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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARU-604788, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 32023-12-12012 December 2023 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 3 U-604703, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 22022-04-14014 April 2022 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 2 U-604687, Post-Outage 90-Day Inservice Inspection (Isi) Summary Report2022-01-21021 January 2022 Post-Outage 90-Day Inservice Inspection (Isi) Summary Report U-604633, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 12021-05-23023 May 2021 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1 U-604555, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 02020-07-13013 July 2020 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0 U-604527, Post Outage 90-Day Lnservice Inspection (ISI) Summary Report2020-01-15015 January 2020 Post Outage 90-Day Lnservice Inspection (ISI) Summary Report NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants U-604457, Third Ten-Year Interval Inservice Testing Program Plan Revision 92018-11-21021 November 2018 Third Ten-Year Interval Inservice Testing Program Plan Revision 9 U-604438, Post Outage 90-Day Lnservice Inspection (ISI) Summary Report2018-08-17017 August 2018 Post Outage 90-Day Lnservice Inspection (ISI) Summary Report ML18233A3982018-08-17017 August 2018 Submittal of Post Outage 90-Day Inservice Inspection (ISI) Summary Report U-604359, Third Ten-Year Interval Lnservice Testing Program Plan, Revision 82017-07-20020 July 2017 Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8 U-604326, Third Ten-Year Interval Inservice Testing Program Plan Revision 72017-03-0808 March 2017 Third Ten-Year Interval Inservice Testing Program Plan Revision 7 U-604303, Post-Outage 90-Day Inservice Inspection Summary Report2016-08-19019 August 2016 Post-Outage 90-Day Inservice Inspection Summary Report U-604262, Third Ten-Year Interval Inservice Testing Program Plan, Revision 62016-02-15015 February 2016 Third Ten-Year Interval Inservice Testing Program Plan, Revision 6 U-604237, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2015-08-14014 August 2015 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report U-604203, Correction to C1R14 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2015-03-23023 March 2015 Correction to C1R14 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report ML14031A2222014-01-28028 January 2014 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report U-604060, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2012-03-21021 March 2012 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report ML11269A0182010-10-12012 October 2010 ISI Program Plan Third Ten-Year Inspection Interval U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval2010-07-12012 July 2010 Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval U-603958, Post-Outage 90-Day Inservice Inspection Summary Report2010-05-0606 May 2010 Post-Outage 90-Day Inservice Inspection Summary Report U-603907, Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan2009-07-31031 July 2009 Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan U-603857, 90-Day Post-Outage Inservice Inspection (ISI) Summary Report2008-05-0505 May 2008 90-Day Post-Outage Inservice Inspection (ISI) Summary Report RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements2007-04-19019 April 2007 Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements U-603774, 90-Day Post-Outage Inservice Inspection (SI) Summary Report2006-05-26026 May 2006 90-Day Post-Outage Inservice Inspection (SI) Summary Report U-603676, Day Post-Outage Inservice Inspection (ISI) Summary Report2004-05-27027 May 2004 Day Post-Outage Inservice Inspection (ISI) Summary Report ML0335802082003-12-24024 December 2003 Ltr Dated 12/24/03 Re Clinton Station Concerning Notification of Baseline Inspection and Request for Information RS-03-188, Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program2003-10-0202 October 2003 Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program U-603571, Day Post-Outage Inservice Inspection (ISI) Summary Report2002-08-0202 August 2002 Day Post-Outage Inservice Inspection (ISI) Summary Report 2023-12-12
[Table view] Category:Letter
MONTHYEARIR 05000461/20230042024-02-0202 February 2024 Integrated Inspection Report 05000461/2023004 ML23361A1572024-01-24024 January 2024 Audit Plan in Support of Review of License Amendment Request Regarding Revision of Technical Specifications Related to Reactor Water Cleanup Isolation ML24004A0792024-01-18018 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0041 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000461/20234022023-12-27027 December 2023 Security Baseline Inspection Report 05000461/2023402 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 IR 05000461/20235012023-12-0505 December 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000461/2023501 ML23284A2512023-11-22022 November 2023 Amendment No. 250 to Adopt TSTF-332 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000461/20230032023-11-0808 November 2023 Integrated Inspection Report 05000461/2023003 ML22300A2212023-11-0202 November 2023 Preliminary Decommissioning Cost Estimate and Fuel Management Plan RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans IR 05000461/20233012023-09-12012 September 2023 NRC Initial License Examination Report 05000461/2023301 RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs IR 05000461/20234202023-08-29029 August 2023 Security Baseline Inspection Report 05000461/2023420 RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation IR 05000461/20230022023-08-0404 August 2023 Integrated Inspection Report 05000461/2023002 RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release