ML20065S014
| ML20065S014 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire  |
| Issue date: | 11/19/1990 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20065R855 | List: |
| References | |
| PROC-901119, NUDOCS 9012200031 | |
| Download: ML20065S014 (56) | |
Text
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o UNIT 2 TABLE OF CONTENTS Page Section Number I. Pump Inservice Testing Program I.1 Introduction I.2 Data Sheets I.3 General Relief Requests I.4 Specific Relief Requests II. Valve Inservice Testing Program II.1 Introduction II.2 Table of Abbreviations 11.3 Definitions of Testing Requirements and Alternatives II.4 System Data Sheets:
Steam Generator Blowdown Recycle (BB) .............., 1 Auxiliary Feedwater (CA) ............................ 2 Feedwater (CF) ...................................... 3 Diesel Generator Engine 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 Resctor-Coolant (NC) ................................ 11 Residual Heat. Removal (ND) .......................... 12 Ice Condensor Ref rigeration (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 l- Nuclear Service Water (RN) .......................... 20-21 Containment Ventila+ on Cooling Water.(RV) .......... 22
, Main Steam Supply to Auxilary Equipment / Turbine L Exhaust (SA) ................................... 23 l Main Steam (SM) ..................................... 24 Main' Steam Vent to Atmosphere (SV) .................. 25 Breathing Air (VB) .................................. 26 Annulus-Ventilation (VE) ............................ 27 Diesel Generator Starting Air (VG) .................. 28 l
l Instrument Air (VI) ................................. 29 Containeent Purge Ventilation (VP) . . . . . . . . . . . . . . . . . . 30 Containment Air Release and Addition (VQ) ........... 31
-Station Air (VS) .................................... 32 9012200031 901210 Re?ision 11 PDR ADOCK 05000369 P PDR
1 I
l UNIT 2 I
Page l Section Number Containment Air Return Exchange and J Hydrogen Skimmer (VX) .......................... 33 1 Equipment Decon&. amination (WE) ...................... 34 Liquid Waste Recycle (WL) ........................... 35 Diesel Generator Room Sump Pump (WN) ................ 36 Makeup Demineralized Water (YM) ..................... 37 11.5 General Relief Requests II.6 Specific Relief Requests 11.7 Cold Shutdown Justifications i
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I 2-Revision 11
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McGUIRE - UNIT 2 ;
b TABLE OF ABBREVIATIONS 4
CLASS 1FICAT10N Duke
, System ;
- Valve ANS Class Designed for Safety l Code Desian Criteria S(fsmic Loadina 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
4 ANSI B31.1.0 (1967) No ---
H Duke Power Company Specification No ---
LEGEND LT - Leak Test MTO- - Movement Test Open MTC - Movement Test closed MTO,0 - Movement Test Open and Closed
-Q - Quarterly i
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 - Terinical Specification CL - Class-CAT - Category FS - Fall Safe 11 Revision 11
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- McGUIRE UNIT 2 l
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i' Ouarterly (Q) Testing will be performed at least once per -
three (3) months.
Refuelino 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 IVV-3510. Testing may be done l while in No Mode as well as Modes 3, 4, 5, and 6.
I Refuelino Outage (RF*) Valve will normally be tested during refueling outages, not to exceed 24 months
- per Appendix J to 10CFR50.
RefsqlinoOutage (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 oe performed per the requirements of IWV-3510.
Fail Safe (FS) Valve will be tested to verify it will reposition to its design safe position upon 11 loss of control air per IWV-3415.
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a Revision 11
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d Page No. 1 11/19/90 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DTACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E i hEMARKS V
- STEAM GENERATOR ELOWDOWN RECYCLE .
2BB-0001B B 2580-1.0 H-02 B ST-Q - - - -
2BB-0002B B 2580-1.0 H-04 B ST-Q - - - -
2BB-0003B B 2580-1.0 H-12 B ST-Q - - - -
2BB-0004B B 2580-1.'s H-10 B ST-Q - - - - '
2BB-0005A B 2500-1.0 F-02 B ST-Q - - - -
2BB-0006A B 2580-1.0 F-04 B ST-Q - - - -
2Pil-0007A B 2580-1.0 F-12 B ST-Q - - - -
2LB-000"A B 2580-1.0 F-10 B ST-Q - - - - I l
Page No. 2 11/19/90 Duke Power Company McCuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM I
VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMA/k'S V .
- AUXILIARY FEEDWATER 2CA-0007AC C 2592-1.1 B-10 B ST-Q - - - -
2CA-0008 C 2592-1.1 B-11 C MTC-Q -
CA2 RF# 10 2CA-0009B C 2592-1.1 C-05 B ST-Q - - - -
2CA-0010 C 2592-1.1 C-05 C MTC-Q -
CA2 RF# 10 2CA-0011A C 2592-1.1 B-04 B ST-Q - - - -
2CA-0012 C 2597-1.1 B-03 C MTC-Q -
CA2 RF# 10 2CA-0015A C 2592-1.1 D-03 B ST-Q - - - -
2CA-0018B C 2592-1.1 0-03 B ST-Q - - - -
2CA-0020AB C 2592-1.1 1-10 AC ST-Q LT - -
11 2CA-0022 C 2592-1.1 1-10 C MTO-Q - - - -
2CA-0026 C 2592-1.1 1-04 C MTO-Q - - - -
2CA-0027A C 2592-1.1 J-05 AC ST-Q LT -- -
11 2CA-0031 0 2592-1.1 1-07 C MTO-Q - - - -
2CA-0032B C 2592-1.1 1-08 AC ST-Q LT - -
11
-2CA-0036AB C 2592-1.0 L-10 B ST-Q - - - -
2CA-0037 B 2592-1.0 K-14 C MTO.C-Q - -
CS-CA1 -
2CA-0038B B 2592-1.0 J-14 B ST-Q - - - -
2CA-0040B C 2592-1.0 G-14 B ST-Q - -
2 SFC 11 2CA-0041 B 2592-1.0 H-14 C MTO.C-Q - - CS-CA1 -
2CA-0042B B 2592-1.0 I-14 B ST-Q - - - -
