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Category:Letter
MONTHYEARML24297A6482024-10-23023 October 2024 5 to the Updated Final Safety Analysis Report, Technical Specification Bases Changes, Technical Requirements Manual Changes, Summary Report and Revised NRC Commitments Report ML24269A2502024-09-26026 September 2024 Acknowledgement of the Withdrawal of the Requested Exemption and License Amendment Request to Remove Tier 1 and Tier 2* Requirements NL-24-0350, Core Operating Limits Report, Cycle 24, Version 22024-09-25025 September 2024 Core Operating Limits Report, Cycle 24, Version 2 NL-24-0369, Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements2024-09-25025 September 2024 Withdrawal of License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2 Requirements ML24243A0072024-09-10010 September 2024 – Correction of Amendment Nos. 223 and 206 Regarding Revision to Technical Specifications to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-24-0337, Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program2024-09-0909 September 2024 Interim 10 CFR 21.21(a)(2) Report Regarding Operation Technology, Inc., ETAP Software Error in Transient Stability Program ML24102A2642024-09-0909 September 2024 – Exemption Request Regarding Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0013) - Letter ML24249A2942024-09-0606 September 2024 Correction of Amendment Nos. 218 and 201 Regarding Revision to Technical Specifications to Use Online Monitoring Methodology 05200025/LER-2024-002, Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve2024-09-0505 September 2024 Manual Reactor Protection System and Automatic Safeguards Actuation Due to an Unexpected Change in Position of a Main Feedwater Pump Minimum Flow Control Valve IR 05000424/20240052024-08-26026 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 1 and 2 - Report 05000424/2024005 and 05000425/2024005 ML24235A1952024-08-22022 August 2024 Updated Inspection Plan for Vogtle Electric Generating Plant, Units 3 and 4 - Report 05200025/2024005 and 05200026/2024005 IR 05000424/20244012024-08-15015 August 2024 4 - Security Baseline Inspection Report 05000424-2024401, 05000425-2024401, 05200025-2024402, and 05200026-2024403 - Cover Letter NL-24-0299, Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information2024-08-14014 August 2024 Exemption Request: Final Safety Analysis Report Update Schedule, Response to Request for Additional Information 05000425/LER-2024-001, Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod2024-08-0909 August 2024 Manual Actuation of the Reactor Protection System Due to a Rod Control Fuse Opening Causing a Misaligned Shutdown Rod ML24218A1842024-08-0707 August 2024 Examination Report and Cover Letter 05200026/LER-2024-001, Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal2024-08-0606 August 2024 Manual Reactor Protection System Actuation Due to Procedure Not Optimally Sequenced to Reset the Rapid Power Reduction Signal ML24212A1442024-08-0101 August 2024 Integrated Inspection Report 05200025/2024002 and 05200026/2024002 IR 05000424/20240022024-07-29029 July 2024 Integrated Inspection Report 05000424/2024002 and 05000425/2024002 IR 05000424/20244042024-07-26026 July 2024 Material Control and Accounting Program Inspection Report 05000424/2024404 and 05000425/2024404 (Cover Letter) NL-24-0282, License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements2024-07-25025 July 2024 License Amendment Request and Exemption Request: Remove Tier 1 and Tier 2* Requirements NL-24-0126, – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.62024-07-25025 July 2024 – Units 3 and 4, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Action a and SR 3.7.6.6 ML24204A0722024-07-23023 July 2024 Issuance of Amendment No. 225, Regarding LAR to Revise TS 3.7.9 for a one-time Change to Support Nuclear Service Cooling Water Transfer Pump Repairs - Emergency Circumstances NL-24-0286, Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair2024-07-20020 July 2024 Emergency Request to Revise Technical Specification 3.7.9 for a One-Time Change to Support a Unit 1 Nuclear Service Cooling Water Transfer Pump Repair ML24191A4562024-07-19019 July 2024 Request for Relief and Alternative Requirements for Squib (Explosively Actuated) Valves First Test Interval NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24194A0342024-07-12012 July 2024 Review of the Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24191A3792024-07-10010 July 2024 – Initial Test Program and Operational Programs Inspection Report 05200026/2024011 NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0087, License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks2024-06-21021 