ML23209A8102023-07-28028 July 2023 05000461; Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23198A0152023-07-27027 July 2023 License Renewal Application Public Meeting Summary of Pre-Submittal Meeting ML23202A0992023-07-24024 July 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000461/2023004 ML23200A2592023-07-24024 July 2023 June 27, 2023, Clinton Power Station License Renewal Environmental Pre-application Public Meeting-Meeting Summary IR 05000461/20234012023-07-19019 July 2023 Cyber Security Inspection Report 05000461/2023401 ML23194A1662023-07-19019 July 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release ML23191A8772023-07-11011 July 2023 Operator Licensing Examination Approval Clinton Power Station July 2023 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 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release IR 05000461/20230102023-05-26026 May 2023 Triennial Fire Protection Inspection Report 05000461/2023010 RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23143A3182023-05-23023 May 2023 Information Meeting (Open House) with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Clinton Power Station, Unit 1 IR 05000461/20230012023-05-0404 May 2023 Integrated Inspection Report 05000461/2023001 ML23118A3472023-05-0101 May 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Correction of Amendment No. 193 Adoption of TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration EPID L-2022-LLA-0143 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23081A0382023-04-25025 April 2023 County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23061A1632023-03-0303 March 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch 3 IR 05000461/20220062023-03-0101 March 2023 Annual Assessment Letter for Clinton Power Station, Unit 1 (Report 05000461/2022006) RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML23031A2972023-03-0101 March 2023 Issuance of Amendment No. 248 Adoption of TSTF-269, Revision 2 RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 ML23039A1852023-02-10010 February 2023 Integrated Inspection Report 05000461/2022004 07201046/2022001 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 IR 05000461/20220112023-01-27027 January 2023 Biennial Problem Identification and Resolution Inspection Report 05000461/2022011 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing ML23005A0682023-01-0505 January 2023 Notification of NRC Fire Protection Team Inspection Request for Information: Inspection Report 05000461/2023010 ML22341A6042022-12-0808 December 2022 Confirmation of Initial License Examination IR 05000461/20224022022-12-0606 December 2022 Security Baseline Inspection Report 05000461/2022402 RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI 2024-02-02
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December 24, 2003 Mr. John L. Skolds, President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
CLINTON POWER STATION - NOTIFICATION OF NRC INSERVICE BASELINE INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Skolds:
On February 9, 2004, the NRC will begin the Inservice baseline inspection at the Clinton Power Station. This on-site inspection will be performed February 9-13, 2004, in accordance with the NRC baseline Inspection Procedure 71111.08.
Experience has shown that this inspection is resource intensive both for the NRC inspector and your staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group identifies information necessary to ensure that the inspector is adequately prepared. The second group identifies the information the inspector will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
We understand that our regulatory contact for this inspection is Ron Frantz of your organization.
If there are any questions about the inspection or the material requested, please contact the inspector Mel Holmberg at (630) 829-9748.
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 (PARS) component of NRCs
J. Skolds 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).
Sincerely,
/RA by Mel Holmberg Acting for/
David E. Hills, Chief Mechanical Engineering Branch Division of Reactor Safety Docket Nos.50-461 License No. NPF-62
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Site Vice President - Clinton Power Station Clinton Power Station Plant Manager Regulatory Assurance Manager - Clinton Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Manager Licensing - Clinton Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing
J. Skolds 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).
Sincerely,
/RA by Mel Holmberg Acting for/
David E. Hills, Chief Mechanical Engineering Branch Division of Reactor Safety Docket Nos.50-461 License No. NPF-62
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Site Vice President - Clinton Power Station Clinton Power Station Plant Manager Regulatory Assurance Manager - Clinton Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Manager Licensing - Clinton Senior Counsel, Nuclear, Mid-West Regional Operating Group Document Control Desk - Licensing ADAMS Distribution:
AJM DFT JBH1 RidsNrrDipmIipb GEG HBC PLL DRPIII DRSIII PLB1 JRK1 DOCUMENT NAME: ML033580208.wpd 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 C RIII N RIII N NAME MHolmberg:tr TTongue for MHolmberg for AStone DHills DATE 12/24/03 12/24/03 12/24/03 OFFICIAL RECORD COPY
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: February 9 - 13, 2004 Inspection Procedures: IP 7111108 Inservice Inspection Inspector: Mel Holmberg (630) 829-9748 A. Information Requested for the In-Office Preparation Week The following information (electronic copy if practicable - msh@nrc.gov) is requested by January 30, 2004, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and request a list of additional documents needed on-site to your staff.