2CA-0044B C 2592-1.0 C-11 B ST-Q - - 2 SEC 11 2CA-0045 B '2592-1.0 C-09 C MTO.C-Q - -
CS-CA1 -
2CA-0046B B 2592-1.0 D-08 B ST-Q - - - -
2CA-0048AB C 2592-1.0 K-08 B ST-Q - - - -
2CA-0049 B 2592-1.0 H-08 C MTO.C-Q - - CS-CA1 -
2CA-0050B B 2592-1.0 G-08 B ST-Q - - - -
2CA-0052AB C 2592-1.0 K-07 B ST-Q - - - -
2CA-0053 B 2592-1.0 H-07 C MTO.C-Q - -
CS-CA1 -
2CA-0054AC B 2592-1.0 0-07 B ST-Q - - - -
2CA-0056A C 2592-1.0 C-04 B ST-Q - - - -
2CA-0057 B 2592-1.0 C-06 C MTO,C-Q - -
CS-CA1 -
2CA-0058A B 2592-1.0 D-07 B ST-Q - - - -
2CA-0060A C 2592-1.0 G-01 B ST-Q - - - -
2CA-0061 B 2592-1.0 H-01 C MTO.C-Q - -
CS-CA1 -
20A-0062A B 2592-1.0 1-01 B ST-Q - - - -
2CA-0064AB C 2592-1.0 L-04 B ST-Q - - - -
2CA-0065 B 2592-1.0 K-01 C MTO.C-Q ~ -
CS-CA1 -
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 - - - -
t 2CA-0161C DELETED 11 l 2CA-0162C DELETED 11 2CA-0165 C 2592-1.1 C-14 C MTO,C-Q -
CA1 RF# 11 2CA-0166 0 2592-1,1 G-14 C MTO.C-Q -
CA1 RF# 11
Page No. 3 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TES11hG PROGRAM TEST R TEST RR VALVE CL FLOW FLOW CAT TEST E REQ 1 REQ 2 ALTERNATIVES /
DIAGRAM COOR V REMARKS
- FEEDWATER - CS-CF2 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-CF1 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-CF2 2CF-0032AB F 2591-1.1 K-13 B ST-Q
- CS-CF1 2CF-0035AB B 2591-1.1 H-13 B ST-Q
- CS-CF4 4
2CF-0104AB F 2591-1.1 K-12 B ST-Q
- - CS-CF4 9 K 09 B ST-Q 9 2CF-0105AB F 2591-1.1 - CS-CF4 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-CF3 8 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 8
2CF-0129B B 2591-1.1 H-01 B ST-Q
- - 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 G-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
- CS-CFS 2CF-0152 B 2591-1.1 F-12 C MTC-Q
- - - 8 B 2591-1,1 G-11 B ST-Q -
2CF-0153B - CS-CFS F-11 C B 2591-1.1 MTC-Q 8 2CF-0154 - -
2CF-0155B B 2591-1.1 G-11 B ST-Q MTC-Q CS-CFS 2CF-0156 B 2591-1.1 F-10 C - - 8 2CF-0157B B 2591-1.1 G-12 B ST-Q -
C3-CF5 2CF-0158 B 2591-1.1 F-12 C MTC-Q
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l Page No. 4 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW Fl.0W CAT TEST TEST RR TEST R i DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V l
1
11 2FD-0093 C 2609-3.0 J-14 C MTO.C-Q - - -
11 2FD-0104 C 2609-3.1 E-13 C MTO.C-Q - - -
11 2FD-0105 C 2609-3.1 J-14 C MTO.C-Q - - -
11 e '
- _ ..- .--. __ -. . - . - -~.- -. . .- . _ - _ - _ - . - ~ _ _ _ - . _ - _ -
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i Page No. 5 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM YALVE CL FLOW FLOW CAT TEST TEST RR TEST R
, DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
2FW-0004 B 2571-1.0 D-08 A LT-RF - -
PASSIVE -
2FW-0005 B 2571-1.0 C-07 AC LT-RF - -
PASSIVE -
2FW-0011 B 2571-1.0 C-02 A LT-RF - - PASSIVE -
2FW-0013 B 2571-1.0 D-02 A LT-RF - -
PASSIVE -
2FW-0027A B 2571-1.0 C-12 B ST-Q - -
CS-FW1 2FW-0028 B 2571-1.0 B-11 C MTO.C-Q - -
CS-FW2 10 2FW-0032B B 2$71-1.0 E-11 B ST-Q - - - -
2FW-0033A B 2571-1.0 F-11 B ST-Q - - - -
2FW-0049B B 2571-1.0 F-10 B ST-Q - - -
2FW-0052 E 2571-1.0 1-05 C MTO-Q - - - --
2FW-0063 B 2571-1.0 C-03 AC LT-RF - -
PASSIVE -
4
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Page No. 6 E 11/19/90
- Duke Power Cotepany McGuire Nuclear Station PLMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E 4 REMARKS V
2 SEC 11 21A-5160 B 2499-IA1 N/A A ST-Q LT-RF -
2 SEC 11 21A-5340 B 2499-IA1 N/A AC LT-RF - - -
11 21A-5350 B 2499-IA1 N/A AC LT-RF - - - 11 2IA-5360 C 2499-IA1 N/A AC LT-RF - IA1 - 11 2IA-5370 C 2499-IA1 N/A AC LT-RF -
IA1 - 11 21A-5380 C 2499-IA1 N/A AC LT-RF - IA1 - 11 21A-5390 C 2499-1A1 N/A AC LT-RF - IA1 - 11 i
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Page No. 7 11/19/90 Duke Pcker Company McGuire Nuclear Station PUMP AND VALVE INSERVICE '
- ESTINC PROCRAM VALVE CL FLOW FLOW CAT 1" J TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
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 - - - -
3 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 25"J-4.0 L-07 AC MTC-Q LT-RF KC5 MT-RF -
2KC-0050A e 2573-1.0 K-07 B ST-Q - - - -
2KC-0051A 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 E-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-02288 C 2573-1.0 K B ST-Q - - - -
2KC-0230A C 2573-1.0 K-07 B ST-Q - - - -
2KC-0279 B 2573-3.1 K-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-14 B ST-Q - - - -
2KL-0315B B 2573-3.1 L-13 B ST-Q - - - -
2KC-0320A B 2573-3.1 0-10 A ST-Q LT-RF - CS-KC4 -
2KC-0322 B 2573-3.1 C-09 AC MTC-Q LT-RF KC2 MT-RF -
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 -
CS-KC3 -
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 11 2KC-0424B B 2573-3.1 L-04 A ST-Q LT-RF -
CS-KC1 -
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 ST-Q LT-RF - - -
2KC-0972 C 2573-1.1 K-08 C SP-RF -
15 PSIC -
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Page No. 8 11/19/90 Duke Power Company McGuire Nuclear Station PLHP AND VALVE INSERVICE TESTING PROGRAM VALVE CL TLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E RLMAhKS V
- DIESEL GENERATOR COOLING WATER 2KD-0009 C 2609-1.0 E-14 B FS-Q - - -
11 2KD-0029 C 2609-1,1 E-14 B FS-Q - - -
11 1
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- Page No. 9 11/19/90 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
2 SEC 11 2MI-5581 B 2499-MI7 N/A A ST-Q LT-RF - 2 SEC 11 2MI-5582 B 2499-MI7 N/A A ST-Q LT-RF -
2 SEC 11 2MI-5$83 B 2499-MI7 N/A A ST-Q LT-RF -
2 SEC 11
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r-v- - .w- - - . - - .-- ...g...,. . , _ . _ . ., . . .
