ML17332A774

Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1

ML17332A774
Person / Time
Site:	Cook
Issue date:	05/25/1995
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17332A775	List: ML17332A774 ML17332A776
References
AEP:NRC:1124B, GL-90-02, GL-90-2, NUDOCS 9506060413
Download: ML17332A774 (10)

Text

l~l~RI(GRIMY ACCELERATED RIDS PROCESSli REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)DOCKET I 05000315 05000316

SUBJECT:

Application for amends to licenses DPR-58&DPR-74,modifying TS 5.3.1 to allow fuel reconstitution,per GL 90-02,Suppl 1.I DISTRIBUTION CODE: A014D COPIES RECEIVED:LTR

+ENCL l SIZE: TITLE: Generic Ltr 90-02 re Line-Item Tech Spec Improvement

-A ternatzve Re R NOTES: ACCESSION NBR:9506060413 DOC.DATE: 95/05/25 NOTARIZED:

YES FACIL:50-315 Donald C.Cook Nuclear Power Plant, Unit 1, Indiana M 50-316 Donald C.Cook Nuclear Power Plant, Unit 2, Indiana M AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.

Indiana Michigan Power Co.(formerly Indiana&Michigan Ele P RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)R INTERNAL: EXTERNAL: NOAC RECIPIENT ID CODE/NAME PD3-1 PD HICKMAN,J%BR-S&A+RX RES/DSIR/EIB COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD11-3 NRR/DSSA OGC/HDS2 NRC PDR COPIES LTTR ENCL 1 1 1 1 1 0 1 1 D C U N NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE iVASTE!CONTACTTHE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.504-2083)TO ELIS II NATE YOUR NAME PRO%I DISTRIBUTION LISTS I'OR DOCL'MEN'I'S YOU DON" I'EED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9

'I Indiana Michigan Power Company P.O.Box 16631 Columbus, OH 43216 May 25, 1995 AEP:NRC:1124B Docket: Nos.: 50-315 50-316 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DE C.20555 Gentlemen:

Donald C.Cook Nuclear Plant Units 1 and 2 PROPOSED TECHNICAL SPECIFICATION AMENDMENT TO ALLOW FUEL RECONSTITUTION (GENERIC LETTER 90-02 SUPPLEMENT 1)This letter and its attachments constitute an application for amendment to the technical specifications (T/Ss)for the Donald C.Cook Nuclear Plant units 1 and 2.Specifically, we are proposing to modify T/S 5.3.1 to allow fuel reconstitution.

The proposed amendment is a line item improvement based on the recommendations of generic letter (GL)90-02 supplement 1,"Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications." The proposed changes will permit removal of suspected defective fuel rods, allowing for future reductions in occupational radiation exposure, and plant radiological releases.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 revised T/S pages.We believe the proposed changes will not result in (1)a significant change in the types of'ny 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.

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ll 11 L 1 U.S.Nuclear Regulatory Commission Page 2 AEP'NRC'1124B In compliance with the requirements of 10 CFR 50.91(b)(l), copies of this letter and its attachments have been transmitted to the Michigan Public Service Commission and to the Michigan Department of Public Health.Sincerely, EZ E.E.Fitzpktrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~>~DAY OF 1995 N tery Public My Commission Expires: eh Attachments CC: A.A.Blind G.Charnoff J.B.Martin NFEM Section Chief NRC Resident Inspector-Bridgman J.R.Padgett ATTACHMENT 1 TO AEP:NRC:1124B 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:1124B Page 1 I.DESCRIPTION OF CHANGES We are proposing to modify technical specification (T/S)5.3.1 (Design Features-Fuel Assemblies) to allow for fuel reconstitution.

The modified statement permits"limited substitutions of zirconium alloy or stainless steel filler rods, in accordance with NRC-approved applications of fuel rod configurations." II.JUSTIFICATION FOR CHANGES The proposed T/S amendment is a line item improvement based on the guidance of generic letter (GL)90-02 supplement 1,"Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications." The present T/S requirement for fuel assemblies specifies the quantity of fuel assemblies and the number of fuel rods per assembly.Flexibility to deviate from the number of fuel rods per assembly is desirable to permit removal of fuel rods that are found to'be leaking or are determined to be probable sources of future leakage, so that reuse of the majority of the affected fuel assembly is permitted with minimal impact on core design.for the subsequent fuel cycle.This improvement may provide reductions in future occupational radiation exposure and plant radiological releases.The proposed change to allow reconstitution is consistent with the recommendation of GL 90-02 supplement 1.Substitution is limited to zirconium alloy or stainless steel filler rods (i.e., no open water channels are permitted).

Also, substitution must be in accordance with"NRC-approved applications of fuel rod configurations." Generic letter 90-02 supplement 1 states: "The staff considers an NRC-approved methodology to be any methodology that the NRC staff has explicitly approved in a written safety evaluation or a plant-specific technical basis.That NRC-approved methodology must be used only for the purpose and the scope of application specified in the reviewed document as approved or modified in the NRC approval documentation." We are submitting this amendment only as a contingency should the need arise in the future.As required by these proposed changes, any reconstitution performed will be done in ATTACHMENT 1 TO AEP:NRC:1124B Page 2 accordance with an already approved methodology, or a specific methodology will be submitted for NRC approval.III.10 CFR 50 92 CRITERI Per 10 CFR 50.92, a proposed change does not involve significant hazards consideration if the change does not: involve a significant increase in the probability or consequence 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 The proposed changes only modify the T/Ss such that reconstitution is recognized as acceptable under very limited circumstances.

Reconstitution is limited to substitution of zirconium alloy or stainless steel filler rods, and must be in accordance with approved applications of fuel rod configurations.

Although these changes permit reconstitution to occur without the need for a specific T/S change, an approved methodology is required prior to its application.

Since the changes will allow substitution of filler rods for leaking or potentially leaking rods, the changes may actually reduce the radiological consequences of an accident.It is noted that the specific changes requested in this letter have previously been found acceptable by the NRC in GL 90-02 supplement 1.For these reasons, we conclude that the changes will not involve a significant increase in the probability or consequences of an accident previously evaluated.

Criterion The proposed changes will not create the possibility of a new or different kind of accident from any accident previously evaluated because they will only affect the assembly configuration and can only be implemented in accordance with an NRC-approved methodology.

The other aspects of plant design, operation limitations, and responses to events will remain unchanged.

It is noted that the changes have previously been determined acceptable by the NRC in GL 90-02 supplement

1.

ATTACHMENT 1 TO AEP:NRC:1124B Page 3 Criterion 3 The proposed amendment will not involve a significant reduction in a margin of safety because the changes can only be implemented in accordance with an NRC-approved methodology.

It is noted that the changes have previously been determined acceptable by the NRC in GL 90-02 supplement l.