June 2024 License Amendment Request: Changes to Technical Specification 3.7.6, Main Control Room Emergency Habitability System (Ves) Air Storage Tanks NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24163A0632024-06-12012 June 2024 2024 Licensed Operator Re-qualification Inspection Notification Letter Vogtle, Units 3 & 4 ML24155A1772024-06-0505 June 2024 Regulatory Audit in Support of Review of the LAR to Revise Emergency Diesel Generator Frequency and Voltage Ranges for Technical Specification 3.8.1, Surveillance Requirements NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24094A1402024-05-16016 May 2024 Staff Response to Request for Revision to NRC Staff Assessment of Updated Seismic Hazard Information and Latest Understanding of Seismic Hazards at the Vogtle Plant Site Following the NRC Process for the Ongoing Assessment of Natural Hazard ML24130A2412024-05-13013 May 2024 Integrated Inspection Report 05200025/2024001 and 05200026/2024001 ML24120A1812024-05-13013 May 2024 Request for Withholding Information from Public Disclosure Responses to NRC Request for Additional Information for Refueling Outage IR24 Steam Generator Tube Inspection Report – Enclosure 2 ML24101A2112024-05-11011 May 2024 Expedited Issuance of Amendment No. 198 Change to Technical Specification 5.5.13, Ventilation Filter Testing Program (VFTP) NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 ML24127A2372024-05-0909 May 2024 Initial Test Program and Operational Programs Inspection Report 05200026/2024010 NL-24-0194, Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1)2024-05-0707 May 2024 Revised Request for Relief and Alternative Requirements for Squib Valves First Test Interval (V34-IST-ALT-03-R1) IR 05000424/20244032024-05-0101 May 2024 Cyber Security Inspection Report 05000424/2024403 and 05000425/2024403 Public ML24120A2832024-04-30030 April 2024 Project Manager Reassignment NL-24-0170, Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report2024-04-25025 April 2024 Responses to Second Round NRC Request for Additional Information for Refueling Outage 1 R24 Steam Generator Tube Inspection Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000424/20240012024-04-23023 April 2024 –Integrated Inspection Report 05000424/2024001 and 05000425/2024001 NL-24-0154, Preservice Inspection Progam Owners Activity Report2024-04-16016 April 2024 Preservice Inspection Progam Owners Activity Report 2024-09-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24290A1572024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley and Vogtle 1 and 2 - Alternative Request for Pressurizer Welds (L-2024-LLR-0047) ML24290A1552024-10-16016 October 2024 NRR E-mail Capture - for Your Action - RAI - Farley, Hatch, and Vogtle 1 and 2 - Proposed Alternative Request for Code Case N-572 ML24289A2002024-10-15015 October 2024 NRR E-mail Capture - for Your Action - RAI - Proposed License Amendment Request (LAR) for Vogtle Electric Generating Plant, Units 3 and 4 TS 3.7.6 Action E and SR 3.7.6.5 (L-2024-LLA-0083) ML24199A1592024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information - Vogtle 3 and 4 - Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Report ML24100A7842024-04-0909 April 2024 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle, Units 3 and 4 - Alternative Request for Explosively Actuated Valves (L-2023-LLR-0016) ML24072A3982024-03-12012 March 2024 NRR E-mail Capture - for Your Action - Second Round Request for Additional Information (RAI) - Vogtle, Unit 1 - SG Tube Inspection Report - 1R24 (L-2023-LRO-0067) ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23342A0802023-12-0808 December 2023 NRR E-mail Capture - Request for Additional Information (RAI) - Vogtle, Unit 1 - Review of SG Tube Inspection Report for Refueling Outage 24 (L-2023-LRO-0067) ML23279A2082023-10-0505 October 2023 Issuance of Formal RAIs - Vogtle, Units 1 and 2 - Proposed LAR and Proposed Alternative Request to Revise TS 3.4.14.1 and IST ALT-VR-02 (EPIDs L-2023-LLA-0061 and L-2023-LLR-0023) ML23257A2092023-09-14014 September 2023 NRR E-mail Capture - Formal Issuance of 2nd Round RAIs for Surry Units 1&2 and North Anna Units 1&2 Emergency Plans LAR ML23248A3482023-09-0505 September 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 6 - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23243A9862023-08-31031 August 2023 NRR E-mail Capture - Draft RAIs for EP Staff Augmentation Times LAR (L-2022-LLA-0166) ML23188A1512023-08-0909 August 2023 Round 2 RAIs for LAR 22-002 TS 3.8.3 Inverters-Operating, Completion Time Extension ML23200A0112023-07-18018 