ML023530500

License Amendment No.251, Delete Requirement to Include Check Valve MVD-V5008 in Facility Check Valve Program

ML023530500
Person / Time
Site:	Brunswick
Issue date:	12/13/2002
From:	Mozafari B NRC/NRR/DLPM/LPD2
To:	Keenan J Carolina Power & Light Co
Olshan L N, NRR/DLPM, 415-1419
References
TAC MB6372
Download: ML023530500 (10)

Text

December 13, 2002 Mr. J. S. Keenan Vice President Carolina Power & Light Company Brunswick Steam Electric Plant Post Office Box 10429 Southport, North Carolina 28461

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 - ISSUANCE OF AMENDMENT NO. 251 TO FACILITY OPERATING LICENSE NO. DPR-62 RE:

FACILITY CHECK VALVE PROGRAM (TAC NO. MB6372)

Dear Mr. Keenan:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 251 to Facility Operating License No. DPR-62 for the Brunswick Steam Electric Plant, Unit 2. The amendment is in response to your application dated September 16, 2002.

The amendment revises a license condition by deleting the requirement to include check valve MVD-V5008 in the facility check valve program.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commission's bi-Weekly Federal Register Notice.

Sincerely,

/RA by L. Olshan for/

Brenda L. Mozafari, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-324

Enclosures:

1. Amendment No. 251 to License No. DPR-62

2. Safety Evaluation cc w/enclosures:

See next page

ML023530500 OFFICE PM:PDII/S2 LA:PDII/S2 SC:SPSB SC:PDII/S2 OGC NAME LOlshan for Dunnington MReinhart AHowe SUttal (NLO)

BMozafari 11/07/0 11/07/02 11/12/02 12/10/02 12/13/02 2

COPY Yes/No Yes/No Yes/No Yes/No AMENDMENT NO. 251 TO FACILITY OPERATING LICENSE NO. DPR BRUNSWICK, UNIT 2 DISTRIBUTION:

PUBLIC PD II-2 Rdg.

OGC G. Hill (2)

R. Dennig ACRS P. Fredrickson, RII L. Olshan M. Reinhart cc: Brunswick Service List

CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 251 License No. DPR-62

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

A. The application for amendment filed by Carolina Power & Light Company (the licensee), dated September 16, 2002 , 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 Appendix B, Additional Conditions, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 251, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.

3. Also, paragraph 3 of the license is hereby amended to read as follows:

3. Additional Conditions The Additional Conditions contained in Appendix B, as revised through Amendment No. 251, are hereby incorporated into this license. Carolina Power & Light Company shall operate the facility in accordance with the Additional Conditions.

4. This license amendment is effective as of the date of its issuance and shall be implemented within 90 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Allen G. Howe, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 13, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 251 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following page of Appendix B, Additional Conditions, with the attached revised page. The revised page is identified by amendment number and contains a marginal line indicating the area of change.

Remove Page Insert Page 1 1

APPENDIX B Additional Conditions Amendment Number Additional Conditions Implementation Date 233 The licensee is authorized to relocate certain This amendment is requirements included in Appendix A and the effective immediately former Appendix B to licensee-controlled and shall be documents. Implementation of this amendment implemented within shall include the relocation of these requirements 90 days of the date to the appropriate documents, as described in the of this amendment.

licensees letters dated November 1, 1996, October 13, 1997, February 26, 1998, April 24, 1998, and May 22, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.

233 The End-Of-Cycle Recirculation Pump Trip system This amendment is instrumentation shall be maintained inoperable effective immediately (i.e. manually bypassed) during Mode 1, when and shall be thermal power is greater than or equal to 30% implemented within rated thermal power. Implementation of this 90 days of the date of amendment shall include this condition, as this amendment.

described in the licensees letter dated March 13, 1998, evaluated in the NRC staffs Safety Evaluation enclosed with this amendment.

246 The licensee shall, consistent with the applicable Prior to startup following the provisions of the BWR Owners Group Report Unit 2 Cycle 16 Refueling NEDC-31858P, Revision 2, as approved in the Outage.

NRC staffs Safety Evaluation dated March 3, 1999, complete the seismic verification walkdowns and modifications necessary to ensure seismic ruggedness of the alternate leakage treatment (ALT) piping and appendages.

246 The licensee shall, consistent with the licensees Prior to startup following the letter dated September 27, 2001 (i.e., Serial: Unit 2 Cycle 16 Refueling BSEP 01-0112), include ALT path motor-operated Outage.

valves MS-F038A, MS-F038B, MS-F038C, MS-F038D, and MVD-F021 in an augmented inservice testing program.

