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Category:Letter
MONTHYEARULNRC-06853, Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.7172024-01-29029 January 2024 Submittal of 2023 Fitness for Duty Performance Data Per Per 10 CFR 26.717 IR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 ML24008A0552024-01-19019 January 2024 Acceptance of Requested Licensing Action - Proposed Alternative to the Requirements of the ASME Code (EPID L-2023-LLR- 0061) ML23353A1712024-01-18018 January 2024 Issuance of Amendment No. 237 to Clarify Support System Requirements for the Residual Heat Removal System and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23317A0012024-01-12012 January 2024 Audit Summary Regarding LAR to Clarify Support System Requirements for the Residual Heat Removal and Control Room Air Conditioning System Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 ML23347A1212024-01-11011 January 2024 Issuance of Amendment No. 236 to Adopt TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control EPID L-2023-LLA-0046) ML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) ULNRC-06847, Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01)2023-12-21021 December 2023 Supplement to Relief Request from Requirements of ASME BPV Code, Section XI, Subsection Iwl Regarding Examination and Testing of the Unbonded Post-Tensioning System (Relief Request C3R-01) ULNRC-06849, License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds2023-12-20020 December 2023 License Renewal Resolution for Commitments 34 and 35 Perform Evaluation of Crack Initiation and Propagation in Steam Generator Divider Plate and Tube-To-Tubesheet Welds ML23346A0392023-12-14014 December 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Relief from Requirements of ASME Code, Section Xl, Examination and Testing Unbonded Post-Tensioning System ULNRC-06844, Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification2023-12-0707 December 2023 Request for Exemption from Specific Requirements in 2023 Security Rule, Enhanced Weapons, Firearms Background Checks, and Security Event Notification 05000483/LER-2023-001, Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications2023-11-29029 November 2023 Submittal of LER 2023-001-00 for Callaway, Unit 1, Inoperable Instrument Tunnel Sump Level Indication Resulted in Condition Prohibited by Technical Specifications ULNRC-06827, Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029)2023-11-20020 November 2023 Supplement to License Amendment Request Regarding Support System Requirements for Residual Heat Removal and Control Room Air Conditioning Systems Under Technical Specifications 3.4.8, 3.7.11, and 3.9.6 (LDCN 22-0029) IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23297A2502023-11-0606 November 2023 Individual Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination and Opportunity for a Hearing (EPID L-2022-LLA-0176) - Letter IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report ML23240A3692023-10-0505 October 2023 Issuance of Amendment No. 235 to Revise Technical Specifications to Use of Framatome Gaia Fuel (EPID L-2022-LLA-0150) (Non-Proprietary) ML23234A1522023-10-0505 October 2023 Exemption from the Requirements of 10 CFR Part 50, Section 50.46, and Appendix K Regarding Use of M5 Cladding Material (EPID L-2022-LLE-0030) (Letter) ML23305A0942023-10-0202 October 2023 10-CW-2023-09 Post-Exam Submittal ML23270B9662023-09-27027 September 2023 10 CFR 50.55a(z)(I) Request for Relief from ASME OM Code Pump and Valve Testing Requirements for Fifth 120-Month Inservice Testing Interval ML23228A0252023-09-25025 September 2023 Issuance of Amendment No. 234 to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML23261C3852023-09-25025 September 2023 Safety Evaluation for Operating Quality Assurance Manual Revision 36A ML23166B0882023-09-20020 September 2023 Issuance of Amendment No. 233 for Adoption of Alternative Source Term and Revision of Technical Specifications ML23206A1992023-09-15015 September 2023 Regulatory Audit Summary Regarding License Amendment and Regulatory Exemptions Request for Fuel Transition to Framatome Gaia Fuel (Epids L-2022-LLA-0150 and L-2022-LLE-0030) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 ML23240A7572023-08-31031 August 2023 NRC Initial Operator Licensing Examination Approval 05000483/2023301 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ULNRC-06824, Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A2023-08-17017 August 2023 Response to Request for Additional Information Regarding Operating Quality Assurance Manual (Oqam) Revision 36A ML23219A1392023-08-15015 August 2023 Request for Withholding Information from Public Disclosure ULNRC-06830, Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak2023-08-15015 August 2023 Transmittal of Updated Technical Specification Markup and Clean Pages for License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak ML23215A1972023-08-0303 August 2023 Supplement to License Amendment and Exemption Request Regarding Use of Framatome Gaia Fuel (LDCN 22-0002) ULNRC-06223, Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004)2023-07-25025 