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MONTHYEARML24247A2752024-09-0404 September 2024 Pmns W3 Outreach September 2024, Information Needed in Pmns to Generate Public Meeting Notice ML24226B2162024-08-12012 August 2024 FAQ 24-01 Waterford 3 IE04 August 2024 ML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML21354A7602021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 15 of 18 ML21354A7462021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 1 of 18 ML21354A7492021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 4 of 18 ML21354A7562021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 11 of 18 ML21354A7572021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 12 of 18 ML21354A7592021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 14 of 18 ML21354A7612021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 16 of 18 ML21354A7632021-12-20020 December 2021 Recertification of Foreign Ownership Control or Influence and Request for FOCI Redetermination - Part 18 of 18 ML20329A1452020-11-20020 November 2020 Terrapower'S QAPD Preliminary Questions ML17290A0492017-10-17017 October 2017 Discussion Topics for October 19, 2017 Category 1 Public Meeting Regarding Fluence Methodology ML17041A1732017-02-10010 February 2017 Further Discussion Topics for Public Meeting to Discuss License Amendment Request Regarding the Revision of TS Table 4.3-2 for Waterford Steam Electric Station, Unit 3 CNRO-2016-00024, Entergy - Form 10-K for Fiscal Year Ended December 31, 20152016-12-20020 December 2016 Entergy - Form 10-K for Fiscal Year Ended December 31, 2015 ML15363A3742015-10-0606 October 2015 Internal Events and Internal Flooding PRA and Fire PRA NFPA 805 Record of Review ML14217A4972014-08-0404 August 2014 Attachment 5 - W3F1-2014-0005 - Waterford Steam Electric Station, Unit 3, List of Regulatory Commitments ML12181A3462012-06-28028 June 2012 Attachment 5 to W3F1-2012-0049, List of Regulatory Commitments ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1206800622012-02-22022 February 2012 Attachment to Email, Issues Related to 10 CFR 50.59 Evaluation - License Amendment Request, Revise Technical Specification Applicability and Action Language for Revised Fuel Handling Accident Analysis ML1203705362012-01-23023 January 2012 Correction to NRC Safety Evaluation for Scv Hatch Repair ML1110807292011-04-18018 April 2011 SG Batwing Inspections Notes RFO-17 (Part 2) ML1109501252011-04-0404 April 2011 Attachment 5 to W3F1-2011-0021, List of Regulatory Commitments ML1104701842011-02-15015 February 2011 Attachment 2 to W3F1-2011-0016, Waterford, Unit 3, List of Regulatory Commitments ML1030001222010-10-27027 October 2010 Markup of Corrections for NRC LLRT Relief SER ML1017301952010-06-17017 June 2010 Revised Responses to the Nrc'S Request for Additional Information Related to GL-2004-02 ML1019304602010-03-25025 March 2010 List of Historical Leaks and Spills at Us Commercial Nuclear Power Plants ML0932105192009-11-12012 November 2009 NRC Mid-RF16 Outage Call Discussion Points ML1002215022009-03-30030 March 2009 Data Sheet for Waterford 3 Steam Electric Station, Checklist for Step 1 Review ML0821804192008-07-11011 July 2008 2008-03, Revised SRO Answer Key ML0808000362008-03-13013 March 2008 List of Attendees, 03/13/2008 Summary of Meeting with Eight Operating Nuclear Power Plant Licensees to Discuss Emerging Metallurgical Issues Certain Welds in Reactor Coolant System for Pressurized-Water Reactors ML0806704192008-03-0707 March 2008 CDBI Findings ML0805105192008-02-0606 February 2008 Modification of LPDES Permit - LA0007374 Waterford Steam Electric Station - Unit 3 (Waterford 3) ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions CNRO-2007-00038, Entergy Operations, Inc. - Proof of Financial Protection (10 CFR 140.15)2007-09-24024 September 2007 Entergy Operations, Inc. - Proof of Financial Protection (10 CFR 140.15) ML0726301142007-09-14014 September 2007 / P. Paquin Ltr Amendment to Certificate of Compliance No. 9208 for the Model No. 10-142B Package (TAC L24117)/S121170 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0721104332007-07-25025 July 2007 Questions from 1 Through 8 ML0721104302007-07-25025 July 2007 SDP Phase 2 