ML013380080

DC Cook, Units 1 and 2, - Issuance of Amendments 264 & 246. Amendments Would Create TS 3.0.6 & Associated Bases to Allow Equipment That Was Removed from Service or Declare Inoperable to Be Returned to Service Under Administrative Control

ML013380080
Person / Time
Site:	Cook
Issue date:	02/01/2002
From:	Stang J NRC/NRR/DLPM/LPD3
To:	Bakken A Indiana Michigan Power Co
References
TAC MB2738, TAC MB2739
Download: ML013380080 (13)

Text

February 1, 2002 Mr. A. Christopher Bakken III, Senior Vice President and Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group 500 Circle Drive Buchanan, MI 49107

SUBJECT:

DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS (TAC NOS. MB2738 AND MB2739)

Dear Mr. Bakken:

The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 264 to Facility Operating License No. DPR-58 and Amendment No. 246 to Facility Operating License No. DPR-74 for the Donald C. Cook Nuclear Plant, Units 1 and 2. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated August 7, 2001.

The amendments would create TS 3.0.6 and associated bases to allow equipment that was removed from service or declared inoperable to be to returned to service under administrative controls solely to perform the testing required to demonstrate its operability or the operability of other equipment. TS 3.0.6 would incorporate the administrative controls currently set forth as TS 3.0.5 in NUREG-1431, Standard Technical Specifications Westinghouse Plants, Revision 2, dated April 30, 2001.

A copy of our related safety evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely,

/RA/

John F. Stang, Senior Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316

Enclosures:

1. Amendment No. 264 to DPR-58

2. Amendment No. 246 to DPR-74

3. Safety Evaluation cc w/encls: See next page

ML013380080 *See previous concurrence OFFICE PM:PD3-1 LA:PD3-1 BC:RTSB OGC (A)SC:PD3-1 NAME JStang THarris WBeckner RWeisman* WReckley DATE 01/28/2002 01/29/2002 02/01/2002 01/23/02 02/01/2002 Donald C. Cook Nuclear Plant, Units 1 and 2 cc:

Regional Administrator, Region III Drinking Water and Radiological U.S. Nuclear Regulatory Commission Protection Division 801 Warrenville Road Michigan Department of Lisle, IL 60532-4351 Environmental Quality 3423 N. Martin Luther King Jr Blvd Attorney General P.O. Box 30630, CPH Mailroom Department of Attorney General Lansing, MI 48909-8130 525 West Ottawa Street Lansing, MI 48913 Scot A. Greenlee Director, Nuclear Technical Services Township Supervisor Indiana Michigan Power Company Lake Township Hall Nuclear Generation Group P.O. Box 818 500 Circle Drive Bridgman, MI 49106 Buchanan, MI 49107 U.S. Nuclear Regulatory Commission David A. Lochbaum Resident Inspector's Office Union of Concerned Scientists 7700 Red Arrow Highway 1616 P Street NW, Suite 310 Stevensville, MI 49127 Washington, DC 20036-1495 David W. Jenkins, Esquire Site Vice President Indiana Michigan Power Company Indiana Michigan Power Company Nuclear Generation Group Nuclear Generation Group One Cook Place One Cook Place Bridgman, MI 49106 Bridgman, MI 49106 Mayor, City of Bridgman Michael W. Rencheck, Vice President P.O. Box 366 Strategic Business Improvements Bridgman, MI 49106 Indiana Michigan Power Company Nuclear Generation Group Special Assistant to the Governor 500 Circle Drive Room 1 - State Capitol Buchanan, MI 49107 Lansing, MI 48909 Joseph E. Pollock Plant Manager Indiana Michigan Power Company Nuclear Generation Group One Cook Place Bridgman, MI 49106

INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-315 DONALD C. COOK NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 264 License No. DPR-58

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Indiana Michigan Power Company (the licensee) dated August 7, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-58 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 264, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William D. Reckley, Acting Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 1, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 264 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3/4 0-1 3/4 0-1 B 3/4 0-3 B 3/4 0-3

INDIANA MICHIGAN POWER COMPANY DOCKET NO. 50-316 DONALD C. COOK NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 246 License No. DPR-74

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Indiana Michigan Power Company (the licensee) dated August 7, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-74 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 246, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

William D. Reckley, Acting Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: February 1, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 246 FACILITY OPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

REMOVE INSERT 3/4 0-1 3/4 0-1 B 3/4 0-3 B 3/4 0-3 B 3/4 0-4 B 3/4 0-4

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 264 TO FACILITY OPERATING LICENSE NO. DPR-58 AND AMENDMENT NO. 246 TO FACILITY OPERATING LICENSE NO. DPR-74 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-315 AND 50-316

1.0 INTRODUCTION

By application dated August 7, 2001, the Indiana Michigan Power Company (the licensee) requested amendments to the Technical Specifications (TSs) for the Donald C. Cook Nuclear Plant, Units 1 and 2. The proposed amendments would create TS 3.0.6 and associated bases to allow equipment that was removed from service or declared inoperable to be to returned to service under administrative controls solely to perform the testing required to demonstrate its operability or the operability of other equipment. TS 3.0.6 would incorporate the administrative controls currently set forth as TS 3.0.5 in NUREG-1431, Standard Technical Specifications Westinghouse Plants, Revision 2, dated April 30, 2001. In addition, the amendments make format changes to the TS pages.

2.0 EVALUATION During normal plant operations there are situations when equipment that was declared inoperable must be returned to service to perform post-maintenance testing to demonstrate its operability or the operability of other equipment. This is not allowed by the current TS requirements. As a result, a plant shutdown may be necessary if the required testing cannot be completed in the current mode of plant operation.

The proposed TS establishes an allowance for restoring equipment to service under administrative controls when the equipment has been removed from service or declared inoperable to comply with required TS actions. The purpose of the proposed TS is to provide an exception to TS 3.0.1 and TS 3.0.2 to allow the performance of required testing to demonstrate either:

The operability of the equipment being returned to service; or The operability of other equipment.

Administrative controls, such as test procedures, ensure the time the equipment is returned to service is limited to the time absolutely necessary to perform the required testing to demonstrate operability. This proposed TS does not provide time to perform any other preventive or corrective maintenance.

The proposed changes are consistent with NUREG-1431. The proposed TS would prevent the need for plant shutdowns, and the associated transient conditions that may challenge safety-related systems to complete the required testing. Therefore, the staff finds the proposed addition of TS Section 3.0.6 to the D. C Cook TS is acceptable.

The proposed amendments make three types of format changes to the revised TS pages:

Reformat the header to include numbered first and second tier TS section titles and a full-width single line to separate the header section titles from the page text.

Reformat the footer to include Page (page number) center page, AMENDMENT (past amendment numbers, with strike through, and ending with the current amendment number) on the right side of the page, and a full-width single line to separate the footer from the page text.

The format changes to the TS pages do not change any current TS requirements. The changes provide consistency between units, improve readability, and improve page layout.

Therefore, the staff finds the proposed format changes are acceptable.

3.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Michigan State official was notified of the proposed issuance of the amendments. The State official had no comments.

4.0 ENVIRONMENTAL CONSIDERATION

These amendments change the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration and there has been no public comment on such finding (66 FR 59508). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.

5.0 CONCLUSION

The staff has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John Stang Date: February 1, 2002