Page No. 10 11/19/90 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE VALVE TESTING PROGRAM CL FLOW F1.0W DIACRAM CAT TEST TEST COOR RR REQ 1 REQ 2 TEST R
ALTERNATIVES / 4
~
REMAPIS E BORON RECYCLE V 2NB-0260B B 2SB-0262 2556-3.0 G-05 A B 2556-3.0 ST-Q LT-RF - -
G-03 AC MTC-Q LT-RT NB1 MT-RF -
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Page No. 11 11/19/90 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
- REACTOR COOLANT 2NC-0001 A 2553-2.0 K-03 C s' 3Y - - 2485 PSIG -
2NC-0002 A 2553-2.0 K-04 C Lf-3Y - -
2485 PSIG -
2NC-0003 A 2553-2.0 K-05 C SP-3Y - - 2485 PSIG -
2NC-0031B A 2553-2.0 F-05 B ST-Q - - - -
2NC-0032B A 2553-2.0 0-05 B ST-Q - -
CS-NC1. 2 SEC CLOSE 11 2NC-0033A A 2553-2.0 F-03 B ST-Q - - - -
2NC-0034A A 2553-2.0 G 03 B ST-Q - -
CS-NC1. 2 SEC CLOSE 11 2NC-0035B A 2553-2.0 F-0? B ST-Q - - - -
2NC-0036B A 2553-2.0 C-02 B ST-Q - -
CS-NC1. 2 SEC CLOSE 11 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 ST-Q LT-RF - - -
2NC-0057 B 2553-2.1 F-13 AC LT-RF - -
PASSIVE -
2NC-0141 B 2553-4.0 C-07 A PC-Q LT-RF -
PASSIVE -
2NC-0142 B 2553-4.0 B-06 A PC-Q LT-RF -
PASSIVE -
2NC-0195B 0 2553-4.0 I-08 A LT-RF - -
PASSIVE -
2NC-0196A B 2553-4.0 H-08 A LT-RF - -
PASSIVE -
2NC-0259 B 2553-4.0 H-08 AC MTC-Q L f-RF NC1 MT-RF* -
2NC-0261 B 2553-4.0 C-08 AC MTC-Q LT-RF NC1 MT-RF* 8 2NC-0272AC A 2553-2,1 J-09 B ST-Q - -
CS-NC2. 2 SEC 11 2NC-0273AC A 2553-2.1 J-10 B ST-Q - -
CS-NC2. 2 SEC 11 2NC-0274B A 2553-2,1 1-09 B ST-Q - -
CS-NC2. 2 SEC 11 2NC-0275B A 2553-2.1 1-10 B ST-Q - -
CS-NC2. 2 SEC 11 r
. - - . ~ . - _ _ - . - - . - _ - _ - - - _ . . - . . _ -. - - - _ .
Page No. 12 11/19/90 Duke Power Company J
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-ND1 PIV -
2ND-0002AC A 2561-1.0 H-13 A ST-Q LT-TS -
CS-ND1 P1V -
2ND-0004B B 2561-1.0 E-12 B ST-Q - - - -
2ND-0008 B 2561-1.0 D-08 C MTO.C-Q - - CS-ND6 10 2ND-0014 B 2561-1.0 D-03 B ST-Q - - - -
2ND-0015B B 2561-1.0 E-03 B ST-Q - -
CS-ND3 -
2ND-0019A B 2561-1.0 H-12 B ST-Q - - - -
2ND-0023 B 2561-1.0 J-08 C MTO.C-Q - -
CS-ND6 10 2ND-0029A B 2561-1.0 J-03 B ST-Q - - -
2ND-0030A B 2561-1.0 1-03 B ST-Q * -
CS-ND3 -
2ND-0058A B 2561-1.0 K-03 B ST-Q - -
CS-ND2 -
2ND-00678 B 2561-1.0 B-09 B ST-Q - - - -
2ND-0068A B 2561-1.0 L-09 B ST-Q - - - -
2ND-0070 B 2561-1.0 K-03 C MTO.C-Q - -
CS-ND4 10 2ND-0071 0 2561-1.0 C-04 C MTO.C-Q - - CS-ND5 10 t
1
I Page No. 13 11/19/90 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE 1ESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
2NF-0229 B 2558-4.0 F-13 AC MTC-0 LT-RF NF1 MT-RF* -
2NF-0233B B 2558-4.0 K-12 A ST-Q LT-RF NF2 LT per TS -
2NF-0234A B 2558-4.0 K-13 A ST-Q LT-RF NF2 LT per TS -
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l Page No. 14 11/19/90 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALIERNATIVES/ E REMARKS V
CS-nil -
2NI-0010B B 2562-1.0 G-12 B ST-Q - -
CS-nil -
2NI-0012 B 2562-1.0 0-09 C MTO-Q - -
CS-NI14 10 i 2NI-0015 A 2562-1.0 K-07 C MTO-Q - -
CS-NI13 10 2NI-0017 A 2562-1.0 1-04 C MTO-Q - -
CS-NI13 10 2NI-0019 A 2562-1.0 F-04 C MTO-Q - -
CS-NI13 10 2NI-00?1 A 2562-1.0 C-07 C MTO-Q - -
CS-NI13 10 2NI-0047A B 2562-2.0 K-05 A ST-Q LT-RF - - -
l 2NI-0048 B 2562-2.0 K-03 AC MTC-Q LT-RF NI3 MT-RF* -
l 2NI-0054A DELETED 9
-2NI-0059 A 2562-2.0 D-13 AC MTO.C-Q LT-TS NI4 PIV RF# -
2N1-0060 A 2562-2.0 D-14 AC MTO.C-Q LT-TS NI6 PIV RF# -
2NI-0065B DELETED 9 2NI-0070 A 2562-2.0 H-13 AC MTO.C-Q LT-TS N14 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 NI4 PIV RF# -
2NI-0082 A 2562-2.1 C-03 AC MTO.C-Q LT-TS NI6 PIV RF# -
2Ni-0088B DELETED 9 2NI-0093 A 2562-2.1 C-08 AC HTC.C-Q LT-TS NI4 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 - - -
2WI-0096B B 2562-2.1 E-13 A ST-Q LT-RF - - -
2NI-0100B B 2562-3.0 F-13 B ST-Q - -
CS-NI3 -
2NI-0101 B 2562-3.0 F-13 C MTO.C-Q - -
CS-NI15 10 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 FT-Q - - - -
2NI-0116 B 2562-3.0 J-09 C HTO.C - -
CS-NI16 10 2NI-0118A B 2562-3.0 H-07 B ST-Q - - - -
2NI-0120B B 2562-3,0 J-07 A ST-Q LT-RF - - -
