ML17328B011
| ML17328B011 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 04/09/1991 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0969S, AEP:NRC:969S, NUDOCS 9104170110 | |
| Download: ML17328B011 (41) | |
Text
'-.ACCELERATED DISTIK3UTION DEMONSTPWTION SYSTEM
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NOTES
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REGULATORY'NFORMATION DXSTRXBUTXON SYSTEM (RIDS)
ESSION NBR:9104170110 DOC.DATE: 91/04/09 NOTARXZED: NO DOCKET'ACXL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Xndiana
!l 05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana 6
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION R
MURLEY,T.E.
Document Control Branch (Document Control Desk)
I
SUBJECT:
Forwards rev to inservice tesing program resulting from I
901207 response to open items in Insp Repts 50-315/90-201 50-316/90-201 re lack of inclusion of certain ESW check valves into inservice testing program.
8 DISTRIBUTION CODE:
A047D COPIES RECEIVED:LTR ENCL SXZE:
TITLE: OR Submittal: Inservice Inspection/Testa.ng/Relief from ASME Code RECIPIENT ID CODE/NAME PD3-1 LA COLBURN,T.
INTERNAL: AEOD/DSP/TPAB NRR/DET/EMEB 7E OC+J gIL 01 ERNAL:
EGGG BROWN,B NRC PDR COPXES LTTR ENCL 1
0 2
2 1
1 1
1 1
0 1
1 1
1 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS2 RES/DSIR/EIB EGGG RANSOME,C NSIC COPIES LTTR ENCL 1
1 1
1 1
1 1
0 1
1 1
1 1
1 D
D S
D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 13 D
D
I c
l
Indiana Michigan Power Company One Summit Square P.O. Box 60 Fort Wayne, IN 46801 219 425 2111 Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 IST PROGRAM REVISION/CHECK VALVE REVERSE FLOW AEP:NRC:0969S U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.
20555 Attn:
T.
E. Murley April 9, l991
Dear Dr. Murley:
References:
1)
Lett:er AEP:NRC:1125H, M.
PE Alexich to A. B. Davis, "Inspection Reports 50-315/90201 (DRS) and 50-316/90201 (DRS)," dated December 7,
1990.
2)
Letter AEP:NRC:0969R, M. P. Alexich to T.
E. Murley, "Revised Second 10-year Inservice Test Program," dated February 16, 1990.
3)
Letter, J.
G. Giitter to M. P. Alexich, "Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and
- Valves, D.
C.
Cook Nuclear Station, Units 1 and 2
(TAC Nos.
60028/60029),"
dated August 29, 1989.
This letter transmits a revision to the In-service Testing Program for the Donald C.
Cook Nuclear Plant.
This revision results from our response to Inspection Report 50-315/90201 and 50-316/90201 Open Item 90-201-09, "Lack of Inclusion of Certain ESW Check Valves Into IST Program."
(Reference 1)
The program has revised the requirements for the following essential service water system valves:
1-ESW-111 1-ESW-112 1-ESW-113 1-ESW-114 1-ESW-101E 1-ESW-101W 2-ESW-141 2-ESW-142 2-ESW-143 2-ESW-144 2-ESW-102E 2-ESW-102W 9i04i70ii0 9i0409 PDR ADOCK 05000315 9
/oft I//
S 1
P F$
4 Ku Il
Dr. T. E. Murley AEP: NRC: 0969S The revised pages of the IST program are included in Attachment l.
These changes will be implemented by July 10, 1991.
This will allow time to revise the applicable test procedures.
As part of our response to the open item, we committed to review the IST program for those check valves not currently assigned a
backflow checking safety function, and to make any changes deemed necessary.
This review, which is currently in progress, has been expanded beyond the scope identified in our February 16, 1990 (Reference
- 2) submittal, and it is estimated that the review will be completed with necessary program changes submitted by October 30, 1991.
Additionally, during the review for this submittal, we discovered two changes to our IST program which were not specifically identified in Attachment 4, Item 3 of our February 16, 1990 submittal.
These changes are the deletion of the full flow test for valves RH-133 and -134 (these are passive valves which have no open safety function) and a revised relief request for valves SI-158, Ll thru L4 and SI-161, Ll thru L4.
The relief was requested because of radiation exposure to plant personnel taking the required flow measurements rather than low temperature overpressure concerns noted in the Safety Evaluation Report (Reference 3).
The previously submitted pages of the IST program are included as Attachment 2 for your information, This letter has been reviewed by the Plant Nuclear Safety Review Committee, This document has been prepared following Corporate procedures that incorporate a reasonable set of controls to ensure its accuracy and completeness prior to signature by the undersigned.
Sincerely,p~
E.
