ML013470142

Issuance of Amendment, Revises the Action Statements for TS 3.3.3.5 to Add a Statement That the Provisions of TS 3.0.4 Are Not Applicable

ML013470142
Person / Time
Site:	Cook
Issue date:	01/16/2002
From:	Stang J NRC/NRR/DLPM/LPD3
To:	Bakken A Indiana Michigan Power Co
Stang, JF, NRR/DLPM/LPD III-1, 415-1345
References
TAC MB3500
Download: ML013470142 (9)

Text

January 16, 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, UNIT 1 - ISSUANCE OF AMENDMENT (TAC NO. MB3500)

Dear Mr. Bakken:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 262 to Facility Operating License No. DPR-58 for the Donald C. Cook Nuclear Plant, Unit 1. The amendment consists of changes to the Technical Specifications (TS) in response to your application dated November 19, 2001.

The amendment would revise the action statements for TS 3.3.3.5, Remote Shutdown Instrumentation, to add a statement that the provisions of TS 3.0.4 are not applicable.

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 No. 50-315

Enclosures:

1. Amendment No. 262 to DPR-58

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

ML013470142 OFFICE PM:PD3-1 LA:PD3-1 BC:RTSB OGC (A)SC:PD3-1 NAME JStang THarris WBeckner RHoefling WReckley DATE 12/10/01 12/18/01 01/04/02 12/26/01 01/14/02 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. 262 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 November 19, 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 (TS) 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 TS contained in Appendices A and B, as revised through Amendment No.

are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TS.

3. This license amendment is effective as of its date of issuance and shall be implemented within 45 days.

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: January 16, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 262 TO FACILITY OPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Replace the following page of the Appendix A Technical Specifications (TS) with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3/4 3-46 3/4 3-46

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 262 TO FACILITY OPERATING LICENSE NO. DPR-58 INDIANA MICHIGAN POWER COMPANY DONALD C. COOK NUCLEAR PLANT, UNIT 1 DOCKET NO. 50-315

1.0 INTRODUCTION

By application dated November 19, 2001, the Indiana Michigan Power Company (the licensee) requested an amendment to the Technical Specifications (TSs) for the Donald C. Cook Nuclear Plant, Unit 1. The proposed amendment would revise the action statements for TS 3.3.3.5, Remote Shutdown Instrumentation, to add a statement that the provisions of TS 3.0.4 are not applicable. The proposed change is requested to allow Unit 1 to enter Mode 3 without having met the Limiting Conditions for Operation for TS 3.3.3.5. This is necessary because the TS required monthly channel check for the pressurizer pressure instrumentation, which has a range of 1,700 to 2,500 pounds per square inch gauge (psig), cannot be performed until pressurizer pressure reaches 1,700 psig. Operation below Mode 3 with pressure at or above 1,700 psig is prohibited by the current operational limitations on primary-to-secondary steam generator tube differential pressure.

2.0 EVALUATION The proposed amendment will eliminate restrictions imposed by TS 3.0.4 for the Remote Shutdown Instrumentation. Specifically, the proposed change will allow Unit 1 to enter Mode 3 without having met the limiting condition for operation (LCO) for TS 3.3.3.5. This is necessary because the TS required monthly channel check for the pressurizer pressure instrumentation, which has a range of 1,700 to 2,500 psig, cannot be performed until pressurizer pressure reaches 1,700 psig. Operation below Mode 3 with pressure at or above 1,700 psig is prohibited by the current operational limitations on primary-to-secondary steam generator tube differential pressure.

TS 3.3.3.5 for the Remote Shutdown Instrumentation is applicable in Modes 1, 2 and 3, so that the plant can be placed and maintained in a safe shutdown condition for an extended period of time from a location other than the control room. TS 3.3.3.5 is not applicable in Modes 4, 5, or 6, because in these modes, the plant is already subcritical and in a condition of reduced reactor coolant system energy. Under these conditions, considerable time is available to restore necessary instrument control functions if the control room instruments or controls become unavailable.

The proposed change to the Unit 1 TS 3.3.3.5 will allow the plant to enter into an applicable mode of operation while relying on the TS action statements. The Remote Shutdown

Instrumentation system ensures that sufficient capability is available to permit shutdown and maintenance of Hot Standby of the plant from locations outside of the control room. The proposed change allows Unit 1 to ascend in mode without meeting the LCO for TS 3.3.3.5. The proposed change does not impact the ability to comply with the allowed outage time (AOT) described in TS 3.3.3.5. As such, the proposed change does not affect any accident initiators or precursors, since the AOT for TS 3.3.3.5 will continue to be met. The proposed change is also consistent with the Unit 2 TS and NUREG-1431, Standard Technical Specifications, Westinghouse Plants, Revision 2, dated April 30, 2001.

The proposed change does not impact the Remote Shutdown Instrumentation systems capability of performing its design function, nor does the proposed change impact the operational characteristics of the Remote Shutdown Instrumentation system. The Remote Shutdown Instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of Hot Standby of the plant from locations outside of the control room. Allowing Unit 1 to ascend in mode without meeting the LCO for TS 3.3.3.5, while continuing to meet the action statement, does not impact Cook Nuclear Plants accident analysis. The proposed change does not involve a reduction in the margin of safety.

Based on the above, the staff finds the proposed change to the TS to be acceptable due to the limitations on the required equipment and ability to meet the action statements for TS 3.3.3.5.

3.0 STATE CONSULTATION

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

4.0 ENVIRONMENTAL CONSIDERATION

The amendment changes the requirements with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change the surveillance requirements. The staff has determined that the amendment involves 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 amendment involves no significant hazards consideration and there has been no public comment on such finding (66 FR 64295). Accordingly, the amendment meets 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 amendment.

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 amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: John Stang Date: January 16, 2002