ML032801628

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License Amendment, Re Allowed Outage Time for the Control Room Emergency Filtration System from 7 Days to 30 Days
ML032801628
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 10/16/2003
From: Spaulding D
NRC/NRR/DLPM/LPD3
To: Cayia A
Nuclear Management Co
References
TAC MB7023, TAC MB7024
Download: ML032801628 (9)


Text

October 16, 2003 Mr. Alfred J. Cayia Site Vice President Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241-9516

SUBJECT:

POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: DELETION OF THE ONE-TIME EXTENSION OF THE ALLOWED OUTAGE TIME FOR THE CONTROL ROOM EMERGENCY FILTRATION SYSTEM FROM 7 DAYS TO 30 DAYS (TAC NOS. MB7023 AND MB7024)

Dear Mr. Cayia:

The Commission has issued the enclosed Amendment No. 210 to Facility Operating License No. DPR-24 and Amendment No. 215 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 Technical Specifications (TSs) in response to your application dated October 17, 2002.

The amendments revise TS 3.7.9, Control Room Emergency Filtration System (CREFS), by deleting the one-time extension to the allowed outage time (AOT) for CREFS and the exception requirements of Limiting Condition for Operation 3.04 and Surveillance Requirement 3.04 that were allowed during the AOT.

A copy of our related safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's 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. 210 to DPR-24
2. Amendment No. 215 to DPR-27
3. Safety Evaluation cc w/encls: See next page

ML032801628

Point Beach Nuclear Plant, Units 1 and 2 cc:

Jonathan Rogoff, Esquire Vice President, Counsel & Secretary Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 Mr. Richard R. Grigg President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 Manager, Regulatory Affairs Point Beach Nuclear Plant Nuclear Management Company, LLC 6610 Nuclear Road Two Rivers, WI 54241 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 Inspectors Office U.S. Nuclear Regulatory Commission 6612 Nuclear Road Two Rivers, WI 54241 Ms. Sarah Jenkins Electric Division Public Service Commission of Wisconsin P.O. Box 7854 Madison, WI 53707-7854 Nuclear Asset Manager Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201 John Paul Cowan Executive Vice President & Chief Nuclear Officer Nuclear Management Company, LLC 700 First Street Hudson, WI 54016 October 2003

NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-266 POINT BEACH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 210 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 October 17, 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. 210, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

L. Raghavan, 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: October 16, 2003

NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 215 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 October 17, 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. 215, are hereby incorporated in the license. The licensee shall operate the facility in accordance with Technical Specifications.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

L. Raghavan, 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: October 16, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 210 TO FACILITY OPERATING LICENSE NO. DPR-24 AND LICENSE AMENDMENT NO. 215 TO FACILITY OPERATING LICENSE NO. DPR-27 DOCKET NOS. 50-266 AND 50-301 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3.7.9-1 3.7.9-1

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 210 TO FACILITY OPERATING LICENSE NO. DPR-24 AND AMENDMENT NO. 215 TO FACILITY OPERATING LICENSE NO. DPR-27 NUCLEAR MANAGEMENT COMPANY, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-266 AND 50-301

1.0 INTRODUCTION

By application dated October 17, 2002, the Nuclear Management Company, LLC (the licensee),

requested changes to the Technical Specifications (TSs) for the Point Beach Nuclear Plant, Units 1 and 2 (PBNP). The proposed changes would delete the one-time extension of the allowed outage time (AOT) for the control room emergency filtration system (CREFS) from 7 days to 30 days. Specifically, the proposed change to TS 3.7.9 would delete the note for the 7-day completion time for Required Action A.1, which extended this completion time to 30 days, on a one-time basis, for performance of CREFS modifications/upgrades. The note also included an exception to the requirements of Limiting Condition for Operation (LCO) 3.0.4 and Surveillance Requirement (SR) 3.0.4 during the extended AOT. The note currently reads as follows:

  • The Completion Time of Required Action A.1 may be extended up to 30 days, on a one-time basis to implement modifications/upgrades to the CREFS. The provisions of LCO 3.0.4 and SR 3.0.4 are not applicable during the modifications/upgrades to the CREFS that require use of the extended Completion Time.

The associated asterisk would also be deleted.

2.0 EVALUATION The licensee recently performed modifications/upgrades of the control room envelope to enhance control room habitability at PBNP, Units 1 and 2. In order to permit installation of certain portions of the upgraded design on the system, it was necessary that the CREFS be declared inoperable. This required entry into the applicable action statement of TS 3.7.9.

However, installation of portions of the modifications/upgrades were expected to take longer than the 7 days normally allowed by TS 3.7.9. To preclude an unnecessary dual-unit shutdown during installation of the safety enhancing upgrades, a one-time extension of the 7-day AOT for CREFS to 30 days was required. Additionally, to facilitate restart of either unit during the CREFS outage, exceptions to the requirements of LCO 3.0.4 and SR 3.0.4 were also required.

By PBNP License Amendment Nos. 203 and 208, dated March 29, 2002, the NRC approved a one-time extension to the CREFS AOT and an exception to the requirements of LCO 3.0.4 and SR 3.0.4 during the extended AOT for the CREFS. The licensee used this one-time extension of the CREFS AOT during July 2002 for installation of the control room envelope pressure boundary modifications/upgrades.

The one-time allowance in TS 3.7.9, which extended the 7-day AOT to 30 days, existed only for the purpose of supporting the planned CREFS modifications/upgrades. This one-time allowance did not affect the existing 7-day AOT of TS 3.7.9 in the event that CREFS was determined to be inoperable for any other reason.

Upon completion of the CREFS modifications and upgrades, this one-time allowance in TS 3.7.9, may no longer be used and the associated note no longer applies. The proposed amendment would return TS 3.7.9 to the condition in which it existed prior to the addition of the note. The version of TS 3.7.9 that existed prior to PBNP License Amendment Nos. 203 and 208 is documented in PBNP License Amendment Nos. 201 and 206, dated August 8, 2001.

In conclusion, the NRC staff finds the licensees proposed TS change to delete the one-time extension to the CREFS AOT and the exception to the requirements of LCO 3.0.4 and SR 3.0.4 during the extended AOT to be consistent with the previously approved TS requirements, and therefore, is acceptable.

3.0 STATE CONSULTATION

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

4.0 ENVIRONMENTAL CONSIDERATION

These amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 or change a surveillance requirement. The staff has determined that the amendments involve 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 published a proposed finding that these amendments involve no significant hazards consideration and there has been no public comment on such finding (68 FR 7818). Accordingly, these 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 these amendments.

5.0 CONCLUSION

The Commission 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: D. Spaulding Date: October 16, 2003