We request that the specific items selected from the lists be available and ready for review on the first day of inspection. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1) A detailed schedule of nondestructive examinations (NDE) planned for Class 1 and 2 systems and containment, performed as part of your ASME Code Inservice Inspection (ISI) Program during the scheduled inspection week.
- 2) A copy of the procedures used to perform the examinations identified in A.1. For ultrasonic examination procedures qualified in accordance with Appendix VIII, of Section XI of the ASME Code, provide documentation supporting the procedure qualification. This documentation should include the test data identifying the types of defects used in the procedure qualification, the equipment used (cables, probes, transducers including serial numbers) and the Code Edition used for qualification.
Additionally, the data supporting the detection and sizing capability of the procedure is to be provided.
- 3) A copy of any ASME Section XI, Code Relief Requests applicable to the examinations identified in A.1.
- 4) A list identifying NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant, visual (VT-1, VT-2, VT-3)) which have identified relevant indications on Code Class 1 and 2 systems since the beginning of the previous refueling outage. Provide records accepting any of these relevant indications for continued service.
- 5) List of welds in Code Class 1 and 2 systems which have been completed since the beginning of the previous refueling outage (identify system, weld number and reference applicable documentation).
- 6) List with short description of ASME Code repairs or replacements which have been completed since the beginning of the last refueling outage.
1 Enclosure
- 7) If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the inspection period, provide a detailed description of the welds to be examined, and the extent of the planned examination.
- 8) List with description of pressure boundary degradation and ISI related issues (e.g.,
piping/component degradation or damage and errors in piping/component pressure boundary examinations) entered into your corrective action system beginning with the date of the last refueling outage.
- 9) Copy of any 10 CFR Part 21 reports applicable to your structures systems or components within the scope of Section XI of the ASME Code, that have been identified since the beginning of the last refueling outage.
- 10) If NDE of core shroud welds is scheduled to occur during this inspection period, identify the type of NDE, the scope of NDE planned and identify the procedures to be used.
Also, provide a copy of your responses to NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors, and core shroud weld examination schedule.
B. Information to be provided on-site to the inspector at the entrance meeting:
- 1) Updated schedule for item A.1.
- 2) For welds selected by the inspector (A.5 above), provide copies of the following documents:
a) Document of the weld number and location (e.g., system, train, branch);
b) Document with a detail of the weld construction; c) Applicable Code Edition and Addenda for weldment; d) Applicable Code Edition and Addenda for welding procedures; e) Applicable weld procedures (WPS) used to fabricate the welds; f) Copies of procedure qualification records (PQRs) supporting the WPS on selected welds; g) Copies of mechanical test reports identified in the PQRs above; h) Copies of the nonconformance reports for the selected welds; and i) Radiographs of the selected welds and access to equipment to allow viewing radiographs.
- 3) For the repair/replacement activities (A.6 above) selected by the inspector provide a copy of the records of the repair or replacement required by the ASME Code Section XI, Articles IWA -4000 or IWA 7000.
- 4) For the ISI related issues (A.8 above) entered into your corrective action system selected by the inspector provide a copy of the corrective actions and supporting documentation.
2 Enclosure
- 5) For the nondestructive examination reports (A.4 above) with relevant indications on Code Class 1 and 2 systems selected by the inspector provide a copy of the examination records and associated corrective action documents.
- 6) Copy of the most recent quality assurance department audit, which included the ISI program and activities. Copies of documents resolving findings in this audit.
- 7) For core shroud welds examined since the beginning of the previous refueling outage, provide the non-destructive examination records for the core shroud welds inspected.
- 8) If NDE of core shroud welds is scheduled to occur during this inspection period, provide a copy of the procedures to be used and the applicable shroud weld fabrication drawings.
- 9) If NDE of reactor vessel welds is scheduled to occur during this inspection period, provide a copy of the applicable vessel weld fabrication drawings.
- 10) Ready access to the Editions of the ASME Code (Sections V, IX and XI) applicable to the inservice inspection program and the repair/replacement program (e.g., copies provided to the inspector to use for the duration of the inspection at the on-site inspection location).
3 Enclosure