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Category:Memoranda
MONTHYEARML24128A2102024-05-0707 May 2024 Public Meeting Summary - 2023 Annual Assessment Meeting Regarding Saint Lucie ML24047A2092024-02-22022 February 2024 Calendar Year 2023 Baseline Inspection Completion ML23166A0042023-06-15015 June 2023 Summary of Meeting Concerning 2023 Annual Assessment of the Saint Lucie and the Turkey Point Nuclear Plants ML22188A0862022-07-0707 July 2022 SLRA - Audit Report ML22145A3932022-05-25025 May 2022 Public Meeting Summary 2021 Annual Assessment Meeting 20220434 ML21337A1962021-12-16016 December 2021 Public Scoping Meeting Summary for the Environmental Review of the Subsequent License Renewal Application for St. Lucie Plant, Units 1 and 2 ML21159A1352021-06-0808 June 2021 Public Meeting Summary Regarding the Saint Lucie Nuclear Plant, Units 1 and 2, Docket No. 50-335 and 389, and the Turkey Point Nuclear Generating Station Units 3 and 4, Docket No. 50-250 and 50-251; Meeting Number 20210505 ML20150A4732020-05-29029 May 2020 EOC Meeting Summary ML19121A6102019-05-0101 May 2019 Public Meeting Summary - St Lucie Nuclear Plant, Docket Nos. 50-389 and 50-335 ML18144A1452018-05-24024 May 2018 Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ML17103A0342017-04-12012 April 2017 Summary of Category 1 Public Meeting to Discuss the Significance Determination Process for a Finding at St. Lucie, Unit 1 ML16097A1302016-04-0404 April 2016 March 29, 2016 Summary of Public Meeting - 2015 Annual Assessment Regarding Saint Lucie ML15320A5512015-11-23023 November 2015 SER MF5835 ML15240A1542015-09-0808 September 2015 Staff Observations of Sump Strainer Head Loss Testing at Alden Laboratory for Generic Safety Issue 191 ML14163A6522014-06-19019 June 2014 Summary of May 29, 2014, Public Meeting with NextEra Energy, Inc. and Florida Power & Light Company Regarding Proposed Amendment to Transition Fuel Type at St. Lucie Unit 2 ML14156A2132014-06-0404 June 2014 Public Meeting Summary - St. Lucie Nuclear Plant Docket Nos. 50-335 and 50-389 ML13059A5522013-03-0101 March 2013 3/14/13 - Forthcoming Meeting with Florida Power and Light Company Regarding Steam Generator Performance at St. Lucie Nuclear Plant, Units 1 and 2 ML12222A0392012-08-0909 August 2012 8/16/2012 Cancellation Notice of Forthcoming Conference Call with NextEra Energy and Florida Power and Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Proto ML12213A0612012-08-0101 August 2012 8/16/12 Forthcoming Conference Call with NextEra Energy and Florida Power & Light Concerning Generic Letter 2004-02 and Request for NRC Staff Review of Draft Proposed Guideline for Strainer Fiber Bypass Test Protocol ML12150A2992012-06-0505 June 2012 May 17, 2012, Summary of Teleconference Held Between the U.S. Nuclear Regulatory Commission, U.S. Fish and Wildlife Service, and Florida Power & Light Co. to Discuss the Terms of the Biological Opinion at the St. Lucie Plant, Units 1 and 2 ML1204005162012-02-0909 February 2012 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML11251A0052011-09-0909 September 2011 9/21/11 Notice of Forthcoming Meeting with Florida Power and Light Regarding St. Lucie Nuclear Plant, Units 1 and 2 Extended Power Uprate ML11231A7172011-08-25025 August 2011 Notice of Forthcoming Meeting with Florida Power and Light Company (FPL) Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. ML11182A0142011-07-0101 July 2011 Forthcoming Meeting with Florida Power & Light Company Regarding St. Lucie