ML17321A174

Application for Amends to Licenses DPR-58 & DPR-74,revising Tech Specs to Reflect Administrative Changes.Fee Paid

ML17321A174
Person / Time
Site:	Cook
Issue date:	10/19/1984
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17321A175	List: ML17321A174 ML17321A176
References
AEP:NRC:0433D, AEP:NRC:433D, NUDOCS 8410230067
Download: ML17321A174 (9)

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ACCESSION NBR:8410230067 DOC ~ DATE: 84/10/19 NOTARIZED: NO DOCKET FACIL:50 315 Donald C ~ Cook Nuclear Power Planti Unit 1P Indiana L 05000315 50-316 Donald C ~ Cook, Nuclear Power Planti Unit 2P Indiana 8 05000316 AUTH, NAME AUTHOR AFFILIATION ALEXICHPM.P ~ Indiana L Michigan Electric Co, REC IP, NA>~E. REC IP IENT AF F ILI A TION DENTONiH.Rs Office of Nuclear Reactor Regulations Director

SUBJECT:

Application for amends to Licenses DPR 58 L DPR 74ir ekising Tech Specs to reflect administrative changes,Fee TITLE: OR CODE: AOOID COPIES RECEIVED:LTR Submittal: General Distribution

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paid'ISTRIBUTION E LX NOTES: 05000315 OL: 10/25/74 05000316 OL 0 12/23/72 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01= 7 7 INTERNAL: ADM/LFMB 1 0 ELD/HDS3 1 0 NRR/DE/MTEB 1 1 NRR/DL D IR 1 1 NRR/DL/DRAB 1 0 N METB 1 1 NRR/DSI/RA 8 1 1 REG F IL 04 1 1-RGN3 1 1 EXTERNAL: ACRS 09 6 6 LPDR 03 2 2 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1 TOTAL NUMBER OF COPIES REQUIRED ~ LTTR 27 ENCL 24

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INDIANA 8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 October 19, 1984 AEP:NRC:0433D Donald C. Cook Nuclear Plant Unit Nos. 1 and 2 Docket Nos. 50-315 and 50-316 License Nos. DPR-58 and DPR-74 TECHNICAL SPECIFICATION CHANGE REQUEST Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Reference:

Submittal No. AEP:NRC:0433 dated May 10, 1983.

Dear Mr. Denton:

This letter and its Attachments constitute an application for amendment to the Appendix 'A'echnical Specifications for the Donald C.

Cook Nuclear Plant Unit Nos. 1 and 2. Attachment No. 1 is the description of the changes. Attachment No. 2 contains the revised Technical Specification pages. All changes have been indicated by a vertical line on the page. The purpose of these changes is to supplement our previous submittal AEP:NRC:0433 refer enced above.

Our evaluation of the content of this Technical Specification change requests proposed by this letter is provided in Attachment No. 1. Many of the changes are administrative. Of those that are not, we believe all are of the type where the change may result in some increase to the probability or consequences of a previously analyzed accident, but the results of the change are clearly within criteria that are currently acceptable to the NRC. Based on our evaluation we have concluded that these changes will not involve a significant hazards consideration as defined in 10 CFR 50.92. In addition we believe that the proposed changes will not adversely impact the environment.

In compliance with the requirements of 10 CFR 50.91(b)('1), a copy of this letter and its attachments have been transmitted to Mr. R. C. Callen of the Michigan Public Service Commission.

These proposed Technical Specifications have been reviewed and approved by both the Plant Nuclear Safety Review Committee and the AEPSC Nuclear Safety and Design Review Committee.

8410230067 8410'i9

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Mr. Harold R. on AEP:NRC:0433D Pursuant to 10 CFR 170.22, a check in the amount of $ 150.00 is attached for the NRC processing of these aforementioned requests. We request that the subject Technical Specification change requests be reviewed in conjunction with the above referenced submittal.

This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, M. . Al ich pQ )g4 Vice Pre ident "Qi '~

MPA/cm Attachments cc: John E. Dolan W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff E. R. Swanson, NRC Resident Inspector - Bridgman

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Unit No. 1; Page 3/4 6-1 This change would add the proposed footnote to page 3/4 6-1 to make Technical Specifications between Unit 1 and Unit 2 consistent.

The change may result in either some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all criteria which ar e acceptable to the NRC as indicated in Revision 4 to the Standard Technical Specifications. In addition, acceptable operation with the proposed change has been denonstrated, as indicated by compliance with the Unit 2 Technical Specifications.

