ML063180036

License Amendment 189 Regarding Referencing the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for Operation and Maintenance of Nuclear Power Plants

ML063180036
Person / Time
Site:	Kewaunee
Issue date:	12/14/2006
From:	Raghavan L NRC/NRR/ADRO/DORL/LPLIII-1
To:	Christian D Dominion, Dominion Energy Kewaunee
R. Ennis
References
TAC MD3055
Download: ML063180036 (10)

Text

December 14, 2006 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

KEWAUNEE POWER STATION - ISSUANCE OF AMENDMENT RE:

REFERENCING THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS BOILER AND PRESSURE VESSEL CODE FOR OPERATION AND MAINTENANCE OF NUCLEAR POWER PLANTS (TAC NO. MD3055)

Dear Mr. Christian:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 189 to Facility Operating License No. DPR-43 for the Kewaunee Power Station. This amendment revises the Technical Specifications (TSs) in response to your application dated September 25, 2006.

The amendment revises TS 4.2.a, "ASME [American Society of Mechanical Engineers] Code Class 1, 2, 3, and MC Components and Supports. The revised TS 4.2.a.2, references the ASME Code for Operation and Maintenance of Nuclear Power Plants.

A copy of the Safety Evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.

Sincerely,

/RA/

L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-305

Enclosures:

1. Amendment No. 189 to License No. DPR-43

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

ML063180036 Pkg: ML063180030 TS: ML063540151 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/CPTB/BC OGC NRR/LPL3-1/BC NAME DJaffe THarris SLee JRund LRaghavan DATE 11/20/06 12/14/06 11/20/06 12/07/06 12/14/06 Kewaunee Power Station cc:

Resident Inspectors Office Ms. Lillian M. Cuoco, Esq.

U.S. Nuclear Regulatory Commission Senior Counsel N490 Hwy 42 Dominion Resources Services, Inc.

Kewaunee, WI 54216-9510 Millstone Power Station Building 475, 5th Floor Regional Administrator, Region III Rope Ferry Road U.S. Nuclear Regulatory Commission Waterford, CT 06385 Suite 210 2443 Warrenville Road Lisle, IL 60532-4351 Ms. Leslie N. Hartz Dominion Energy Kewaunee, Inc.

Kewaunee Power Station N 490 Highway 42 Kewaunee, WI 54216 Mr. Chris L. Funderburk Director, Nuclear Licensing and Operations Support Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Thomas L. Breene Dominon Energy Kewaunee, Inc.

Kewaunee Power Station N490 Highway 42 Kewaunee, WI 54216

DOMINION ENERGY KEWAUNEE, INC.

DOCKET NO. 50-305 KEWAUNEE POWER STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 189 License No. DPR-43

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

A. The application for amendment by Dominion Energy Kewaunee, Inc. dated September 25, 2006, 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-43 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 189, are hereby incorporated in the license. The licensees 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 60 days of the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

L. Raghavan, Chief Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Facility Operating License and Technical Specifications Date of Issuance: December 14, 2006

ATTACHMENT TO LICENSE AMENDMENT NO. 189 FACILITY OPERATING LICENSE NO. DPR-43 DOCKET NO. 50-305 Replace the following page of the Facility Operating License No. DPR-43 with the attached revised page. The changed area is identified by a marginal line.

REMOVE INSERT Page 3 Page 3 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 4.2-1 4.2-1

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR, Chapter 1: (1) Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70, (2) is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect, and (3) is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 1772 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 189, are hereby incorporated in the license. The licensee shall operate the facility In accordance with the Technical Specifications.

(3) Fire Protection The licensee shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the licensee's Fire Plan, and as referenced in the Updated Safety Analysis Report, and as approved in the Safety Evaluation Reports, dated November 25, 1977, and December 12, 1978 (and supplement dated February 13, 1981) subject to the following provision:

The licensee may make changes to the approved Fire Protection Program without prior approval of the Commission, only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

(4) Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: Nuclear Management Company Kewaunee Nuclear Power Plant Physical Security Plan (Revision 0)" submitted by letter dated October 18, as supplemented by letter dated October 21, 2004.

(5) Fuel Burnup The maximum rod average burnup for any rod shall be limited to 60 GWD/MTU until completion of an NRC environmental assessment supporting an increased limit.

Amendment No. 189 3

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO AMENDMENT NO. 189 TO FACILITY OPERATING LICENSE NO. DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION DOCKET NO. 50-305

1.0 INTRODUCTION

By application for license amendment dated September 25, 2006, Dominion Energy Kewaunee, Inc. (the licensee) requested a change to the Technical Specifications (TSs) for Kewaunee Power Station (KPS). The amendment revises TS 4.2.a, "ASME [American Society of Mechanical Engineers] Code Class 1, 2, 3, and MC Components and Supports. The revised TS 4.2.a.2, would reference the American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants.

