 10 C FSO CSD 73ST-9XI27 CSJ-05 Notes 1. 2, 3 CONTAINMENT SPRAY PUMP DISCHARGE C10 CK A PSO QTR 73ST-9SI06 CSJ-05 CHECK VALVE 2 SA 0 SIAV485 SIP-001 10 C FSO CSD 73ST-9XI26 CSJ-05 Notes 1, 2. 3 CONTAINMENT SPRAY PUMP DISCHARGE H1O CK A PSO OTR 73ST-9SI06 CSJ-05 CHECK VALVE 2 SA 0 SIAV486 SIP-001 2 C FSO OTR 73ST-9SI06 Notes 1. 2, 3 CONTAINMENT SPRAY PMP RECIRC LINE G1O CK A CHECK VALVE 2 SA 0 SIBV487 SIP-001 2 C FSO TR 73ST-9SI06 Notes 1, 2. 3 CONTAINMENT SPRAY PMP RECIRC LINE C10 CK A CHECK VALVE 2 SA 0 SIAV522 SIP-002 3 AC FSO RFO 73ST-9X133 ROJ-06 Notes 1, 2. 3. Leak test frequency HPSI LONG-TERM RECIRC CHECK VALVE C02 CK A FSC STF 73ST-9S103 VRR-08 Is 18 months per TS SR 3.4.1 5.1 I SA OC LT 18M 73ST-9SI03 SIAV523 SIP-002 3 AC FSO RFO 73ST-9Xi33 ROJ-06 Notes 1, 2, 3. Leak test frequency HPSI LONG-TERM RECIRC INBOARD CIV F02 CK A FSC STF 73ST-9SI03 VRR-08 is 18 months perTS SR 3.4.15.1 (PEN. 77) 1 SA OC LT 18M 73ST-9SI03 SIBV532 SIP-002 3 AC FSO RFO 73ST-9XI33 ROJ-06 Notes 1. 2. 3. Leak test frequency HPSI LONG-TERM RECIRC CHECK VALVE B10 CK A FSC STF 73ST-9SI03 VRR-08 is 18 months per TS SR 3.4.1 5.1 1 SA OC LT 18M 73ST-9S103 SIBV533 SIP-002 3 AC FSO RFO 73ST-9X133 ROJ-06 Notes 1, 2. 3. Leak test frequency HPSI LONG-TERM RECIRC INBOARD CIV F09 CK A FSC STF 73ST-9S103 VRR-08 Is 18 months per TS SR 3.4.15.1 (PEN. 67) 1 SA OC LT 18M 73ST-9SI03 SIEV540 SIP-002 12 AC FSO CSD 73ST-9X127 CSJ-31 Notes 1. 2, 3. Leak test frequency COLD LEG SAFETY INJECTION CHECK B13 CK A FSC STF 73ST-9SI03 VRR-08 is 18 months per TS SR 3.4.15.1 VALVE 1 SA OC LT 18M 73ST-9S103 SIEV541 SIP002 12 AC FSO CSD 73ST-9X127 CSJ-31 Notes 1. 2, 3. Leak test frequency COLD LEG SAFETY INJECTION CHECK B11 CK A FSC STF 73ST-9S103 VRR08 Is 18 months per TS SR 3.4.15.1 VALVE 1 SA OC LT 18M 73ST-9S103 SIEV542 SIP-002 12 AC FSO CSD 73ST-9XI26 CSJ-31 Notes 1. 2, 3. Leak test frequency COLD LEG SAFETY INJECTION CHECK C06 CK A FSC STF 73ST-9S103 VRR-08 Is 18 months per TS SR 3.4.15.1 VALVE I SA OC LT 18M 73ST-9S103 SIEV543 SIP002 12 AC FSO CSD 73ST-9XI26 CSJ-31 Notes 1, 2. 3. Leak test frequency COLD LEG SAFETY INJECTION CHECK C04 CK A FSC STF 73ST-9S103 VRR08 Is 18 months per TS SR 3A.15.1 VALVE I SA OC LT 18M 73ST-95103 SIAHV0604 SIP-001 3 B FSO CTR 73ST-9X113 VRR-12 Note 5 HPSI LONG TERM RECIRC ISOLATION G03 GA A FSC OTR 73ST-9X113 VRR-12 QTR FS FOR PRAtRA.

VALVE 2 MO OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 38 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rvision COMPONENT TABLES Drawing Size (In) Cat. CSJ/

Valve ID Coord/Sht# Type AIP ROJ/

Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SIAHV0605 SIP-002 1 B 'FSO CSD 73ST-9XI37 CSJ-26 SAFETY INJECTION TANK 2A F15 GL A FSC CSD 73ST-9Xi37 CSJ-26 ATMOSPHERIC VENT VALVE 2 so OC STO CSD 73ST-9Xi37 CSJ-26 STC CSD 73ST-9X137 CSJ-26 FTC CSD 73ST-9Xi37 CSJ-26 VP 2YR 73ST49Xi37 SIAHV0606 SiP-002 1 B FSO CSD 73ST-9X137 CSJ-26 SAFETY INJECTION TANK 28 F12 GL A FSC CSD 73ST-9XI37 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 73ST-9XI37 CSJ-26 STC CSD 73ST-9X137 CSJ-26 FTC CSD 73ST-9XI37 CSJ-26 VP 2YR 73ST9XI37 SIAHV0607 SIP-002 1 B FSO CSD 73ST9XI37 CSJ-26 SAFETY INJECTION TANK 1A F07 GL A FSC CSD 73ST9XI37 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 73ST-9X137 CSJ-26 STC CSD 73ST-9X137 CSJ-26 FTC CSD 73ST9XI37 CSJ-26 VP 2YR 73ST-9XI37 SIAHV0608 SIP-002 1 B FSO CSD 73ST9X137 CSJ-26 SAFETY INJECTION TANK 1B F04 GL A FSC CSD 73ST-9X137 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 73ST-9X137 CSJ-26 STC CSD 73ST-XI37 CSJ-26 FTC CSD 73ST-9XI37 CSJ-26 VP 2YR 73ST-9X137 SIBHV0609 SIP-001 3 B FSO QTR 73ST-9X114 VRR-12 Note 5 HPSI LONG TERM RECIRC ISOLATION C03 GA A FSC QTR 73ST-9X114 VRR-12 QTR FS FOR PRA/RA VALVE 2 MO OC SIBUVO611 SIP-002 2 B FSC QTR 73ST-9XI04 Considered active during first IST SAFETY INJECTION TANK 2A FILLDRAIN B16 GL P STC QTR 73ST-X104 Interval, re-evaluated as passive ISOLATION VALVE 2 AO C FTC OTR 73ST-9XI04 during 10-year update, further VP 2YR 73ST-9XI04 reviews being performed before dis-continuing exercise testing SIBHV0613 SIP-002 1 B FSO CSD 73ST-9X137 CSJ-26 SAFETY INJECTION TANK 2A E1S GL A FSC CSD 73ST-9XI37 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 73ST-9X137 CSJ-26 STC CSD 73ST-9X137 CSJ-26 FTC CSD 73ST-9X137 CSJ-26 VP 2YR 73ST-9X137 SIBUVO614 SIP-002 14 B FSO 1CY 73ST-9X125 VRR-12 Note 5 SAFETY INJECTION TANK 2A DISCHARGE A15 GA A STO 18M 73ST-9X125 VRR-12 18M ST FOR TS 3.3.5.4 ISOLATION VALVE 1 MO 0 SIBUVO615 SIP-002 12 B FSO 1CY 73ST-xX112 VRR-12 FSOIncludespositionstop LPSI DISCHARGE HEADER OUTBOARD CIV G14 GL A verification per SR 3.5.3.7 (PEN. 17) 2 MO O Note 5 SIBUVO616 SIP-002 2 B FSO QTR 73ST-9X114 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G14 GL A STO 18M 73ST-9X114 VRR-12 QTR FS FOR PRAfRA CIV (PEN. 13) 2 MO O 18M ST FOR TS 3.3.5.4 SIAUVO617 SIP-002 2 B FSO QTR 73ST-9XI13 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G15 GL A STO 18M 73ST-9XI13 VRR-12 QTR FS FOR PRA/RA CIV (PEN. 13) 2 MO O 18M ST FOR TS 3.3.5.4

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 39 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES Drawing Size (In) Cat CSJI Valve ID CoordlSht# Type A/P ROJ/

Descriptlon Code Class Act S.P. Test Freq Procedure VRR Remarks SIBVO618 SIP-002 I B FSC QTR 73ST-9XI04 SAFETY INJECTION TANK 2A CHECK B16 GL A STC qTR 73ST-X104 VALVE LEAKAGE TEST LINE ISOLATION 1 AO C FTC QTR 73ST-9XI04 VALVE VP 2YR 73ST9XIO4 SIAHV0619 SIP-002 1 B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D15 GL P 2 AO C SIBUVO621 SIP-002 2 B FSC OTR 73ST-9XI4 Considered active during first IST SAFETY INJECTION TANK 2B FILLIDRAIN B12 GL P STC aR 73ST-9X104 Interval, re-evaluated as passive ISOLATION VALVE 2 AO C FTC QTR 735T-9X104 during 10-year update, further VP 2YR 735T-9X104 reviews being performed before dis-continuing exercise testing SIBHV0623 SIP-002 1 B FSO CSD 735T-9XI37 CSJ-26 SAFETY INJECTION TANK 2B E12 GL A FSC CSD 735T-9X137 CSJ-26 ATMOSPHERIC VENT VALVE 2 so OC STO CSD 735T-9X137 CSJ-26 STC CSD '735T4X137 CSJ-26 FTC CSD 735T-9X137 CSJ-26 VP 2YR 735T-9X137 SIBUV0624 SIP-002 14 B FSO ICY 735T-9X125 VRR-12 Note 5 SAFETY INJECTION TANK 2B DISCHARGE A12 GA A STO 18M 735T-9X125 VRR-12 18M ST FOR TS 3.3.5.4 ISOLATION VALVE 1 MO O SIBUVO625 SIP-002 12 B FSO ICY 735T-xX112 VRR-12 FSO Includes position stop LPSI DISCHARGE HEADER OUTBOARD CIV Gil GL A verification per SR 3.5.3.7 (PEN. 18) 2 MO O Note 5 SIBUVO626 SIP-002 2 B FSO QTR 735T-9X114 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD Gil GL A STO 18M 735T-9X114 VRR-12 QTR FS FOR PRA/RA CIV (PEN. 14) 2 MO 0 18M ST FOR TS 3.3.5.4 SIAUVO627 SIP-002 2 B FSO QTR 735T-9X113 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G12 GL A STO 18M 73ST-9XI13 VRR-12 QTR FS FOR PRA/RA CIV (PEN. 14) 2 MO ° 18M ST FOR TS 3.3.5.4 SIBUVO628 SIP-002 I B FSC QTR 735T-9XI4 SAFETY INJECTION TANK 2B CHECK 613 GL A STC QTR 735T-9X104 VALVE LEAKAGE TEST LINE ISOLATION 1 AO C FTC QTR 735T-9XI04 VALVE VP 2YR 735T-9XI04 SIAHV0629 SIP-002 1 B VP 2YR 735T-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D12 GL P 2 AO C SIBUVO631 SIP-02 2 B FSC OTR 73ST-9X103 Considered active during first IST SAFETY INJECTION TANK 1A FILLIDRAIN C08 GL P STC QTR 735T-X103 Interval, re-evaluated as passive ISOLATION VALVE 2 AO C FTC OTR 735T-9X103 during 10-year update. further VP 2YR 735T-9X103 reviews being performed before dis-continuing exercise testing SIBHV0633 SIP-002 1 B FSO CSD 735T-9X137 CSJ-26 SAFETY INJECTION TANK IA E07 GL A FSC CSD 735T-9X137 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 735T-9X137 CSJ-26 STC CSD 735T-9X137 CSJ-26 FTC CSD 735T-9XI37 CSJ-26 VP 2YR 735T-9X137

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 40 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rvio COMPONENT TABLES 14 Drawing Size (in) Cat. CSJI Valve ID CoordlSht# Type A/P ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SIAUVO634 SIP-002 14 B FSO ICY 73ST-9XI25 VRR-12 Note 5 SAFETY INJECTION TANK 1A DISCHARGE B07 GA A STO 18M 73ST-9X125 VRR-12 18M ST FOR TS 3.3.5.4 ISOLATION VALVE ' MO 0 SIAUVO635 SIP-002 12 B FSO ICY 73ST-xXII1 VRR-12 FSO Includes position stop LPSI DISCHARGE HEADER OUTBOARD CIV G06 GL A verification per SR 3.5.3.7 (PEN. 19) 2 MO 0 Note 5 SIBUV0636 SIP-002 2 B FSO QTR 73ST-Xi14 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G07 GL A STO 18M 73ST-9Xi14 VRR-12 CTR FS FOR PRAIRA CIV (PEN. 15) 2 MO O 18M ST FOR TS 3.3.5.4 SIAUV0637 SIP-002 2 B FSO QTR 73ST-9X113 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G08 GL A STO 18M 73ST-9X13 VRR-12 QTR FS FOR PRAIRA CIV (PEN. 15) 2 MO O IBM ST FOR TS 3.3.5A SIBUV0638 SIP-002 I B FSC QTR 73ST-9XI03 SAFETY INJECTION TANK IA CHECK B09 GL A STC QTR 73ST-9X03 VALVE LEAKAGE TEST LINE ISOLATION 1 AO C FTC qTR 73ST-9XI03 VALVE VP 2YR 73ST-9XIO3 SIAHV0639 SIP-002 1 B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE D07 GL P 2 AO C SIBUV0641 SIP-002 2 B FSC QTR 73ST-9XI03 Considered active during first IST SAFETY INJECTION TANK 1B FILLIDRAIN B06 GL P STC QTR 73ST-9XI03 Interval. re-evaluated as passive ISOLATION VALVE 2 AO C FTC 0TR 73ST-9X103 during 10-year update, further VP 2YR 735T-9X103 reviews being performed before dis-continuing exercise testing SIBHV0643 SIP-002 1 B FSO CSD 73ST-9X137 CSJ-26 SAFETY INJECTION TANK 1 E04 GL A FSC CSD 73ST-9XI37 CSJ-26 ATMOSPHERIC VENT VALVE 2 SO OC STO CSD 73ST-9XI37 CSJ-26 STC CSD 73ST-9X137 CSJ-26 FTC CSD 735T-9X137 CSJ-26 VP 2YR 73ST-9XI37 SIAUVO644 SIP-002 14 B FSO iCY 73ST-9X125 VRR-12 Note 5 SAFETY INJECTION TANK 1B DISCHARGE 604 GA A STO 18M 73ST-9X125 VRR-12 18M ST REQ'D FORTS 3.3.5.4 ISOLATION VALVE I MO 0 SIAUVO645 SIP-002 12 B FSO ICY 73ST-xXI VRR-12 FSO Includes position stop LPSI DISCHARGE HEADER OUTBOARD CIV G04 GL A verification per SR 3.5.3.7 (PEN. 20) 2 MO 0 Note 5 SIBUVO646 SIP-002 2 B FSO 0TR 73ST-9X114 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G04 GL A STO 18M 73ST-9X114 VRR-12 QTR FS FOR PRAtRA CIV (PEN. 16) 2 MO 0 IBM ST FORTS 3.3.5.4 SIAUV0647 SIP-002 2 B FSO QTR 73ST-9XI13 VRR-12 Note 5 HPSI DISCHARGE HEADER OUTBOARD G05 GL A STO 18M 73ST-9XI13 VRR-12 QTR FS FOR PRAIRA CIV (PEN. 16) 2 MO 0 18M ST FOR TS 3.3.5.4 SIBUVO648 SIP-002 1 B FSC QTR 73ST-9X103 SAFETY INJECTION TANK 1B CHECK 806 GL A STC QTR 735T-9X03 VALVE LEAKAGE TEST LINE ISOLATION ' AO C FTC QTR 73ST-9XI03 VALVE VP 2YR 73ST-9X103 SIAHV0649 SIP-002 I B VP 2YR 73ST-9XI25 SIT NITROGEN SUPPLY ISOLATION VALVE DOS GL P 2 AO C

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 41 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 14 R,,I, COMPONENT TABLES Drawing Size (In) Cat CSJI Valve ID Coord/Sht# Type AIP ROJI Descriptlon Code Class Act. SP. Test Freq Procedure VRR Remarks SIAUVO651 SIP-002 16 A FSO ICY 73ST-9X121 VRR-12 Leak lest frequency is 18 months SHUTDOWN COOLING SUCTION C03 GA A FSC ICY 73ST-9X121 VRR-12 per TS SR 3.4.15.1 ISOLATION VALVE 1 htO OC LT 18M 73ST-9S103 Note 5 SIBUV0652 SIP-002 16 A FSO ICY 73ST-9X121 VRR-12 Leak test frequency Is 18 months SHUTDOWN COOLING SUCTION CIO GA A FSC 1CY 73ST9XI21 VRR-12 per TS SR 3.4.15.1 ISOLATION VALVE I MO OC LT 18M 73ST-9S103 Note 5 SICUVO653 SIP-002 16 A FSO CSD 73ST-9XI21 VRR-12 Leaktestfrequencyls 18 months SHUTDOWN COOLING SUCTION INBOARD D03 GA A FSC CSD 73ST9XI21 VRR-12 per TS SR 3.4.15.1 CIV (PEN. 27) 1 htO OC LT 18M 73ST-9S103 Note 5 PRAIRA REQ'D QTR EXERCISING IS N/A PER CSJ-27.

SIDUVO654 SIP-002 16 A FSO CSD 73ST9XI21 VRR-12 Leak test frequency 1s18 months SHUTDOWN COOLING SUCTION INBOARD D10 GA A FSC CSD 73ST-9X121 VRR-12 per TS SR 3.4.15.1 CIV (PEN. 26) 1 htO OC LT 18M 735T-9S103 Note 5 PRAIRA REQ'D QTR EXERCISING IS NIA PER CSJ-27.

SIAUVO655 SIP-002 16 B FSO ICY 73ST-9S111 VRR-12 Note 5 SHUTDOWN COOLING SUCTION G03 GA A FSC ICY 73ST-9S11 VRR-12 (PREVIOUSLY TESTED IN73ST-OUTBOARD CIV (PEN. 27) 2 MO OC 9X121.)

SIBUV0656 SIP-002 16 B FSO ICY 73ST-9S111 VRR-12 Note 5 SHUTDOWN COOLING SUCTION G10 GA A FSC 1CY 73ST-9S111 VRR-12 PREVIOUSLY TESTED IN73ST OUTBOARD CIV (PEN. 26) 2 MO OC 9XI21.

