ML17331A891

Forwards Summary of Revs to ISI Valve Test Program Made to Incorporate Results of Recently Conducted Program Review

ML17331A891
Person / Time
Site:	Cook
Issue date:	06/28/1993
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
AEP:NRC:0969V, AEP:NRC:969V, NUDOCS 9307020178
Download: ML17331A891 (39)

Text

ACCEI ERAT DOCUMENT DIST VTION SYSTEM REGULAT INFORMATION DISTRIBUTIO STEM (RIDS)

ACCESSION NBR:9307020178 DOC.DATE: 93/06/28 NOTARIZED: NO DOCKET g FACIL:50-315 Donald C. Cook Nuclear Power Plant, Unit 1, Indiana M 05000315 50-316 Donald C. Cook Nuclear Power Plant, Unit 2, Indiana M 05000316 AUTH. NAME AUTHOR AFFILIATION FITZPATRICK,E. Indiana Michigan Power Co. (formerly Indiana & Michigan Ele RECIP.NAME RECIPIENT AFFILIATION MURLEY,T.E. Office of Nuclear Reactor Regulation, Director (Post 870411 I

SUBJECT:

Forwards summary of revs to ISI valve test program made to incorporate results of recently conducted program review.

DISTRIBUTION CODE: A047D TITLE: OR COPIES RECEIVED:LTR Submittal: Inservice/Testing/Relief from

( ENCL J SIZE:

ASME Code NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 0 PD3-1 PD 1 1 DEAN,W 2 2 D INTERNAL: NRR/DE/EMEB 1 1 NUDOCS-ABSTRACT 1 1 D 1 0 OGC/HDS2 1 0 REG FILE 01 1 1 RES/DSIR/EIB 1 1 EXTERNAL: EGGG BROWN,B 1 1 EGEG RANSGME,C 1 1 NRC PDR 1 1 NSIC 1 1

'

R D

D.

NOTE TO,ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO EUMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 11 J

Indiana Iachlgan Power Company P.O. Box 16631 Columbus, OH 43216 AEP:NRC:0969V Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 ISI PROGRAM REVISIONS - REQUESTS FOR RELIEF U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Attn: Dr. T. E. Murley June 28, 1993

Reference:

Letter, L. B. Marsh (NRC) to E. E. Fitzpatrick (IMCo) "In Service Testing (IST) Program Relief Requests, D. C. Cook Nuclear Plant Units 1 and 2,"

dated February 19, 1993.

This letter transmits revisions to the Donald C. Cook Nuclear Plant Inservice Inspection (ISI) Valve Test Program that were made to incorporate the results of recently conducted program reviews.

A summary of the changes is given in Attachment A.

In some instances, it is not possible to comply with the requirements of ASME Section XI and regulatory relief, as allowed by 10 CFR 50.55 a(a)(3), is requested. This relief is required by the start of the Unit 1, 1994 refueling outage that is currently scheduled to begin February 5, 1994. Attachment B provides a listing of the valves for which regulatory relief is required together with those ISI program pages that provide the bases for the relief requests.

In addition to the relief requests for the valves which have been added to the program, permanent relief is requested for valves 1-ESW-111, -112, -113, -114 and 2-ESW-141, -142, -143, -144.

Temporary relief was granted in the reference pending a study of A l n.mr=

qpppopo17"8 930628 pDR ADOC<

0500031 5 PDR

Dr. T. E. Murley AEP:NRC:0969V the use of non-intrusive examinations for these valves. As noted in the attached relief requests, non-intrusive examinations are not considered to be feasible for these valves.

Attachment C to this letter contains the revised description of l

the ISI program for Units and 2.

Sincerely, Vice President gmd Attachments cc: A. A. Blind - Bridgman J. R. Padgett G. Charnoff NFEM Section Chief A. B. Davis - Region III NRC Resident Inspector - Bridgman

Dr. T. E. Murley AEP:NRC:0969V bc: S. J. Brewer J. B. Kingseed D. H. Malin M. L. Horvath - Bridgman J. B. Shinnock W. G. Smith, Jr.

B. A. Wetzel, NRC - Washington, D.C.

AEP:NRC:0969V DC-N-6015.1

1 Attachment A to AEP:NRC:0969V Summary of ISI Valve Test Program Changes

ITIN t

CHANGE ASHE Section XI Valve Inservice Testing Pr Revision 4 Sumery of Chenges - Hay 7, 1993 SUBHI TTAL REASON 1-CA-181H DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-2895

'I-CA-18'IS DELETED AEP:HRC:0969V DESIGN CHANGES PER RFC-2895 1-CA-7042 ADDED AEP:NRC:0969V NEM EQUIPHENT PER HH-417 1-CA-7043 ADDED AEP:NRC:0969V NEM EQUIPHENT PER HH-417 1-CCM-176-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED CCNHENT REGARDING TESTING MITH ALTERHATE PUHP OOS 1- CCM-176-M REVI SED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED CONHENT REGARDING TESTING MITH ALTERNATE PUHP OOS 1-CCM-224-1 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUHCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1-CCM.224-2 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1-CCM.224-3 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUHCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1-CCM-224-4 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED)

