Letter Sequence Request |
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EPID:L-2018-JLD-0153, Submittal of Request for Extension of Seismic Probabilistic Risk Assessment (Open) |
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Category:Letter type:ULNRC
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 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 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 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) 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 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 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 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) 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 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 . 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) ULNRC-06812, Submittal of 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ULNRC-06806, Submittal of Radiological Emergency Response Plan, Revision 552023-04-12012 April 2023 Submittal of Radiological Emergency Response Plan, Revision 55 ULNRC-06807, Submittal of Single Positive Test Forms2023-04-0303 April 2023 Submittal of Single Positive Test Forms ULNRC-06798, Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan2023-03-30030 March 2023 Submittal of Status of Plant Decommissioning Funding and ISFSI Decommissioning Funding Plan ULNRC-06801, CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions2023-03-30030 March 2023 CFR 50.46 Annual Report Regarding ECCS Evaluation Model Revisions ULNRC-06804, Submittal of Nuclear Property Insurance Reporting2023-03-29029 March 2023 Submittal of Nuclear Property Insurance Reporting ULNRC-06751, Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control2023-03-29029 March 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Rev. 1, Relocate Stored Oil & Lube Oil Volume Values to Licensee Control ULNRC-06803, Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection2023-03-29029 March 2023 Submittal of Response to Request for Additional Information Regarding Results of Steam Generator Tube In-Service Inspection ULNRC-06805, Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days2023-03-21021 March 2023 Transmittal of Special Report 2023-02 Non-Functionality of Containment Hydrogen Analyzer Channel for Greater than 30 Days ULNRC-06802, Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument2023-03-0909 March 2023 Special Report 2023-01 (PAM Report); Non-Functionality of a Post-Accident Monitoring Instrument ULNRC-06795, Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms2023-01-24024 January 2023 Submittal of Fitness for Duty Reports for 2022, Including Single Positive Test Forms ULNRC-06794, Submittal of Fitness for Duty Program Data for 20222023-01-24024 January 2023 Submittal of Fitness for Duty Program Data for 2022 ULNRC-06787, Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-12-0808 December 2022 Response to Request for Additional Information Regarding License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06781, License Amendment Request 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 (LDCN 22-0029)2022-12-0101 December 2022 License Amendment Request 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 (LDCN 22-0029) ULNRC-06780, Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-0072022-11-30030 November 2022 Additional Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505, LDCN 20-007 ULNRC-06772, 10 CFR 50.59 and 10 CFR 72.48 Summary Report2022-11-23023 November 2022 10 CFR 50.59 and 10 CFR 72.48 Summary Report ULNRC-06777, Operating Quality Assurance Manual (Oqam) Revision 362022-11-16016 November 2022 Operating Quality Assurance Manual (Oqam) Revision 36 ULNRC-06779, ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves2022-11-14014 November 2022 ULNRC-06779: Contesting of Green NCV 05000483/2022010-03, Failure to Perform Required Inservice Testing of Residual Heat Removal Heat Exchanger Pneumatically (Air) Operated Outlet and Bypass Valves ULNRC-06765, 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 Testing Frequencies (LDCN 2020-0004)2022-11-0303 November 2022 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 Testing Frequencies (LDCN 2020-0004) ULNRC-06773, Results of Steam Generator Tube In-Service Inspection2022-11-0101 November 2022 Results of Steam Generator Tube In-Service Inspection ULNRC-06775, Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days2022-10-27027 October 2022 Submittal of Non-Functionality of Loose-Part Detection System Channel for Greater than 30 Days ULNRC-06771, Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013)2022-10-25025 October 2022 Correction to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections (LDCN 21-0013) ULNRC-06770, Cycle 25 Commitment Change Summary Report2022-10-19019 October 2022 Cycle 25 Commitment Change Summary Report ULNRC-06766, Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014)2022-09-0808 September 2022 Correction of Text Contained in Enclosures Provided with Supplements to Request for License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address GSI-191 and Respond to GL 2004-02 (LDCN 19-0014) ULNRC-06767, Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies2022-09-0606 September 2022 Presentation Information for Pre-Application Meeting Regarding New License Amendment Request for Use of Framatome Fuel Assemblies ULNRC-06764, Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015)2022-09-0101 September 2022 Revised Response to Request for Additional Information Regarding License Amendment Request for Adoption Off Alternate Source Term and Revision of Technical Specifications (LDCN 21-0015) ULNRC-06763, Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013)2022-09-0101 September 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspection (LDCN 21-0013) ULNRC-06762, Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 252022-08-25025 August 2022 Submittal of Owner'S Activity Reports (OAR-1 Forms) for Cycle/Refuel 25 ULNRC-06758, Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002)2022-08-0404 August 2022 Union Electric Co. - Renewed Facility Operating License NPF-30, Withdrawal of License Amendment Request and Exemption Request Regarding Transition to Framatome Fuel (LDCN 22-0002) ULNRC-06755, Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals2022-07-13013 July 2022 Response to Requests for Additional Information for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals ULNRC-06754, Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications2022-07-0505 July 2022 Response to Request for Additional Information Regarding Licensee Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ULNRC-06739, Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007)2022-06-30030 June 2022 Post-Audit Supplement to License Amendment Request to Adopt TSTF-439 and TSTF-505 (LDCN 20-0007) ULNRC-06752, Evacuation Time Estimates Report2022-06-27027 June 2022 Evacuation Time Estimates Report ULNRC-06753, Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis2022-06-23023 June 2022 Presentation Information for Pre-Submittal Meeting Regarding Updated Spent Fuel Criticality Safety Analysis ULNRC-06750, Submittal of Cycle 26 Core Operating Limits Report (COLR)2022-06-13013 June 2022 Submittal of Cycle 26 Core Operating Limits Report (COLR) ULNRC-06735, Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014).2022-05-27027 May 2022 Response to Request for Additional Information Regarding Request for License Amendment and Regulatory Exemptions for Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004-02 (LDCN 19-0014). 2024-01-29
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.... ,, Callaway Plant MISSOURI Niib 14; 20 18 ULNRC-06469 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-000 1 10 CFR 50.54(f)
Ladies and Gentlemen:
DOCKET NUMBER 50-483 CALLAWAY PLANT UNIT 1 UNION ELECTRIC CO.