SIAHV0657 SIP-001 16 B FSO ICY 73ST9X113 VRR-12 Note 5 SHUTDOWN COOLING HEAT EXCHANGER H03 BF A FSC ICY 73ST-9XI13 VRR-12 OUTLET THROTTLE VALVE 2 MO OC SIBHV0658 SIP-001 16 B FSO ICY 73ST-9X114 VRR-12 Note 5 SHUTDOWN COOLING HEAT EXCHANGER C03 BF A FSC ICY 73ST-9XI14 VRR-12 OUTLET THROTTLE VALVE 2 htO OC SIBUVO659 SIP-001 4 B FSO QTR 73ST-9X114 SI COMBINED RECIRC TO RWT ISOLATION B06 GL A FSC QTR 73ST-9XI14 VALVE 2 SO OC STO QTR 73ST-9XI14 STC QTR 73ST-XI14 FTC QTR 73ST-9XI14 VP 2YR 73ST4GXI14 SIAUVO660 SIP-001 4 B FSO QTR 73ST-9XI13 SI COMBINED RECIRC TO RWT ISOLATION F06 GL A FSC QTR 73ST-XI13 VALVE 2 SO OC STO 0TR 73ST-9XI13 STC OTM 73ST-9XI13 FTC QTR 73ST-9XI13 VP 2YR 73ST-9X113 SIAUVO664 SIP-001 2 B FSO 1CY 73ST-9XI03 VRR-12 Note 5 CONTAINMENT SPRAY PUMP RECIRC TO GIO GL A FSC 1CY .73ST-9X103 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 RWT ISOLATION VALVE 2 MO OC STO 18M 73ST-9X103 VRR-12 STC 18M 73ST-9X103 VRR-12 SIBUVO665 SIP-001 2 B FSO ICY 73ST-9X104 VRR-12 Note 5 CONTAINMENT SPRAY PUMP RECIRC TO B10 GL A FSC iCY 73ST-9X104 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 RWT ISOLATION VALVE 2 MO OC STO 18M 73ST-9X104 VRR-12 STC 18M 73ST-9X104 VRR-12

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 42 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XIOI 14 COMPONENT TABLES 14 Drawing Size (in) Cat. CSJI Valve ID Coord/Sht# Type AIP ROJI Description Code Class Act S.P. Test Freq Procedure VRR Remarks SIAUVO666 SIP-001 2 B FSO ICY 73ST-9Xi3 VRR-12 Note 5 HPSI PUMP RECIRC TO RWT ISOLATION FIO GL A FSC ICY 73ST-9XI13 VRR-12 18M ST REO'D FOR TS 3.3.5.4 VALVE 2 MO OC STO 18M 73ST-9XI13 VRR-12 STC IBM 73ST49X13 VRR-12 SIBUVO667 SIP-001 2 B FSO ICY 73ST-9XI14 VRR-12 Note 5 HPSI PUMP RECIRC TO RWT A1O GL A FSC ICY 73ST-9Xi14 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 2 MO OC STO 18M 73ST-9Xi14 VRR-12 STC 18M 73ST-9Xi14 VRR-12 SIBUVO668 SIP-001 2 B FSO ICY 73ST-9X114 VRR-12 Note 5 LPSI PUMP RECIRC TO RWT ISOLATION Bil GL A FSC ICY 73ST-9XI14 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 VALVE 2 MO OC STO 18M 73ST-9Xi14 VRR-12 STC 18M 73ST9Xi14 VRR-12 SIAUVO669 SIP-001 2 B FSO iCY 73ST-9X113 VRR-12 Note 5 LPSI PUMP RECIRC TO RWT ISOLATION G10 GL A FSC ICY 73ST-9XI13 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 VALVE 2 MO OC STO 18M 73ST-9XI13 VRR-12 STC 18M 73ST-9X113 VRR-12 SIBUVO671 SIP-001 8 A FSO iCY 73ST-9XI04 VRR-12 Note 5 CONTAINMENT SPRAY CONTROL VALVE C06 GA A FSC ICY 73ST-9XI04 VRR-12 18M ST REQ'D FORTS 3.3.5.4 AND OUTBOARD CIV (PEN. 22) 2 MO OC STO 18M 73ST-9X104 VRR-12 STC 18M 73ST-9X104 VRR12 AJ CLR 73ST-9CLI01 SIAUVO672 SIP-001 8 A FSO ICY 73ST-9XI03 VRR-12 Note 5 CONTAINMENT SPRAY CONTROL VALVE G06 GA A FSC ICY 73ST-9XI03 VRR-12 18M ST REQD FORTS 3.3.5.4 AND OUTBOARD CIV (PEN. 21) 2 MO OC STO 18M 735T-9X103 VRR-12 STC IBM 73ST9Xi03 VRR-12 AJ CLR 73ST-9CLOI SIAUVO673 SIP-001 24 B FSO QTR 73ST-9X103 VRR-12 Note 5 CONTAINMENT SUMP TO St PUMP G16 BF A STO 18M 735T-9XI03 VRR-12 QTR FS FOR PRAIRA SUCTION INBOARD CIV (PEN. 23) 2 MO O 18M ST FOR TS 3.3.5.4 SIAUVO674 SIP-001 24 B FSO QTR 735T-9X103 VRR-12 Note 5 CONTAINMENT SUMP TO Si PUMP G14 BF A STO 18M 73ST-9XI03 VRR-12 OTR FS FOR PRAIRA SUCTION OUTBOARD CIV (PEN. 23) 2 MO 0 18M ST FOR TS 3.3.5A SIBUVO675 SIP-001 24 B FSO QTR 73ST-9XI4 VRR-12 Note 5 CONTAINMENT SUMP TO SI PUMP A16 BF A STO 18M 73ST-9X104 VRR-12 QTR FS FOR PRAJRA SUCTION INBOARD CIV (PEN. 24) 2 MO 0 18M ST FOR TS 3.3.5.4 SIBUVO676 SIP-001 24 B FSO QTR 73ST-9X104 VRR-12 Note 5 CONTAINMENT SUMP TO SI PUMP A14 BF A STO IBM 73ST-9X04 VRR-12 OTR FS FOR PRAIRA SUCTION OUTBOARD CIV (PEN. 24) 2 MO 0 18M ST FOR TS 3.3.5.4 SIAHV0678 SIP-001 10 B FSO ICY 73ST-9XI03 VRR-12 Note 5 S/D COOLING HEAT EXCHANGER H09 GA A FSC ICY 73ST-9X103 VRR-12 ISOLATION TRAIN A 2 MO OC SIBHV0679 SIP-001 10 B FSO ICY 73ST-9Xi04 VRR-12 Note 5 S/D COOLING HEAT EXCHANGER C09 GA A FSC ICY 73ST-9XI04 VRR-12 ISOLATION TRAIN B 2 MC OC SIAUV0682 SIP-001 2 A FSC OTR 73ST-9X103 SAFETY INJECTION TANK FILL LINE CIV D10 GL A STC QTR 73ST-9X103 (PEN. 28) 2 AO C FTC QTR 73ST-9XI03 Al CLR 73ST-9CLO1 VP 2YR 73ST-9XI03

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 43 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 14 COMPONENT TABLES Drawing Size (in) Cat. CSJI Valve ID CoordlSht# Type AIP ROJI Description Code Class At. S.P. Test Freq Procedure VRR Remarks SIAHV0683 SIP-001 20 B FSO QTR 73ST-9SI11 VRR-12 Note 5 LPSI PUMP SUCTION ISOLATION TRAIN A F13 GA A FSC QTR 73ST-9SI11 VRR-12 QTR FS FOR PRAIRA-2 MO OC PREVIOUSLY TESTED IN 73ST-9XI03.

SIAHV0684 SIP-001 10 B FSO ICY 73ST-9XI03 VRR-12 Note 5 CTMT SPRAY TO SID COOLING HEAT H09 GA A FSC ICY 73ST-94X103 VRR-12 EXCHANGER ISOLATION TRAIN A 2 MO OC SIAHV0685 SIP-401 10 B FSO ICY 73ST-9SI1 VRR-12 Note 5 LPSI PUMP TO SHUTDOWN COOUNG HEAT G08 GA A FSC ICY 73ST-9SIll VRR-12 PREVIOUSLY TESTED IN 73ST.

EXCHANGER ISOLATION VALVE 2 MO OC 9XI13 SIAHV0686 SIP-001 20 a FSO iCY 73ST-9X113 VRR-12 Note 5 SHUTDOWN COOLING HEAT EXCHANGER H06 GA A FSC iCY 73ST-9X113 VRR-12 OUTLET TO LPSI ISOLATION VALVE 2 MO OC SIAHV0687 SIP-001 10 B Note 5 CTMT SPRAY ISOLATION TRAIN A G06 GA P PASSIVE VALVE - NO CC 2 MO 0 EXERCISE REQT.

SIAHV0688 SIP-001 10 a FSO ICY 73ST-9XI03 VRR-12 Note 5 CONTAINMENT SPRAY BYPASS VALVE G09 GA A FSC ICY 73ST-9X103 VRR-12 2 MO OC SIBHV0689 SIP-001 10 B FSO ICY 73ST-9XI04 VRR-12 Note 5 CTMT SPRAY TO SID COOLING HEAT C09 GA A FSC ICY 73ST-9XI04 VRR-12 EXCHANGER ISOLATION TRAIN B 2 MO OC SIBHV0690 SIP-002 10 B FSO QTR 73ST-9SI11 VRR-12 Note 5 SHUTDOWN COOLING WARMUP BYPASS H13 GL A FSC OTR 73ST-9SI11 VRR-12 OTR FS FOR PRAIRA-CONTAINMENT ISOLATION VALVE 2 Mc OC PREVIOUSLY TESTED IN73ST-9XI04.

SIAHV0691 SIP-002 10 B FSO' OTR 73ST-9SI11 VRR-12 Note 5 SHUTDOWN COOLING WARMUP BYPASS H03 GL A FSC TR 73ST-9I11 VRR-12 OTR FS FOR PRAIRA -

CONTAINMENT SOLATION VALVE 2 MO Oc PREVIOUSLY TESTED IN73ST-9XI03.

SIBHV0692 SIP-OI 20 B FSO TR 73ST-9SI11 VRR-12 Note 5 LPSI PUMP SUCTION ISOLATION TRAIN B B13 GA A FSC TR 73ST-9SI11 VRR-12 OTR FS FOR PRAIRA-2 MO OC PREVIOUSLY TESTED IN 73ST-9XI04.

SIBHV0693 SIP-001 10 B FSO CY 73ST-X104 VRR-12 Note 5 CONTAINMENT SPRAY BYPASS VALVE C09 GA A FSC CY 73ST-XIO4 VRR-12 2 MO OC SIBHV0694 SIP-001 10 B FSO CY 73ST-9S111 VRR-12 Note 5 LPSI CROSS CONNECT VALVE TO C08 GA A FSC CY 73ST-9SI11 VRR-12 PREVIOUSLY TESTED IN73ST-SHUTDOWN COOLING HEAT EXCHANGER 2 MO OC 9XI14 SIBHV0695 SIP-001 10 B Note 5 CTMT SPRAY ISOLATION TRAIN B C06 GA P PASSIVE VALVE - NO CC 2 MO 0 EXERCISE REQT.

SIBHV0696 SIP-001 20 B FSO ICY 73ST-9X114 VRR-12 Note 5 SHUTDOWN COOLING HEAT EXCHANGER C06 GA A FSC ICY 73ST-9X114 VRR-12 OUTLET TO LPSI ISOLATION VALVE 2 MO OC SIAHV0698 SIP-001 4 B FSO CY 73ST-9X133 VRR-12 Note 5 HPSI HEADER DISCHARGE ISOLATION F04 GA A FSC CY 73ST-9X133 VRR-12 PREVIOUSLY TESTED IN 73ST-VALVE 2 MD OC 9X113.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 44 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 14 COMPONENT TABLES 14 Drawing Size (in) Cat. CSJI Valve ID CoordlSht# Type A/P ROJI Description Code Class AcL S.P. Test Freq Procedure VRR Remarks SIBHV0699 SIP-001 4 B FSO ICY 73ST-9Xi33 VRR-12 Note 5 HPSI HEADER DISCHARGE ISOLATION B03 GA A FSC ICY 73ST-9Xi33 VRR-12 PREVIOUSLY TESTED IN 73ST-VALVE 2 MO OC 9XI14.

SIAUVO708 SIP-001 0.5 B STC RFO 73ST-X121 STC Is an augmented test, CONTAINMENT SUMP TRAIN A SAMPLE TO GIS GL P VP 2YR 73ST-9XI21 performed at RFO to satisfy ESF PASS ISOLATION VALVE (PEN. 23) 2 SO C response Ume testing per SR 3.3.5.4 and CIV isolation time testing per SR 3.6.3.5.

SIAUVO709 SIP-001 0.5 B STC RFO 73ST-9X121 STC Is an augmented test, MINI-FLOW RECIRC LINE SAMPLE E08 GL P VP 2YR 73ST-9XI21 performed at RFO to satisfy ESF ISOLATION VALVE 2 SO C response time testing per SR 3.3.5.4.

SIBUVO710 SIP-001 0.5 B STC RFO 73ST-9XI21 STC Is an augmented test, MINI-FLOW RECIRC LINE SAMPLE 807 GL P VP 2YR 73ST-9XI21 performed at RFO to satisfy ESF ISOLATION VALVE 2 SO C response time testing per SR 3.3.5.4.

SIAPSVO754 SIP-002 0.5 C SV 5YR 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR B03 SV A SIAUV0651 BONNET I SA OC SIBPSVO755 SIP-02 0.5 C SV SYR 73ST-9ZZ20 PRESSURE LOCKING RELIEF VALVE FOR B03 SV A SIBUVO652 BONNET 1 SA OC SIAV997 SIP-002 1 C FSO RFO 73ST9X121 ROJ-12 Notes 1, 2. 3 PRESSURE LOCKING CHECK VALVE FOR E03 CK A FSC RFO 73ST-9XI21 ROJ-12 SICUV0653 BONNET 1 SA OC SIBV998 SIP-002 1 C FSO RFO 73ST-9X121 ROJ-12 Notes 1. 2, 3 PRESSURE LOCKING CHECK VALVE FOR D10 CK A FSC RFO 73ST-9X121 ROJ-12 SIDUV654 BONNET 1 SA OC SPBV012 SPP-001 24 C FSO GTR 73ST-9SP01 Notes 1 2. 3 ESSENTIAL SPRAY POND PUMP C06 CK A DISCHARGE CHECK VALVE 3 SA 0 SPAPSVO029 SPP002 I C SV lay 73ST-9ZZ20 ESSENTIAL COOLING WATER HEAT D03 SV A EXCHANGER PRESSURE RELIEF VALVE 3 SA OC SPBPSVO030 SPP-002 1 C SV laY 73ST-9ZZ20 ESSENTIAL COOLING WATER HEAT D06 SV A EXCHANGER PRESSURE RELIEF VALVE 3 SA OC SPAV041 SPP-01 24 C FSO QTR 73ST-9SP01 Notes 1, 2. 3 ESSENTIAL SPRAY POND PUMP C04 CK A DISCHARGE CHECK VALVE 3 SA 0 SPAPSVOI37 SPP-002 2.5 C SV OY 73ST-9ZZ20 EDG FUEL OIL COOLER PRESSURE G02 SV A RELIEF VALVE 3 SA *OC SPBPSVO138 SPP-002 2.5 C SV lay 73ST-9ZZ20 EDG LUBE OIL COOLER PRESSURE G06 SV A RELIEF VALVE 3 SA OC SPAPSVOI39 SPP-002 2.5 C SV 0Y 73ST-9ZZ20 EDG JACKET WATER COOLER PRESSURE F02 SV A RELIEF VALVE 3 SA OC

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 45 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 v4sion COMPONENT TABLES Drawing Size (In) CaL CSJt Valve ID CoordlSht# Type AIP ROJt Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SPBPSVOI40 SPP-002 2.5 C SV 10Y 73ST-9ZZ20 EDG AIR INTERCOOLER PRESSURE F06 SV A RELIEF VALVE 3 SA OC SPAPSVO141 SPP-002 2.5 C SV OY 73ST-9ZZ20 EDG AIR INTERCOOLER PRESSURE F02 SV A RELIEF VALVE 3 SA OC SPBPSVO142 SPP002 2.5 C SV 10Y 73ST-9ZZ20 EDG JACKET WATER COOLER PRESSURE F06 SV A RELIEF VALVE 3 SA OC SPAPSVOI43 SPP-002 2.5 C SV 10Y 73ST-9ZZ20 EDG LUBE OIL COOLER PRESSURE E02 SV A RELIEF VALVE 3 SA OC SPBPSVO144 SPP-002 2.5 C SV IY 73ST-9ZZ20 EDG FUEL OIL COOLER PRESSURE F06 SV A RELIEF VALVE 3 SA OC SPEHCV0207 SPP-001 10 B FSO QTR 73ST-9X131 SPRAY POND CROSSCONNECT VALVE E05 BF A FSC aTR 73ST-9X131 3 MA OC SPEHCV0208 SPP-001 10 B FSO QTR 73ST-9XI31 SPRAY POND CROSSCONNECT VALVE E04 BF A FSC QTR 73ST9X131 3 MA OC SSBUVO200 SSP-001 0.38 A FSC OTR 73ST-9XI06 HOT LEG SAMPLE LINE OUTBOARD CIV G05 GL A STC CTR 73ST-9X106 (PEN. 42C) 2 SO C FTC QTR 73ST-9X106 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9X106 SSBUV201 SSP4001 0.38 A FSC QTR 73ST-9X106 PRESSURIZER SURGE LINE SAMPLE LINE F05 GL A STC QTR 73ST-9X106 OUTBOARD CIV (PEN. 42A) 2 SO C FTC 0TR 73ST9X106 AJ CLR 73ST-9CLOI VP 2YR 73ST-9X106 SSBUVO202 SSP-001 0.38 A FSC QTR 73ST-9X106 PRESSURIZER STEAM SPACE SAMPLE F05 GL A STC QTR 73ST-9X106 LINE OUTBOARD CIV (PEN. 42B) 2 SO C FTC 0TR 73ST-9X106 AJ CLR 73ST9CL01 VP 2YR 73ST-9XI06 SSAUVO203 SSP-001 0.38 A FSC OTR 73ST-9X106 HOT LEG SAMPLE LINE INBOARD CIV(PEN. G07 GL A STC aTR 73ST-9X106 42C) 2 SO C FTC OTR 73ST9X106 AJ CLR 73ST9CL01 VP 2YR 73ST-9X106 SSAUVO204 SSP-001 0.38 A FSC 0TR 73ST-9XI06 PRESSURIZER SURGE LINE SAMPLE LINE F07 GL A STC QTR 73ST40X106 INBOARD CIV (PEN. 42A) 2 SO C FTC QTR 73ST-9X106 Al CLR 73ST9CL01 VP 2YR 73ST-9X106

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 46 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rv14 COMPONENT TABLES 14 Drawing Size (in) Cat. CSJ/

Valve ID Coord/Sht# Type A/P ROJI Description Code Class Act. S.P. Test Freq Procedure VRR Remarks SSAUVO205 SSP-001 0.38 A FSC QTR 73ST-9XI06 PRESSURIZER STEAM SPACE SAMPLE E07 GL A STC CTR 73ST4X106 LINE INBOARD CIV (PEN. 42B) 2 SO C FTC QTR 73ST-9XI06 AJ CLR 73ST-9CLO1 VP 2YR 73ST-9XI06 WCEV039 WCP-001 10 AC FSC CSD 73ST9XI28 CSJ-28 Notes 1 2. 3 NORMAL CHILLED WATER SUPPLY TO E05 CK A AJ CLR 73ST-9CLO1 CONTAINMENT INBOARD CIV (PEN. 60) 2 SA C WCBUVO061 WCP-001 10 A FSC ICY 73ST-9XI07 VRR-12 Note 5 NORMAL CHILLED WATER RETURN FROM G05 GA A STC 18M 73ST9XI07 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT INBOARD CIV (PEN. 61) 2 MO C A) CLR 73ST-9CLO1 WCAUVO062 WCP-001 10 A FSC ICY 73ST-9XI07 VRR-12 Note 5 NORMAL CHILLED WATER RETURN FROM G05 GA A STC 18M 73STOX107 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 61) 2 MO C A) CLR 73ST-9CLO1 WCBUVO063 WCP-001 10 A FSC ICY 73ST-9XI07 VRR-12 Note 5 NORMAL CHILLED WATER SUPPLY TO G06 GA A STC 18M 73ST4GXI07 VRR-12 18M ST REQ'D FOR TS 3.3.5.4 CONTAINMENT OUTBOARD CIV (PEN. 60) 2 MD C A) CLR 73ST-9CLO1

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pae 47 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 PRRs, CSJs, ROJs, and VRRs The following table lists the Pump Relief Requests (PRRs), Cold Shutdown Justifications (CSJs),

Refueling Outage Justifications (ROJs), and Valve Relief Requests (VRRs) in the PVNGS Pump and Valve Inservice Testing Program. Items that have been deleted are shaded.

Identifier Subject (and Notes)

PRR-O1 Essential Auxiliary Feedwater Pump Flow Rate Measurement PRR-02 Non-Essential Auxiliary Feedwater Pump Flow Rate Measurement PRR-03 Charging Pump Flow Rate Measurement PRR-04 (Not used).; *'

PRR-05 LPSI Pump Flow Rate Measurement PRR-06 HPSI Pump Flow Rate Measurement PRR-07 Charging Pump Vibration Measurement PRR-08 Smooth-Running Pumps PRR-09 Evaluation as Corrective Action PRR-10 ANII Involvement in Pump Inservice Testing PRR-I I Containment Spray Pump Flow Rate Measurement CSJ-01 Auxiliary Feedwater Pump Suction Check Valve Open Exercising CSJ-02 AFW Pump Discharge Check Valve Open Exercising CSJ-03 AFW Discharge Header Check Valve Open and Closed Exercising CSJ-04 AFW Header Check Valve Open Exercising CSJ-05 LPSI and CS Pump Discharge Check Valve Open Exercising CSJ-06 Auxiliary Pressurizer Spray Valve Exercising CSJ-07 Boration Flowpath Isolation Valve Exercising CSJ-08 ;VCT Outlet Valve Closed Exercising ;_,

.f. .. . -

" (Dleteddurin' the iplemintaiioh of ASME M Code Case OMN-I per VRR-2.)'

