Letter Sequence RAI |
---|
|
Results
Other: ML12125A181, ML12125A332, ML12131A451, ML12131A473, ML12139A058, ML12180A023, ML12244A571, ML12271A423, ML13029A016, ML14035A575, ML14045A284, ML14052A230, ML14083A617, ML14112A355, ML14112A450, ML14125A199, ML14169A441, ML14169A604, ML14169A637, ML14223A602, ML14281A365, ML14302A302, ULNRC-05886, Enclosure 1, Responses to the Individual Requests Contained in July 5, 2012 RAIs and Enclosure 2, Contains LRA Amendment 5 to Reflect Changes Made as a Result of the RAI Responses, ULNRC-05928, Enclosure 2 to ULNRC-05928, Amendment 15, LRA Updates, ULNRC-05957, Enclosure 2 to ULNRC-05957, Amendment 21, LRA Changes from RAI Responses, ULNRC-05979, Enclosure 2 to ULNRC-05979, Amendment 23, LRA Changes from RAI Responses and Commitment Updates Enclosure 2 Summary Table
|
MONTHYEARML12131A4732012-05-15015 May 2012 (Enclosure 4) Environmental Site Audit Regarding Callaway Plant, Unit 1, Project stage: Other ML12125A3322012-05-15015 May 2012 (Enclosure 3) Environmental Site Audit Regarding Callaway Plant, Unit 1 Project stage: Other ML12125A1812012-05-15015 May 2012 Environmental Site Audit Regarding Callaway Plant, Unit 1 Project stage: Other ML12131A4512012-05-15015 May 2012 (Enclosure 2) Environmental Site Audit Regarding Callaway Plant, Unit 1 Project stage: Other ML12139A0582012-05-31031 May 2012 Project Manager Change for the License Renewal Project (Safety) for Callaway Plant, Unit 1 Project stage: Other ML12144A0352012-06-11011 June 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application Project stage: RAI ML12159A1542012-06-22022 June 2012 Summary of Site Audit Related to the Review of the License Renewal Application for Callaway Plant, Unit 1 (TAC Nos. ME7715 and ME7716) Project stage: Approval ML12157A0582012-06-22022 June 2012 Request for Additional Information for the Review of the Callaway Plant, Unit 1, License Renewal Application (TAC ME7708) 6 4 2012 Fmp Neutron Embrittlement and Rv Surveillance RAIs on Yee Chris Sydnor Project stage: RAI ML12164A9052012-07-0505 July 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1, LRA Project stage: RAI ML12172A1112012-07-0909 July 2012 Request for Additional Information for the Review of the Callaway Plant, Unit 1, License Renewal Application, Set 4, Project stage: RAI ML12179A4002012-07-18018 July 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application Project stage: RAI ML12206A2642012-08-0606 August 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 6 Project stage: RAI ML12220A1602012-08-0606 August 2012 Responses to RAI Set #3 and Amendment 5 to the Callaway License Renewal Application (LRA) Project stage: Response to RAI ULNRC-05886, Enclosure 1, Responses to the Individual Requests Contained in July 5, 2012 RAIs and Enclosure 2, Contains LRA Amendment 5 to Reflect Changes Made as a Result of the RAI Responses2012-08-0606 August 2012 Enclosure 1, Responses to the Individual Requests Contained in July 5, 2012 RAIs and Enclosure 2, Contains LRA Amendment 5 to Reflect Changes Made as a Result of the RAI Responses Project stage: Other ML12180A0232012-08-0909 August 2012 Aging Management Programs Audit Report Regarding the Callaway Plant Unit 1 License Renewal Application Project stage: Other ML12271A4232012-08-13013 August 2012 Responses to Environmental RAI Set #1 to the Callaway LRA Project stage: Other ML12216A3382012-08-16016 August 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 7 Project stage: RAI ML12233A6132012-08-23023 August 2012 Request for Additional Information for the Review of the Callaway Plant, Unit 1, License Renewal Application, Set 8, Electrical Project stage: RAI ML12244A5712012-08-30030 August 2012 Responses to E-RAI Set 2 to the License Renewal Application Project stage: Other ML12233A5702012-09-0606 September 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 9 Project stage: RAI ML12284A4542012-09-12012 September 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 10, Public Version Project stage: RAI ML12240A1742012-09-18018 September 2012 Review of the 2011 Refueling Outage Steam Generator Tube Inservice Inspection Reports Project stage: Approval ML12244A4292012-09-18018 September 2012 Summary of Telephone Conference Call Held on August 29, 2012, Between the U.S. Nuclear Regulatory Commission and Union Electric Company, Concerning the Request for Additional Information Pertaining to the Callaway Plant, Unit 1, License Ren Project stage: RAI ML12250A7702012-09-20020 September 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 11 Project stage: RAI