July 2023 Document Request for Vogtle Unit 3 RP Inspection ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23193A7832023-07-12012 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - TSTF-339 LAR (L-2023-LLA-0053) ML23065A0612023-03-0303 March 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) 14 - Vogtle - AST, TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML23006A0882023-01-0606 January 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Vogtle - Accident Source Term (Ast), TSTF-51, TSTF-471, and TSTF-490 LAR (L-2022-LLA-0096) ML22348A0332022-12-13013 December 2022 NRR E-mail Capture - for Your Action - RAI - Vogtle, Unit 2 - Steam Generator Tube Inspection Report (L-2022-LRO-0120) ML22192A1042022-08-0101 August 2022 Acceptance of Requested Licensing Action Amendment Request Application to Allow Use of Lead Test Assemblies for Accident Tolerant Fuel with Request for Additional Information ML22157A0902022-06-0606 June 2022 NRR E-mail Capture - RAIs - Vogtle, Unit 1 - Refueling Outage (RFO) 1R23 Steam Generator (SG) Tube Inspection Report ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22026A3942022-01-26026 January 2022 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21350A1032021-12-16016 December 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21321A3762021-11-15015 November 2021 NRR E-mail Capture - Request for Additional Information - Vogtle, Units 1 and 2, TS 3.7.2 LAR ML21075A0032021-03-12012 March 2021 Emergency Preparedness Exercise Inspection Request for Information for - Brunswick, Catawba, North Anna, Oconee, Vogtle 1 & 2 ML21033B1072021-02-0202 February 2021 NRR E-mail Capture - RAI - Vogtle Unit 1 - SG Report (L-2020-LRO-0059) ML20338A1512020-12-0303 December 2020 NRR E-mail Capture - RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20325A0432020-11-20020 November 2020 NRR E-mail Capture - for Your Review - Draft RAIs for Vogtle GSI-191 LAR (L-2020-LLA-0182) ML20297A3052020-10-22022 October 2020 NRR E-mail Capture - RAIs for Vogtle Relief Request - EPRI Report (L-2020-LLR-0109) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML19263A6432019-09-19019 September 2019 NRR E-mail Capture - RAI - Vogtle End State License Amendment Request (LAR) to Revise the Technical Specifications (Tss) for Vogtle, Units 1 and 2 (L-2019-LLA-0148) ML19156A1872019-06-0505 June 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Vogtle Unit 2 Core Operating Limits Report, Cycle 21 ML19105B1632019-04-15015 April 2019 NRR E-mail Capture - Request for Additional Information (RAI) for Voglte TSTF-412 Adoption LAR (L-2018-LLA-0731) ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18236A4452018-08-30030 August 2018 Review of Response to RAI License Amendment Request for Approval to Utilize the Tornado Missile Risk Evaluator to Analyze Tornado Missile Protection Non-Conformances ML18227A0222018-08-15015 August 2018 Notification of Inspection and Request for Information ML18225A3362018-08-13013 August 2018 NRR E-mail Capture - Request for Additional Information Regarding Relief Request VEGP-ISI-RR-03 ML18197A0602018-07-13013 July 2018 Us NRC Final RAI No. 1 for Vogtle 3 and 4 LAR-18-015, Fire Protection System Non-Safety Cable Spray Removal ML18197A1882018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18197A1052018-07-13013 July 2018 Us NRC Final Request for Additional Information (Final RAI) No. 1 on Vogtle 3 and 4 LAR-17-043, Containment Pressure Analysis ML18192C0782018-07-11011 July 2018 RAI (LAR 18-009) - Vogtle Electric Generating Plant, Unit 3 and 4 ML18192B7692018-07-11011 July 2018 Us NRC Draft Request for Additional Information (Draft RAI) No. 4 on Vogtle LAR-17-024, Technical Specification Updates for Reactivity Controls and Other Miscellaneous Changes ML18136A4972018-06-0101 June 2018 Request for Additional Information, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML18109A1152018-05-0101 May 2018 Request for Additional Information ML18079A9572018-03-28028 March 2018 Request for Additional Information Incorporate Seismic Probabilistic Risk Assessment Into the 10 CFR 50.69 Categorization Process (CAC Nos. MF9861 and MF9862; EPID L-2017-LLA-0248) ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18030B0622018-02-0808 February 2018 Request for Additional Information Reverse Technical Specification 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (CAC Nos. MG0240, MG0241; EPID L-2017-LLA-0295) 2024-07-17
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVE N.E., SUITE 1200 ATLANTA, GEORGIA 30303 January 20, 2015 Mr. Brian K. Taber Vice President - Vogtle Southern Nuclear Operating Company, Inc.