I-CCM.225-1 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1-CCM-225-2 ADDED AEP:NRC:0969V DETERHIHED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 1-CCM-225-3 ADDED AEP:NRC:0969V DETERHINED TO NAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1.CCM-225-4 ADDED AEP:NRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 1-CS-295 ADDED AEP:NRC:0969V ADDED TO IST PROGRAH PER MESTINGHOUSE NUCLEAR SAFETY ADVISORY LETTER, 0/C SAFETY FUNCTION (RELIEF REQUESTED FOR CLOSED TESTIHG) 1- CS-415-1 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED COHHENT REGARDING TESTING MITH ALTERNATE PUHP OOS 1-CS-415-2 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTIOH ADDED AEP:NRC:0969V ADDED COHHENT REGARDING TESTING MITH ALTERNATE PUHP OOS 1-CTS-127-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTION, REVISED RELIEF REQUEST 1-CTS-127-M REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTIOH, REVISED RELIEF REQUEST 1.CTS-131-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 1-CTS-131-M REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 1-DF-108C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTION

SME Section XI Valve lnservice Testing Pr Revision 4 Sunnnry of Changes - May 7, 1993 ITEM CHANGE SUBMITTAL REASON 1-DF-108C ADDED AEP:NRC:0969V ADDED COMMENT REGARDING TESTING UITH ALTERHATE PUMP OOS 1.DF-109C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED COMMENT REGARDING TESTING WITH ALTERNATE PUHP OOS 1-DF-114A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V CORRECTED TAG FROM 1-DF-114C AND FLSI DIAGRAM REFERENCE ADDED ADDED COMMENT REGARDIHG TESTING llITH ALTERNATE PUMP OOS 1-DF-115A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V CORRECTED TAG FROM 1-DF-115C AND FLSI DIAGRAH REFERENCE ADDED ADDED COMMENT REGARDING TEST!NG MITH ALTERNATE PUMP OOS 1.DG-127A REVISED AEP:NRC!0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V ADDED RELIEF REQUEST 1-DG.127C REVISED AEP:NRC:0968U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V ADDED RELIEF REQUEST 1.DG-129A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:HRC:0969V ADDED RELIEF REQUEST 1-DG-129C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V, ADDED RELIEF REQUEST 1-DG-151A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMHENT REVISED AEP:NRC:0969V REVISES COMMENT 1-DG 'I51C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMMENT REVISED AEP:HRC:0969V REVISED COMMENT 1-DG. 153A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTION AND COMMENT REVISED AEP:NRC:0969V REVISED COMMENT 1-DG-153C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMMENT REVISED AEP:NRC:0969V REVISED COMMENT 1-DL-115A REVISED AEP:NRC:0969V ADDED COMMENT DOCUMENTING NO CLOSED SAFETY FUHCTION 1-DL-115C REVISEO AEP:NRC:0969V ADDED COMMENT DOCUMENTING NO CLOSED SAFETY FUNCTION 1.ESU-101E REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND COMMENT 1-ESLI-101'EVISED AEP:HRC:0969S ADDED CLOSED SAFETY FUNCTION AND COMMENT 1-ESW.111 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:NRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF

1. ESM-112 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:NRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF 1-ES'N-113 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:NRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF 1 ES'W-114 REVI SED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:HRC:0969V REVISED RELIEF REQUEST TO REQUEST PERHANEHT RELIEF

