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Category:Inspection Report Correspondence
MONTHYEARML19171A3942019-06-20020 June 2019 Ltr. 06/20/19 Point Beach Nuclear Plant, Units 1 and 2 - Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000266/2019004 and 05000301/2019004 (DRS-L.Rodriguez) ML18193B0922018-07-12012 July 2018 Ltr 071218 Point Beach Nuclear Plant, Unit 2 - Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2018004; 05000301/2018004 (Jen) ML18164A3162018-06-12012 June 2018 Information Request for an NRC Triennial 10 CFR 50.59 Baseline Inspection; Inspection Report 05000266/2018011; 05000301/2018011 (DRS-G.Hausman) ML17047A6432017-02-16016 February 2017 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2017002; 05000301/2017002 IR 05000266/20164052016-08-11011 August 2016 NRC Security Baseline Inspection Report 05000266/2016405; 05000301/2016405 (Cover Letter Only) ML16217A3992016-08-0404 August 2016 Information Request to Support Upcoming Problem Identification and Resolution Inspection 05000266/2016007 and 05000301/2016007 ML0812003172008-04-29029 April 2008 Errata to Point Beach 2008-007 DRS SIT Inspection Report IR 05000266/20080072008-04-21021 April 2008 IR 05000266-08-007, 05000301-08-007, on 01/18/2008 - 03/07/2008, Point Beach, Special Inspection to Review Circumstances Surrounding the Loss of the Unit 1, 1X 04 Transformer and Safety Bus 1B 04 IR 05000266/20062012006-09-13013 September 2006 Ltr to Dennis Koehl - Point Beach Nuclear Plant - Security Inspection 05000266/2006201 and 05000301/2006201 ML0511803742005-04-28028 April 2005 Re Notification of NRC Inservice Inspection and Request for Information ML0515202442004-05-24024 May 2004 Draft Inspection Report Point Beach Nuclear Plant, Unit 1 DRS Input to Integrated Report 50-266-04-003 & 50-301-04-003 ML0334900222003-12-11011 December 2003 EA-03-057, Point Beach, Final Significance Determination for a Red Finding and Notice of Violation ML0212104882002-04-30030 April 2002 IR 05000266/2002-004(DRS), IR 05000301/2002-004(DRS), on 02/11-04/1/2002, Nuclear Management Company, LLC, Point Beach Nuclear Plant, Units 1 and 2. Exercise Evaluation ML0211606832002-04-26026 April 2002 IR 05000266/2002-005; 05000301/2002-005, on 02/20-03/31/2002, Nuclear Management Company, LLC, Point Beach Nuclear Plant, Units 1 & 2. Operability Evaluations IR 05000266/20010172002-04-0303 April 2002 IR 05000266/2001-017 (Drs), 05000301/2001-017 (Drs), on 12/03/2001-02/28/2002, Nuclear Management Company, LLC, Point Beach Nuclear Plant. Special Inspection. Violations Identified IR 05000266/20020022002-02-0606 February 2002 IR 05000266/2002-002(DRS); IR 05000301/2002-002(DRS), Point Beach Nuclear Plant, Inspection on 01/14/2002 - 01/18/2002 Related to Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Report. No Violations Noted ML0203802102002-02-0606 February 2002 IR 05000266/2002-002(DRS); IR 05000301/2002-002(DRS), Point Beach Nuclear Plant, Inspection on 01/14/2002 - 01/18/2002 Related to Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications Report. No Violations Noted 2019-06-20
[Table view] Category:Letter
MONTHYEARML24036A2652024-02-0505 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 L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, 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 Applications2023-03-27027 March 2023 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 2024-02-05
[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
December 11, 2003 EA-03-057 Mr. Alfred J. Cayia 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 FINAL SIGNIFICANCE DETERMINATION FOR A RED FINDING AND NOTICE OF VIOLATION (NRC INSPECTION REPORT NO. 50-266/02-15(DRP);
50-301/02-15(DRP))
Dear Mr. Cayia:
The purpose of this letter is to provide you the final results of our significance determination of the preliminary Red finding identified in the subject inspection report. The inspection finding was assessed using the Significance Determination Process and was preliminarily characterized as Red, a finding of high importance to safety that results in increased NRC inspection and other NRC action. This Red finding involved the potential common mode failure of all trains of the auxiliary feedwater (AFW) system due to the susceptibility of the pressure reduction orifices in the AFW pump recirculation lines to become plugged by debris typically found in the plant service water system.