July 2023 Minor Correction to License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies (LDCN 2020-0004) ULNRC-06799, Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications2023-07-13013 July 2023 Submittal of Licensee Event Report 2022-003-01, Class 1E Electrical Air Conditioning System Thermal Expansion Valve Failure Resulted in Condition Prohibited by Technical Specifications IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23171A9942023-06-22022 June 2023 Acceptance of Request for Approval of Operating Quality Assurance Manual Revision 36a ULNRC-06821, Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301)2023-06-21021 June 2023 Post-Audit Follow-Up Information in Support of Callaway'S License Amendment Request and Proposed Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (EPID L-2022-LLA-0150 and EPID L-2022-LLE-00301) IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ULNRC-06822, Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a2023-06-14014 June 2023 Additional Information Regarding Request for NRC Approval of Operating Quality Assurance Manual (Oqam) Revision 36a ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ULNRC-06815, Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a2023-06-0505 June 2023 Request for NRC Approval of Operating Quality Assurance Manual, Revision 36a ULNRC-06818, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate .2023-06-0505 June 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate . ML23093A0952023-05-10010 May 2023 Issuance of Amendment No. 232 Regarding Technical Specification Changes for Spent Fuel Storage ULNRC-06816, Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015)2023-05-0909 May 2023 Withdrawal of Previously Submitted Enclosures Regarding License Amendment Request for Adoption of Alternative Source Term and Revision of Technical Specifications (LDCN 21-0015) ML23129A7942023-05-0909 May 2023 Post-Audit Supplement to License Amendment Request and Exemption to Allow Use of Framatome Gaia Fuel (LDCN 22-0002) (Iepid L-2022-LLA-0150 and EPID L-2022-LLE-0030) ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections ML23118A3492023-05-0808 May 2023 Request for Withholding Information from Public Disclosure 2024-01-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21319A0062021-11-30030 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21159A2352021-06-17017 June 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000483/2021003) and Request for Information ML21130A5882021-05-11011 May 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions to Adopt a Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004 02 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20280A5442020-03-25025 March 2020 Cwy 2020 PIR Request for Information ML20064B6582020-02-27027 February 2020 Second, Third, and Fourth Request for Information for Callaway Dba Teams Inspection 2020011 ML19317E6332019-11-13013 November 2019 Request for Supporting Information for the Callaway SPRA Audit Review ML19107A5152019-04-11011 April 2019 Cwy 2019410 RFI Cyber Security Gap ML19078A2932019-03-18018 March 2019 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2019010) and Request for Information ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information ML19009A3442019-01-0909 January 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Plant Class 1E LAR, L-2018-LLA-0062 ML18355A4882018-12-20020 December 2018 NRR E-mail Capture - Formal Release of RAI Ref: Callaway Plant EAL Changes, L-2018-LLA-0239 ML18331A2052018-11-27027 November 2018 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Relief Request EPID L-2018-LLR-0051 ML18025B4672018-01-24024 January 2018 NRR E-mail Capture - Request for Extension of Due Date for RAI Response ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection ML17142A1352017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000483/2017007) and Initial Request for Information ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 ML17038A2292017-02-0707 February 2017 NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474 ML16111B3222016-04-20020 April 2016 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000483/2016007) and Request for Information ML15316A1532015-11-12012 November 2015 Request for Additional Information Email, Relief Request 13R-11 (Pressurizer Welds) from Code Case N-460 Requirements, Third 10-Year Inservice Inspection Interval ML15096A0942015-04-0606 April 2015 Notification of Inspection (NRC Inspection Report 05000483/2015003) and Request for Information ML14353A1172014-12-22022 December 2014 Request for Additional Information, Round 3, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14294A7752014-10-28028 October 2014 Request for Additional Information, Round 2, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14203A0632014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Rv ISI Frequency from 10 to 20 Years, Third 10-Year ISI Interval ML14178A8232014-07-0101 July 2014 Request for Additional Information, License Amendment Request to Revise Final Safety Analysis Report- Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ULNRC-06117, Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses2014-04-24024 April 2014 Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses ML14114A1102014-04-24024 April 2014 License Revewal Application, Request for Additional Information (RAI) Set 31 Responses 2023-07-19
