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MONTHYEARML22207A0312022-07-22022 July 2022 NRC-2022-000092 - Resp 1 - Final, Agency Records Subject to the Request Are Enclosed LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility2022-02-24024 February 2022 Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility RS-20-140, Proposed Changes to Decommissioning Trust Agreements2020-10-30030 October 2020 Proposed Changes to Decommissioning Trust Agreements ML19101A4052019-04-10010 April 2019 Annual Assessment Meeting Attendee List ML18334A1232018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, List of Current Pages ML18334A1222018-11-12012 November 2018 Revision 23 to Updated Final Safety Analysis Report, Table of Contents ML18156A0142018-05-30030 May 2018 30-2018 Annual Assessment Meeting Attendee List ML17097A2102017-04-0707 April 2017 List of Attendees for Annual Assessment Meeting for Salem, Hope Creek ML16096A0412016-03-30030 March 2016 Attendance List for Salem_Hope Creek Aam March 30, 2016 ML16049A4582016-02-18018 February 2016 FOIA/PA-2016-0261 - Resp 1 - Final, Salem 2011 Annual Environmental Operating Report ML13364A2832013-12-30030 December 2013 Announcement of 2014 Generic Fundamentals Examination Administration Dates-Letter Dated Dec 30, 2013 ML13176A3662013-06-21021 June 2013 Audit Proposed Questions ML13176A3642013-06-21021 June 2013 Audit Proposed Questions ML13143A3312013-06-0606 June 2013 Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2 ML13059A2972013-02-26026 February 2013 SL-011725, Rev. 0, Salem, Mitigation Strategies for Beyond Design Basis External Events, EA-12-049 Overall Integrated Plan Response. ML13052A7942013-02-21021 February 2013 Complete Set of NRC Questions_2-21-13 ML12334A4512012-11-21021 November 2012 SL-2012-10795, Rev. 0, Sgs Flood Walkdown Report, 10 CFR 50.54(f) Section 2.3 (Flood) Response. ML12366A2972012-11-0808 November 2012 Bypass Testing Information ML12290A1442012-10-0404 October 2012 EN-AA-602-0006, Revision 0, Cultural and Historic Resources ML12138A0062012-05-15015 May 2012 Aam Attendance Sheet, May 15, 2012 LR-N12-0124, Salem Generating Station, Units 1 and 2 - Attachment 1 to LR-N12-0124, Generic Letter 2004-02, Updated Supplemental Response for Salem Regarding Generic Letter 2004-022012-04-27027 April 2012 Salem Generating Station, Units 1 and 2 - Attachment 1 to LR-N12-0124, Generic Letter 2004-02, Updated Supplemental Response for Salem Regarding Generic Letter 2004-02 ML12129A3892012-04-27027 April 2012 Attachment 1 to LR-N12-0124, Generic Letter 2004-02, Updated Supplemental Response for Salem Regarding Generic Letter 2004-02 ML12129A3902012-04-27027 April 2012 Attachments 1 Through Attachment 8, Response to Generic Letter 2004-02 ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1113601032011-05-10010 May 2011 2011 Salem/Hope Creek Annual Assessment Meeting Attendance List ML1211703782011-01-0404 January 2011 Branch Evaluation, Plan & Recommendation, Allegation Number: RIV-2010-A-0202 ML1030004062010-10-22022 October 2010 Document: SAP685996 ML1030004052010-10-22022 October 2010 Document: Operability Evaluation, Opeval, Rev 0, Salem Unit 2 with Handwritten Notes ML1030004072010-10-22022 October 2010 Large Bore Pipe Detail Index List Psbp No. 132419, Aux Feedwater ML1030003422010-10-22022 October 2010 Document: Operability Evaluation, Opeval, Rev 0, Salem Unit 2 with Handwritten Notes ML1030003412010-10-22022 October 2010 Document: Operability Evaluation, Opeval, Rev 0, Salem Unit 2, with Handwritten Notes ML1030003402010-10-22022 October 2010 Document: Operability Evaluation, Opeval, Rev 0, Salem Unit 2, Draft ML1030003392010-10-22022 October 2010 Document: Operability Evaluation, Opeval, Rev 0 Salem Unit 2 ML1030003382010-10-22022 October 2010 Document: Salem NRC Punchlist ML1030003372010-10-22022 October 2010 Document: Configuration Change #80101381 Rev 1 ML1030004092010-10-22022 October 2010 Document: Label Request Form, Label 12AF155 S1 Aix ML1030004022010-09-21021 September 2010 Document PSEG Notification 20462034 Basis AFW Discharge Line Design Pressure ML1030104972010-08-18018 August 2010 Document: Operation Key Info, Buried Pipe Program Inspection Reports for 12 and 14 Aux Feedwater Lines ML1030104962010-08-18018 August 2010 Document: 1R20 AF Buried Pipe Insp Results, Notification #20457262, Salem 1- Auxiliary Feedwater ML1016002752010-06-17017 June 2010 List of Attendees for NRC Public Management No. Nm 10-019; Salem Nuclear Generating Station Discussion of Independent Spent Fuel Storage on 05/27/10 