RENEWED FACILITY OPERATING LICENSE NPF-30 REQUEST FOR EXTENSION OF SEISMIC PROBABILISTIC RISK ASSESSMENT SUBMITTAL
References:
1 . NRC Letter, Request for Information Pursuant to Title 1 0 ofthe Code of Federal Regulations
- 50. 54(f) Regarding Recommendations 2.1, 2.3, and 9.3 ofthe Near-Term Task Force Review oflnsights from the Fukushima Daiichi Accident, dated March 12, 2012 (ML12053A340)
- 2. ULNRC-06102, Ameren Missouri Seismic Hazard and Screening (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(1) Regarding Recommendation 2. 1 of the Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident, dated March 28, 2014 (ML14090A448) 3 . NRC Letter, Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 1 0 of the Code of Federal Regulations 50.54(f)
Regarding Recommendation 2. 1 Seismic ofthe Near-Term Task Force Review of Insights from the Fukushima Daiichi Accident, dated October 27, 201 5 (ML15194A015)
- 4. ULNRC-06377, Request For Extension of Seismic Probabilistic Risk Assessment Submittal, dated June 15, 2017 (ML17166A474)
- 5. NRC Letter, Callaway Plant, Unit 1 NRC Response to Request for Extension of Seismic Probabilistic Risk Assessment Submittal, dated August 22, 2017 (ML17200D113)
- 6. NRC Letter, Callaway Plant, Unit 1 Staffreview of Spent Fuel Pool Evaluation Associated with Reevaluated Seismic Hazard Implementing Near-Term Task Force Recommendation 2. 1:
Seismic, dated January 23, 2018 (ML18003B419)
STARS Alliance
ULNRC-06469 November 14, 2018 Page 2 of 5 Union Electric Company (Ameren Missouri) hereby requests an extension ofthe December 3 1, 2018, due date for submittal ofthe Seismic Probabilistic Risk Assessment (SPRA) for Callaway Plant Unit 1.
Ameren Missouri is requesting that the due date be extended to September 30, 2019.
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report. Reference 2 provided the Seismic Hazard and Screening Report for Callaway Plant. Based on the results of the screening evaluation provided in Reference 2, it was determined that Callaway Plant screens in for a required risk evaluation in the form of a Seismic PRA (SPRA), a spent fuel pool evaluation, and a high frequency confirmation (relay chatter) evaluation. Reference 3 was issued by the NRC and provided the required submittal dates for the SPRAs and remaining high frequency and spent fuel pool seismic evaluations in order for licensees to complete their responses to the March 12, 2012 request for information (Reference 1). In Reference 4, Callaway requested an extension of the submittal date for the SPRA until December 3 1 201 8 In Reference 5, the NRC approved the extension request for the SPRA and the corresponding seismic Mitigating Strategies Assessment (MSA).
Ameren Missouri has completed the spent fuel pooi evaluation for Callaway Unit 1 as reviewed by the NRC per Reference 6. The effects ofhigh frequency exceedance on plant equipment will be assessed as part ofthe SPRA.