[Table view] Category:Inspection Report
MONTHYEARIR 05000483/20230042024-01-19019 January 2024 Integrated Inspection Report 05000483/2023004 IR 05000483/20230102023-11-15015 November 2023 NRC License Renewal Phase 1 Inspection Report 05000483 2023010 IR 05000483/20233012023-11-0909 November 2023 NRC Examination Report 05000483-2023301 ML23293A2652023-10-24024 October 2023 3rd Quarter 2023 Integrated Inspection Report IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) IR 05000483/20234012023-09-13013 September 2023 NRC Security Baseline Inspection Report 05000483/2023401 IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 IR 05000483/20230022023-07-10010 July 2023 Integrated Inspection Report 05000483/2023002 IR 05000483/20230112023-06-15015 June 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000483/2023011 ML23122A3172023-05-0808 May 2023 Review of the Spring 2022 Steam Generator Tube Inservice Inspections IR 05000483/20230012023-04-12012 April 2023 Integrated Inspection Report 05000483/2023001 IR 05000483/20234022023-03-29029 March 2023 NRC Security Baseline Inspection Report 05000483/2023402 IR 05000483/20220062023-03-0101 March 2023 Annual Assessment Letter for Callaway Plant (Report 05000483/2022006) ML23019A0802023-01-19019 January 2023 Notification of Comprehensive Engineering Team Inspection (05000483/2023011) and Request for Information IR 05000483/20220042023-01-12012 January 2023 Integrated Inspection Report 05000483/2022004 IR 05000483/20220132022-11-15015 November 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000483/2022013 IR 05000483/20220032022-10-17017 October 2022 Integrated Inspection Report 05000483/2022003 IR 05000483/20220102022-10-12012 October 2022 Biennial Problem Identification and Resolution Inspection Report 05000483-2022010 - Draft IR 05000483/20224032022-09-27027 September 2022 Security Baseline Inspection Report 05000483/2022403 IR 05000483/20220052022-08-23023 August 2022 Updated Inspection Plan for Callaway Plant (Report 05000483/2022005) IR 05000483/20224022022-08-11011 August 2022 NRC Security Inspection Report 05000483/2022402 (Cover Letter Only) IR 05000483/20220112022-08-0202 August 2022 Triennial Fire Protection Inspection Report 05000483 2022011 IR 05000483/20220022022-07-27027 July 2022 Integrated Inspection Report 05000483/2022002 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information IR 05000483/20220402022-05-0606 May 2022 95001 Supplemental Inspection Report 05000483/2022040 and Follow-Up Assessment Letter IR 05000483/20224012022-05-0505 May 2022 Cyber Security Inspection Report 05000483/2022401 IR 05000483/20220012022-04-26026 April 2022 Integrated Inspection Report 05000483/2022001 IR 05000483/20223012022-04-12012 April 2022 NRC Examination Report 05000483/2022301 ML22082A2012022-03-28028 March 2022 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2022011) and Request for Information IR 05000483/20224042022-03-24024 March 2022 Final Security Baseline Inspection Report 05000483/2022404 (Letter) IR 05000483/20210062022-03-0202 March 2022 Annual Assessment Letter for Callaway Plant (Report 05000483/2021006) IR 05000483/20210042022-01-0707 January 2022 Integrated Inspection Report - 05000483/2021004 IR 05000483/20210032021-11-0808 November 2021 Integrated Inspection Report 05000483/2021003 IR 05000483/20214202021-10-29029 October 2021 NRC Security Baseline Inspection Cover Letter 050004832021420 IR 05000483/20214022021-10-26026 October 2021 Security Baseline Inspection Report 05000483/2021402 IR 05000483/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Callaway Plant (Report 05000483/2021005) IR 05000483/20210022021-08-0505 August 2021 Integrated Inspection Report 05000483/2021002 and Independent Spent Fuel Storage Installation Report 07201045/2021001 IR 05000483/20214012021-05-26026 May 2021 Security Baseline Inspection Report 05000483/2021401 IR 05000483/20210012021-05-11011 May 2021 Integrated Inspection Report 05000483/2021001 IR 05000483/20214032021-04-15015 April 2021 Material Control and Accounting Program Inspection Report 05000483-2021403 (Public) IR 05000483/20200042021-02-0909 February 2021 CWY2020004-RP-DSB, Callaway Plant - Integrated Inspection Report and Assessment Follow-Up Letter (05000483/2020004) IR 05000483/20200032020-11-0202 November 2020 Integrated Inspection Report 05000483/2020003 IR 05000483/20204112020-10-27027 October 2020 Security Baseline Inspection Report 05000483/2020411 IR 05000483/20203012020-10-13013 October 2020 NRC Examination Report 05000483/2020301 IR 05000483/20200052020-09-0101 September 2020 Updated Inspection Plan for Callaway Plant (Report 05000483/2020005) IR 05000483/20200022020-07-29029 July 2020 Integrated Inspection Report 05000483/2020002 IR 05000483/20200102020-06-12012 June 2020 Biennial Problem Identification and Resolution Inspection Report 05000483/2020010 IR 05000483/20204102020-04-24024 April 2020 NRC Security Inspection Report 05000483/2020410 IR 05000483/20200012020-04-20020 April 2020 Integrated Inspection Report 05000483/2020001 IR 05000483/20200112020-04-15015 April 2020 Design Basis Assurance Inspection (Teams) Inspection Report 05000483/2020011 2024-01-19