E. Fitzpatrick Vice President ldp Attachments cc:
D. H. Williams, Jr, A. A. Blind - Bridgman J
~ R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector
- Bridgman
ATTACHMENT 1 REVISION TO THE DONALD C.
COOK NUCLEAR PLANT IN-SERVICE INSPECTION PROGRAM
DONALD C.
COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT 1 LIST OF DRAWINGS Revision No:
3A Date:
3-7-91 Figure 2
NO.
SYSTEM FLOW DIAGRAM NO.
REVISION Main Steam Main Steam Steam Generating System Feedwater Feedwater (Auxiliary)
Essential Service Water Non-Essential Service Water Station Drainage Containment Reactor Coolant Reactor Coolant 1-5105 1-5105B 1-5105D 1-5106 1-5106A 1-5113 1-5114A 1-5124 1-5128 1-5128A 29 35 1
35 38 46 31 22 19 37 CVCS-Reactor Letdown 6 Charging 1-5129 1-5129A 31 19 Component Cooling Component Cooling Component Cooling Nuclear Sampling Nuclear Sampling Post Accident Sampling-Containment Hydrogen 1-5135 1-5135A 1-5135B 1-514 1 1-514 lA 1-514 1D 35 30 14 29 32 10 Page 9 of 81
li~
DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5113-46 Revision No:
3A Date:
3-7-91 NOTE 1:
ESW-111
-112
-113
-114 Code Relief These check valves open to provide cooling water flow to various Emergency Diesel Generator loads.
In addition, these valves close to prevent back flow into the opposite ESW train header.
The open safety function will be tested in accordance with IWV-3520.
The closed safety function cannot be tested in accordance with IWV-3520 for the following reasons:
There are no external position indicators associated with the valves, and no instrumentation or taps available at the valve to determine positive closure.
In order to determine valve
- closure, an entire ESW header and safety train, including both Emergency Diesel Generators, must be removed from service.
These valves cannot be tested at cold shutdown frecpxency since, with fuel
- loaded, the ESW is at its highest load demand (RHR operating) at this time and cannot be removed from service.
The closed safety function of these valves shall be verified by disassembly at refueling frequency.
NOTE 2:
ESW-109
-115
-243 Cold Shutdown Justification These valves are normally closed and are required to be open when the condensate storage tank is exhausted.
Exercising the valves could cause lake water contamination of the steam generators.
Lake water chemistry can potentially impact steam generator tube integrity.
Therefore, the valves will be full stroke tested at a cold shutdown frequency.
Since the valves are manual, stroke timing is not required.
Page 20 of 81
DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5113-46 Revision No:
3A Date:
3-7-91 NOTE 3
WRV-721
-723
-725
-727 Code Relief These valves are located in the essential service water supply lines to the emergency diesel generators air after coolers.
These three-way valves regulate water flow to maintain the temperature at which the after cooler air discharge thermostatic controller has been set.
Water flow is regulated by passing a portion of the flow through the air coolers and bypassing the excess flow around the air after coolers.
Code relief is being requested from the testing requirements since (1),
these valves function only as regulating valves and not open/closed valves (2), these valves are demonstrated operable during diesel generator testing (diesel generators are tested per Technical Specification 4.8.1.1.2);
and (3), these valves are demonstrated operable during diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs performed each refueling outage.
The valves will be "fail-safe" tested using their control scheme that will remove air from the valve operators causing them to direct all ESW flow to the air after coolers.
This proposed test for each valve will be performed at refueling frequency.
The valves cannot be stroke timed because they are thermostatic valves whose position is controlled by process fluid temperature.
There is no external control available.
NOTE 4:
ESW-101E
-101W Comment Testing of the backflow checking function cannot be performed if the opposite unit's ESW System is not available.
Should the opposite unit's ESW System not be available when testing of this valve's backflow checking function is required, the testing will be deferred until-the opposite unit's ESW System is returned to service, and will be performed as soon as practical thereafter.