ML1030002042010-05-24024 May 2010 Document: Design Analysis Minor Revision, Subject: Qualification of Safety-Related Buried Commodities for Tornado Missile and Seismic Evaluation ML1030004032010-05-0505 May 2010 Document: PSEG Notification 2041785 ML1029502392010-04-29029 April 2010 Branch 3 Daily Status ML1034404482010-04-24024 April 2010 Document: Salem Unit 1 12/14 AF Piping Reroute, #80101382 Rev 2 ML1029804652010-04-23023 April 2010 RM Documentation No. SA-SURV-2010-001, Rev. 1, Risk Assessment of Missed Surveillance - Auxiliary Feedwater Discharge Line Underground Piping Pressure Testing. ML1034404512010-04-23023 April 2010 Document: Ansys Input Files and Calculation Package Drafts ML1030002032010-04-22022 April 2010 Document: Stress and Support Summary ML1029804892010-04-22022 April 2010 Operability Evaluation with Tracked Changes ML1029802612010-04-21021 April 2010 Notification 000020459689, Submitted by Edley Giles ML1030002012010-04-20020 April 2010 Document: Ultrasonic Thickness Examination Record, Order #60084266, Procedure #OU-AA-335-004 2022-07-22
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0: What actions has the NRC put in place to identify early indications of deteriorating safety conditions, decide on shutting down a plant, and/or monitor lessons learned from previous incidents?
A: One of the key objectives of the NRC inspection program is to determine the causes of declining performance before such performance reaches a level that may result in an undue risk to public health and safety. The inspection program focuses on activities and systems that are risk significant, that is, those activities and systems that have a potential to trigger an accident, can mitigate the effects of an accident, or increase the consequences of a possible accident. The inspection program also evaluates the "cross-cutting issues" of human performance, the "safety-conscious work environment," and how the utilities find and fix problems. Inspections beyond the baseline will be performed at plants with performance below established thresholds, as assessed through information gained from performance indicators and NRC inspections. Additional inspections may also be performed in response to a specific event or problem which may arise at a plant. As a result of the Davis Besse lessons learned, the staff has instituted several changes to the Reactor Oversight Process (ROP), which the staff believes should improve the agency's performance in this area. These changes include more discrete guidance for the processing of cross-cutting issues, and more focused inspections of longstanding equipment issues and equipment trends. Future changes include strengthening inspection guidance to consider operating experience.
In addition to the inspection activities discussed above, the NRC staff uses the allegation program to provide insights on licensee performance. The staff reviews data concerning allegations that the agency receives to identify any trends that may indicate a change in the work environment at a licensee's facility. Based on the results of these reviews and the results of follow-up activities regarding individual allegations, the staff determines whether the trend in allegations is indicative of a decline in the licensee's work environment.
The insights the staff gains from our inspection activities, performance indicators, and the analyses of allegation trends are considered during the ROP mid-cycle and end-of-cycle assessments. The assessment process enables the agency to arrive at objective conclusions about the licensee's safety performance. Based on this assessment information, the NRC determines the appropriate level of agency response, including supplemental inspection and pertinent regulatory actions ranging from management meetings up to and including orders for plant shutdown. If the NRC determines that there may be potential issues with a licensee's safety conscious work environment or safety culture, then this concern is elevated to NRC management for further discussion and evaluation. This may lead to possible action, such as the staffs current efforts at Salem and Hope Creek.
In addition, NRC senior management will review the adequacy of agency actions for plants with significant performance problems. The managers will also take a wider view both of the overall industry performance and of the performance of the agency's regulatory programs. The performance of plants requiring heightened agency scrutiny will then be discussed during a public meeting with the NRC Commissioners.