CSJ-09 Letdown Isolation Valve Closed Exercising CSJ-10 Containment Refueling Purge Valve Closed Exercising CSJ-l I RCP Seal Injection Containment Isolation Valve Closed Exercising CSJ-12 EW/NC CrosstieValvesClosedExercising'U,' '

(Deleted duriig the implementation of ASME OM Code Case OMN-1 per VRR-12.):-' ' ;

CSJ-13 Instrument Air Containment Isolation Valve Closed Exercising CSJ'14 NC Containment Isolation'Valve'Closed Exercising' -:-;

(Deleted during the iplemenitatioin fASME.OM Code Case OMN-I per VRR-12.) '

CSJ-15 Reactor Head Vent and Pressurizer Vent Valve Exercising CSJ Feedwater Economizer Check Valve Closed Exercising ' - '

- : (Deleted'during iplementatio of Check Valve Condition Monitoring Program per VRR-13) <'*

CSJ- 17 Turbine-Driven AFW Pump Steam Supply Check Valve Exercising CSJ-18 Feedwater Isolation Valve Closed Exercising CSJ-19 Main Steam Isolation Valve Closed Exercising CSJ-20 HPSI Header Check Valve Closed Exercising CSJ-21 LPSI Header Check Valve Open and Closed Exercising CSJ-22 - AFNV Turbine Steam' Supply Check Valve Closed Exercising " . -' ,

(SupersededbyROJ-13) '-. . . .,.. ,

CSJ-23 Nitrogen Containment Isolation Check Valve Closed Exercising CSJ-24 Hydrogen Return Containment Isolation Check Valve Closed Exercising CSJ-25 Shutdown Cooling Isolation Valve Bonnet Vent Check Valve Open and Closed Exercising

. (Superseded by ROJ-12) . ; % * - - . - ; ;

CSJ-26 SIT Vent Valve Exercising CSJ-27 Shutdown Cooling Suction Isolation Valve Exercising

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pae 48 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Identifier Subject (and Notes)

CSJ-28 Normal Chilled Water Containment Isolation Check Valve Closed Exercising CSJ-29 _ RMW Supply to RDT Containment Isolation Check Valve Closed Exercising CSJ-30 NC to Containment Check Valve Closed Exercising CSJ-31 SI Header Check Valve Open Exercising CSJ-32 RCP Seal Bleed-Off Isolation Valve Closed Exercising CSJ-33 SIT.Outlet MOV.OpenExercising

'*- ; - ' ' '+

.(Deleted during the implementation of ASME OM Code' Case OMN-I per VRR-12i.)

ROJ-Ol Boration Flow Path Check Valve Open Exercising ROJ-02 RWT Outlet Check Valve Open Exercising ROJ-03 BAMP Discharge Check Valve Open Exercising ROJ-04 HPSI Header Check Valve Open Exercising ROJ-05 HPSI Pump Discharge Check Valve Open and Closed Exercising ROJ-06 HPSI Long-Term Recirculation Check Valve Open Exercising ROJ-07 'SIT Discharge Check Valve Open ExercisingK'- '..' ': ' .*-.-.

(Deleted durin'g iplenientation of CheckVave Condition Monitoring Program per VRR-13)

ROJ-08 :'SIIRCS Check Valve Open Exercising. ;.-. ,-. -

'(Deleted duing inpeetto fCeck alve Conidition Monitoring Program pr VRR-)

ROJ-09 Regenerative Heat Exchanger Inlet Check Valve Closed Exercising ROJ-I0 Safety Injection Pump Suction Flowpath Check Valve Closed Exercising ROJ-I I LPSI and CS Pump Suction Check Valve Open Exercising ROJ-12 Shutdown Cooling Isolation Valve Bonnet Vent Check Valve Open and Closed Exercising ROJ-13 AFW Turbine Steam Supply Check Valve Closed Exercising VRR-01 Emergency Diesel Generator Skid-Mounted Check Valve Open Exercising VRR-02 ADV Nitrogen Solenoid Valve Stroke Timing VRR-03 'EC Surge Tank Nitrogen SupplyCheck Valve Closed Exercising "-.

(Deleted duringimplementation ofCheckValve Condition'Monitoring Program per VRR-13) -

VRR-04 SI Pump Room Floor Drain Check Valve Exercising

VRR-05 Downcomer Feedwater Check Valve Closed Exercising. . .. ' . '

'(Deleted' duringimplementation of Check Valve Condition Monitoring Program per VRR:13)

VRR-06 -' Containment Spray Check Valve Open and Closed Exercising .

._'_'_'._-_. :(Dileted during implementation of Check ValvePCondition Monitoing Program per VRR-13) '. "

VRR-07. Containment Sump Discharge Check Valve Open Exercising '- ;: . . .

. -Rby Cbecauseofiiiiii justiicaionfor extreme hardship, perNRCSER dated.

. .^ .'July 8, 1999. :,VRR subsequenly e during mplementation of Check Valve ondition '-';,..

. . 'Monitoring Program per VR.R-13) ' '.- . '; ' .: - - . . -.

VRR-08 SI Check Valve Closed Exercising VRR-09 Verification of Thermal Equilibrium During Safety/Relief Valve Testing VRR-10 Accumulator Volume for Safety/Relief Valve Testing VRR-I I ANII Involvement in Valve Inservice Testing VRR-12 MOV Exercising and Stroke Timing VRR-13 Check Valve Condition Monitoring

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 49 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Pump Relief Request No. 1 (PRR-01)

Essential Auxiliary Feedwater Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

AFA-P01 Essential Auxiliary Feedwater Pump (Turbine-Driven) 3 AFP-00 / D06 AFB-P01 Essential Auxiliary Feedwater Pump (Motor-Driven) 1 3 AFP-00 1B06 Function The essential auxiliary feedwater pumps supply water to the steam generators during an accident. They also can be used to supply feedwater to the steam generators during plant startup and shutdown.

Test Pump flow rate shall be measured and compared with its reference value. (OM-Requirement 6 para. 5.2)

Alternate AFA-POI and AFB-PO1 will be tested at mini-flow conditions during plant Testing operation, but flow rate will not be measured. AFA-POI and AFB-POI will be tested at design flow on a Cold Shutdown frequency, with all Code-required parameters measured.

Basis for There are only two practical flow paths available for testing AFA-POI and Relief AFB-PO1. The primary flow path is into the main feedwater lines to the steam generators. The other flow path is the minimum flow recirculation line that recirculates back to the condensate storage tank. The flow path to the steam generators is equipped with flow instrumentation, but the recirculation line is a fixed-resistance circuit with no provisions for flow indication.

Use of the primary flow path at power would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

AFA-POI and AFB-PO1 are standby pumps. Little degradation is expected during plant power operation when the pumps are idle except for testing.

Testing the pumps at design flow on a Cold Shutdown frequency will provide additional information regarding the condition of the pumps. This information compensates for not measuring flow rate during the quarterly test.

Approval Complies with GL 89-04 Position 9. Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 50 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES I 14 Pump Relief Request No. 2 (PRR-02)

Non-Essential Auxiliary Feedwater Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

AFN-P01 Non-Essential Aux. Feedwater Pump (Motor-Driven) NA AFP-001 / H06 Function The non-essential auxiliary feedwater pump AFN-P I supplies feedwater to the steam generators during plant startup and shutdown. AFN-PO1 is not within the required scope of the IST Program because it is not ASME Code Class 1, 2, or 3, and it does not perform a required function in shutting down the reactor, maintaining the shutdown condition, or mitigating the consequences of an accident. It is included in the IST Program as an augmented component to facilitate testing required by Technical Specification 4.7.1.2(a)(1).

Test Pump flow rate shall be measured and compared with its reference value. (OM-Requirement 6 para. 5.2)

Alternate AFN-PO1 will be tested at mini-flow conditions during plant operation, but flow Testing rate will not be measured.

Basis for There are only two practical flow paths available for testing AFN-PO1. The Relief primary flow path is into the main feedwater lines to the steam generators. The other flow path is the minimum flow recirculation line that recirculates back to the condensate storage tank. The flow path to the steam generators is equipped with flow instrumentation, but the recirculation line is a fixed-resistance circuit with no provisions for flow indication.

Use of the primary flow path at power would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

AFN-POI is a standby pump normally used only during startup. Little degradation is expected during plant power operation when the pump is idle except for testing.

Approval Since AFN-POI is an augmented component, deviations from the Code do not require regulatory approval. This relief request is provided for information and documentation purposes only.

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Charging Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

CHA-P01 . Charging Pump 2 CHP-002 / B03 CHB-PO1 Charging Pump 2 .CHP-002 / D03 CHE-P0l Charging Pump 2 1CHP-002 / G03 Function The charging pumps provide makeup water to the reactor coolant system for chemistry and volume control. They also provide auxiliary spray to the pressurizer.

Test The full-scale range of each analog instrument shall be not greater than three Requirement times the reference value. (OM-6 para. 4.6.1.2(a))

Alternate None. The installed flow instrument, CHB-FI-212, will be used to measure Testing charging pump during inservice testing.

Basis for Each charging pump is a constant-speed, positive displacement pump with a Relief typical flow rate reference value of 43 gpm. The analog charging flow indicator CHB-FI-212 is located in the common discharge line of the three pumps. The full-scale range of CHB-FI-212 is 150 gpm, which exceeds the range requirement of 4.6.1.2(a).

The combined requirements of OM-6 Table I (flow rate accuracy Within 2% of full-scale) and para. 4.6.1.2(a) (full scale range not greater than 3 times the reference value) result in a measurement within 6% of the reference value. 6%

is also the guideline for instrument acceptability provided in NUREG-1482, Paragraph 5.5.1.

The loop accuracy of CHB-FI-212 (based on the square root of the sum of the squares of the inaccuracies of each instrument or component in the loop) is +/-

1.32% of full-scale. When combined with the 150 gpm range of the instrument, which is 3.49 times the reference value, the accuracy of the CHB-FI-212 instrument loop is within 4.7% of the reference value. Therefore, flow indicator CHB-FI-212 meets the combined requirement for measurement accuracy within 6% of the reference value. This accuracy is sufficient to provide an acceptable level of quality and safety.

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999.

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LPSI Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

SIA-POl Low Pressure Safety Injection (LPSI) Pump 2 SIP-O01 / Fl I SIB-POI Low Pressure Safety Injection (LPSI) Pump 2 SIP-OO / BI I Function LPSI pumps SIA-POI and SIB-POI provide low-pressure coolant injection of borated water into the reactor coolant system under accident conditions. They also provide shutdown cooling flow post-accident and during normal reactor startup and shutdown.

Test Where system resistance cannot be varied, flow rate and pressure shall be Requirement determined and compared to their respective reference value. (OM-6, Para.

5.2(c))

Alternate LPSI pumps SIA-POI and SIB-POI will be tested at mini-flow conditions Testing during plant operation per OM-6 para. 5.2(c), but flow rate will not be measured. SIA-POI and SIB-POl will be tested at design flow on a Cold Shutdown frequency, with all Code-required parameters measured and evaluated per OM-6 para. 5.2(d).

Basis for During normal power operation, the LPSI pumps cannot develop sufficient Relief discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, LPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction of the design flow. The installed flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy is not sufficient to meet OM-6 accuracy requirements. A larger recirculation flowpath is available; however, it uses the same flow instrument as the minimum-recirculation line.

The LPSI pumps are normally used to provide shutdown cooling flow during shutdown operations, and occasionally for recirculating the refueling water tank when the unit is at power. Little degradation is expected during power operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.

Approval Complies with GL 89-04 Position 9. Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pacie 53 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Pump Relief Request No. 6 (PRR-06)

HPSI Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

SIA-P02 High Pressure Safety Injection (HPSI) Pump 2 SIP-001 /ElI SIB-P02 High Pressure Safety Injection (HPSI) Pump 2 SIP-001 / Al I I Function The HPSI pumps provide high-pressure coolant injection of borated water into the reactor coolant system under accident conditions. They also provide flow for long-term cooling and flushing to prevent boron precipitation.

Test Where system resistance cannot be varied, flow rate and pressure shall be Requirement determined and compared to their respective reference value. (OM- 6, Para. 5.2(c))

Alternate HPSI pumps SIA-P02 and SIB-P02 will be tested at mini-flow conditions Testing during plant operation per OM-6 para. 5.2(c), but flow rate will not be measured. SA-P02 and SIB-P02 will be tested at design flow on a Refueling frequency, with all Code-required parameters measured and evaluated per OM-6 para. 5.2(d).

Basis for During normal power operation, the HPSI pumps cannot develop sufficient Relief discharge pressure to overcome RCS pressure and allow flow through the safety injection headers. Thus, during quarterly testing, .HPSI flow is routed through a minimum flow recirculation line to the refueling water tanks. The minimum-flow recirculation flowpath is a fixed resistance circuit containing a flow-limiting orifice capable of passing only a small fraction of the design flow. The installed flow instrumentation (permanently mounted ultrasonic flowmeter) has only limited capability, and its accuracy is not sufficient to meet OM-6 accuracy requirements.

During cold shutdown conditions, full flow operation of the HPSI pumps to the RCS is restricted to preclude RCS pressure transients that could result in exceeding Technical Specification pressure-temperature limits (LTOP).

The HPSI pumps are standby pumps. SIB-P02 is used only occasionally to recharge the safety injection tanks. Little degradation is expected during power operation. Thus, the alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.

Approval Complies with GL 89-04 Position 9. Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 54 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Pump Relief Request No. 7 (PRR-07)

Charging Pump Vibration Measurement Pump ID Pump Description Code Drawing!

Class Coord.

CHA-POI Charging Pump 2 CHP-002 / B03 CHB-P01 Charging Pump 2 lCHP-002 / D03 CHE-POI Charging Pump 2 CHP-002 / G03 Function The charging pumps provide makeup water to the reactor coolant system for chemistry and volume control. They also provide auxiliary spray to the pressurizer.

Test The frequency response range of the vibration measuring transducers and their Requirement readout system shall be from one-third minimum pump rotational speed to at least 1000 Hz. (OM-6 para. 4.6.1.6)

Alternate The instrumentation used to measure charging pump vibration will have a Testing frequency response range from 1.6 hz to 100 hz.

Basis for The charging pumps are positive-displacement pumps with a constant running Relief speed of 199 rpm (equivalent to 3.3 Hz). Compliance with paragraph 4.6.1.6 would require using vibration instrumentation with a frequency response range of 1.1 Hz to at least 1000 Hz.

Two different vibration probes are used at PVNGS, one with a frequency response range of 4.9 Hz to 1000 Hz, and a special low-speed probe with a frequency response range of 1.6 Hz to 100 Hz. The low-speed probe was purchased specifically for charging pump testing when the IST requirement for frequency response was one-half pump speed to at least pump shaft rotational speed. This probe does not meet the lower bound or the upper bound of the Code-required frequency response range.

The charging pump bearings are oil-lubricated, sleeve type journal bearings.

Because of the high reciprocating loads, the charging pump bearings are not susceptible to oil whirl, which is the primary failure mode that causes vibration below pump shaft rotational speed. There are no other failure mechanisms that manifest themselves with elevated vibration levels in the range of one-third to one-half pump shaft rotational frequency; all the remaining failure modes cause vibration at or above the pump speed. Experience with these pumps confirms this fact.

Therefore vibration instrumentation with a frequency response range above 1.6 Hz is acceptable for monitoring vibration of the charging pumps.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 55 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES l 14 The low-speed probe is sensitive to vibration frequencies up to 30 times the running speed of the charging pumps. This is sufficient to identify bearing degradation, mechanical rubs, and other pump problems producing high-frequency vibrations. These pumps are not susceptible to degradation mechanisms that would manifest themselves in the 100-1000 Hz range but not in the vibration range being monitored (1.6-100 Hz). Therefore, use of the higher frequency vibration probe provides no benefit. The charging pumps are monitored for other symptoms of degradation under the PVNGS Predictive Maintenance Program (see PRR-08 for a description of the PVNGS Predictive Maintenance Program). Therefore use of this probe during charging pump inservice testing will provide an acceptable level of quality and safety.

Approval "Hardship" alternative authorized pursuant to 10 CFR 50.55a(a)(3)(ii) per NRC SER dated July 8, 1999.

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Smooth-Running Pumps Pump ID Pump Description Code Drawing / Coord.

Class AFA-P01 Essential Auxiliary Feedwater Pump (Turbine-Driven) 3 AFP-00 / D06 AFB-POl Essential Auxiliary Feedwater Pump (Motor-Driven) 3 AFP-O01 / B06 AFN-P01 Non-Class Auxiliary Feedwater Pump (Motor-Driven) N AFP-001 I H06 CTA-P01 Condensate Transfer Pump 3 CTP-001 I C05 CTB-P01 Condensate Transfer Pump 3 CTP-00 B05 ECA-P01 Essential Chilled Water Circulation Pump 3 ECP-001 I B08 ECB-P01 Essential Chilled Water Circulation Pump 3 ECP-001 I B04 ENVA-P01 Essential Cooling Water Pump 3 EWP-001 / E06 EWB-P01 Essential Cooling Water Pump 3 EWP-001 I E02 PCA-PO1 Spent Fuel Pool Cooling Pump 3 PCP-001 / D15 PCB-POI Spent Fuel Pool Cooling Pump 3 PCP-001 / B15 SIA-POI Low Pressure Safety Injection (LPSI) Pump 2 SIP-001 / Fl I SIB-P01 Low Pressure Safety Injection (LPSI) Pump 2 SIP-001 / BI I SIA-P02 High Pressure Safety Injection (HPSI) Pump 2 SIP-001 / El SIB-P02 High Pressure Safety Injection (HPSI) Pump 2 SIP-001 /Al I SIA-P03 Containment Spray Pump 2 SIP-001 / HI I SIB-P03 Containment Spray Pump 2 SIP-001 / Cl SPA-P01 Essential Spray Pond Pump 3 SPP-001 Sh. I / C04 SPB-P01 Essential Spray Pond Pump 3 SPP-001 Sh. I / C07 Function Various Test If deviations fall within the alert range of Table 3, the frequency of testing Requirement specified in para. 5.1 shall be doubled until the cause of the deviation is determined and the condition corrected. If deviations fall within the required action range of Table 3, the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected. (OM-6 para.

6.1)

Alternate Vibration parameters that would have reference values < 0.05 ips may be Testing considered "smooth-running". The Alert and Required Action values for these parameters will be determined as if their reference value is 0.05 ips; that is, the Alert Range will be > 0.125 ips to 0.3 ips, and the Required Action Range will be > 0.3 ips.

In addition to the Code-mandated monitoring, these pumps are monitored under the PVNGS Predictive Maintenance Program. This program includes the following:

Spectrum band monitoring

Bearing acceleration monitoring (on ball and roller bearings only)

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Bearing oil analysis (for oil lubricated bearings)

Motor Current Signature analysis (for all but the smallest motors)

If any of these parameters are outside normally expected ranges, an evaluation will be performed and appropriate corrective actions will be taken.

Before being treated as "smooth-running" under this relief request, each candidate pump will be evaluated to verify that testing performed under the provisions of this relief request will not prevent the detection of significant pump degradation.

Basis for The repeatability of pump vibration readings at PVNGS is in the range of 0.05 Relief ips due to hydraulic flow noise in this amplitude range and the repeatability of the vibration instruments. When vibration velocities are less than 0.05 ips, changes have been shown to be non-significant.

At vibration velocities less than 0.05 ips, flow noise and instrument repeatability can significantly affect reference values. Candidates for "smooth-running" status will be analyzed per OM-6 paragraph 4.3 to verify that use of this relief request will not prevent the detection of significant pump degradation.

For displacement reference values less than 0.5 mils, it is noted that the Section XI code in effect for the first interval IST Program (1980 Edition, Winter 1981 Addenda) sets the Alert Range at >1.0 mil and the Required Action Range at

>1.5 mil. This implies a minimum reference value of 0.5 mils, which is equivalent to 0.047 ips for 1800 rpm pumps and 0.094 ips for 3600 rpm pumps.

The effective reference values proposed for smooth-running pumps are roughly equal to the implied Section Xl reference values for 1800 rpm pumps and more conservative than the implied reference values for 3600 rpm pumps. Without this relief request, the Alert Ranges for some smooth running pumps will be reduced by a factor of 10.