ML12256A8952012-09-25025 September 2012 RAI for the Review of the Callaway Plant, Unit 1, LRA, Set 12 Project stage: RAI ML12255A2872012-10-0101 October 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1, License Renewal Application, Set 13 Project stage: RAI ML12262A3112012-10-0202 October 2012 Summary of Telephone Conference Call Held on September 14, 2012, Between NRC and Union Electric Company, Concerning the SAMA RAI for the Callaway Plant, Unit 1, LRA Project stage: RAI ML12270A1472012-10-0303 October 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 14 Project stage: RAI ML12276A3732012-10-12012 October 2012 RAI for the Review of the Callaway Plant Unit 1, LRA Set 15 Project stage: RAI ML12299A2482012-10-24024 October 2012 Responses to RAI Set #11 & #12 and Amendment 13 to the Callaway LRA Project stage: Response to RAI ULNRC-05928, Enclosure 2 to ULNRC-05928, Amendment 15, LRA Updates2012-11-0808 November 2012 Enclosure 2 to ULNRC-05928, Amendment 15, LRA Updates Project stage: Other ML12314A1412012-11-0808 November 2012 Responses to RAI Set #15 and Amendment 15 to the Callaway LRA Project stage: Response to RAI ML12321A1992012-11-29029 November 2012 9/27/12 - Summary of Telephone Conference Call Held Between the NRC and Union Electric Company (Ameren Missouri), Concerning RAIs Pertaining to the Callaway Plant, Unit 1, License Renewal Application Project stage: RAI ML12326A9152012-12-0707 December 2012 RAI for the Review of the Callaway Plant Unit 1, LRA, Set 18 Project stage: RAI ML12342A1722012-12-27027 December 2012 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application Project stage: RAI ML13009A2112013-01-14014 January 2013 Request for Additional Information for the Review of the Callaway Plant 1 License Renewal Application Project stage: RAI ULNRC-05950, Responses to RAI Set 19 & Set 20 and Amendment 20 to the Callaway LRA2013-01-24024 January 2013 Responses to RAI Set 19 & Set 20 and Amendment 20 to the Callaway LRA Project stage: Response to RAI ML13025A0312013-01-30030 January 2013 Request for Additional Information for the Review of the Callaway Plant, Unit 1, License Renewal Application, Set 21 Project stage: RAI ML13029A0162013-02-12012 February 2013 Summary of Telephone Conference Call Held on January 22, 2013, Between the U.S. Nuclear Regulatory Commission Project stage: Other ML13029A6592013-02-12012 February 2013 Summary of Telephone Conference Call Held on December 6, 2012, Between the NRC and Union Electric Company, Concerning Request for Additional Information Pertaining to the Callaway Plant Unit 1, LRA Project stage: RAI ULNRC-05957, Enclosure 2 to ULNRC-05957, Amendment 21, LRA Changes from RAI Responses2013-02-14014 February 2013 Enclosure 2 to ULNRC-05957, Amendment 21, LRA Changes from RAI Responses Project stage: Other ML13046A3072013-02-14014 February 2013 Enclosure 1 to ULNRC-05957, License Renewal Application, Request for Additional Information (RAI) Set #21 Responses Project stage: Request ML13046A3062013-02-14014 February 2013 Response to RAI Set #21 and Amendment 21 to the Callaway LRA Project stage: Response to RAI ML13038A3082013-02-21021 February 2013 RAI for the Review of the Callaway Plant Unit 1, LRA, Set 22 Project stage: RAI ML12307A3912013-02-26026 February 2013 Schedule Revision for the Environmental Review of the Callaway Plant, Unit 1 License Renewal Application (TAC Nos. ME7715 and ME7716) Project stage: Approval ML13063A4762013-02-28028 February 2013 Response to RAI Set #22 and Amendment 22 to the Callaway LRA Project stage: Response to RAI ML13059A8002013-03-11011 March 2013 Summary of Telephone Call Held on 11/5/12, Between NRC and Union Electric Company, Regarding Request for Clarification of Responses to the SAMA RAI Concerning Callaway Plant, Unit 1, LRA Project stage: RAI ML13042A0422013-03-26026 March 2013 Request for Additional Information for the Review of the Callaway Plant Unit 1 License Renewal Application, Set 23 Project stage: RAI ML13058A1242013-03-29029 March 2013 Request for Additional Information for the Review of the Callaway Plant, Unit 1, License Renewal Application, Set 24 Project stage: RAI ULNRC-05979, Enclosure 2 to ULNRC-05979, Amendment 23, LRA Changes from RAI Responses and Commitment Updates Enclosure 2 Summary Table2013-04-26026 April 2013 Enclosure 2 to ULNRC-05979, Amendment 23, LRA Changes from RAI Responses and Commitment Updates Enclosure 2 Summary Table Project stage: Other 2012-08-30
[Table View] |
|
---|