[Table view] |
See also: IR 05000483/2011005
Text
UNITED STATES
NU CLE AR RE G ULAT O RY CO M M I S S I O N
R E GI ON I V
612 EAST LAMAR BLVD , SU ITE 400
AR LIN GTON , TEXAS 76011-4125
August 4, 2011
Mr. Adam C. Heflin, Senior Vice
President and Chief Nuclear Officer
Union Electric Company
P.O. Box 620
Fulton, MO 65251
SUBJECT: CALLAWAY PLANT - NOTIFICATION OF INSPECTION (NRC INSPECTION
REPORT 05000483/2011005) AND REQUEST FOR INFORMATION
Dear Mr. Heflin:
From October 17 to October 28, 2011, reactor inspectors from the Nuclear Regulatory
Commissions (NRC) Region IV office will perform the baseline inservice inspection at your
Callaway Plant, using NRC Inspection Procedure 71111.08, Inservice Inspection Activities.
Experience has shown that this inspection is a resource intensive inspection both for the NRC
inspectors and your staff. In order to minimize the impact to your onsite resources and to
ensure a productive inspection, we have enclosed a request for documents needed for this
inspection. These documents have been divided into two groups. The first group (Section A of
the enclosure), due by September 26, identifies information to be provided prior to the
inspection to ensure that the inspectors are adequately prepared. The second group (Section B
of the enclosure) identifies the information the inspectors 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 have discussed the schedule for these inspection activities with your staff and understand
that our regulatory contact for this inspection will be Mr. Steve Petzel of your licensing
organization. Our inspection dates are subject to change based on your updated schedule of
outage activities. If there are any questions about this inspection or the material requested,
please contact the lead inspector Dustin Reinert at (817) 860-8244 (dustin.reinert@nrc.gov).
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. 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.
Union Electric Company -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 NRCs 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/
Gregory E. Werner, Chief
Plant Support Branch 2
Division of Reactor Safety
Docket: 50-483
License: NPF-30
Enclosure:
Inservice Inspection Document Request
Distribution via ListServ for Callaway Plant
Union Electric Company -3-
Electronic distribution by RIV:
Regional Administrator (Elmo.Collins@nrc.gov)
Deputy Regional Administrator (Art.Howell@nrc.gov)
DRP Director (Kriss.Kennedy@nrc.gov)
Acting DRP Deputy Director (Jeff.Clark@nrc.gov)
DRS Director (Anton.Vegel@nrc.gov)
Acting DRS Deputy Director (Robert.Caldwell@nrc.gov)
Senior Resident Inspector (David.Dumbacher@nrc.gov)
Branch Chief, DRP/B (Geoffrey.Miller@nrc.gov)
Senior Project Engineer, DRP/B (Rick.Deese@nrc.gov)
Project Engineer, DRP/B (Nestor.Makris@nrc.gov)
CWY Administrative Assistant (Dawn.Yancey@nrc.gov)
Public Affairs Officer (Victor.Dricks@nrc.gov)
Public Affairs Officer (Lara.Uselding@nrc.gov)
Project Manager (Mohan.Thadani@nrc.gov)
Acting Branch Chief, DRS/TSB (Dale.Powers@nrc.gov)
RITS Coordinator (Marisa.Herrera@nrc.gov)
Regional Counsel (Karla.Fuller@nrc.gov)
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SUNSI Review Completed: ___Y___ ADAMS: 7 Yes No Initials: __DRR___
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R:\_REACTORS\_CW\2011\CW2011005-ISI RFI LTR-drr.doc ML112200187
RI:EB1 RI:EB1 C:PSB2
D. Reinert A. Fairbanks G. Werner
/RA/ /RA/ /RA/
08/03/2011 08/03/2011 08/04/2011
OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: October 17 through October 28, 2011
Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities
Inspectors: Dustin Reinert, Reactor Inspector (Lead Inspector - ISI)
Abin Fairbanks, Reactor Inspector
A. Information Requested for the In-Office Preparation Week
The following information should be sent to the Region IV office in hard copy or
electronic format (ims.certrec.com preferred), in care of Dustin Reinert, by
September 26, 2011, to facilitate the selection of specific items that will be reviewed
during the onsite inspection week. The inspectors will select specific items from the
information requested below and then request from your staff additional documents
needed during the onsite inspection week (Section B of this enclosure). We ask that the
specific items selected from the lists be available and ready for review on the first day of
inspection. Please provide requested documentation electronically if possible. If
requested documents are large and only hard copy formats are available, please inform
the inspector(s), and provide subject documentation during the first day of the onsite
inspection. If you have any questions regarding this information request, please call the
inspector as soon as possible.