Page 21 of 81
SYSTEM:
ESSENTIAL SERVICE WATER DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNHARY SHEET - UNII'1 FLOW DIAGRAN:
1-5113-46 4/2/91 16:39 Number VALVE Revision Type Size Actuator PAID Type Coordinates VALVE POSITION Power Safety Operation Function ASNE SECTION XI Code Active/
Category Primary Test Test Test Relief Request(s)
Class Passive Required Performed Node 01-ESW-101-E 01-ESW-101-W 01-ESM-109 01-ESW-111 01-ES'W-112 01-ESM-113 01-ESW-114 01-ESM-115 01-ESM-168-N 01-ESW-168-S 01-ESM-169-N 01-ESW-169-S 01-ESW-170-H 01-ESM-170-S 01-ESM-171-H 01-ESW-171-S 01-ES'W-243 01-SV-14-E 01-SV W 01-SV-15-E 01-SV-15-M 01-SV-16-ABi 01-SV CD 3A CK 20.00 SA N/8 3A 3A CK 6.00 SA 8/6 CK 6.00 SA B/6 BF 6.00 N
BF 3.00 M
BF 3.00 N
BF 3.00 N
BF 3.00 N
BF 3.00 H
BF 3.00 H
BF 3.00 H
BF 3.00 N
BF 4.00 N
REL 1.00 SA REL 1.00 SA REL 0.75 SA REL 0.75 SA REL 1.00 SA REL 1.00 SA E/6 G/1 G/1 F/1 F/1 F/1 F/1 D/6 A/1 C/1 E/4 G/4 C/8 C/8 3A CK 20.00 SA H/8 3
BF 4.00 N
8/5 3A CK 6.00 SA C/6 3A CK 6.00 SA C/6 0/C 0/C 0/C 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A CF-1 CF-1 EF-1 CF-1 CF-1 CF-1 CF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 CF-1 CF-1
.EF-2 CF-1 CF-1 CF-1 CF-1 EF-2 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-2 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 P
NO, NOTE 4 P
NO, NOTE 4 C
NO, CSJ 2
P
- YES, NOTE 1
P
- YES, NOTE 1
P
- YES, NOTE 1
P
- YES, NOTE 1
C HO, CSJ 2
P NO P
HO P
NO P
NO P
NO P
NO P
NO P
NO C
HO, CSJ 2
R NO R
HO R
HO R
NO R
HO R
NO
SYSTEM:
ESSENTIAL SERVICE WATER DONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT 01 FLOW D IAGRAM:
1-5113-46 4/2/91 16:30 VALVE VALVE POSITION ASME SECTION XI Number Revision Type Size Actuator P&ID Type Coordinates Power Safety Operation Function Code Active/
Category Class Passive Primary Test Required Test Performed Test Relief Request(s)
Mode 01-WMO-701 BF 20.00 MO N/8 C
0 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
NO HO P
NO 01-WMO-702 OI -WMO-705 OI-WM0.707 01-WMO-713 01-WMO-717 01-WM0-.721 01-WMO-723 01-WMO-725 OI-WM0.727 01-WMO.733 BF 20.00 MO BF 20.00 MO BF 20.00 MO BF 12.00 MO 3
BF 12.00 MO BF 6.00 MO BF 6.00 MO BF 6.00 MO BF 6.00 MO BF 16.00 MO H/8 G/6 G/7 A/5 8/5 D/6 C/6 8/6 8/6 C/3 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
NO HO P
NO P
NO NO P
NO P
NO HO P
NO P
NO NO P
NO P
NO NO P
NO P
NO HO P
NO P
NO HO P
NO P
HO HO P
NO P
NO HO P
NO P
NO NO P
HO
SYSTEH:
ESSENTIAL SERVICE WATER DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUNHARY SHEET - UNIT 01 FLOW 0 IAGRAN:
1-5113-46 4/2/91 16:36 Hebe r VALVE Revision Type Size Actuator P810 Type Coordinates VALVE POSITION Power Safety Operation Function Code Active/
Category Class Passive ASNE SECTION XI Primary Test Test Test Relief Request(s)
Required Performed Node 01-WNO-737 BF 16.00 NO E/3 0/C 0
3 A
EF-'1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO HO 01-WHO-744 OI-WNO-753 01-WHO-754 01-WRV-721 01-WRV-723 01-WRV-725 01-MRV-727 BF 4.00 NO BF 6.00 NO BF 4.00 NO 3M 4.00 A
3M 4.00 A
3M 4.00 A
3'W 4.00 A
0/6 D/6 0/5 D/8 B/8 D/8 B/8 3
A 3
A 3
A 3
A 3
A 3
A 3
A EF-1 EF-5 EI'-XXX EF-1 EF.5 EI'-XXX EF-1 EF-5 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NOTE 3 EF-8 NOTE 3 NOTE 3 EF-8 NO'IE 3 NOTE 3 EF-8 NOTE 3 NOTE 3 EF-8 NOTE 3 NO NO HO HO HO NO HO HO NO
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, HOTE 3
- YES, HOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
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DONALD C.
COOK NUCLEAR P 2ND TEN YEAR INSPECTION INTERVAL OF VALVE TEST PROGRAM FOR UNIT 2 LIST OF DRAWINGS Revision No:
3A Date:
3-7-91 Figure 2
NO.
SYSTEM FLOW DIAGRAM NO.