2NI-0121A B 2562-3.0 J-06 B ST-Q - -
CS-NIS -
2NI-0124 A_ 2562-3.0 J-03 AC MTO.C-Q LT-TS - PIV CS-NI17 10 2NI-0125 A 2562-3.0 I-03 AC MTO.C-Q LT-TS -
PIV CS-NI20 10 2NI-0126 A 2562-3,0 J-02 AC MTO.C-Q LT-TS -
PIV CS-N120 10 2NI-0128 A 2562-3.0 1-04 AC MTO.C-Q LT-TS -
PIV CS-NI17 10 2NI-0129 A 2562-3.0 1-03 AC MTO C-Q LT-TS -
PIV CS-N120 10 2NI-0134 A 2562-3,0 H-04 AC MTO.C-Q LT-TS -
PIV CS-NI20 10 2NI-0135B B 2562-3.0 E-14 B ST-Q - - - -
2NI-0136B B 2562-3.0 C-14 B ST-Q - -
CS-NI21 11 2NIe0143 B 2562-3,0 F-09 C MTO.C-Q - - - -
2NI-0144B B 2562-3.0 G-09 B ST-Q - - - -
2NI-0147A B 2562-3.0 G-11 B ST-Q - -
CS-NI4 -
<2NI-0148 B 2562-3.0 D-09 C MTO.C - -
CS-NI16 10 2NI-0150B B 2562-3.0 E-07 B ST-Q - - - -
l l
1 Page No. 15 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM i
1 VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V 2NI-01528 B 2562-3.0 D-06 B ST-Q - - CS-NI6 -
2NI-0156 A 2562-3.0 D-03 AC MTO.C-Q LT-TS -
PIV CS-N117 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 - P1V CS-N117 10 ;'
2NI-0160 A 2562-3.0 B-03 AC MTO.C-Q LT-TS -
PIV CS-NI17 10 2N1-0162A B 2562-3.1 K-11 B ST-Q - -
CS-NI7 -
2NI-0165 A 2562-3.1 J-03 AC MTO.C-Q LT-TS -
PIV CS-N118 10 2NI-0167 A 2562-3.1 J-05 AC MTO.C-Q LT-TS -
PIV CS-NI18 10 2NI-0169 A 2562-3.1 J-06 AC MTO.C-Q LT-TS -
PIV CS-N118 10 2NI-0171 A 2562-3.1 J-07 AC MTO.C-Q LT-TS -
PIV CS-NI18 10 2NI-0173A B 2562-3.1 1-12 B ST-Q - - CS-NI8 -
2N1-0175 A 2562-3.1 1-08 AC MTO.C-Q LT-TS -
P1V CS-N119 10 2N1-0176 A 2562-3.1 H-08 AC MTO.C-Q LT-TS - PIV CS-N119 10 2NI-0178B B 2562-3.1 F-12 B ST-Q - -
CS-N19 -
2NI-0180 A 2562-3.1 T-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-N119 10 2NI-0183B B 2562-3.0 0-03 B ST-Q - - CS-nil 0 -
2NI-0184B B 2562-3.1 D-12 B ST-Q - -
CS-N111 -
2NI-0185A -B 2562-3.1 B-12 B ST-Q - -
CS-N111 -
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 - - -
2N1-0347- A 2562-1.0 1-04 C MTO-Q - -
CS-N113 10 2NI-0348 A 2562-1.0 F-05 C MTO-Q - -
CS-NI13 10 2NI-0349 A 2562-1.0 C-07 C MTO-Q - -
CS-N113 10 2N1-0354 A 2562-1.0 K-07 C MTO-Q - -
CS-N113 10 2NI-0430A B 2562-2.0 F-04 B ST-Q - -
CS-NI2 -
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 tit-RF * -
1 i
I Page No. 16 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR IEST R j DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V l
- NUCLEAR SAMPLING 2NM-0003AC D 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-00268 B 2572-1.0 K-09 A ST-Q - - - -
2NM-0069 B 2572-1.1 G-09 A LT-RT - -
PASSIVE -
4 2NM-0072B B 2572-1.1 1-06 A ST-Q LT-RF - - -
2NM-0075B B 2572-1.1 1-08 A ST-Q LT-RF - - -
2NM-00788 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 LT-RF - - -
2NM-0187A B 2572-3.0 K-01 B ST-Q - - - -
2NM-0190A B 2572-3.0 K-02 B ST-Q - - - -
2NM-0191B B 2572-3.0 1-02 B ST-Q - - - -
2NM-0197B B 2572-3,0 K-05 B ST-Q - - - -
2NM 0200B B 2572-3.0 K-06 B ST-Q - - - -
2NM-0201A B 2572-3.0 I-06 B ST-Q - - - -
2NM-0207A B 2572-3,0 K-08 B ST-Q - - - -
2NH-0210A B 2572-3.0 K-09 B ST-Q - - - -
2NM-0211B B 2572-3.0 1-09 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 1-12 B ST-Q - - - -
2NM-0420 B 2572-1.0 J-03 AC MTC-Q LT-RF NM1 MT-RF* -
2NM-0621 B 2572-1.0 J-12 AC MTC-Q LT-RF NM1 MT-RF* -
\
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pin.mi mis . q Page No. 17 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVTCE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
- 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 RFH 11 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 - - - -
2NS-0021 B 2563-1.0 F-12 C MTO.C-Q -
NS2 RF# 11 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 h 2563-1.0 H-04 B ST-Q - - - -
2NS-0033 B 2563-1.0 H-02 C MTO-Q NS1 RF# -
2NS-0038B B 2563-1.0 J-05 B ST-Q - - CS-NS1 11 2NS-0041 B 2563-1.0 J-03 C MTO-Q -
NS1 RF# -
2NS-0043A B 2563-1.0 K-05 B ST-Q - -
CS-NS1 11 2NS-0046 B 2576-1.0 K-03 C MTO-Q -
NSI RF# -
2NS-5550B B 2499-NS8 N/A A ST-Q LT-RF - 2 SEC 11 2NS-3351A B 2499-NS8 N/A A ST-Q- LT-RF -
2 SEC 11
. . _ . . .. . m.
