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Category:Letter
MONTHYEARIR 05000266/20240032024-11-0505 November 2024 Integrated Inspection Report 05000266/2024003 and 05000301/2024003 ML24295A1142024-10-31031 October 2024 Suppl Env Audit Summary Letter W/Enclosure 1 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024 Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41) ML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections IR 05000266/20244012024-07-23023 July 2024 Public - 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June 1, 2004 Mr. Gary D. Van Middlesworth 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 INFORMATION REQUEST FOR AN NRC BIENNIAL HEAT SINK PERFORMANCE INSPECTION; 05000266/2004003(DRS);
05000301/2004003(DRS)
Dear Mr. Van Middlesworth:
On June 14, 2004, the NRC will begin the Biennial Heat Sink Performance Inspection at your Point Beach Nuclear Plant, Units 1 and 2. This inspection will be performed in accordance with NRC baseline inspection procedure 71111.07. The systems selected for detailed review during this baseline inspection are the Emergency Diesel Generator Coolant Heat Exchanger (G01 and G02) and Component Cooling System Heat Exchanger (HX-12C).
We have enclosed requests for the documents needed for this inspection.
This information can be sent to the following e-mail address: dls3@nrc.com. Please send the information when it becomes available, so that we may start our review of these documents.
The lead inspector for this inspection is Mr. Darrell Schrum. If there are questions about the material requested, or the inspection, please call Mr. Schrum at (630) 829-9741.
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice, "a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs
G. Van Middlesworth document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Julio F. Lara, Chief Electrical Engineering Branch Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
Enclosure:
Initial Document Request cc w/encl: F. Kuester, President and Chief Executive Officer, We Generation J. Cowan, Executive Vice President Chief Nuclear Officer D. Cooper, Senior Vice President, Group Operations J. McCarthy, Site Director of Operations D. Weaver, Nuclear Asset Manager Plant Manager Regulatory Affairs Manager Training Manager Site Assessment Manager Site Engineering Director Emergency Planning Manager J. Rogoff, Vice President, Counsel & Secretary K. Duveneck, Town Chairman Town of Two Creeks Chairperson Public Service Commission of Wisconsin J. Kitsembel, Electric Division Public Service Commission of Wisconsin State Liaison Officer
G. Van Middlesworth document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Julio F. Lara, Chief Electrical Engineering Branch Division of Reactor Safety Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
Enclosure:
Initial Document Request cc w/encl: F. Kuester, President and Chief Executive Officer, We Generation J. Cowan, Executive Vice President Chief Nuclear Officer D. Cooper, Senior Vice President, Group Operations J. McCarthy, Site Director of Operations D. Weaver, Nuclear Asset Manager Plant Manager Regulatory Affairs Manager Training Manager Site Assessment Manager Site Engineering Director Emergency Planning Manager J. Rogoff, Vice President, Counsel & Secretary K. Duveneck, Town Chairman Town of Two Creeks Chairperson Public Service Commission of Wisconsin J. Kitsembel, Electric Division Public Service Commission of Wisconsin State Liaison Officer DOCUMENT NAME: ML041600211.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RIII E RIII NAME DSchrum:tr PLouden JLara DATE 06/01/04 06/01/04 06/01/04 OFFICIAL RECORD COPY
G. Van Middlesworth ADAMS Distribution:
WDR DFT HKC RidsNrrDipmIipb GEG HBC PGK1 CAA1 DRPIII DRSIII PLB1 JRK1
BIENNEAL HEAT SINK INSPECTION DOCUMENT REQUEST The systems selected for detailed review during this baseline inspection are the Emergency Diesel Generator Coolant Heat Exchangers (G01 and G02) and Component Cooling System Heat Exchanger (HX-12C).
- 1. Copy of the two most recently completed tests confirming thermal performance of each HX. Include documentation and procedures that identify the types, accuracy, and location of any special instrumentation used for these tests (e.g., high accuracy ultrasonic flow instruments or temperature instruments).
Include calibration records for the instruments used during these tests.
- 2. Copy of the evaluations of data for the two most recent completed tests confirming the thermal performance of each HX.
- 3. Copy of the calculation which establishes the limiting (maximum) design basis heat load which is required to be removed by each of these HXs.
- 4. Copy of the calculation which correlates surveillance testing results from these HXs with design basis heat removal capability (e.g., basis for surveillance test acceptance criteria).
- 5. The clean and inspection maintenance schedule for each HX.
- 6. For the last two clean and inspection activities completed on each HX, provide a copy of the document describing the inspection results.
- 7. Provide a copy of the document which identifies the current number of tubes in service for each heat exchanger and the supporting calculation which establishes the maximum number of tubes which can be plugged in each HX.
- 8. Provide a copy of the document establishing the repair criteria (plugging limit) for degraded tubes which are identified in each HX.
- 9. Copy of the design specification and heat exchanger data sheets for each HX.
- 10. Copy of the vendor/component drawing for each HX.
- 11. Provide a list of issues with a short description documented in your corrective action system associated with these HXs in the past three years.
- 12. Provide a list of calculations with a short description which currently apply to each HX.
- 13. Provide HX performance trending data tracked for each HX.
- 14. Provide the Design Basis Documents for Emergency Diesel Generator/Heat Exchanger and the Component Cooling System/Heat Exchanger.
1 Enclosure
- 15. System health report(s), maintenance rule system notebooks for these HX(s).
- 16. Provide a list of CR(s) related to these HX(s) for the past three years (open and closed).
- 17. List of operability evaluations currently relied upon and those that were previously (past two years) relied upon for operability.
- 18. List of engineering-related Operator Workarounds for these HX(s).
- 19. Copy of HX self-assessments and audits for HX(s).
- 20. Updated Final Safety Analysis Report (UFSAR) pages for these HX(s)
- 21. Copies of the condition report (open or closed) initiated in the last three years for these HX(s) that required an operability determination (include determination).
- 22. List of existing temporary modifications for these HX(s).
2 Enclosure