REVISION Main Steam Steam Generating System Feedwater Feedwater (Auxiliary)
Essential Service Water Non-Essential Service Water Station Drainage Containment Reactor Coolant Reactor Coolant CVCS-Reactor Letdown
& Charging 2-5105B 2-5105D 2-5106 2-5106A 2-5113 2-5114A 2-5124 2-5128 2-5128A 2-5129 2-5129A 42 2
34 41 27 20 19 34 32 20 Component Cooling Component Cooling Component Cooling Nuclear Sampling Nuclear Sampling Post Accident Sampling-Containment Hydrogen 2-5135 2-5135A 2-5135B 2-5141 2-514 1A 2-5141D 34 30 14 27 30 Page 9 of 81
DONALD C.
COOK NUCLEAR VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5113-41 Revision No:
3A Date:
3-7-91 NOTE 1 ESW-141
-142
-143
-144 Code Relief These check valves open to provide cooling water flow to various Emergency Diesel Generator loads.
In addition, these valves close to prevent back flow into the opposite ESW train header.
The open safety function will be tested'n accordance with IWV-3520.
The closed safety function cannot be tested in accordance with IWV-3520 for the following reasons:
There are no external position indicators associated with the valves, and no instrumentation or taps available at the valve to determine positive closure.
In order to determine valve
- closure, an entire ESW header and safety train, including both Emergency Diesel Generators, must be removed from service.
These valves cannot be tested at cold shutdown frequency since, with fuel
- loaded, the ESW is at its highest load demand (RHR operating) at this time and cannot be removed from service.
The closed safety function of these valves shall be verified by disassembly at refueling frequency.
NOTE 2:
ESW-145
-240
-243 Cold Shutdown Justification These valves are normally closed and are required to be open when the condensate storage tank is exhausted.
Exercising the valves could cause lake water contamination of the steam generators.
Lake water chemistry can potentially impact steam generator tube integrity.
Therefore, the valves will be full stroke tested at a cold shutdown frequency.
Since the valves are manual, stroke timing is not required.
Page 20 of 81
l II
DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5113-41 Revision No:
3A Date:
3-7-91 NOTE 3:
WRV-722
-724
-726
-728 Code Relief These valves are located in the essential service water supply lines to the emergency diesel generators air after coolers.
These three-way valves regulate water flow to maintain the temperature at which the after cooler air discharge thermostatic controller has been set.
Water flow is regulated by passing a portion of the flow through the air coolers and bypassing the excess flow around the air after coolers.
Code relief is being requested from the testing requirements since (1),
these valves function only as regulating valves and not open/closed valves (2), these valves are demonstrated operable during diesel generator testing (diesel generators are tested per Technical Specification 4.8.1.1.2);
and (3), these valves are demonstrated operable during diesel generator 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> runs performed each refueling outage.
The valves will be "fail-safe" tested using their control scheme that will remove air from the valve operators causing them to direct all ESW flow to the air after coolers.
This proposed test for each valve will be performed at refueling frequency.
The valves cannot be stroke timed because they are thermostatic valves whose position is controlled by process fluid temperature.
There is no external control available.
NOTE 4 ESW-102E
-102W Comment Testing of the backflow checking function cannot be performed if the opposite unit's ESW System is not available.
Should the opposite unit's ESW System not be available when testing of this valve's backflow checking function is required, the testing will be deferred until the opposite unit's ESW System is returned to service, and will be performed as soon as practical thereafter.
Page 21 of 81
SYSTEM:
ESSENI'IAL SERVICE WATER DONALD C.
