ML11102A048

Correction to Amendment No. 257 & 285 (TAC ME3856 & ME3857)

ML11102A048
Person / Time
Site:	Brunswick
Issue date:	04/12/2011
From:	Saba F E Plant Licensing Branch II
To:	Annacone M J Carolina Power & Light Co
Saba F E
References
TAC ME3856, TAC ME3857
Download: ML11102A048 (3)

Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 SUB..BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857)

Dear Mr. Annacone:

By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively.

The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011. The April 8, 2011 letter stated that the NRC staff's safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with the opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments.

Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments.

In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure

3. The corrected page is enclosed.

We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447.

Sincerely, t:-t!;/1 c= Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc w/enclosure:

Distribution via ListServ OFFICIAL USE ONLY PROPRIETARY UNITED NUCLEAR REGULATORY WASHINGTON, D.C.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NOS. 257 AND 285 TO RENEWED FACILITY OPERATING LICENSES NOS. DPR*71 AND DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50*325 AND 50*324

1.0 INTRODUCTION

By application dated April 29. 2010 (Reference 1). as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18. and December 16, 2010, and April 6, 2011 (References 2 through 10, and Reference 39), Carolina Power & Light Company (CP&L, the licensee), requested license amendments to revise the Technical Specifications (TSs) for the Brunswick Steam Electric Plant (BSEP), Units 1 and 2. The proposed license amendments will revise BSEP TS 5.6.5.b by adding the AREVA topical report, ANP-10298PA, "ACE/ATRIUM 10XM Critical Power Correlation," Revision 0, March 2010 (Reference 11), to the list of analytical methods that have been reviewed and approved by the Nuclear Regulatory Commission (NRC) for determining core operating limits. The proposed amendments would change the BSEP TSs to support transition to ATRIUM 10XM fuel and associated core design methodologies.

BSEP Units 1 and 2 are General Electric (GE) boiling water reactors (BWRs) BWR/4 design. Both BSEP units are currently operating at 120 percent of originally licensed thermal power at extended power uprate and maximum extended load line limit analysis conditions.

Each unit reactor core is composed of 560 fuel assemblies.

In each cycle. approximately 40 percent of the irradiated fuel assemblies are replaced with new fuel. On March 27. 2008, the NRC issued Amendments Nos. 246 and 274 for transition from GE fuel to ATRIUM*10 fuel for BSEP Units 1 and 2, respectively (Reference 12). The first transition from GE fuel to ATRIUM*10 fuel occurred in spring 2008 and spring 2009, when the licensee loaded 248 and 238 fresh ATRIUM 10 fuel assemblies in BSEP Units 1 and 2, respectively.

The licensee plans to implement this amendment loading the ATRIUM 10XM fuel design in the BSEP Unit 2 during the spring 2011 refueling outage, beginning with Cycle 20. The BSEP Unit 1 amendment supporting transitioning to ATRIUM 10XM will be implemented during the spring 2012 refueling outage, beginning with Cycle 19. The supplements dated June 9, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011, provided additional information that clarified the application, did not expand the scope of the original Federal Register notice, did not change the OFFICIAL USE ONLY PROPRIETARY INFORMATION Enclosure 3

April 12, 2011 Mr. Michael J. Annacone, Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461 BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 -CORRECTION TO AMENDMENT NOS. 257 AND 285 (TAC NOS. ME3856 AND ME3857)

Dear Mr. Annacone:

By letter dated April 8, 2011, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 257 and 285 to Renewed Facility Operating License Nos. DPR-71 and DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2, respectively.

The amendments were in response to your application dated April 29, 2010, as supplemented by letters dated June 9, July 22, July 29, September 29, October 12, November 9, November 18, and December 16, 2010, and April 6, 2011. The April 8, 2011 letter stated that the NRC staffs safety evaluation (SE) contained proprietary information and, accordingly the NRC staff prepared a redacted, nonproprietary version. The letter also stated that we would delay placing the nonproprietary SE in the public document room for a period of 10 working days from the date of this letter to provide you with opportunity to comment on any proprietary aspects. However, this process is not consistent with the NRC's procedure for issuing amendments.

Also, the draft proprietary SE with markups for proprietary information had been reviewed by your staff for the proprietary information prior to issuance of the amendment.

Therefore, given the aforementioned reasons, the nonproprietary version of the SE was made public upon issuance of the amendments.

In addition, upon issuance of the amendments, the NRC staff noticed that the nonproprietary version of the SE was incorrectly marked as Enclosure 4, instead of Enclosure

3. The corrected page is enclosed.

We regret any inconvenience this may have caused. If you have any questions regarding this matter, please contact me at (301) 415-1447.

Sincerely, IRA! Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324 cc: Distribution via ListServ DISTRIBUTION:

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