At the request of the Nuclear Management Company, LLC (NMC), a Regulatory Conference was held, on June 6, 2003, to further discuss NMCs views on this issue. A summary of that meeting and a copy of the handout provided by NMC was provided with a letter to Mr. John Paul Cowan of NMC dated June 16, 2003, and is available from the NRCs document system (ADAMS) at Accession No. ML031681102. During the meeting, NMC staff stated that the analysis of the risk from internal events associated with the orifice plugging issue would be completed in about two weeks and that the analysis of the risk from external events, including fire, would be completed in August 2003. This information was submitted to the NRC with letters dated June 27, 2003, and September 18, 2003. The September 18, 2003, letter provided the NRC with the Unit 2 internal and external events risk analysis results, including fire events. Your analysis determined that the total change in core damage frequency due to internal and external events for Unit 2 was in the range of 1.9E-4 to 3.1E-4 (Red), with fire events dominating the results. We understand that the Unit 2 results bounded the Unit 1 results because the Unit 2 turbine-drive AFW pump (TDAFWP) recirculation line orifice was installed much longer than the Unit 1TDAFWP recirculation line orifice.
A. Cayia After considering the information provided during the June 6th Regulatory Conference and a review of the information provided in the June 27th and September 18th letters, the NRC has concluded that the inspection finding is appropriately characterized for Unit 1 as Yellow, an issue with substantial importance to safety that would normally result in additional NRC inspection, and for Unit 2 as Red, an issue of high importance to safety that would normally result in increased NRC inspection and other NRC action. The difference in significance between the Units is a result of the longer period of time that the AFW recirculation line pressure reduction orifices were installed in Unit 2.
As discussed in the letter dated April 2, 2003, transmitting Inspection Report No. 50-266/02-15 (DRP); 50-301/02-15(DRP), the failure to implement thorough and complete corrective actions for the AFW/instrument air Red inspection finding allowed other design deficiencies, including the use of a nonsafety-related power supply for relays, single electrical bus dependencies for three of the four recirculation line air-operated flow control valves, and the inadequate orifice modification to continue to exist. As a result, the finding associated with the AFW/instrument air issue was determined not to be an old design issue. The AFW/instrument air finding and the AFW orifice plugging finding, which is the subject of this letter, share as a common cause the lack of understanding of the design basis of the recirculation lines. However, the differences in time of occurrence and the failure of corrective actions for the first finding to prevent occurrence of the second finding warranted treating these issues as separate findings. In response to the AFW/instrument air Red inspection finding, the NRC recently conducted an inspection per Inspection Procedure (IP) 95003, Supplemental Inspection for Repetitive Degraded Cornerstones, Multiple Degraded Cornerstones, Multiple Yellow Inputs, or One Red Input, in accordance with NRC Inspection Manual Chapter 0305, Operating Reactor Assessment Program. During this inspection, the inspection team also reviewed NMCs corrective actions for the AFW orifice plugging issue. Based on the results of the IP 95003 supplemental inspection, which are currently under review, the NRC will determine what further regulatory action is warranted. We will notify you, by separate correspondence, of that determination.
You have 30 calendar days from the date of this letter to appeal the staffs determination of significance for the identified Unit 1 Yellow finding and the Unit 2 Red 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 that the installation in the AFW recirculation lines of orifices susceptible to plugging by service water-borne debris is a violation of 10 CFR Part 50, Appendix B, Criterion III, Design Control, as cited in the enclosed Notice of Violation (Notice).
In addition to the two AFW recirculation line orifice design control violation examples, a third example of inadequate design control is cited in the Notice. This example involves the failure to assure that the upgraded safety design of the AFW recirculation line air-operated flow control valves relied upon a safety-related power source for a relay associated with the air-operated valves. The circumstances surrounding the violation are described in detail in the subject inspection report. In accordance with the NRC Enforcement Policy, NUREG-1600, the Notice of Violation is considered escalated enforcement action because it is associated with a Red finding.
A. Cayia You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
In accordance with 10 CFR 2.790 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 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). To the extent possible, your response should not include any personal privacy, propriety, or safeguards information so that it can be made available to the public without redaction.
Sincerely,
/RA/
James L. Caldwell Regional Administrator Docket Nos. 50-266; 50-301 License Nos. DPR-24; DPR-27
Enclosure:
Notice of Violation cc w/encl: R. Kuester, President and Chief Executive Officer, WE Generation J. Cowan, Executive Vice-President Chief Nuclear Officer Licensing Manager D. Weaver, Nuclear Asset Manager Plant Manager Regulatory Affairs Manager Training Manager J. Rogoff, Esquire General Counsel D. Cooper, Senior Vice-President 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 J. Kitsembel, Electric Division Wisconsin Public Service Commission State Liaison Officer
DOCUMENT NAME: C:\ORPCheckout\FileNET\ML033490022.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 OE NAME MKunowski/trn* SBurgess* AVegel* BClayton* AVegel for FCongel*
DATE 11/03/03 11/03/03 11/18/03 11/19/03 11/24/03 OFFICE NRR NRR RIII RIII NAME AVegel for AVegel for SReynolds* JCaldwell BRuland* (email) SRichards*
DATE 11/21/03 11/21/03 11/26/03 12/11/03 OFFICIAL RECORD COPY FCongel concurred via telecon with J. Dixon-Herrity.