SHE Section XI Valve lnservice Testing Pr Revision 4 Sunnnry of Changes - Hay 7, 1993 ITEH CHANGE SUBHI TTAL REASON 1-ICH-129 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHEHTS IH COHMENT 1-ICH-250 REVISED AEP:NRC:0969V COLD SHUTDOWN JUSTIFICATION REVISED TO COHHENT PER RFC-3050 DESIGN CHANGES 1 I CH-251 REVISED AEP:NRC:0969V COLD SHUTDOLN JUSTIFICATION REVISED TO COHHENT PER RFC-3050 DESIGN CHANGES 1- IRV-251 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 1-IRV-252 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 1-IRV-255 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 1-HRV 220 REVISED AEP:HRC:0969V CORRECTED aTEST HODEa COLUMN FROM P TO C 1-HRV-230 REVISED AEP:NRC:0969V CORRECTED aTEST HOOE" COLUMN FROM P TO C 1-PA-342 REVISION AEP:NRC:0969V TYPOGRAPHICAL ERROR, TAG INCORRECT IH ATTACHMENT A 1-PCR-40 REVISED AEP:NRC:0969V CORRECTED "TEST.PERFORHED" COLUHH FROM ET-XX TO ET-XXX 1-QCR-300 REVISED AEP:HRC:0969V CORRECTED TYPO IH TABLE FOR TEST HODE FOR ET-XXX FROM aPu TP llCu 1-QCR-301 REVISED AEP:HRC:0969V CORRECTED TYPO IN TABLE FOR TEST HOOE FOR ET-XXX FROM llpll TO llCII 1-RH-133 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COHMEHT 1-RH-134 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COHMEHT 1-RH-'141 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 1-RH.142 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTIOH, REVISED RELIEF REQUEST 1-SF-152 REVISION AEP:NRC:0969V TYPOGRAPHICAL ERROR, TAG INCORRECT IH ATTACHMENT A 1 SF-154 REVISION AEP:NRC:0969V TYPOGRAPHICAL ERROR, TAG INCORRECT IN ATTACHMENT A 1-SI-101 REVISED AEP:NRC:0969V CLOSED SAFETY FUNCTIOH ADDED, HEM RELIEF REQUEST MR I TTEN 1-Sl-110-H REVISED AEP:HRC:0969V CLOSED SAFETY FUNCTION ADDED, RELIEF REQUEST REVISED 1-S1-110 S REVISED AEP:NRC:0969V CLOSED SAFETY FUNCTION ADDED, RELIEF REQUEST REVISED 1-S1-126 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 1-SI-142.L1 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 1-SI-142-L2 REVISED AEP:HRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 1 SI-142 L3 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGH CHANGES

SME Section Xt Vetve lnservlce Testing Pr Revlslon 4 Swmnry of Changes - May 7, 1993 ITEH CHANGE SUBMITTAL REASON 1 SI-142-L4 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 1-SI-151 E REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1-SI-151-U REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1-Sl-152-N REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 1-S1-152-S REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1- S I -158- L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHENTS IH COMMENT 1-SI.158-L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHENTS IN COMMENT 1-SI-158.L3 REVISED AEP:NRC:0969S CLARIFICATlON OF TESTING REQUIREHENTS lk COMMENT 1-Sl-158-L4 REVISEO AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMHEHT 1-Sl-161-L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMHENT 1-SI-161-L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1-Sl-161-L3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHENTS IN COMHEHT 1.SI-161-L4 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHEHTS IN COMMENT 1-SI-166-1 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 1-SI-166-2 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1-SI.166-3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 1-SI-166-4 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 1-Sl-170-L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COHMENT 1-SI-170.L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHEHTS IN COMHENT 1-SI-170-L3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 1-SI-170-L4 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 1-SI-185 REVISED AEP:HRC:0969V CLOSED SAFETY FUNCTION ADDED, RELIEF REQUEST REVISED 1-SV-122-3 REVISED AEP:NRC:0969V TYPOGRAPHICAL ERROR, CHANGED TAG FROM SV-122-25B 1-SV-'122-4 REVISED AEP:NRC:0969V TYPOGRAPHICAL ERROR, CHANGED TAG FROM SV-122-728 1/2 5113 REVISED AEP:NRC:0969S REVISION HUMBER UPDATED 12-CCM-170 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V CHANGED MOTE NUMBER FROM 2 TO 3 FOR CONSISTENCY U/ UNIT 2

2-CA-181M DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC.2895

SHE Section XI Vntve Inservice Testing Pr Revision 4 Swmnry of Chonges - May 7, 1993 ITEM CHANGE SUBMITTAL REASON 2-CA-181S DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-2895 2-CA-7044 ADDED AEP:HRC:0969V HEll EQUIPMENT PER MM.417 2-CA-7045 ADDED AEP:NRC:0969V NEM EQUIPMENT PER MM-417 2-CCll-176-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED COMMENT REGARDING TESTING lllTH ALTERNATE PUMP OOS 2-CN-176-ll REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTION ADDED AEP:NRC:0969V ADDED COMMENT REGARDING TESTING lllTH ALTERNATE PUMP OOS 2-CCM-224-1 ADDED AEP:HRC:0969V DETERMINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 2-CCM-224-2 ADDED AEP:HRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 2- CCll-224-3 ADDED AEP:NRC:0969V DETERMINED TO HAVE A CLOSED SAFETY FUHCTIOH, ADDED TO PROGRAM (RELIEF REQUESTED) 2-C5l-224-4 ADDED AEP:NRC:0969V DETERMINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 2-CCM-225-1 ADDED AEP:HRC:0969V DETERHINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAH (RELIEF REQUESTED) 2-CCM-225-2 ADDED AEP:HRC:0969V DETERMINED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 2-CCM-225-3 ADDED AEP:NRC:0969V DETERMIHED TO HAVE A CLOSED SAFETY FUNCTION, ADDED TO PROGRAM (RELIEF REQUESTED) 2-CGI-225-4 ADDED AEP:HRC:0969V DETERMINED TO HAVE A CLOSED SAFETY FUNCTIONS ADDED TO PROGRAM (RELIEF REQUESTED) 2-CS-295 ADDED AEP:NRC:0969V ADDED TO IST PROGRAM PER MESTINGHOUSE NUCLEAR SAFETY ADVISORY LETTER, 0/C SAFETY FUNCTION (RELIEF REQUESTED FOR CLOSED TESTING) 2-CS-415-3 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUHCTIOH ADDED AEP:NRC:0969V ADDED COMMENT REGARDIHG TESTING MITH ALTERNATE PUMP OOS 2-CS-415-4 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:HRC:0969V ADDED COMMENT REGARDIHG TESTING MITH ALTERNATE PUMP OOS 2-CTS-127-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 2-CTS-127-iI REVISED AEP:HRC:0969U ADDED CLOSED SAFETY FUHCTION, REVISED RELIEF REQUEST 2-CTS-131-E REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 2-CTS-131-'N REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 2-DF-108A REVISED AEP:HRC:0969U ADDED CLOSED SAFETY FUHCTION ADDED AEP:HRC:0969V ADDED COMMENT REGARDING TESTING UITM ALTERNATE PUMP OOS