Vogtle Electric Generating Plant 7821 River Road Waynesboro, GA 30830
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Mr. Taber:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a problem identification and resolution (PI&R) inspection at your Vogtle Electric Generating Plant Units 1 and 2 during the weeks of March 16 - 20, 2015, and March 30 - April 3, 2015. The inspection team will be led by Mr. Wesley Deschaine, the NRCs Resident Inspector at Sequoyah Nuclear Plant. This inspection will be conducted in accordance with the baseline inspection procedure (IP) 71152, Problem Identification and Resolution, effective date January 31, 2013.
The biennial PI&R inspection and assessment of the licensees Corrective Action Program (CAP) complements and expands upon the resident baseline inspections of routine daily screening of all corrective action program issues, quarterly focused issue reviews, and semiannual trend PI&R reviews.
On January 9, 2015, Mr. Deschaine confirmed with Ms. Karen Morrow of your staff, arrangements for the two-week onsite inspection.
The enclosure lists documents that will be needed prior to the inspection. Please have the referenced information available no later than March 2, 2015. Contact Mr. Deschaine with any questions concerning the requested information. The inspectors will try to minimize your administrative burden by specifically identifying only those documents required for inspection preparation.
If additional documents are needed, they will be requested when identified. Prior to the onsite inspection, Mr. Deschaine will discuss with your staff the following inspection support administrative details: availability of knowledgeable plant engineering and licensing personnel to serve as points of contact during the inspection; method of tracking inspector requests during the inspection; access to licensee computers; working space; arrangements for site access; and other applicable information.
B. Taber 2 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 NRC's 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).
Thank you for your cooperation in this matter. If you have any questions regarding the information requested or the inspection, please contact Mr. Deschaine at (423) 842-8001.
Sincerely,
/RA/
Anthony D. Masters, Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos.: 05000424, 05000425 License Nos.: NPF-68 and NPF-81
Enclosure:
Information Request for Vogtle Electric Generating Plant Problem Identification and Resolution Inspection cc Distribution via ListServ
_________________________ SUNSI REVIEW COMPLETE FORM 665 ATTACHED OFFICE RII:DRP RII:DRP SIGNATURE Via email ADM2 /RA/
NAME WDeschaine AMasters DATE 1/20/2015 1/20/2015 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO B. Taber 3 Letter to Brian K. Taber from Anthony D. Masters dated January 20, 2015.
SUBJECT:
VOGTLE ELECTRIC GENERATING PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION DISTRIBUTION:
D. Gamberoni, RII EICS L. Gibson, RII EICS OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMVogtleResource
INFORMATION REQUEST FOR VOGTLE ELECTRIC GENERATING PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (March 16 - 20, 2015 and March 30 - April 3, 2015)
Note: Unless otherwise noted, the information requested below corresponds to documents generated since February 2013. Please provide the requested documents in electronic format.
If the information is not available in electronic format, please contact the inspection team leader to coordinate other available methods to provide the information.
- 1. Copies of the corporate and site level procedures and sub-tier procedures associated with the corrective action program. This should include procedures related to:
(a) Corrective action process (b) Cause evaluation (c) Operating experience program (d) Employee concerns program (e) Self-assessment program (f) Maintenance rule program and implementing procedures (g) Operability determination process (h) Degraded/non-conforming condition process (e.g., RIS 2005-20)
(i) System health process or equivalent equipment reliability improvement programs (j) Preventive maintenance deferral and Condition Report (CR) extension process If any of the procedures requested above were revised after February 2013, please provide (or have available) copies of all revisions during the onsite inspection.