2.0 REGULATORY EVALUATION

Section 182a of the Atomic Energy Act requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The U.S. Nuclear Regulatory Commissions (NRC's) regulatory requirements related to the content of the TSs are contained in Section 50.36 of Title 10 of the Code of Federal Regulations (10 CFR 50.36) which requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements (per Section 50.36(c)(3));

(4) design features; and (5) administrative controls. In accordance with 10 CFR 50.36(c)(3),

surveillance requirements are requirements related to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met.

The NRC regulation at 10 CFR Part 50, Section 50.55a, defines the requirements for applying industry codes to each licensed nuclear powered facility. Licensees are required by 10 CFR 50.55a(f)(4)(i) to prepare programs to perform in-service testing of certain ASME Code Class 1, 2, and 3 pumps and valves during the initial 120-month interval. The regulations require that programs be developed using the latest edition and addenda incorporated into paragraph (b) of 10 CFR 50.55a on the date 12 months prior to the date of issuance of the operating license subject to the limitations and modification identified in paragraph (b). NRC regulations also require that the in-service testing programs be revised during successive 120-month intervals to comply with the latest edition and addenda of the Code incorporated by reference in paragraph (b) 12 months prior to the start of the interval. NRC amended 10 CFR 50.55a(f)(4)(ii) to require licensees to update their inservice test (IST) programs to the latest edition of the ASME Code

for Operation and Maintenance of Nuclear Power Plants (OM Code), which was incorporated by reference into 10 CFR 50.55a(b). The final rule was published in the Federal Register on September 22, 1999 (64 FR 51370).

Section XI of the ASME Code has been revised on a continuing basis over the years to provide updated requirements for the in-service inspection and in-service testing of components. The ASME Code requirements addressing the in-service testing of pumps and valves were contained in Section Xl, Subsections IWP (pumps) and IWV (valves). In the 1998 Edition with the 2000 Addenda, all requirements for testing pumps and valves were removed from Section XI and re-located in the ASME Code for Operation and Maintenance of Nuclear Power Plants.

As identified in NRC SECY-99-017, dated January 13, 1999, the NRC has generally considered the evolution of the ASME Code to result in a net improvement in the measures for inspecting piping and components and testing pumps and valves.

3.0 EVALUATION

3.1 Background

The current TS 4.2.a.2 addresses the IST program and referencesSection XI of the ASME Boiler and Pressure Vessel Code as the source of the IST program requirements for ASME Code Class 1, 2, and 3 components whereas, by the rule change, the reference should be to the ASME OM Code. NRC amended 10 CFR 50.55a(f)(4)(ii) to require licensees to update their IST programs to the latest edition of the ASME OM Code, which was incorporated by reference into 10 CFR 50.55a(b). The licensee stated that the proposed changes are necessary for TS 4.2.a.2 to be consistent with the IST requirements of 10 CFR 50.55a.

3.2 Evaluation of Proposed TS Changes The licensees proposed TS revision would adopt the administrative, editorial, and clarification TS changes contained in Technical Specification Task Force (TSTF)-479, Revision 0, Changes to Reflect Revision of 10 CFR 50.55a. TSTF-479 revised the Standard Technical Specifications (STS) by adopting the American Society of Mechanical Engineers Code and certain associated frequencies for IST activities consistent with the requirements of 10 CFR 50.55a (i.e., adopting the ASME OM Code). Since KPS has custom (non-Standard Technical Specifications), the changes associated with TSTF-479, proposed by the licensee, are limited to the referencing of the OM Code in TS 4.2.a.2.

TSTF-479 updates references to Section XI of the ASME Boiler and Pressure Vessel Code to the ASME OM Code, which is consistent with the requirements of 10 CFR 50.55a.

3.3 Conclusion Based on its review of the proposed amendment, the NRC staff concludes that the licensees proposed change to KPS TS 4.2.a.2 is acceptable since it does not otherwise change the TS requirements and conforms to the requirements of 10 CFR 50.55a. Based on this, the NRC staff also concludes that the proposed changes meet 10 CFR 50.36. On this basis, the NRC staff concludes that the proposed change to TS 4.2.a.2 is acceptable.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

This amendment changes a requirement 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 amendment involves no significant increase in the amounts, and no significant change in the types, of any effluent 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 62308). Accordingly, this 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 this amendment.

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

Principal Contributor: D. Jaffe Date: December 14, 2006