SME Section XI Valve lnservice Testing Pr Revision 4 Burry of Changes - May 7, 1993 ITEM CHANGE SUBHITTAL REASOH 2.DF-109A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:HRC:0969V ADDED COMMENT REGARDING TESTING WITH ALTERHATE PUMP OOS 2-DF-114C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION ADDED AEP:NRC:0969V ADDED COMMENT REGARDIHG TESTING WITH ALTERNATE PUMP OOS REVISED CORREC'TED TAG FROM 2-DF-114A AND FLOW DIAGRAM REFERENCE 2.DF.115C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V CORRECTED TAG FROM 2-DF-115A AND FLOW DIAGRAM REFERENCE ADDED ADDED COMMENT REGARDIHG TESTING WITH ALTERNATE PUHP OOS 2-DG-128A REVISED AEP:NRC:0969U ADDEC CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V ADDED RELIEF REQUEST 2-DG.128C REVISED AEP:HRC:0968U ADDED CLOSED SAFETY FUNCTION REVISED AEP:HRC:0969V ADDED RELIEF REQUEST 2-DG-130A REVISED AEP:HRC:0968U ADDED CLOSED SAFETY FUHCTIOH REVISED AEP:NRC:0969V ADDED RELIEF REQUEST 2-DG-130C REVISED AEP:HRC:0968U ADDED CLOSED SAFETY FUNCTION REVISED AEP:NRC:0969V ADDED RELIEF REQUEST

2. DG-152A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMMENT REVISED AEP:NRC:0969V REVISED COMMENT 2.DG-152C REVISED AEP:HRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMMENT REVISED AEP:HRC:0969V REVISED COMHEHT 2-DG" 154A REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AHD COMMENT REVISED AEP:HRC:0969V REVISED COMMENT 2-00-154C REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION AND COMMENT REVISED AEP:NRC:0969V REVISED COMMENT 2-DL-116A REVISED AEP:NRC:0969V ADDED COMMENT DOCUMENTING NO CLOSED SAFETY FUNCTION 2-DL-116C REVI SED AEP:NRC:0969V ADDED COMMENT DOCUMENTING NO CLOSED SAFETY FUNCTION 2-ECR-36 REVISED AEP:HRC:0969V CORRECTED TABLE ENTRY UNDER ET-XXX FROM "YES, CSJ 1a TO "HO, CSJ 1" 2.ES'W-102E REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND COMMENT 2.ESW-102W REVISED AEP:HRC:0969S ADDED CLOSED SAFETY FUNCTION AND COMMENT 2-ESW.141 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:NRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF

2. ESW-142 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUHCTIOH AND RELIEF REQUEST REVISED AEP:HRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF 2-ESW-'143 REVISED AEP:NRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:HRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF 2-ESW-144 REVISED AEP:HRC:0969S ADDED CLOSED SAFETY FUNCTION AND RELIEF REQUEST REVISED AEP:NRC:0969V REVISED RELIEF REQUEST TO REQUEST PERMANENT RELIEF

ITEM t

CHANGE ASME Section Xl Valve Inservice Testing P Revision 4 Smeary of Changes - May 7, 1993 SUBMITTAL REASOH

