ML20072T683

Rev 12 to Unit 2 Pump & Valve Inservice Testing Program

ML20072T683
Person / Time
Site:	McGuire, Mcguire
Issue date:	04/08/1991
From:	DUKE POWER CO.
To:
Shared Package
ML20072T678	List: ML20072T673 ML20072T679 ML20072T683
References
PROC-910408-01, NUDOCS 9104180222
Download: ML20072T683 (134)

Text

{{#Wiki_filter:_ _ _ _ _ _ - _ _ _ _ UNIT 2 TABLE OF CONTENTS Page Section Number; 1. Pump Inservice Testing Program 1.1 Introduction 1.2 Data Sheets 1.3 General Relief Requests 1.4 Specific Relief Requeste 11. Valve Inservice Testing Program 11.1 Introduction 11.2 Table of Abbreviations 11.3 Definitions of Testing Requirements and Alternatives !!.4 System Data Sheets: Steam Generator Blowdow' Recycle (BB)............... 1 Auxiliary Feedwater (CAi............................ 2 Feedwater (CF)................................... 3 Diesel Generator Engint fuel Oil (FD)............... 4 Refueling Water (FW)................................ 5 Airlock (IA)......................................... 6 Component Cooling (KC).............................. 7 Diesel Generator Cooling Water (KD).................. 8 Radiation Monitoring (MI)........................... 9 Boron Recycle (NB).................................. 10 Reactor Coolant (NC)................................ 11 Residual Heat Removal (ND).......................... 12 Ice Condensor Refrigeration (NF).................... 13 Safety injection (NI)............................... 14-15 Nuclear Sampling (NM)............................... 16 Containment Spray (NS).............................. 17 Chemical and Volume Control (NV).................... 18 Fire Protection (RF)................................ 19 Nuclear Service Water (RN).......................... 20-21 Containment Ventilation Cooling Water (RV).......... 22 Main Steam Supply to Auxilary Equipment / Turbine Exhaust (SA)................................... 23 Main Steam (SM)..................................... 24 Main Steam Vent to Atmosphere (SV).................. 25 Breathing Air (VB).............. 26 Annulus Ventilation (VE)............................ 27 Diesel Generator Starting Ai r (VG).................. 28 Instrument Air (VI)................................. 29 Containment Purge Ventilation (VP).................. 30 Containment Air Release and Addition (VQ)........... 31 Station Air (VS).................................... 32 I ,91onos 910416 f; c'5000369 Revision 12 PDR A PDR P

UNIT 2 Page Section Numtier Containment Air Return Exchange and Hyd roge n S ki mme r (VX).......................... 33 Equipment Decontamination (WE)...................... 34 Liquid Waste R6 cycle (WL)........................... 35 Diesel Generator Room Sump Pump (WN)................ 36 Makeup Domineralized Water (YM)..................... 37 11.5 General Relief Requests II.6 Specific Relief Requests II.7 Cold Shutdown Justifications 2-Pevision 12

McGUIRE - UNIT 2 TABLE OF ABBREVIATIONS CLASSIFICATION Duke System ANS Valve Designed for Safety Class Code Design Criteria Seismic Loading Class A Class 1, ASME Section III, 1971 Yes 1 B Class 2 ASME Section III, 1971 Yes 2 C Class 3, ASME Section III, 1971 Yes 3 D Class 2, ASME Section III, 1971 No 2 E ANSI B31.1.0 (1967) No NNS F ANSI B31.1.0 (1967) Yes NNS G ANSI B31.1.0 (1967) No H Duke Power Company Specification No LEGEND LT - Leak Test MT0 - Movement Test Open MTC - Movement Test Closed MTO,0 - Movement Test Open and Closed Q - Quarterly CS - Cold Shutdown RF - Refueling Outage ST - Stroke Time (cycle and time) SP - Setpoint PC - Procedure Check CIV - Containment Isolation Valve PIV - Pressure Isolation Valve RR - Relief Request TS - Technical Specification CL - Class CAT - Category FS - Fail Safe 12 Revision 12

i Mc0UIRE - UNIT 2 j Quarterly (Q) Testin will be performed at least once per three 3) months. Refueling Outage (RF) Testing will be performed when the unit is shut down for refueling. Safety valves will be tested periodically per the testing schedule defined in ASME Subsection IW-3510. Testing may be done while--in No Mode as well as Modes 3, 4, 5, and 6. Refueling Outage (RF*) Valve will normally be tested during refueling outages, not to exceed 24 months per Appendix J to 10CFR50. Refueling Outage (RF#) Valve will normally be tested on a routine basis via a sample valve disassembly program (1 valve from a group of identical valves under similar system conditions). Failure of one valve of the group during a refueling outage will result in all remaining valves of the group being tested during that outage. Setpoint (SP) Valve will be tested to verify that it will relieve pressure at its specified setpoint. Testing will be performed per the i requirements of IW-3510. Fail Safe (FS) Valve will be tested to verify it will i reposition to its design' safe position upon 12 loss of control air per IW-3415. f l Revision 12 e

l Mc0UIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-CA1 VALVE: 2CA-165, 2CA-166 FLOW DIAGRAM: MC-2592-1.1 CATEGORY: C CLASS: C FUNCTION: Prevents backflow from Aux. Feedwater System to Nuclear Service Water System TEST REQUIREMENT: Full stroke exercise quarterly BASIS: Neither full nor partial flow can be put through these valves withoui contaminating the Auxiliary Feedwater System with raw water, No means exist for alternate 12 testing techniques using air or any other medium, ALTERNATE TESTING: At least one of these two valves will be disassembled and full stroked during each refueling outage, and both valves will have been disassembled and full stroked after two consecutive refueling outages. Failure of one valve to properly full stroke during a refueling outage will result in the remaining valves being disassembled and full stroked during that

outage, Revision 12 l

..~- _. _ _ _. _ _ _.--.__ _ _ _. _. -._ McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-IAl VALVE: 21A-5360, 21A-5370, 2IA-5380, 21A-5390 FLOW DIAGRAMt MC-2499-IA1 CATEGORY: AC CLASS: B FUNCTION: Check containment pressure on reactor building side of airlock and relieve to containment to prevent overpressurization.of airlock. TEST REQUIREMENT: Verify proper valve movement. BASIS: These valves are double isolation check valves and are arranged in series. There is no means to leak test the valves individually. ALTERNATE TESTING: These valves will be verified closed by leak testing performed in accordance with Appendix J. The valves will be tested in series, not individually. l New Page Revision 12 .a.-

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-NB1 VALVE: 2NB-262 FLOW DIAGRAM: MC-2556-3,0 CATEGORY: A, C CLASS: B FUNCTION: Provide containment isolation. TEST REQUIREMENT: Verify proper valve movement once per three months. BASIS: The system design does not provide any indication for verifying valve closure upon flow reversal. ALTERNATE TESTING: Valve will be verified shut by leak test performed in 12 accordance with Appendix J. I Revision 12 1 l i, l

McGUIRE - UNIT 2 REllEF/ JUSTIFICATION: RR-NF1 VALVE: 2NF-229 FLOW DIAGRAM: MC-2558-4.0 CATEGORY: A,C CLASS: B FUNCTION: Provide containment isolation TEST REQUIREMENT: 1) Verify proper valve movement once per three

months, 2) 10CFR50 Appendix J requires measurement of local leak rate using air or nitrogen.

BASIS: The system design does not provide any indication for verifying valve closure upon flow reversal. 12 ALTERNATE TESTING: 1) Valve will be verified closed by leak test performed in accordance with Appendix J. 2) Leak Rate testing of the valve will be performed per Tech Spec 4.6,1,2.d.4). Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-NF2 (Deleted per Rev. 12) VALVE: 2NF-228A, 2NF-233B, 2NF-234A 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-RV1 VALVE: 2RV-130, 2RV-126 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-VI3 VALVE: 2VI-135, 2VI-136, 2VI-137, 2VI-138, 2VI-139, 2VI-140, 2VI-141, 2VI-142 FLOW DIAGRAM: MC-2605-1.3 CATEGORY: AC CLASS - C FUNCTION: Check instrument air from the main steam isolation valve accumulator tank. i TEST REQUIREMENT: Cycle quarterly and leak test, j BASIS: These valves are double isolation check valves and are arranged in series. There is no means to test the valves individually. Testing these valves makes one of the main steam isolation valves inoperable due to deprescurizing the accumulator tank. ALTERNATE TESTING: .These valves will be cycled and leak tested during cold shutdown. Relief is required because two valves at a time are tested.in series, not individually. New Page Revision 12

l McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-FW1 VALVE: 2FW-27A FLOW DIAGRAM: MC-2571-1. 0 CATEGORY: B CLASS: B FUNCTION: Isolates low pressure injection from FWST TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: Closure of this valve would render all low pressure injectioninoperable. ALTERNATE TESTING: Valve will be cycled and timed during cold shutdown, 12 Revision 12

l McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-FW2 VALVE: 2FW-28 FLOW DIAGRAM: MC-2571-1. 0 CATEGORY: C CLASS: B FUNCTION: Prevents reverse flow to the FWST and prevents pressurizing the FWST. TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: 2FW-28 cannot be full stroked during power operation since the only full flow path is into the RCS by the Residual Heat Removal Pumps (ND). The ND Pumps cannot overcome RCS pressure. ALTERNATE TESTING: Valve will be full stroke exercised at cold shutdown. 12 Revision 12

l l McGUIRE - UNIT 2 i RELIEF / JUSTIFICATION: CS-ND4 VALVE: 2ND-70 FLOW DIAGRAM: MC-2561-1.0 CdTEGORY: C CLASS: B FUNCTION: RHR to SI Suction Check TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: 2ND-70 cannot be full stroked during power operation since the only full flow path is into the RCS and this can only be performed during cold shutdown. The miniflow for ND Pump 2A does not pass through 2ND-70 so it cannot be partial stroked during power operation. 2ND-70 cannot be seat leak tested during power operation since the required valve lineup cannot be made without putting 2000 ppm boron water from the RWST into the Chemical and Volume Control Pump Suction. Additionally, with the RCS at normal operating pressure, the seat leakage cannot be identified. ALTERNATE TESTING: 2ND-70 will be full stroke exercised and seat leak tested at cold shutdown and depressurized. 12 l Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: Cs "05 VALVE: 2ND-71 FLOW DIAGRAM: MC-2561-1.0 CATEGORY: C CLASS: B FUNCTION: RHR to SI Suction Check TEST REQUIREMENT: Full stroke exercise quarterly, BASIS: Valve cannot be full stroked at power since the only full flow path is int.o the RCS and this can only be performed at cold shutdown. 2ND-71 cannot be partial 12 stroked during power since the required valve lineup would render both trains of safety injection inoperable, 2ND-71 cannot be leak tested with the RCS at normal operating pressure because the seat leakage cannot be { identified. ALTERNATE TESTING: Valve will be full stroked at cold shutdown and depressurized. 12 Revision 12 l

l McGUIRE - WIT 2 REllEF/ JUSTIFICATION: CS-ND6 VALVE: 2ND-8, 2ND-23 FLOW DIAGRAM: MC-2561-1.0 CATEGORY: C CLASS: B FUNCTION: Prevents reverse flow through the ND Pumps TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: 2ND-8 and 2ND-23 cannot be fully stroked during power operation since the only full flow path is into the RCS and the ND Pumps cannot overcome RCS presure. The ND Pump recirc line is not large enough to accomodate full design flow. ALTERNATE TESTING: Valves will be full stroke exercised at cold shutdown. Valves will be partial stroked quarterly. 12 The opposite train check valves will be tested closed during quarterly pump testing except when the opposite train of ND is in service. Revision 12 l l

I McGUIRE - UNIT 2 i RELIEF / JUSTIFICATION: CS-NI13 VALVE: 2NI-15, 2NI-354, 2N1-17, 2NI 347, 2NI-19, 2NI-348, 2NI-21, 2NI-349 FLOW DIAGRAM: MC-2562-1.0 CATEGORY:- C I CLASS: A FUNCTION: Provides safety injection flow path. TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: Full or partial stroke during power operation would I result in thermal shock to injection nozzles. I ALTERNATE TESTING:- Valve will be full stroked at cold shutdown, i 12 l l l l Revision 12 i

l l McGUIRE - UNIT 2 i RELIEF / JUSTIFICATION: CS nil 4 VALVE: 2N1-12 FLOW DIAGRAM: MC-2562-1.0 CATEGORY: C CLASS: B FUNCTION: provides safety injection flow path TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: Full or partial stroke during power operation would result in thermal shock to injection nozzles. ALTERNATE TESTING: Valve will be full stroked at cold shutdown, g Revision 12

McGUIRL - UNIT 2 I RELIEF / JUSTIFICATION: CS-N115 VALVE: 2NI-101 FLOW DIAGRAM: MC-2562-3.0 CATEGORY: C CLASS: B FUNCTION: Opens on flow from FWST to SI. Checks flow if k}lR is supplying SI suction pressure. TEST REQUIREMENT: Full stroke exercise quarterly. BASIS: Valve cannot be full stroked during power operation since the SI pumps cannot overcome RCS pressure. ALTERNATE TESTING: Valve will be partial stroked quarterly and full stroked and leak tested at cold shutdown. 12 l Revision 12-

I McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NI16 VALVE: 2NI-116, 2NI-148 FLOW DI AGRA.'1: MC-2562 3.0 CATEGORY: C CLASS: B FUNCTION: Opens to flow from the NI pump (s). Check flow ftom opposite train. TEST REQUIREMENT: Verify proper valve movement once per three mor.ths. BASIS: Valves cannot be full or partial stroked during power operation t.ince the safety injection pumps cannot overcome RCS pressure. ALTERNATE TESTING: Valves will be cycled full open during cold shutdown. Valves will be checked closed quarterly. 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-N117 YALVE: 2NI-128, 2NI-159, 2NI-160, 2NI-156, 2NI-124, 2NI-157 FLOW DIAGRAM: MC-2562-3,0 CATEGORY: A,C CLASS: B FUNCTION: Open on flow from the SI pumps to the RCS hot legs. Reactor Coolant Boundary valve. TEST REQUIREMENT: Verify proper valve movement once per three months and leak test per Technical Specifications. BASIS: Valves cannot be full or partial stroked during power operation since the safety injection pumps canact discharge into the RCS at operating pressure. ALTERNATE TESTING: Valves will be verified to tully cycle during cold ~ shutdown. Valves will be leak tested in accordance . ith Tech Spec 4.4.6.2.2. 12 w Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NI18 VALVE: 2NI-165, 2NI-167, 2NI-169, 2NI-171 FLOW DIAGRAM: MC-2562-3.1 CATEGORY: A,C CLASS: A FUNCTION: SI discharge check valves to RCS cold legs. Reactor Coolant Boundary valves. TEST REQUIREMENT: Full stroke exercise quarterly and leak test per Technical Specifications. BASIS: Valves cannot be cycled during power operation since the SI pumps cannot overcome RCS pressure to perinit flow through the valves. ALTERNATE TESTING: Valves will be fully cycled during cold shutdown. Valves will be leak tested in accordance with Tech Spec 4.4.6.2.2.. 12 l l l l 1 I l l. L l Revision 12 l-

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS NI19 . VALVE: 2N1-180, 2NI-181, 2NI 175, 2NI-176 FLOW DIAGRAM: .MC-2562-3.1 CATEGORY: A,C CLASS: A FUNCTION: Opens on flow from the ND to the RCS. Reactor Coolant Boundary valve. TEST REQUIREMENT: Verify proper valve movement once per three months and leak test per Technical Specifications. -BASIS: The discharge pressure of the HD Pumps is not 4 sufficient for opening the valve to the Reactor Coolant System during power operation. ALTERNATE TESTING: Valve vill be verified to fully cycle during cold shutdown by acoustic emission monitoring, Valves will be leak tested in accordance with Technical 12 Specifications, i Revision 12

_ _ _ ~ McGUIRE - UNIT 2 9 4 RELIEF / JUSTIFICATION: CS-NI20 VALVE: 2NI-129, 2NI-125, 2NI 134, 2NI 126 FLOW DIAGlW1: MC 2562-3.0 CATEGORY: A,C CLASS: A FUNCTION: Opens on flow from the ND syrtem to the NC Hot Legs, Reactor Coolant Boundary valve. TEST REQUIREMENT: Verity proper valve movement once per three months and leak test per Technical Specifications. BASIS: ND pumps do not develop enough discharge pressure to overcome RCS pressure at power operation. ALTERNATE TESTING: Valve will be verified to fully cycle during cold shutdown by acountic emission monitoring. Valves will be leak tested in accordance with Technical 12 Specifications. l s i l l' l Revision 12

Mc0UIRE UNIT 2 s RELIET/ JUSTIFICATION: CS-NI21 VALVE: 2NI-136B FLOW DIAGRAM: MC-2562-3.0 CATEGORY: 'B CLASS: B -FUNCTION: Safety injection suction from RHR TEST REQUIREMENT: Cycle time quarterly. BASIS: Opening this valve during modes in which safety injection.is required could seat the check valve from the refueling water storage tank, NI-101, in the event of a LOCA. The RllR pumps would start, seating the check valve and causing the safety injection pumps to runout the RHR ptuups. ALTERNATE TESTING: Valves will be cycle timed during cold shutdown. I i l l New Page l~ Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NSI VALVE: 2NS 38B, 2NS 43A FLOW DIAGRAM: tK-2503-1.0 CATEGORY: B CLASS: B FUNCTION: Containment Spray Header ' solation TEST REQUIREMENT: Cycle time quarterly. BASIS: Opening either of these valves during modes in which the Residual Heat Removal (RKR) system is required would divert flow from the Reactor Coolant system cold legs if the RHR system were to automatically initiate. The flowrate would not meet the initial flowrate requirements for a large break LOCA in modes 1 through 4. ALTERNATE TESTING: Valves will be cycle timed during cold shutdown.- L l j; 1. New Page Revision 12

Mc0UIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV3 (Deleted per Rev. 12) VALVE: 2NV-1A, 2NV-2A 12 Revision 12

f g$ l McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV5 (Deleted per Rev, 12) L-VALVE: 2NV-22 (; 12 Revision 12 (, --m--- - - - ~ ~ -

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV6 (Deleted per Rev. 12) VALVE: 2NV-1007, 2NV-1008, 2NV-1009, 2NV-1010 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV10 (Deleted per Rev. 12) VALVE: 2NV 459A 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV14 VALVE: 2NV-225, 2NV-231 FLOW DIAGRAM: MC-2554-3.1 CATEGORY: C CLASS: B FUNCTION: Opens on flow from the Centrifugal Charging Pump (s). TEST REQUIREMENT: Verify proper valve movement every three months. BASIS: Valve cannot be full stroke exercised during power operation because this would result in an increase in the RCS boron inventory and could result in a plant shutdown. To fully stroke 2NV-225 and 2NV-231 the full centrifugal charging pump flow would have to go through the valves. The reactor coolant system letdown capacity would not be enough to maintain volume control tank level. The additional flow would have to come from the refueling water storage tank which has a boron concentration of 2000 ppm. ALTERNATE TESTING: Valve will be full stroked during cold shutdown and partial stroked with normal use. 12 Revision 12