The PVNGS Predictive Maintenance (PdM) Program is part of the Preventive Maintenance (PM) Program described in UFSAR section 17.2.3.11.1.6. The PM Program was developed using RCM, NPRDS, EPRI, and INPO guidelines as well as factoring in PVNGS site-specific experience and regulatory requirements. The PM Program and PdM activities are controlled by plant procedures. Each of these pumps has a maintenance plan documented in the PM Program which describes the PM and PdM activities performed on that pump. The performance of the system associated with each of these pumps is monitored and compared to performance criteria under the PVNGS Maintenance Rule Program. This ensures the continued effectiveness of the PM program to minimize component failures and maintain or improve system performance (balance availability and reliability).

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 58 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 The PVNGS Predictive Maintenance Program uses vibration analysis, lubricant analysis, and infrared thermographic analysis as appropriate, to predict the need for maintenance so that equipment can be reworked prior to failure. The components included in this program include those considered important to safe and reliable plant operation, including all the pumps in the 1ST Program. The intervals for monitoring are based on manufacturer's recommendations, maintenance history, cost effectiveness, and experience. Although the monitoring, analyses, database, and software used in the Predictive Maintenance Program do not fall under the PVNGS Quality Program, the Predictive Maintenance Program still provides valuable information for assuring the operational readiness of smooth-running pumps.

The vibration analysis program monitors the vibration of rotating machinery. In addition to the vibration at pump bearings, the vibration of the driver (turbine or motor) bearings are also collected and trended. Analyzed parameters and methods include vibration velocity, bearing acceleration, bearing high frequency detection, and spectral analysis.

The lubricant analysis program samples lubricants and analyzes them to identify degradation or negative trends. Most testing is performed at the on-site lubrication laboratory, where capabilities include wear debris, chemical composition, and lubrication cleanliness analysis.

In both the vibration monitoring and lubricant analysis programs, recently acquired data is compared with previous data to detect any indicated degradation of equipment condition. If degradation indicates the reliability of operating equipment may be negatively affected, or if acceptance criteria is no longer being met, appropriate corrective action is taken. Corrective action may include: continuing trending of the degraded condition, if the condition is not considered to be immediately threatening to the equipment and can be corrected during a time window convenient to plant operation; additional testing or monitoring to confirm the suspected degraded condition; inspection and repair of the equipment as necessary; changes to preventive maintenance procedures or schedules; or design changes.

PVNGS expends considerable resources on preventive and predictive maintenance. One result of these efforts are pumps that run very smoothly. For example, many pumps in the PVNGS IST Program would currently be candidates for "smooth-running" status under PRR-08, as shown in the table below. To continue to impose Code-mandated Alert and Required Action values on smooth-running pumps unnecessarily penalizes PVNGS for achieving this high level of performance.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 59 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES l 14 Typical Vibration Pump Reference Values (ips)

Auxiliary Feedwater 0.12 - 0.21 Condensate Transfer

0.0044 - 0.0556 Essential Chilled Water

0.0075 - 0.0496 Essential Cooling Water

0.00295 - 0.0931 Low Pressure Safety Injection

0.0343 - 0.319 High Pressure Safety Injection 0.0667 - 0.296 Containment Spray 0.086 - 0.141 Spent Fuel Pool Cooling

0.0295 - 0.11 Essential Spray Pond

0.0018-0.0316

Candidates for "smooth-running" status under PRR-08 Approval Partially authorized pursuant to i 0 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999. Alternatives to OM-6 para. 5.1 and 6.1 were authorized, but relief from para. 4.3 was denied. Accordingly, reference to OM-6 para. 4.3 has been deleted from the "Test Requirements" section of PRR-08.

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Evaluation as Corrective Action Pump ID Pump Description Code Drawing I Class Coord.

Various This is a general request for relief Various Various Function Various Test If deviations fall within the alert range of Table 3, the frequency of testing Requirement specified in para. 5.1 shall be doubled until the cause of the deviation is determined and the condition corrected. If deviations fall within the required action range of Table 3, the pump shall be declared inoperable until the cause of the deviation has been determined and the condition corrected. (OM-6 para.

6.1)

Alternate In cases where a pump's test parameters fall within either the alert or action Testing required ranges and the pump's continued use at the changed values is supported by an analysis, a new set of reference values may be established. The supporting analysis will include verification of the pump's operational readiness and an evaluation of test data that verifies that the subject pump is not expected to fall below the minimum required performance level in the periods between testing. The analysis will include both pump and system level operational readiness evaluations, description of the cause of the change in pump performance, and an evaluation of the trends indicated by the available test and maintenance data. The results of this analysis will be documented in the record of tests.

Basis for The 1995 Edition of ASME OM Code provides an alternate concept of Relief corrective action should a pump's performance enter the action required range.

Specifically, Paragraph ISTB 6.2.2 permits an analysis of the pump and establishment of new reference values. This can avoid premature maintenance of a pump that is subject to expected continual and gradual deterioration over time while operating at a level where it is fully capable of reliably performing its designated safety function.

By using the test requirements of the 1995 Code edition, PVNGS can reduce the frequency of unnecessary pump maintenance with essentially no adverse affect on plant safety since the new Code requirements are equivalent to (or better than) the requirements of the 1988 addenda.

In addition, by expanding this capability to pumps that are in the alert range, frequent and unnecessary testing can be avoided. Note that more frequent testing of pumps is a degrading mechanism for these pumps. This also is required to avoid unnecessary plant shutdown for pumps that are tested at cold

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 61 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X01 l Revision COMPONENT TABLES 1 14 shutdown should a pump enter the alert range during such testing.

The proposed alternative testing is consistent with the response to Question 3.3.2 in the "Summary of Public Workshops Held in NRC Regions on Inspection Procedure 73756".

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Passe 62 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 l Revision COMPONENT TABLES l 14 Pump Relief Request No. 10 (PRR-10)

ANII Involvement in Pump Inser ice Testing Pump ID Pump Description Code Drawing /

Class Coord.

Various l This is a general request for relief Various Various Function Various Test Duties of the Authorized Nuclear Inspector include:

Requirement (c) verifying that the visual examinations and tests on pumps and valves have been completed and the results recorded. (Preface to Section XI)

It is the duty of the Inspector:

(1) to perform a detailed review of the inspection plan (IWA-2400) prior to the start of preservice inspection and each inspection interval ... Review of the inspection plan shall cover any features of the inspection plan which are affected by the requirements of this Division, as applicable, and shall include the following:

(a) examination categories and items (b) test and examination requirements (e) inservice test quantities (g) test frequency (2) to review any revisions to the inspection plan during the preservice inspection or the inspection interval; (3) to submit a report to the Owner documenting review of the items identified in (1) and (2) above; (IWA-21 10(a))

It is the duty of the Inspector to verify that the inservice tests required on pumps, valves, and component supports (IWF, IWP, and IWV) have been completed and the results recorded. (IWA-2 110(c))

Alternate The PVNGS Pump and Valve IST Program will be developed and implemented Testing in accordance with applicable regulations, codes, quality assurance requirements, plant procedures, and Authorized Inspection Agency requirements. ANII involvement with the Pump and Valve IST Program will not be required.

Basis For In the nuclear industry, the Authorized Nuclear Inservice Inspectors (ANIs)

Relief have historically been involved primarily with the development and implementation of the Inservice Inspection Program. Involvement with the Inservice Testing Program has been minimal. This is consistent with the experience and training of the individual inspectors, who are well schooled in the areas of plant construction and repair. Recognizing this, ASME recently published the OMb-1997 addenda to the ASME/ANSI OM Code, which

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pane 63 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X1I01 Revision COMPONENT TABLES l 14 includes a change that eliminates all involvement of the ANII in the development and implementation of the Inservice Testing Program.

Each revision to the PVNGS IST Program is subjected to a comprehensive review process including technical reviews, management reviews, and a review under 10 CFR 50.59. In addition, quality assurance evaluations and self-assessments periodically monitor the implementation of the IST Program.

These measures, along with the constant attention by highly qualified individuals tasked with program implementation ensure that the previous duties of the inspector are routinely and adequately performed and the intent of the ASME Code is maintained. Thus the proposed alternative testing provides an acceptable level of quality and safety.

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999.

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Containment Spray Pump Flow Rate Measurement Pump ID Pump Description Code Drawing /

Class Coord.

SIA-P03 Containment Spray (CS) Pump 2 SIP-O /H I SIB-P03 Containment Spray (CS) Pump 2 SIP-O / C I Function CS pumps SIA-P03 and SIB-P03 deliver borated water to the containment spray headers, providing containment cooling and pressure control during accident conditions. The CS pumps can also be lined up to provide flow for shutdown cooling.

Test The full-scale range of each analog instrument shall be not greater than three Requirement times the reference value. (OM-6, para. 4.6.1.2(a))

Where system resistance cannot be varied, flow rate and pressure shall be determined and compared to their respective reference value. (OM-6, para.

5.2(c))

Alternate CS pumps SIA-P03 and SIB-P03 will be tested at mini-flow conditions during Testing plant operation per OM-6 para. 5.2(c), but flow rate will not be measured. SIA-P03 and SIB-P03 will be tested at design flow during cold shutdown periods when the pump is used for shutdown cooling. During design flow testing, all Code-required parameters will be measured and evaluated per OM-6 para.

5.2(d).

Basis for The containment spray pumps are single stage, vertical pumps normally lined Relief up to the containment spray headers. The "rumble range" of the pumps, where operation is unstable due to flow oscillations, is approximately 1800-2800 gpm.

Each CS pump has two possible recirculation flowpaths: a minimum-flow recirculation flowpath with a flow-limiting orifice capable of passing only a small fraction of the design flow, and a larger flowpath used mainly for RWT mixing. All the flowpaths pass through the flowmeter just downstream of the CS pump discharge. The recirculation flowpaths also pass through a common recirculation line flowmeter. The CS pump discharge flowmeter is an orifice-type analog flowmeter with a range of 0-5000 gpm. The common recirculation line flowmeter is a permanently-mounted ultrasonic flowmeter which has only limited capability. The accuracy of the ultrasonic flowmeter is not sufficient to meet OM-6 accuracy requirements or to be relied upon for determining pump operability.

The normal containment spray flow path cannot be used for testing the CS pumps without spraying down the inside of the containment building and risking damage to important equipment. The RCS injection portion of the

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 65 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 lRevision COMPONENT TABLES 14 shutdown cooling flow path cannot be used for testing during power operation because the CS pumps are unable to develop sufficient discharge pressure to overcome RCS pressure.

The flow rate through the pump discharge flowmeter must be at least 1634 gpm to satisfy the full-scale range requirement of OM-6 para. 4.6.1.2(a). The flow capacity of the minimum-flow recirculation line is well below 1634 gpm. The larger recirculation flowpath is capable of carrying more than 1634 gpm, but routine surveillance testing at flow rates above this value is not practical because of the pump rumble range (1800-2800 gpm). Testing in or near the rumble range is not practical because of the potential for equipment damage.

Testing at flow rates above the rumble range (> 2800 gpm) is not practical because flow velocities in the recirculation piping would exceed the design criteria.

The CS pumps are standby pumps. Little degradation is expected during power operation. The alternate testing will adequately monitor these pumps to ensure continued operability and availability for accident mitigation.

Approval Complies with GL 89-04 Position 9. Relief granted pursuant to 10 CFR 50.55a(f(6)(i) per NRC SER dated July 8, 1999.

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Auxiliary Feedwater Pump Suction Check Valve Open Exercising Valve ID Valve Description Code Category Drawing I Coord.

AFAV007 AFW Pump AFA-P01 Suction 3 C AFP-001 / D07 Header Check Valve I I I AFBV022 AFW Pump AFB-P01 Suction 3 C AFP-001 / C07 I _______________ Header Check Valve Function These check valves open to provide flowpaths from the Condensate Storage Tank to the respective auxiliary feedwater pump. They have no specific safety function in the closed position.

Alternate These valves will be partial-stroke exercised open during quarterly pump Testing testing via the minimum flow recirculation lines, and full-stroke exercised open during cold shutdown periods.

Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising at power is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

This cold shutdown justification is similar to CSJ-1 in the first interval IST Program.

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AFW Pump Discharge Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

Class _

AFAV137 Essential AFW Pump AFA-P0I 3 C AFP-00 / D06 I _______________ Discharge Check Valve I_

I AFBVI38 Essential AFW Pump AFB-P01

-Discharge Check Valve _ _ _ _

C I AFP-001 / C06 Function These check valves open to provide flowpaths from the respective essential auxiliary feedwater pumps to the auxiliary feedwater supply headers. They have no specific safety function in the closed position.

Alternate These valves will be partial-stroke exercised open during quarterly pump Testing testing via the minimum flow recirculation lines, and full-stroke exercised open during cold shutdown periods.

Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising at power is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

This cold shutdown justification is similar to CSJ-1 in the first interval IST Program.

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AFV Discharge Header Check Valve Open and Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

AFAV015 AFW Pump AFA-P01 Discharge 3 C AFP-001 /E05 I__ _ Header Check Valve I I I AFBV024 AFW Pump AFB-PO1 Discharge 3 C AFP-001 /C05 Header Check Valve Function These check valves open to provide flowpaths from the respective auxiliary feedwater pump to the auxiliary feedwater headers. They close so that if one pump fails to start after an auxiliary feedwater actuation signal (AFAS), flow from the operating pump is not diverted back through the idle pump.

Alternate These valves will be full-stroke exercised open and exercised closed during Testing cold shutdown periods.

Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising at power is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock I fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

Closure testing these valves can be performed by two methods. The normal method is to operate the opposite pump with the pumps lined up for parallel operation to the steam generators while the pump associated with the valve being tested is idle. Performing this test at power is not practical because it would inject cold auxiliary feedwater into the main feedwater lines, with the temperature perturbations and undesirable consequences described above. Alternately, a source of pressurized water could be introduced between the check valve and the normally-closed downstream flow control and header isolation valves.

Performance of this test would require draining the AFW pump recirculation lines and entry into an extended LCO for the duration of the test (approx. 4-6 hours).

During power operation these valves remain closed and cannot be opened due to the lack of an available discharge path. Thus, it is extremely unlikely that a valve would be discovered in the open position during periodic closure testing.

Therefore quarterly closure testing is considered impractical because the risk of performing this testing outweighs the anticipated benefits.

This CSJ is similar to CSJ-2 in the first interval IST Program.

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AFW Header Check Valve Open Exercising Valve ID l Valve Description j Code AFAVOs9 j Category Drawing / Coord.

H AFAV079 AFW Header Check Valve C AFP-001 / E02 AFBV080 AFW Header Check Valve 2 C AFP-001 / C02 Function These check valves open to provide flowpaths from the auxiliary feedwater pump headers to the respective feedwater line and steam generator. They have no specific safety function in the closed position.

Alternate These valves will be full-stroke exercised open during cold shutdown periods.

Testing Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising at power is not practical because this would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

This cold shutdown justification is similar to CSJ-3 in the first interval IST Program.

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LPSI and CS Pump Discharge Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ __ _ __ _ _ _ _ _ _ _ _ Cla s s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SIAV434 LPSI Pump Discharge Check Valve 2 C SIP-00I / F09 SIBV446 LPSI Pump Discharge Check Valve 2 C SIP-001 / B09 SIAV485 CS Pump Discharge Check Valve 2 C SIP-001 / H10 SIBV486 CS Pump Discharge Check Valve 2 C SIP-001 GIO Function Open for pump discharge flowpath for shutdown cooling or low pressure safety injection. These valves close to prevent reverse flow, but closure is not a required safety function.

Alternate These valves will be partial-stroke exercised open quarterly, and full-stroke Testing exercised open during cold shutdown periods when the associated pump is used for shutdown cooling.

Basis These are simple check valves with no external means of exercising or for determining disc position. During power operation, the valves can be part-stroke exercised open with flow when the associated pump is operated via the 6" recirculation line. Full-stroke exercising during power operation is not practical because pump discharge pressure is not sufficient to overcome RCS pressure, and there is not a recirculation flow path capable of handling maximum accident condtion flow as required by Generic Letter 89-04 Position 1. The valves will be full-stroke exercised open at cold shutdown when the associated pump is used for shutdown cooling.

This cold shutdown justification is similar to CSJ-29 and CSJ-30 in the first interval IST Program.

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Auxiliary Pressurizer Spray Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.

CHBHV0203 Auxiliary Pressurizer SprayI B CHP-001 / HIO Isolation Valve CHAHV0205 Auxiliary Pressurizer Spray I B CHP-001 / H I Isolation Valve CHEV43 1 Auxiliary Pressurizer Spray Check 1 C CHP-001 / G09

_____ __ __ __ Valv e _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Function These valves open to provide flowpaths from the charging pump discharge header to the pressurizer for auxiliary pressurizer spray. Valves CHBHV0203 and CHAHV0205 close for spray/pressure control. Check valve CHEV43 is not relied upon to perform a specific safety function in the closed direction.

Alternate The auxiliary pressurizer spray isolation valves will be full-stroke exercised Testing open and closed during cold shutdown. Stroke time testing and fail-safe testing will be performed in conjunction with exercise tests.

The auxiliary pressurizer spray check valve will be full-stroke exercised open during cold shutdown.

Basis Opening either of the auxiliary pressurizer spray isolation valves during power operation initiates spray flow to the pressurizer. This could cause an RCS pressure transient that could adversely affect plant safety and lead to a plant trip. In addition, the pressurizer spray piping and nozzle would be subjected to unnecessary thermal shock. Opening these valves at power is considered impractical for these reasons.

CHEV431 is a simple check valve with no external means of exercising or for determining disc position. Thus testing in the open direction requires a flow test. In order to full-stroke exercise this valve, either CHBHV0203 or CHAHV0205 must be fully opened. As discussed above, routinely opening these valves during plant operation is impractical. Therefore testing this valve is also considered impractical at power.

This cold shutdown justification is similar to CSJ-6 in the first interval IST Program.

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Boration Flowvpath Isolation Valve Exercising Valve ID Valve Description Code Category Drawing Coord.

CHEHV0532 Isolation for Refueling Water Tank 3 B CHP-002 / E16 I__________I____ to Boric Acid Makeup Pumps I I I Function CHEHV0532 is normally open to provide an emergency boration flowpath to the charging pump suction header. It is closed to prevent sluicing water from the spent fuel pool to the Refueling Water Storage Tank (RWT) during emergency boration when using the spent fuel pool as a borated water source.

Alternate CHEHV0532 will be full-stroke exercised open and closed during cold Testing shutdown. Stroke time testing and fail-safe testing will be performed in conjunction with the exercise tests.

Basis CHEHV0532 could be closed at power for testing, however this would isolate the common line from the RWT to multiple boration flowpaths. This is considered impractical, because CHE-HV532 is non-redundant and failure to re-open would render multiple boration flowpaths inoperable.

This justification is consistent with the guidelines on deferring testing provided in NUREG- 1482, Paragraphs 3.1.1 (1).

This CSJ is similar to CSJ-4 in the first interval IST Program, except that Valve CHEHV0536 has been deleted from this CSJ due to the implementation of ASME OM Code Case OMN-l per VRR-12.

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Letdown Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing I Coord.

Class CHBUVO515 Reactor Coolant Letdown Isolation I B CHP-OO1 / H15 Valve CHAUVO516 Reactor Coolant Letdown Inbd. I A CHP-OO I/ G15 Isolation Valve CHBUVO523 Reactor Coolant Letdown Otbd. I A CHP-OO1 / F13 Isolation Valve Function These valves open to provide a flowpath for reactor coolant letdown flow -

non-safety function. CHBUVO5 15 and CHAUVOS 16 close to secure letdown on a Safety Injection Actuation signal (SIAS). CHAUVO516 and CHBUVO523 close on a Containment Isolation Actuation signal (CIAS) signal for containment isolation.

Alternate These valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise test.

Basis Closing any of these valves isolates the letdown line from the RCS. During power operation, this would result in undesirable pressurizer level transients with the potential for a plant trip. If a valve failed to reopen, then a plant shutdown may be required.

This cold shutdown justification is similar to CSJ-8 in the first interval IST Program.

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Containment Refueling Purge Valve Closed Exercising Valve ID Valve Description Code Category Drawing Coord.

