NRC 2002-0101, Transmittal of Fire Protection Evaluation Report, Revision 1 (2024)

Nuclear Management Company, LLC Point Beach Nuclear Plant NMC Committed to Nuclear Excellence 6610 Nuclear Road Two Rivers, WI 54241 NRC 2002-0101 10 CFR 50.48 10 CFR 50.71 (e)

November 18, 2002 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, DC 20555 Ladies/Gentlemen Docket Numbers 50-266 and 50-301 Point Beach Nuclear Plant, Units 1 and 2 Transmittal of Fire Protection Evaluation Report, Revision 1 In accordance with the requirements of 10 CFR 50.48, Generic Letter 88-12 and 10 CFR 50.71(e), enclosed is Revision 1 to the Fire Protection Evaluation Report (FPER) for Point Beach Nuclear Plant. This revision includes the results of the extensive Appendix R re-evaluation efforts conducted by the plant staff. Attachment A provides a listing of the significant changes to the Fire Protection Evaluation Report included in this revision. A summary of the 10 CFR 50.59 safety evaluation for this FPER revision was provided with our "Annual 10 CFR 50.59 Summary Report for 2001," dated June 28, 2002.

Note that this revision was completed in August 2001. Copies of the revised FPER were provided to the NRC resident inspectors at that time and this FPER revision was reviewed as part of the NRC triennial fire protection inspection of PBNP during September 2001. However, the omission of providing a docket transmittal of this revision was only recently identified by plant staff. Appropriate actions have been identified within the PBNP corrective action process to preclude recurrence of this oversight.

If you have any questions concerning the information provided in this FPER revision, please contact Norm Hoefert at 920-755-7590.

Sincerely, SIVICe re dent

/0)/#---RC Regional Administrator NRC Project Manager enc sure NRC Resident Inspector PSCW A-006

NRC 2002-0101 ATTACHMENT A Summary of Revision 1 Changes to the Fire Protection Evaluation Report Dated August 17, 2001

NRC 2002-0101 ATTACHMENT A Summary of Revision 1 Changes to Fire Protection Evaluation Report The FPER has been completely revised to support the Appendix R re-baselining effort.

1) The FPER has been reformatted to address the topics set forth in BTP CMEB 9.5.1. "Guidelines for Fire Protection for Nuclear Power Plants"

2) The detailed results of the safe shutdown analysis portion of the FPER have been put into a separate document called the Safe Shutdown Analysis Report (SSAR).

3) The detailed fire hazards analysis portion of the FPER has been put into a separate document called the Fire Hazards Analysis Report (FHAR).

4) This revision incorporate Modification 91-116 which added two new Emergency Diesel Generators (EDG), G-03 and G-04, and made G-01/G-02 the A Train EDGs and G-03/G-04 the B Train EDGs.

5) The revision incorporated appropriate changes to organization names resulting from the transference of the Facility Operating Licenses to the NMC.

6) The term "Hot Shutdown" has been replaced with "Hot Standby" throughout the document to accurately depict Point Beach as a hot standby plant. This aligns with the terminology used in 10 CFR 50, Appendix R for PWRs and with the Improved Technical Specifications.

7) As a result of the re-base-lining effort, the safe shutdown methodology for certain areas has been revised. Alternate shutdown strategy is now relied upon for the Cable Spreading Room. Furthermore the Gas Turbine (G-05) is credited for certain fire scenarios in the Auxiliary Feedwater Pump Room. These changes provide a more consistent approach for Operations in critical areas of the plant. In all Fire Areas, the Fire Protection Program shows that the plant can be safely shutdown after an Appendix R fire event by following the documented strategies.

8) The following FPER change requests were incorporated:

• 99-029 - Nitrogen backup system for charging speed control

• 99-031 - Installation of a 500 gallon liquid propane tank west of the wellhouse.

NRC 2002-0101 0 99-032 - SW supply, return pipe & valves for SFP HX-13A & B. The affected figures were updated to show the new system equipment.

0 99-033 - Control Room to Cable Spreading Room barrier acceptability.

0 00-001 - SW supply, return pipe & valves for AFW Pumps. The affected figures were updated to show the new system equipment.

• 00-004 - Change "weekly" plant material condition inspection requirement to "regular.".

• 00-007 - Revise reference for audits from Technical Specifications to reference the FSAR.

• 00-008 - SW supply, return pipe & valves for SW west supply header. The affected figures were updated to show the new system equipment.

• 00-009 - Delete the requirement to test run the second fire pump every 24 hours2.777778e-4days <br />0.00667hours <br />3.968254e-5weeks <br />9.132e-6months <br /> after it is initially tested to demonstrate operability when one fire pump is inoperable.

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