McGUIRE - UNIT 2 i RELIEF / JUSTIFICATION: CS-NV15 VALVE: 2NV-223 FLOW DIAGRAM: MC-2554-3.1 CATEGORY: C CLASS: B FUNCTION: Opens on flow alignment from FWST, Closes to ensure sufficient centrifugal charging pump suction presure when RHR is used as a suction source. TEST REQUIREMENT: Verify proper valve movement every three months. BASIS: Testing of these valve requires opening 2NV-221A or 2NV-2228. Failure of one of these valves in the open position aligns the FWST to the suction of the charging pumps with no means of isolating the flow path. This would result in an increase in boron inventory in the RCS and could result in a plant shutdown. ALTERNATE TESTING: Valve will be full stroked and leak tested during cold

shutdown, 12 l

Revision 12

1 McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV16 VALVE: 2NV-1046 FLOW DIAGRAM: MC-2554-3.0 CATEGORY: C CLASS: B FUNCTION: Opens on reciprocating charging pump recirc. flow. Closes to prevent diversion of flow to the centrifugal charging pump suctions. TEST REQUIREMENT: Verify proper valve movement once every 3 months. BASIS: Testing this valve on line would result in adding 2000 ppm borated water to the centrifugal charging pump suction resulting in a reactor power transient. ALTERNATE TESTING: Valve will be verified to seat closed during cold shutdown. New Page Revision 12

1^ McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-RN1 (Deleted per Rev. 12) VALVE: 2RN-21A, 2RN-22A, 2RN-258, 2RN-26B 12 Revision 12 l

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-RN4 VALVE: 2RN-42A FLOW DIAGRAM: MC-2574-4.0 CATEGORY: B CLASS: C FUNCTION: Isolates Nuclear Service Water System Non-Essential Header TEST REQUIREMENT: Cycle and time valve every three months. BASIS: Failure of this valve in the closed position during testing would inhibit cooling flow to heat exchangers. This action could result in damage to the equipment 12 served by these heat exchangers. This equipment includes the PD charging pump and the computer room A/C. ALTERNATE TESTING: This valve will be tested during cold shutdown. Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-SM2 (Deleted per Rev. 12) VALVE: 2SM-9AB, 2SM-10AB, 2SM-11AB, 2SM-12AB 12 Revision 12

McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-VG1 VALVE: 2VG-17, 2VG-18, 2VG-19, 2VG-20 FLOW DIAGRAM: MC-2609-4.0 CATEGORY: C CLASS: C FUNCTION: Open to provide diesel generator control air from individual starting air banks. TEST REQUIREKENT: Full stroke exercise quarterly. BASIS: To test these valves, the diesel generator would have to be started on a single bank of control air which would be a degraded condition. This is not justified for quarterly starts. ALTERNATE TESTING: Valves will be full stroke exercised during cold shutdown. New Page Revision 12 l

Page No, 1 03/27/91 Duke Power Company [} McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE C1. FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • NUCLEAR SERVICE WATER 12 ORN-0002B C 1574-1.0 K-10 B ST-Q 12 ORN-0003A C 1574-1.0 K-10 B ST-Q 16 OP.N-0004AC C 1574-1.0 F-13 B ST-Q 12 ORN-0005B C 1574-1.0 E-12 B ST-Q 12 ORS-0007A C 1574-1.0 J-09 B ST-Q 12 ORN-0009B C 1574-1.0 D-09 B ST-Q 12 ORS-0010AC C 1574-1.0 G-11 B ST-Q 12 ORN-00llB C 1574-1.0 F-11 B S1-Q 12 ORN-0012AC C 1574-1.0 1-11 B ST-Q 12 ORN-0013A C 1574-1.0 J-11 P

ST-Q ORN-0014A C 1574-1.0 1-13 B ST-Q 12 ORN-0015B C 1574-1.0 F-13 B ST-Q 12 12 ORN-0147AC C 1574-1.0 H-02 B ST-Q 16 ORN-0148AC C 1574-1.0 H-03 B ST-Q ORN-0149A. C 1574-1.0 J-07 B ST-Q 12 12 ORN-0150A C 1574-1.0 1-06 B ST-Q 12 ORN-0151B C 1574-1.0 F-06 B ST-Q 12 ORN-0152B C 1574-1.0 E-07 B ST-Q ORN-0283AC C 1574-1.0 F-02 B ST-Q 12 12 ORN-0284B C 15'/4-1,0 F-02 B ST-Q 12 ORN-0301AC C 1574-1.0 G-10 B ST-Q 12 ORN-0302B C 1574-1.0 F-10 B ST-Q s

Page No. 2 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VAINE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • STEAM GENERATOR BLOWDOWN RECYCLE 1BB-0001B B 1580-1.0 11- 0 2 b ST-Q IBB-0002B B 1580-1.0 H-04 b

ST-Q 1BB-0003B B 1580-1.0 H-10 B ST-Q IBB-0004B B 1580-1.0 H-10 B ST-Q IBB-0005A B 1580-1.0 F-02 B ST-Q 1BB-0006A B 1580-1.0 F-04 B ST-Q 1BB-0007A B 1580-1.0 F-12 B ST-Q IBB-0008A B 1580-1.0 F-10 B ST-Q

i Page No. 3 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVF INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • AUX 1LIARY FEEDWATER ICA-0007AC C 1592-1.1 B-10 B ST-Q CA2 RF#

14 ICA-0008 C 1592-1.1 B-11 C MTC-Q 1CA-0009B C 1592-1.1 C-05 B ST-Q CA2 RF# 14 1CA-0010 C 1592-1,1 C-05 C MTC-Q 1CA-0011A C 1592-1.1 B-04 B ST-Q CA2 RF# 14 ICA-0012 C 1592-1,1 B-03 C MTC-Q 1CA-0015A C 1592-1.1 D-03 B ST-Q ICA-0018B C 1592-1.1 D-04 B ST-Q 16 1CA-0020AB C 1592-1.1 1-10 AC ST-Q LT 1CA-0022 C 1592-1.1 1-10 C MTO-Q ICA-0026 C 1592-1.1 1-04 C MTO-Q 16 ICA-0027A C 1592-1.1 J-05 AC ST-Q LT 1CA-0031 C 1592-1.1 1-07 C MTO-Q 16 1CA-0032B' C 1592-1,1 J-08 AC ST-Q LT 1CA-0036AB. C 1592-1.0 L-10 B ST-Q CS-CA1 ICA-0037 B 1592-1.0 K-14 C MTO.C-Q ICA-0038B B 1592-1.0 J-14 B ST-Q 16 1CA-0040B C 1592-1.0 G-14 B ST-Q 1CA-0041 B 1592-1.0 H-14 C MTO.C-Q - CS-CA1 ICA-0042B B 1592-1.0 1-14 B ST-Q ICA-0044B C 1592-1.0 C-11 B ST-Q CS-CA1 1CA-0045 B 1592-1.0 C-09 C MTO.C-Q - ICA-0046B B 1592-1.0 D-08 B ST-Q ICA-0048AB C 1592-1.0 K-08 B ST-Q CS-CA1 ICA-0049 B 1592-1.0 H-08 C MTO C-Q ICA-0050B B 1592-1.0 G-08 B ST-Q 1CA-0052AB C 1592-1.0 K-07 B ST-Q CS-CA1 ICA-0053 B 1592-1.0 H-07 C MTO.C-Q ICA-0054AC B 1592-1.0 G-07 B ST-Q 16 ICA-0056A C 1592-1.0 C-04 B ST-Q CS-CA1 1CA-0057 B 1592-1.0 C-06 C MTO.C-Q ICA-0058A B 1592-1.0 D-07 B ST-Q 1CA-0060A C 1592-1.0 G B ST-Q CS-CA1 ICA-0061 B 1592-1.0 H-01 C HTO.C-Q - ICA-0062A B 1592-1.0 I-01 B ST-Q 1CA-0064AB C 1592-1.0 L-04 B ST-Q CS-CA1 ICA-0065 B 1592-1.0 K-01 C MTO.C-Q ICA-0066AC B 1592-1.0 1-01 B ST-Q ICA-0086A C 1592-1,1 c-14 B ST-Q ICA-0116B C 1592-1.1 E-14 B ST-Q ICA-0161C DELETED 16 1CA-0162C DELETED 16 1CA-0165 C 1592-1.1 C-14 C MTO.C-Q CA1 RF# 16 1CA-0166 C 1592-1.1 F-14 C MTO.C-Q CA1 RF# 16

Page No. 4 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL F LO'a FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • FEEDWATER CS-CF2 ICF-0017AB F 1591-1.1 K-03 B ST-Q CS-CF2 ICF-0020AB F 1591-1.1 K-06 B ST-Q CS-CF2 ICF-0023AB F 1591-1.1 K-09 B ST-Q CS-CF1 ICF-0026AB B 1591-1.1 H-03 B ST-Q CS-CF1 ICF-0028AB B 1591-1.1 H-06 B ST-Q CS-CF1 ICF-0030AB B 1591-1.1 H-09 B ST-Q CS-CF2 ICF-0032AB F 1591-1,1 K-13 B ST-Q CS-CF1 1CF-0035AB B 1591-1.1 H-13 B ST-Q CS-CF4 13 ICF-0104AB F 1591-1.1 K-12 B ST-Q CS-CF4 13 1CF-0105AB F 1591-1.1 K-09 B ST-Q CS-CF4 13 1CF-0106AB F 1591-1,1 K-05 B ST-Q CS-CF4 13 1CF-0107AB F 1591-1.1 K-02 B ST-Q 1CF-0126B B 1591-1.1 H-14 B ST-Q CS-CF3 12 CS-CF3 12 1CF-0127B B 1591-1.1 H-10 B ST-Q 1CF-0128B-B 1591-1.1 H-07 B ST-Q CS-CF3 12 CS-CF3 12 1CF-0129B B 1591-1.1 H-03 B ST-Q 12 1CF-0134A B 1591-1.1 G-13 B ST-Q 12 1CF-0135A B 1591-1.1 G-10 B ST-Q 1CF-0136A B 1591-1.1 G-07 B ST-Q 12 12 1CF-0137A B 1591-1.1 G-05 B ST-Q 12 1CF-0151B B 1591-1.1 G-12 B ST-Q CS-CF5 1CF-0152 B 1591-1.1 F-12 C MTC-Q ICF-0153B B 1591-1.1 F-08 B ST-Q 12 1CF-0154 B 1591-1.1 F-08 C MTC-Q CS-CFS 12 ICF-0155B B 1591-1.1 F-07 B ST-Q CS-CFS 1CF-0156 B 1591-1.1 E-07 C MTC-Q 12 ICF-0157B B 1591-1.1 G-12 B ST-Q CS-CFS 1CF-0158 B 1591-1.1 F-12 C MTC-Q

Page No. 5 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRA41 COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • DIESEL GENERATOR ENGINE FL'EL Olt 16 1FD-0092 C

1609-3.0 E-13 C MTO.C-Q - 16 1FD-0093 C 1609-3.0 J-14 C MTO.C-Q 16 1FD-0104 C 1609-3.1 E-13 C MTO.C-Q - 16 1FD-0105 C 1609-3.1 J-14 C MTO.C-Q i

Page No. 6 03/27/91 Duke Power Company McGuire Nuclear Station Pl'MP AND VALVE INSERVICE TESTING PROGRAM VA1VE CL FLOW FLOW CAT TEST TEST RR TEST R DTAGRAM COOR REQ 1 REQ 2 ALTERNAl1VES/ E REMARKS V

• • REFL'ELING WATER 1FW-0001A B 1571-1.0 E-11 B ST-Q 1- ""

FASSIVE 1r'l 60r ' P 1 ' ' l '. ' IFW-0005 B 1571-1.0 C-07 AC 1T-RF PA??TVF PASSIVE IFW-0011 B 1571-1.0 C-02 A LT-RF IFW-0013 B 1571-1,0 D-02 A LT-RF PASSIVE IFW-0027A B 1571-1.0 C-12 B ST-Q CS-FW1 CS-FW2 14 IFW-0028 B 1571-1.0 B-11 C MTO,C-Q - 1FW-0032B B 1571-1.0 E-11 B ST-Q 1FW-0033A B 1571-1.0 F-11 B ST-Q 1FW-0049B B 1571-1.0 F-10 B ST-Q IFW-0052 E 1571-1.0 1-05 C MTO-Q PASSIVE IFW-0067 B 1571-1,0 C-01 AC LT-RF

Page No. 7 03/27/91 Duke Power Company McGuire Fuclear Station PUMP AND VALVE INSERVICE TESTING FROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES! E REMARKS V

• • AIRLOCK 16 11A-5080 B 1499-IA1 N/A A

ST-Q LT-RF 16 11A-5160 B 1499-IA1 N/A A ST-Q LT-RF 16 11A-5340 B 1499-IA1 N/A AC LT-RF 16 11A-5350 B 1499-IA1 N/A AC LT-RF 16 IA1 11A-5360 C 1499-IA1 N/A AC LT-RF 16 IA1 IIA-5370 C 1499-IA1 N/A AC LT-RF 16 IA1 11A-5380 C 1499-IA1 N/A AC LT-RF 16 IA1 11A-5390 C 1499-IA1 N/A AC LT-RF

Page No. 8 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • ' COMPONENT COOLING 1KC-0001A C 1573-1.0 C-07 B ST-Q 1KC-0002B C 1573-1.0 C-08 B ST-Q 1KC-0003A C 1573-1.0 C-07 B ST-Q IKC-0005 C 1573-1.0 F-04 C MTO-Q 1KC-0008 C 1573-1.0 F-04 C MTO-Q IKC-0011 C 1573-1.0 F-11 C MTO-Q 1KC-0014 C 1573-1.0 F-11 C MTO-Q 1KC-0018B-C 1573-1.0 C-08 B ST-Q 1EC-0047 B 1573-4.0 L-12 AC MTC-Q LT-RF KC3 MT-RF 1RC-0050A-C 1573-1.0 K-07 B ST-Q 1KC-0051A C 1573-1.0 J-05 B ST-Q IKC-0053B C 1573-1.0 K-08 B ST-Q 1KC-0054B-0 1573-1,0-J-10 B Sf-Q

~1KC-0056A C 1573-1.1 E-02 B ST-Q IKC-0057A C 1573-1,1 D-06 B ST-Q IKC-0081B C 1573-1.1 E-13 B ST-Q ~1KC-0082B C 1573-1.1 D-09 B ST-Q 1KC-0228B C 1573-1.0 K-08 B ST-Q 1KC-0230A C '1573-1.0 K-07 B ST-Q-IKC-0279 B 1573-3.1 K-04 AC MTC-Q LT-RF KC3 MT-RF IKC-0280 B 1573-3.1 D-01 AC MTC-Q LT-RF kcl-MT-RF 1KC-0305B B 1573-3.1 D-14 B ST-Q-1KC-0315B B 1573-3.1 L-13 B ST-Q 1KC-0320A B 1573-3.1 C-10 A ST-Q LT-RF CS-KC4. '1KC-0322-B 1573-3.1 C-09 AC MTC-Q LT-RF KC2 MT-RF 1KC-0332B B 1573-3.1 'D-01 A ST-Q LT-RF CS-KC3 1KC-0333A -B 1573-3.1 G-01 A ST-Q LT-RF CS-KC3 1KC-0338B B 1573-3.1 D-12 A ST-Q-LT-RF CS-KC2 1KC-0340. B 1573-3.1 E-12 AC MTC-Q LT-RF KC4 MT-RF 16 -1KC-04248 B 1573-3.1 _L-04 A ST-Q LT-RF CS-KC1 -1RC-0425A B 1573-3.1 L-06 A ST-Q LT-RF CS-KC1 D 1KC-0429B B 1573-4.0 K-12 A ST-Q LT-RF IKC-0430A 'B 1573-4.0 K-10 A ST-Q LT-RF f IKC-0800 -C 1573-1.1 1-11 C SP-3R 10 PSIG 16 l-1KC-0897 C 1573-1.0 K-2 C MTC-Q 16 l '1KC-0903 C 1573-1.0 K-13 C MTC-Q 16 L 1EC-0958 C 1573-1.0 I-8 C MTC-Q 16 E 1KC-0972 C 1573-1.1 J-10 C SP-3R 15 PSIG 16

1 Page No. 9 03/27/91 Juke Power Company McGuire Nuclect Station Pt'MP AND YALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REHARKS V

• • DIESEL GENERATOR COOLING WATER 16 1KD-0009 C 1609-1.0 E-14 B FS-Q 16 1KD-0029 C 1609-1,1 E-14 B

FS-Q l

Page No. 10 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARRS V

• • RADIATION MONITORING 16 IMI-5580 B 1499-MI7 N/A A

ST-Q LT-RF 16 1MI-5581 B I499-MI7 N/A A ST-Q LT-RF 16 1MI-5582 B 1499-MI7 N/A A ST-Q LT-RF 16 IMI-5583 B 1499-MI7 N/A A ST-Q LT-RF i

Page No, 11 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGPAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V BORON RECYCLE INB-0260B B 1556-3,0 G-05 A ST-Q LT-RF INB-0262 B 1556-3,0 G-03 AC MTC-Q LT-RF NB1 MT-RF i ._--._.______mm_

Page No. 12 03/27/91 Duke Power Company McGuire Nuclear Station Pt3tP AND VALVE INSERVICE TESTING PROCRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • REACTOR COOLANT INC-0001 A 1553-2.0 J-09 C SP-3Y 2485 PSIG 2485 PSIG INC-0002 A 1553-2.0 J-10 C SP-3Y 2485 PSIG INC-0003 A 1553-2.0 J-11 C SP-3Y INC-0031B A 1553-2.0 H-06 B ST-Q CS-NC1 16 INC-0032B-A 1553-2.0 J 06 B ST-Q INC-0033A A 1553-2.0 H-L4 B ST-Q CS-NC1 16 1NC-0034A A 1553-2.0 J-04 B ST-Q INC-0035B A 1553-2.0 H-02 B ST-Q CS-NC1 16 INC-0036B A 1553-2.0 J-02 B ST-Q 1NC-0053B B 1553-2.1 1-10 A ST-Q LT-RF INC-0054A B 1553-2.1 1-08 A ST-Q LT-RF INC-0056B B 1553-2,1 E-13 A ST-Q LT-RF PASSIVE 1NC-0057 B 1553-2.1 G-12 AC LT-RF INC-0141 B 1553-4.0 B-06 A PC-Q LT-RF PASSIVE PASSIVE INC-0142 B 1553-4.0 B-05 A PC-Q LT-RF PASSIVE INC-0195B B 1553-4.0 K-07 A LT-RF PASSIVE INC-0196A B 1553-4.0 1-07 A LT-RF 1NC-0259 B 1553-4.0 1-07 AC MTC-Q LT-RF NC1 MT-RF*

INC-0261 B 1553-4.0 B-07 AC MTC-Q LT-RF NC1 MT-RF* CS-NC2 .16 INC-0272AC A 1553-2.1 L-07 B ST-Q CS-NC2 16 INC-0273AC A 1553-2,1 L-07 B ST-Q CS-NC2 16 1NC-0274B A 1553-2.1 K-07 B ST-R CS-NC2 16 INC-0275B A 1553-2.1 K-07 B ST-Q

Page No. 13 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM _ VALVE. CL-FLOW FLOW ~ CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V t

• • RESIDUAL HEAT. REMOVAL IND-0001B' A 1561-1.0 1-13 A ST-Q LT-TS CS-ND1 PIV L1ND-0002AC A 1561-1.0

-H-13 A ST-Q LT-TS CS-ND1 PIV 1ND-0004B B 1561-1.0 E-12 B ST-Q ~IND-0008 B 1561-1.0 D-08 C MTO.C-Q CS-ND6 14 1ND-0014. B.1561-1.0 D-03 B ST-Q IND-0015B. B.1561-1.0 E-03 B ST-Q CS-ND3 1ND-0019A B 1561-1.0 H-12 B ST-Q IND-0023 B 1561-1.0 J-08 C MTO,C-Q - CS-ND6 14 1ND-00?9 B 1561-1.0 J-03 B ST-Q IND-0030A B-1561-1.0 I-03 B ST-Q CS-ND3 L IND-0058A .B 1561-1.0 K-03 B. ST-Q CS-ND2 j. 1ND-0067B B 1561-1.0 .B-09 D ST-Q L 1ND-0068A .B. 1561-1.0 L-09 B ST-Q IND-0070 B.1561-1,0 K-03 C MTO.C-Q CS-ND4 14 1ND-0071 B 1561-1.0 C-04 C MTO C-Q CS-NDS 14 i I L

Page No. 14 03/27/91 Duke Power Company McGuire Nuclear Station PlfMP ANb VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • ICE CONDENSOR REFRIGATION INF-0228A B 1558-4.0 H-13 A ST-Q LT-RF LT per TS 16 1NF-0229 B 1558-4.0 F-13 AC MTC-Q LT-RF NF1 MT-RF*

1NF-0233B B 1558-4.0 K-12 A ST-Q LT-RF LT per TS 16 1NF-0234A B 1558-4.0 K-13 A ST-Q LT-RF LT per TS 16 l l } l l I l i I

PaBe No. 15 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • SAFETY INJECTION CS-nil INI-0009A B 1562-1.0 H-09 B ST-Q CS-nil INI-0010B-B 1562-1.0 G-09 B ST-Q CS-NI14 14 1NI-0012-B 1562-1.0 G-08 C MTO-Q CS-NI13 14 1NI-0015 A 1562-1.0 K-07 C MTO-Q CS-NI13 14 1NI-0017 A 1562-1,0 1-07 C MTO-Q CS-N113 14 1NI-0019 A 1562-1.0 F-07 C MTO-Q CS-NI13 14 INI-0021 A 1562-1.0 D-07 C MTO-Q INI-0047A B 1562-2.0 K-05 A ST-Q LT-RF INI-0048 B 1562-2.0 N-03 AC MTC-Q LT-RF N13 MT-RF*

INI-0054A DELETED 13 1NI-0059 . A-1562-2.0 D-13 AC MTO.C-Q LT-TS NI4 PIV RF# INI-0060 .A 1562-2.0 D-14 AC MTO,C-Q LT-TS NI6 PIV RF# IN1-0065B DELETED 13 1NI-0070 A 1562-2.0 H-13 AC MTO.C-Q LT-TS NI4 PIV RFo 1NI-0071 A 1562-2.0 H-13 AC MTO.C-Q LT-TS NI6 PIV RF#

• 5 -2276A DELETED 13 1!:T-0021 7.