COOK NUCLEAR PLAN'I SECOND TEN YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT 02 FLOW DIAGRAM:
2-51'l3-41 4/2/91 16:35 Nunber VALVE Revision Type Size Actuator PAID Type Coordinates VALVE POSITION Power Safety Operation Function Code Active/
Category Class Passive ASME SECTION XI Primary Test Test Test Relief Request(s)
Required Performed Mode 02-ESW-102-2E 02-ESW-102-2W 02-ESW-141 02-ESW-142 02-ESW-143 02-ESM-144 02-ESW-145 02-ESW-168-N 02-ESW-168-S 02-ESW-169-N 02-EQI-169-S 02-ESM-170-N 02-ESW-170-S 02-ESW-171-H 02-EQI-171-S 02-ESM-240 02-ESW-243 02-SV-14-2E 02-SV-14-2W 02-SV-15-2E 02-SV-15-2W 02-SV-16-AB 02-SV-16-CO 3A 3A 3A 3A 3A 3A CK 20.00 SA CK 20.00 SA CK 6.00 SA CK 6.00 SA CK 6.00 SA CK 6.00 SA BF 4.00 M
BF 3.00 M
BF 3.00 M
BF 3.00 M
BF 3.00 M
BF 3.00 M
BF 3 00 M
BF 3.00 M
BF 3 00 M
BF 6.00 M
BF 4 00 M
REL 1.00 SA REL 1.00 SA REL 0.75 SA REL 0.75 SA REL 1.00 SA REL 1.00 SA H/8 H/8 K/6 L/6 M/6 M/6 J/6 H/1 G/1 G/1 F/1 F/1 F/1 F/1 M/5 J/7 M/'I G/3 J/4 L/8 L/8 C
0/C 0/C 0/C 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
.A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 CF-1 CF-1 CF-1 CF-1 CF-1 CF-1 EF-2 EF-'I EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-1 EF-2 EF-2 TF-1 TF-1 TF-1 TF-1 TF-1 TF-1 P
HO, NOTE 4 P
HO, NOTE 4 P
- YES, NOTE 1
P
- YES, NOTE 1
P
- YES, NOTE 1
P
- YES, NOTE 1
C HO, CSJ 2
P HO P
NO P
HO P
NO P
NO P
HO P
HO P
HO C
NO, CSJ2 C
HO, CSJ2 R
HO=
R NO R
NO R
HO R
NO R
NO
SYSTEM:
ESSENTIAL SERVICE WATER DONALD C.
COOK NUCLEAR PLANT SECOND TEH YEAR INTERVAL VALVE
SUMMARY
SHEET - UNIT. 02 FLOW DIAGRAM:
2-5113-41 4/2/91 16:35 VALVE VALVE POSITION ASME SECTION XI Revision Type Size Actuator PAID Type Coordinates Power Safety Operation Function Code Active/
Category Class Passive Primary Test Required Test Performed Test Mode Relief Request(s) 02-WMO-703-2E 3
BF 20.00 MO H/8 C
0 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX NO NO HO 02-WM0.704-2W 3
02-WMO-706 02-WMO-708 02-WMO-714 02-WMO-718 02-WMO-722 02-WMO-724 02-WMO-726 02-WMO-728 02-WMO-734 BF 20.00 MO BF 20.00 MO BF 20.00 MO BF 12.00 MO BF 12.00 MO BF 6.00 MO BF 6.00 MO BF 6.00 MO BF 6.00 MO BF 16.00 MO H/8 G/8 G/6 M/5 H/5 M/6 M/6 K/6 L/6 H/3 0/C 0/C 0/C 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX P
P HO NO NO HO HO NO HO HO HO HO HO HO NO HO HO HO NO NO HO NO HO HO HO NO HO NO HO HO NO NO
SYSTEH:
ESSENTIAL SERVICE WATER OOHALO C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUHHARY SHEET - UNIT 02 FLOW DIAGRAM:
2-5113-41 4/2/91 16:35 Nmher VALVE Revision Type Size Actuator PSIO Type Coordinates VALVE POSITION Power Safety Operation Function ASHE SECTION XI Code Active/
Category Primary Test Test Test Relief Request(s)
Class Passive Required Performed Hode 02-WMO-738 BF 16.00 HO K/3 0/C 0
3 A
EF-1 EF-5 ET-XXX EF-1 P
EF-5 ET-XXX P
HO HO HO 02-WHO-744 02-WMO-753 02-WMO-754 02-IIRV-722-CO 3
02-WRV-724-CO 3
02-WRV-726-AB 3
02-WRV-728-AB 3
BF 4.00 MO BF 6.00 MO BF 4.00 HO 3W 4.00 A
3W 4.00 A
3W 4.00 A
3II 4.00 A
J/6 H/5 K/6 K/8 M/8 K/8 H/8 3
A 3
A 3
A 3
A 3
A 3
A 3
A EF-1 EF-5 ET-XXX EF-1 EF-5 ET-XXX EF-1 EF.S ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 EF-7 ET-XXX EF-1 P
EF-5 ET-XXX P
EF-1 P
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NOTE 3 NOTE 3 P
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- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
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- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
- YES, NOTE 3
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ATTACHMENT 2 FEBRUARY 16, 1990 SUBMITTAL INFORMATION
'~a DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5143-36 Revision No:
3 Date:
2-5-90 NOTE 5:
SI-166-1 throu h 4
Code Relief These check valves function to prevent backflow from the RCS into the accumulators during normal operation.
These valves function to supply flow from the accumulators to the RCS during an accident condition.
These valves cannot be exercised during power operation because the accumulators do not have sufficient head to overcome RCS pressure.
These valve's cannot be exercised during cold shutdown because this would result in a possible low temperature overpressurization of the RCS; Full stroke testing during refueling outages is not possible because of the resulting water surge into the reactor and the potential for high airborne radiation contamination.