l Page No. 18 11/19/90 Duke Power Company McGuire Nuclear Station PL'MP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW FLOW CAT TEST TFST RR TEST R DIACRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
CS-NV2 -
2NV-0021A A 2554-1.2 E-03 h ST-Q - -
CS-NV4 2 SEC 11 2NV-0022 DELETED 11 2NV-0024B A 2554-1.2 D-06 B ST-Q - -
2 SEC 11 2NV-002$B A 2554-1.2 D-07 B ST-Q - - 2 SEC 11 2NV-0035A B 2554-1.2 K-07 B ST-Q - - -
11 2NV-0094AC B 2554-1.1 J-13 B ST-Q - - CS-NV1 -
2NV-0095B B 2554-1.1 H-13 B ST-Q - -
CS-NV1 -
2NV-0141A B 2554-2.0 D-08 B ST-Q - -
CS-NV7 -
2NV-0142B B 2554-2.0 B-07 B ST-Q - -
CS-NV7 -
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-NV12 8 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-NV9 -
2NV-0223 B 2554-3.1 1-02 C MTO.C-Q - -
CS-NV15 10 2NV-0225 B 2554-3.1 F-05 C MTO.C-Q - -
CS-NV14 10 2NV-0227 B 2554-3.1 E-06 C MTO.C-Q - - - -
2NV-0231 B 2554-3.1 F-10 C MTO.C-Q - -
CS-NV14 10 2NV-0233 8 2554-3.1 E-10 C NTO.C-Q - - - -
2NV-0244A B 2554-3,0 K-08 B ST-Q - -
CS-NV8 -
2NV-0245B B 2554-3.0 K-09 B ST-Q - - CS-NV8 -
2NV-0264 B 2554-3.1 J-10 C MTO-Q - -
CS-NV1] -
2NV-0265B B 2554-3.1 J-09 B ST-Q - -
CS-NV13 8 e 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 11 2NV-0842AC DELETED 11 2NV-0844 DELETED 11 2NV-0849AC B 2554-1.3 F-08 A ST-Q LT-RF - - -
2NV-1002 B 2554-1,3 F-10 A.C MTC-Q LT-E7 NV1 MT-RF 11 2NV-1007 DELETED 11 2NV-1008 DELETED 11 2NV-1009 DELETED 11 2NV-1010 DELETED 11 2NV-1012C DELETED 11 2NV-1013C DELETED 11 2NV-1046 B 2554-3.0 H-12 C MTC-Q - - CS-NV16 11
l 1
Par.e No. 19 11/19/90 I Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE ;
TESTING PROGRAM l VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E l
]'
REMARKS V j
- FIRE PROCIECTION 1RF-0832A B 1599-2.2 1-05 A LT-RF - -
PASSIVE. U2CIV -
1RF-0834 B 1599-2.2 1-08 AC MTC-Q LT-RF RF1 MT-RF*. U2CIV -
l l
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. ~ . . . _ . _ _ . . - . . _ . . . . . . . . _ _ . . . - . . . _ . . . _ . _ . . . - , - , . . , - , _ _ . _ . . . _ - . ,
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Page No. 20 11/19/90 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-03 B ST-Q - - - -
- 2RN-0018B~ C 2574-1.1 E-02 B ST-Q - - - -
2RN-0021A C 2574 ',. J-02 B ST-Q - - -
11 2RN-0022A C 2$74-2 1 H-uS B ST-Q - - -
11 2RN-0025B C 2574-1.1 C-04 B ST-Q - - -
11 2RN-0026B C 2574-1,1 G-05 B ST-Q - - -
11 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 - - - -
2RN-00&iB C 2574-1.1 F-12 B ST-Q - -
U2 & U1 SIGNAL -
2RN-0042A C 2574-4.0 B-09 B ST-Q - -
CS-RN4 -
2RN-0043A C 2574-1.1 F-12 B ST-Q - -
U2 & U1 SIGNAL -
2RN-0063B C 2574-4.0 L-10 B ST-Q - -
CS-RN5 -
2RN-0064A C 2574-4.0 L-11 B ST-Q - -
CS-RN5 -
2RN-0068A C 2574-1.1 L-12 B ST-Q - -
2 SEC 11 2RN-0069A C 2574-2.0 K-01 B ST-Q - - - -
2RN-0070A C 2574-2.0 E-06 B ST-Q - - - -
2RN-0073A C 2574-2.0 1-06 B ST-Q - - - -
2RN-0086A C 2574-2.0 D-12 B ST-Q - - - -
2RN-0089A C 2574-2.0 J-12 B ST-Q - - - -
2RN-0103A C 2574-2.1 C-06 B ST-Q - -
2 SEC 11 2RN-0112A C 2574-2.0 I-08 B ST-Q - -
2 SEC 11 2RN-0113 C 2574-2.0 D-13 C MTO-Q -
RN1 RF -
2RN-0114A C 2574-2.1 B-11 B ST-Q - -
2 SEC 11 2RN-0117A C 2574-2.0 1-10 B ST-Q - -
2 SEC 11 2RN-0126A C 2574-2,1 D-10 B ST-Q - - -
8 2RN-0130A C 2574-2.1 C-10 B ST-Q - -
2 SEC 11 2RN-0134A C 2574-2,1 0-07 B ST-Q - - - -
2RN-0137A C 2574-2.1 H-07 B ST-Q -
2RN-0140A C 2574-2.0 E-14 B ST-Q - -
2 SEC 11 2RN-0161B C 2574-1.1 B-12 B ST-Q - -
2 SEC 11 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 1-01 B ST-Q - - - -
2RN-0171B C 2574-3,0 F-07 B ST-Q - - - -
2RN-0174B C 2574-3.0 1-07 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 - - - -
2RN-0204B C 2574-3.1 C-05 B ST-Q - -
2 SEC 11 2RN-0213B C 2574-3.0 J-08 B ST-Q - -
2 SEC 11 2RN-0214 C 2574-3,0 D-14 C MTO-Q RN1 RF -
2RN-0215B C 2574-3.1 B-11 B ST-Q - - -
11 2RN-0218B C 2574-3.0 1-10 B ST-Q - -
2 SEC 11 2RN-0227B C 2574-3.1 E-10 B ST-Q - - - -
2RN-0231B C 2574-3.1 C-10 B ST-Q - -
2 SEC 11
__-.._ .___.._ . _ . . _ _ _ . . ~ _ . _ _ _ . _ . __
Pace No. 21 2 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROCRAM "ALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V i 2RN-0235B C 2574-3.1 E-07 B ST-Q - - - -
2RN-0238B C 2574-3.1 1-07 8 ST-Q - - - -