Exercise ML0634705992006-12-14014 December 2006 Plant Service List ML0607301852006-03-31031 March 2006 Mid-Inspection Questions with the NRC for Waterford 3 Steam Generators During RF13 ML0536302482005-12-31031 December 2005 Indemnity Agreement No. B-92, Amd. 7 (New Name: Entergy Louisiana, LLC) ML0525002622005-09-0606 September 2005 Recap of NRC Emergency Planning Roundtable to Be Included in Transcript and Record ML0512401522005-05-0909 May 2005 Event Description: Attachment 7 ML0326909822005-02-14014 February 2005 August 2003 - Init Exam - Es 401-4 Rejected K/A ML0404104922004-02-20020 February 2004 Order EA-03-009 Service List ML0505404692004-02-10010 February 2004 Dynamic Web Page Printout Dated 02/10/2004, ROP PIM Report - All Sites - Event Dates: 01/01/2003 - 02/10/2004 ML0505404642004-02-0909 February 2004 Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants 2024-09-04
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Waterford 3 Event Description Safety Injection Sump Outlet Header B Isolation Valve SI-602B is a normally closed valve. The valve is required to close on a Safety Injection Actuation Signal (SIAS) and required to open on a Recirculation Actuation Signal (RAS) to provide a flow path from the Safety Injection Sump to the Emergency Core Cooling System (ECCS) and Containment Spray (CS) pumps.
On September 9, 2004, while performing Surveillance Test OP-903-1 10, "RAB Fluid Systems Leak Test," on the Safety Injection (SI) piping between valves SI-602B and Sl-604B, the piping could not be pressurized. Subsequent troubleshooting efforts identified that Valve Sl-602B was not fully seated. The licensee identified that this was due to inadequate valve setup following T-Ring replacement during Refueling Outage 12.
The licensee identified that under certain accident conditions with a large break or medium break Loss-of-Coolant-Accident (LOCA) present, containment pressure would force air through Valve Sl-602B into the safety injection sump suction piping. This would create a back pressure on Refueling Water Storage Pool (RWSP) Suction Check Valve, S-i 07B. Under certain conditions, the void pressure could isolate flow from the RWSP to the CS and ECCS pumps before the RWSP level reached the RAS actuation setpoint. Based on this, the SI system was considered to be unavailable between November 11, 2003, when Refuel 12 ended, and September 9, 2004, when the valve leakage was identified and corrected.
NRC's Understandinq of the Licensee's Position The licensee contends that the root cause of this event was a design deficiency in that valves Sl-602A and Sl-602B had been incorrectly classified as category B valves under the IST program (which do not require leak testing), when the valves should have been classified as category A (which do require leak testing). As a result, no routine testing had been performed that would quantify any leakage past the valve. Thus no surveillance tests were available to guarantee the leak-tightness of these valves and prevent the back pressure that could cause the inoperability of the ECCS and CS system. In addition, because the condition existed since the original design and licensing basis and was a condition of long duration, the licensee believes that they meet the criteria set forth in NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 2, Page 33, Line 17:
NRC's Interpretation of the Issue The NRC's position is that the licensee should include in the SSU High Pressure Injection System PI the time from when SI-602B had its T-ring replaced (November 11, 2003) to when the valve failure was identified (September 9, 2004). The unavailability was the result of inadequate test controls whereby the lack of post maintenance testing resulted in the failure by the licensee to identify the maintenance errors.
The staff believes that the root cause of the failure of Sl-602B was the maintenance errors that occurred during the T-ring installation effort and the failure to perform a post maintenance test as required per 10 CFR 50, Appendix B, Criterion Xl. The licensee had many opportunities between 1984 and 2004 to identify both the voiding and back-pressure condition as well as the valve mis-classification.
Attachment 7