SRichards concurred via email from Doug Coe
A. Cayia ADAMS Distribution:
WDR DFT JFS2 RidsNrrDipmIipb GEG HBC KAC DRPIII DRSIII PLB1 JRK1 BJK1 FJC JGL JLD LAD OEMAIL OEWEB SECY OCA MDS1 RJS2 PLA RWB1 MRJ1 MAS JRJ RML2 BAB2 WMD LSG WHR SAR DWS DWW WDT SJC1 JLC1 LJC DCD JED2 JWC1 DJH CFE GFS RLF2 PGK1 WMB HTB GPC RDC
NOTICE OF VIOLATION Nuclear Management Company, LLC Docket No. 50-266; 50-301 Point Beach Nuclear Plant License Nos. DPR-24; DPR-27 EA-03-057 During two NRC inspections conducted between September 23, 2002, and March 24, 2003, 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 III, Design Control, of 10 CFR Part 50, Appendix B, requires, in part, that design control measures be established to assure that applicable regulatory requirements and the design basis for structures, systems, and components were correctly translated into specifications, drawings, procedures, and instructions.
Contrary to the above, as of March 24, 2003:
- 1. The licensee failed to establish adequate measures to assure that the auxiliary feedwater (AFW) system design bases were correctly translated into specifications, drawings, procedures, and instructions (modification packages) for the installation of the pressure reduction orifice in the recirculation line of the Unit 1 turbine-driven AFW pump (1P-29). Specifically, the licensee developed Modification Packages 99-029*A, B, C, and D in 1999 to install a revised design orifice in the four recirculation lines of the four pumps of the AFW system. By May 2002, the revised design orifices were installed per Modifications Packages 99-029*A, B, and D in three of the four recirculation lines.
Subsequently, the licensee developed Modification Package 02-029, Safety Upgrade of the AFW System Recirculation Line Air-Operated Flow Control Valve, to change the safety-related design basis of the AFW system to require that the recirculation line, including the pressure reduction orifice, be able to pass flow during all required operating conditions. This modification package was implemented on September 12, 2002. On October 14, 2002, the licensee installed the revised design orifice into the 1P-29 turbine-driven AFW pump recirculation line per Modification Package 99-029*C.
However, the licensee failed to establish adequate measures to assure that the design basis change requiring the safety-related passing of flow during all required operating conditions, approved as part of Modification Package 02-029, was translated into Modification Package 99-029*C prior to the installation of the revised design orifice.
- 2. The licensee failed to correctly translate the AFW system design basis recirculation line flow requirements into modification packages. Specifically, service water (SW) strainer mesh size was not considered when the pressure reduction orifice design using 0.125-inch diameter holes and smaller-sized, inscribed flow channels was incorporated into Modification Packages 99-029*A, B, C, and D. The SW strainer mesh size of 0.125-inch was larger than the smallest limiting flow dimensions of the revised orifice design. Consequently, a common mode failure of all AFW trains could have occurred because debris passing through the SW strainers could plug the holes and flow channels of the AFW recirculation line pressure reduction orifices.
Notice of Violation 3. The license failed to correctly translate the AFW system design basis power supply requirements into Modification Package 02-029 for the safety classification upgrade of the recirculation line air-operated flow control valve (AOV) in each of the four recirculation lines. Specifically, the licensee did not assure that the upgraded safety design relied only upon a safety-related power source for a relay associated with the AOVs. Instead, the AFW system relied on a single train of nonsafety-related power supply for all trains of the AOV relays. Consequently, a common mode failure could have occurred during a loss of the nonsafety-related power supply.
This violation is associated with a Yellow SDP finding for Unit 1 and a Red SDP finding for Unit 2 (EA-03-057).
Pursuant to the provisions of 10 CFR 2.201, Nuclear Management Company, LLC, 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 3, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, 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; EA-03-057" and should include: (1) the reason for the violation, or, if contested, the basis for disputing the violation or severity level, (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 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 NRCs document system (ADAMS), accessible from the NRC Web site at http://www.usnrc.gov/reading-rm/adams.html, 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. 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
Notice of Violation 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 11th day of December 2003.