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] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 2, 2013 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALLAWAY PLANT, UNIT 1, LICENSE RENEWAL APPLICATION, SET 26 (TAC NO. ME7708) Dear Mr. Heflin: By letter dated December 15, 2011, Union Electric Company (Ameren Missouri) (the applicant) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54 (10 CFR Part 54) for renewal of operating license No. NPF-30 for the Callaway Plant, Unit 1 (Callaway). The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staff's requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Sarah G. Kovaleski, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel. CuadradoDeJesus@nrc.gov. Sincerely, /' Cuadrado de Jesus,tPfOject Manager ( Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-483 Enclosure: As stated cc: Listserv August 2, 2013 Mr. Adam C. Heflin Senior Vice President and Chief Nuclear Officer Union Electric Company P.O. Box 620 Fulton, MO 65251 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALLAWAY PLANT, UNIT 1, LICENSE RENEWAL APPLICATION, SET 26 (TAC NO. ME7708) Dear Mr. Heflin: By letter dated December 15, 2011, Union Electric Company (Ameren Missouri) (the applicant) submitted an application pursuant to Title 10 of the Code ofFederal Regulations Part 54 (10 CFR Part 54) for renewal of Operating License No. NPF-30 for the Callaway Plant, Unit 1 (Callaway). The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing this application in accordance with the guidance in NUREG-1800, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants." During its review, the staff has identified areas where additional information is needed to complete the review. The staffs requests for additional information are included in the enclosure. Further requests for additional information may be issued in the future. Items in the enclosure were discussed with Sarah G. Kovaleski, of your staff, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me by telephone at 301-415-2946 or bye-mail at Samuel.CuadradoDeJesus@nrc.gov. Sincerely, IRA! Samuel Cuadrado de Jesus, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-483 Enclosure: As stated cc: Listserv DISTRIBUTION: See next page ADAMS Accession No.: ML13192A025 OFFICE LA:DLR/RPB2 PM:DLR/RPB1 BC:DLR/RPB1 PM:DLR/RPB1 NAME YEdmonds SCuadrado YDiaz-Sanabria SCuadrado DATE 7/30/13 8/1113 8/1/13 8/2/13 OFFICIAL RECORD
-Letter to Adam C. Heflin from S. Cuadrado de Jesus dated August 2, 2013 REQUEST FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE CALLAWAY PLANT, UNIT 1, LICENSE RENEWAL APPLICATION, SET 26 (TAC NO. ME7708) DISTRIBUTION: HARD COPY: DLR R/F E-MAIL: PUBLIC RidsNrrDlrResource RidsNrrDraAfpb Resource RidsNrrDraApla Resource RidsNrrDeEmcb Resource RidsNrrDeEeeb Resource RidsNrrDssSrxb Resource RidsNrrDssSbpb Resource RidsNrrDssScvb Resource RidsOgcMailCenter Resource SCuadrado FLyon THartman CFelis DMorey BMizuno (OGC) DCylkowski (OGC) LSubin (OGC) GPick (RIV) 1 CALLAWAY PLANT, UNIT LICENSE RENEWAL REQUEST FOR ADDITIONAL INFORMATION, SET RAI 82.1.3-1 c Background: By letter dated April 26, 2013, the applicant responded to RAI B2.1.3-1 b, and stated in part that detensioning of stud No. 18 during each refueling outage (RFO) confirms its intended function will be maintained. The applicant also stated that normal reactor pressure vessel (RPV) head stud tensioning and detensioning operations performed during each RFO are a form of "proof test" of the adequacy of the threaded connection to support in-service RPV head stud loads. The applicant further stated that the minimum RPV head stud load experienced by RPV head stud No. 18 during detensioning is a 113 percent proof test of the maximum in-service primary plus secondary RPV head stud loading during heatup. The applicant stated that the 1987 evaluation which calculated the RPV head stud minimum thread engagement (6.31 inches) was based on a conservative methodology. The applicant also stated that an evaluation performed in 2013 demonstrates that the minimum RPV head stud engagement required to resist all primary loads is 4.77 inches. The applicant further stated that the stuck stud No. 18 nominally has in excess of 35 percent more thread engagement than is required to meet American Society of Mechanical Engineers (ASME) Code limits, and that the margin is sufficiently large that the comments related to plastic deformation in the 1989 evaluations do not apply to RPV stud No. 18. The applicant stated that although the condition of the threads on the inside of the RPV head stud hole No. 18 cannot be observed through direct visual examination, the 2013 evaluation