Valve l ID ~~~~~~~Classlll CPAUVO002A Containment Purge Supply Otbd. 2 A CPP-00 / D06 Isolation Valve CPAUVO002B Containment Purge Exhaust Inbd. 2 A CPP-001 / E03 Isolation Valve CPBUVO003A Containment Purge Supply Inbd. 2 A CPP-001 / D05 Isolation Valve CPBUVO003B Containment Purge Exhaust Otbd. 2 A CPP-001 / E02 Isolation Valve I Function These 42" valves open to provide flowpaths for containment ventilation during shutdown periods - non-safety function. They are required to close on a containment purge isolation actuation signal (CPIAS) during a loss of shutdown cooling or a fuel handling accident in containment. They are locked closed for containment isolation during power operation (Modes 1-4).

Alternate These valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing will be performed in conjunction with exercise test.

Basis Per PVNGS Technical Specification 3.6.1.7a, these valves must remain closed during operation. These valves are administratively maintained in the closed position at all times when the plant is operating in Modes 1-4. The valves are not capable of closing against accident pressure. Thus they are not required to operate (stroke closed) during operational periods. Due to the large size of these valves and the potential for damage as a result of frequent cycling, it is not prudent to operate them more than is absolutely necessary.

This cold shutdown justification is similar to CSJ-1 I in the first interval IST Program.

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RCP Seal Injection Containment Isolation Valve Closed Exercising I ---

Valve ID CHNV835 l

I Valve Description I

Reactor Coolant Pump Seal Injection Check Valve l Code I

2 j

I Category j ~ ~~~~~~~Class AC

_ _ _ I_

I Drawing / Coord.

CHP-OO I / G03 Function This valve opens to provide a flowpath from the charging pump discharge header to the reactor coolant pump (RCP) seals - non-safety function. It closes for containment isolation.

Alternate CHNV835 will be exercised closed during cold shutdown.

Testing Basis During power operation when the RCPs are running, these valves are normally open to supply seal water to the RCPs. Seal injection is necessary for the proper operation of the RCP seals. Closing these valves for testing would necessitate isolating seal injection flow and risking damage to the seals. Stopping the RCPs at power for the sole purpose of valve testing is not considered practical because the reactor will trip.

It is noted that paragraph 3.1.1.4 of NUREG-1482 permits deferral of tests that require shutdown of RCPs until refueling outages. However, since PVNGS typically secures RCPs during cold shutdown outages, this test will be performed at cold shutdown.

This cold shutdown justification is similar to CSJ-10 in the first interval IST Program, except that Valve CHBHV0255 was deleted from this CSJ due to the implementation of ASME OM Code Case OMN-I per VRR-12.

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Instrument Air Containment Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

IAAUVO002 Instrument Air Supply To 2 A IAP-003 / G07 Containment Isolation Valve IIII IAEV0021 Instrument Air Supply To 2 AC IAP-003 / G05 I______________ Containment Isolation Check Valve Function These valves open to provide a flowpath for instrument air to the containment

- non-safety function. They close to provide containment isolation.

Alternate IAAUVO002 will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.

IAEV0021 will be full-stroke exercised closed during cold shutdown periods.

Basis Closing either of these valves during power operation isolates operating air to important equipment within the containment building, including the pressurizer spray control valves and letdown isolation valves. This would, in turn, risk pressurizer level and pressure transients with a potential for a plant trip. If IAAUVO002 were to fail to re-open, an expedited plant shutdown would be required. It is also noted that closure testing of IAEV0021 requires containment entry.

This cold shutdown justification is similar to CSJ-13 and CSJ-14 in the first interval IST Program.

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Reactor Head Vent and Pressurizer Vent Valve Exercising Valve ID Valve Description Code Category Drawing I Coord.

Class Reactor VeseVnVlv_______/__

RCAHV0101 Reactor Vessel Vent Valve 2 B RCP-001 / G15 RCBHV0 102 Reactor Vessel Vent Valve 2 B RCP-001 G15 RCAHV0103 Pressurizer Vent Valve 2 B RCP-001 / G14 RCBHV0105 Reactor Coolant System Common 2 B RCP-001 /G13 Vent Valve To RDT RCAHV0106 Reactor Coolant System Common 2 B RCP-001 / G13 Vent Valve To Containment RCBHV0108 Pressurizer Vent Valve 2 B RCP-001 / G13 RCBHV0109 Pressurizer Vent Valve 2 B RCP-001 / G13 Function These valves open to remotely vent non-condensible gasses from the reactor vessel and/or pressurizer steam space. They can also be used to depressurize the RCS. They close for reactor coolant system integrity.

Alternate These valves will be full-stroke exercised open and closed during cold Testing shutdown periods. Stroke time testing and fail-safe testing will be performed in conjunction with the exercise testing.

Basis These valves are administratively controlled in the keylocked closed position with the power supply disconnected to prevent inadvertent operation. Since these are reactor coolant system boundary valves, failure of a valve to close or significant leakage following closure can result in a loss of coolant in excess of the limits imposed by the Technical Specifications leading to a plant shutdown. Furthermore, if a valve were to fail open or valve indication fail to show the valve returned to the fully closed position after exercising, it is likely that a plant shutdown would be required. Note also that Technical Specifications require that these valves be closed in Modes 1-4.

This justification is consistent with the guidelines for deferring testing provided in NUREG-1 482, Paragraph 3.1.1.

This cold shutdown justification is similar to CSJ-16 in the first interval IST Program.

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Turbine-Driven AFW Pump Steam Supply Check Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ _ _ __ _ __ _ __ __ _ _ _ _ _ _ __ _ __ _ __ _ __ _ __ _ __ _ C la ss _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SGAV0043 Main Steam Supply From SG #1 3 C SGP-001, Sh. I / E12 To AFW Pump AFA-POI Check Valve l SGAV0044 Main Steam Supply From SG #2 3 C SGP-001, Sh. / C12 To AFW Pump AFA-P01 Check Valve Function These valves open to provide flowpaths for steam from the steam generators to turbine-driven Auxiliary Feedwater Pump, AFA-P01. They close to prevent blowdown of the opposite steam generator after a main steam line break when an AFAS opens the associated isolation valve.

Alternate These valves will be partial-stroke exercised open and exercised closed during Testing quarterly pump minimum-flow recirculation testing. Full-stroke exercising open will be performed during pump full-flow testing at cold shutdown.

Basis Full-stroke exercising of these valves would require operation of Auxiliary Feedwater Pump AFA-POI at full rated capacity. This is not practical during power operation because it would inject cold auxiliary feedwater into the main feedwater lines. The resulting temperature perturbations could lead to unnecessary thermal shock / fatigue damage to the feedwater piping and steam generators, and the cooldown of the reactor coolant system could cause undesirable reactivity variations and power fluctuations.

This cold shutdown justification is similar to CSJ-28 in the first interval IST Program.

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Feedwater Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

______________ Class ______ __________

SGBUVO130 Inbd. FWIV to SG #I Downcomer 2 B SGP-002 / GIl SGBUVO132 Inbd. FWIV to SG #1 Economizer 2 B SGP-002 / E12 SGBUVO135 Inbd. FWIV to SG #2 Downcomer 2 B SGP-002 / Cl I SGBUVO137 Inbd. FWIV to SG #2 Economizer 2 B SGP-002 / A12 SGAUVOI72 Otbd. FWIV to SG #1 Downcomer 2 B SGP-002 / G12 SGAUVO174 Otbd. FWIV to SG #1 Economizer 2 B SGP-002 / E12 SGAUVOI75 Otbd. FWIV to SG #2 Downcomer 2 B SGP-002 / C12 SGAUVO177 Otbd. FWIV to SG #2 Economizer 2 B SGP-002 / A12 Function The main feedwater isolation valves (FWIVs) are normally open during steaming operations to provide flowpaths for main feedwater flow to the steam generators - non-safety function. They close to isolate and maintain the integrity of the steam generators and to secure feeding a faulted steam generator in the event of a steam leak inside containment.

Alternate Each of these valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with the exercise testing.

Basis Closing any of these valves isolates the associated feedwater header. During power operation, isolation of a feedwater header would require a significant power reduction and could result in unacceptable steam generator level and reactor power transients with the potential for a plant trip.

The downcomer isolation valves do not have partial-stroke capability, however the economizer isolation valves are capable of partial stroke exercising. Part-stroke exercising is not considered practical because of the risk of full closure. This risk was recognized by NUREG-1432, Vol 1, Rev.

1, "Standard Technical Specifications - Combustion Engineering Plants Specifications", which states that "MFIVs should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power" as the basis for the 18-month test frequency specified by SR 3.7.3.1. Nevertheless, part-stroke exercising continues to be performed as an augmented test to satisfy System and Maintenance Engineering's desire to periodically exercise the 4-way pilot valves to confirm continued operability.

This cold shutdown justification is similar to CSJ-17 and CSJ-26 in the first interval IST Program.

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Main Steam Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ __ _ __ _ _ _ _ _ _ _ _ Cla s s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SGEUV0170 Main Steam Isolation Valve From 2 B SGP-001, Sh. I /GI0 Steam Gen. #1 SGEUVOI71 Main Steam Isolation Valve From 2 B SGP-001, Sh. I DIO0 Steam Gen. #2 SGEUVOl80 Main Steam Isolation Valve From 2 B SGP-001, Sh. /F10 Steam Gen. #1 SGEUVO81 Main Steam Isolation Valve From 2 B SGP-001, Sh. I /Bl10 Steam Gen. #2 1 Function These valves are normally open during steaming operations to provide flowpaths for steam flow to the main turbine generators and associated auxiliaries - non-safety function. They close to isolate and maintain the integrity of the steam generators.

Alternate Each of these valves will be full-stroke exercised closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.

Basis Closing any of these valves isolates the associated steam header. During power operations, isolation of a main steam header would require a significant power reduction and could result in unacceptable steam generator level and reactor power transients with the potential for a plant trip.

The main steam isolation valves are capable of partial stroke exercising. Part-stroke exercising is not considered practical because of the risk of closure.

This risk was recognized by NUREG-1432, Vol 1, Rev. 1, "Standard Technical Specifications - Combustion Engineering Plants Specifications",

which states that "MSIVs should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power" as the basis for the 18-month test frequency specified by SR 3.7.2.1.

Nevertheless, part-stroke exercising continues to be performed as an augmented test to satisfy System and Maintenance Engineering's desire to periodically exercise the 4-way pilot valves to confirm continued operability.

This cold shutdown justification is similar to CSJ-25 in the first interval IST Program.

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HPSI Header Check Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ __ _ __ _ __ _ __ __ __ _ _ _ _ _ __ _ __ _ __ _ __ _ __ _ __ _ C la s s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SIEVI 13 High Pressure Safety Injection 2 C SIP-002 / F14 Pump Header Check Valve SIEV123 High Pressure Safety Injection 2 C SIP-002 / F12 Pump Header Check Valve SIEV133 High Pressure Safety Injection 2 C SIP-002 / F07 Pump Header Check Valve SIEV143 High Pressure Safety Injection 2 C SIP-002 / F04 Pump Header Check Valve I Function These valves open to provide flowpaths from the high pressure safety injection headers to the reactor coolant system. They close to prevent flow diversion during LPS1 operation.

Alternate Each of these valves will be verified closed during cold shutdown periods.

Testing Tests performed during cold shutdown will not necessarily include pre-test open exercising.

Basis These are simple check valves with no external means of exercising nor for determining disk position. Thus they can only be verified closed by developing a differential pressure across the valve disc and then determining reverse-direction leakage. During power operation the LPSI pump could be operated to pressurize the downstream piping thus providing a pressure differential across the respective valve, however, pressurizing the safety injection headers can unseat downstream check valves V540, V541, V542, and V543. Per TS SR 3.4.15.1, this would then require leak testing of these valves which would entail containment entry. Thus, closure verification at power is considered impractical.

As discussed in NUREG-1482, Appendix A, Question Group 24, closure testing of valves with safety functions in both directions requires that the valves be opened and then verified to close. It is impractical to exercise these valves open except during refueling outages, as discussed in the ROJ for open exercising. Since these valves can be verified closed more frequently (cold shutdown) than the valves can be opened (refueling), closure verification will be performed at cold shutdown without opening the valve. This strategy is consistent with the Current Considerations under Question Group 24.

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LPSI Header Check Valve Open and Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

SIEV1 14 Low Pressure Safety Injection 2 C SIP-002 / F13 Pump Header Check Valve SIEV124 Low Pressure Safety Injection 2 C SIP-002 / Fl I Pump Header Check Valve SIEV134 Low Pressure Safety Injection 2 C SIP-002 / F06 Pump Header Check Valve SIEV144 . Low Pressure Safety Injection 2 C SIP-002 / F04 Pump Header Check Valve I I Function These valves open to provide flowpaths from the low pressure safety injection headers to the reactor coolant system for safety injection and shutdown cooling. They close to prevent flow diversion during HPSI operation.

Alternate Each of these valves will be full-stroke exercised open and exercised closed Testing during cold shutdown periods.

Basis These are simple check valves with no external means of exercising nor for determining disc position. Part-stroke exercising open at power through the safety injection check valve test line test via valves SIEUVO618, 628, 638, and 648 is not practical, because this would unseat check valves STEV540, V541, V542, and V543, requiring a containment entry to perform the leak test required by TS SR 3.4.15.1. Full-stroke exercising open at power is not possible because the discharge pressure of the LPSI pumps is not sufficient to overcome RCS pressure. The valves can be full-stroke exercised open at cold shutdown while the shutdown cooling system is in operation.

These valves can only be verified closed by developing a differential pressure across the valve disc and then determining reverse-direction leakage. During power operation the HPSI pump could be operated to pressurize the downstream piping thus providing a pressure differential across the respective valve, however, pressurizing the safety injection headers can unseat downstream check valves SIEV540, V541, V542, and V543. Per TS SR 3.4.15.1, this would then require leak testing of these valves which would entail containment entry. Thus, closure verification at power is considered impractical.

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Nitrogen Containment Isolation Check Valve Closed Exercising Valve ID l Valve Description t _______