These valves will be part stroke exercised at refueling frequency.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of four) per GL-89-04, Attachment 1, Item g2, at re'fueling frequency.
NOTE 6:
SI-161 Ll L2 L3 L4 Code Relief These check valves are located in the supply lines from the Residual Heat Removal and Safety Injection Pumps to.the RCS cold legs (loop 1 through 4).
These valves cannot be exercised during power operation because the RHR pumps and SI pumps do not develop sufficient head to overcome RCS pressure.
Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow instrumentation is not available downstream of the flow split.
These valves will be part stroke exercised at cold shutdown frequency and full stroke will be locally verified using portable instrumentation at refueling frequency.
Page 44 of 81
DONALD C.
COOK NUCLEAR PL VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
1-5143-36 Revision No:
3 Date:
2-5-90 NOTE 10 NOTE 11 SI-152 N
S Code Relief These check valves function to provide Safety-Injection pump discharge to either the hot or cold legs.
These valves cannot be exercised during power. operation because the SI pumps do not develop sufficient pressure to overcome RCS pressure.
These valves cannot be exercised during cold shutdown because the safety injection pumps are required to be inoperable by Technical Specification Section 3.5.3, to protect against low temperature overpressurization of the reactor vessel.
Also, during cold shutdown, there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke.
These valves will be full stroke exercised at refueling frequency.
SI-158 Ll L2 L3 L4 Code Relief Check valves SI-158 are located in the supply lines from the Residual Heat Removal and Safety Injection Pumps to the RCS hot legs (loop 1 through 4).
These valves cannot be exercised during power operation because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.
Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow instrumentation is not available downstream of the flow split.
These valves will be part stroke exercised at cold shutdown frequency.
Full stroke will be verified using portable instrumentation at refueling frequency.
Page
.46 of 81
SYSTEM NAHE:
EMERGENCY CORE COOLING - RHR DONALD C.
COOK tIUCLEAI PLANT SECOtlD TEN YEAR ItITERVAL VALVE
SUMMARY
SHEET - UtlIT 1 FLOW DIAGRAM:
I-5163-36 RUN DATE AND TIME:
15FE890:16:07 VALVE I VALVE POSITION I
I I
ASHE SECTION XI NUMDER REV TYPE SIZE ACT F 0 I
POIIER SAFETY ICD A/P CAT PRIM TEST TEST TEST RELIEF REQUESTIS
)
TYPE COORO I OPER PORCT ICL REQUIRED PERFORMED HODE 1RH108W 3
CK 8
SA N/9 C
0 2
A C
CF-1 CF-3 C
1-RH-133 3
CK 8
SA C/5 C
1 P
AC SLT-1 SLT-1 R
NOP IIOTE 1 I-RH-134 3
CK 8
SA C/5 C
1 P
AC SLT-1 SLT-1 R
NOP tlOTE 1
I-SI-168 3
CK 12 SA G/7 C
0 2
A C
CF1 CF-3 YES, tlOI'E 8 1-SI-151-E 3
CK 8
SA D/7 C
0 2
A AC CF1 CF2 C
SLT-1 SLT-1 R
tlOP NOTE 1
1-SI-151-W 3
CK 8
SA D/7 C
2 A
CF-2 C
SLT-1 SLT-1 R
NOR NOTE 1
1-SI-152-N 3
CK SA D/8 C
0 2
SI.T-l CF-2 SLT-1 R
YESO NOTE 10 R
NOP tl01E 1
1-SI-152-S 3
CK SA 0/7 C
0 2
A AC CF-1 CF-2 SLT-1 SLT-1 R
YFSP IIOTE 10 R
NOI NOTE 1 1-SI-158-Ll 3
CK 6
SA 8/8 C
0 1
A AC CF-1 SLT-1 Cf-2 SLT-1 YES E tlOTE 1 1 R
NOP N01E 1
1-SI-158-L2 3
CK 6
SA 8/7 C
0 1
A AC CF-1 SLT-1 CF-2 YES, tlOTE ll SLT-1 R
NOJ NOTE 1
~
~
)
SYSTEtt NANEt Et1ERGENCY CORE COOLlttG - RHR DONALD C.
COOK NUCLEAI! PLANT SECOND TEN YEAR INTERVAL VALVE SUtttIARY SIIEET - UNIT 1 FLOH DIAGRAH:
I-5143-36 RUN DATE AND TINE:
15FEB9D:16t07 VALVE I VALVE POSITION I
I ASltE SECTION XI NUttDER REV TYPE SIZE ACT F.D.