2RN-0240B C 2574-3.0 F-13 B SI-Q - - 2 SEC 11 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 -
CS-RN2 -
2RN-0276A C 2574-4.0 J-02 A ST-Q LT-RF - CS-RN3 -
2RN-0277B C 2592-4.0 H-02 A ST-Q LT-RF - CS-RN3 2RN-0279B C 1574-1.0 C-02 B ST-Q - - - -
2RN-0296A C 2574-1.1 L-13 B ST-Q - - - -
2RN-0297B C 2574-3.0 L-05 B ST-Q - - - -
2RN-0299A .C 1574-1.0 C-02 B ST-Q - - -
<W l
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Page No. 22 j
11/19/90 Duke Power Company McGuire Nuclear station M'MP 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 j
CS-RV1 -
2RV-0033B 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 -
1 2RV-0077B B 2604-3.0 C-10 A ST-Q LT-RF -
CS-RV1 - !
2RV-0079A B 2604-3.0 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 B 2604-3,0 B-12 AC MTC-Q LT-RF RV1 MT-RF* -
. 2RV-0130 B 2604-3,0 J-12 AC MTC-Q LT-RF RV1 MT- RF * -
+
Page No. 23 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLOW TLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E RDiARKS V
- MAIN STEAM TO AUX. EQUIPMENT j 2SA-0005 B 2593-1.2 F-04 C MTO.C-Q - - -
10 2SA-0006 D 2593-1.2 T-03 C MTO.C-Q - - - 10 2SA-0048ABC L 2593-1.2 E-04 B ST-Q - - - -
2SA-0049AB B 2593-1.2 T-02 B ST-Q - - - -
-l l
l-E_-_--, -_.-2-__ , _ . _ _ _ _ _ _ , _ , , _ _ , . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ . , _ _ _ _ _ . _ _
Page No. 24 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTI:'G PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
- MAIN LTEAM 2SM-0001AB B 2593-1.0 K-13 B ST-Q - - CS-SM1 -
2SM-0003AB ? 2593-1.0 11 - 1 3 B ST-Q - -
CS-SM1 -
2SM-000$AB B 2593-1.0 1-14 B ST-Q - -
CS-SM1 -
')M-0007AB B 2593-1.0 C-14 B ST-Q - -
CS-SM1 -
/SM-0009AB B 2593 .'.0 J-13 B ST-Q - - CS-SM2, 2 SEC 11 2SM-0010AB B 2593-1.0 G-13 B ST-Q - - CS-SM2, 2 SEC 11 2SM-0011AB B 2593-1.0 1-13 B ST-Q - - CS-SM2, 2 SEC 11 2SM-0012AB B 2593-1.0 C-13 B ST-Q - - CS-SM2, 2 SEC 11
l Page No.. 25 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICC TESTING PROGRAM VALVE CL FLOW 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 - - - -
2SV-0002 B 2593-1.3 K-06 C SP-5Y - -
1170 PSIG -
2SV-0003 8 2593-1.3 K-07 C SP-5Y - -
1190 PSIG -
2SV-0004 B 2593-1.3 K-09 C SP-5Y - - 1205 PSIG -
2SV-0005 B 2593-1,3 K-11 C SP-5Y - -
1220 PSIG -
2SV-0006 8 2593-1.3 K-12 C SP-5Y - -
1225 PSIG -
2SV-0007ABC B 2593-1,3 G-05 B ST-Q - - - -
2SV-0008 8 2593-1.3 E-06 C SP-5Y - - 1170 PSIG -
2SV-0009 B 2593-1,3 E-07 C SP-5Y - -
1190 PSIG -
2SV-0010 B 2593-1.3 E-09 C SP-5Y - -
1205 PSIG -
2SV-0011 B 2593-1,3 E-11 C SP-5Y - -
1220 PSIG -
2SV-0012 B 2593-1.3 E-12 C SP-5Y - -
1225 PSIG -
2SV-0013AB B 2593-1.0 L-04 B ST-Q - - - - I 2SV-0014 C' 2593-1.0 K-05 L SP-5Y - -
1170 PSIG -
2SV-0015 B 2593-1.0 K-07 C SP-5Y - -
1190 PSIG -
2SV-0016 B 2593-I.0 K-09 C SP-5Y - -
1205 PSIG -
2SV-0017 B 2593-1.0 K-10 C SP-5Y - -
1220 PSIG - i 2SV-0018 B 2593-1.0 K-12 C SP-5Y - -
1225 PSIG -
2SV-0019AB B 2593-1.0 G-05 B ST-Q - - - - >
2SV-0020 B 2593-1.0 E-05 C SP-5Y - -
1170 PSIG -
2SV-0021 B 2593-1.0 E-07 C SP-5Y - -
1190 PSIG -
2SV-0022 B 2593-1.0 E-09 C SP-5Y - -
1205 PSIG -
2SV-0023 8 2593-1.0 E-10 C SP-5Y - -
1220 PSIG - 2 2SV-0024 B 2593-1.0 E-12 C SP-5Y - -
1225 PSIG -
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Page No. 26 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE C1 FLOW FLOW CAT TEST TEST RR TEST n
- T 'fMM COOR REQ 1 REQ 2 ?LTERNATIVES/ E REMARKS V
2VB+0050 B 2605-3.1 E-04 AC MTC-Q LT-RF VB1 MT-RF* -
Page No. 27 11/19/90 Duko Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTING PROGRAM VALVE CL FLC FLOW CAT TEST TEST RR- TEST R DIAG +wM COOR REQ 1 REQ 2 ALTERNATIVES / E REMARKS V
2VE-0006B B 2564-1 G-04 A ST-Q LT-RF - - -
2VE-0008A B 2564-1 J-02 B ST-Q - - - -
2VE-0010A B 2564-1 11 - 0 3 A ST-Q LT-RF - - -
2VE-0011 B 2564-1 H-03 AC LT-RF - -
PASEIVE -
-r
Page No. 28 11/19/90 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
- D1ESEL GENERATOR STARTING AIR 2VG-0003 C 2609-4.0 J-12 C MTO-Q - - -
11 2VG-0004 C 2609-4.0 E-12 C MTO-Q - - -
11 2VG-0017 C 2609-4.0 J-06 C MTO-Q - - -
11 2VG-0018 C 2609-4.0 1-06 C MTO-Q - - -
11 2VG-0019 C 2609-4.0 E-06 C MTO-Q 11 2VG-0020 C 2609-4.0 D-06 C MTO-Q - - -
11 2VG-0061 C 2609-4.0 K-02 B ST-Q - -
2 SEC 11 2VG-0062 C 2609-4.0 K-02 B ST-Q - -