1 *f. 2 - 2.1 C-01 \\C '!T ^ "- ; iT T' N:' TI'J "r" '1NI-0082 -A 1562-2.1 C-03 AC MTO.C-Q LT-TS NI6 PTV RFn INI-0088B DELETED 13' INI-0093 A 1562-2.1 C-08 AC MTO.C-Q LT-TS NI4 PIV RF# INI-0094 A 1562-2.1 C-08 'AC MTO.C-Q LT-TS NI6 PIV RF# INI-0095A B 1562-2.1 F-12 A-ST-Q LT-RF 1NI-0096B B-1562-2,1 E-13 A' ST-Q LT-RF CS-NI3 1NI-0100B-B 1562-3,0 F-13 B ST-Q CS-NI15 14 1NI-0101 'B 1562-3,0. F-13 C MTO.C-Q 1NI-0103A B 1562-3.0 :J-14 B ST-Q 1NI-0114 B 1562-3,0 I-09 C MTO-Q 1NI-0115B B 1562-3.0 .H-09 B ST-Q CS-NI16 14 1NI-0116 B 1562-3.0 J C MTO C-Q 1NI-0118A B 1562-3.0 H-07 B ST-Q IN1-0120B B 1562-3,0 J-07 A ST-Q LT-RF CS-NIS INI-0121A B 1562-3.0 J-06 B ST-Q PIV CS-NI17 14-INI-0124 A 1562-3.0 J-03 AC MTO.C-Q LT-TS PIV CS-NI20 14 INI-0125 A 1562-3.0 I-03 AC MTO,C-Q LT-TS INI-0126 A 1562-3.0 J-02 AC MTO.C-Q LT-TS-PIV CS-NI20 14-INI-0128 A 1562-3.0 1-04 AC MTO.C-Q LT-TS PIV CS-NI17 14 PIV CS-N120 14 1NI-0129 A 1562-3.0 1-03 AC MTO.C-Q LT-TS 'PIV CS-NI20 14 1NI-0134 A 1562-3.0 G-04 AC MTO.C-Q LT-TS a 1NI-0135B B 1562-3.0 E-14 B ST-Q INI-0136B B 1562-3.0 C-14 B ST-Q CS-NI21 16 INI-0143 B 1562-3,0 F-09 C MTO.C-Q INI-0144B B 1562-3.0 G-09 B ST-Q 1NI-0147A B 1562-3.0 G-11 B ST-Q CS-NI4 1NI-0148 B 1562-3.0 D-09 C MTO.C-Q - CS-NI16 14 1NI-0150B B 1562-1.0 E-07 B ST-Q

Page No. 16 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V CS-NI6 1NI-0152B B 1562-3.0 D-06 B ST-Q PIV CS-N117 14 1NI-0156 A 1562-3,0 D-03 AC MTO.C-Q LT-TS PIV CS-NI17 14 1NI-0157 A 1562-3,0 D-02 AC MTO,C-Q LT-TS PIV CS-NI17 14 1NI-0159 A 1562-3,0 B-04 AC MTO.C-Q LT-TS PIV CS-NI17 14 1NI-0160 A 1562-3.0 B-03 AC MTO.C-Q LT-TS CS-NI7 1NI-0162A B 1562-3.1 K-11 B ST-Q PIV CS-NI18 14 1NI-0165 A 1562-3.1 J-03 AC MTO.C-Q LT-TS PIV CS-NI18 14 1NI-0167 A 1562-3.1 J-05 AC MTO C-Q LT-TS PIV CS-NI18 14 1NI-0169 A 1562-3.1 J-06 AC MTO.C-Q LT-TS PIV CS-NI18 14 1NI-0171 A 1562-3.1 J-07 AC MTO.C-Q LT-TS CS-NI8 1NI-0173A B 1562-3.1 I-12 B ST-Q PIV CS-NI19 14 INI-0175 A 1562-3,1 1-08 AC MTO.C-Q LT-TS PIV CS-NI19 14 1NI-0176 A 1562-3.1 H-08 AC MTO,C-Q LT-TS CS-N19 1NI-0178B B 1562-3,1 F-12 B ST-Q 1NI-0180 A 1562-3.1 F-06 AC MTO.C-Q L1-TS PIV CS-NI19 14 PIV CS-NI19 14 1NI-0181 A 1562-3,1 D-05 AC MTO.C-Q LT-TS CS-nil 0 1NI-0183B B 1562-3,0 G-03 B ST-Q CS-N111 INI-0184B B 1562-3.1 D-12 B ST-Q CS-Nill 1NI-0185A B 1562-3.1 B-12 B ST-Q 1NI-0332A B 1562-3.0 L-14 B ST-Q 1NI-0333B B 1562-3,0 L-12 B ST-Q 1NI-0334B B 1562-3.0 L-11 B ST-Q CS-NI13 14 INI-0347 A 1562-1.0 1-07 C MTO-Q CS-NI13 14 1NI-0348 A 1562-1.0 F-07 C MTO-Q CS-NI13 14 1NI-0349 A 1562-1.0 D-07 C MTO-Q 1NI-0354 A 1562-1.0 K-07 C MTO-Q CS-NI13 14 CS-NI2 1NI-04304 B 1562-2.0 E-04 B ST-Q CS-N12 INI-0431B B 1562-2.0 J-04 B ST-Q INI-0436 B 1562-2.1 G-11 AC MTC-Q LT-RF NIS MT-RF*

Page No. 17 03/27/91 l Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING FROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • NUCLEAR SAMPLING INM-0003AC B 1572-1.0 K-03 A ST-Q LT-RF 1NM-0006AC D 1572-1.0 J-03 A ST-Q LT-RF INM-0007B B 1572-1.0 K-06 A ST-Q LT-RF INM-0022AC B 1572-1.0 J-12 A ST-Q LT-RF INM-0025AC B 1572-1.0 K-12 A ST-Q LT-RF INM-0026B B 1572-1.0 K-08 A ST-Q LT-RF PASSIVE INM-0069 B 1572-1.1 G-09 AC Lf-RF 1NM-0072B B 1572-1.1 1-06 A ST-Q LT-RF INM-0075B B 1572-1,1 1-08 A ST-Q LT-RF INM-0078B B 1572-1.1 1-09 A ST-Q LT-RF INM-0081B B 1572-1.1 1-11 A ST-Q LT-RF INM-0082A B 1572-1.1 E-09 A ST-Q LT-RF INM-0187A B 1572-3.0 K-01 B ST-Q INM-0190A B 1572-3.0 K-02 B ST-Q INM-0191B B 1572-3.0 1-02 B ST-Q 1NM-0197B B 1572-3.0 K-05 B ST-Q INM-0200B B 1572-3,0 K-06 B ST-Q 1NM-0201A B 1572-3.0 1-06 B ST-Q INM-0207A B 1572-3,0 K-08 B ST-Q INM-0210A B 1572-3.0 K-09 B ST-Q INM-0211B B 1572-3.0 1-09 B ST-Q INM-0217B B 1572-3.0 K-11 B ST-Q INM-0220B B 1572-3,0 K-12 B ST-Q 1NM-0221A B 1572-3.0 1-12 B ST-Q INM-0420 B 1572-1.0 J-03 AC MTC-Q LT-RF NM1 MT-RF*

INM-0421 B 1572-1.0 J-12 AC MTC-Q LT-RF NM1 MT-RF*

Page No. 18 03/27/91 Duke Power Company McGuire Nuclear Station PLMP AND YALVE INSERVICE TESTING PROGRA,M VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COCK REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT SPEAY 1NS-0001B B 1563-1.0 C-13 B ST-Q INS-0003B B 1563-1.0 B-13 B

$T-Q NS2 RF# 16 INS-0004 B 1563-1.0 B-12 C MTO.C-Q 1NS-0012B B 1563-1.0 C-04 B ST-Q INS-0013 B 1563-1.0 B-02 C MTO-i, NS1 RF# INS-0015B B 1563-1.0 D-04 B ST-Q NS1 RF# INS-0016 B 1563-1.0 D-02 C MTO-Q 1NF-0018A B 1563-1.0 0-13 B ST-Q INS-0020A B 1563-1.0 F-13 B ST-Q NS2 RF# 16 INS-0021 B 1563-1.0 F-12 C MTO.C-Q INS-0029A B 1563-1.0 F-04 B ST-Q NSI RF# INS-0030 B 1563-1.0 F-02 C MIO-Q 1NS-0032A B 1563-1.0 11 - 0 4 B ST-Q NSI RF# 1NS-0033 B 1563-1.0 H-02 C MTO-Q CS-NS1 16 1NS-0038B B 1563-1.0 J-05 B ST-Q NS1 RF# INS-0041 B 1563-1.0 J-03 C MTO-Q CS-NS1 16 INS-0043A B 1563-1.0 K-05 B ST-Q NS1 RF# INS-0046 B 1563 1.0 K-03 C MTO-Q 16 INS-5550B B 1499-NSB N/A A ST-Q LT-RF 16 INS-5551A B 1499-NS8 N/A A ST-Q LT-RF

Page No. 19 03/27/91 Duke Power Company McGuire Nuclear Station Pl'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTLRNATIVES/ E REMARKS V

• • CHEMICAL AND Y0tt'ME CONTROL INV-0001A DELETED 16 INV-0002A DELETED 16 CS-NV2 INY-0007B B 1554-1.2 J-10 B ST-Q CS-NV4 16 INY-CA21A A 1554-1.2 E-03 B ST-Q INV-0022 DELETED 16 16 INY-0024B A 1554-1,2 D-06 B ST-Q 16 INY-0025B A 1554-1.2 D-07 B ST-Q 14 INV-0035A B 1554-1.2 R-07 B ST-Q CS-NV1 INY-0094AC B 1554-1.1 J-13 B ST-Q CS-NV1 U:V-0095B B 1554-1.1 H-13 B ST-Q CS-NV7 INV-0141A B 1554-2.0 B-0B B S1-9 CS-NV7 INY-0142B B 1554-2.0 B-07 B ST-Q CS-NV12 12 INV-0150B B 1554-2.0 F-02 B ST-Q CS-NV12 12 INV-0151A B 1554-2.0 G-02 B ST-Q CS-NV9 INY-0221A B 1554-3.1 H-01 B ST-Q CS-NV9 INY-0222B B 1554-3.1 1-01 B ST-Q CS-NV15 14 INV-0223 B 1554-3.1 1-02 C MTO.C-Q CS-NV14 14 1NV-0225 B 1554-3.1 F-05 C MTO.C-Q 1NV-0227 B 1554-3.1 E-06 C MTO.C-Q CS-NV14 14 INY-0231 B 1554-3.1 0-10 C MTO.C-Q 1NV-0233 B 1554-3.1 E-10 C MTO.C-Q CS-NV8 1NV-0244A B 1554-3.0 K-08 B ST-Q CS-NV8 INY-0245B B 1554-3.0 K-09 B ST-Q CS-NV11 INV-0264 B 1554-3.1 J-10 C MTO-Q CS-NV13 12 INY-0265B B 1554-3.1 J-09 B ST-Q NV4 RF#

12 INV-0411 C 1154-5.0 0-02 C MTO-Q NV4 RF# 12 INV-0413 C 1554-5.0 B-02 C MTO-Q 16 INY-0457A B 1554-1.2 1-07 B ST-Q 1NY-0458A B 1554-1.2 J-07 B ST-Q INV-0459A DELETED 14 1NV-0842AC DELETED 16 INY-0844 DELETED 16 INY-0849AC B 1554-1,3 F-08 A ST-Q LT-RT 1NV-1002 B 1554-1,3 T-10 AC MTC-Q LT-RF NV1 RF 16 INV-1007 DELETED 16 INV-1008 DELETED 16 1NV-1009 DELETED 16 INV-1010 DELETED 16 1NV-1012C DELETED 16 hV-1013C DELETED 16 CS-NV16 16 INV-1046 B 1554-3,0 H-12 C MTC-Q

Page No. 20 03/27/91 Duke Power Company

• ";Cuire Nuclear Station 7""? '.'T ' '.'.'.:.t T ';r *,y t

..p 7 77... VALVE CL TI.0W FLOW CAT TFST TT?T l'R TF?' F. DIAGRAM C00R REQ 1 REQ 2 ALTERNATIVES / E R NARRS Y

• • FIRE PROCTECTION 1RF-0821A B 1$99-2,2 E-05 A LT-RT PASSIVE 1RF-0823 B 1599-2,2 E-07 AC MTC-Q LT-RF RT1 MT-RF*

1RT-0832A B 1$99-2.2 1-05 A LT-RF PASSIVE, U2CIV 1RF-0834 B 1$99-2,2 1-08 AC HTC-Q LT-RF RF1 MT-RT*. U2CIV L i ~ l l i. l l , -.. -.....,,, -.. ~

l Page No. 21 03/27/91 Duke Power Company McGuire Nuclear Station Pl'MP AND VALVE INSERVICE TESTING PROGRAM YALVE CL F1.0W FLOW CAT 1EST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • NUCLEAR SERVICE WATER IkN-0016A C 1574-1,1 J-03 B ST-Q 1RN-0018B C 1574-1.1 E-02 B ST-Q 16 1kN-0021A C 1574-1.1 J-02 B ST-Q 16 1RN-0022A C 1574-1.1 H-05 B ST-Q 16 1RN-0025B C 1574-1.1 C-04 B ST-Q 16 1RN-0026B C 1574-1.1 G-05 B ST-Q 1RN-0028 C 1574-1.1 J-09 C MTO-Q 1RN-0030 C 1574-1.1 E-09 C MTO-Q 1RN-0040A C 1574-1.1 1-12 B ST-Q U1 & U2 SIGNAL 1RN-0041B C 1574-1.1 F-12 B ST-Q CS-RN4 16 1RN-0042A C 1574-4.0 B 09 B ST-Q U1 6 U2 SIGNAE 1RN-0043A C 1574-1.1 F-12 B ST-Q CS-RSS 16 1RN-0063B C 1574-1.0 1-02 B ST-Q CS-RN5 16 1RN-0064A C 1574-1.0 I-02 B ST-Q 16 1RN-0068A C 1574-1.1 K-12 B ST-Q 1RN-0069A C 1574-2.0 K-03 B ST-Q 1RN-0070A C 1574-2.0 T-03 B ST*Q 1RN-0073A C 1574-2.0 1-03 B ST-Q 1RN-0086A C 1574-2.0 D-09 B ST-Q 1RN-0089A C 1574-2.0 J-10 B ST-Q 16 1RN-0103A C 1574-2.1 C-06 B ST-Q 16 1RN-0112A C 1574-2.0 1-06 B ST-Q RN1 RF#

1RN-0113 C 1574-2.0 D-13 C MTO-Q 16 1RN-0114A C 1574-2.1 B-11 B ST-Q 16 1RN-0117A C 1574-2.0 I-08 B ST-Q 16 1RN-0126A C 1574-2.1 D-09 B ST-Q 16 1RN-0130A C 1574-2.1 C-10 B ST-Q 1RN-0134A C 1574-2.1 C-07 B ST-Q 1RN-0137A C 1574-2.1 H-07 B ST-Q 16 1RN-0140A C 1574-2.0 E-13 B ST-Q 16 1RN-0161B C 1574-1.1 B-13 B ST-Q 1RN-0162b C 1574-3,0 K-03 B ST-Q 16 1RN-0166A C 1574-2.0 J-02 B ST-Q 16 1RN-0170B C 1574-3.0 1-01 B ST-Q 1RN-0171B C 1574-3.0 E-03 B ST-Q 1RN-0174B C 1574-3.0 I-03 B ST-Q 1RN-0187B C 1574-3.0 E-10 B ST-Q 1RN-0190B C 1574-3.0 J-10 B ST-Q 16 1RN-0204B C 1574-3.1 C-05 B SI-Q 16 1RN-0213B C 1574-3.0 J-06 B ST-Q RN1 RF# 1RN-0214 C 1574-3.0 D-13 C MTO-Q 16 1RN-0215B C 1574-3.1 B-11 B ST-Q 16 1RN-0218B C 1574-3.0 1-08 B ST-0 16 1RN-0227B C 1574-3.1 E-10 B ST-Q 16 1RN-0231B C 1574-3.1 C-10 B ST-Q