performed a bounding estimate based on the amount of force used during efforts to remove stud No. 18 and concluded that the effective damage could be no more than 20 percent of a Single thread, which would result in less than 0.025 inches of lost effective thread engagement. The applicant also stated that stud No. 18 is protected from boric acid corrosion by encapsulation during refueling to prevent exposure to the boric acid in the refueling pool. The applicant further stated that most wear occurs when an RPV head stud is threaded in and out of the RPV head stud hole, since stud No. 18 is stuck, it is not removed or installed, therefore essentially there is no wear (loss of material). In addition, the applicant stated that the existing RPV head stud handling procedures and practices do not damage threads. The applicant stated that with the exception of minor maintenance on RPV head stud No. 18 (burr removal in 1996) and RPV head stud No. 20 (chasing lead threads), no threads have been damaged in over 20 years. The applicant also stated that it has not destructively removed an RPV head stud since 1989, when five stuck studs were removed due to their interference with the fuel transfer path and to restore functionality to RPV head stud No.2. The applicant further stated that at that time the risks associated with destructive removal, which included possible introduction of foreign material, worker safety, dose exposure, possibility of additional damage during the repair process, technical challenges associated with the RPV head stud removal tooling, and failure to restore the normal fuel transfer path, were acceptable in order to repair the RPV. Finally, the applicant stated that given the above considerations, it is considered appropriate to monitor and manage the continued use of RPV head stud No. 18 rather than pursue its removal. Issue: The staff finds that the applicant's response still did not fully address how the condition of the threads for the RPV head stud and stud hole No.18 would be monitored during the period of extended operation. In its response the applicant stated that normal RPV head stud tensioning and detensioning operations performed during each RFO is a form of "proof test" of the adequacy of the threaded connection to support in-service RPV head stud loads for the subsequent cycle. The staff does not agree that successful tensioning and detensioning provides adequate assurance that the threads will withstand all in-service loads in the subsequent operating cycle. Specifically, the tensioning and detensioning is usually performed at ambient temperatures. In addition, during tensioning and detensioning, some of the stresses may be distributed or shared by the adjacent studs and flange ligaments, while during in-service transients the adjacent areas may not be able to share as much of the stresses. Furthermore, the staff noted that the applicant is essentially assuming zero corrosion at the location of the stuck stud, because the stuck stud is encapsulated during RFOs. The staff noted that leakage past the encapsulation may occur along with leakage past the inner o-ring, and therefore loss of material at this location is an aging effect which requires management during the period of extended operation. Request: Explain how the current aging management program (AMP) will monitor the condition of the threads on the stud and vessel flange hole threads, so that there is reasonable assurance that the known degradation and any postulated degradation along with the number of unengaged threads will not exceed the acceptance criteria during the period of extended operation. Background: By letter dated April 26, 2013, the applicant responded to RAI B2.1.3-2b, and stated that during the 1989 and 1992 repairs, a tool especially desjgned for inspection of RPV stud holes was used which produced a high quality video of the stud hole threads by using a laser to illuminate and map the profile of the threads. The applicant stated that the laser inspection tool was used before and after the repairs. The applicant also stated that since 1992, due to improved RPV head stud handling procedures, only one minor indication was found on RPV stud hole No. 20 threads. The applicant further stated that the laser inspection device has not been used since 1992. In addition the applicant stated that the 1989 evaluation was intended to apply to the remainder of the "RPV design life" and includes a discussion on the pattern of the degraded RPV head at that time, however the thread damage existing at that time was used only to support the discussions estimating the effective thread engagement in hole locations 2,4, 5, 7, and 9. The applicant also stated that thread damage to RPV stud hole Nos. 13. 