Nuclear Plant, Unit 1 to Discuss Extended Power Uprate License Amendment Request That Is Currently Under Review ML1109006712011-04-21021 April 2011 Acceptance of License Amendment Request for an Extended Power Uprate (Epu), St Lucie Nuclear Plant ML1106104272011-03-0707 March 2011 Notice of Forthcoming Pre-Application Meeting with Florida Power & Light Company and NextEra Energy Regarding Turkey Point, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1, and 2, and Duane Arnold ML1035405732010-12-21021 December 2010 Acceptance of License Amendment Request for an Extended Power Uprate (Epu), St. Lucie Nuclear Plant, Unit 1 ML1025601362010-09-0707 September 2010 Notice of Meeting with Florida Power & Light Company to Discuss the Florida Power & Light Company'S Forthcoming Applications for the Extended Power Uprates of St. Lucie Units 1 & 2 and Turkey Point Units 3 & 4, Focusing on the Topic of Spen ML0921805182009-08-0606 August 2009 Notice of Public Meeting with Florida Power & Light Energy ML0909705822009-04-0707 April 2009 Phone Call Summary with Licensees and Alion Science and Technology on April 2, 2009 to Address NRC Staff Position on Chemical Effects Refinements ML0832502332008-12-0202 December 2008 Summary of Public Meeting with Operators of Vogtle Units 1 & 2, San Onofre Units 2 & 3, St. Lucie Unit 1, Turkey Point Unit 3, Indian Point Units 2 & 3, Nuclear Energy Institute, and Alion Science and Technology ML0826006252008-09-16016 September 2008 Draft Request for Additional Information on Relief Request No. 2 Regarding Structural Weld Overlays ML0820008422008-07-18018 July 2008 Memorandum of the Secretary (Referring a Petition to Intervene to the ASLBP) ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0810502852008-03-11011 March 2008 NDE Report, on PSL-1 Pressurizer Nozzles, Attachment 3 ML0635602592006-12-27027 December 2006 Forthcoming Meeting with Florida Power and Light to Discuss Proposed License Amendment Request to Adopt Alternate Source Term at the St. Lucie Nuclear Plant ML0633303802006-11-29029 November 2006 Forthcoming Meeting with Florida Power & Light Regarding Proposed License Amendment Request to Adopt Alternate Source Term at St. Lucie Nuclear Plant ML0614505922006-05-26026 May 2006 Wits 200600198 - Actions to Be Taken in Response to Hurricane Lessons Learned Task Report ML0609602052006-04-0606 April 2006 Meeting Notice, Florida Power & Light, St. Lucie Unit 2, Steam Generator Tube Inspection During Refueling ML0523704412005-08-31031 August 2005 Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0517402732005-06-23023 June 2005 Notice of Meeting with Florida Power and Light Company (FPL) & Westinghouse LAR to Increase SG Tube Plugging at St. Lucie ML0502701092005-01-25025 January 2005 Safety Evaluation on the Relief Request 2 Associated with the Third 10-year Inservice Inspection Interval - Inservice Inspection Program for St. Lucie Unit 2 ML0419005722004-07-0101 July 2004 Ltr, Temporary Change in Personnel Assignment ML0326809972003-10-0909 October 2003 Renewal of Full-Power Operating Licenses for St. Lucie, Units 1 and 2 ML0324005942003-08-25025 August 2003 June 10-11, 1997, Summary of NRC Senior Management Meeting to Review Performance of Operating Nuclear Power Plants and Materials Facilities Licensed by Nrc. Partially Withheld ML0321800032003-08-0606 August 2003 08/20-21/2003 Notice of Meeting with Florida Power and Light Regarding Increased Steam Generator Tube Plugging and Reload Methodology at