- 2. List of top ten risk-significant systems, top ten risk-significant components for each one of the top ten risk-significant systems, and top ten risk-significant operator manual actions
- 3. List of all CRs initiated including the following information for each CR:
(a) CR number (b) Brief, but complete problem description (c) Priority or level (d) Affected system (e) Affected component (f) Responsible plant department (g) CR completion status If possible, provide this list in a format compatible with spreadsheet software (example shown below)
CR # Problem Priority System Component Org Status CR001 A RHR Pump 2 RHR 2-RHR- ENG Open failed flow criteria PMP-A per SR 5.0.5.4 Enclosure
2
- 4. List of outstanding corrective actions including the following information for each action:
(a) Corrective action number (b) Corrective action type (e.g., corrective action to prevent recurrence, enhancement, maintenance rule evaluation, etc)
(c) Brief, but complete corrective action description (d) Associated CR number (e) Corrective action initiation date (f) Number of Extensions (g) Corrective action due date (h) Completion status If possible, provide this list in a format compatible with spreadsheet software (example shown below)
Corrective Type Description CR Initiation Extensions Due Status Action # Date Date AR0034 CAPR Revise CR0058 01/05/08 2 06/15/08 Closed Procedure NGK-003-4585
- 5. List of control room deficiencies with a brief description and corresponding CR and/or work order (WO) number
- 6. List of operator workarounds and operator burdens with a brief description and corresponding CR number
- 7. List of all currently extended CRs or overdue, sorted by initiation date, with the following information:
(a) CR number (b) Priority or Significance (c) CR title and short description
- 8. List of all CRs that have been voided or cancelled. Please provide the following information for each CR:
(a) CR Number (b) Brief, but complete problem description (c) Reason voided or cancelled
- 9. List of all structures, systems, and components (SSCs) which were classified as (a)(1) in accordance with the Maintenance Rule since February 2013. Please include the following information for each system in (a)(1):
(a) Date of classification in (a)(1)
(b) Reason for being placed in (a)(1)
(c) Planned actions and their status
3
- 10. List of Maintenance Preventable Functional Failures (MPFF) of risk significant systems.
Please include actions completed and current status.
- 11. List of corrective maintenance work orders. Please include the following information for each work order:
(a) WO number (b) Brief, but complete work description (c) Affected system and components (d) Date of initiation (e) Date of completion (if completed)
If possible, provide this list in a format compatible with spreadsheet software (example shown below)
Work Description System Component Initiation Due Status Order # Date Date WO01345 Replace breaker SI 2A-SI-PMP, 01/05/08 03/15/09 Closed 2A-BKR-08-BB4 BKR-08-BB4 for 2A SI Pump.
- 12. Corrective action closeout packages, including CRs with description of corrective actions, for all NRC findings and Licensee identified violations. Please include a cross reference linking NRC Finding numbers and LIVs to appropriate CR numbers.
- 13. Corrective action closeout packages, including CRs with description of corrective actions, for all licensee event reports (LERs) issued. Please include a cross reference linking LER number to appropriate CR number.
- 14. List of all NRC generic communications (e.g., Information Notices, Generic Letters, etc.)
and industry operating experience (OE) documents (e.g., Part 21 reports, vendor information letters, information from other sites, etc.,) evaluated by the site for applicability to the station, regardless of the determination of applicability. Please include the reference number (e.g., CR #) for the documents that evaluated the aforementioned OE information.
- 15. Copies of all quality assurance audits and/or assessments issued, including the last two audits/assessments of the corrective action program.
- 16. Copies of all department self-assessments for those programs related to the Corrective Action Program (e.g. Operating Experience, Maintenance Rule, etc)
- 17. Copy of the most recent integrated plant trend report, departmental trend report(s), and corrective action trend report, including any human performance and equipment reliability trends
- 18. Copy of the latest Corrective Action Program statistics (if exists) such as the number of CRs initiated by department, human performance errors by department, and others as may be available
4
- 19. Copies of any minutes of meetings by the offsite safety review boards/groups. In addition, please provide a list of routine meetings involving the CAP to be held while team is onsite.
- 20. List of CRs related to equipment aging issues in the top ten risk significant systems since February 2010 (e.g., system erosion and/or corrosion problems; electronic component aging or obsolescence of circuit boards, power supplies, relays, etc.;
environmental qualification). Please provide the following information for each CR:
(a) CR number (b) Priority (c) CR problem description
- 21. If performed, please provide any recent self-assessment of the site safety culture.
- 22. Copies of corrective action program documents related to cross-cutting issues (human performance, problem identification and resolution, and safety conscious work environment) identified via trending, self-assessments, safety review committee or other oversight methods
- 23. List of all root cause evaluations with a brief description
- 24. Copy of Probabilistic Risk Assessment importance measures report, if available
- 25. System Health Reports, system design basis documents, and system description information for the top ten risk significant systems