2. I CM-129 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2- I CM-250 REVISED AEP:NRC:0969V COLD SHUTDOW JUSTIFICATION REVISED TO COMMEHT PER RFC-3050 DESIGN CHANGES 2- I CM-251 REVISED AEP:NRC:0969V COLD SHUTDOWN JUSTIFICATION REVISED TO COMMENT PER RFC-3050 DESIGN CNANGES 2-IRV-251 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 2-IRV-252 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC-3050 2-IRV-255 DELETED AEP:HRC:0969V DESIGN CHANGES PER RFC-3050 2.RH-133 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-RH-134 REVISED AEP:NRC:0969S CLARIFICATIOH OF TESTING REQUIREMENTS IN COMMENT 2-RH-141 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 2-RH-142 REVISED AEP:NRC:0969U ADDED CLOSED SAFETY FUNCTION, REVISED RELIEF REQUEST 2-SI-101 REVISED AEP:NRC:0969V CLOSED SAFETY FUNCTION ADDED, NEM RELIEF REQUEST MRITTEH 2-SI-110-N REVISED AEP:NRC:0969V CLOSED SAFETY FUHCTION ADDED, RELIEF REQUEST REVISED 2-SI-IIO-S REVISED AEP:HRC:0969V CLOSED SAFETY FUHCTION ADDED, RELIEF REQUEST REVISED 2-$ 1.126 DELETED AEP:NRC:0969V DESIGN CHANGES PER RFC 3050 2-SI-142-L1 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 2-SI-142.L2 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 2-SI-142-L3 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 2-SI-142-L4 REVISED AEP:NRC:0969V RELIEF REQUEST REVISED TO REFLECT RFC-3050 DESIGN CHANGES 2-SI- 151-E REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREHENTS IH COMMENT 2-SI-151-W REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-152-N REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-152-S REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-158-L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 2-S I -158- L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTIHG REQUIREMENTS IN COMHENT 2-81-158- L3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMEHT

ITEM t

CHANGE ASME Section XI Valve Inservice Testing Pr Revision 4 Sumery of Changes . May 7, 1993 SUBMITTAL REASON 2-Sl-158-L4 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 2-Sl-161-L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-S1-161.L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-Sl-161-L3 REVISED AEP:NRC:0969S CLARIFICAT10H OF TESTING REQUIREMENTS IN COMMENT 2-SI-161-L4 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMEHT 2-SI-166-1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-166-2 REVISED AEP:HRC:0969S CLARIFICATIOH OF TESTING REQUIREMENTS IN COMMENT 2-SI-166-3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2.S I-166-4 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-170-L1 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-Sl-170-L2 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENI'S IN COMMENT 2-Sl-170-L3 REVISED AEP:NRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IH COMMENT 2-Sl-170-L4 REVISED AEP:HRC:0969S CLARIFICATION OF TESTING REQUIREMENTS IN COMMENT 2-SI-185 REVISED AEP:NRC:0969V CLOSED SAFETY FUNCTION ADDED, REL!EF REQUEST REVISED 2-SV-122-23 REVISED AEP:NRC:0969V TYPOGRAPHICAL ERROR, CHAHGED TAG FROM SV-122 2-SV-122-3 REVISED AEP:NRC:0969V TYPOGRAPHICAL ERROR, CHANGED TAG FROM SV-122-72B 2-SV-122-4 REVISED AEP:NRC:0969V TYPOGRAPHICAL ERROR, CHANGED TAG FROM SV-122-25B SLT-2 TEST REVISED DESCRIPTION AEP:HRC:0969V CLARIFICATION PER PLANT REQUEST SLT-2A TEST REVISED DESCRIPTIOH AEP:NRC:0969V CLARIFICATION PER PLANT REQUEST

Attachment B to AEP:NRC:0969V Relief Requests

Attachment B to AEP:NRC:0969V Page 1 Valves for Which Relief is Requested Unit 1 Unit 2 ESW-111, -112, -113, -114 ESW-141, -142, -143, -144 SI-185 SI-185 CS-295 CS-295 CCW-224-1, -2, -3, -4 CCW-224-1, -2, -3, -4 CCW-225-1, -2, -3, -4 CCW-225,-1, -2, -3, -4 SI-110N, -110S SI-110N, -110S SI-142 LI, L2, L3, L4 SI-142 LI, L2, L3, L4 SI-101 SI-101 DG-127A, -129A DG-128A, -130A DG-127C, -129C DG-128C, -130C

DONALD C COOK NUCLEAR PLANT VALVE TEST PROGRAM ~ I RELIEF REQUEST NOTES Flow Diagram No: 1-5113-~+4',

Revision No: 4 Date: 5-7-93 NOTE 1 NOTE 2: ESW-109 -115 -243 Cold Shutdown Justificatio : 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 85

t DONALD C- COOK NUCLEAR PLANT I i

VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5129-31 Revision No: 4 Date: 5-7-93 NOTE 9: RV-251 Code Relief : This air operated valve's used to regulate charging header flow to the reactor coolant system and seal water flow to the reactor coolant pump seals. The valve cannot be full-stroke exercised at power operation because RCP seal injection flow and would also upset pressurizer level.

it would interrupt the The valve will be part-stroke exercised during power operation and full-stroke exercised at a cold shutdown frequency. The valve cannot be stroke timed because there is no local or remote position indicator available and cycle times are directly proportional to "how fast" the operator can turn the control knob. Therefore, meaningful stroke times are not achievable. The control scheme of this valve functions to remove air from the valve operator, which duplicates the fail-safe condition, resulting in. the valve going to fail-safe (open) position. Therefore, the alternative testing proposed will consist of locally observing the valve during full-stroke testing for smooth operation and apparent problems which can affect the valve operation..'II.",':,:.':,::,.:.-.'.-:.:.1 NOTE 10: leap::;I'.,.::.:alt-..;,,'-I,;.:::..II.:.r::: .,':..y:.