St. Lucie, Unit 2 ML0316210252003-06-11011 June 2003 Peer Review of Risk-informed Safety Evaluation of the Suppression Capability in the Cable Spreading Room at St. Lucie Nuclear Power Plant Unit 1 ML0312702872003-05-0707 May 2003 Submission of Draft Request for Additional Information and Summary of a Conference Call Regarding Steam Generator Tubesheet Amendment ML0309808612003-04-0909 April 2003 Corrected Notice for Meeting with FPL to Discuss Requests for Relaxation from Reactor Pressure Vessel Head Inspection Order at St.Lucie, Unit 2 ML0309306732003-04-0303 April 2003 Meeting with FPL to Discuss Requests for Relaxation from Reactor Pressure Head Inspection Order at St. Lucie 2024-05-07
[Table view] Category:Safety Evaluation
MONTHYEARML24255A3092024-09-30030 September 2024 SLRA - Revised SE Letter ML24184B2822024-07-16016 July 2024 – Request to Use a Later Code Edition and Addenda of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML24172A1562024-06-27027 June 2024 Relief Request - PSL2-I5-RR-01 Proposed Alternative to Amse Code XI Code Examination Requirements - System Leakage Test of Reactor Pressure Vessel Bottom Head and Class 1 and 2 Piping in Covered Trenches 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 ML24078A2622024-03-26026 March 2024 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML24017A2092024-03-12012 March 2024 – Issuance of Amendment Nos. 254 and 209 to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML24005A2772024-02-20020 February 2024 Issuance of Amendment Nos. 253 and 208 Regarding Conversion to Improved Standard Technical Specifications ML23219A0032023-09-0101 September 2023 SLRA SER Rev 1 ML23200A1462023-07-21021 July 2023 Safety Evaluation Related to the SLRA of St. Lucie Plant, Units 1 and 2 ML22255A1022022-09-21021 September 2022 Authorization and Safety Evaluation for Alternative Relief Request No. 10 - Hardship or Unusual Difficulty Without Compensating Increase in Level of Quality or Safety ML22038A1872022-02-0909 February 2022 Authorization and Safety Evaluation for Relief Request No. 19 (RR19) - the Use of an Alternative to ASME Code Case N-729-6 for Replacement Reactor Vessel Closure Head Penetration Nozzle 85 ML21342A2092022-01-14014 January 2022 Issuance of Amendment Nos. 252 and 207 to Allow Risk-Informed Completion Times (RICT) for the 120-Volt Alternating Current (AC) Instrument Bus Requirements ML21236A1312021-09-30030 September 2021 Authorization of RR 15 Regarding Extension of ASME Requirements Related to Reactor Pressure Vessel Weld Examinations from 10 to 20 Years ML21022A2192021-02-26026 February 2021 Issuance of Amendment No. 206 to Replace the Current Time-Limited Reactor Coolant System Pressure/Temperature Limit Curves and LTOP Setpoints with Curves and Setpoints That Will Remain Effective for 55 Effective Full Power Years ML21027A2262021-02-17017 February 2021 Approval of Alternative to ASME Code, Section XI to Use an Alternative Inservice Inspection Schedule for the Reaction Vessel Closure Head Bolting ML20329A4022021-02-0303 February 2021 Approval of Alternative to Use ASME Code Case N-513-4 for Alternative Repair of Intake Cooling Water System ML20259A2982020-11-18018 November 2020 Issuance of Amendment No. 205 Regarding Modification of the Reactor Coolant Pump Flywheel Inspection Program ML20237F2572020-10-30030 October 2020 Issuance of Amendment Nos. 251 and 204 Regarding Adoption of Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6 Development of Emergency