Unit No. 1; Page 3/4 6-14 and 6-15 (a) In Section 4.6.3. 1. 1, items (a) and (b) have been replaced by a new paragraph and reference to 92 days testing of the operable valves has been deleted. The test frequency will be as per the ASME Code Section XI requirements when tested pursuant to specification 4.0.5.

The testing requirements for each valve under specification 4.0.5 has been incorporated in a new section 4.6.3.1.3.

(b) In Section 4.6.3. 1.2, items (d) and (e), which referred to cycling the valves one complete cycle, have been deleted and replaced by a new section No. 4.6.3.1.3. The new section notes that each valve in table 3.6-1 will be tested pursuant to specification 4.0.5.

This change would add consistency between the Technical Specification surveillance requirements in Units 1 and 2. This change would be administrative change since the ASME Section XI code requirement are similar to current Technical Specification requirements. A small number of valves, involved with item (a) above, will be tested every cold shutdown instead of once every 92 days, when tested pursuant to ASME code,Section XI requirements. The change may result in either some increase to the probability or consequences of a previously analyzed accident or may reduce in some way a safety margin, but the results of the change are clearly within all criteria which are acceptable to the NRC as indicated in Revision 4 to the Standard Technical Specifications. In addition acceptable operation, with the proposed changes has been denonstrated, as indicated by compliance with the Unit No. 2 Technical Specifications.

Unit No. 1; Pages 3/4-6-16 through 6-22; Table 3.6-1 We propose the column entitled "Testable During Plant Operation" be deleted to be consistent with Unit No. 2 Technical Specifications. This would allow the valves in Table 3.6-1 to be tested pursuant to Technical Specification 4.0.5. Specification 4.0.5 requires that the in-service testing of ASME Code Class 1, 2 and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code.

This proposed change is considered an administrative change which would achieve consistency in the valve testing requd.rements and make the Unit No. 1 Technical Specification identical to that of Unit No. 2.

Unit No. 2; Page 3/4 6-30; Table 3.6-1 We propose asterisks be added to valves SM-8 and SM-10 to denote that these valves may be opened on an intermittent basis under administrative controls. Administrative control of these valves would allow upper containment samples to be taken in MODES 1, 2, 3, and 4 without having personnel to access upper containment. Thus, our ALARA program would be further enhanced. This change would make Unit No. 1 Technical Specification consistent with that of Unit No. 2. Since this proposed change would allow the identical operating practices to that of Unit 1, which have been denanstrated as acceptable, we believe this change would not involve a Significant Hazards Consideration.

Unit No. 2; Pages 3/4 6-28 and 6-31; Table 3.6-1 This change would delete valves listed in Table 3.6-1 as E6 (NSW-415-1),

E7 (NSW-415-2), E8 (NSW-415-3), E9 (NSW<<415-4), E10 (NSW-419-1), E11 (NSW 419 2) ~ E12 (NSW 419 3) ~ E13 '(NSW 419 4) ~ E14 (NSW 224 1) ~ E15 (NSW-224-2), E16 (NSW-224-3), E17 (NSW-224-4), E32 (NSW-417-3), and E33 (NSW-417-4). We propose that the valves be renumbered sequentially (i.e.,

E6, E7, etc.) Xn Amendment No. 47 these valves were replaced by air operated isolation valves listed in Table 3.6<<1 as B48 (WCR-900), B50 (WCR-904), B52 (WCR-908), B54 (WCR-912), B56 (WCR-920), B58 (WCR-924), B60 (WCR-928), B62 (WCR-932), B28 (WCR-941), B29 (WCR-942), B30 (WCR<<943), B31 (WCR-944), B64 (WCR-960), and B66 (WCR-964). When the previous Technical Specification change request was submitted, the original designation (NSW) valves cited above was inadvertantly left in the Technical Specifications.

This is considered to be an administrative change to correct this oversight.

Unit No. 1; Table 3.6-1; Pages 3/4 6-17, 6-18, and 6-19 Unit No. 2; Table 3.6-1 Pages 3/4 6-17, 6-18, 6-19, 6-22, 6-23, 6-24, and 6-30.

We propose that the footnote in all of the above pages be deleted. The footnote references an effective time period prior to 1982 refueling outage. This proposed change is an administrative change, in that, a sentence in the Technical Specifications that is no longer applicable, would be deleted.