Code J Category

~~~~Class__I__

Drawing / Coord.

GAEVOI5 Nitrogen Supply To Containment 2 AC GAP-OO I / E02

_ _ _ _ I Check Valve I I I Function This check valve opens to provide a flowpath for nitrogen to several non-critical components inside containment - non-safety function. It closes for containment isolation.

Alternate This valve will be verified closed during cold shutdown periods. Closure Testing testing will not necessarily include pre-test open exercising.

Basis These are simple check valves with no external means of exercising or for determining disc position. Thus the only way of verifying valve closure is by performing a reverse flow test. Performing this test on this valve requires containment entry. Containment entry for routine inservice testing is considered impractical during power operations.

Since this valve performs a safety function only in the closed position, exercising open before closure verification is not required. This testing satisfies Code requirements and is consistent with the discussion in NUREG-1482, Appendix A, Question Group 24.

This cold shutdown justification is similar to CSJ-13 in the first interval IST Program.

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Hydrogen Return Containment Isolation Check Valve Closed Exercising Valve ID Valve Description Code Category Drawing I Coord.

______________ Class ______ __________

HPAV002 Hydrogen Sample/Recombiner 2 AC HPP-001 / F15 Return To Containment Check Valve HPBV004 Hydrogen Sample/Recombiner 2 AC HPP-001 / C15 Return To Containment Check Valve Function These check valves open to provide air return flowpaths to the containment from the recombiners and the post-LOCA hydrogen monitors. They close for containment isolation.

Alternate These valves will be verified to close during cold shutdown periods.

Testing Basis These are simple check valves with no external means of exercising or for determining disc position. Thus the only way of verifying valve closure is by performing a reverse flow test. Performing this test on these valves requires plugging the line which would require operator action to restore in the event of an accident during testing. Performing this test also requires containment entry. Containment entry for routine inservice testing is considered impractical during power operations.

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- COMPONENT TABLES 14 Cold Shutdown Justification No. 26 (CSJ-26)

SIT Vent Valve Exercising Valve ID Valve Description Code Category Drawing I Coord.

_ _ _ __ _ _ _ Safety_________________________

. nn20Class _ _ __ 5 SIAHV0605 Safety Inj. Tank 2A Vent Valve 2 B SIP-002 / F15 SIAHV0606 Safety Inj. Tank 2 Vent Valve 2 B SIP-002 / F12 SIAHV0607 Safety Inj. Tank IA Vent Valve 2 B SIP-002 / F07 SIAHV0608 Safety Inj. Tank lB Vent Valve 2 B SIP-002 / F04 SIBHV0613 Safety Inj. Tank 2A Vent Valve 2 B SIP-002 / E15 SIBHV0623 Safety Inj. Tank Vent Valve 2 B SIP-002 / El2 SIBHV0633 Safety Inj. Tank I AVent Valve 2 B SIP-002 / E07 SIBHV0643 Safety Inj. Tank l B Vent Valve 2 B SIP-002 E04 Function These valves are normally closed to ensure the integrity of the associated safety injection tank (SIT) so that the required nitrogen overpressure is maintained. They are opened to reduce the nitrogen pressure in the SITs during plant depressurization to preclude nitrogen injection into the RCS.

Alternate Each of these valves will be exercised open and closed during cold shutdown Testing periods. Stroke time testing and fail-safe testing will be performed in conjunction with exercise testing.

Basis These valves are normally closed during power operation. Plant technical specifications require that power be removed from the valves, and that the SIT nitrogen cover gas pressure be maintained within the required range.

Exercising a valve during operation would render the associated SIT inoperable if the cover gas pressure were reduced below the required range.

A valve failing open during testing would completely depressurize the SIT and result in an expedited plant shutdown.

This cold shutdown justification is similar to CSJ-22 in the first interval IST Program.

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Shutdown Cooling Suction Isolation Valve Exercising Valve ID Valve Description Code Category Drawing I Coord.

_______________ Class ______

SICUVO653 Shutdown Cooling Suction Inboard I A SIP-002 / D03 Containment Isolation Valve SIDUVO654 Shutdown Cooling Suction Inboard I A SIP-002 / DIO Containment Isolation Valve Function These valves are normally closed to ensure the integrity of the reactor coolant system and to provide containment isolation. They are opened during plant cooldown to initiate shutdown cooling.

Alternate Each of these valves will be full-stroke exercised open and closed during cold Testing shutdown periods. Stroke time testing will be performed in conjunction with the exercise testing.

Basis These valves provide pressure barriers between the reactor coolant system pressure and the lesser rated shutdown cooling piping systems. As an installed safety feature they are provided with electrical interlocks that prevent them from being opened when pressurizer pressure is greater than 400 psig. Although this interlock can be overridden, routine operation of these valves with a large differential pressure across the seats is considered impractical due to the risk of damage to the seating surfaces of the valves.

This cold shutdown justification is similar to CSJ-24 in the first interval IST Program, except that Valves SIAHV065 1, SIBHV0652, SIAUV0655 and SIB-UV0656 have been deleted from this CSJ due to the implementation of ASME OM Code Case OMN-I per VRR-12..

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Normal Chilled Water Containment Isolation Check Valve Closed Exercising Valve ID WCEV039 I_ _

Valve Description I

Chilled Water Supply To Containment Check Valve I Code 2

j I

Category j ~~~~~~~Class_

AC

_ I__

I Drawing / Coord.

WCP-00 / E05 I

Function This valve is normally opened to supply cooling water to the containment -

non-safety function. It closes for containment isolation.

Alternate This valve will be verified closed during cold shutdown periods. Closure Testing testing will not necessarily include pre-test open exercising.

Basis This is a simple check valve with no external means of exercising nor for determining disc position. Closure verification must be performed by developing a differential pressure across the disc and measuring reverse flow.

Performing these tests requires containment entry. Containment entry for routine inservice testing is considered impractical during power operations.

In addition, exercising this valve to the closed position requires an extended shutdown of the primary containment cooling system. This could cause the containment temperature to exceed the technical specification limit for air temperature and hamper testing activities inside containment.

Since this valve performs a safety function only in the closed position, exercising open before closure verification is not required. This testing satisfies Code requirements and is consistent with the discussion in NUREG-1482, Appendix A, Question Group 24.

This cold shutdown justification is similar to CSJ-13 in the first interval IST Program.

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RMW Supply to RDT Containment Isolation Check Valve Closed Exercising Valve ID } Valve Description

.__ ChckVavetoR nbarC Code Class Category Drawing / Coord.

CHNV494 Reactor Makeup Water Supply 2 AC CHP-003 / E15 I 1 ~~Check Valve to RDT Inboard CIV II Function Opens to supply RMW to the reactor drain tank - not a safety function.

Closes for containment isolation.

Alternate This valve will be verified closed during cold shutdown periods. Closure Testing testing will not necessarily include pre-test open exercising.

Basis This is a simple check valve with no external means of exercising nor for determining disc position. Closure verification must be performed by developing a differential pressure across the disc and measuring reverse flow.

Performing this tests requires a containment entry. Containment entry for routine inservice testing is considered impractical during power operations.

Since this valve performs a safety function only in the closed position, exercising open before closure verification is not required. This testing satisfies Code requirements and is consistent with the discussion in NUREG-1482, Appendix A, Question Group 24.

This cold shutdown justification is similar to CSJ-32 in the first interval IST Program.

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NC to Containment Check Valve Closed Exercising Valve ID NCEVI 18 l

4 ____

Valve Description Nuclear Cooling Water Supply To I1 Containment Check Valve Code 4~~~~~~

2 I

Category

~~Class_

AC II Drawing / Coord.

NCP-003 / E06 Function This valve opens to provide a flowpath for cooling water to important equipment inside the containment - non-safety function. It closes to provide containment isolation.

Alternate These valves will be full-stroke exercised closed during cold shutdown Testing periods.

Basis This is a simple check valve with no external means of exercising nor for determining disc position. Closure verification must be performed by developing a differential pressure across the disc and measuring reverse flow.

Performing this test requires securing cooling water flow to important equipment within the containment building, including the reactor coolant pumps (RCPs). It is impractical to secure this cooling water flow for an extended period with the RCPs running without endangering the reactor coolant pumps and motors. Thus testing at power is impractical because it would require the unnecessary shutdown of all of the reactor coolant pumps.

Testing at cold shutdown is practical because the RCPs are typically not running during cold shutdown periods.

It is noted that paragraph 3.1.1.4 of NUREG-1482 permits deferral of tests that require shutdown of RCPs until refueling outages. However, since PVNGS typically secures RCPs during cold shutdown outages, this test will be performed at cold shutdown.

Closure testing will not include pre-test open exercising, since the valve is known to be open during power operation prior to the closure verification.

This testing satisfies Code requirements and is consistent with the discussion in NUREG-1482, Appendix A, Question Group 24.

This cold shutdown justification is similar to CSJ-15 in the first interval IST Program.

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SI Header Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

_________ l_SafetyIjectionH ader_Chec__xACClass _ SIP-002_/_ _ l SIEV540 Safety Injection Header Check 1 AC SIP-002 / Cl3 Valve SIEV541 Safety Injection Header Check I AC SIP-002 / CII

________________ S e I cValve eader Check lACSIP-002 _/ __

SIEV542 Safety Injection Header Check I AC SIP-002 / C06 V alve__ _ _ __ _ _ _ _

SIEV543 Safety Injection Header Check I AC SIP-002 C04

_ _ __ _ __ _ _ __ _V

_ _ a lv e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Function These valves open to provide flowpaths from the safety injection headers to the reactor coolant system for safety injection and shutdown cooling. They close to isolate the safety injection system from the reactor coolant system.

Alternate Each of these valves will be full-stroke exercised open during cold shutdown.

Testing Basis These are simple check valves with no external means of exercising nor for determining disc position. Part-stroke exercising open at power through the safety injection check valve test line test via valves SIEUVO618, 628, 638, and 648 is not practical, because because unseating the check valves requires a containment entry to perform the leak test required by TS SR 3.4.15. 1. The valves can be full-stroke exercised by directing LPSI flow to the RCS, but this is not possible at power because the discharge pressure of the LPSI pumps is not sufficient to overcome RCS pressure.

This cold shutdown justification is similar to CSJ-31 in the first interval IST Program.

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RCP Seal Bleed-Off Isolation Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

CHBUVO505 Reactor Coolant Pump Seal Bleed- 2 A CHP-002 / H13 off Otbd. Isolation Valve CHAUVO506 Reactor Coolant Pump Seal Bleed- 2 A CHP-002 /IH14 I_______________ off Inbd. Isolation Valve Function These valves are normally open during power operation to provide a flowpath for seal bleed-off from the reactor coolant pumps (RCPs) - non-safety function. They close for containment isolation.

Alternate These valves will be exercised closed during cold shutdown periods. Stroke Testing time testing and fail safe testing will be performed in conjunction with exercise testing.

Basis These air-operated valves are electrically interlocked so that they cannot be closed when any of the reactor coolant pumps are in operation. Closing either of these valves during RCP operation would interrupt bleed-off flow from the RCP seals and could result in damage to the seals. Thus testing these valves at power would require the unnecessary shutdown of all of the reactor coolant pumps.

It is noted that paragraph 3.1.1.4 of NUREG-1482 permits deferral of tests that require shutdown of RCPs until refueling outages. However, since PVNGS typically secures RCPs during cold shutdown outages, this test will be performed at cold shutdown.

This cold shutdown justification is similar to CSJ-7 in the first interval IST Program.

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Boration Flow Path Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

__ _ _ __ _ _ _ _ _ _ _ Cla s s _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

CHAV177 Boration Flowpath Check Valve To 2 C CHP-002 / B07 I___ _Charging Pump Suction I_ I I I CHAV190 Emerg. Boration Flowpath Check12 C CHP-002 / A07 Valve To Charging Pump Suction __

Function These check valves open to provide emergency boration flowpaths from the boration header (CHAV 177) or via gravity drain directly from the Refueling Water Tank (RWT) (CHAV190). They have no specific safety function in the closed position.

Alternate These check valves will be part-stroke exercised open during cold shutdown Testing and full stroke exercised open during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining disc position, thus, testing these valves in the open direction requires system flow. Since there is no recirculation flowpath capable of full flow (68 gpm per TRM TSR 3.1.101.2), the only practical flowpath is into the charging pump suction header. This would introduce highly concentrated boric acid solution from the RWT into the RCS via the charging pumps. The rapid insertion of negative reactivity during plant operation would cause a RCS cooldown and depressurization which could result in an unscheduled plant trip or safety injection system actuation.

During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS. The radioactive waste processing system would also be overburdened by the large amounts of RCS coolant that would require processing to decrease the boron concentration at startup.

Since the boron concentration is normally increased to a limited extent for shutdown margin prior to reaching cold shutdown, a part-stroke exercise of these valves could be performed at that time.

This refueling outage justification is similar to CSJ-4 in the first interval IST Program.

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RWT Outlet Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ __ _ __ _ _ _ _ _ _ _ _ Cla ss _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

CHAV306 Refueling Water Tank Outlet 2 C CHP-002 / C13

_______________ Check Valve CHBV305 Refueling Water Tank Outlet 2 C CHP-002 / B15 I _______________ Check Valve _

Function These check valves open to provide flowpaths from the Refueling Water Tank (RWT) to the suctions of the safety injection and containment spray pumps.

They close during post-accident recirculation cooling to prevent backflow of water from the containment sump to the RWT.

Alternate These valves will be part-stroke exercised open during quarterly testing of the Testing safety injection pumps via the pumps' minimum flow circuit, and full-stroke exercised open during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining obturator position. Thus, testing these valves in the open direction requires system flow. The various pump mini-flow lines are capable of part-stroke testing only since their size precludes passing full accident flow through these valves. Full-stroke exercising these valves to the open position requires injection into the RCS via the simultaneous operation of the containment spray and LPSI pumps in the train. During plant operation this is precluded because neither the containment spray nor the LPSI pumps can develop sufficient discharge pressure to overcome RCS pressure. At cold shutdown there is no available reservoir in the reactor coolant system to accept the injected water, and the shutdown cooling system cannot provide sufficient flow back to the RWT. Also, the excessive quantities of boric acid injected during such testing would seriously hamper the ensuing startup.

Therefore, the only practical opportunity for full-flow testing these valves is during refueling outages when the reactor head has been removed and RWT inventory is used to fill the refueling cavity.

This refueling outage justification is similar to VRR-6 in the first interval IST Program.

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BAMP Discharge Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

CHNVI54 Boric Acid Make-up Pump CHN- 3 C CHP-002 / B13

_______________ PO2A Discharge Check Valve I II CHNVI55 Boric Acid Make-up Pump CHN- 3 C CHP-002 / B 13

________________ P02B Discharge Check Valve ______

Function The boric acid makeup pump (BAMP) discharge check valves open to allow flow through the idle BAMPs as part of the emergency boration flowpaths (Ref. TRM TLCO 3.1.101). They have no specific safety function in the closed position.

Alternate These check valves will be part-stroke exercised open quarterly and full-Testing stroke exercised open during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining disc position. Testing these valves in the open direction requires system flow. The boric acid makeup pumps can be operated to open these valves, however there is no installed flow instrumentation in the BAMP recirculation line. Therefore the only practical instrumented flowpath is into the RCS via the charging pumps. During plant operation, the rapid insertion of negative reactivity resulting from the introduction of highly concentrated boric acid solution to the RCS would result in a RCS cooldown and de-pressurization, which could cause an unscheduled plant trip or possible safety injection system actuation.

During cold shutdown, the introduction of excess quantities of boric acid into the RCS is undesirable from the aspect of maintaining proper plant chemistry and the inherent difficulties that may be encountered during the subsequent startup due to over-boration of the RCS. The radioactive waste processing system would also be overburdened by the large amounts of RCS coolant that would require processing to decrease the boron concentration at startup.

This refueling outage justification is similar to CSJ-4 in the first interval IST Program.

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HPSI Header Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

______________ Class__________________

SIEVI 13 High Pressure Safety Injection 2 C SIP-002 /F14 Pump Header Check Valve SIEV123 High Pressure Safety Injection 2 C SIP-002 / F12 Pump Header Check Valve SIEV133 High Pressure Safety Injection 2 C SIP-002 / F07 Pump Header Check Valve SIEV143 High Pressure Safety Injection 2 C SIP-002 / F04 Pump Header Check Valve I Function These valves open to provide flowpaths from the high pressure safety injection (HPSI) headers to the reactor coolant system. They close to prevent flow diversion during LPSI operation.

Alternate These valves will be full-stroke exercised open during each refueling outage.

Testing Basis These are simple check valves with no external means of exercising or for determining disc position. Part-stroke exercising open at power through the safety injection check valve test line test via valves SIEUVO618, 628, 638, and 648 is not practical, because this would unseat check valves SIEV540, V541, V542, and V543, requiring a containment entry to perform the leak test required by TS SR 3.4.15.1. Full-stroke exercising at power is not possible because the discharge pressure of the HPSI pumps is not sufficient to overcome RCS pressure. Exercising at cold shutdown is not practical because low-temperature over-pressure concerns preclude directing HPSI flow to the RCS.

This refueling outage justification is similar to VRR-28 in the first interval IST Program.

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HPSI Pump Discharge Check Valve Open and Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

SIAV404 High Pressure Safety Injection2 C SIP-001 /F06 Pump I Discharge Check Valve __I SIBV405 High Pressure Safety Injection 1 2 C SIP-0OITB04 Pump 2 Discharge Check Valve _

Function These valves open to provide flowpaths from the high pressure safety injection (HPSI) pumps to the safety injection headers and thence to the reactor coolant system. They close to prevent flow diversion through an idle HPSI pump during HPSI operation.

Alternate These valves will be full-stroke exercising open and exercised closed during Testing each refueling outage. The valve will be exercised open prior to closure verification.

Basis These are simple check valves with no external means of exercising or for determining disc position. Full-stroke exercising at power is not possible because the discharge pressure of the HPSI pumps is not sufficient to overcome RCS pressure. Part-stroke exercising open at power through the safety injection check valve test line test via valves SIEUVO618, 628, 638, and 648 is not practical, because this would unseat check valves SIEV540, V541, V542, and V543, requiring a containment entry to perform the leak test required by TS SR 3.4.15.1. Exercising at cold shutdown is not practical because low-temperature over-pressure (LTOP) concerns preclude directing HPSI flow to the RCS.

Since these valves have safety functions in both the open and closed positions, closed exercising requires the valve to be exercised to the open position and then be verified to close. Exercising open is not practical except at refueling as described above.

Verification of closure without opening the valve is not practical more frequently than refueling because closure verification requires a reverse-flow test, which is performed by connecting a pressure source downstream of the check valve and determining reverse flow. The opposite-train HPSI pump can be used as the pressure source via the cross-connect valves, but this is not practical at power since cross-connecting the two trains of HPSI renders both trains inoperable. It is also not practical at cold shutdown, because any leakage through the HPSI header isolation valves could challenge the LTOP protection system. Using another pressurized water source via a downstream

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 97 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES l 14 test connection is not practical at power or cold shutdown, because the risk of routinely placing the HPSI system in this configuration and the burden of setting up the test equipment outweighs the benefits of testing.

This refueling outage justification is consistent with the provisions of NUREG-1482 section 4.1.4, which states that the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage. It is also consistent with the requirements for exercising check valves with a safety function in both positions by exercising the valve open and then verifying that it closes discussed in NUREG-1482, Appendix A, Question Group 24, and with the guidelines for deferring valve testing given in NUREG-1482 section 3.1.1.

This refueling outage justification is similar to VRR-28 in the first interval IST Program.

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HPSI Long-Term Recirculation Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

Class SIAV522 HPSI Long-Term Recirc. Check I AC SIP-002 / C02 Valve SIAV523 HPSI Long-Term Recirc. Ctmt. I AC SIP-002 / F02 Isolation Check Valve SIBV532 HPSI Long-Term Recirc. Check I AC SIP-002 / BIO Valve SIBV533 HPSI Long-Term Recirc. Ctmt. I AC SIP-002 / F09 Isolation Check Valve Function These valves open to provide flowpaths from the high pressure safety injection headers to the reactor coolant system for hot leg injection. They close to isolate the safety injection system from the reactor coolant system.

Alternate These valves will be full-stroke exercised open during each refueling outage.

Testing Basis These are simple check valves with no external means of exercising or for determining disc position. Exercising with flow can be accomplished with the HPSI pumps (or the charging pumps via cross-tie valves) to the RCS.

SIAV523 and SIBV533 can also be part-stroke exercised using the SIT fill/drain line via valves SIBUV0322 and SIBUVO332. Exercising at power is not practical because unseating the valves would require a containment entry to perform the leak test required by TS SR 3.4.15.1; containment entry is not considered practical for quarterly surveillance testing. Exercising at cold shutdown is not practical because of the potential for a low-temperature over-pressure (LTOP) event, which could challenge the LTOP relief valves, violate RCS temperature/pressure limits, or damage equipment.

This refueling outage justification is similar to VRR-35 in the first interval IST Program.

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Regenerative Heat Exchanger Inlet Check Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

_ _ _ _ _ __ __ _ __ _ _ __ _ _ __ _ __ Cla ss _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _

CHEVM70 Charging to Regenerative Heat 2 AC CHP-001 / F15 Exchanger Inlet Inboard Containment Isolation Check Valve Function Valve opens for charging flowpath to support boration and auxiliary pressurizer spray. Closes for containment isolation.

Alternate This valve will be verified closed during each refueling outage. Closure Testing testing will not necessarily include open exercising immediately prior to the closure verification.

Basis This is a simple check valve with no external means of exercising nor for determining disc position. Testing in the closed direction requires a reverse flow test. The valve alignment for this test requires isolating and draining a portion of the charging line. Performing this test at power or cold shutdown is not practical because it renders auxiliary pressurizer spray and multiple boration flowpaths out of service for an extended period of time, requires several entries into high radiation areas inside containment, and violates containment integrity, with entry into numerous LCOs. During testing, manual realignment of numerous valves would be required to restore the system to an operable status if the system functions became necessary during inservice testing.

