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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 - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 2024-09-09
[Table view] Category:Notice of Violation
MONTHYEARIR 05000266/20200122020-08-0303 August 2020 NRC Inspection Report 05000266/2020012 and 05000301/2020012; Preliminary White Finding and Apparent Violations IR 05000266/20130122013-08-0909 August 2013 IR 05000266-13-012 and 05000301-13-012, and Notice of Violation, Point Beach, Units 1 and 2, Final Significance Determination of a White Finding with Assessment Follow-up IR 05000266/20120102013-01-0202 January 2013 EA-12-220, Point Beach Nuclear Plant, Unit 1, Final Significance Determination of a White Finding with Assessment Followup and Notice of Violation; NRC Inspection Report No. 05000266-12-010 IR 05000266/20125042012-07-24024 July 2012 EA-12-106, Point Beach, Final Significance Determination of a White Finding with Assessment Followup and Notice Of Violation ML12206A5142012-07-24024 July 2012 EA-12-106, Point Beach, Final Significance Determination of a White Finding with Assessment Followup and Notice of Violation IR 05000266/20100102010-04-0707 April 2010 Inspection Report (IR) 05000266-10-010, 05000301-10-010; February 17, 2010; Point Beach Nuclear Plant, Units 1 and 2; Results of NRC Investigation Report No. 3-2009-011 and Notice of Violation IR 05000266/20090092009-06-24024 June 2009 EA-09-012, Point Beach Nuclear Generating Plant, Units 1 and 2, NRC Inspection Report Nos. 05000266-09-009(DRS), 05000301-09-009(DRS) IR 05000266/20060112007-01-29029 January 2007 EA-06-274, Point Beach Nuclear Plant, Units 1 and 2, Notice of Violation (NRC Special Inspection Report 05000266/2006011; 050000301/2006011) ML0701001382006-08-22022 August 2006 Dennis L. Koehl Ltr. Apparent Violation of Employee Protection Requirements (Office of Investigations Report No. 3-2005-010) ML0334900222003-12-11011 December 2003 EA-03-057, Point Beach, Final Significance Determination for a Red Finding and Notice of Violation IR 05000266/20020152003-04-0202 April 2003 IR 05000266-02-015 (Drp); IR 05000301-02-015 (Drp), on 9/23 -26/2002 and 10/31/2002 - 3/24/2003, Nuclear Management Company, LLC; Point Beach Nuclear Plant, Unit 1 and Unit 2. Special Inspections to Evaluate a Red Inspection Finding ML0307701832002-07-12012 July 2002 Final Significance Determination for Red Finding & Notice of Violation NRC Special Inspection Report IR 05000266-01-017 & IR 05000301-01-017(DRS) ML0307701782002-07-12012 July 2002 Final Significance Determination for Red Finding & Notice of Violation NRC Special Inspection Report IR 05000266-01-017 & IR 05000301-01-017(DRS) ML0219601242002-07-12012 July 2002 EA-02-031, Point Beach Nuclear Plant, NOV and Red Finding 07/12/2002 ML0307701042002-07-0808 July 2002 Undated Letter from NRC to Point Beach Regarding Final Significance Determination for Red Finding and Notice of Violation IR 05000266/20020032002-06-13013 June 2002 Final Significance Determination for a White Finding and Notice of Violation (IRs 05000266-02-03, 05000301-02-03, 05000266-02-05 & 05000301-02-05) ML0307603352002-05-15015 May 2002 Draft of the Final Significance Letter for the Point Beach Red Finding & Notice of Violation ML0307603302002-05-15015 May 2002 Draft of the Final Significance Letter for the Point Beach Red Finding and Notice of Violation 2020-08-03
[Table view] |
Text
une 13, 2002
SUBJECT:
FINAL SIGNIFICANCE DETERMINATION FOR A WHITE FINDING AND NOTICE OF VIOLATION (NRC INSPECTION REPORT NOS. 50-266/02-03; 50-301/02-03 AND 50-266/02-05; 50-301/02-05) (POINT BEACH NUCLEAR PLANT, UNIT 2)
Dear Mr. Warner:
The purpose of this letter is to provide you with the final results of our significance determination of the finding identified in the subject inspection reports. As discussed in the letter from the NRC to you, dated May 14, 2002, the inspection finding was assessed using the significance determination process and was preliminarily characterized as White, an issue with low to moderate increased importance to safety, which may require additional NRC inspections.
This White finding involved the self-revealing failure of safety injection system pump 2P-15B due to nitrogen gas binding.
In a telephone conversation with Mr. Roger Lanksbury of NRC, Region III, on May 24, 2002, you indicated that Nuclear Management Company agreed with the preliminary characterization of the risk significance of this finding and the apparent violation associated with this issue. You also indicated that there was no additional information you wished to present and, therefore, a Regulatory Conference was not needed.