ha%ety"fhne@ioy 6mB"rq~4i ii'ii'%f'i i q~ <TED W'h'fi'jii<jj'":jeri'g"'!i'iii'hei'xiiit'i8NWM by'~y'i'evezitiixijig46h<5xQme~tb:s'iiY7ijgwa'ter>,;tiom~~ent'el'.':n jg~bhki~RNS T c

Page 32 of 85 I

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5129-31 Revision No: 4 Date: 5-7-93 Note 10 (continued) adRi'teRPtBii~yatet'edheypcioaed-duni~ng;ax'eaux'eulatpos)g;castanet.'::he:,.,:Cashed Ou ~". X", 3. <>Ye:IL '(YX3 l '4~3.%g '+3! '1'4 ~'f; c30'8'e:iij~08i4xbn)~::;:wk3~2@5eppeL-.xorme8kcfQS%4ex'Xv-";.:to'~R

'

4eej'l" .',,ll'ill-.'i '::i'!'4'1'k it.:i '1: .:: ':: !': "

"4:.'!J NOTE 11: CS-299E&W Comment: See Attachment "A" for permissible seat leakage values.

NsxFi<~12~ww:-" 'l i'c "'

tne~Vn3unajLonti,'.el~

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e'zchaen'gegKcigauia~pus<~iijate3':;y CO'At@.LAment:;i>~~,"!:RXeXC3.:89 Bg~+06';:~Va'fVS~Ci.08eCgOQh'3 Ag>;.;Oor'mat~~

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.

he'a~3 'i 'a.'. 'eiti;:onj+S3 6v"'~!'4'::"8am~3:.-.<ia'jean:-'i,:vari~"g376w'",-.is,;:mai'atained Page 33 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5129-31 Revision No: 4 Date: 5-7-93 Note 12 (continued)

KXarCi;~iie)."~i~p,,acocndenne:;!With!::,XWW.;.p0'2p~('a)~at::;:;-Xefueii~n'g.; CZeO)ueenoc)IFj Qa.:8a55eNM.'84:,";,'.8n8e X%8ge058A~Atl!'X',efQe34l1g@f-;, .

C}N...QQ Page 34 of 85

S 4

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES I

Flow Diagram No: 1-5135-35 Revision No: 4 T

Date: 5-7-93 5 Note 5 (continued)

This valve is controlled by an auto/manual station with auto input from the letdown heat exchanger outlet temperature sensor (QTC-302). The valve also trips closed from an SX signal via a solenoid valve. The valve will be full-stroke exercised quarterly using auto/manual station which will permit rapid cycling of this regulating valve resulting in minimal impact on letdown temperature. Meaningful stroke time data is not available since this valve does not have local or remote position indication.

Fail safe testing this valve closed requires a longer period of time than cycling the valve using the auto/manual station. The valve will be fail safe tested to its closed position at cold shutdown frequency with letdown flow out of service thus avoiding high letdown line temperatures that could cause'flashing in the letdown heat exchanger and lifting of safety valves.

Page 37 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5135-35 Revision No: 4 Date: 5-7-93 gC j F C

I I ~

Page 38 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5142-Q Revision No: 4 Date: 5-7-93 NOTE 1:

NOTE 2: ICM-250 -251 -260 and -265 Code Relief : See Attachment "A" for permissible seat leakage values.

NOTE 3: IMO-261 Cold Shutdown Justification : This valve cannot be tested when SI pumps are required to be operable. Testing would result in isolation of the common suction 'line to both SI trains. This valve will be stroke tested and timed at cold shutdown frequency.

NOTE 4: IMO-262 and -263 Cold Shutdown Justification : These motor operated valves are located in series in the re-circulation line of the Safety Injection pumps. Exercising either of these valves will make both SI pumps inoperable. These valves will be full-stroke exercised and timed at cold shutdown frequency when SI pumps are not required to be operable.

NOTE 5: SI-110N -110S Code Relief  : Safety Injection (SI) pump discharge valves, SI-110N and -110S, cannot be exercised during power operation because the SI pumps cannot overcome reactor coolant system pressure. Therefore, no flow path exists and, because minimum flow lines branch off upstream of these valves, they cannot be part-stroke tested during pump testing. These valves cannot be exercised during cold shutdown because the SI pumps are required to be inoperable by Technical Specification 3.5.3 to protect against low temperature ovezpressurization of the reactor. Fh~s'se'."v'a'!vers Page 43 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5142-g2:=

Revision No: 4 Date: 5-7-93 Note 5 (continued) wi!1'i!'haaxuihll:='str<<iks!.-.'exancl~eB~!8;:.wiltjl iso pen4, and~~a1~ossd~@osi& ~on V~3:8%8kjgÃ4~kX4'XQVX~LSQ-'4XXN~85C+Pe NOTE 6 82-142 Ll L2 L3 and L4 Code Relief: jfh~f88efC eok~yuaXVgS~isn4j 8 8 4 2 8 i i 8 2 8

2 4 f 8 4 shut'duos% 4 mei'Oined"'.-- 8%'::"::,'i; efi3";,iiiijgi"::f'a4ajuenuy'::."