As discussed in NUREG-1482, Appendix A, Question Group 24, closure testing of valves with safety functions in both directions requires that the valves be opened and then verified to close. This valve is exercised open with normal charging flow during power operation. This satisfies the code requirement for verifying the valve is open prior to the closure verification.

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Safety Injection Pump Suction Flovpath Check Valve Closed Exercising Valve ID Valve Description l Code Category Drawing / Coord.

_ _ _ _ _ 06 _ R _ W_ T _ _ _ _ _ _ _ [hec kssV alv __ e 2 C /Cla CHAV306 RWT Outlet Check Valve 2 C CHP-002 / C13 CHBV305 RWT Outlet Check Valve 1 2 C ICHP-002 B15 Function CHAV306 and CHBV305 open to provide flowpaths from the Refueling Water Tank (RWT) to the suctions of the safety injection and containment spray pumps. They close during post-accident recirculation cooling to prevent backflow of water from the containment sump to the RWT.

Alternate These valves will be exercised to the open position and then verified to close Testing during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining disc position. Testing in the closed direction involves a reverse flow test requiring set up of hoses, gauges, and other test equipment. The test also requires a valve alignment that renders the complete safety injection train (LPSI, HPSI, and containment spray) inoperable, with entry into multiple LCOs for an extended period of time. During this test, manual realignment of numerous valves would be required to restore the system to an operable status if the system functions became necessary during inservice testing. Therefore testing is considered impractical during power operation and cold shutdown.

This justification is consistent with the guidelines on extension of test intervals to refueling outage for check valves verified closed by leak testing provided in NUREG-1482, section 4.1.4.

The valves will be exercised to the open position and then verified to close as required for check valves with safety functions in both directions per NUREG-1482, Appendix A, Question Group 24.

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LPSI and CS Pump Suction Check Valve Open Exercising Valve ID Valve Description Code Category Drawing / Coord.

______________ Class ______ __________

SlAV157 Containment Spray Pump Suction 2 C SIP-OI G13 Line Check Valve SIBV158 Containment Spray Pump Suction 2 C SIP-O /13 Line Check Valve SIBV200 LPSI Pump Suction Line Check 2 C SIP-OO I / B12 Valve SIAV201 LPSI Pump Suction Line Check 2 C SIP-001I /F13 I______ _____ _Valve I I Function These valves open to provide flowpaths to the suctions of the respective pumps.

Alternate These check valves will be part-stroke exercised open quarterly and full-Testing stroke exercised open during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining disc position. During power operation, the valves can be part-stroke exercised open with flow when the associated pump is operated via the recirculation lines. Full-stroke exercising during power operation is not practical because pump discharge pressure is not sufficient to overcome RCS pressure, and there is not a recirculation flow path capable of routinely handling maximum accident condition flow as required by Generic Letter 89-04 Position 1. Full-stroke exercising during cold shutdown while on shutdown cooling is not practical because these valves are not in the shutdown cooling lineup (the shutdown cooling lines tap into the suction lines downstream from these valves). These valves can be full-stroke exercised open during refueling outages while the reactor refueling pool is being filled from the RWT by the LPSI and CS pumps.

This refueling outage justification is similar to VRR-30 in the first interval IST Program.

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Shutdown Cooling Isolation Valve Bonnet Vent Check Valve Open and Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

______________ Class ______ __________

SIAVAIO Shutdown Cooling Isolation Valve 2 C SIP-002 / G03 Bonnet Vent Check Valve SIBVAI5 Shutdown Cooling Isolation Valve 2 C SIP-002 / G10 Bonnet Vent Check Valve SIAV997 Shutdown Cooling Isolation Valve I C SIP-002 / E03 Bonnet Vent Check Valve SIBV998 Shutdown Cooling Isolation Valve I C SIP-002 / D10 Bonnet Vent Check Valve Function These valves open to provide flowpaths from the bonnet area of S1AUV0655, SIBUV0656, SICUV0653, and SIDUV0654 to prevent pressure locking of the valves. They close for containment isolation.

Alternate Each of these valves will be full-stroke exercised open and exercised closed Testing during each refueling outage.

Basis These are simple check valves with no external means of exercising or for determining disc position. The only way to exercise the valves open is by initiating flow through the valves with an external pressure source via test fittings installed for that purpose. The only way to verify valve closure is to perform a reverse-flow test in the same manner. The shutdown cooling isolation valve associated with the check valve is rendered inoperable during testing.

Both the open and closure tests require the use of test equipment, whose setup makes testing impractical during power operation and cold shutdown outages.

This justification is consistent with the provisions of NUREG-1482 section 4.1.4, which states that the NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage. In addition, performing this testing on SIAV997 and SIBV998 requires containment entry. Containment entry for routine inservice testing is considered impractical during power operations.

This refueling outage justification is similar to CSJ-34 in the first interval IST Program.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 103 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 1 14 Refueling Outage Justification No. 13 (ROJ-13)

AFW Turbine Steam Supply Check Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

Class AFAV096 Aux Steam Supply Check Valve to 3 C AFP-OO I / G02 AFW Turbine SGEV887 Turbine-Driven AFW Pump Steam 3 C SGP-001 / D12 Supply Warmup Line Check Valve SGEV888 Turbine-Driven AFW Pump Steam 3 C SGP-001 / C13 Supply Warmup Line Check Valve _

Function AFAV096 opens to provide auxiliary steam to the steam-driven auxiliary feedwater pump (not a safety-related function). The valve closes and remains closed to prevent steam diversion through the aux steam system from affecting pump performance.

SGEV887 and SGEV888 open during the turbine-driven auxiliary feedwater pump start sequence to clear any residual condensation and to warm up the steam lines to prevent the pump from overspeeding and tripping. The warmup line check valves close to prevent spurious opening of the solenoid-operated warmup line isolation valves SGAUVO134A and SGAUVOI38A due to pressure under the seat after a main steam line break, which would result in flow diversion that could cause the pump to overspeed.

Alternate These valves will be exercised closed during each refueling outage.

Testing Basis These are simple check valves with no external means of exercising or for determining disc position. The only way of verifying valve closure is by performing a reverse flow test. Performing this test involves the setup and use of hoses, gauges, and other test equipment. NUREG-1482 section 4.1.4 states that "The NRC has determined that the need to set up test equipment is adequate justification to defer backflow testing of a check valve until a refueling outage".

It is noted that performing this test at power would render the turbine-driven auxilary feedwater pump inoperable for the duration of the test (approximately 1-3 hours). Testing at power also involves potential hazards to test personnel when venting the steam systems and connecting /

disconnecting the test equipment. Although these factors are not sufficient to justify test deferral by themselves, they were considered along with the need for test equipment when the determination was made to perform this test on a refueling outage frequency.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 104 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Reviion COMPONENT TABLES l 14 Valve Relief Request No. 1 (VRR-O1)

Emergency Diesel Generator Skid-Mounted Check Valve Open Exercising Valie ID Valve Description Code Category Drawing / Coord.

___________________________ Class ______

DGAV317 EDG Engine-Driven Jacket Water 3 C DGP-00 I Sh. 4 / F06 Circ Pump Discharge Check Valve DGAV318 EDG Motor-Driven Jacket Water 3 C DGP-001 Sh. 4 / D06 Circ Pump Discharge Check Valve DGAV364 Pre-Lube Pump and Heater Check 3 C DGP-001 Sh. 3 / C06 Valve DGBV417 Engine-Driven Jacket Water Circ 3 C DGP-001 Sh. 4/ F02 Pump Discharge Check Valve DGBV418 Motor-Driven Jacket Water Circ 3 C DGP-001 Sh. 4 / D02 Pump Discharge Check Valve DGBV464 Pre-Lube Pump and Heater Check 3 C DGP-001 Sh. 3 / C02 Valve Function These check valves on the emergency diesel generator (EDG) skid open for jacket water flow and lube oil flow when the EDG is starting or running.

Test Check valves shall be exercised nominally every 3 months, except as Requirement provided by Paragraph 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5. (OM-10 para.

4.3.2)

Alternate These check valves will be tested during periodic EDG testing performed in Testing accordance with plant Technical Specifications; All valves will be tested at least once per quarter. Acceptable valve operation will be verified by successfully meeting the starting and running acceptance criteria for the EDG.

Basis For These check valves were purchased as part of the EDG skid and are mounted Relief on the skid. They are simple check valves with no external means of exercising or for determining disc position. Thus, testing these valves in the open direction requires establishing maximum required accident condition flow through the valve and verifying, by measurement, that the required flow is attained. Due to system design there is no flowpath available with suitable installed instrumentation capable of measuring flow through these valves.

Current plant Technical Specifications require test starting the EDG every 31 days. During testing, each redundant starting subsystem is tested on a rotating basis to ensure that a failure in one starting subsystem is not masked by operation of the other starting subsystem. The EDG must start and attain proper speed, frequency, and voltage within 10 seconds to be considered a successful test. Valve malfunction or degradation will reduce EDG starting and running capability. Therefore testing the EDG is adequate since EDG

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 105 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES R 14 testing adequately tests these skid-mounted valves.

The provisions of this relief request are consistent with NUREG-1482 section 3.4, and para. ISTC 1.2(c) of OMa-1996.

Approval Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 106 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Valve Relief Request No. 2 (VRR-02)

ADV Nitrogen Solenoid Valve Stroke Timing Valve ID Valve Description Code Category Drawing / Coord.

_ __ __ _ _ _ _ _ _ _ _ _ Cla s s_ _ _ _ _ _ _ _ _ _ _

SGBPV0306A ADV Nitrogen Solenoid Valve 3 B SGP-00I Sh.2 / F5 SGBPV0306B ADV Nitrogen Solenoid Valve 3 B SGP-OO ISh. 2 / E5 SGAPV0313A ADV Nitrogen Solenoid Valve 3 B . SGP-OO ISh. 2/C5 SGAPV0313B ADV Nitrogen Solenoid Valve 3 B SGP-001 Sh.2 / H5 Function These valves are normally closed to isolate the normal atmospheric dump valve (ADV) actuation system (instrument air) from the nitrogen backup system - not a safety function. They open on low instrument air header pressure to supply nitrogen from the accumulators to the ADV.

Test The limiting value(s) of full-stroke time of each power-operated valve shall be Requirement specified by the Owner. (OM-10 para. 4.2.1.4(a))

The stroke time of all power-operated valves shall be measured to at least the nearest second. (OM-10 para. 4.2.1.4(b))

Alternate The ADV nitrogen solenoid valves will be exercised during quarterly testing Testing of the associated ADV nitrogen backup system. The ADV nitrogen solenoid valves will not be individually stroke time tested. Operational readiness of the solenoid valves will be verified by acceptable exercising and stroke timing of the ADV when actuated by the nitrogen backup system.

Basis For Each ADV has a nitrogen backup system that can be used to actuate the ADV Relief if instrument air is not available. The solenoid valves are simple solenoid-operated valves that automatically open to enable the nitrogen backup system when low pressure is sensed in the instrument air header. There are no hand switches for manual operation of the valves, and no means of visually determining valve position. Stroke timing these valves is not possible without lifting leads or using other intrusive testing equipment, which would render the ADV inoperable for the duration of the test. Therefore stroke timing these valves is not considered practical.

The solenoid valves have no specific time in which they must actuate to fulfill their safety function. Solenoid valve malfunction or degradation will reduce ADV stroking capability. The ADV must stroke properly within the required stroke time to be considered a successful test. Testing the ADV is adequate to verify the operational readiness of the solenoid valves.

The provisions of this relief request are consistent with the guidance provided

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pane 107 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 in NUREG-1482 section 3.4 on testing component subassemblies, and and with para. ISTC 1.2(c) of OMa-1996.

Approval Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 108 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 Valve Relief Request No. 4 (VRR-04)

SI Pump Room Floor Drain Check Valve Exercising Valve ID Valve Description Code Category Drawing / Coord.

______________ Class ______ __________

RDAV020 Containment Spray Pump "A" 3 C RDP-002 / B 14 Room Floor Drain Check Valve RDAV021 HPSI Pump "A" Room Floor Drain 3 C RDP-002 / B 14 Check Valve RDAV022 LPSI Pump "A" Room Floor Drain 3 C RDP-002 / B14 Check Valve RDBV040 Containment Spray Pump "B" 3 C RDP-002 / B05 Room Floor Drain Check Valve RDBV041 HPSI Pump "B" Room Floor Drain 3 C RDP-002 / B05 Check Valve RDBV042 LPSI Pump "B" Room Floor Drain 3 C RDP-002 / B05 Check Valve Function These check valves open to allow floor drain flow from the respective pump room to the associated engineered safety feature sump. They close to prevent back-flooding from the sump to the pump rooms.

Test During plant operation, each check valve shall be exercised or examined in a Requirement manner which verifies obturator travel to the closed, full-open or partially open position required to fulfill its function. (OM-10 para. 4.3.2.2)

As an alternative to the testing in (a) or (b) above, disassembly every refueling outage to verify operability of check valves may be used. (OM-10 para. 4.3.2.4(c))

Alternate Each fuel cycle, at least 3 of these valves (on a rotating schedule) will be Testing disassembled, inspected, and manually full-stroke exercised. If, during inspection, it is discovered that a valve is incapable of performing its required functions, then the remaining valves will be disassembled, inspected, and manually full-stroke exercised during the same refueling outage (if the inspection is performed during a refueling outage) or within 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months after the subject valve is returned to service (if the inspection is performed at other times).

Basis For These are simple check valves with no external provision for exercising or for Relief determining disc position. The only methods of exercising open and closed are by flow testing, or by disassembly and inspection. Due to the system configuration, forward and reverse flow testing measurements are impractical.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 109 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES l 14 All six of these valves are identical with respect to manufacturer, size, model, orientation, and service conditions. Numerous previous inspections have not found any evidence of valve degradation that would affect their ability to open or close.

Since the frequency for disassembling and inspecting these valves in the floor drain system is not determined by refueling outages, inspection may be performed on a schedule that does not conform to a refueling outage schedule, such as during power operation. This is allowed as discussed in NUREG-1482, Appendix A, Question Group 14, under "Current Considerations".

Generic Letter 89-04 Position 2 allows a sample disassembly and inspection plan to be implemented where the licensee determines that it is burdensome to disassemble and inspect all applicable valves during each refueling outage.

Although these valves are not especially difficult to access, disassemble, or inspect, inspecting every valve in the group each fuel cycle is burdensome in that it creates a hardship without a compensating increase in the level of quality and safety.

The proposed sample disassembly schedule results in each valve being disassembled and inspected every 3 years. It is noted that this is half of the maximum inspection interval of 6 years recommended under Position 2. The proposed inspection frequency is adequate for assuring continued reliability and operational readiness of these valves.

Approval "Hardship" alternative authorized pursuant to 10 CFR 50.55a(a)(3)(ii) per NRC SER dated July 8, 1999. Complies with GL 89-04 Position 2.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Palie 110 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 Valve Relief Request No. 8 (VRR-08)

SI Check Valve Closed Exercising Valve ID Valve Description Code Category Drawing / Coord.

__________________ S H e C k aAS - 2Class SIEV540 SI Header Check Valve I AC SIP-002 / B13 SIEV541 SI Header Check Valve I AC SIP-002 / I I SIEV542 SI Header Check Valve I AC SIP-002 / C06 SIEV543 SI Header Check Valve I AC SIP-002 I C04 SIAV522 HPSI Long-Term Recirc. Check I AC SIP-002 / C02

_________________ LhPValve SIAV523 HPSI Long-Term Recirc. Check I AC SIP-002 / F02 Valve SIAV532 HPSI Long-Term Recirc. Check I AC SIP-002 IB 10

_ _ __ _ __ _ __ __ _V

_ _ alv e _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

SIAV533 HPSI Long-Term Recirc. Check I AC SIP-002 /F09

__ _ __ _ __ _ __ _ _ V alve _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

Function These valves close to provide safety system isolation from the reactor coolant system.

Test Check valves shall be exercised nominally every 3 months, except as Requirement provided by Paragraph 4.3.2.2, 4.3.2.3, 4.3.2.4, and 4.3.2.5. (OM-10 para.

4.3.2)

Alternate The closure capability of these check valves will be demonstrated by Testing performing leak rate testing in accordance with applicable Technical Specification requirements.

Basis For These are simple check valves with no external means of exercising nor for Relief determining disc position. The only practical means of verifying closure is by performing a leakage or back flow test. This typically involves a considerable effort with the test connections and valves required for the test alignment in radiation areas with inconvenient access provisions.

Leak testing to verify the closure capability of these valves is primarily for the purpose of confirming their capability of preventing over-pressurization of the related safety injection piping and components. In this regard, the Palo Verde Technical Specifications address the valve test frequency in a manner appropriate for these valves. Technical Specifications (SR 3.4.15.1) requires verifying that the leakage of each valve is within its limit at least once per 18 months, and prior to entering MODE 2 whenever the plant has been in MODE 5 for 7 days or more, if leakage testing has not been performed in the previous 9 months, except for SDC PlVs, and within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months following valve

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 111 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 actuation due to automatic or manual action or flow through the valve, except for SDC PlVs. Performing leak testing as prescribed in the Technical Specifications is adequate to ensure proper and reliable closure of these valves.

Approval Relief granted pursuant to 10 CFR 50.55a(f)(6)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 112 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI0 1 Revision COMPONENT TABLES l 14 Valve Relief Request No. 9 (VRR-09)

Verification of Thermal Equilibrium During Safety/Relief Valve Testing Valve ID l Valve Description Code Category Drawing / Coord.

Various All safety and relief valves tested Various C Various under ambient conditions using a

_ test medium at ambient conditions Function Provide over-pressure protection to associated systems.

Test Temperature Stability. The test method shall be such that the temperature of Requirement the valve body shall be known and stabilized before commencing set pressure testing, with no change in measured temperature of more than 10 deg-F (5 deg-C) in 30 minutes. (OM-I para. 8.1.2.4 and 8.1.3.4)

Alternate For safety and relief valves tested under ambient conditions using a test Testing medium at ambient conditions, the valve body temperature will be measured and recorded prior to each series of tests (which may consist of multiple lifts) but there will be no verification of attaining thermal equilibrium.

Basis For This is a generic request for relief for all safety and relief valves tested under Relief ambient conditions using a test medium at ambient conditions. For valves tested under normal prevailing ambient conditions with test medium at approximately the same temperature, the requirement for verifying temperature stability is inappropriate and of no value. There is little or no consequence of minor variations in ambient temperature.

This issue has been identified by the ASME OM Code Committees and is reflected in the 1995 version of the Code, Paragraphs I 8.1.2(d) and 1 8.1.3(d).

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER, dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Parze 113 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Valve Relief Request No. 10 (VRR-10)

Accumulator Volume for Safety/Relief Valve Testing Valve ID Valve Description Code Category Drawing / Coord.

_ _ __ __ _ _ __ ____ _ __ __ _ _ __ ___ ___ ___ ___ ___ ___ C las s _ _ _ _ _ _

Various All Class 2 and 3 safety and relief Various C Various valves used for compressible fluid services other than steam -

Function Provide over-pressure protection to associated systems Test Accumulator Volume. There shall be a minimum accumulator volume below Requirement the valve inlet, based on the valve capacity (cu f) and calculated from the following formula:

Minimum Volume = [valve capacity (cu ft per sec) x time open (sec) /

10. (OM-1 para. 8.1.2.2)

Alternate The volume of the accumulator drum and the pressure source flow rate shall Testing be sufficient to determine the valve set-pressure. (Ref. ASME OM Code-1995, para. 1 8.1.2)

Basis For This is a generic request for relief for all Class 2 and 3 safety and relief valves Relief used for compressible fluid services other than steam. The accumulator volume required by OM-1 para. 8.1.2.2 is not needed for determination of the set pressure for these valves. This has been recognized by the ASME Code Committee and reflected in more recent versions of the OM Code.

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 114 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 Valve Relief Request No. 11 (VRR-11)

ANII Involvement in Valve Inservice Testing Valve ID Valve Description Code Category Drawing I Coord.

Class Various Various Various Various Various Function Various Test Duties of the Authorized Nuclear Inspector include:

Requirement (c) verifying that the visual examinations and tests on pumps and valves have been completed and the results recorded. (Preface to Section XI)

It is the duty of the Inspector:

(1) to perform a detailed review of the inspection plan (IWA-2400) prior to the start of preservice inspection and each inspection interval ... Review of the inspection plan shall cover any features of the inspection plan which are affected by the requirements of this Division, as applicable, and shall include the following:

(a) examination categories and items (b) test and examination requirements (e) inservice test quantities (g) test frequency (2) to review any revisions to the inspection plan during the preservice inspection or the inspection interval; (3) to submit a report to the Owner documenting review of the items identified in (1) and (2) above; (IWA-21 10(a))

It is the duty of the Inspector to verify that the inservice tests required on pumps, valves, and component supports (IWF, IWP, and IWV) have been completed and the results recorded. (IWA-2 110(c))

Alternate The PVNGS Pump and Valve IST Program will be developed and Testing implemented in accordance with applicable regulations, codes, quality assurance requirements, plant procedures, and Authorized Inspection Agency requirements. ANII involvement with the Pump and Valve IST Program will not be required.

Basis For This is a generic relief request for all valves tested in the PVNGS Pump and Relief Valve IST Program. In the nuclear industry, the Authorized Nuclear Inservice Inspectors (ANIIs) have historically been involved primarily with the development and implementation of the Inservice Inspection Program.

Involvement with the Inservice Testing Program has been minimal. This is consistent with the experience and training of the individual inspectors, who

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 115 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES l 14 are well schooled in the areas of plant construction and repair. Recognizing this, ASME recently published the OMb-1997 addenda to the ASME/ANSI OM Code, which includes a change that eliminates all involvement of the ANII in the development and implementation of the Inservice Testing Program.

Each revision to the PVNGS IST Program is subjected to a comprehensive review process including technical reviews, management reviews, and a review under 10 CFR 50.59. In addition, quality assurance evaluations and self-assessments periodically monitor the implementation of the IST Program.

These measures, along with the constant attention by highly-qualified individuals tasked with program implementation ensure that the previous duties of the inspector are routinely and adequately performed and the intent of the ASME Code is maintained. Thus the proposed alternative testing provides an acceptable level of quality and safety.

Approval Alternative authorized pursuant to 10 CFR 50.55a(a)(3)(i) per NRC SER dated July 8, 1999.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL- Page 116 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Valve Relief Request No. 12 (VRR-12)

MOV Exercising and Stroke Timing Valve ID Valve Description Code Category Drawing Coord.

Class Various MOVs in the IST Program Various Various Various Function Various Test OM- 10 Sections 4.1, "Valve Position Verification", and 4.2.1, "Valve Requirement Exercising Test".