A.1 ISI/Welding Programs and Schedule Information
a) A detailed schedule (including preliminary dates) of:
i) Nondestructive examinations planned for Class 1 & 2 systems and
containment, performed as part of your ASME Section XI, risk informed (if
applicable), and augmented inservice inspection programs during the
upcoming outage;
Provide a status summary of the nondestructive examination inspection
activities vs. the required inspection period percentages for this interval
by category per ASME Section XI, IWX-2400. Do not provide separately
if other documentation requested contains this information;
ii) Reactor pressure vessel head examinations planned for the upcoming
outage;
iii) Examinations planned for Alloy 82/182/600 components that are not
included in the Section XI scope (If applicable);
iv) Examinations planned as part of your boric acid corrosion control
program (Mode 3 walkdowns, bolted connection walkdowns, etc.); and
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v) Welding activities that are scheduled to be completed during the
upcoming outage (ASME Class 1, 2, or 3 structures, systems, or
components).
b) A copy of ASME Section XI Code Relief Requests and associated NRC safety
evaluations applicable to the examinations identified above.
c) A list of nondestructive examination reports (ultrasonic, radiography, magnetic
particle, dye penetrant, Visual VT-1, VT-2, and VT-3), which have identified
relevant conditions on Code Class 1 & 2 systems since the beginning of the last
refueling outage. This should include the previousSection XI pressure test(s)
conducted during start up and any evaluations associated with the results of the
pressure tests. Also, include in the list the nondestructive examination reports
with relevant conditions in the reactor pressure vessel head penetration nozzles
that have been accepted for continued service. The list of nondestructive
examination reports should include a brief description of the structures, systems,
or components where the relevant condition was identified.
d) A list with a brief description (e.g., system, material, pipe size, weld number, and
nondestructive examinations performed) of the welds in Code Class 1 and 2
systems which have been fabricated due to component repair/replacement
activities since the beginning of the last refueling outage, or are planned to be
fabricated this refueling outage.
e) If reactor vessel weld examinations required by the ASME Code are scheduled to
occur during the upcoming outage, provide a detailed description of the welds to
be examined and the extent of the planned examination. Please also provide
reference numbers for applicable procedures that will be used to conduct these
examinations.
f) 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.
g) A list of any temporary noncode repairs in service (e.g., pinhole leaks).
h) Please provide copies of the most recent self-assessments for the inservice
inspection, welding, and Alloy 600 programs.
A.2 Reactor Pressure Vessel Head
a) Provide the detailed scope of the planned nondestructive examinations of the
reactor vessel head which identifies the types of nondestructive examination
methods to be used on each specific part of the vessel head to fulfill
commitments made in response to NRC Bulletin 2002-02 and
NRC Order EA-03-009. Also, include examination scope expansion criteria and
planned expansion sample sizes if relevant conditions are identified. (If
applicable)
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b) A list of the standards and/or requirements that will be used to evaluate
indications identified during nondestructive examination of the reactor vessel
head (e.g., the specific industry or procedural standards which will be used to
evaluate potential leakage and/or flaw indications).
