ML17333A320

Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor

ML17333A320
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
ML17333A321	List: ML17333A320 ML17333A322
References
AEP:NRC:0659AA, AEP:NRC:659AA, NUDOCS 9602280006
Download: ML17333A320 (9)

Text

CATEGORY 1 E

REGULATOhINFORMATION DISTRIB':TION ~TEN (R/DS)

ACCESSi.ON NBR:9602280006 DOC.DATE: 96/02/22 NOTARIZED: 'YES DOCKET ¹ FAC'lL: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 !; Mi;chigan -Ele RECIP.NAME RECIPIENT AFFILIATION Document Cont:ol Branch (Document Control Desk)

SUBJECT:

Application for amends to licenses DPR-58 !'PR-74,proposing to remove requirement that Operations Superintendent must hold or have held SOL at plant or similar reactor.

DISTRIBUTION CODE: AOOID TITLE: OR COPIES RECEIVED:LTR Submittal: General Distribution t ENCL I SIZE: 7 NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-1 LA 1 1 PD3-1 PD 1 1 HICKMAN,J 1 j.

INTERNAL: 1 1 NRR/DE/EMCB 1 1 CH/HICB 1 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 1 NUDOCS-ABSTRACT 1 1 OGC/HDS2 1 0 EXTERNAL: NOAC 1 1 NRC PDR 1 1 D

U E

N 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 REQUIR"'D: LTTR 12 ENCL ll

-p /

.t V

f

'l

~ ~

,Indiana Michigan

'Power Company PO Box 16631 Columbus, OH 43216 IHQIANAl NlCHlGAM PQWKR h

February 22, 1996 AEP:NRC:0659AA 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 SECTION 6 ADMINISTRATIVE CONTROLS This letter and its attachments constitute an application for amendment to the technical specifications (T/S) for Donald C. Cook Nuclear Plant units 1 and 2. Specifically, we are proposing to remove the requirement that the Operations Superintendent must hold or have held a Senior Operator License at Cook Nuclear Plant, or a similar reactor. In addition, a mid-level operations manager will only be required to hold a Senior Operator License if the Operations Superintendent does not hold one.

Attachment 1 provides a detailed description of t'e 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.

270070 9602280006 050003i5, P

ADOCK 960222,'DR PDR pj i

U. S. Nuclear Regulatory Commission AEP:NRC:0659AA Page 2 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 the Michigan Department of Public Health.

Sincerely, E. E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS@~~ DAY OF 1996 N tery Pu lic pit Attachments CC: A. A. Blind G. Charnoff H. J. Miller NFEM Section Chief NRC Resident Inspector - Bridgman J. R. Padgett

ATTACHMENT 1 TO AEP:NRC:0659AA DESCRIPTION AND JUSTIFICATION OF CHANGES 10 CFR 50.92 ANALYSIS FOR CHANGES ~

TO THE DONALD C. COOK NUCLEAR PLANT UNIT 1 AND 2 TECHNICAL SPECIFICATIONS

ATTACHMENT TO AEP:NRC:0659AA Page 1 I. SCOPE The change to Section 6 of the Cook Nuclear Plant Technical Specifications, is administrative in nature and affects specifications 6.2.2.h, 6.3.1 and 6.5.1.2 as they are related to Operation Superintendent qualifications.

II. PURPOSE The purpose of this change is to incorporate the guidance found in ANSI/ANS 3.1 - 1993 Section 4.2.2 which defines the special requirements for the position of Operations Manager.

III'ESCRIPTION OF CHANGES The proposed amendment makes the following specific changes to the Cook Nuclear Plant Units 1 and 2 Technical Specifications:

The introduction to 6.2.2 has been moved from page 6-1 to 6-2.

6.2.2.h has been changed to,.read:

h. The Operations Superintendent shall meet one of the following: (a) hold a Senior Operator License at Cook Nuclear Plant or similar reactor, or (b) have held a Senior Operator License at Cook Nuclear Plant or similar reactor, or (c) have been certified for equivalent senior operator knowledge, or (d) have plant operational knowledge consistent with the requirements of the Operations Superintendent gob. If the Operations Superintendent does not hold a Senior Operator License, then an operations middle manager shall hold a Senior Operator License.

6.3.1 was changed to correspond to the changes made to 6.2.2.h.

In Technical Specifications 6.5.1.2 change the third paragraph to read:

PNSRC members and alternates shall meet or exceed the minimum qualifications of ANSI N18.1-1971 Section 4.4 for comparable positions. The nuclear power plant operations individual shall meet the qualifications of Section 4.2.2 of ANSI N18.1-1971 except for the requirement to hold a Senior Operator License. The operations individual shall meet the requirements of section 6.2.2.h. The maintenance individual shall meet the qualifications of Section 4.2.3 of ANSI N18.1-1971.

<7

'js ATTACHMENT TO AEP'NRC'0659AA Page 2 IV. JUSTIFICATION FOR CHANGE Item (d) of Section 4.2.2 of ANSI/ANS 3.1 - 1993 provides a relaxation from the requirement for the Operations Manager to obtain a Senior Operator License or certification. The ANSI/ANS standard provides for equivalent "plant operational knowledge of the Operations Manager's job," in place of obtaining a license or certification. In the event the Operations Manager does not hold an SRO, a mid-level operations manager is required to hold one per ANSI/ANS 3.1.

The proposed amendment is consistent with this requirement.

This position is further supported in a letter dated January 26, 1984, from Steven A. Varga (NRR) to our Mr. John Dolan, containing the NRC's response to our request to change Technical Specification 6.3. The letter stated in part:

"Ve believe the Operations Superintendent's knowledge of plant operations should remain current but that this can be done through effective training and daily interactions. Since maintaining the SOL would require considerably more effort and might detract, from the overall operations supervision, we also believe the Operations Superintendent need not maintain the SOL but he should have capable and licensed individuals reporting to him."

In light of the NRC's opinion, and in addition to the changes in qualification requirements as put forth in ANSI/ANS 3.1 which replaced ANSI N18.1, changing the Technical Specification will allow us to better manage the plant, and meet the intent of the updated ANS/ANSI requirements.

V. 10 CFR 50 92 CRITERIA Per 10 CFR 50.92, a proposed change does not involve a significant hazards consideration if the change does 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.

Crite o The amendment request does not involve a significant increase in the probability or consequences of accident previously evaluated because the proposed change to the Technical

ATTACHMENT TO AEP: NRC: 0659AA Page 3 Specification does not affect the assumptions, parameters, or results of any UFSAR accident analysis. The proposed amendment does not modify any existing equipment. It is concluded that the changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

Criterion 2 The proposed change does not involve physical changes to t'e plant or changes in plant operating configuration. The proposed change updates the requirements for the Operations Superintendent. 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.

n Criterion 3 The proposed change updates the requirements for Operations Superintendent. There is no reduction in the margin of safety.

ATTACHMENT 2 TO AEP:NRC:0659AA CURRENT TECHNICAL SPECIFICATION PAGES WITH CHANGES MARKED