S tiara +8e

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g5jijggà ~~<AX-::::l!joe Oda:::Relief! -:,"':,:::!~W!haj';:,,:.Cccmmcn@ tpgpumpca>y>auoticn~yheo Page 44 of 85

DONALD C. COOK NUCLEAR PLANT al'I

,I VALVE TEST PROGRAM RELXEF REQUEST NOTES Flow Diagram No: 1-5151B-28 Revision No: 4 Date: 5-7-93 ROL+KM  ;..~xlDNWIXW-::.1WBA. 'da'.R~i1liaf-:,'. <:- 'aaS,.SVva',~Vaa jarffbrai. jpapaa'~a a4'basal lnllh%tLibT1g~Vb$'j8'6nl1<tPPSX PgX'bggav~1485llh'ti8@gZSbsiV'81 8'i'P'VO gkia. ltlNPfii)atl I I' lt

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Page 61 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 1-5151D-28 Revision No: 4

~ ~

Date: 5-7-93

,;:5~5.'O'"I~%14~; ndaÃXR~.:i~ad'~e-:.;,li'gBa~a'i.:,ga~lyasypKga~~an, apan;aagaKPj ilg'+lOfiji!CO@8dh'iCtgfSX'g'~g'kXibagl,",81+8%!BC!ti'8'k'"2'SC

':*:""i'tii I::!!et'%tiiiijgt~Otal'5'l'l 'iiiil".'-": '""~bJ"

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I Page 65 of 85

I DONALD C. COOK NUCLEAR PLANT ~ S 5

VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 I~

Revision No: 4 I

Date: 5-7-93 t

NOTE 9: RV-251 Code Relief : This air operated valve is used to regulate charging header flow to the reactor coolant system and seal water flow to the reactor coolant pump seals. The valve cannot be full-stroke exercised at power operation because it, would interrupt the RCP seal injection flow and would also upset pressurizer level.

The valve will be part-stroke exercised during power operation and full-stroke exercised at a cold shutdown frequency. The valve cannot be stroke timed because there is no local or remote position indicator available and cycle times are directly proportional to "how fast" the operator can turn the control knob. Therefore, meaningful stroke times are not achievable. The control scheme of this valve functions to remove air from the valve operator, which duplicates the fail-safe condition, resulting in the valve going to fail-safe (open) position. Therefore, the alternative testing proposed will consist of locally observing the valve during full-stroke testing for smooth operation and apparent problems which can affect the valve operation.

NOTE 10: SI-185 Code Relief: Bits;p'armKgXyj&c':oij9i<yaXjyejhas":,";an~'op'eq I.

Page 32 of 85

~ - ~

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 4 Date: 5-7-93 Note 10 (continued)

KBKicjaks'Qgwateye$ M~Pn~,:exasedyy~l6@ingfxeasxeaxafion): cKifrio . s":rescÃ6 NOTE 11: CS-299E&W Comment: See Attachment "A" for permissible seat leakage values.

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C i<ri~Xv~~,;;i Page 33 of 85

~ ~

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELXEF REQUEST NOTES Flow Diagram No: 2-5129-32 Revision No: 4 Date: 5-7-93 Note 12 (continued) egezat SeB,~In :a'e:-eel.deduce,,:.WiP'heidi-";3d'2'if/);;<<.:-',~t'!Xe?fue1 ileafl8~Ã4~3~f4NXE'K60885WCFt~~'pL83N~~'O'OXiC3;0'85VYAX'8'83'. "6~~%%be.~~%69'V~YM394A'DYi 4FAWMASZPx?4/454kkM x%%W445: 4?e %MA'kM9 Six<,.+QMCCw~;,y~>~" "Qp%4qi>%4~/?, '?Yj@$.'+ >>$)@?? >'@'<?S?e??~pS@@~?'

Q 6$ 'aahs'emb 'e6~~and~ Lies'aheg"tat'~x"ef e'e3;"~4cj~~~.:tie'cj'juicy~~'.

.

Page 34 of 85

DONALD C. COOK NUCLEAR PLANT I VALVE TEST PROGRAM ~ I I

RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 4 Date: 5-7-93 Note 5 (continued)

This valve is controlled by an auto/manual station with auto input from the letdown heat exchanger outlet temperature sensor (QTC-302). The valve also trips closed from an SI signal via a solenoid valve. The valve will be full-stroke exercised quarterly using auto/manual station which will permit rapid cycling of this regulating valve resulting in minimal impact on letdown temperature. Meaningful stroke time data is not available since this valve does not have local or remote position indication.