In order to complete the SPRA evaluation for the Callaway Plant, an extension of 9 months beyond the current December 3 1 201 8 due date is needed. This would move the submittal date to September 30, 2019. Ameren Missouri discussed the need for this extension with NRC staffvia telephone in October 20 1 8 As noted in that discussion, the in-progress results received for Callaways SPRA are not believed to be a realistic representation of the seismic risk at the plant. Since the first extension request, the focus has been on identifying possible drivers for those results and performing refinements to the SPRA model. Until recently, these refinement efforts were largely unsuccessful in developing significant changes in the model results. Refinement efforts made within the past 3 months, however, appear to be more impactful, and the SPRA model is beginning to identify drivers and more realistic insights into the seismic risk for the Callaway Plant. To support the NRC performing an effective review of the results, additional time is required to fully complete the seismic PRA refinement and analysis that realistically quantifies the seismic risk at Callaway Plant.
A peer review was performed of the Callaway SPRA in accordance with NET 12-1 3 External ,
Hazards PRA Peer Review Process Guidelines, in June of2Ol8. The peer review team concluded that the Callaway SPRA meets most of the PRA Standard requirements. However, the peer review team noted that a number of the modeling approaches in the fragility analysis and plant response analysis for the Callaway SPRA are overly conservative and have resulted in a seismic CDF result that appears unrealistic for this plant design and operation.
ULNRC-06469 November 14, 2018 Page 3 of 5 Following the peer review, the seismic PRA model has been used to guide and prioritize a number of refinements to the fragility analysis for specific components. Consequentially, the current risk estimates and insights are converging to results that are more in line with expectations and industry experience. None of the fragility refinements required advanced fragility analysis techniques or any assumptions for modification to the plant. The refinements are based instead on more realistic estimates and treatment of either the existing seismic demand or the actual seismic capacity of individual components. The Callaway risk profile is extremely flat (i.e., no individual components are driving the risk estimates) which is an indication of a balanced design, but it also means that a relatively large number of fragility refinements are needed for a more realistic risk estimate.
In addition to the unanticipated flat risk profile and resultant extensive refinements required, the Callaway SPRA initial proj ect schedule did not provide an adequate amount of time to complete the SPRA Peer Review and then resolve the resulting Facts and Observations. The effort to resolve the Facts and Observations resulting from the Peer Review effort typically requires a six-month duration.
With the extension of the $PRA submittal date, Ameren Missouri will have adequate time to address the Facts and Observations and utilize the NRC endorsed method to conduct an Independent Assessment Team process to closeout the Facts and Observations.
Ameren Missouri has developed a detailed schedule for the required activities, and it indicates that the final Callaway Unit 1 SPRA can be submitted to the NRC on or before September 30, 2019. Ameren Missouri is therefore requesting that the SPRA submittal due date be extended to that date.
Depending on the results of the SPRA, a seismic M$A could be required. If a seismic MSA is required for the Callaway Plant, an extension until December 3 1 201 9 is requested. This provides an additional three months to complete the MSA evaluation beyond the SPRA submittal date.
Continued plant operation during the extension period is justified based on considerations that include consistency with the NRC overall schedule for submittal of all Near-Term Task Force related plant SPRAs, the defense-in-depth provided by compliance with all NRC Orders regarding beyond design basis events, completion ofthe NRC endorsed Expedited Seismic Evaluation Process and all actions identified by that process, the inherent nuclear power plant design margins, and completion of the evaluation demonstrating the beyond design basis seismic robustness of the Callaway Plant Unit 1 spent fuel pool. No plant vulnerabilities have been identified and no safety concerns have been raised by the continuous review of the insights from the in-process SPRA for the Callaway Plant. Therefore, there is no undue risk associated with delaying submittal of the SPRA results for NRC review.
This letter does not contain new commitments. If you have any questions, please contact Justin Hiller at 314-225-1 141 or Bruce Huhmann at 573-694-6741.
Sincerely, Stephanie Banker Vice President, Engineering
ULNRC-06469 November xx, 2018 Page 4 of 5 cc: Mr. Kriss M. Kennedy Regional Administrator U. S. Nuclear Regulatory Commission Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 Senior Resident Inspector Callaway Resident Office U.S. Nuclear Regulatory Commission 8201 NRC Road Steedman, MO 65077 Mr. L. John Klos Project Manager, Callaway Plant Office ofNuclear Reactor Regulation U. S. Nuclear Regulatory Commission Mail Stop 09E3 Washington, DC 20555-0001
ULNRC- 06469 November xx, 2018 Page 5 of 5 Index and send hardcopy to QA File A160.0761 Hardcopy:
Certrec Corporation 6100 Western Place, Suite 1050 FortWorth,TX 76107 (Certrec receives ALL attachments as long as they are non-safeguards and may be publicly disclosed.)
Electronic distribution for the following can be made via Responses and Reports ULNRC Distribution:
F. M. Diya T. E. Herrmann B. L. Cox S. P. Banker F. J. Bianco R. C. Wink T. B. Elwood J. W. Hiller B. E. Huhmann Corporate Communications NSRB Secretary STARS Regulatory Affairs Mr. Jay Silberg (Pillsbury Winthrop Shaw Pittman LLP)