BSEP 07-0095, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

ML072620146
Person / Time
Site:	Brunswick
Issue date:	09/11/2007
From:	Ivey R Progress Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BSEP 07-0095
Download: ML072620146 (6)

Text

jProgress Energy 10 CFR 50.46(a)(3)(ii)

SEP 11 2007 SERIAL: BSEP 07-0095 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors

Reference:

Letter from Randy C. Ivey to the U.S. Nuclear Regulatory Commission, "Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors," dated September 28, 2006, ADAMS Accession Number ML062780225 Ladies and Gentlemen:

In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors," paragraph (a)(3)(ii), Carolina Power &

Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., is submitting the annual report of the emergency core cooling system (ECCS) evaluation model changes and errors for the Brunswick Steam Electric Plant (BSEP), Unit Nos. I and 2.

This report covers the period from August 16, 2006, through August 15, 2007. The previous annual report for BSEP, Units 1 and 2, was submitted by CP&L's letter dated September 28, 2006. Since the previous annual report, no error or change notifications have been issued by Global Nuclear Fuels which affect the ECCS evaluation model for BSEP, Units 1 and 2. Therefore, the estimated licensing basis peak cladding temperatures (PCTs) remain unchanged from the values previously reported (i.e., <15670 F for GEl4 fuel).

Progress Energy Carolinas, Inc.

Brunswick Nuclear Plant POBox 10429 Southpoil, NC28461

Document Control Desk BSEP 07-0095 / Page 2 No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Ms. Annette H. Pope, Supervisor - Licensing/Regulatory Programs, at (910) 457-2184.

Sincerely, Randy C. Ivey Manager - Support Services Brunswick Steam Electric Plant WRM/wrm cc: U. S. Nuclear Regulatory Commission, Region II ATTN: Dr. William D. Travers, Regional Administrator Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)

ATTN: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510

Progress Energy 2007 BRUNSWICK ANNUAL 10 CFR 50.46 REPORT Prepared By: David J. Pribyl (NFM&SA)

Date: August 22, 2007 PassPort NTM: 00207790 BNP 10 CFR 50.46 Assessment Period: August 16, 2006 - August 15, 2007 A. Introduction The documentation herein supports compliance to 10 CFR 50.46 (a)(3)(ii) (Reference B.1) requiring licensees of light-water nuclear power reactors to report the nature of a change or the error in an ECCS evaluation model to the Commission at least annually. The purpose of this assessment is to support the 2007 Brunswick Annual 10 CFR 50.46 Report. The requirements of 10 CFR 50.46 with regard to the identification and evaluation of changes to or errors in the LOCA evaluation model are implemented by Progress Energy procedure REG-NGGC-0006 (Reference B.2).

B. References B. 1 Title 10 Code of Federal Regulation 50.46, "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors," June 29, 2007.

B.2 Progress Energy Procedure REG-NGGC-0006, "Identification of Changes to (or Errors in) LOCA Evaluation Models or Applications According to 10 CFR 50.46," Revision 2.

B.3 Email Correspondence from Mark Mneimneh (GNF) to Eric Geyer (PGN), "RE: 10 CFR 50.46 Notification - 2007 - Brunswick," August 21, 2007 (Attachment 1).

B.4 PassPort Condition Report 00168654, "2006 Annual 10 CFR 50.46 Report."

B.5 Brunswick Design Calculation 0B21-0112, "IOCFR50.46 SAFER/GESTR-LOCA ECCS Analysis Update," Revision 12, January 25, 2007.

C. Summary As reported by GNF in Reference B.3 (Attachment 1), there have been no additional notices for Brunswick since 2006-01. Notice 2006-001 was addressed in the 2006 Brunswick Annual 10 CFR 50.46 Report (Reference B.4). Therefore, there are no changes to (or errors in) the Brunswick LOCA evaluation model to record for the Brunswick 2007 10 CFR 50.46 assessment period. The assessment of the Brunswick LOCA evaluation model in Reference B.5 remains valid.

Page 1 of 4

. Progress Energy Tables 1, 2, and 3 (below) summarize the current LOCA evaluation results as documented in Reference B.5.

1Table 1 BNP SAFER/GESTR-LOCA ECCS Analysis Change/Error Summary Estimated BNP Cumulative BNP Change Notice Period Change or GE BWR Licensing PCT Licensing PCT Is BNP Licensing PCT or Error or Covered Error Estimated Impact and Change Change Greater than 50°F?

Notice Docu- Description Licensing Estimated PCT Incremental Cumulative ment PCT Impact (GEl4)

Date NA NA Through NA NA NA NA NA NA 8/15/07 Table 2 BNP Licensing PCT Change Summary Through 8/15/07*

Fuel Type Most Recent Licensing (most recent LOCA PCT Reported in a Current Estimated Change from reported analysis Licensing PCT) LOCA Document Licensing PCT Licensing PCT Submitted to the NRC (Analysis or Notice)

GE14 <1567°F <1567'F 0°F Table 3 BNP Upper Bound PCT Change Summary Through 8/15/07*

Upper Bound PCT Fuel Type Corresponding to Current Estimated Change from Previous (most recent LOCA Table 2 Most Recent Upper Bound PCT Upper Bound PCT analysis Upper Bound Submitted to the NRC PCT)

GE14 < 1497'F <1497°F 0°F

• BNP LOCA Results presented for Unit 2, which bounds Unit 1.

Page 2 of 4

Progress Energy ATTACHMENT 1 From: Mneimneh, Mark (GNF) [Mark.Mneimneh@gnf.com]

Sent: Tuesday, August 21, 2007 3:37 PM To: Geyer, Eric; Pribyl, David

Subject:

RE: 10 CFR 50.46 Notification - 2007 - Brunswick Eric, Dave;*

There have been no additional notices for Brunswick since 2006-01.

Annual notifications letters have not been sent since 2001. In the past these letters were sent to NRC and then sent to each customer as an attachment. At some point, GE realized that utilities, as the owner of plant configuration, are the right entities to send the annual notification to NRC.

The SRLR is now used as the means to summarize the 50.46 errors. We have been sending emails to customers (on request, similar to this) with the list of errors since their last SRLR.

Thanks Mark From: Geyer, Eric pqnmail.com

Sent: Monday, August 20, 2007 5:13 PM To: Mneimneh, Mark (GNF)

Cc: Lingenfelter, Andy (GNF); Pribyl, David

Subject:

FW: 10 CFR 50.46 Notification - 2007 - Brunswick

Mark, Is an annual reporting letter pending? Or no news is good news?

Last notice we received (attached) was 7/28/06.

Thanks, Eric

<<20060728 10 CFR50-46 Notification 2006-01 Brunswick GNF Email Attachment.pdf>>

<<20060728 10 CFR50-46 Notification 2006-01 Brunswick GNF Email.pdf>>

Original-----

Message -----

From: Pribyl, David Sent: Monday, August 20, 2007 1:41 PM To: Geyer, Eric

Subject:

10 CFR 50.46 Notification - 2007 - Brunswick

Eric, Has GNF transmitted the 50.46 notification for Brunswick? Can I get a copy?

Page 3 of 4

Progress Energy I need to start preparing the Brunswick transmittal soon.

Thanks ... David David Pribyl Progress Energy - Carolinas BWR Fuels Engineer 410 S. Wilmington St., PEB06 Raleigh, NC 27601 T > 919.546.2516 F > 919.546.4361 C > 919.539.0009 E > david.pribyl@pgnmail.com Page 4 of 4