ML17333A315

Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test

ML17333A315
Person / Time
Site:	Cook
Issue date:	02/22/1996
From:	Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17333A316	List: ML17333A315 ML17333A317
References
RTR-REGGD-01.009, RTR-REGGD-01.108, RTR-REGGD-1.009, RTR-REGGD-1.108 AEP:NRC:1243, NUDOCS 9602260305
Download: ML17333A315 (8)

Text

CATEGORY 1 REGULATOR NFORMATION DISTRIBUTION

.EM (RIDS)ACCFCSSIOU NBR:9602260305 DOC.DATE: 96/02/22 NOTARIZED:

YES DOCKET¹FACIL:50-315 Donald C.Cook Nuc'ear 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 Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to licenses DPR-58!'PR-74,modifying Table 4.8-1,DG Test Schedule by ref RG 1.9,Rev 3 rather than RG 1.108,Rev 1 criteria for determination of valid DG test.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR 1 ENCL I SIZE: TITLE: OR Submittal:

General Distribution NOTES: RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNA: FAIRE CRENATE>I NRR DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN SD-5(EXT.415-2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 12 ENCL , 11 Indiana Michigan Power Company PO Box 16631 Columbus, OH 43216 lNOIANA NICHIGAN PWM February 22, 1996 AEP:NRC:1243 Docket: Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen:

Donald C.Cook Nuclear Plant Units 1 and 2 PROPOSED AMENDMENT TO TECHNICAL SPECIFICATION SECTIONS 3/4.8.1~1 FOR ELECTRICAL POWER SYSTEMS This letter and"its attachments constitute an application for amendment to the technical specifications,(T/Ss) for Donald C.Cook Nuclear Plant units 1 and 2.Specifically, we are proposing to modify Table 4.8-1, Diesel Generator Test Schedule, by referencing Regulatory Guide 1.9, Revision 3 rather than Regulatory Guide 1.108, Revision 1 criteria for the determination of a valid diesel generator test.Attachment 1 provides a detailed description of the proposed changes, the justification for the changes, and our determination of no significant hazards consideration performed pursuant to 10 CFR 50.92.Attachment 2 contains the existing T/S pages marked to reflect the proposed changes.Attachment 3 contains the proposed T/S pages.We believe the proposed changes will not result in (1)a significant change in the types of any effluent that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee and the Nuclear Safety and Design Review Committee.

9'602260305 960222 PDR ADQCK 05000315 P PDR U.S.Nuclear Regulatory Commission Page 2 AEP:NRC:1243 In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to t'e Michigan Department of Public Health.Sincerely, C4.4 E.E.Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~~DAY OF 1996 otary Pub ic pit Attachments CC: A.A.Blind G.Charnoff H.J, Miller NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett

'lg r ATTACHMENT 1 TO AEP:NRC:1243 DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES TO THE DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 TECHNICAL SPECIFICATIONS ATTACHMENT 1 TO AEP:NRC:1243 Page 1 DESCRIPTION OF CHANGES The proposed amendment to Technical Specification (T/S)3/4.8.1.1 makes the following specific change to the Cook Nuclear Plant units 1 and 2 T/S: Revises a footnote in Table 4.8-1 to read as follows: Criteria for determining number of failures and valid tests shall be in accordance with Regulatory Position C.2.1 of Regulatory Guide 1.9, Revision 3, where the number of tests and failures is determined on a per diesel generator basis.For the purposes of this test schedule, only valid tests conducted after the OL issuance date shall be included in the computation of the"last 20 valid tests." II.JUSTIFICATION FOR CHANGES The proposed revision to the T/S is based on the fact that Regulatory Guide 1.9, Revision 3 has incorporated the pertinent guidance previously addressed in Revision 1 of Regulatory Guide 1.108, and, being a more recent document, it better reflects the NRC requirements regarding diesel generator testing.IIX.10 CFR 50 92 CRITERIA Per 10 CFR 50.92, proposed changes do not involve a significant hazards consideration if the changes do not: involve a significant increase in the probability of consequences of an accident previously evaluated, 2.create the possibility of a new or different kind of accident from any accident previously evaluated, or 3.involve a significant reduction in a margin of safety Criterion 1 This amendment request does not involve a significant increase in the probability or consequences of an accident previously evaluated because the proposed change to the T/S does not affect the assumptions, parameters, or results of any UFSAR accident analysis.The proposed amendment does not modify any existing equipment, and the proposed acceptance criteria for diesel generator testing will conform to NRC guidance.Based on these considerations, it is concluded that the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

ATTACHMENT 1 TO AEP'NRC'1243 Page 2 Criter on The proposed changes do not involve physical changes to the plant or changes in plant operating configuration.

The proposed changes update guidance for diesel generator testing.Thus, it is concluded that the proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated.

Crite ion 3 The proposed changes update guidance for the testing of diesel generators.

The guidance is endorsed by the NRC in Regulatory Guide 1.9, and compliance with this guidance will ensure the operability of the diesel generators.

Thus, there is no significant reduction in the margin of safety.