After considering the information developed during the inspections, the NRC has concluded that the inspection finding is appropriately characterized as White (i.e., an issue with low to moderate increased importance to safety, which may require additional NRC inspections).
You have 30 calendar days from the date of this letter to appeal the staffs determination of significance for the identified White finding. Such appeals will be considered to have merit only if they meet the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC has also determined the failure to take prompt corrective actions to preclude repetition after Point Beach personnel concluded that the safety injection system was susceptible to gas binding and when decreasing trends in the Unit 2 A safety injection accumulator level were identified is a violation of Criterion XVI, Corrective Action, of 10 CFR Part 50, Appendix B, which requires, in part, that conditions adverse to quality be promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective actions taken to preclude repetition. The violation is cited in the attached Notice of Violation (Notice).
The circumstances surrounding the violation are described in detail in the subject inspection reports. In accordance with the NRC Enforcement Policy, NUREG-1600, the Notice of Violation is considered escalated enforcement because it is associated with a White finding.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
Because plant performance for this issue has been determined to be in the regulatory response band, we will use the NRC Action Matrix to determine the most appropriate NRC response for this event. We will notify you, by separate correspondence, of that determination.
In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter, its enclosure, and your response will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRCs 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/
Geoffrey E. Grant, Director Division of Reactor Projects Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27 Enclosure: Notice of Violation See Attached Distribution DOCUMENT NAME: C:\ORPCheckout\FileNET\ML021640295.wpd *See previous concurrence 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 RIII RIII RIII NAME MKunowski:dtp RLanksbury BClayton GGrant
DATE 06/04/02 06/04/02 06/07/02 06/07/02 OFFICIAL RECORD COPY cc w/encl: R. Grigg, President and Chief Operating Officer, WEPCo R. Anderson, Executive Vice President and Chief Nuclear Officer T. Webb, Licensing Manager D. Weaver, Nuclear Asset Manager T. Taylor, Plant Manager A. Cayia, Site Director J. ONeill, Jr., Shaw, Pittman, Potts & Trowbridge K. Duveneck, Town Chairman Town of Two Creeks D. Graham, Director Bureau of Field Operations A. Bie, Chairperson, Wisconsin Public Service Commission S. Jenkins, Electric Division Wisconsin Public Service Commission State Liaison Officer ADAMS Distribution:
WDR DFT BAW WDT WFK FJC JLD LJC DCD SJC1 RWB1 LAD SFG HTB GPC DBD DJH CFE GFS JED2 GEG HBC KJL PGK1 RidsNrrDipmIipb RJS2 RML2 JLL2 DRPIII DRSIII PLB1 JRK1 ADAMS (PARS)
SECY OCA OEWEB OEMAIL
NOTICE OF VIOLATION Nuclear Management Company, Inc. Docket No. 50-301 Point Beach Nuclear Plant, Unit 2 License No. DPR-27 EA-02-090 During NRC inspections conducted from January 22 through March 31, 2002, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:
Criterion XVI, Corrective Action, of 10 CFR Part 50, Appendix B, requires, in part, that conditions adverse to quality be promptly identified and corrected. In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined and corrective actions taken to preclude repetition.
Contrary to the above, between April 2000 and February 20, 2002, the licensee failed to promptly identify and correct a significant condition adverse to quality regarding leakage from the 2T-34A safety injection accumulator. Nitrogen that leaked from the accumulator caused gas binding and subsequent failure of the 2P-15B safety injection pump on February 20, 2002. Specifically:
a. In April 2000, the licensee completed a review of Information Notice 88-023, Supplement 5, Potential for Gas Binding of High-Pressure Safety Injection Pumps During a Loss-of-Coolant-Accident, and identified that the Point Beach safety injection systems were susceptible to gas binding in the event of leakage from the safety injection accumulators through multiple check valves and/or motor-operated valves. However, corrective actions were not promptly taken.
b. On February 12, 2001, (Condition Report 01-0454), and on January 15, 2002, (Action Request 1862), licensed control room operators identified decreasing trends in 2T-34A safety injection accumulator level. However, the cause of the condition was not determined and corrective actions were not taken to preclude repetition.
This violation is associated with a White SDP finding.
Pursuant to the provisions of 10 CFR 2.201, Nuclear Management Company, Inc., is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region III, and a copy to the NRC Resident Inspector at Point Beach, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include: (1) the reason for the violation, or, if contested, the basis for disputing the violation or significance determination, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or
Notice of Violation -2-revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.
Because your response will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
In accordance with 10 CFR 19.11, you may be required to post this Notice within two working days.
Dated this 13th day of June 2002.