Page No 22 03/27/91 Duke Power Cornpany McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOP REQ 1 itEQ2 ALTERNATIVES / E REMARKS Y ~ 1RN-0235B C 1574-3.1 E-07 B ST-Q 1RN-0238B C 1574-3.1 1-07 B ST-Q 16 1RN-0240B C 1574-3.0 E-13 B ST-Q CS-RN2 16 1RN-0252B C 1574-4.0 E* 92 A ST-Q LT-RF CS-RN2 16 1RN-0253A C 1574-4.0 C-02 A ST-Q LT-RF CS-RN3 16 1RN-0276A C 1574-4.0 J-02 A ST-Q LT-RF CS-RN3 16 1RN-0277B C 1574-4.0 I-02 A ST-Q LT-RF 1RN-0279B C 1574-1;0 K-02 B ST-Q 1RN-0296A C 1574-1.0 1-01 B ST-Q 1RN-0297B C 1574-1.0 G-02 B ST-Q 1RN-0299A C 1574-1.0 K-02 B ST-Q 16 1RN-0442 C 1574-2.0 J-11 B ST-Q 16 1RN-0445 C 1574-2.0 J-11 B ST-Q 16 1RN-0457 C 1574-3.0 J-11 B ST-Q 16 1RN-0460 C 1574-3.0 J-11 B ST-Q

l Page No. 23 03/27/91 Duke Tower Company McGuire Nuclear Station M'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT VENTILATION COOLING WATER CS-RV1 1RV-0032A B 1604-3.0 R-10 A ST-Q LT-RF CS-RV1 1RV-0033B B 1604-3.0 R-12 A ST-Q LT-RF CS-RV1 1RV-0076A B 1604-3.0 C-12 A ST-Q LT-RF CS-RV1 1RV-0077B B 1604-3.0 C-10 A ST-Q LT-RF 1RV-0079A B 1604-3.0 K-07 A ST-Q LT-RF 1RV-0080B B 1604-3.0 R-05 A ST-Q LT-RF 1RV-0101A 3 1604-3.0 C-05 A ST-Q LT-RF 1RY-0102B B 1604-3,0 C-07 A ST-Q LT-RF 1RV-0126 B 1604-3.0 B-12 AC MTC-Q LT-RF RV1 MT-RF*

1RV-0130 B 1604-3.0 J-12 AC MTC-Q LT-RF RV1 MT-RF*

- - =.. -. Page No. 24 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE TNSERVICE TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • MAIN STEAM TO Al'X. EQtTIPMENT ISA-0005 B 1593-1.2 F-04 C MTO.C-Q 14 1SA-0006 B -1593-1.2 T-04 C MTO.C-Q 14 ISA-0048ABC.B 1593-1.2 E-04 B ST-Q 1SA-0049AB B 1593-1.2 F-02 B ST-Q l

r v r e,n,,, -m

Page No. 25 03/27/91 Duke Power Company McGuire Nuclear Station Pl*MP AND VALVE INSERVICE TESTING FROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMAPIS V

• • MATN STEAM CS-SM1 1SM-0001AB B 1593-1,3 1-14 B ST-Q CS-SM1 1SM-0003AB B 1593-1.3 C-14 B ST-Q CS-SM1 ISM-0005AB B 1$93-1.0 1-14 B ST-Q CS-SM1 ISM-0007AB B 1593-1.0 C-14 B ST-Q 16 ISM-0009AB B 1593-1.3 1-13 B ST-Q

?6 ISM-0010AB B 1593-1.3 C-13 B ST-Q 16 ISM-0011AB B 1593-1.0 1-13 B ST-Q 16 ISM-0012AB B 1593-1.0 C-13 B ST-Q

Page No. 26 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL PLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • MAIN STEAM VENT TO ATMOSPHERE ISV-0001AB B 1593-1,3 L-05 B ST-Q 1170 PSIG ISV-0002 B 1593-1.3 K-06 C SP-5Y 1190 PSIG ISV-0003 B 1593-1.3 K-07 C SP-5Y 1205 PSIG ISV-0004 B 1593-1.3 K-09 C SP-5Y 1220 PSIG ISV-0005 B 1593-1,3 K-11 C SP-5Y 1225 PSIG ISV-0006 B 1593-1,3 K-12 C SP-5Y ISV-0007ABC B 1593-1.3 G-05 B ST-Q 1170 PSIG ISV-0008 B 1593-1.3 E-06 C SP-5Y 1190 PSIC ISV-0009 B 1593-1.3 E-07 C SP-5Y 1205 PSIG I SV-0 !G B 1593 1.3 E-09 C SP-5Y 1220 PSIG ISV 0011 B 1593-1.3 E-11 C SP-5Y 1225 PSIC 15V-0012 B 1593-1,3 E-12 C SP-5Y ISV-0013AB B 1593-1.0 L-04 B ST-Q 1170 PSIG ISV-0014 B 1593-1.0 K-05 C SP-5Y 1190 PSIG ISV-0015 B 1593-1.0 K-07 C SP-5Y 1205 PSIG ISV-0016 B 1593-1.0 K-09 C SP-5Y 1220 PSIG ISV-0017 B 1593-1.0 K-10 C SP-5Y 1225 PSIG ISV-0018 B 1593-1.0 K-12 C SP-5Y ISV-0019AB B 1593-1.0 G-04 B ST-Q 1170 PSIG ISV-0020 B 1593-1.0 E-05 C SP-5Y 1190 PSIG ISV-0021 B 1593-1.0 E-07 C SP-5Y 1205 PSIG ISV-0022 B 1593-i.0 E-09 C SP-Si 1220 PSIG ISV-0023 B 1593-1.0 E-10 C SP-5Y 1225 PSIG ISV-0024 B 1593-1.0 E-12 C SP-5Y i

Page No. 27 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V - ** BREATHING AIR IVB-0049B B 16C5-3.1 G-02 A ST-Q LT-RF IVB-00$0 B 1605-3.1 E -O t. AC MTC-Q LT-RF VB1 MT-RT* l I I 1.

Page No. 28 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL ELOW FLOW CAT TEST TEST RR TEST P DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTROL AREA VENTILATION 16 IVC-0001A NA 1578-1 1-13 B ST-Q 16 IVC-0002A NA 1578-1 1-13 B ST-Q 15 1VC-0003B NA 1578-1 1-13 B ST-Q 16 IVC-0004B NA 1578-1 11 - 1 3 B ST-Q 16 IVC-0009A NA 1578-1 E-13 B ST-Q 16 IVC-0010A NA 1578-1 D-13 D ST-Q 16 IVC-0011B NA 1578-1 E-13 B ST-Q 16 IVC-0012B NA 1578-1 D-13 B ST-Q

_.m..._-.m__.---___mm_,___

1 Page No, 29 03/27/91 Duke Power Company McGuire Nuclear Station PlHP AND VALVE INSERVICL TESTING PROGRAM VALVE CL FLOW TLOW CAT TEST TEST RR TF.ST H DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKG V .........r.,.. y 7 ;.,,. p.. IVE-nonM P 1

• f, ', - 1 G-O',

A ?T-Q iT-FJ IVE-00068-B 1564-1 0-04 A ST-Q LT-RT IVE-0008A B 1564-1 J-02 B ST-Q IVE-0010A-B 1564-1 H-03 A ST-Q LT-RT PASSIVE IVE-0011 B 1$64-1 H-03 AC LT-RF' i ? b l-f l

Iage No. 30 03/27/91 Duke Power Cornpany McGuire Nuclear Station Pl'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGPRI COOR REQ 1 REQ 2 ALTERNATIVES / E REN RKS V

• • DIESEL GENERATOR STARTING AIR 16 IVG-0003 C 1609-4.0 J-12 C MTO-Q 16 IYG-0004 C 1609-4.0 E-12 C MTO-Q CS-VG1 16 IVG-0017 C

1609-4.0 J-06 C MTO-Q CS-VG1 16 1YG-0018 C 1609-4.0 1-06 C MTO-Q CS-YG1 16 IVG-0019 C 1609-4.0 E-06 C MTO-Q CS-YG1 16 IVG-0020 C 1609-4.0 D-06 C MTO-Q 16 IVG-0061 C 1609-4.0 K-02 B ST-Q 16 IVG-0062 C 1609-4.0 K-02 B ST-Q 16 IVG-0063 C 1609-4.0 11 - 0 2 B ST-Q 16 IVG-0064 C 1609-4.0 1-02 B S1-Q 16 IVG-0065 C 1609-4.0 E-02 B ST-Q 16 IVG-0066 C 1609-4.0 F-02 B ST-Q 16 IVG-0067 C 1609-4.0 C-02 B ST-Q 16 1VG-0068 C 1609-4.0 C-02 B ST-Q IVG-0115 C 1609-4.0 E-09 C MTO-Q IVG-0116 C 1609-4.0 11 - 0 9 C MTO-Q IVG-0117 C 1609-4.0 f-09 C MTO-Q IVG-0118 C 1609-4.0 C-09 C MTO-Q

Page No. 31 03/27/91 Duke Power Company McGuire Nuclear Statton PtHP AND VALVE INSERVICE TESTINC PROCRAM YALVE CL FLOW FLOW CAT IEST 1EST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARRS V

• • INSTRtHENT AIR IVI-0040 B 1605-1,3 11 - 0 4 AC MTC-Q LT-RF V12 MT-RF*

16 1VI-0124 8 1605-1.2 D-03 AC MTC-Q LT-RF VII MT-RT* 16 IVI-0129B B 1605-1.17 J-06 A ST-Q LT-RF 16 IVI-0135 C 1605-1.13 1-10 AC M7C-Q LT V13 16 IVI-0136 C 1605-1.13 1-10 AC MTC-Q LT V13 16 IVI-0137 C 1605-1.13 J-04 AC MTC-Q LT VI3 16 117-0138 C 1605-1.13 J-03 AC MTC-Q LT VI3 16 IV1-0139 C 1605-1.13 H-04 AC MTC-Q LT VI3 16 IVI-0140 C 1605-1.13 11 - 0 3 AC MTC-Q LT V13 16 IVI-0141 C 1605-1.13 I-09 AC MTC-Q LT VI3 16 IVI-0142 C 1605-1.13 1-09 AC MTC-Q LT V13 16 IVI-0148B B 1605-1.14 C-04 A ST-Q LT-RF 16 -1VI-0149 8 1605-1.2 1-03 AC MTC-Q LT-RF VII MT-RF* 16 IVI-0150B B 1605-1.14 B-03 A ST-Q LT-RF 16 IVI-OlbOB B 1605-1.17 C-06 A ST-Q LT-RT 16 IVI-0161 B 1605-1,3 E-04 AC MTC-Q LT-RF -VI2 MT-RF* 16 IVI-0362A B 1605-1.2 1-02 A ST-Q LT-RF 16

Page No. 32 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND YALVE TNSERVICE TESTING PROGRAM YALVE CL TLOW TLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTLRNATIVES/ E REMARKS V

• • CONTAINMENT PL*RGE VENTILATION

-IVP-0001B- =B-1576-1 1-06 A LT-TS 14 IVP-0002A B 1576-1 1-07 A LT-TS 14 1\\T-0003B B 1576-1 K-06 A LT-TS 14 IVP-0004A B 1576-1 K-07 A LT-TS 14 IVP-0006B B 1576-1 E-06 A LT-TS 14 IVP-0007A B 1576-1 E-07 A LT-TS 14 IVP-0008B B 1576-1 D-06 A LT-TS 14 IVP-0009A B 1576-1 D-07 A LT-TS 14 IVP-0010A B 1576-1 J-08 A LT-TS 14 IVP-0011B B 1576-1 J-09 A LT-TS 14 IVP-0012A B 1576-1 1-08 A LT-TS 14 IVP-0013B B 1576-1 1-09 A LT-TS 14 IVP-0015A B 1576-1 F-08 A LT-TS i 14 IVP-0016B B 1576-1 T-09 A LT-TS 14 IVP-0017A B 1576-1 B-07 A LT-TS 14 IVP-0018B B 1576-1 B-06 A LT-TS 14 IVP-0019A B 1576-1 B-08 A LT-TS 14 r IVP-0020B B' 1576-) B-09 A LT-TS 14 l l l. l L t .. _ _ _,, ~.., -l

Page No. 33 i 03/27/91 Duke Power Company McGuire Nuclear Station PtHP AND VALVE INSERVICE TESTING PROGRAM VALVE CL 0 LOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT AIR RELEASE AND ADDITION 16

-1VQ-0001A B 1585-1.0 J-04 A ST-Q LT-RF 16 IVQ-0002B B 1585-1.0' J-06 A ST-Q LT-RF -16 1YQ-000$B B 1$85-1.0 E-06 A ST-Q LT-RT I 16 IVQ-0006A B 1585-1.0 E-03 A ST-Q LT-RF i= i-i

Page No. 34 03/27/91 Duke Power Company McGuire Nuclear Station Pl'MP AND VALVE INSERVICE TLSTING I'ROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / t REHARKS V

• • STATION AIR 1YS-00120 B 1605-2.2 K-05 A S1-Q LT-KF IVS-0013 B 1605-2,2 1-05 AC MTC-Q LT-RT VS1 MT-RF
• Page No.

35 03/27/91 Duke Power Cornpany McGuire Nuclear Station ITMP AND YALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 PEQ2 ALTERNATIVES / E REMARKS V

• • CONT. ATR RETl'RN EXC}lANGE AND tlYDROGEN ADD.

IVX-0001A B 1557-1 1-03 B ST-Q IVX-0002B B 1557-1 1-12 B ST-Q IVX-0030 B 1557-1 J-03 AC MTC-Q LT-RT VX1 MT-RF 16 IVX-0031A B 1557-1 J-13 A ST-Q LT-RF 16 IVX-0033B B 1557-1 J-12 A ST-Q LT-RF PASSIVE IVX-0034 B 1357-1 K-12 A LT-RF PASSIVE IVX-0040 B 1557-1 K-03 A LT-RF

Page No. 36 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST 11'ST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / L REMARES V

• • EQUll'MI.NT DECONTAMINATION PASSIVE IWE-0013 B 1568-1.0 E-06 A LT-RF PASSIVE 1WE-0023 11 1568-1,0 E-10 A LT-RF i

Page No. 37 03/27/91 Duke Power Company McGuire Nucient Station Pl'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIYLS/ E REMARRS V

• • LIQUID WASTE RECYCLE IWL-0001B B 1565-1.1 L-11 A ST-Q LT RF Iki-0002A B 1565-1.1 R-13 A ST-Q LT-RT 1WL-0024 B 1565-1.1 J-14 AC MTC-Q LT-RF WL2 MT-RT*

IWL-0039A B 1565-1.1 J-05 A ST-Q LT-RT 1WL-0041B B 156$-1,1 R-05 A ST-Q LT-RT Iki-0064A B 1565-1.0 J-03 A ST-Q L1-RT 1hl-0065B B 1565-1.0 R-05 A ST-Q LT-RF IWL-0264 11 1565-1.0 J-02 AC LT-RF PASSIVE IWL-0321A B 1565-7.0 H-07 A ST-Q LT-RT 1WL-0322B-B 1565-7.0 1-06 A ST-Q LT-RT 1WL-0385 B 1565-7.0 H-07 AC ~MTC-Q LT-RI' WL3 MT-RF* 1WL-0466 DELETED 14 IWL-1301B B 1565-1.0 G 03 A ST-Q LT-RF 1WL-1302A A 1565-1.0 E-04 A ST-Q LT-RF i i L L i

s Page No. 38 03/27/91 Duke Power Company McGuire Nuclear Station P(MP AND YALVE INSERVICE TESTING l'ROGRAM VALVE CL ELOW FLOW CAT TEST TEST RR T ES1 R DIAGRAM COOR REQ 1 REQ 2 AETERNA11YES/ E REMARKS V DIESEE GENERATOR ROOM StHP PLMP 1WN-0003 C 1609-7.0 L-11 C MTO,C-Q IWN-0005 C 1609-7.0 K-11 C MTO.C-Q IWN-0007 C 1609-7.0 J-11 C MTC-Q 1WN-0011 C 1609-7.0 E-11 C M10,C-Q 1WN-0013 C 1609-7.0 E-11 C MTO.C-Q 1WN-0015 C 1609-7.0 D-11 C MTC-Q i i I

_..__-.m i Page'No. 39 03/27/91 + Duke Power Company McCuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • CONTROL AREA CHILLED' WATER 1YC-0002A C 1618-1 H-02 11 ST-Q 1YC-0013 C 1618-1 K-09 C MTO-Q 1YC-0014

.c 1618*1 K-10 C MTO-Q 1YC-0016A C 1618-1 -J-12 B ST-Q 1YC-0017B C 1618-1 H-12 B ST-Q 1YC-0027B C 1618*1 E-14 B ST-Q 1YC-0029A C. 1618-1 G-12 B $T-Q 1YC-0030A C 1618-1 F-14 B ST-Q 1YC-0038A C 1618 1 E-12 B ST-Q 1YC-0039B C 1618-1 T-12 B ST-Q 3 1YC-0040B C 1618-l' E-12 B -ST-Q 16 j. 1YC-00$4 .C 1618-1 H-09 B FS-Q 16 1YC-0076 C 1618 H-04 B FS-Q 1YC-0083D. C 1618-1 T-02 B ST-Q-1YC-0094 C 161841 C-09 C MTO-Q 1YC-0095-C -1618.C-10 C MTO-Q 1YC-0099B C 1618-1-. D-12 B ST-Q 16 1YC-0113 0 1618-1 T-09 B FS-Q 16 1YC-0135 0 1618-1 -F-04 B FS-Q. 16 1YC-0148 C 1618-2 E-02 B FS-Q 16 1YC-0162 C 1618-2 E-03 B FS-Q 16 1YC-0176-C -1618-2 E P> FS-Q. 16 = 1YC-0190 C 1618-2 E-07 8 FS-Q '16 1 YC- 0.'04 C.1618 E-0A B TS-Q 16 '1YC- 0213 - CL 1619-2L

.:a :

TC-? 10 1YC-0232 C 1618.E B r$-Q ' 16 1YC-0246 C 1618-2 -E-14 B FS-Q -16 1YC-0347-0 1618-4 G-05 B FS-Q 16 1YC-0357 C ~1618-4 0-12 R FS-Q l ll

i Page No. 40 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM YAINE CL FLOW TLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / r. REMARKS V

• • mal:El'P DEMINERALIZED WATER 1YM-011$B B 1601-2.4 C-09 A ST-Q LT-RT 1YM-0116 B 1001-2,4 Call AC MTC+Q YM1 RF*

Page No. 1 03/27/91 Duke Poker Company McGuire Nuclear-Station PLHP AND YALVE INSERY!CE TESTING PROGRAM YALVE 'CL TLOW FLOW CAT TEST TEST RR TEST DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / REMARRS y

• • STEAM GENERATOR-BLOWDOWN RECYCLE 2BB-0001B B 2580-1.0_ 11 - 0 2 B ST-Q 2BB-0002B B 2580-1.0 11-04 B ST-Q 2BB-0003B B 2580-1.0

!!-12 B ST-Q 2BB-0004B .B 2500-1.0 11 - 1 0 B ST-Q 2BB-0005A B 2580-1.0 T-02 B ST-Q 2BB-0006A B 2580 1.0 T-04 B ST-Q 29B-0007A B 2580-1.0 F-12 B ST-Q 2BB-0008A D 2580-1.0 T-10 B ST-Q .r l

Page No. 2 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE C1 ILOW FLOW CA1 TEST ifs 1 RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • APXILIARY FLEDWATER 2CA-0007AC C 2592-1.1 B-10 B sT-Q CA2 RF" 10 2CA-0008 0