Alternate Motor-operated valve (MOV) testing may be conducted in accordance with Testing requirements of ASME OM Code Case OMN-1, "Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants, OM Code-1995, Subsection ISTC", with the following limitations:

1. The potential benefits (such as identification of decreased thrust output and increased thrust requirements) and potential adverse effects (such as accelerated aging or valve damage) will be considered when determining the appropriate testing for each MOV.

2. Where the selected test interval extends beyond 6 years or 4 refueling outages (whichever is longer), performance and test experience will be evaluated to justify the periodic verification interval. Test intervals will not exceed 10 years.

In addition the following exceptions/clarifications are necessary:

3. In order to maintain consistency and compatibility with the Joint Owners Group (JOG) MOV Periodic Verification Program, "functional margin" will be redefined as follows to agree with the definition of "margin" as used in Topical Report MPR-I 807 (Joint BWR, Westinghouse, and Combustion Engineering Owners' Group Program on Motor-Operated Valve Periodic Verification, Topical Report MPR-1 807",

Revision 2, July 1997).

Margin (Adjusted ActuatorOutput Thrust/Torque) - (Adjusted RequiredThrust/Torque)

Adjusted RequiredThrust/Torque The terms "functional margin" and "margin'! are used synonymously in the PVNGS MOV Program.

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4. OMN - I section 3.3(b) states that inservice tests will be conducted in the as-found condition. At PVNGS, as-found testing will be performed prior to preventive maintenance (PM) when scheduled during the same refueling outage.

Regularly scheduled PM activities, such as for stem lubrication

, will continue to be performed on a periodic basis to ensure that the MOV is maintained in optimum working condition.

In some cases, as-found testing may be waived if a modification or some other circumstance creates the condition where MOV trending will be re-baselined and the results of the as-found testing will no longer apply to future operation of the MOV. In all cases, the technical justification is documented with the appropriate management approvals in accordance with station procedures.

Section ( c ) states that the inservice testing program consists of a mix of static and dynamic testing. PVNGS is participating in the Joint Owners Group (JOG) MOV Periodic Verification Program, and the results of this program will be used to determine the need for and frequency of continued dynamic testing. For MOVs at PVNGS not included in the scope of the JOG program, site specific information will be used to justify the necessity for and frequency of continued dynamic testing.

Station Procedures currently contain the requirements to determine when Dynamic testing is required following valve modifications and this guidance is in accordance with Generic Letter 89-10 requirements.

Basis For The industry has long recognized the limitations of using stroke-time testing as Relief a means of monitoring the operational readiness of MOVs. After nuclear power plant experience, valve performance problems, and MOV research revealed that the focus of the ASME Code on stroke time and leak-rate testing for MOVs was not sufficient, the NRC issued Generic Letters 89-10 and 96-05. GL 89-10 requested licensees to ensure the capability of MOVs in safety-related systems to perform their intended functions by reviewing MOV design bases, verifying MOV switch settings initially and periodically, testing MOVs under design basis conditions where practicable, improving evaluations of MOV failures and necessary corrective action, and trending MOV problems. Generic Letter 96-05 requested licensees to establish a program, or to ensure the effectiveness of their current programs, to verify on a periodic basis that safety-related MOVs continue to be capable of performing their safety functions.

The PVNGS MOV Program was developed as part of the response to GLs 89-10 and 96-05. This program, which includes both periodic testing and preventive maintenance elements, complies with the requirements of GL 89-10.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paiae 11 8 of 129 PUMP AND VALVE NSERVICE TESTING PROGRAM.: 73DP-9XIO1 Revision COMPONENT TABLES 14 The requirements of GL 96-05 are being implemented as described in the response to GL 96-05.

All MOVs in the PVNGS ST Program are included in the PVNGS MOV Program. The periodic verification and preventive maintenance activities performed under the PVNGS MOV Program, together with the other testing performed on these valves in the 1ST Program, provide adequate assurance of MOV operational readiness. The additional assurance of operational readiness provided by continuing traditional ST exercising and stroke time testing is negligible. Thus, the testing proposed by this relief request provides an acceptable level of quality and safety.

Approval Valve Relief Request No. 12 (VRR-1 2) was submitted as a proposed alternative in accordance with 10 CFR 50a(a)3 in the PVNGS Second 10 year Interval for the Pump and Valve Inservice Testing Program on December 10, 1998. The NRC response, dated July 8, 1999, stated that VRR-12 provided an acceptable level of quality and safety and that PVNGS was authorized to use the OMN-1I Code Case for MOV Inservice Testing pursuant to 10 CFR 50.55a(a)(3)(i). The NRC Safety Evaluation Report (SER) Section 3.12 dealt with VRR-12. Section 3.12.4, Conclusion, states that PVNGS should notify the NRC upon completion of procedures for implementing ASME Code Case OMN- 1. This notification was made via APS Letter # 102-04973 dated July 18, 2003.

The NRC also stated that they were evaluating possible endorsement of the OMN-1I Code Case through rulemakeing or by regulatory guide. When that endorsement occurs, PVNGS is to follow the provisions of Code Case OMN-I with any limitations or conditions specified in the NRC endorsement. The NRC endorsement occurred in the Federal Register, Vol. 64, No. 183 on September 22, 1999 in 10 CFR 50 Paragraph 2.5.3. 1, entitled Code Case OMN-I. The endorsement specified 2 requirements:

1. At 5 years or three refueling outages (whichever is longer) from the initial implementation of Code Case OMN-I, the adequacy of the test interval for each MOV must be evaluated and adjusted as necessary.

2. The licensee is expected to ensure that the potential increase in core damage frequency and risk associated wvith extending exercise intervals for High Risk MOVs beyond a quarterly frequency is small and consistent with the intent of the Commission's Safety Goal Policy Statement.

The NRC endorsement also cautioned, as noted in GL 96-05, MOV Periodic Testing, about balancing the benefits and potential adverse affects on valves

I~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pae 119 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Rcvision COMPONENT TABLES l 14 and systems caused by MOV testing (specifically Dynamic Testing).

Based on the subject NRC SER and the OMN-l Code Case endorsement in the Federal Register, ASME Code Case OMN-1 can be implemented at PVNGS.

The following addresses the NRC requirements:

1. The PVNGS 89-10 Program for MOVs established frequency for MOV preventive maintenance and diagnostic testing will be used to ensure the operational readiness of MOVs in the PVNGS IST Program. The PVNGS 89-10 Program maintenance and testing frequencies are reviewed, evaluated and adjusted by the Valve Services Engineering Group following each refueling outage. This review process satisfies the NRC requirement to evaluate and adjust the MOV test intervals.

2. OMN-I Code Case implementation at PVNGS involved a risk analysis (Engineering Study 13-NS-C061) associated with extending the exercise interval beyond the current IST frequency for Stoke-time Testing. All High Risk MOVs will be exercised in accordance with their previous testing interval: quarterly or during Cold Shutdown. The Low Risk MOV exercise intervals will be changed to once per fuel cycle (1CY) - which is typically performed during Cold Shutdown.

Code Case Implementation of Code Case OMN-I resulted in deleting the IST Implementat- requirement for the Valve Position Indication Test (VP) and the Stroke Time ion Details Test (STO/STC). The IST MOV operational readiness is now monitored using the PVNGS 89-10 Program for MOVs, along with exercising each IST MOV once per fuel cycle.

The following 2 considerations impacted the implementation of this Code Case:

1. The PRA / Risk Assessment evaluation determined that the PVNGS High Risk IST MOVs, previously exercised quarterly via Stroke Time Testing, still needed to be exercised quarterly. This was done under the existing STs as a valve exercise, represented as a Full Stroke Open (FSO) and/or a Full Stroke Closed (FSC) instead of as a Stroke Time Test.

2. Certain IST MOVs need to be stroke timed to meet Technical Specification 3.3.5.4, an 18 month ESF Response Time Calculation requirement. For applicable IST MOVs, Stroke Time Testing was retained in the appropriate STs to be performed on a frequency of once per 18 months.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 120 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 Where possible, credit has been taken, in this procedure's Valve Component Table, for IST MOVs, that are stroked open and closed during the performance of another IST ST. The new ST has been recorded as the "Procedure" in the Valve Component Table.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 121 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X10I Revision COMPONENT TABLES 14 Valve Relief Request No. 13 (VRR-13)

Check Valve Condition Monitoring Valve ID Valve Description Code Category Drawing / Coord.

Class Various Various check valves Various C and AC Various Function Various Test Check valves shall be exercised nominally every 3 months, except as Requirement provided by paras. 4.3.2.2,4.3.2.3,4.3.2.4, and 4.3.2.5. (OM- 0para.

4.3.2.1)

Alternate As an alternative to the testing or examination requirements of OM-IO Testing paragraphs 4.3.2.1 through 4.3.2.5, check valves may be placed in a condition-monitoring program. The program shall be implemented in accordance with the ASME OMa-1996 Code, Appendix II, Check Valve Condition Monitoring Program, with the following modifications:

1. Condition monitoring activities shall assess the condition of the check valve and confirm acceptable performance.

2. The initial interval for tests and associated examinations shall not exceed two fuel cycles or three years (with 25% margin), which ever is longer.

3. The maximum interval shall not exceed 10 years.

4. Trending and evaluation of existing data shall be used to reduce or extend the time interval between tests.

5. Plant safety shall be considered when extending intervals.

6. If the condition-monitoring program is discontinued, the requirements of OM-10 section 4.3.2 shall apply.

Basis For The purpose of the Condition Monitoring Program is to both improve check Relief valve performance and to optimize testing, examination, and preventive maintenance activities in order to maintain the continued acceptable performance of a select group of check valves. Certain check valves need more attention in order to determine their failure or maintenance patterns.

Once these mechanisms have been analyzed, confirmed, and the valve or group of similar valves have had their performance improved, then the same level of attention is no longer needed. Certain other check valves need less attention as they have continuously exhibited acceptable operation.

After the reasons for their behavior have been analyzed, and confirmed, then the test, examination, and preventive maintenance activities necessary to maintain the continued acceptable performance can be optimized.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 122 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES l 14 These examples demonstrate how the same types of tests and their associated intervals may need to be periodically adjusted based on the valve's performance. The use of ASME OMa-1996 Code, Appendix II provides a process that allows certain flexibility in establishing the types of test, examination, and preventive maintenance activities and their associated intervals. Use of condition monitoring will:

Make inservice testing more flexible to adapt to different testing situations or preferences. Different types of analysis techniques can be used. Each valve can be approached in a slightly different manner based on the increasing skill levels of the individuals involved or the resources available.

Allow for analysis and provide some flexibility for decision making regarding the specification of the type and of the interval of tests, examinations, and preventive maintenance activities.

Shift emphasis to the problem valves by increasing the scope or interval of testing, monitoring, or examining activities until the cause is determined and the condition is corrected.

Shift emphasis from the valves that have continuously exhibited acceptable performance by decreasing the scope and frequency of testing, monitoring, or examination activities. Sufficient test, examination and preventive maintenance activity experience is needed before the scope of activities and their interval is adjusted.

Improve on failure detection capability and on the predictive capability as other activities that are geared to determine the condition of the valve are used. The current IST testing just uses exercising which provides a "snapshot" picture of the valve but gives no clue as to the future performance capability of the valve.

Increase preventive maintenance activities, not just by creating activities, but because there is a justifiable reason for doing them.

The current check valve testing program as described in OM-1 0 is extremely rigid and inflexible. Yet for all the of the plant resources that go into running this test program, check valve failures still occur. Many of these failures cannot be predicted by OM-10 testing, and studies show that many are not even detected by OM-IO testing.

The ASME OM Committee spent several years developing requirements for a check valve condition-monitoring program that would lead to goals as listed in the bullets above. After review and approval, these requirements were published with the OMa-1996 Addenda to the OM Code. Implementation of these requirements in place of the check valve exercising requirements of OM-10 paragraph 4.3.2 will provide an equivalent level of quality and safety.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 123 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 RCvision COMPONENT TABLES 1 14 After reviewing the relief request and SER for the check valve condition monitoring program at the Wolf Creek Generating Station, and the proposed change to 10 CFR 50 published in Vol. 62, No. 232 of the Federal Register, the following modifications have been made to the alternate testing proposed under this Relief Request:

1. Condition monitoring activities shall assess the condition of the check valve and confirm acceptable performance. This modification addresses the underlying basis for bi-directional testing.

The rulemaking states that valve opening and closing functions must be demonstrated when flow testing or examination methods (non-intrusive, or disassembly and inspection) are used. However, the demonstration of opening and closing functions is only one way to achieve the goal of condition monitoring, (i.e., maintaining the continued acceptable performance of check valves). Other methods may be equally effective. If PVNGS devises alternate methods that effectively assess the condition of check valves and confirm acceptable performance, use of such methods should be allowed under the condition monitoring program.

2. The initial interval for tests and associated examinations shall not exceed to fuel cycles or three years (with 25% margin), which ever is longer. The 2 fuel cycle /3 year limit ensures that the intervals are not initially overextended. The 25% margin facilitates scheduling by allowing for plant operating conditions that may not be suitable for conducting condition monitoring activities (e.g., transient conditions or other ongoing surveillance or maintenance activities).

The 25% extension does not significantly degrade the reliability that results from performing the condition monitoring activity at its specified interval. This is based on the recognition that the most probable result of any particular condition monitoring activity being performed is that the check valve is in conformance with the acceptance criteria. The 25% margin is not intended to be used repeatedly merely as an operational convenience to extend condition monitoring intervals (other than those consistent with refueling intervals) beyond those specified under this relief request.

3. The maximum interval shall not exceed 10 years. The 10 year limit ensures that interval lengths do not become excessive.

4. Trending and evaluation of existing data shall be used to reduce or extend the time interval between tests. Trending and evaluating data provide assurance that the component is capable of performing its intended function over the entire IST interval.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL PaEie 124 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14

5. Plant safety shall be considered when extending intervals.

Consideration of plant safety will provide assurance that testing under the condition-monitoring program does not significantly degrade plant safety. Implementation of this modification will draw on the experience gained by PVNGS while participating in the risk-informed IST pilot plant effort.

6. If the condition-monitoring program is discontinued, the requirements of OM-10 section 4.3.2 shall apply. This modification is similar to the one in the proposed rulemaking, except that reference is made to the code section applicable to check valve testing in the PVNGS IST Program. This modification was part of the January 13, 1998, "Inservice Testing Second 10 year Program" submittal, but has been reformatted as a modification for consistency and clarity.

Approval The NRC SER dated July 8, 1999, stated that VRR- 13 provides an acceptable level of quality and safety in assuring the operational readiness of check valves with the scope of the IST Program and that PVNGS was authorized to use ASME ISTC Appendix II pursuant to 10 CFR 50.55a(a)(3)(i).

Section 3.13 of the SER addressed VRR-13. Section 3.13.4, Conclusion, stated that the PVNGS request to use a 25% margin to extend the maximum interval past 10 years was denied. VRR-13 has been revised accordingly, deleting references to the use of 25% margin to extend the maximum interval.

The NRC SER also stated that the NRC was evaluating the Check Valve Condition Monitoring Program, ASME ISTC Appendix II, to be endorsed through rulemaking. When that endorsement occurs, any limitations included in the rulemaking would apply to the PVNGS implementation of this program. The NRC endorsement is documented in the Federal Register, Vol. 64, No. 183 dated September 22, 1999, in 10 CFR 50 Paragraph 2.5.3.2, entitled Appendix II. This endorsement applies to the 1995 Edition with the 1996 Addenda of ASME OM Code. The endorsement specified 3 requirements:

1. It is required to demonstrate bi-directional exercising movement of the check valve disc.

2. Prudent, safe test interval extensions should be implemented such that extensions be limited to one fuel cycle beyond the current test interval, up to a maximum of 10 years.

3. If the Condition Monitoring Program is discontinued, then all the requirements of ISTC 4.5.1 through 4.5.4 (of the 1995 Edition with the 1996 Addenda of ASME OM Code)

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Page 125 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES 14 must be met.

Based on the NRC SER and the endorsement of ISTC Appendix II in the Federal Register, PVNGS is approved to implement the Check Valve Condition Monitoring Program. The following addresses the NRC concerns and limitiations:

1. PVNGS will not use the 25% margin extension on the maximum 10 year interval.

2. The PVNGS Check Valve Condition Monitoring Program will incorporate bidirectional testing.

3. Test interval extensions will be not exceed I fuel cycle beyond the current test interval, up to a maximum of 10 years.

4. It is understood that if the Check Valve Condition Monitoring Program is discontinued, that the requirements of ISTC 4.5.1 through 4.5.4 (of the 1995 Edition with the 1996 Addenda of ASME OM Code) will apply to PVNGS IST Program check valves.

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 126 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9XI01 Revision COMPONENT TABLES - 14 Notes, Legends. Definitions, and Abbreviations Notes Note 1 Whenever check valve is disassembled, perform a manual exercise per 73ST-9ZZ25.

Note 2 Manual exercise per 73ST-9ZZ25 can be substituted for the regular check valve exercise test.

Note 3 Perform a partial stroke exercise with flow after reassembly, if practical.

Note 4 Check valve is tested under the PVNGS Check Valve Condition Monitoring Program per VRR-13 and 73DP-9XI05.

Note 5 MOVs are tested in the PVNGS 89-10 Program for MOVs per ASME OM Code Case OMN-I. This Code Case requires Active MOVs to be exercised once per fuel cycle (lCY). Additional exercising is performed at the Licensee's discretion (refer to VRR-12).

Pump Table Legend Pump ID Plant equipment identifier. The first 2 letters in the ID indicate the system.

Description Name / description of the pump Code Class ISI classification of the pump: 1, 2, 3, or N (non-class)

Drawing / Coord. Piping and Instrument Diagram number and coordinates showing the pump Test Parameters The table indicates the frequency which pump speed, pressure, flow rate, and vibration are measured, along with any applicable relief requests Test Procedure Procedure(s) which satisfy the testing requirements Remarks Additional explanation or clarification, if required Valve Table Legend Valve ID Plant equipment identifier. The first 2 letters in the ID indicate the system.

Description Name / description of the valve Drawing Piping and Instrument Diagram number showing the valve Coord Coordinates where the valve is located on the drawing Sht# Drawing sheet number Code Class ISI classification of the valve: 1, 2, 3, orN (non-class)

Size Nominal pipe size of the valve, in inches

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL . Paue 127 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X1I01 Revision COMPONENT TABLES 14 Type Valve type:

BF Butterfly Valve CK Check Valve DI Diaphragm valve GA Gate Valve GL Globe Valve PSV Pressure Safety Relief Valve RD Rupture Disk Act. Valve actuator type:

AO Air Operated HY Hydraulically Operated MA Manually Operated MO Motor Operated SA Self Actuating SO Solenoid Operated Cat. Valve category, per OM-I 0 para. 1.4 and 2: A, B, C, or D.

A/P A (active) or P (passive) valve, per OM-10 para. 1.3.

S.P. Safety position: 0 (open), C (closed), or OC (both open and closed).

Test Test(s) performed on the valve. The first two letters indicate the type of test:

AJ Appendix J Leak Test CM Check Valve Condition Monitoring Test FS Full Stroke Exercise Test FT Fail Safe Test LT Leak Test other than an Appendix J Test PS Partial Stroke Exercise Test ST Stroke Time Test SV Pressure Safety Relief Valve Test VP Valve Position Indication Test A third letter is used where required to indicate stroke direction: 0 (open) or C (closed), or a special activity, like I (inspection).

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Paae 128 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 1 14 Freq Frequency at which a test is performed:

CLR Per the Containment Leak Rate Program CMP Per the Check Valve Condition Monitoring Program CSD Cold Shut Down QTR Quarterly RFO Refueling Outage STF Special Test Frequency I YR Once per year 18M Once per 18 months ICY Once per fuel cycle 2YR Once every 2 years 5YR Per OM-I para. 1.3.3.1 (at least once every 5 years) lOY Per OM-I para. 1.3.4.1 (at least once every 10 years)

Procedure Procedure in which the test is performed CSJIROJJVRR Applicable Cold Shutdown Justification, Refueling Outage Justification, or Valve Relief Request Remarks Additional explanation or clarification, if required Definitions Augmented Components or tests included within the IST Program at the discretion of IST Engineering. Augmented components are generally tested in accordance with the Code to the extent practical, however, deviations from Code requirements do not require relief.

Abbreviations ACU Air Conditioning Unit CP Containment Purge system AF Auxiliary Feedwater system CPIAS Containment Purge Isolation Actuation Signal AFAS Auxiliary Feedwater Actuation Signal CS Containment Spray AFW Auxiliary Feedwater CSD Cold Shutdown ANII Authorized Nuclear Inservice Inspector CSJ Cold Shutdown Justification AOV Air-Operated Valve CST Condensate Storage Tank ASMIE American Society of Mechanical Engineers CT Condensate Transfer system BANIP Boric Acid Makeup Pump DF Diesel Fuel system CC Code Case DG Diesel Generator system CEDNI Control Element Drive Mechanism DW Demineralized Water system CHI Charging system EC Essential Chilled Water system CIAS Containment Isolation Actuation Signal EDG Emergency Diesel Generator CIV Containment Isolation Valve ESF Engineered Safety Features

NUCLEAR ADMINISTRATIVE AND TECHNICAL MANUAL Pace 129 of 129 PUMP AND VALVE INSERVICE TESTING PROGRAM - 73DP-9X101 Revision COMPONENT TABLES 14 EW Essential Cooling Water system SDC Shutdown Cooling FP Fire Protection system SG Steam Generator FNN'IV Feedwater Isolation Valve SG Main Steam system GA Service Gas system SI Safety Injection system GL Generic Letter SIAS Safety Injection Actuation Signal GR Gaseous Radwaste system SIT Safety Injection Tank 112 Hydrogen SOV Solenoid-Operated Valve

'IC Containment HVAC system SP Essential Spray Pond system liP Hydrogen Purge system SR Surveillance Requirement IIPSI High Pressure Safety Injection SS Sampling system IIVAC Heating, ventilation, and air conditioning TDAFNN' Turbine-Driven Auxiliary Feedwater Pump IA Instrument Air system TRMI Technical Requirements Manual IS' Inservice Inspection TS Technical Specification IST Inservice Testing TSR TRM Surveillance Requirement LCO Limiting Condition for Operation VCT Volume Control Tank LOCA Loss of Coolant Accident VRR Valve Relief Request LPSI Low Pressure Safety Injection W\'C Normal Chilled Water system LTOP Low Temperature Over Pressure NIFIV Main Feedwater Isolation Valve NSOV Motor-Operated Valve r*ISIV Main Steam Isolation Valve NC Nuclear Cooling Water system PASS Post-Accident Sampling System PEN. Penetration PRAIRA Probablistic Risk Assessment/Risk Assessment PRR Pump Relief Request PVNGS Palo Verde Nuclear Generating Station RC Reactor Coolant system RCP Reactor Coolant Pump RCS Reactor Coolant System RD Radioactive Drains RDT Reactor Drain Tank RNIW Reactor Makeup Water ROJ Refueling Outage Justification RWT Refueling Water Tank

ML040440424

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2. Applicable Code Edition and Addenda

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ML040440424

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Dear Sirs:

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Enclosures:

2. Applicable Code Edition and Addenda

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