ML023370093

License Amendment Nos. 207 and 212, Increase the Licensed Reactor Core Power Level

ML023370093
Person / Time
Site:	Point Beach
Issue date:	11/29/2002
From:	Spaulding D NRC/NRR/DLPM/LPD3
To:	Cayia F Nuclear Management Co
Shared Package
ML023370460	List: ML023370093
References
TAC MB4956, TAC MB4957
Download: ML023370093 (9)

Text

November 29, 2002 Mr. Fred J. Cayia Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE (TAC NOS. MB4956 AND MB4957)

Dear Mr. Cayia:

The Commission has issued the enclosed Amendment No. 207 to Facility Operating License No. DPR-24 and Amendment No. 212 to Facility Operating License No. DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Operating Licenses and Technical Specifications (TSs) in response to your application dated April 30, 2002, as supplemented by letters dated June 26, August 29, October 3, October 23, and November 11, 2002.

These amendments increase the licensed reactor core power level by 1.4 percent from 1518.5 megawatts thermal (MWt) to 1540 MWt.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Deirdre W. Spaulding, Project Manager, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301

Enclosures:

1. Amendment No. 207 to DPR-24

2. Amendment No. 212 to DPR-27

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

cc w/encls: See next page Letter: ML023370093 TS pages: ML023370460 DISTRIBUTION Safe Evaluation: ML023370133 PUBLIC OGC SPeters Package: ML023370142 PDIII-1 Reading ACRS CWu JZwolinski MMitchell ZFu KMcConnell KParczewski MHart LRaghavan WBeckner HGarg DSpaulding GHill(4) NTrehan RBouling GGeorgiev RLanksbury, RGN-III

• • No legal objection with comments OFFICE PDIII-1/PM PDIII-1/LA OGC/NLO** PDIII-1/SC PDIII/D DLPM/D NAME DSpaulding RBouling RWeisman KMcConnell for KMcConnell KMcConnell LRaghavan for JZwolinski DATE 11/18/02 11/18/02 11/27/02 11/29/02 11/29/02 11/29/02 The following technical branches provided safety evaluation input by memos dated*

OFFICE SRXB EEIB EEIB EMCB EMCB NAME FAkstulewicz EMarinos CHolden ALund SCoffin DATE* 10/31/02 9/19/02 7/23/02 9/24/02 10/4/02 OFFICE EMEB SPSB NAME KManoly FReinhart DATE* 9/27/02 7/16/02

Point Beach Nuclear Plant, Units 1 and 2 cc:

Mr. John H. ONeill, Jr. Ms. Sarah Jenkins Shaw, Pittman, Potts & Trowbridge Electric Division 2300 N Street, NW Public Service Commission of Wisconsin Washington, DC 20037-1128 P.O. Box 7854 Madison, WI 53707-7854 Mr. Richard R. Grigg President and Chief Operating Officer Mr. Roy A. Anderson Wisconsin Electric Power Company Executive Vice President and 231 West Michigan Street Chief Nuclear Officer Milwaukee, WI 53201 Nuclear Management Company, LLC 700 First Street Site Licensing Manager Hudson, WI 54016 Point Beach Nuclear Plant Nuclear Management Company, LLC Nuclear Asset Manager 6610 Nuclear Road Wisconsin Electric Power Company Two Rivers, WI 54241 231 West Michigan Street Milwaukee, WI 53201 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, WI 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4351 Resident Inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 October 2002

NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 207 License No. DPR-24

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

A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated April 30, 2002, as supplemented by letters dated June 26, August 29, October 3, October 23, and November 11, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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 3.B of Facility Operating License No. DPR-24 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 207, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

In addition, the license is amended to revise paragraph 3.A to reflect the increase in the reactor core power level. Paragraph 3.A is hereby amended to read as follows:

A. NMC is authorized to operate the facility at reactor core power levels not in excess of 1540 megawatts thermal.

3. This license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance. Implementation of this amendment shall include documentation of a formal engineering evaluation of the effects of the power uprate on the Final Safety Analysis Report 14.2.3 accidents, as described in the licensees April 30, 2002, application, and evaluated in the associated safety evaluation by the Office of Nuclear Reactor Regulation, dated November 29, 2002. The engineering evaluation shall be reflected in the next update of the FSAR submitted to the NRC pursuant to 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by Keith I. McConnell for/

Ledyard B. Marsh, Acting Director Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of issuance: November 29, 2002

NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. DPR-27

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

A. The application for amendment by Nuclear Management Company, LLC (the licensee), dated April 30, 2002, as supplemented by letters dated June 26, August 29, October 3, October 23, and November 11, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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 3.B of Facility Operating License No. DPR-27 is hereby amended to read as follows:

B. Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 212, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

In addition, the license is amended to revise paragraph 3.A to reflect the increase in the reactor core power level. Paragraph 3.A is hereby amended to read as follows:

A. NMC is authorized to operate the facility at reactor core power levels not in excess of 1540 megawatts thermal.

3. This license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance. Implementation of this amendment shall include documentation of a formal engineering evaluation of the effects of the power uprate on the Final Safety Analysis Report 14.2.3 accidents, as described in the licensees April 30, 2002, application, and evaluated in the associated safety evaluation by the Office of Nuclear Reactor Regulation, dated November 29, 2002. The engineering evaluation shall be reflected in the next update of the FSAR submitted to the NRC pursuant to 10 CFR 50.71(e).

FOR THE NUCLEAR REGULATORY COMMISSION

/RA by Keith I. McConnell for/

Ledyard B. Marsh, Acting Director Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Operating License and Technical Specifications Date of issuance: November 29, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 207 TO FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO. 212 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following page of Facility Operating License No. DPR-24 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 3 Replace the following page of Facility Operating License No. DPR-27 with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 2 2 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The pages are identified by amendment numbers.

REMOVE INSERT 1.1-5 1.1-5 5.6-3 5.6-3 5.6-4 5.6-4 5.6-5 5.6-5 5.6-6 5.6-6