Action Levels for Non-Passive Reactors ML20099A3482020-06-25025 June 2020 Safety Evaluation for Relief Request for Fifth Ten-Year Inservice Inspection (ISI) Interval - Alternative Risk-Informed Inservice Inspection Program for Class 1 and 2 Piping Welds ML20023B3782020-02-19019 February 2020 Safety Evaluation for Relief Request RR-16, Alternate Repair of 2B Boric Acid Makeup Pump Revision for the Fourth 10-Year Inservice Inspection Interval ML20015A1232020-02-0606 February 2020 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML19266A0722020-01-27027 January 2020 Issuance of Amendment Nos. 250 and 202 Regarding Technical Specification Changes to Allow the Performance of Selected Emergency Diesel Generator Surveillance Requirements During Power Operation ML19254B5332019-09-30030 September 2019 Safety Evaluation for Relief Request RR#15, Revision 0, Regarding Limited Piping Examinations ML19148A7442019-07-31031 July 2019 Issuance of Amendment Nos. 161, 249, 200, 287, and 281 to Add Technical Specification Limiting Condition for Operation 3.0.6 ML19203A1662019-07-26026 July 2019 Issuance of Exigent Amendment No. 248 Technical Specification 3/4.8.1 Change to Allow for a One-Time Extension of the Allowed Outage Time for One Emergency Diesel Generator ML19115A2812019-05-31031 May 2019 Safety Evaluation for Relief Request No. 6 for the Fifth 10 Year Inservice Inspection Interval ML19058A4922019-04-23023 April 2019 Issuance of Amendment 198 Regarding Technical Specification Changes to Reduce the Number of Control Element Assemblies ML18274A2242018-11-0202 November 2018 Issuance of Amendment Nos. 246 and 197 Regarding Technical Specifications Site Area Map ML18256A0982018-10-30030 October 2018 Safety Evaluation for Relief Request No.5 for the Fifth 10-Year Inservice Inspection Interval ML18129A1492018-07-0909 July 2018 Issuance of Amendments Regarding Technical Specification Changes Related to the Auxiliary Feedwater System (CAC Nos. MG0237 and MG0238; EPID L-2017-LLA-0296) ML18106B1212018-04-25025 April 2018 Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques ML18046A7122018-03-26026 March 2018 Issuance of Amendments Regarding the Unusual Event Fire Related Emergency Action Level Scheme ML18018A0332018-01-26026 January 2018 Safety Evaluation of Relief Requests for the Fifth 10-Year Inservice Testing Program (EPID L-2017-LLR-0113; L-2017-LLR-0017, L-2017-LLR-0018, L-2017-LLR-0119, L-2017-LLR-0120, L-2017-LLR-0121, and L-2017-LLR-0122) ML17334A9362018-01-0404 January 2018 Relief from the Requirements of the ASME Code Regarding Relief Request No. 17, Revision 0, for the Fourth 10-Year Inservice Inspection Interval (CAC No. MF9826; EPID L-2017-LLR-0043) ML17341A4422018-01-0404 January 2018 Relief from the Requirements of the ASME Code Relief Request No. 3 for the Fifth 10-Year Inservice Inspection Interval (CAC No. MF9288; EPID L-2017-LLR-0003) ML17257A0152017-10-31031 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to the Reactor Protection System and Limiting Condition for Operation 3.0.5 ML17263A1202017-10-27027 October 2017 Inservice Inspection Plan Fourth 10-Year Interval Relief Request No. 16 (CAC No. MF9827; EPID L-2017-LLR-0044) ML17248A3792017-10-23023 October 2017 Issuance of Amendments to Revise the Renewed Facility Operating Licenses Fire Protection License Conditions (CAC Nos. MF9681 and MF9682; EPID L-2017-LLA-0230) ML17235A5652017-10-0505 October 2017 Issuance of Amendments Regarding Technical Specification Changes Related