A.3 Boric Acid Corrosion Control Program
a) Copy of the procedures that govern the scope, equipment and implementation of
the inspections required to identify boric acid leakage and the procedures for
boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including Code class of the components) that have
been identified since the last refueling outage and associated corrective action
documentation. If during the last cycle, the unit was shutdown, please provide
documentation of containment walkdown inspections performed as part of the
boric acid corrosion control program.
c) Please provide a copy of the most recent self-assessment performed for the
boric acid corrosion control program.
A.4 Steam Generator Tube Inspections
a) A detailed schedule of:
i) Steam generator tube inspection, data analyses, and repair activities for
the upcoming outage
ii) Steam generator secondary side inspection activities for the upcoming
outage
b) Please provide a copy of your steam generator inservice inspection program and
plan. Please include a copy of the operational assessment from last outage and
a copy of the following documents as they become available:
i) Degradation assessment
ii) Condition monitoring assessment
c) If you are planning on modifying your Technical Specifications such that they are
consistent with Technical Specification Task Force Traveler TSTF-449, Steam
Generator Tube Integrity, please provide copies of your correspondence with the
NRC regarding deviations from the standard technical specifications.
d) Copy of steam generator history documentation given to vendors performing
eddy current testing of the steam generators during the upcoming outage.
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e) Copy of steam generator eddy current data analyst guidelines and site validated
eddy current technique specification sheets. Additionally, please provide a copy
of EPRI Appendix H, Examination Technique Specification Sheets, qualification
records.
f) Identify and quantify any steam generator tube leakage experienced during the
previous operating cycle. Also provide documentation identifying which steam
generator was leaking and corrective actions completed or planned for this
condition (If applicable).
g) Provide past history of the condition and issues pertaining to the secondary side
of the steam generators (including items such as loose parts, fouling, top of tube
sheet condition, crud removal amounts, etc.)
h) Provide copies of your most recent self assessments of the steam generator
monitoring, loose parts monitoring, and secondary side water chemistry control
programs.
i) Indicate where the primary, secondary, and resolution analyses are scheduled to
take place.
j) Provide a summary of the scope of the steam generator tube examinations,
including examination methods such as Bobbin, Rotating Pancake, or Plus Point,
and the percentage of tubes to be examined. Do not provide these documents
separately if already included in other information requested.
A.5 Additional Information Related to all Inservice Inspection Activities
a) A list with a brief description of inservice inspection, boric acid corrosion control
program, and steam generator tube inspection related issues (e.g., condition
reports) entered into your corrective action program since the beginning of the
last refueling outage. For example, a list based upon data base searches using
key words related to piping or steam generator tube degradation such as:
inservice inspection, ASME Code,Section XI, NDE, cracks, wear, thinning,
leakage, rust, corrosion, boric acid, or errors in piping/steam generator tube
examinations.
b) Please provide names and phone numbers for the following program leads:
Inservice inspection (examination, planning)
Containment exams
Reactor pressure vessel head exams
Snubbers and supports
Repair and replacement program
Licensing
Site welding engineer
Boric acid corrosion control program
Steam generator inspection activities (site lead and vendor contact)
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B. Information to be Provided Onsite to the Inspector(s) at the Entrance Meeting (October
17, 2011):
B.1 Inservice Inspection / Welding Programs and Schedule Information
a) Updated schedules for inservice inspection/nondestructive examination activities,
including steam generator tube inspections, planned welding activities, and
schedule showing contingency repair plans, if available.
b) For ASME Code Class 1 and 2 welds selected by the inspector from the lists
provided from section A of this enclosure, please provide copies of the following
documentation for each subject weld:
i) Weld data sheet (traveler);
ii) Weld configuration and system location;
iii) Applicable Code Edition and Addenda for weldment;
iv) Applicable Code Edition and Addenda for welding procedures;
v) Applicable weld procedures used to fabricate the welds;
vi) Copies of procedure qualification records supporting the weld procedures
from B.1.b.v;
vii) Copies of mechanical test reports identified in the procedure qualification
records above;
viii) Copies of the nonconformance reports for the selected welds (If
applicable);
ix) Radiographs of the selected welds and access to equipment to allow
viewing radiographs (If radiographic testing was performed);
x) Copies of the preservice examination records for the selected welds;
xi) Copies of welder performance qualifications records applicable to the
selected welds, including documentation that welder maintained
proficiency in the applicable welding processes specified in the weld
procedures (at least 6 months prior to the date of subject work); and
xii) Copies of nondestructive examination personnel qualifications (Visual
inspection, penetrant testing, ultrasonic testing, radiographic testing), as
applicable.