25, 39, 53 and 54, subsequent to the 1989 evaluations do not invalidate past evaluations as long as the minimum thread engagement criteria are met. The applicant further stated that the thread degradation evaluation criteria developed in the 1989 report was analyzed such that each RPV stud engagement region fully meets applicable ASME Code rules, provided that the thread degradation evaluation criteria are met for each vessel stud hole. The applicant stated that using this evaluation. the RPV flange as a whole would fully meet ASME Code rules even if the effective thread engagement of all 54 RPV head stud locations were at a minimum. The applicant stated that there is no interaction mechanism between adjacent RPV stud hole locations, provided that each one meets the acceptance criteria established in the 1989 evaluation. The applicant also stated that Recommendation 2 from the 1989 evaluation which stated that "studs used in vessel flange holes with degraded threads should be free from damage," was based on the assumption that the vessel threads would engage with RPV head stud threads that were each fully intact. The applicant stated that use of RPV head stud No. 18 after removing a small burr was not in conflict with the recommendation that "studs used in vessel flange holes with degraded threads should be free of damage." The applicant further stated that the recommendations of the 1989 evaluations are considered to be optional since the language used was "should" rather than "must" or "shall." The applicant stated that the 1987 evaluation calculated a 6.31 inch minimum vessel/stud thread engagement length based on a conservative calculation methodology. However a 2013 evaluation demonstrates that the minimum vessel/stud engagement required to resist all primary loads is 4.77 inches. The applicant also stated that the stuck RPV head stud No. 18 has in excess of 35 percent more thread engagement than is required to meet ASME Code limits. The applicant further stated that this margin is sufficiently large that the comments related to localized plastic deformation do not apply to stuck stud No. 18. Issue: During its review, the staff noted that the evaluations (1987 and 1989), essentially used similar language such as "should" rather than "must" or "shall." This is because at the time these evaluations were performed the applicant had other options, such as the option to repair the RPV stud hole locations with stud hole inserts. However, in perusing the continued use of the 1987 and 1989 evaluations to justify the use of the RPV closure bolting in its current condition (Le., with multiple locations with less than full thread engagement), the use of the recommendations should not be considered as "optional" by the applicant. In addition, since these evaluations are only valid if the acceptance criteria are still being met, the staff still seeks assurance that for locations Nos. 2, 4, 5, 7, 9, 13, 18, 25, 39, 53, and 54 the minimum thread engagement criteria will continue to be met during the term of the renewed license, with sufficient margin such that there is an extremely low probability of abnormal leakage, rapidly propagating failure, and gross rupture. The staff noted that the applicant in its response stated that the 1989 evaluation was intended to apply to the remainder of the RPV design life. The staff reviewed the license renewal application (LRA) and did not note that the 1989 evaluation was identified as time-limited aging analyses (TLAA) , the applicant's response did not provide additional information for the staff to determine whether this evaluation should have been identified as a TLAA in the LRA.
Request: Explain what is meant by the term "remainder of the RPV design life," as discussed above. In addition, clarify whether the 1987 and/or 1989 evaluations should be identified as a TLAA in accordance with 10 CFR 54.3. If the evaluations are identified as TLAAs, revise the LRA accordingly and provide TLAA disposition in accordance with 10 CFR 54.21(c)(1). If not, provide the justifications why these evaluations are not considered as TLAAs. Explain how the current AMP will monitor the condition of the threads such that there is adequate assurance that the acceptance criteria will continue to be met at repaired RPV stud hole location Nos. 2, 4, 5, 7, 9, 13, 25, 39, 53, and 54 during the period of extended operation.