2*.92-1.1 l'-11 MTC-Q 2CA-0009B C 2592-1.1 C-05 B ST-Q CA2 RF# 10 2CA-0010 C 2592-1.1 C-05 C MTC-Q 2CA-0011A C 2592-1.1 B-04 B ST-Q CA2 RF# 10 2CA-0012 0 2592-1.1 B-03 C MTC-Q 2CA-0015A C 2592-1.1 D-03 B ST-Q 2CA-0018B C 2592-1.1 D-03 B ST-Q 12 2CA-0020AB C 2592-1.1 1-10 AC ST-Q LT 2CA-0022 C 2592-1.1 1-10 C MTO-Q 2CA-0026 C 2592-1.1 1-04 C MTO-Q 12 2CA-0027A C 2592-1.1 J-05 AC ST-Q LT 2CA-0031 C 2592-1.1 1-07 C MTO-Q 12 2CA-0032B C 2592-1.1 1-08 AC ST-Q LT 2CA-0036AB C 2592-1.0 L-10 B ST-Q CS-CA1 2CA-0037 B 2592-1.0 K-14 C MTO.C-Q 2CA-0038B B 2592-1.0 J-14 B ST-Q 12 2CA-0040B C 2592-1.0 G-14 B ST-Q CS-CA1 2CA-0041 B 2592-1.0 H-14 C MTO.0-Q 2CA-0042B B 2592-1.0 1-14 B ST-Q 12 2CA-0044B C 2592-1.0 C-11 B ST-Q CS-CA1 2CA-0045 B 2592-1.0 C-09 C MTO.C-Q 2CA-0046B B 2592-1.0 D-08 B ST-Q 2CA-0048AB C 2592-1.0 K-08 B ST-Q CS-CA1 2CA-0049 B 2592-1.0 H-08 C MTO.C-Q 2CA-0050B B 2592-1.0 G-08 B ST-Q 2CA-0052AB C 2592-1.0 K-07 B ST-Q CS-CA1 2CA-0053 B 2592-1.0 H-07 C MTO.C-Q 2CA-0054AC D 2592-1.0 0-07 B ST-Q 2CA-0056A C 2592-1.0 C-04 B ST-Q CS-CA1 2CA-0057 B 2592-1.0 C-06 C MTO.C-Q 2CA-0058A B 2592-1.0 0-07 B ST-Q 2CA-0060A C 2592-1.0 0-01 B ST-Q CS-CA1 2CA-0061 B 2592-1.0 H-01 C MTO.C-Q 2CA-0062A B 2592-1.0 I-01 B ST-Q 2CA-0064AB C 2592-1.0 L-04 B ST-Q CS-CA1 2CA-0065 B 2592-1.0 K-01 C MTO.C-Q 2CA-0066AC B 2592-1.0 J-01 B ST-Q 2CA-0086A C 2592-1.1 C-14 B ST-Q 2CA-0116B C 2592*1.1 G-14 B ST-Q 2CA-0161C DELETED 12 2CA-0162C DELETED 12 CA1 Rrn-12 2CA-0165 C 2592-1,1 C-14 C MTO,C-Q CA1 RFd 12 2CA-0166 C 2592-1.1 G-14 C MTO.C-Q - ~ _ - _ - _ - -. - - _ _

Page No. 3 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND YALVE INSERVICE TFSTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • FEEDWATER 2CF-0017AB F 2591-1.1 K-03 B ST-Q CS-CF2

~2CF-0020AB F 2591-1.1 K-06 B ST-Q CS-CF2 -2CF-0023AB F 2591-1.1 K-09 B ST-Q CS-CF2 2CF-0026AB B 2591 1.1 H-03 B ST-Q CS-CF1 2CF-0028AB B 2591-1.1 H-06 B ST-Q CS-CF1 2Cf-0030AB B 2591-1.1 H-09 B ST-Q CS-CF1 2CF-0032AB F '2591-1.1 K-13 B ST-Q CS-CF2 2CF-0035AB B 2591-1.1 H-13 B ST-Q CS-CT1 2CF-0104AD F 2591-1.1 K-12 B ST-Q CS-CF4 9 2CF-0105AB F 2591-1.1 K-09 B ST-Q CS-CF4 9 .2CF-0106AB F 2591-1,1 K-05 B ST-Q CS-CF4 9 2CF-0107AB F 2591-1.1 K-02 B ST-Q CS-CF4 9 2CF-0126B B 2591-1.1

H-11 B

ST-Q CS-CF3 8 2CF-0127B B. 2591-1.1 H-08 B ST-Q CS-CF3 8 2CF 0128B B 2591-1.1 H-04 B ST-Q CS-CF3 B 2CF-0129B B 2591-1.1 H-01 B ST-Q CS-CF3 8 2CF-0134A B 2591 1.1 H-12 B ST-Q 8 2CF-0135A-B 2591-1,1 G-09 B ST-Q 8 '2CF-0136A B 2591-1.1 0-05 B ST-Q 8 -2CF-0137A. B 2591-1.1 G-02 B ST-Q 8 2CF-0151B B 2591-1.1 G-12 B ST-Q 8 2CF-0152 B 2591-1.1 F-12 C MTC-Q CS-CF5 2CF-0153B B 2591-1.1 G-11 B ST-Q 8 2CF-0154 B 2591-1.1 F-11 C MTC-Q C$-CF5 l 2CF-0155B B-2591-1.1 G-11 B ST-Q B 2CF-0156 B 2591-1.1 F-10 C MTC-Q CS-CF5 2CF-0157B B 2591-1.1 G-12 B ST-Q 8 2CF-0158 B 2591-1.1 F-12 C HTC-Q -CS-CF5 l --

l Page No. 4 03/27/91 Duke Power Company McGuire Nuclear Station PtHP AND VAINE INSERVICE TESTING PROGRAM VALVE CL TLOW TLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 RIQ2 ALTERNATIVES / E j REMARKS Y

• • DIESEL GENERATOR ENGINE FUEL Olt 2TD-0092-C 2609-3.0 E-13 -C MTO.C-Q 12 2rD-0093 C 2609-3.0 J-14 C MTO.C-Q 12-2TD-0104 C 2009-3.1-E-13 C MTO.0-Q 12 20D-0105 C 2609-3.1 J-14 C MTO C-Q 12 4

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Page No. 5 03/27/91 Duke Power Company McGuire Nuclear Station PtHP AND VALVE INSERVICE TESTING PROGRAM YALVE CL FLOW FLOW CAT TESI TEST RR TEST R DIAGRAM COOR REQ 1 MQ2 ALTERNATIVES / E REMARKS V

• • RErtTLING WATER 2fW-0001A B 2571-1.0 E-11 B ST-Q PASSIVE 2rW-0004 B 2571-1.0 D-08 A LT-RT PASSIVE 20W-0005 B 2571-1.0 C-07 AC LT-kr PASSIVE 2rW-0011 B 2571-1.0 C-02 A LT-RT PASSIVE 2rW-0013 B 2571-1.0 D-02 A LT-Rr CS-rW1 2rW-0027A B 2571-1.0 C-12 B ST-Q CS-rW2 10 2rW-0028 B 2571-1.0 B-11 C MTO.C-Q 2rW-0032B B 2571-1.0 E-11 B ST-Q 20W-0033A B 2571-1.0 T-11 B ST-Q 2rW-0049B B 2571-1.0 T-10 B ST-Q 20W-0052 E 2571-1.0 1-05 C MTO-Q PASSIVE 20W- )003 B 2571-1.0 C-03 AC LT-RT

Page No. 6-03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AFD VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • AIRLOCK 12 21A-5080 B 2499-IAl N/A A

ST-Q LT-RF 12 21A-5160 B 2499-IAl N/A A ST-Q LT-RF 12 21A-5340 B 2499-IAl N/A LT-RF 12 21A-5350 B-2499-IAl N/A LT-RF 12 IAl -21A-5360 C 2499-IAl N/A AC LT-RF 12 2IA-5370 C 2499-1A1 N/A AC LT-RF 1A1 12 IA) 21A-5380 C -2499-IAl N/A AC LT-RF IAl - 12 2IA-5390 C 2499-IA1 N/A AC LT-RF i

Page No. 7 03/27/91 .i Duke Power Cor.pany McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • COMPONENT COOLING 2KC-0001A C 2573-1.0 C-07 B ST-Q 2KC-0002B C 2573-1.0 C-08 B ST-Q 2KC-0003A C 2573-1.0 C-07 B ST-Q 2KC-0005 C 2573-1.0 F-04 C MTO-Q 2KC-0008 C 2573-1.0 F-04 C MTO-Q 2KC-0011 C 2573-1.0 F-11 C MTO-Q 2KC-0014 C.

2573-1.0 F-11 C MTO-Q 2KC-0018B C 2573-1.0 C-08 B ST-Q 2KC-0047 B 2573-4.0 L-07 AC MTC-Q LT-RF KC5 MT-RF 2KC-0050A C 2573-1.0 K-07 B .i-Q 2KC-0S$1A C 2573-1.0 J-05 B ST-Q 2KC-0053B C 2573-1.0 K-08 B ST-Q 2KC-0054B C 2573-1.0 J-10 B ST-Q 2KC-0056A C 2573-1.1 F-02 B ST-Q -2KC-0057A C 2573-1,1 D-06 B ST-Q 2KC-0081B C 2573-1.1 E-13 B ST-Q 2KC-0082B C-2573-1.1 D-09 B ST-Q 2KC-0228B C 2573-1,C K-08 B ST-Q 2KC-0230A C 2573-1.0 K-07 B ST-Q 2KC-0279 B 2573-3.1 F-04 AC MTC-Q LT-RF KC3 MT-RF 2KC-0280 B 2573-3,1 D-01 AC MTC-Q LT-RF KC1 MT-RF 2KC-0305B B 2573-3.1 D-16 B ST-Q 2KC-0315B B 2573-3.1 L-13 B ST-Q 2KC-0320A B 2573-3.1 C-10 A ST-Q LT-RF CS-KC4 2KC-0322 B 2573-3.1 C-09 AC MTC-Q LT-RF KC2 MT-RF CS-KC3 2KC-0332B B 2573-3.1 D-01 A ST-Q LT-RF CS-KC3 2KC-0333A B 2573-3.1 G-01 A ST-Q LT-RF 2KC-0338B B.2573-3.1 D-12 A ST-Q LT-RF CS-KC2 2KC-0340 B 2573-3.1 E-12 AC MTC-Q LT-RF KC4 MT-RF 12 CS-KC1 2KC-0424B B 2573-3.1 L-04 A ST-Q LT-RF 2KC-0425A B 2573-3.1 L-06 A ST-Q LT-RF CS-KC1 2KC-0429B B 2573-4.0 K-07 A ST-Q LT-RF 2KC-0430A B 2573-4.0 K-08 A "T-Q LT-RF 10 PSIG 12 2KC-0800 C 2573-1.1 1-11 C SP-3R 2KC-0972 C 2573-1.1 K-08 C SP-3R 15 PSIG 12 l Y

j Page No. 8 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL PLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • DIESEL GENERATOR COOLING WATER 12 2KD-0009 C 2609-1.0 E-14 B FS-Q 12 2KD-0029 C 2609-1.1 E-14 B FS-Q 9

Page No. 9 03/27/91 Duke Power Company McGuire Nuclear Station PLMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 "EQ2 ALTERNATIVES / E REMARKS V

• • FADIATION MONITORING 12 2MI-5580 B 2499-MI7 N/A A

ST-Q LT-RF 12 2tfI-5581 E 2499-M17 N/A A ST-Q LT-RF 12 2MI-5582 B 2499 '!17

• /.*.

ST-Q LT-RF 12 2MI-5583 B 2499-MI7 N/A A ST-Q LT-RF

Page No.. 10 03/27/91 Duke Power Company McGuire Nuclear Station l PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • BORON RECYCLE 2NB-0260B B 2556-3.0 G-05 A ST-Q LT-RF 2hB-0262 B 2556-3,0 G-03 AC MTC-Q LT-RF NB1 MT-RF

Page No. 11 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE C'. FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • REACTO\\ COOLANT 2485 PSIG 2NC-0001 A 2553-2.0 K-03 C SP-3Y 2485 PSIG 2NC-000'.

A 2553-2.0 K-04 C SP-3Y 2485 PSIG 2NC-000.1 A-2553-2.0 K-05 C SP-3Y 2NC-0031B A 2553-2.0 F-05 B ST-Q CS-NC1 12 2NC-0032B A 2553-2.0 0-05 B ST-Q 2NC-0033A A 2553-2.0 F-03 B ST-Q -CS-NC1 12 2NC-0034A A 2553-2,0 G-03 B ST-Q 2NC-0035B A 2553-2.0 F-02 B ST-Q CS-NC1 12 2NC-0036B A 2553-2.0 G-02 B ST-Q 2NC-0053B B 2553-2.1 H-10 A ST-Q LT-RF 2NC-0054A B 2553-2,1 H-09 A ST-Q LT-RF 2NC-0056B B 2553-2.1 D-14 A SI-Q LT-RF PASSIVE 2NC-0057 B 2553-2.1 F-1. i AC LT-RF ~ PASSIVE 2NC-0141 B 2553-4.0 C-O'i A PC-Q LT-RF PASSIVE 2NC-0142 B 2553-4.0 B-06 A PC-Q LT-RF PASSIVE 2NC-0195B B 2553-4.0 I-08 A LT-RF PASSIVE 2NC-0196A B 2553-4.0 H-08 A LT-RF 2NC-0259 B 2553-4.0 H-08 AC MTC-Q LT-RF Nul MT-RF* 2NC-0261 B 2553-4,0 C-08 AC MTC-Q LT-RF NC1 MT-RF* 8 CS-NC2 12 2NC-0272AC A 2553-2.1 J-09 B ST-Q CS-NC2 12 2NC-0273AC A 2553-2,1 J-10 B ST-Q CS-NC2 12 2NC-0274B A 2553-2,1 1-09 B ST-Q CS-NC2 12 2NC-0275B A 2553-2.1 1-10 B ST-Q

Page No. 12 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMAPES V

• • RESIDUAL HEAT REMOVAL CS-ND1 PIV 2ND-0001B A 2561-1.0 1-13 A ST-Q LT-TS CS-ND1 PIV 2ND-0002AC A 2561-1.0 H-13 A ST-Q LT-TS 2ND-0004B B 2561-1.0 E-12 B ST-Q CS-ND6 10 2ND-0008 B 2561-1.0 D-08 C MTO.C-Q 2ND-0014 B 2561-1.0 D-03 B ST-Q CE-ND3 2ND-0015B B 2561-1.0 E-03 B ST-Q 2ND-0019A B 2561-1.0 H-12 B ST-Q CS-ND6 10 2ND-0023 B 2561-1.0 J-08 C MTO C-Q 2ND-0029A b 2561-1.0 J-03 B ST-Q CS-ND3 2ND-0030A B 2561-1.0 1-03 B ST-Q CS-ND2 2ND-0058A B 2561-1.0 K-03 B ST-Q 2ND-0067B B 2561-1.0 B-09 B ST-Q 2ND-0068A B 2561-1.0 L-09 B ST-Q CS-ND4 10 2ND-0070 B 2561-1.0 K-03 C MTO,C-Q CS-NDS 10 2ND-0071 B 2561-1.0 C-04 C MTO.C-Q 1

Page No. 13 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • ICE CONDENSOR REFRIGATION 2NF-0228A B 2558-4.0 K-13 A ST-Q LT-RF LT per TS 12 1

2NF-0229 B 2558-4.0 F-13 AC MTC-Q LT-RF NF1 MT-RF* '2NF-0233B B 2558-4.0 K-12 A ST-Q LT-RF LT per TS 12 2NF-0234A B 2558-4.0 K-13 A ST-Q LT-RF LT per TS 12 i

Page No. 14 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • SAFETY INJECTION CS-nil 2NI-0009A B 2562-1.0 H-12 B ST-Q CS-nil 2NI-0010B B 2562-1.0 G-12 B ST-Q CS-N114 10 2NI-0012 B 2562-1.0 G-09 C MTO-Q CS-NI13 10 2NI-0015 A -2562-1.0 K-07 C MTO-Q CS-N113 10 2NI-0017 A 2562-1.0 1-06 C

MTO-Q CS-NI13 10 2NI-0019 A 2562-1.0 F-04 C MTO-Q CS-NI13 10 2NI-0021 A 2562-1.0 C-07 C MTO-Q 2NI-0047A B 2562-2.0 K-05 A ST-Q LT-RF 2NI-0048 B 2552-2.0 K-03 AC MTC-Q LT-RF N13 MT-RF* 2NI-0054A DELETED 9 2NI-0059 A 2562-2.0 D-13 AC MTO,C-O LT-T5 N14 PIV RF# 2NI-0060 A 2562-2.0 D-14 AC MTO.u C LT-TS NI6 PIV RF# 2NI-0065B DELETED 9 2NI-0070 A 2562-2.0 H-13 AC MTO,C-Q LT-TS N PIV RF# 2NI-0071 A 2562-2.0 H-14 AC MTO.C-Q LT-TS NI6 PIV RF# 2NI-0076A DELETED 9 2NI-0081 A 2562-2.1 C-03 AC MTO.C-Q LT-TS NI 4 - PIV RF# 2NI-0082 A 2562-2.1 C-03 AC MTO.C-Q LT-TS N16 PIV RF# 2NI-0088B DELETED 9 2N1-0093 A 2562-2.1 C-08 AC MTO,C-Q LT-TS N14 PIV RF# 2NI-0094 A 2562-2.1 C-08 AC MTO.C-Q LT-TS NI6 PIV RF# 2NI-0095A B 2562-2,1 F-11 A ST-Q LT-RF 2NI-0096B B 2562-2.1 E-13 A ST-Q LT-RF CS-NI3 2NI-0100B B '2562-3.0 F-13 B ST-Q CS-N115 10 '2NI-0101 B 2562-3.0 F-13 C MTO.C-Q 2NI-0103A B 2562-3.0 1-14 B ST-Q 2NI-0114 B 2562-3.0 1-09 C MTO-Q 2NI-0115B B 2562-3.0 H-09 B ST-Q CS-N116 10 2NI-0116 B 2562-3.0 J-09 C MTO.C 2NI-0118A B 2562-3.0 H-07 B ST-Q 2NI-0120B B 2562-3.0 J-07 A ST-Q LT-RF CS-NIS .2NI-0121A B 2562-3.0 J-06 B ST-Q PIV CS-N117 10 s?.T-0124 A 2562-3.0 J-03 AC MTO.C-Q LT-TS 'i'-0125 A 2562-3.0 1-03 AC MTO.C-Q LT-TS PIV CS-NI20 10

tt-0126 A 2562-3.0 J-02 AC MTJ.C-Q LT-TS PIV CS-NI20 10 PIV CS-NI17 10 2NI-0128 A 2562-3.0 1-04 AC MTO.C-Q LT-TS PIV CS-NI20 10 2N1-0129 A 2562-3.0 I-03 AC MTO C-Q LT-TS PIV CS-NI20 10 2NI-0134 A 2562-3,0 H-04 AC MTO.C-Q LT-TS 2NI-0135B B 2562-3.0 E-14 B

ST-Q CS-NI21 12 2NI-013(B B 2562-3,0 C-14 B ST-Q 2NI-0143 B 2562-3.0 F-09 C MTO.C-Q - 2NI-0144B B 2562-3.0 G-09 B ST-Q CS-N14 2NI-0147A B 2562-3,0 G-11 B ST-Q CS-N116 10 2NI-0148 B 2562-3.0 D-09 C MTO.C 2NI-0150B B 2562-3.0 E-07 B ST-Q l