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c) For the inservice inspection related corrective action issues selected by the
inspectors from section A of this enclosure, provide a copy of the corrective
actions and supporting documentation.
d) For the nondestructive examination reports with relevant conditions on Code
Class 1 and 2 systems selected by the inspectors from Section A above, provide
a copy of the examination records, examiner qualification records, and
associated corrective action documents.
e) A copy of (or ready access to) most current revision of the inservice inspection
program manual and plan for the current Interval.
f) For the nondestructive examinations selected by the inspectors from section A of
this enclosure, provide a copy of the nondestructive examination procedures
used to perform the examinations (including calibration and flaw
characterization/sizing procedures). For ultrasonic examination procedures
qualified in accordance with ASME Section XI, Appendix VIII, provide
documentation supporting the procedure qualification (e.g., the EPRI
performance demonstration qualification summary sheets). Also, include
qualification documentation of the specific equipment to be used (e.g., ultrasonic
unit, cables, and transducers including serial numbers) and nondestructive
examination personnel qualification records.
B.2 Reactor Pressure Vessel Head
a) Provide the nondestructive personnel qualification records for the examiners who
will perform examinations of the reactor pressure vessel head.
b) Provide drawings showing the following: (If a visual examination is planned for
the upcoming refueling outage)
i) Reactor pressure vessel head and control rod drive mechanism nozzle
configurations
ii) Reactor pressure vessel head insulation configuration
Note: The drawings listed above should include fabrication drawings for
the nozzle attachment welds as applicable.
c) Copy of nondestructive examination reports from the last reactor pressure vessel
head examination.
d) Copy of evaluation or calculation demonstrating that the scope of the visual
examination of the upper head will meet the 95 percent minimum coverage
required by NRC Order EA-03-009 (If a visual examination is planned for the
upcoming refueling outage).
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e) Provide a copy of the procedures that will be used to identify the source of any
boric acid deposits identified on the reactor pressure vessel head. If no explicit
procedures exist which govern this activity, provide a description of the process
to be followed including personnel responsibilities and expectations.
f) Provide a copy of the updated calculation of effective degradation years for the
reactor pressure vessel head susceptibility ranking.
g) Provide copy of the vendor qualification report(s) that demonstrates the detection
capability of the nondestructive examination equipment used for the reactor
pressure vessel head examinations. Also, identify any changes in equipment
configurations used for the reactor pressure vessel head examinations which
differ from that used in the vendor qualification report(s).
B.3 Boric Acid Corrosion Control Program
a) Please provide boric acid walkdown inspection results, an updated list of boric
acid leaks identified so far this outage, associated corrective action
documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks
identified since the end of the last refueling outage. Please include a status of
corrective actions to repair and/or clean these boric acid leaks. Please identify
specifically which known leaks, if any, have remained in service or will remain in
service as active leaks.
B.4 Steam Generator Tube Inspections
a) Copies of the Examination Technique Specification Sheets and associated
justification for any revisions.
b) Copy of the guidance to be followed if a loose part or foreign material is identified
in the steam generators.
c) Please provide a copy of the eddy current testing procedures used to perform the
steam generator tube inspections (specifically calibration and flaw
characterization/sizing procedures, etc.). Also include documentation for the
specific equipment to be used.
d) Please provide copies of your responses to NRC and industry operating
experience communications such as Generic Letters, Information Notices, etc.
(as applicable to steam generator tube inspections) Do not provide these
documents separately if already included in other information requested such as
the degradation assessment.
e) List of corrective action documents generated by the vendor and/or site with
respect to steam generator inspection activities.
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B.5 Codes and Standards
a) Ready access to (i.e., copies provided to the inspector(s) for use during the
inspection at the onsite inspection location, or room number and location where
available):
i) Applicable Editions of the ASME Code (Sections V, IX, and XI) for the
inservice inspection program and the repair/replacement program
ii) EPRI and industry standards referenced in the procedures used to
perform the steam generator tube eddy current examination
Inspector Contact Information:
Dustin Reinert Abin Fairbanks
Reactor Inspector Reactor Inspector
817-860-8244 817-860-8158
dustin.reinert@nrc.gov abin.fairbanks@nrc.gov
Mailing Address:
US NRC Region IV
Attn: Dustin Reinert
612 E. Lamar Blvd, Suite 400
Arlington, TX 76011
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