2 SEC 11 2VG-0063 e 2609-4.0 1-02 B ST-Q - -
2 SEC 11 2VG-0064 C 2609-4.0 H-02 B ST-Q - -
2 SEC 11 2VG-0065 C 2609-4.0 F-02 B ST-Q - -
2 SEC 11 2VG-0066 C 2609-4.0 E-02 B ST-Q - -
2 SEC 11 2VG-0067 C 2609,4.0 C-02 B ST-Q - -
2 SEC 11 2VG-0068 C 2609-4.0 C-02 B ST-Q - -
2 SEC 11 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 P-09 C MTO-Q - - - -
2VG-0118 C 2609-4.0 C-09 C MTO-Q - - - -
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Page No. 29 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSERVICE TESTINC PROGRAM VALVE CL FLOW FLOW CAT TEST TEST RR TEST R DIAGRAM COOR REQ 1 REQ 2 ALTERNATIVES! E REMARKS V
2VI-0124 B 2605-1,2 B-04 AC MTC-0 LT-RF VII MT-Rr* -
2VI-0129B B 2605-1,3 J-11 A ST-Q LT-RF - - -
2VI-0135 C 2605-1,3 J-07 AC MTC-Q LT VI3 -
11 2VI-0136 C 2605-1,3 J-08 AC MTC-Q LT VI3 - 11 2VI-0137 C 2605-1,3 D-06 AC MTC-Q LT VI3 -
11 2VI-0138 C 2605-1,3 D-06 AC MTC-Q LT VI3 -
11 2VI-0139 C 2605-1.3 D-07 AC MTC-Q LT VI3 - 11 2VI-0140 C 2605-1.3 D-07 AC MTC-Q LT VI3 -
11 2VI-0141 C 2605-1.3 J-06 AC MTC-Q LT VI3 - 11 2VI-0142 C 2605-1,3 J-06 AC MTC-Q LT VI3 -
11 2VI-01488 B 2605-1.2 E-03 A ST-Q LT-RF - - -
2VI-0149 B 2005-1.2 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 - - -
. . . . _ _ _ _ . . _ _ ~ .._ . . . _ _
Page No. 30 11/19/90 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
- CONTAINMENT PURGE VENTILATION 2VP-0001B B 2576-1 1-06 A LT-TS - - -
10 2VP-0002A B 2576-1 1-07 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 - - -
' ')
2VP-00138 B 2576-1 1-09 A LT-TS - - -
A0 2VP-0015A B 2576-1 .F-08 A LT-TS - - -
10 2VP-0016B B 2576-1 F-09 A LT-TS - -
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 - - -
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Page ?!o. 31 I 11/19/90 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 l REMARRS V l l
2 SEC 11 2VQ-0002B B 2585-1.0 J-06 A ST-Q LT-RF -
2 SEC 11 2VQ-0005B B 2585-1.0 E-06 A ST-Q LT-RF -
2 SEC 11 ' '
2VQ-0006A B 2585-1,0 E-03 A ST-Q LT-RF -
2 SEC 11 l
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Page No. 32 ,
11/19/90 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
2VS-0013 B 2605-2.2 H-08 AC MTC-Q LT-RF VS1 MT-RF* -
Page No. 33 11/19/90 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
2VX-0002B B 2557-1 I-12 B ST-Q - - - -
2VX-0030 B 2557-1 J-03 AC MTC-Q LT-RF VX1 MT-RF -
2VX-00;1A B 2557-1 J-13 A ST-Q LT-RF -
2 SEC 11 2VX-0033B B 2557-1 J-12 A ST-Q LT-RF -
2 SEC 11-2VX-0034 B 2557-1 K-12 A LT-RF - -
PASSIVE -
2VX-0040 B 2557-1 K-03 A LT-RF - -
PASSIVE -
Page No. 34 11'19/90 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
- EQUIPMENT DECONTAMINATION 2WE-0013 B 2568-1.0 E-08 A LT-RF - -
PASSIVE -
2WE-0023 B 2568-1.0 E-09 A LT-RF - -
PASSIVE -
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1 Page No. 35 11/19/90 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
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 WL2 MT-RF* -
2WL-0039A P. 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 - - -
2WL-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 7565-7,0 1-05 A ST-Q LT-RF - - -
2WL-0322B- B 2565-7.0 H-04 A ST-Q LT-RF - - -
2WL-0385 B 2565-7.0 J-05 AC MTC-Q LT-RF tiL3 MT-RF* -
2WL-0466 DELETED 9 2WL-1301B B 2565-1.0 03 A ST-Q LT-RF - - -
2WL-1302A B 2565-1.0 E-04 A ST-Q LT-RF - - -
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Page No. 36 11/19/90 Duke Power Company McGuire Nuclear Station PUMP AND VALVE INSEPVICE TFSTING PROGRAM VALVE CL FLOW FLOW CAT T iEST RR TEST R DIAGRAM COOR F REQ 2 ALTERNATIVES / E REMARKS V
, ** DIESEL GENERATOR ROOM SUMP PUMP 2VN-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 - - - -
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Page No. 37 11/19/90 Duke Power Company McGuire Nuclear Station TUMP 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
2YM-0116 B 1601-2,4 C-04 AC MTC-Q LT-RF YM1 MT-RF* -
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McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-IAl ,
VALVE: 2IA-5360, 21A-5370, 2IA-5380, 2IA-5390 FLOW DIAGRAM: MC-2499-IAI CATEGORf: AC
-CLASS: B FUNCTION: Check containment pressure on reactor building side of airlock and relieve to containment to preveat 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.