Page No. 15 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARNS V 2NI-0152B B 2562-3.0 D-06 B ST-Q CS-NI6 2NI-01f6 A_ 2562-3,0 D-03 AC MTO.C-Q LT-TS PIV CS-NI17 10 2NI-0157 A 2562-3.0 D-02 AC MTO.C-Q LT-TS PIV CS-NI17 10 2NI-0159 A. 2562-3.0 B-04 AC MTO.C-Q LT-TS PIV CS-NI17 10 2NI-0160 A 2562-3,0 B-03 AC MTO.C-Q LT-TS PIV CS-NI17 10 2NI-0162A B 2362-3.1 E-11 B ST-Q CS-NI? 2NI-0165 A 2562-3.1 J-03 AC MTO.C-Q LT-TS PIV CS-NI18 10 =2NI-0167 A 2562-3.1 J-05 AC MTO.C-Q LT-TS PIV CS-NI18 10 PIV CS-NI18 10 2NI-0169 A' 2562-3.1 J-06 AC MTO.C-Q LT-TS 2NI-0171 A 2562-3.1 J-07 AC MTO.C-Q LT-TS PIV CS-NI18-10 2NI-01'3A .B 2562-3.1 I-12 B ST-Q CS-NI8 PIV CS-NI19 10 2NI-0175 A 2562-3.1 1-08 AC MTO.C-Q LT-TS 2NI-0176 A 2562-3.1 .H-08 AC MTO.C-Q LT-TS PIV CS-NI19 10 2NI-0178B B 2562-3.1 F-12 B ST-Q CS-NI9 2NI-0180 A 2562-3,1 F-07 AC MTO.C-Q LT-TS PIV CS-NI19 10 2NI-0181 .A 2562-3.1 D-08 AC MTO,C-Q LT-TS PIV CS-NI19 10-2NI-0183B B 2562 3.0 G-03 B ST-Q CS-nil 0 2NI-0184B 'B 2562-3.1. D-12 B -ST-Q CS-Sill .2NI-0185A B 2562-3.1 B-12 B ST^Q CS-Nill 2NI-0332A B -2562-3,0 L-14 B ST-Q 2NI-0333B B 2562-3,0 -L-12 B ST-Q 2NI-0334B .B 2562-3,0 L-11 B ST-Q .CS-NI13 10 L2NI-0347 A 2562-1.0 I-04 C MTO-Q CS-NI13 10 2NI-0348 A 2562-1.0 i-05 C MTO-Q z2NI-0349 A 2562-1.0 C-07 C MTO-Q CS-NI13 10 CS-NI13 10 '2NI-0354 A-2562-1.0 K-07 C MTO-Q CS-NI2 2NI-0430A' B '2562-2.0 F-04 B ST-Q 2NI-0431B B 2562-2.0 J-04 B ST-Q CS-NI2 2NI-0436' B-2562-2.1 G-11 AC LT-RF MTC-Q NIS MT-RF* l I l l l. E le

Page No. 16 03/27/91 Duke Power Company McGuire Nuclear Station Pt.'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • NUCLEAR SAMPLING 2NM-0003AC B 2572-1.0 K-03 A ST-Q LT-RF 2NM-0006AC-B 2572-1.0 J-03 A ST-Q 2NM-0007B B 2572-1.0 K-06 A ST-Q LT-RF 2NM-0022AC B 2572-1.0 J-12 A ST-Q LT-RF 2NM-0025AC B 2572-1.0 K-12 A ST-Q LT-RF 2NM-0026B B 2572-1_0 E-09 A ST-Q PASSIVE 2NM-0069 B 2572-1.1 G-09 A LT-RF

'2NM-0072B B 2572-1.1 1-06 A SI-Q LT-RF 2NM-0075B B 2572-1.1 1-0J A ST-Q LT-RF 2NM-0078B B 2572-1.1 1-10 A ST-Q LT-RF 2NM-0081B -B 2572-1.1 1-11 A ST-Q LT-RF .2NM-0082A B 2572-1.1 E-09 A ST-Q LI-RF 2NM-0187A B 2572-3.0 K-01 B ST-Q 2NM-0190A B 2572-3,0 K-02 ST-Q 2NM-0191B B 2572-3.0 1-02 L ST-Q 2NM-0197B B 2572-3.0 K-05 B ST-Q 2NM-0200B P 2572-3.0 K-06 B ST-Q 2NM-0201A B 2572-3.0 1-06 B ST-Q 2NM-0207A B 2572-3.0 K-08 B ST-P 2NM-0210A B 2572-3,0 K-09 B ST-Q 2NM-0211B B 2572-3,0 1 B ST-Q 2NM-0217B B 2572-3.0 K-11 B ST-Q 2NM-0220B B 2572-3.0 K-12 B ST-Q 2NM-0221A B 2572-3.0 I-12 B ST-Q 2NM-0420 B 2572-1.0 J-03 AC MTC-Q LT-RF NM1 MT-RF* 2NM-0421 B 2572-1.0 J-12 AC MTC-Q LT-RF NM1 MT-RF* 4

Page No. 17 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V s

• • CONTAINMENT SPRAY 2NS-0001B B 2563-1;0 C-13 B ST-Q

- 2NS-0003B B 2563-1.0 B-13 B ST-Q 2NS-0004 B 2563-1.0 C-12 C MTO.C-Q NS2 RF# 12 2NS-0012B B 2563-1.0 C-04 B ST-Q .2NS-0013. B 2563-1.0 B-02 C MTO-Q NS1 RF# 2NS-0015B .B 2563-1.0 D-04 B ST-Q 2NS-0016 B 2563-1.0 D-02 -C MTO-Q NSI RF# 2NS-0018A B 2563-1.0 G-13 B ST-Q 2NS-0020A B -2563-1.0 F-13 B ST-Q NS2 RF# 12 - 2NS-0021 B 2563-1.0 F-12 C MTO.C-Q L . 2NS-0029A-B 2563-1.0 F-04 B ST-Q ?* 2NS-0030-B 2563-1.0 F-02 C MTO-Q NSI RF# 2NS-0032A 'B 2563-1.0 h-04 B ST-Q. 2NS-0033 B 2563-1.0 H-02 C MTO-Q NSI-RF# 2NS-0038B 'B .2563-1.0 - J-05 B ST-Q CS-NS1 12 2NS-0041' B 2563-1.0 J-03 C MTO-Q NS1 RF# 2NS-0043A B' 2563-1.0-K-05' B STrQ CS-NSI 12 l-2NS-0046 B 2576-1.0 R-03 C MTO-Q NS1 RF# 2NS-5550Bf B -2499-NS8 N/A A ST-Q LT-RF 12 - 2NS-5551A B 2499-NS8 N/A' A 'ST-Q LT-RF 12 l 1 4 Y F m =- a x

l Page No. 18 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARF.S V

• • CHEMICAL AND VOLUME CONTROL 2NV-0001A DELETED 12 2NV-0002A DELETED 12 CS-NV2 2NV-0007B B 2554-1.2 J-ll B ST-Q CS-NV4 12 2NV-0021A A 2554-1.2 E-03 B ST-Q 2NV-0022 DELETED 12 12 2NV-0024B A 2554-1.2 D-06 B ST-Q 2NV-0025B A 2554-1.2 D-07 B ST-Q 12 12 2NV-0035A B 2554-1.2 K-07 B ST-Q CS-NV1 2NV-0094AC B 2554-1.1 J-13 B ST-Q 2NV-0095B B 2554-1.1 H-13 B ST-Q CS-NV1 CS-NV7 2NV-0141A B 2554-2.0 B-08 B ST-Q CS-NV7 2NV-0142B B 2554-2.0 B-07 B ST-Q CS-NV12 8

2NV-0150B B 2554-2.0 F-02 B ST-Q CS-NV12 8 2NV-0151A B 2554-2.0 G-02 B ST-Q CS-NV9 2NV-0221A B 2554-3.1 H-01 B ST-Q CS-NV9 2NV-0222B B 2554-3.1 .1-01 B ST-Q CS-NV15 10 2NV-0223 B 2554-3.1 I-02 C MTO.C-Q - CS-NV14 10 2NV-0225 B 2554-3.1 F-05 C MTO.C-Q 2NV-0227 B 2554-3.1 E-06 C MTO.C-Q - CS-NV14 10 2NV-0231 B 2554-3.1 F-10 C MTO.C-Q - 2NV-0233-B 2554-3.1 E-10 C MTO.C-Q CS-NV8 2NV-0244A B 2554-3.0 K-08 B ST-Q 2NV-0245B B 2554-3.0 K-09 B ST-Q CS-NV8 CS-NV11 2NV-0264 B 2554-3.1 J-10 C MTO-Q 2NV-0265B B 2554-3.1 J-09 B ST-Q CS-NV13 8 2NV-0457A B 2554-1.2 1-07 B ST-Q 2NV-0458A B 2554-1.2 J-07 B ST-Q 2NV-0459A DELETED 12 2NV-0842AC DELETED 12 2NV-0844 DELETED 12 2NV-0849AC P 2554-1.3 F-08 A ST-Q LT-RF ] '2NV-1002 B 2554-1.3 F-10 A.C MTC-Q LT-RF NV1 MT-RF 12 2NV-1007 DELETED 12 2NV-1008 DELETED 12 2NV-100) DELETED 12 2NV-1010 DELETED 12 2NV-1012C DELETED 12 2NV-1013C DELETED 12 CS-NV16 12 2NV-1046 B 2554-3.0 H-12 C MTC-Q

-m Page No. 19 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • NUCLEAR SERVICE WATER 2RN-0016A C 2574-1.1 J B ST-Q 2RN-0018B C 2574-1,1 E-02 B ST-Q 12 2RN-0021A C 2574-1.1 J-02 B ST-Q 12 2RN-0022A C 2574-1.1 H-05 B ST-Q 12 2RN-0025B C 2574-1.1 C-04 -B ST-Q 12-2RN-0026B C 2574-1,1 G-05 B ST-Q 2RN-0028 C 2574-1.1 J-09 C MTO-Q 2RN-0030 C 2574-1.1 E-09 C MTO-Q 2RN-0040A C.

2574-1.1 1-12 B ST-Q U2 & U1 SIGNAL 2RN-0041B C 2574-1.1 F-12 B ST-Q 2RN-0042A C 2574-4.0 .B-09 B ST-Q CS-RN4 U2 & U1 SIGNAL 2RN-0043A C 2574-1,1 -F-12 B ST-Q CS-RN5 2RN-0063B C 2574-4.0 L-10 B ST-Q CS-RN5 2RN-0064A C 2574-4.0-L-11 B ST-Q 12 3-0068A C 2574-1,1 L-12 B ST-Q 2dN-0069A C 2574-2.0 K-07 B SI-Q 2RN-0070A C -2574-2.0 E-06 B ST-Q 2RN-0073A C 2574-2.0 I-06 B ST-Q 2FsN-0086A C 2574-2.0 D-12 B ST-Q 2RN-0089A C 2574-2.0 J-)? P cT-Q 12 2RN-0103A -C 2574-2-1 C-06 B ST-Q-12 2RN-0112A C 2574-2.0 1-08 -B ST-Q RN1 RF 2RN-0113 C 2574-2.0-D-13 C MTO-Q '12 2RN-0114A C L574-2.1 B-11 B ST-Q 12 2RN-0117A C 2574-2.0 .1-10 B ST-Q 8 2RN-0126A - C 3574-2.1 D-10 B ST-Q 12 2RN-0130A. C 2574-2.1 C-10 B ST-Q ~~ 2RN-0134A ~ C 2574-2.11 C-07 B ST-Q 12RN-0137A C' 2574-2,1 H-07 B ST-Q, 12 2RN-0140A C-2574-2.0-E-14 .B ST-Q ~ 12 ~2RN-0161B C 2574-1.'1 B-12 B ST-Q 2RN-0162B C. 2574-3.0 J-07 B ST-Q -2RN-0166A C -2574-2.0 1-01 B ST-Q 2RN-0170B C 2574-3.0 I-01 B ST-Q 2RN-0171B - C 2574-3.0 F-07 B ST-Q 2RN-0174B C 2574-3,0 I-07 B ST-Q 2RN-0187B C 2574-3.0 F-12 B ST-Q ~2RN-0190B C 2574-3.0 J-12 B ST-Q 12 2RN-0204B. C 2574-3.1 C-05 B ST-Q 12 2RN-0213B C '2574-3.0 J-08 B ST-Q 2RN-0214 C 2574-3.0 D-14 C MTO-Q RN1 RF- -2RN-0215B C 2574-3.1 B-11 B ST-Q 12 l p 12 l 2RN-0218B C 2574-3-0 I-10 B ST-Q 2RN-0227B C-2574-3.1. E-10 B ST-Q 12 2RN-0231B C 2574-3.1 C-10 B ST-Q

Page No. 20 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARRS V 2RN-0235B C 2574-3.1 E-07 B ST-Q 2RN-0238B C 2574-3.1 1-07 B ST-Q 12 2RN-0240B C 2574-3.0 F-13 B ST-4 CS-RN2 2RN-0252B C 2574-4.0 E-02 A ST-Q LT-RF CS-RN2 2RN-0253A C 2574-4.0 C-02 A ST-Q LT-RF 2RN-0276A C 2574-4.0 1-02 A ST-Q LT-RF CS-RN3 CS-RN3 2RN-0277B C 2592-4.0 H-02 A ST-Q LT-RF 2RN-0279B C 1574-1.0 C-02 B ST-Q 2RN-0296A C 2574-1.1 L-13 B ST-Q 2RS-0297B C 2574-3,0 L-05 B ST-Q 2RN-0299A C 1574-1.0 C-02 B ST-Q /

l' ~ Page No. 21 03/27/91 Duke Power Company McGuire Nuclear Station PlHP AND VALVE INSERVICE TESTING PROCPAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT VENTTLATION COOLING WATER 2RV-0032A B 2604-3,0 R-10 A ST-Q LT-RF CS-RV1 2RV-00338-B 2604-3,0 K-12 A ST-Q LT-RF CS-RV1 2RV-0076A B 2604-3,0 C-12 A ST-Q LT-RF CS-RV1 2RV-0077B B 2604-3,0 C-10 A ST-Q LT-RT CS-RV1 2RV-0079A B N04-3.0 K-07 A ST-Q LT-RF l

2RV-0080B B 2604-3,0 K-06 A ST-Q LT-RF 2RV-0101A B 2604-3.0 C 05 A ST-Q LT-RF 2RV-0102B B 2604-3,0 C-07 A ST-Q' 2RV-0126 DELETED 12 2RV-0130 DELETED 12 2RV-0445 B 2604-3,0 J-12 C LT-RF 135 PSTG _12 2RV-0446-B 2604-3,0 E-12 C LT-RF 135.PSIG -12 i E

..~ L Page No. 22 03/27/91 Duke Power Company McGuire Nuclear Station l PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM C00R REQ 1 REQ 2 ALTERNATIVES / E REMARI:S V. I

• • MAIN STEAM TO Al'X. EQt'IPMENT L

2SA-0005' B. 2593-1,2 F-04 C MTO.C-Q - 10 -j 2SA-0006- 'B 2593-1.2 F-03 C MTO.C-Q 10 2SA-0048ACC B-2593-1.2 E B ST-Q 2SA-0049AB B-2593-1.2 F-02 B ST-Q 1 l. I l.' L; j.- I-t i-t 5 l I l. L g-

Page No. 23 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM YALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS Y

• • MATN STEAM CS-SM1 2SM-0001AB B 2593-1.0 K-13 B ST-Q CS-SM1 2SM-0003AB B 2593-1,0 H-13 B ST-Q CS-SM1 2SM-0005AB B 2593-1.0 1-14 B ST-Q CS-SM1 2SM-0007AB B 2593-1.0 C-14 B ST-Q 12 2SM-0009AB B 2593-1.0 J-13 B ST-Q 12 2SM-0010AB B 2593-1.0 G-13 B ST-Q 12 2SM-0011AB B 2593-1.0 1-13 B ST-Q 12 2SM-0012AB B 2593-1.0 C-13 B ST-Q

Page No. 24 03/27/9? Duke Power Company McGuire Nuclear Station PDIP AND VALVE INSERVICE R TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • MAIN STEAM VENT TO ATMOSPHERE 2SV-0001AB B 2593-1.3 L-05 B ST-Q 1170 PSIG 2SV-0002 B 2593-1.3 K-06 C SP-5Y 1190 PSIG 2SV-0003 B 2593-1,3 K-07 C SP-5Y 1205 PSIG 2SV-0004 B 2593-1.3 K-09 C SP-5Y 1220 PSIG 2SV-0005 B 2593-1.3 K-12 C

SP-5Y 1225 PSIG 2SV-0006 B 2593-1.3 K-12 C SP-5Y 2SV-0007ABC B 2593-1.3 G-05 B ST-Q 1170 PSIG 2SV-0008 B 2593-1.3 E-06 C SP-5Y 1190 PSIG 2SV-0009 B 2593-1.3 E-07 C SP-5Y 1205 PSIG 2SV-0010 B 2593-1.3 E-09 C SP-5Y 1220 PSIG 2SV-0011 B 2593-1.3 E-11 C SP-5Y 1225 PSIG 2SV-0012 B 2593-1,3 E-12 C SP-5Y 2SV-0013AB B 2593-1.0 L-04 B ST-Q 1170 PSIG 2SV-0014 C 2593-1.0 K-05 C SP-5Y '.190 PSIG 2SV-0015 B 2593-1.0 K-07 C SP-5Y 1205 PSIG 2SV-0016 B' 2593-1.0 K-09 C SP-5Y 1220 PSIG 2SV-0017 B 2593-1.0 K-10 C SP-5Y 1225 PSIG 2SV-0018-B 2593-1.0 K-12 C SP-5Y 2SV-0019AB B 2593-1.0 G-05 B ST-Q 1170 PSIG 2SV-0020 B 2593-1.0 E-05 C SP-5Y 1190 PSIG 2SV-0021 B 2593-1.0 E-07 C SP-5Y 1205 PSIG 2SV-0022 B 2593-1.0 E-09 C SP-5Y 1220 PSIG 2SV-0023 B 2593-1.0 E-10 C SP-5Y 1225 PSIG 2SV-0024 B 2593-1.0 E-12 C SP-5Y

Page No. 25 03/27/91 Duke Power Company McGuire Nuclear Station PLMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGER1 COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • BREATHING AIR 2VB-0049B B 2605-3.1 F-02 A ST-Q LT-RF 2VB-0050 B 2605-3.1 E-04 AC MTC-Q LT-RF VB1 MT-RF*

Page No. 26 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGPAM YALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARRS V

• • ANNULUS VENTILATION 2VE-0005A B 2564-1 G-04 A ST-Q LT-RF 2VE-0006B B 2564-1 G-04 A ST-Q LT-RF 2\\T-0008A B 2564-1 J-02 B ST-Q 2VE-0010A B 2564-1 11 - 0 3 A ST-Q LT-RF PASSIVE 2VE-00ll B 2564-1 11 - 0 3 AC LT-RF I

,~. Page No', 27 03/27/91 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • DIESEL GENERATOR STARTING AIR 2VG-0003 C 2609-4.0 J-12 C MTO-Q 12 2VG-0004 C 2609-4.0 E-12 C MTO-Q 12 12 i