to Component Cyclic or Transient Limits ML17219A1742017-08-31031 August 2017 Relief from the Requirements of the ASME Code Regarding Relief Request 12 for the Fourth 10-Year Inservice Inspection Interval ML17195A2912017-08-14014 August 2017 Issuance of Amendments Regarding Relocation of Radiation Monitor Requirements from Technical Specifications to Licensee-Controlled Documents ML17132A1672017-07-10010 July 2017 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 13 ML17110A2702017-05-10010 May 2017 Inservice Inspection Plan Fourth 10-year Interval Relief Request No. 14 Rev 0 - ML17027A0782017-04-0707 April 2017 Issuance of Amendments Regarding Technical Specifications for Inservice Testing Programs (CAC Nos. MF8202 Through MF8209) ML17038A2252017-03-29029 March 2017 Issuance of Amendment No. 188 Regarding Emergency Diesel Generator Day Tank Volume ML16330A1182016-12-15015 December 2016 NextEra Fleet - Safety Evaluation for Proposed Alternative to the American Society of Mechanical Engineers Operation and Maintenance Code by Adoption of Approved Code Case OMN-20, Inservice Test Frequency (CAC Nos. MF8195 Through MF8201) ML16251A1282016-12-0505 December 2016 Issuance of Amendments to Update Appendix B to the Renewed Facility Operating License to Incorporate the 2016 Biological Opinion ML16292A7612016-11-0202 November 2016 Inservice Inspection Plan Fourth 10 Year Interval Relief Request No. 11 ML16166A4242016-10-0505 October 2016 St. Lucie Plant, Unit Nos. 1 and 2 - Issuance of Amendments Regarding the Use of a New Computer Code to Model the Containment Vacuum Analyses ML16183A1382016-09-19019 September 2016 Issuance of Amendments Regarding Technical Specification Change to Eliminate the Moderator Temperature Coefficient Surveillance Test at the End of Cycle 2024-09-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVE N.E., SUITE 1200 ATLANTA, GEORGIA 30303 February 9, 2012 Mr. Mano Nazar Executive Vice President Nuclear and Chief Nuclear Officer Florida Power and Light Company P.O. Box 14000 Juno Beach, Florida 33408-0420
SUBJECT:
ST. LUCIE NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION
Dear Mr. Nazar:
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 St.
Lucie Nuclear Plant during the weeks of April 2 - 6 and April 16 - 20, 2012. The inspection team will be led by Thomas Morrissey, a Senior Resident Inspector from the Crystal River Nuclear Power Plant. This inspection will be conducted in accordance with the baseline inspection procedure, Procedure 71152, Problem Identification and Resolution, issued on December 5, 2011.
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 February 1, 2012, Mr. Morrissey confirmed with Mr. Eric Katzman 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, 2012. Contact Mr. Morrissey 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.
FPL 2 If additional documents are needed, they will be requested when identified. Prior to the onsite inspection, Mr. Morrissey 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.
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. Morrissey at (352) 795-7677.
Sincerely,
/RA/
George T. Hopper, Chief Reactor Projects Branch 7 Division of Reactor Projects Docket Nos.: 50-335, 50-389 License Nos.: DPR-67, NPF-16
Enclosure:
INFORMATION REQUEST FOR ST. LUCIE NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION cc w/encl: (See page 3)
PAPERWORK REDUCTION ACT STATEMENT This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget control number.