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4 New Page Revision 11 t-
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McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: RR-NB1 VALVE: 2NB-262 FLOW DIAGRAM: MC-2556-3.0 CATErORY: 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 i accordance with Appendix J. 111 Revision 11
_ _- _ _ ____ -.__.___. . - ._..___._.____._.__.__.m.--,_.__
Mc0's - -
UNIT-2 7
4 RELIEF / JUSTIFICATION: RR-VI3 VALVE: 2VI-135, 2VI-136, 2VI-137, 2VI-138, 2VI-139, 2VI-140, 2VI-141, 2VI-142 FLOW DI.\ GRAM: MC-2605-1.3
.g CATEGORY: AC CLASS: C FUNCTIONi Check instrument air from the main steam isolation valve accumulator tank.
TEST REQUIREMENT . Cycle quarterly and leak test.
1 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 depressurizing 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 4
Revision 11
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f 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 :
injection inoperable.
ALTERNATE TESTING: Valve will be cycled and timed during cold shutdown. it ,
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Revision 11
- W-- e, ++-pi--
- w. y -, my..e 9....rgm4: y. ,,,-. g. v+- w-. og y-m-.p e. y---3 g,yw.-vr , , y a
McGUIRE - LHIT 2 RELIEF /dOSTIFICATION: CS-ND4 VALVE: 2ND-70 FLOW OIAGRAM: MC-2561-1.0 CATEGORY: C i CLASS: B FUNCTION: RHR to SI Suction Check TEST REQUIREMENT: Full stroke exercise quarterly.
BASIS: 2ND-70 cannot be full stroked during pcwer operation since the only full flow path is into the'RCS and this
'can only he performed during cold shutdown. The miniflow for NO Pump 2A-does not pass through 2ND-70 so it cannot be partial strcKed during power operation.
2NO-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 testedsat cold shutdown and depressurized, but not it more often than once per nine months.
Revision 11
l McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-ND5 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 into the RCS and this can only be done at refueling. 2NO-71 cannot be partial 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, but not more often than once per 11 nine months.
Revision 11
McGUIRE - UNIT 2 RELIEF /JUbTIFICATION: 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 valv3 from the refueling water storage taak, NI-101, in tha event of a LOCA. The RHR pumps would start, seating the check valve and causing the safety injection pumps to runout the RHR pumps.
ALTERNATE TESTING: Valves will be cycle timed during cold shutdova.
New Page Revision 11
McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NSI VALVE: 2NS-38B, 2NS-43A FLOW DIAGRAM: MC-2563-1.0 CATEGORY: B CLASS: B FUNCTION: Containment Spray Header Isolation TEST REQUIREMENT: Cycle time quarterly.
BASIS: Opening either of these valves during modes in which the Residual Heat Removal (RHR) 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 vill be cycle timed during cold shutdown.
p-New Page Revision 11'
McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-NV3 (Deleted per Rev. 11)
VALVE: 2NV-1A, 2NV 2A I
1 i
Revision 11
McGUIRE - UNIT 2 s
RELIEF / JUSTIFICATION: CS-NVS (Deleted per Rev. 11)
VALVE: 2NV-22 l
Revision 11
McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: C9-NV6 (Deleted per Rev, 11)
VALVE: civ-1007, 2NV-1008, 2NV-1009, 2HV-1010 Revision 11
McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-HV10 (Deleted per Rev. 11)
VALVE: 2NV-459A Revision 11
McGUIRE - UNIT 2 RELIEFMUS(IFICATION: CS-NV16 VALVE:
2NV-1046 FLOW DIAGRAM:
MC-2554-3.0 CATEGORY: C CLASS: B FUNCTI0ti:
Opens on reciprocating charging pump recirc. flow. .
Closes to charging prevent pump diversion of flow to tb centrifugal suctions.
TEST REQUIREMENT:
Verify proper valve movement once every 3 months.
BASIS:
Testing this valve on line would result in adding 2000 ppm barated water to the centrifugal charging pump suction resulting in a reactor power transient.
ALTERNATE TEST 1HG:
Valve shutdown.
will be verified to seat closed during cold l
New Page Revision 11
McGUIRE - UNIT 2 RELIEF / JUSTIFICATION: CS-P.11 (Deleted per Rev. 11)
VALVE:
2PF 21A, 2RN-22A, 2RN-25B 2RN-26B t
i Revision 11
McGUIRE - UNIT 2 l
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 REQUIREMENT:
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.
ALTERNA'1E TESTING:
Valves will be full stroke exercised during cold shutdown.
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