2VG-0017. C' 2609-4,0 J-06 C MTO-Q 2VG-0018 C 2609-4.0 1-06 C MTO-Q 12 2VG-0019 C 2609-4.0 E-06 C MTO-Q 12 2VG-0020 C 2609-4.0 D-06 C MTO-Q 12 2VG-0061 C 2609-4,0 K-02 B ST-Q 12 2VG-0062 C 2609-4.0 K-02 B ST-Q 12 .2VG-0063 C 2609-4.0 I-02 B ST-Q 12 2VG-0064 C 2609-4.0 H-02 B ST-Q 12 2VG-0065 C 2609-4,0 T-02 B ST-Q 12 l 2VG-0066 C 2609-4.0. E-02 B ST-Q 12 2VG-0067 C 2609-4.0 -C-02 B ST-Q 12 2VG-0068 C 2609-4.0 C-02 B ST-Q 12 2VG-0115 C 2609-4.0 K-09 C MTO-Q 2VG-0116 C 2609-4.0 H-09 C MTO-Q 2VG-0117 C 2609-4.0 F-09. C MTO-Q 2VG-0118 C 2609-4.0 C-09 C -MTO-Q

l Page No. 28 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST k DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARRS V

• • INSTRth!EST AIR 2V1-0040 B 2605-1,3 J-13 AC MTC-Q LT-RF V12 MT-RF*

2VI-0124 B 2605-1.2 B-04 AC MTC-Q LT-RF VII MT-RF* 2VI-0129B B 2605-1.3 J-11 A ST-Q LT-KF 2VI-0135 C 2605-1.3 J-07 AC MTC-Q LT V13 - 12 2VI-0136 C 2605-1.3 J-08 AC MTC-Q LT VI3 - 12 2VI-0137 C 2605-1.3 D-06 AC MTC-Q LT VY3 12 2\\1-0138 C 2605-1,3 D-06 AC MTC-Q LT VI3 12 2VI-0139 C 2605-1.3 D-07 AC MTC-Q LT VI3 - 12 2VI-0140 C 2605-1.3 D-07 AC MTC-Q LT VI3 12 2VI-0141 C 2605-1,3 J-06 AC MTC-Q LT VI3 12 12 2\\1-0142 C 2605-1.3 J-06 AC MTC-Q LT VI3 2VI-0148B B 2605-1.2 E-03 A ST-Q LT-RF 2\\1-0149 B 2605-1.2 E-05 AC MTC-Q LT-RF VII MT-RF* 2VI-0150B B 2605-1.2 C-02 A ST-Q LT-RF 2VI-0160B B 2605-1.3 D-11 A ST-Q LT-RF 2VI-0161 B 2605-1.3 D-13 AC MTC-Q LT-RF VI2 MT-RF* 2VI-0362A B 2605-1.2 D-04 A ST-Q LT-RF y

Page No. 29 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE TNSERVTCE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT PURGE VENTILATION 10 2VP-0001B B 2576-1 T-06 A LT-TS 10 2VP-0002A B 2576-1 I-07 A LT-TS 10 2VP-0003B B 2576-1 K-06 A LT-TS 10 2VP-0004A B 2576-1 K-07 A LT-TS 10 2VP-0006B B 2576-1 E-06 A LT-TS 10 2VP-0007A B 2576-1 E-07 A LT-TS 10 2VP-0008B B 2576-1 D-06 A LT-TS 10 2VP-0009A B 2576-1 D-07 A LT-TS 10 2VP-0010A B 2576-1 J-08 A LT-TS 10 2VP-0011B B 2576-1 J-09 A LT-TS 10 2VP-0012A B 2576-1 1-08 A LT-TS 10 2VP-0013B B 2576-1 1-09 A LT-TS 2VP-0015A B 2576-1 F-08 A LT-IS 10 10 2VP-0016B B 2576-1 F-09 A LT-IS 10 2VP-0017A B 2576-1 B-07 A LT-TS 10 2VP-0018B B 2576-1 B-06 A LT-TS 10 2VP-0019A B 2576-1 B-08 A LT-TS 10 2VP-0020B B 2576-1 B-09 A LT-TS

Page No. 30 03/27/91 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE l l TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONTAINMENT AIR RELEASE AND ADDITION 12 2VQ-0001A B 2585-1.0 J-04 A ST-Q LT-RF 12 2VQ-0002B B 2585-1.0 J-06 A ST-Q LT-RF 12 2VQ-0005B B 2585-1.0 E-06 A ST-Q LT-RF 12 2VQ-0006A B 2585-1.0 E-03 A ST-Q LT-RF

I / Ok,@. F,o O ^ 't IMAGE EVALUATION A [o// 'E[ %)eI* TEST TARGET (MT-3) / / j';!$ eg, Q gp,;* 'g d 1.0 lt a 2 t"l lf El U $ j,l [ g-b!jl 2.0 a= l.25 1.4 l _I.6

== im 4 150mm 6" %yp sp+ sA+ 9>V>>d 4>e'l;j;j'y, >,gjj,,7 . 4 j #p o>ffff7 .y be -... u,,,pc)Ib,.

'Page No. 31 03/27/91 Duke Power Company McGuire Nuclear Station PtHP AND YALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • STATION AIR 2VS-0012B-B 2605-2.2 F-08 A ST-Q LT-RF 2VS-0013 B 2605-2.2 H-08 AC MTC-Q LT-PJ VS1 MT-RF*

Page No. 32 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • CONT, AIR RETURN EXCHANGE AND HYDROGEN ADD.

2VX-0001A B 2557-1 T-03 B ST-Q 2VX-0002B B 2557-1 1-12 B ST-Q 2VX-0030 B 2557-1 J-03 AC MTC-Q LT-RF VXI MT-RF 12 2VX-0031A B 2557-1 J-13 A ST-Q LT-RF 12 2VX-0033B B 2557-1 J-12 A ST-Q LT-RF PASSIVE 2VX-0034 B 2557-1 K-12 A LT-RF PASSIVE 2VX-0040 B 2557-1 R-03 A LT-RF

. - _ _ ~ _. _... _ _ _.. ~ _ _.. Page No. 33 03/27/91 Duke Power Company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL -FLOW - FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V 2WE-0013 DELETED 12 2WE-0023 DELETED 12-i I ""wei-

i Page No. 34 03/27/91 Duke Power Company McGuire Nuclear Station l PUMP AND VALVE INSERVICE l TESTING PROGRAM V.\\LVE CL FLOW FLOW CAT TEST TEST PS TEST R DIAGRAM COOR REQ 1 REQ 2 ALTEP.N.\\T! YES / E REMARKS V

• • LIQUID WASTE RECYCLE 2hl-0001B B 2565-1.1 L-11 A ST-Q LT-RF 2WL-0002A B 2565-1.1 K-13 A ST-Q LT-RF 2WL-0024-B 2565-1.1 J-14 AC MTC-Q LT-RF h12 MT-RF*

2hi-0039A B 2565-1.1 J-05 A ST-Q LT-RF 2WL-0041B B 2565-1.1 K-05 A ST-Q LT-RF 2WL-0064A B 2565-1.0 J-03 A ST-Q LT-RF 2hl-0065B B 2565-1.0 K-05 A ST-Q LT-RF 2WL-0264 B 2565-1.0 J-02 AC LT-RF PASSIVE 2WL-0321A B 2565-7.0 1-05 A ST-Q LT-RF ~ 565-7.0 H-04 A ST-Q LT-RF 2hi-0322B B 2 .2WL-0385 B 2565-7.0 J-05 AC MTC-Q LT-RF WL3 MT-RF* 2WL-0466 DELETED 9 2hl-1301B B 2565-1,0 G-03 A ST-Q LT-RF i 2hl-1302A B 2565-1.0 -E-04 A ST-Q LT-RF l l l

Page No. 35 03/27/91 Duke Power Company McGuire Nuclear Station PLHP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • DIESEL GENERATOR ROOM StMP PI'MP 2WN-0003 C 2609-7.0 L-11 C MTO.C-Q 2WN-0005 C 2609-7.0 K-11 C MTO C-Q 2WN-0007 C 2609-7.0 J-11 C MTC-Q 2WN-0011 C 2609-7.0 F-11 C MTO C-Q 2WN-0013 C 2609-7.0 E-11 C MTO C-Q -

2WN-0015 C 2609-7.0 D-11 C MTC-Q

= - _.. -Page No. 36 03/27/91 Duke Power company McGuire Nuclear Station Pt'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V

• • MAKEUP DEMINERALIZED WATER 2YM-0115B B 1601-2.4 C-09 A ST-Q LT-RF 2YM-0116 B 1601-2.4 C-04 AC MTC-Q LT-RF YM1 MT-RF*

l {' t I l-l l

ATTACHMENT-2 McGUIRE UllITS~l AND ; IWP PROGRAM REVISIONS -Note: Revisions are both Units unlcss otherwise indicated, 1 1. General Relief Request .3(E) Rel.ef request rest.bmitted f or review by NRC Staf f. Also, Attachment : Is prtvided as additicnal ;nfermation for c%;ar;ng relief request with QM-ti requ:rements. 2. Sect 1Cn !.2-

3) Changed Table to reflect :hange in rel:.ef request for bear:.ng tar.perature neasurments.

al IWP'CA testing ie conducted quarterly rather than monthly c) Corrected contain;aent Opray pumps flow diagram number. -d). Changed lubricat;on level verification-for TD and WN pumps to-NR as this code requirement does not apply to-these pumps, e) Deleted Standby Makeup Pump from IWP program, f) Corrected legend symbols 3. Deleted Relief Request-I.4(A). (Unit I only)

4. Relief Request I.4(B). (I.4(A) for Unit 2) a)-Added additional justification for widened acceptance range.-

o) Deleted lubrication level verification since this Code requiremntidees not apply to these pumps. --5.' Relief: Request I.4(C)-(_I-4(B)_for Unit 2). .a) Clarified quarterly testing of NI pumps, b).. Clarified refueling test options for full flow-testing of NI pumps. 4 6. Relief Request I.4(D) (I.4(C) for Unit 2) a) Clarified quarterly testing of ND pumps. b)) Changed refueling-testing to cold shutdown. -c ) Clarified test _ options-fer full flow testing of MD pumps. l

ATTACHME:1T McGU F,E U!1ITE 1 A11D '. !WP PROGRAM REVISIO!15 7. Relief R+ quest

1. 4 ; E '; i!.4iO) f o r l'r.i t 1) a) Clar fled quarter 2y te: iting of.NV pumps.

) "lartf1ed :eit. p u r. s for full flow testing C f N', p..id p i. 5. Rellef Request I.44F: (!.4(E) fcr Unit ) Deleted ducussi n of lubricant level observation for Wil pumps as t!.ls code l equlreraent does not apply ta these pumps. 9. Relief Request I.4tJ) (!.4:7) for Unit 2) Relief request was deleted since Standby Makeup Fump was deleted frc.T. :ST program.

.SECTION.I.2 McGUIRE NUCLEAR STATION - UNIT 1 PUMP INSERVICE. TESTING PROGRAM s T C Z x 3 ^ ^ a L a 3 E E-7. 5 C U 2 G . :r E 3 5 i s7 z s' a t 3 F ?. E t i 4 2 t t ii u 3 3 PUMPS y g g g 3 3 g g g go a m a m ~ a u. a m a a u. Cent. Charging Pumps (IA, IB) [NV] 2 QU NR X X RR X(1) X RR X MC-1554-3.1 Component Cooling Pumps (IA1, lA2, 181, 182) [KC] 3 QU NR X X X X(1) X RR X MC-1573-1.0 Containment Spray Pumps (1A, IB) [NS] 2 QU NR X X X X(1) X(2) RR X MC-1563-1.0 Control Area Chilled Water Pumps (CRA-P-1,2) [YC] 3 -QU NR X X X X(1) X RR X MC-1618-1.0 D/G Euel Oil Transfer Pumps (1A, 18) [FD] 3 QU NR RR RR X X(1) NR RR X MC-1609-3.0 D/G Room Sump Pumps (1A2, IA3, 182, 183) [WN] 3 QU NR RR RR X X(1) NR RR X MC-1609-7.0 M/D Aux. Feedwater Pumps (IA, IB) [CA] 3 QU NR X X X X(1) X RR X MC-1592-1.1 Nuclear Service Water Pumps (1A, IB) [RN] 3 QU NR X X X X(1) X RR X MC-1574-1.1 Residual Heat Removal Pumps (IA, 18) [ND] 2 QU NR X X X X(1) X(2) RR X MC-1561-1.0 1 NOTES: 1) Reference General Relief Request I.3(B) 2) Pump is close coupled; therefore motor lubricant level will be observed. LEGEND X - Instrumentation Available .QU - Quarterly NR - Not required for IWP Compliance () - Note RR - Exempted by Relief Request [] - System Abbreviation Rev. 16

s 'SECTION I.2 I McGUIRE NUCLEAR STATION - UNIT 1 PUMP INSERVICE TESTING PROGRAM c. D 3 a c 2 8-3 a a 3 3 2 th E s 5 3 $3 ee b 4 u 3 5 .2 PUMPS 0 E S U S 5 5 U 55 E O 5 5 2 C 3 E SC Safety Injection Pumps (IA,18) [NI] 2 QU NR X X X X(1) X RR X MC-1562-3.0 Tll) Aux. Feedwater Pump (No.1) [CA] 3 QU X X X X X(1) X RR X MC-1592-1 1 l .t NOTES: 1) Reference General Relief. Request I.3(B) 2) Pump is close coupled; therefore motor lubricant level will be observed. LEGEND X - Instrumentation Available- -QU - Quarterly NR - Not required for IWP Compliance () - Note RR - Exempted by Relief Request [] - System Abbreviation Rev. 16 i i

SECTION I.2 iMcGUIRE NUCLEAR STATION - UNIT 2 PUMP INSERVICE TESTING PROGRAM t C Z ? x e ia a 8 a 8 S Z u G l E 3 5 t z w e 3 E Eo PUMPS U i 2 2 3 2 2

1. 2 m

s e u o u. a m o o u. Cent. Charging Pumps (2A, 28) [NV) 2 QU NR X X RR X(1) X RR X MC-2554-3.1 Component Cooling Pumps (2A1, 2A2, 2B1, 292) [KC] 3 QU NR X X X X(1) X RR X MC-2573-1.0 l ontainment Spray Pumps (2A, 28) [NS] 2 QU NR X X X X(1) X(2) RR X MC-2563-1.0 D/G Fuel Oil fransfer Pumps (2A, 28) [FD] 3 QU NR RR RR X X(1) NR RR X MC-2609-3.0 D/G Room Sump Pumps (2A2, 2A3, 282, 2B3) [WN] 3 QU NR RR RR X X(1) NR RR X MC-2609-7.0 M/D Aux. Feedwater Pumps (2A, 28) [CA] 3 QU NR X X X X(1) X RR X MC-2592-1.1 Nuclear Service Water Pumps (2A, 2B) [RN] 3 QU NR X~ X X X(1) X RR X MC-2574-1.1 Residual Heat Removal Pumps (2A, 28) [ND] 2 QU NR X X X X(1) X(2) RR X MC-2561-1.0 Safety Injection Pumps (2A, 28) [NI] 2 QU NR X X X X(1) X RR X HC-2562-3.0 T/D Aux. Feedwater Pump (No. 2) [CA] 3 QU X X X X X(1) X RR X MC-2592-1.1 NOTES: 1) Reference General Relief Request I.3(B) 2) Pump is close coupled; therefore motor lubricant level will be observed-. LEGEND X - Instrumentation Available QU - Quarterly c NR - Not required for IWP Compliance () - Note RR - Exempted by Relief Request [] - System Abbreviation -Rev. 12

l (B) PUMPS: All pumps included in the IST program. TEST REQUIREMENT: IWP-3100 and IWP-3210 require vibration amplitude to be measured. IWP-3210 specifies the allowable ranges of vibration amplitude measurements. IWP-4110 requires the accuracy of vibration amplitude measurements to be +/-5% of full scale. IWP-4120 requires the full scale range of vibration instrumentation to be three times the reference value or less. IWP-4510 requires displacement vibration amplitude to be read at ons specific location during each test. iWP-4520(b) requires the frequency response range of vibration instrumentation to t,e from one-half minimum speed to at least maximum pump shaft speed. BASIS FOR RELIEF: Experience has shown that measuring vibration as required by IWP is not the most effective way to determine the mechanical condition of a pump. In order to better determine the mechanical condition of pumps, multiple vibration velocity measurements will be obtained/ evaluated and supplemented, when necessary, with acceleration / displacement measurements and spectral analysis. In order to facilitate this testing, digital vibration instrumentation will be used. IWP does not provide adequate guidance / requirements for performing the better/ alternate testing. ALTERNATE TESTING: In lieu of the vibration requirements of IWP-3100 and IWP-3200, peak vibration velocity will be measured. In most cases, vibration velocity gives the best indication of machine mechanical condition. In lieu of IWP-4520(b), vibration instrumentation will be calibrated and vibration velocity will be measured over a range of 10 to 1000 Hz. This is the range that the state of the art instrumentation used can be adequately calibrated over. In lieu of IWP-4520(b), vibration velocity will be measured over a range from 1/3 minimum pump chaft rotational speed to 1000 HZ. 12 (Measurements at other frequencies will be taken as necessary). This range will encompass most potential noise contributors. Rev. 12

In lieu of the vibration instrument accuracy requirements of IWP-4110, the loop accuracy of vibration instruments will be +/- 6.56% of reading. This accuracy will be used because IWP does not specify an accuracy for vibration velocity. This accuracy is the best that can be reasonably obtained from the state of the art instrumentation used. (The requirements of 12 IWP allow vibration inaccuracles of greater than +/- 15% of reading.) In lieu of the range requirements imposed on vibration instrumentation by IWP-4120, there will be no vibration instrumentation range requirement (digital vibration instrumentation is auto-ranging). It is not necessary to have a range requireuent because the accuracies stated above and the readability of a digital gauge are not dependent upon instrument range. In lieu of the vibration ranges specified in IWP-3210, the following ranges shell be used. These ranges will be used because IWP does not specify ranges for vibration velocity. These ranges are based on current vibration standards (vibration severity charts). Acceptable Alert Required Range Range Action Range For All Pumps When 0 to 0.19 >0.19 to 0.45 > 0. 4 5 - Vr <0.075 in/sec in/sec in/sec 'n/sec For Centrifugal Pumps wWhen V7 >0.075 in/sec -<2.5V >2.5V to 6V or >6V or I >0.325[o0.70in/sec >0.70 in/sec r P For Reciprocating Pumps <2.5V >2.5V to 6V >6V r r r r When Vr >0.075 in/sec Acceptable Alert Required Range Range Action Range For Internal Gear Positive Displacement Pumps when -<2.5V >2.5V to 6V >6V r r r r Vr >0.075 in/sec l l l Rev. 12