Fail safe testing this valve closed requires a longer period of time than cycling the valve using the auto/manual station. The valve will be fail safe tested to its closed position at cold shutdown frequency with letdown flow out of service thus avoiding high letdown line temperatures that could cause flashing in the letdown heat exchanger and lifting of safety valves.

Page 37 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5135-34 Revision No: 4 Date: 5-7-93 Page 38 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-Q$

Revision No: 4 Date: 5-7-93 NOTE 1: ICM-250 and ICM-251 f:Commentu 7:.-:,:::.:;-:ghana~!previous'~,::suhvmi~a6,:::i'~18 NOTE 2 ICM-250 -251 -260 and -265 Code Relief  : See Attachment "A" for permissible seat leakage values.

NOTE 3: IMO-261 Cold Shutdown Justification : This valve cannot be tested when SI pumps are required to be operable. Testing would result in isolation of the common suction line to both SI trains. This valve will be stroke tested and timed at cold shutdown frequency.

NOTE 4 IMO-262 and -263 Cold Shutdown Justification : These motor operated valves are located in series in the re-circulation line of the Safety Injection pumps. Exercising either of these valves will make both SI pumps inoperable. These valves will be full-stroke exercised and timed at cold shutdown frequency when SI pumps are not required to be operable.

NOTE 5: SI-110N -110S Code Relief : Safety Injection (SI) pump discharge valves, SI-110N and -110S, cannot be exercised during power operation because the SI pumps cannot overcome reactor coolant system pressure. Therefore, no flow path exists and, because minimum flow lines branch off upstream of these valves, they cannot be part-stroke tested during pump testing. These valves cannot be exercised during cold shutdown because the SI pumps are required to be inoperable by Technical Specification 3.5.3 to protect against low temperature overpressurization of the reactor gh~.ssiaivg:"ves Page 43 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5142-35 Revision No: 4 Date: 5-7-93 Note (continued) 5

.a!iln,!g.,e::-:;:, -.e ':.:::,-----, -1:

~V~3;::X:i8dY>498;5j~4'8$98'X5.'Ng,4W8~ebCQ""

':.-,:.i::!tlat",-"':j.:, i'-,:., 5*:::::,.:, . a ~ic-NOTE 6 51-142 L1 L2 L3 and L4 Code Relief': 5iheSe:;:.";;Ch'nohow>Vates'8,:;8@

in'I!7!::. '~i!i ! (, .:ii:.: i:i:,.:,. i -i,,:li.

hei-nlfn: dtMo'll+b." ecnaue'ee aCi.oke'.-";"'..."exert'ice'd,at;. 're'Xiii -i'rij~frej'uCfiajj',:

Page 44 of 85

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELIEF REQUEST NOTES Flow Diagram No: 2-5151B-27 Revision No: 4 Date: 5-7-93 l@EW. ')jj'"'i".,",:.IFfk"..K(FA"."'::'LOttRWK1~5!li~ -"' - 'lB'SPV~'1iYfBB"'PBXXO&!Bf+t','OPSIS,81'8@+

YNbie:. V$

etc " yp:eieexiie-:se'.

'~ii'~~;-:ix~Ve'>n6i"eztevn'a5:>yOSi+XOiigiiii"C5C'XO.':,~~Xi'itmieirit'aSXOn;,r<<<iiiearia.'-,'-.i

;:,,ize'i'its,':i~g~..j-.", .

'on: ui,:n'jp+~,>$ as:

au'jan%:";.t'ic[i"ti y'rii:

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'p.; '"'r:es~w': ',;:;;.i,'."::;

,r'oy':o's.ec'ij,I" '- ~ ','j '.';,, ":: '~jv,.

"'~:: *:.::::!" i!"""'"*i!~~i!i::4"-"*"::.'-"i!".iiiMpilia'i-'k-"'"""',--""""'"'-:"":sw' '= '

~

Page 61 of 85

~ ~

(~ v

( )

DONALD C. COOK NUCLEAR PLANT VALVE TEST PROGRAM RELXEF REQUEST NOTES Flow Diagram No: 2-5151D-27 Revision No: 4 Date: 5-7-93 (W!~5:::.-,-@ÃW&W,---::Ãa,:,::-:4's --4W,'..'.:..:.: -,- i,;-!:,,;jp:,**P,,T,:,,R..,P- PQ ski-'ei'Sioah8 on."'",.4',,-",'..':s "':iWR.."":."~aai':.~d'J

' ":..i 1i:*: "'::!it- --"t::,-:I'-"'::: -"!@l'll':",' h'!8!4$ ": '-" '8':

Page 65 of 85

Attachment C to AEP:NRC:0969V Revised ISI Valve Test Program