ML17319B256

Application to Amend Licenses DPR-58 & DPR-74,changing Tech Specs to Incorporate Editorial & Organizational Changes

ML17319B256
Person / Time
Site:	Cook
Issue date:	03/29/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17319B257	List: ML17319B256 ML17319B258
References
AEP:NRC:0659, AEP:NRC:659, NUDOCS 8204060050
Download: ML17319B256 (9)

Text

REGULATORY ~FORMATION DISTRlBUTION SY M (RIDS)

ACCESSION NBR:8204060050'OC ~ DATE: 82/03/29 NOTARIZED: NO DOCKET FACIL:50-315 Donald C. Cook Nuclear Power Plant~ Unit 1> Indiana 8 05000315 50"316 Donald C ~ Cook Nuclear Power Planti Uni,t 2i Indiana BYNAME 8 05000316

'AUTH AUTHOR AFFILIATION HUNTERiR ~ ST Indiana 8 Michigan Electric Co.

.RECIP ~ NAME RECIPIENT AFFILIATION DENTONIH ~ RE Office of Nuclear Reactor Regula'tioni Director

SUBJECT:

.Application )to amend Licenses DPR-58 8 DPR 74ichanging "Tech Specs to incorporate ediitorial 8 organizational changes.

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INDIANA II MICHIGAN ELECTRIC COMPANY P. O. 8OX 18 80 WLING GR E EN STATION NEW YORK, N. Y. 10004 March 29, 1982

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AEP:NRC:0659 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 SPECIFICATIONS CHANGE REQUEST Mr. Harold R. Denton, Director 6'g9e+~

Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter and its Attachments request several changes to the Donald C. Cook Nuclear Plant, Unit No. 1 and No. 2 Appendix A Technical Specifications. Attachment No. 1 to this letter contains the description of the changes. Attachment No. 2 contains the revised Technical Specification pages for Unit No. l. and Attachment No. 3 contains the revised Technical Specification pages for Unit No. 2. All changes are indicated by a vertical line on the right hand side of the page in Attachment Nos. 2 and 3.

The proposed Technical Specification changes contained herein have been reviewed and approved by the Plant Nuclear Safety Review Committee (PNSRC). Change No. 1 has been approved by the AEPSC Nuclear Safety and Design Review Committee (NSDRC) and Change Nos. 2, 3, and 4 will be presented to the NSDRC at their next meeting. g/

O Four proposed Technical Specification revisions are contained in this submittal. Change Nos. 2 and 3 are considered to be Class II amendments ($ 1,200.00 fee each). Class I duplicate fees also apply for these changes. Change Nos. 1 and 4 are editorial in nature. Enclosed, therefore, is a check in tha amount of g3,200.00 for NRC processing of ~/t+~

the aforementioned requests.

g/ gazoo 820329 82040b0050 05000315 PDR ADOCK PDR

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Mr. Harold R. Denton AEP:NRC:0659 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, R. S. Hunter Vice President

/md cc: John E. Dolan Columbus R. W. Jurgensen W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant Bridgman

ATTACHMENT NO. 1 TO AEP:NRC:00659 DESCRIPTION OF PROPOSED TECHNICAL SPECIFICATION CHANGES FOR D. C. COOK UNIT NOS ~ 1 AND 2

Chan e No. 1 Unit 1; Page 3/4 3-9; Table 3.3-1 Unit 2; Page 3/4 3-8; Table 3.3-1

, This change is editorial in nature. For Unit Nos. 1 and 2, it is requested to change the words "Turbine impulse chamber pressure" under Designation P-7 of the Reactor Trip System Interlocks of Table 3.3-1 ("Reactor Trip System Instrumentation" ) to more accurately describe these channels. For Unit No. 1, it is requested that these words be changed to "Turbine First Stage Pressure" which is the control room nameplate terminology used for these channels. For Unit No. 2, it is requested to change these words to "Pressure Before the First Stage" which is a technically accurate description of these channels. The Unit No. 2 control room nameplate terminology will be changed to coincide with the proposed wording. The above changes will result in accurate and consistent Technical Specification and control room nameplate terminology descriptions of- these channels. These changes will not adversely affect the health and safety of the general public.

Chan e No. 2 Unit 1; Page 6-2; Figure 6.2-1 Unit 2; Page 6-2; Figure 6.2-1 Figure 6.2-1 is the "Offsite Organization for Facility Management and Technical Support". This Figure has been revised to incorporate the most recent offsite organizational management changes.

The proposed changes will result in a Figure which more accurately describes our current organization. These changes will not adversely affect the health and safety of the general public.

Chan e No. 3 Unit 1; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-6; Section 6.5.1.2 Unit 2; Page 6-3; Figure 6.2-2 Page 6-5; Section 6.3 Page 6-5; Section 6.5.1.2 Figure 6.2-2 of both Units'echnical Specifications is the "Facility Organization" of the Donald C. Cook Nuclear Plant. This Figure has been amended to show current position titles and the addition of the following five supervisory positions:

Fire Protection Coordinator Chief Security Supervisor Shift Security Supervisor Environmental Coordinator Shift Technical Advisor

Three footnotes have also been added to the legend of the chart to more accurately describe the reporting nature of the QA Supervisor and to indicate the Unit Supervisor's present operating license. The indicated changes will make the Facility Organization chart current.

In addition, Specification 6.3.2 has been added under Specification 6.3, "Facility Staff Qualifications", of both Units.

Specification 6.3.2 has been added to accommodate our new Operations Superintendent, who does not presently hold a Senior Reactor Operator's License (SOL).

Specification 6.5.1.2, which identifies the Chairman and Members of the Plant Nuclear Safety Review Committee (PNSRC), has been amended to reflect present position titles. In addition, the Shift Supervisor and Environmental Coordinator have been included as PNSRC members.

These changes will not adversely affect the health and safety of the general public.

Chan e No. 4 Unit 1; Page 6-13; Section 6. 7. 1. d Unit 2; Page 6-13; Section 6.7.1.d Specification 6.7.l.d identifies to .whom a Safety Limit Violation Report shall be submitted in the event a Safety Limit is violated. This change is editorial in nature and serves to reflect the present position title of the previous Vice President,- Nuclear Engineering. Thus, in addition to the Commission and the Chairman of the NSDRC, a Safety Violation Report shall also be submitted to the Executive Vice President, Construction and New York Engineering, AEPSC.

This change will not adversely affect the health and safety of the general public.

ATTACHMENT NO. 2 TO AEP:NRC:00659 REVISED TECHNICAL SPECIFICATION PAGES FOR D.C. COOK UNIT NO. 1