~ _.. -. -.. In lieu of IWP-4510, peak vibration velocity measurements shall be taken during each test. On centrifugal and internal gear PD pumps, measurements shall be taken in a plane approximately perpendicular to the rotating shaft in two orthogonal directions. These measurements shall be taken on each accessible pump bearing housing. If no pump bearing housings are accessible, these measurements shall be taken at the accessible location that gives the best indication of lateral pump vibration. This location shall be one of the following: Pump casing Motor bearing housing Measurements also shall be taken in the axial direction. This measurement shall be taken on each accessible pump thrust bearing housing. If no pump thrust bearing housings-are accessible, this measurement shall be taken at the accessible location that gives the beast indication of axial pump vibration. This location shall be one of the following: Pump casing Motor. thrust bearing housing-Motor casing On reciprocating pumps,-a measurement shall be taken on the bearing housing of,the crankshaft, approximately perpendicular to both the crankshaft and the line of plunger travel. l l l { l Rev. 12

l 1.4 The following Safety Class 2 and 3 Pumps (see Section 1.2 for available instrumentation) will be tested in accordance with the intent of Subsection IWP of the ASME Code, except where relief requests have been written for specific require,'ents determined to be impractical as described below: i (A) PUMPS: 0/G Fuel Oil Transfer Pumps (2A, 28) SAFETY CLASS: 3 FUNCTION: Diesel Generator Auxiliary Support j TEST REQUIREMENTS: Test pumps in accordance with Subsection IWP BASIS FOR RELIEF: IWP does not provide appropriate provisions for testing positive displacement pumps. ALTERNATE TESTING: The Fuel Oil Transfer Pumps are internal gear positive displacement pumps. The performance 1 curve for these pumps is relatively flat. 1 Capacity of these pumps is independent of i discharge pressure when operating properly and operating below the cracking pressure of the pump internal relief valve. Discharge pressure will be measured for information purposes, but i will not be compared to any acceptance t criteria. Pumps will be tested by measuring i level rise in tiie Fuel Oil Day Tank and j converting this to flowrate. Pump testing is between the level setpoints of the Fuel Oil Day Tank and this gives a run time of approximate'y 60-75 seconds. The flowrate (Q) will be compared to acceptance criteria established in accordance with Table IWP-3100-2 except the Acceptable Range has been widened and the High Alert Range increased to allow for level instrument fluctuations. Acceptable Range: 0.94 to 1.07 Qr Low Alert Range: 0.90 to 0.94 Qr High Alert Range: 1.07 to 1.10 Qr Low Required Action Range: <0.90 Qr High Required Action Range: >1.10 Qr 12 Rev. 12

These pumps are designed to produce a flow rate of 22 gpm. The requirements of the Diesel Generator are approximately 6 gpm. Five vibration points are monitored and trended on the Fuel Oil Transfer pumps. Acceptance criteria for the vibration points are established based on Relief Request 1.3(B). Vibration data is trended on a quarterly basis similar to the flow test results. Any degradation in the performance of the Fuel Oil Transfer pump will first appear in the vibration data. Also, the FOT pumps are conservatively designed in the discharge pressure that can be obtained. The capabilities of the-pump are the challenged during the quarterly test with respect to discharge pressure. System limitations 12 restrict the discharge pressure to less than or equal to 55 psig; however, the F0T pump could easily pump against 150 psig. Since the pump.is installed with considerable safety margin with respect to flow and discharge pressure, the most prudent data to use for trending for pump degradation would be velocity vibration data. By trending the f_ive velocity vibration data points, the acceptability of the widened High Alert and Required Action for flow is justified. The flow test ensures system operability requirements are met while the vibration test ensures an adequate trending program is in place to ensure continued operability during testing intervals. In addition, monthly Diesel Generator starting and=1oading (as required by McGuire Technical -Specifications) will assess the hydraulic condition of the subject euxiliary pumps and demonstrates the capability of the individual components to perform their design function. l Rev. 12

(B) PUMPS: Safety Injection Pumps (2A, 28) SAFETY CLASS: 2 FUNCTION: To provide emergency core cooling in the event l of a break in either the reactor coolant or steam system piping. TEST REQUIREMENT: IWP-3100 requires the resistance of the system to be varied until either the measured differential pressure or the measured flow rate equals the corresponding reference value. BASIS FOR RELIEF: When testing these pumps on line, the.,nly flow path available is thru the miniflow to the

FWST, Flow is limited by an orifice in the miniflow line, which yields a test point back on the head curve.

As stated in Generic Letter 89-04, minimum flow lines are not designed for pump testing purposes. The test point for monitoring pump performance for degradation should be in a more stable region on the pump performance curve. Also, the amount of time the pump is run at miniflow should be minimized. l ALTERNATE TESTING: The Safety Injection Pumps will be tested according to the following program, which is consistent with Generic Letter 89-04. Quarterly The Safety Injection Pumps will be tested quarterly to verify Technical Specification limits are met. The test measures differential pressure and vibrations. This data will be trended as required by IWP-6000. For the quarterly test, the instrumentation accuracy and range requirements of IWP will be waived. The instrumentation used to measure suction and discharge pressure will meet applicable 12 accuracy requirements for the determination of operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements as specified in relief requast I.3(B). Since the test loop in the minimum flow line with a flow limiting orifice is installed, flow will be recorded for information only. l l Rev. 12

Refueling Outaae During each reTueling outage, a code pump test, including velocity vibration measurements, will be performed at a test point in the stable region of the performance curve. As an alternative to repeat testing at a single test point in the stable region of the performance curve, a reference curve n,ay be obtained with applicable IWP curves plotted. Using this technique, the full flow test point 12 (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data obtained is then plotted and pump operability at the test point will be verified when compared against IWP reference curves. Each of these test methods will provide an acceptable level of quality and safety while maintaining the most flexibility to accommodate system conditions and configurations during refueling outages. _ Implementation The new testing program (quarterly and refueling) will be in place by the 1990 Unit 2 refueling outage and the 1991 Unit 1 refueling outage. Rev. 12

(C) PUMPS: Residual Heat Removal Pumps (2A, 28) SAFETY CLASS: 2 FUNCTION: To remove heat energy from the core and Reactor Coolant System during cooldown and refueling operations. Also, utilized as part of Safety injection System and Containment Spray System during an accident condition. BASIS FOR RELIEF: When testing these pumps on line, the only flow path available is thru the miniflow line. Flow is limited by the miniflow control valve in the line, which yields a test point back on the head curve. As stated in Generic Letter 89-04, minimum flow lines are not designed for pump testing purposes. The test point for monitoring pump performance for degradation should be in a more stable region on the pump performance curve. Also, the amount of time the pump is run at miniflow should be minimized. ALTERNATE TESTING: The Residual Heat Removal Pumps will be tested according to the following program, which is consistent with Generic Letter 89-04. Quarterly The Residual Heat Removal Pumps will be tested quarterly to verify Technical Specification limits are met. The test measures dif ferential pressure and vibrations. This data will be trended a:s required by IWP-6000. For the quarterly test, the instrumentation accuracy and range requirements of IWP will be waived. 12 The instrumentation used to measure suction and discharge pressure will meet applicable accuracy r'equirements for the determination of operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements as specified in relief request I.3(B). Since the test loop in the minimum flow line with a flow limiting control valve is installed, flow will be recorded for information only. Rev. 12

Cold Shutdown During each cold shutdown, a code pump test, including velocity vibration measurements, will be performed at a test point in the stable region of the performance curve. As an alternative to repeat testing at a single test point in the stable region of the g performance curve, a reference curve may be obtained with applicable IWP curves plotted. Using this technique, the full flow test point (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data obtained is then plotted and pump operability at the test point will be verified when compared against IWP reference curves. Each of these test methods will provide an acceptable level of quality and safety while maintaining the most flexibility to accommodate system conditions and configurations. Implementation The new testing program (quarterly and refueling) will be in place by the 1990 Unit 2 refueling outage and the 1991 Unit I refueling outage. Rev. 12

(0) PUMPS: Centrifugal Charging Pump (2A, 28) SAFETY CLASS: 2 FUNCTION: To supply reactor coolant inventory in the Volume Control Tank or Refueling Water Storage Tank to the reactor coolant system. TEST REQUIREMENT: Table IWP-3100-1 requires measuring dif ferential pressure (DP) and flow rate (Q). BASIS FOR RELIEF: When testing these pumps on line, the only flow path available is thru a combination of the normal charging and the miniflow to the VCT. The miniflow is not instrumented for flow. Flow through the line is assumed to be at the flow rate corresponding to the orifice design conditions. Also, the combination flow paths yield a test point back on the head curve. The best test point back for monitoring pump performance for degradation should be in a more l stable region on the pump performance curve. ALTERNATE TESTING: TheCentrifugal'ChargingPumpswillbetested according to the foliowing program, which is consistent with Generic Letter 89-04. Quarterly The Centrifugal Charging Pumps will be tested quarterly to verify Technical Specification limits are met. The test measures differential pressure and vibrations. This data will be trended as required by NP-6000. For the quarterly test, the in:trumentation accuracy u and range requirements of IWP will be waived. The instrumentation used to measure suction and discharge pressure will meet applicable accuracy requirements for the determination of operability per Technical Specifications. The instrument used to measure vibrations will meet the requirements as specified in relief request I.3(B). Since the test loop in the minimum flow line with a flow limiting orifice is installed, flow will be recorded for information only. Rev. 12

Refueling Outage During each refueling outage, a code pump test, including velocity vibration measurements, will be performed at a test point in the stable region of the performance curve, As an alternative to repeat testing at a single test point in the stable region of the performance curve, a reference curve may be obtained with applicable IWP curves plotted. Using this technique, the full flow test point (also in the stable region of the pump curve) will be bound by flow points obtained in the development of the reference curve. The data 12 obtained is then plotted and pump operability at the test point will be verified when compared against IWP reference curves. Each of these test methods will provide an acceptable level of quality and safety while maintaining the most flexibility to accommodate system conditions and configurations.during refueling outages. Implementation 1 The new testing program (quarterly and refueling) will be-in place by the 1990 Unit 2-refueling outage and the 1991 Unit 1 refueling outage. Rev. 1.2

(E) PUMPS: 0/G Room Sump Pumps (2A2, 2A3, 282, 283) SAFETY CLASS: 3 FUNCTION: Water removal from Diesel Generator Rooms TEST REQUIREMENT: Test pumps in accordance with Subsection IWP. l BASIS FOR RELIEF: The 0/G Room Sump Pumps are vertical pumps tested by filling the 0/G Room Sump and pumping the sur.p down. No stable system conditions can be obtained due to the continuous decrease in sump level. No suction pressure, flow, bearing temperature, or lubricant level instrumentation is available. ALTERNATE TESilf4G: The 0/G Room Sump Pumps will be tested for greater than or equal to emergency design flow by: (1) Filling the sump and recording level. (2) Pumping down the sump and recording both level and pump down time. An average flow rate will be determined from the time it takes to pump a known volume from the sump. Pumping down the sump takes approximately 60 seconds. An average discharge pressure will be determined and recorded. The flow rate will be compared with acceptance criteria established per Table IWP-3100-2. The above testing procedure is an interim method until modifications are made to the system which will permit full flow testing using a recirculation loop back to the sump. Included in the test loop modification will be direct flow-indication and throttling capability to set either AP or Q. The modifications will be installed by the 1992 refueling outages, u No suction pressure instrumentation is required since this pressure can be calculated from sump level measurements. Rev. 12

1 l (F) Deleted by Revision 12 12 Rev. 12

~ Additicnal Information for Relief Eequest I.3tL) Re'.,1ef was requested f r:m the vibr ation monitoring requirements of IWP because they are outda:ed. The relief request specifies vibratien monitor 1n] requirements that are far superior to those of IWF. The requirements of the relief request are at a pcint cf du-inishing r+ turns. Moat uap r.. vem e n t s t tne relief request w:ald have a negliq1cle..: any, m e.s i t i v e u.jpact :.n McGuire's vibratica u ni;orin; progr m. The relief request does not specify that vibration mcniterlag wl.1 be performed per CM-6 because there are fundamental technical prcblems witn the vibration acnitcring requirements of CM-6. These problems are 1:.dicated belcw. These problems adve been trought to the attention of the OM 6&lo Working Group by Duke Fower and other utilitit. Duke Power presented a paper on the impracticalities and problems associated with the vibratica monitoring requirements cf OM-6 to the CM 6&lo Wcrking Grcup, Vibrat.cn Task Group on December 2, 1989. The CM 6610 Work;ng Group is currently in the process of making significar t improvements to the vibration menitoring requirements cf OH-6. Each OH-6 Section that establishes vibration monitoring requirements, and hcw these requirements relate to McGuire Relief Request !.3.3, are discuss +d bclow. CM-d Secticn 4.6.1.1. Instrument Accuracy This code section sp+cifies that vibration instrument accurac; shall.be +/- 5 percent: ( a )- of full-scale for individual analog instruments, (b) of total loop accuracy fcir a combination of inctruments. or (c)- 'over the calibrated range for digital instruments. This requirement is not clear. Section 4.6.1.2.c of OH-6 excludes vibration Instruments from range requirements; thus-(a> is not clear. (b) and (c) are not clear tecause they do not =specify what the +/- 5 percent is relative-to. In other words. It is not clear whether they mean +/- 5 percent of each reading over the calibrated range, or +/- 5 percent of the the largest value. Since OH-6 does not have a clear accuracy = statement, a specific comparison with the accuracy specified in the relief request.is not possible. The proposed accuracy statement of 6.56't of reading is adequate because it is the best that can reasonably be obtained with-the state-of-the-art = instrumentation used. This equipment allows for quick data acquisition and detailed data analysis. Also, any improvement in vibration instrument accuracy would have a negligible positive impact on the effectiveness of vibration monitoring. As stated below, a +/-6.56% accuracy statement is insignificant; therefore, any small improvements in accuracy are even more insignificant. Also, any instrumentation changes would J m--m <-4 ~ -. ~

Additional Information for-P.elief Peque8t I,3'B) be. expensive and wculd disrupt the well established and effective vibration monitoring program that is in place. The stated lastrument accuracy is adequate because large changes y in "inration 'evels are tae best indicator of and are usually relied u;1n to assess operational readiness and degradation. Wuen. It : a t :. c a 1+vels are in ;he alert ;r required amtlin. range, but hwe act +3c+eded tav faed aart cr lequired act1:n ult' of 0.325 Infsec cr-0,70 an/sec respectively, they have increased at least 250% or-{001 respectively, Therefore, an accuracy atatement of w'- G.56% ot reading is insignificant, The ststed instrument accuracy is alsc adequate when small changes :.n vioration are us+d to aseess pump condition. When vibration-levels are outside of tne acceptable range solely because they have exceeded the fixed alert limit of 0,325 in/sec or the f;xed requi:ed act;an limit of 0.70 in/sec, they may in some cases not have increased significantly. In these cases the i .fixed limits cf 0.325 in/sec and 0.70 in/see will be relied upon to assess operational readiness and degradation. These fixed limits are scmewhat g+neral and need not be considered absolutes. They were extracted from vibration severity charts. While the charts are in general agreement, there is not agreement on l' as easily as 0.325 In/sec for the fixed alert limit. 0.75 or specific numbers, 0.300 cr 0.350 in/sec could have been chesen 0.5; in/see ce.uld have seen chosen as easily as 0.70 in/see for the fixed required actioa limit, These windows encompass

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106.54% of 0.325 in v's e c and 0,70 in/see respectively; therefsr?, g a +/- 6.56Y of reading accuracy statement is insignificant. OM-6-section 4.6.1.6. Frequency Response Range This code section specifies =that the frequency response range ;f i the vibration measuring transducers and their readout system shall be'from one-third minimum pump shaft rotational speed to at least'1000 H;..The relief request now specifies thatEvibration velocity wi-11.be measured over a range from 1/3 minimum. pump 7 j shaft rotational speed to 1000 H:. .As indicated in the. relief request,- however, vibration instrumentationiis calibrated over a range from 10 to 1000 H. Calibrating below 10 H: is not reasonably possible with-the state-of-the-art instrumentation used. This equipment allows for quick data acquisition and detailed data analysis. Also,,as indicated below, calibrating at less than 10 H: Would have a negligible-positive impact on the effectiveness of vibration-monitoring. Also, any instrumentation changes would be expensive and would disrupt the well established and effective vibration monitoring program in place. t I The slowest speed pumps in the McGuire IST program are the Nuclear Service-Water Pumps and the Diesel Generator ruel oil Transfer Pumps. They run at 1135 and 1745 rpm respectively. I

= Attachment 3 Additional Information for Relief Eequest I.3(D) 1 1/3 pump speed for these pumps carresponds to 6.58 and 9.G9 H: respectively. Therefore, the Nuclear Service Water Pumps are the only pumps that-will te monitored significantly belcw the range instruments are calibrated ever. Th+ fact that Instruments will not be cal;brated below 10 H: does act :.w an t h a t meaningful measurements can not be taken over the reage f rerc. 5.59 to 10 H:. "he vibration instruments used are repeatable ab this range. Also, the instrument manufacturers specify that their ac uracy statements are valid over this range under certain canditions. The range frcm 5.53 to'10 H: constitutes less than.52 percent of the range ever-whi:n measurements will be taken. Therefore, any additional inaccuracy over this range will have an :.nsignificant impact on everall vibration measurements. Hence, the lack of an accuracy statement over this range 18 insignificant. OH-3 Section 4.6.4.a, b; Vibration Measurement Points These cede sections specify vibration-measurement points for centrifugal (including vertical line shaft) pumps. The relief request elaborates on and adds some tlexibility to these requirements. Such flexibility is necessary because in some cases bearing housings are not accessible. I'or example, tne upper motor bearing _ housings en some vertical line shaft pumps are-inaccessible due to motor fans / cages. Therefore, if specified nearing-housings are inaccessible, the relief request sllows vibration to be measured at specified locations that.glve

the best indication of pump vibration.

The rel'ief reqtiest -also incorporates measurement points for internal gear positive displacement pumps, which are notLaddressed by OM-6. OM-6=Section 4.6.4.c, Vibration Measurement Points This code section specifies measurement points for reciprocating pumps. The relief request does not deviate from this requirement. - OM-6 Section 4.6.4.d, Vibration Measurement Points -This code section specifies that vibration measurement points must be clearly marked. The relief request does not request relief from that part of-IWP which has a similar requirement, thus, this requirement is met. h :- 1 i I u-a e.u----. a mMamvu -wW v-w rr

Additional 'nformation for Felief Request I.3(B) 31-6 Section 6.1,. Acceptance Criteria This code section specifies vibration acceptance criteria. The reitef requett adopts these acceptance criteria, with minor modifications. CM-6 does not include any acceptance criteria for Internal gear positive displacement pun.ps. Appropriate acc+ptance criteria were included in the relief request far these pumps. Also, fixed acceptance limits have been assigned for smcoth running pumps to inst.re that they do act fall into the alert or required action range while still running smoothly. The alert and required action ranges in OM-d are relative to reference values; therefore, smooth running pumps could fall into the alert or required action range, for example, when V. = This is inhppro.005 in/sec, acticn is required at.031 in/sec. priate since pump vibrations of.031 in/see are of no concern. Also, any I corrective actions taken would probably increase vibration l-levels. The fixed acceptance limits that have been assigned for smooth running pumps are acceptable because they are conservative. Vibration levels within the limits are acceptable for pumps in I the McGuire IST pregrem and any changes up to the limits are considered acceptable. The-limits were ectablished, in part, by substituting 0.075 in/sec into the rela ive acceptance criteria of OM-6. Therefore, i "very smooth" running pumps (V_ < 0.075 in/sec) will have the E same alert and action limits-that OM-6 establishes for " moderately' smooth" running pumps (V = 0.075). r -It should be noted that IWP-3210 allows alternate acceptance criteria to established and-used. 1/ CM-6 Section 5.2, Type of Vibration Measurement l l This section-allows either vibration displacement or velocity to l be measured. t is implied /specified that displacement should be l measured for pumps that operate at less than 600 rpm, and that velocity should be measured otherwise. None of the pumps in the McGuire IST program operate at less than 600 rpm; therefore, there is no need for the relief request to address the OH-6 recommendation to measure vibration displacements for pumps that L operate-at less than 600 rpm. o l L- -}}