I POttER SAFETY ICD A/P CAT PRIH TEST TEST TEST RELIEF REQUEST(S)
TYPE COORDI OPER FUHCT ICL REQUIRFD PERFORttED ltODE 1-SI-150-L3 3
CK 6
SA B/7 C
0 1
HOTE ll SLT-1 SLT-1 R
HO> ttOTE 1 I-SI-158-L0 3
CK 6
SA B/7 C
0 1
A AC CF-1 SLT-1 CF-2 YESy NOTE ll SLT-1 R
HO1 NOTE 1 1-SI-161-Ll 3
CK 6
SA 8/6 C
0 1
A AC CF-1 CF-2 SLT-1 SLT-1 YESp ttOTE 6 NO> ttOTE 1 1-SI-161-L2 3
CK 6
SA B/5 C
0 1
A AC CF-1 CF-2 YES)
NOTE 6 SLT-1 SLT-1 R
HOp NOTE 1
1-SI-161-L3 3
CK 6
SA D/5 C
0 1
A AC CF-1 SLT-1 CF-2 SLT-1 YES> NOTE 6 R
ttOp ttOTE 1 1 SI 161-Lr>
3 CK 6
SA D/6 C
0 1
A AC CF-1 CF-2 YES>
NOTE 6 SLT-1 SLT-1 R
t<0 p NOTE 1
1-SI-166-1 3
CK 10
~
=
I
~
SA C/0 C
0 1
A AC CF1 CF-2 R
YES p tJOTE 5 SLT-1 SLT-1 R
NO>
NOTE 1 1-SI-156-2 3
CK 10 SA C/4 C
0 1
A AC CF-1 SLT-1 CF-2 R
YES>
NOTE 5 SLT-1
-R ttOp NOTE 1
1-SI-166-3 3
CK 10 SA C/0 C
0 1
A AC CF1 SLT-1 CF-2 SLT-1
'R R
YES'OTE 5 NO>
NOTE 1
DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5143-35 Revision No:
3 Date:
2-5-90 NOTE 5 SI-166-1 throu h 4
Code Relief These check valves function to prevent backflow from the RCS into the accumulators during normal operation.
These valves function to supply flow from the accumulators to the RCS during an accident condition.
These valves cannot be exercised during power operation because the accumulators do not have sufficient head to overcome RCS pressure.
NOTE 6
These valves cannot be exercised during cold shutdown because this would result in a possible low temperature overpressurization of the RCS.
Full stroke testing during refueling outages is not possible because of the resulting water surge into the reactor and the potential for high airborne radiation contamination.
These valves will be part stroke exercised at refueling frequency.
The valves will be disassembled, manually full stroke exercised and visually examined on a sampling basis (one of four) per GL-89-04, Attachment 1, Item N2, at refueling frequency.
SI-161 Ll L2 L3 L4 Code Relief These check valves are located in the supply lines from the Residual Heat'emoval and Safety Injection Pumps to the RCS cold legs (loop 1 through 4).
These valves cannot be.exercised during power operation because the RHR pumps and SI pumps do not develop sufficient head to overcome RCS pressure.
Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow instrumentation is not available downstream of the flow split.
These valves will be part stroke exercised at cold shutdown frequency and full stroke will be locally verified using portable instrumentation at, refueling frequency.
Page 44 of 81
C,
- o
DONALD C.
COOK NUCLEAR P VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No:
2-5143-29 Revision No:
3 Date:
2-5-90 NOTE 10:
NOTE 11 SI-152 N
S Code Relief These check valves function to provide Safety Injection pump discharge to either the hot or cold legs.
These valves cannot be exercised during power operation because the SI pumps do not develop sufficient pressure to overcome RCS pressure.
These valves cannot be exercised during cold shutdown because the safety injection pumps are required to be inoperable by Technical Specification Section 3.5.3, to protect against low temperature overpressurization of the reactor vessel.
Also, during cold shutdown, there may not be sufficient volume in the RCS to accommodate the amount of water needed to full stroke.
These valves will be full stroke exercised at refueling frequency.
SI-158 Ll L2 L3 L4 Code Relief Check valves SI-158 are located in the supply lines from the Residual Heat Removal and Safety Injection Pumps to the RCS hot legs (loop 1 through 4).
These valves cannot be exercised during power operation because the RHR and SI pumps do not develop sufficient head to overcome RCS pressure.
Full stroke of these valves (individually) cannot be verified at cold shutdown frequency because flow instrumentation is not available downstream of the flow split.
These valves will be part stroke exercised at cold shutdown frequency.
Full stroke will be verified using portable instrumentation at refueling frequency.
Page 46 of Sl
L
SYSTEM NAME:
EMERGENCY CORE COOLING - RIIR DONALD C.