___ML120400516_______ XSUNSI REVIEW COMPLETE X FORM 665 ATTACHED OFFICE RII:DRP RII:DRP SIGNATURE TXM1 by phone GTH1 NAME TMorrissey GHopper DATE 02/08/2012 02/09/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
FPL 3 cc w/encl:
Richard L. Anderson William A. Passetti Site Vice President Chief St. Lucie Nuclear Plant Florida Bureau of Radiation Control Electronic Mail Distribution Department of Health Electronic Mail Distribution Robert J. Hughes Plant General Manager Bryan Koon St. Lucie Nuclear Plant Director Electronic Mail Distribution Florida Division of Emergency Management Electronic Mail Distribution Gene St. Pierre Vice President, Fleet Support Donna Calabrese Florida Power & Light Company Emergency Preparedness Manager Electronic Mail Distribution St. Lucie Plant Electronic Mail Distribution Daniel D. DeBoer Operations Site Director J. Kammel St. Lucie Nuclear Plant Radiological Emergency Planning Electronic Mail Distribution Administrator Department of Public Safety Eric Katzman Electronic Mail Distribution Licensing Manager St. Lucie Nuclear Plant Senior Resident Inspector Electronic Mail Distribution St. Lucie Nuclear Plant U.S. Nuclear Regulatory Commission Larry Nicholson P.O. Box 6090 Director Jensen Beach, FL 34957-2010 Licensing Florida Power & Light Company Seth B. Duston Electronic Mail Distribution Training Manager St. Lucie Nuclear Plant Alison Brown Electronic Mail Distribution Nuclear Licensing Florida Power & Light Company Faye Outlaw Electronic Mail Distribution County Administrator St. Lucie County Mitch S. Ross Electronic Mail Distribution Vice President and General Counsel Nuclear Jack Southard Florida Power & Light Company Director Electronic Mail Distribution Public Safety Department St. Lucie County Marjan Mashhadi Electronic Mail Distribution Senior Attorney Florida Power & Light Company Electronic Mail Distribution
FPL 4 Letter to Mano Nazar from George T. Hopper dated February 9, 2012
SUBJECT:
ST. LUCIE NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION FOR NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION Distribution w/encl:
C. Evans, RII EICS L. Douglas, RII EICS OE Mail RIDSNRRDIRS PUBLIC RidsNrrPMStLucie Resource
INFORMATION REQUEST FOR ST LUCIE NUCLEAR PLANT PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION (APRIL 2-6 AND APRIL 16-20, 2011)
A. Documents needed prior to the inspection Note: Unless otherwise noted, the information requested below corresponds to documents generated since April 23, 2010. If the information is not available in electronic format, please contact the inspection team leader to coordinate how the information will be provided.
- 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 Nuclear Condition Reports (CR) extension process If any of the procedures requested above were revised after April 23, 2010, 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: If possible please provide this information in a sortable electronic format (MS Excel preferred).
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
- 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 Enclosure
2 d) Associated CR number e) Corrective action initiation date f) Number of Extensions g) Corrective action due date h) Completion status If possible please provide this information in a sortable electronic format (MS Excel preferred). (example shown below)
Corrective Type Description CR Initiation Extensions Due Status Action # Date Date 0034 CAPR Revise 2010-058 01/05/08 2 06/15/08 Open Procedure NGK-003-4585
- 5. List of control room deficiencies with a brief description and corresponding CR and/or work order (WO) number and date identified
- 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 #
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 April 23, 2010. 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
- 10. List of Maintenance Preventable Functional Failures (MPFF) of risk significant systems.
Please include actions completed and current status.
Enclosure
3
- 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 please provide this information in a sortable electronic format (MS Excel preferred). (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 (hard copies available for first onsite inspection week) including CRs with description of corrective actions, for all NRC findings and licensee-identified violations documented in NRC inspection reports issued in CY 2010 and 2011. Please include a cross reference linking NRC Finding numbers and LIVs to appropriate CR numbers.
- 13. Corrective action closeout packages (hard copies available for first onsite inspection week), including CRs with description of corrective actions, for all licensee event reports (LERs) issued in CY 2010 and 2011. 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 Enclosure
4
- 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
- 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 the team is onsite.
- 20. List of CRs related to equipment aging issues in the top ten risk significant systems since April 23, 2007 (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 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.
- 26. Copies of corrective actions completed after September 30, 2010 associated with the Yellow finding documented in NRC Supplemental Inspection report 05000335/2010009.
- 27. List of all corporate CRs associated with St. Lucie, sorted by initiation date, with the following information:
a) CR #
b) Priority or Significance c) CR title and short description B. Review of the above material will help in the selection of systems and components for further review. An additional document request will be made after March 2 to support the Inspection Preparation Week (March 12-17, 2012)
- 1. For the risk significant systems selected by the team leader, please provide copies of the latest System Health Reports, system design basis documents, system description information, and P&IDs.
Enclosure