251 The licensee shall include ALT path check valve Prior to startup following the MVD-V5009 in the facility check valve program. Unit 2 Cycle 16 Refueling Outage.

Amendment No. 251

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 251 FOR FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 DOCKET NO. 50-324

1.0 INTRODUCTION

By letter dated September 16, 2002, the Carolina Power & Light Company (the licensee) submitted a request for license amendment for the Brunswick Steam Electric Plant, Unit 2.

The requested change would revise a license condition to delete the requirement to include check valve MVD-V5008 in the facility check valve program.

2.0 REGULATORY EVALUATION

In Section 6.5 of Appendix A to Regulatory Guide (RG) 1.183, Alternate Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, it states A reduction in MSIV [main steamline isolation valve] releases that is due to holdup and deposition in main steam piping downstream of the MSIVs and in the main condenser, including the treatment of air ejector effluent by offgas systems, may be credited if the components and piping systems used in the release path are capable of performing their safety function during and following a safe shutdown earthquake (SSE). As part of the actions to satisfy this requirement, a license condition was added with the issuance of Amendment No. 246. The license condition required that check valves MVD-V5008 and MVD-5009 be included in the facility check valve program.

3.0 TECHNICAL EVALUATION

Amendment No. 246, issued May 30, 2002, revised the Technical Specifications to accommodate use of an alternate source term. The staffs Safety Evaluation supporting the amendment approved the use of an alternate means for main MSIV leakage treatment provided that the main steam piping and components that comprise the alternate means are seismically rugged (see Section 2.0 above) and are able to perform the safety function of an MSIV leakage treatment system. To limit the extent of the piping that had to be seismically rugged, the licensee committed to install a check valve on each of the two lines connecting to the main steam drains header that leads to the condenser. These check valves are identified as MVD-V5008 and MVD-V5009.

Subsequent to the issuance of the amendment, the licensee noted that the design of Units 1 and 2 were different with respect to the MSIV drain piping. On Unit 2, one of these two lines ties into a drain line from the steam bypass chest. This line is required to be seismically verified, so there is no benefit to installing a check valve (MVD-V5008) that would limit the

extent of piping that has to be seismically rugged. Thus, the proposed license condition deletes the requirement to include MVD-V5008 in the facility check valve program. Based on the foregoing, the NRC staff concludes that the proposed license condition is acceptable and that the regulatory position from RG 1.183, stated in Section 2.0 above, is still satisfied.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The 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 and changes the Surveillance Requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents 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 the amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 68731). Accordingly, the 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 the amendment.

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

Principal Contributor: L. Olshan Date: December 13, 2002

Mr. J. S. Keenan Brunswick Steam Electric Plant, Unit 2 Carolina Power & Light Company cc:

Mr. William D. Johnson Mr. Robert P. Gruber Vice President and Corporate Secretary Executive Director Carolina Power & Light Company Public Staff - NCUC Post Office Box 1551 4326 Mail Service Center Raleigh, North Carolina 27602 Raleigh, North Carolina 27699-4326 Mr. Donald E. Warren Mr. C. J. Gannon Brunswick County Board of Commissioners Director - Site Operations Post Office Box 249 Carolina Power & Light Company Bolivia, North Carolina 28422 Brunswick Steam Electric Plant Post Office Box 10429 Resident Inspector Southport, North Carolina 28461 U. S. Nuclear Regulatory Commission 8470 River Road Mr. Norman R. Holden, Mayor Southport, North Carolina 28461 City of Southport 201 East Moore Street Mr. John H. ONeill, Jr. Southport, North Carolina 28461 Shaw, Pittman, Potts & Trowbridge 2300 N Street NW. Mr. Dan E. Summers Washington, DC 20037-1128 Emergency Management Coordinator New Hanover County Department of Ms. Beverly Hall, Acting Director Emergency Management Division of Radiation Protection Post Office Box 1525 N.C. Department of Environment Wilmington, North Carolina 28402 and Natural Resources 3825 Barrett Dr. Mr. Terry C. Morton, Manager Raleigh, North Carolina 27609-7721 Performance Evaluation and Regulatory Affairs CPB 7 Mr. W. C. Noll Carolina Power & Light Company Plant Manager Post Office Box 1551 Carolina Power & Light Company Raleigh, North Carolina 27602-1551 Brunswick Steam Electric Plant Post Office Box 10429 Mr. Edward T. ONeil Southport, North Carolina 28461 Manager - Support Services Carolina Power & Light Company Public Service Commission Brunswick Steam Electric Plant State of South Carolina Post Office Box 10249 Post Office Drawer 11649 South Port, North Carolina 28461 Columbia, South Carolina 29211 Ms. Margaret A. Force Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, North Carolina 27602