COOK NUCLEAR PLANT SECOND TEN YEAR INTERVAL VALVE SUttHARY SHEET - UNIT 2 FLON DIAGRAM:
2-5163-35 RUN DATE AND TII4E:
15FEB90:16:ll VALVE I VALVE POSITION I
I I
ASHE SECTION XI NUHBER REV TYPE SIZE ACT F.D.
I POHER SAFETY ICD A/P CAT PRItl TEST TEST TEST RELIEF REQUEST(st TYPE COORDI OPER FUttCT ICL REQUIRED PERFORMED MODE 2-RH-108M 3
CK 8
SA N/9 C
2 A
C CF1 CF-3 C
NO CSJ 7
2-RH-133 CK 8
SA C/5 C
1 P
AC SLT-1 SLT-1 R
ttO y NOTE 1
2-RH-13%
CK 8
SA C/5 C
1 P
AC SLT-1 SLT-1 R
NO>
NOTE 1
~
2-SI-148 3
CK 12 SA G/7 C
2 A
C CF1 CF-3 YES> ttOTE 8 2-SI-151-E 3
CK 8
SA D/7 C
2 A
AC CF1 SLT-1 CF-2 SLT-1 C
NO> CSJ 9
R tt0> NOTE 1 2-SI-151-N 3
CK 8
SA D/7 C
0 2
A AC CF1 CF2 C
NO> CSJ 9
SLT-1 SLT-1 R
NO> ttOTE 1 2-SI-152-N 3
CK CI SA D/8 C
0 2
A AC CF-1 LT-1 CF-2 SLT-1 R
YES>
NOTE 10 R
ttOi NOTE 1 2-SI-152-S 3
CK SA D/7 C
0 2
A AC CF1 CF2 SLT-1 SLT-1 R
R YES'tOTE 10 NOp NOTE 1
2"SI-158-Ll 3
CK 6
SA 8/8 C
1 A
AC CF1 SLT-1 CF-2 YES ttOl'E ll SLT-1 R
NO~
NOTE 1 2-SI-158-L2 3
CK 6
SA 8/7 C
1 A
AC CF-1 SLT-1 CF-2 SLT-1 YES>
NOTE 11 NOi NOTE 1
c
SYSTEH HAtfEt EHERGEHCY CORE COOLING - RRR DONALD C.
COOK NUCLEAR PLANT SECOHD. TEN YEAR INTERVAL VALVE SUl41ARY SllEET - UNIT 2 FLON DIAGRAH:
2-5163-35 RUN DATE AHD TINE:
15FEB9Dt16tll VALVE I VALVE POSITION I
l I
ASttE SECTION XI NUttBER REV TYPE SIZE ACT F.D.
I PONER SAFETY ICD A/P CAT PRIl4 TEST TEST TEST RELIEF RMUEST< S)
TYPE COORD 1 OPER FUHCT ICL REQUIRED PERFORHED NODE 2-SI-158-L3 3
CK 6
SA 8/7 C
1 A
CF-2 SLT-1 SLT-1 YESp NOTE -ll R
NOp ttOTE 1 2-SI"158-L4 3
CK 6
SA 8/7 C
0 1
A AC CI -1 SLT-I CF-2 YESp ttOTE ll SLT-1 R
HOp NOTE 1 2-SI-161-Ll 3
CK 6
SA 8/6 C
0 1
A AC CF1 SLT-1 CF-2 SLT"1 YES) NOTE 6 R
NOp NOTE 1 2-SI-161-L2 3
CK 6
SA 8/5 C
0 1
A AC CF-1 SLT-1 CF-2 SLT-1 YESp NOTE 6 R
NOp NOTE 1 2-.SI-161-L3 3
CK 6
SA 8/5 C
0 1
A AC CF-1 SLT-1 CF-2 SLT-1 YESp NOTE 6 R
NOp HOTE 1 2-SI-161-LI 3
CK 6
SA 8/6 C
0 1
A AC CF1 SLT"1 CF-2 SLT-1 YESp NOTE 6 NOp NOTE 1 2-SI-166-1 3
CK 10 SA C/0 C
0 1
A AC CF-1 SLT-1 CF-2 SLT-1 R
YESp NOTE 5 R
NOp NOTE 1 2-SI-166-2 3
CK 10 SA C/0 C
0 1
A AC CF1 SLT-1 CF-2 SLT-1 R
YESp NOTE 5 R
NO, NOTE 1 2-SI"166"3 3
CK 10 SA C/4p C
0 1
A AC CF-1 SLT-1 CF-2 SLT-1 R
YESp NOTE 5 R
NOp NOTE 1
~C I
l
~ I