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Category:E-Mail
MONTHYEARML24193A0362024-07-10010 July 2024 NRR E-mail Capture - LIC-109 Acceptance Email - Callaway Plant, Unit 1 - Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition - EPID L-2024-LLA-0076 ML23362A0572023-12-28028 December 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - SUNSI Review of the Final Safety Analysis Report (FSAR) Revision OL-26 ML23338A0392023-12-0101 December 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Unacceptable with Opportunity to Supplement - Callaway - RR from Requirements of ASME BPV Code, Section Xl, Subsect IWL-Exam & Test-Unbonded Post Tensioning System - EPID L-2023-LLR-0061 ML23208A1052023-07-27027 July 2023 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Regulatory Audit Questions - LAR to Clarify Support System Requirements for the Residual Heat Removal & Control Room Air Conditioning Systems ML23200A2982023-07-19019 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 ML23121A0112023-04-28028 April 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Revise TS to Adopt TSTF-501-A Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control - EPID L-2023-LLA-0046 ML23114A2302023-04-24024 April 2023 NRR E-mail Capture - Regulatory Audit Question - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 ML23107A1812023-04-17017 April 2023 NRR E-mail Capture - Regulatory Audit Questions - Callaway LAR and Exemption for Fuel Transition to Framatome Gaia Fuel - EPIDs - L-2022-LLA-0150 and L-2022-LLE-0030 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 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 ML23037A0022023-02-0303 February 2023 NRR E-mail Capture - Callaway - LAR to Adopt AST - EPID L-2021-LLA-0177 - Revised Schedule for Completion of the Project 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 - ML23010A2902023-01-10010 January 2023 NRR E-mail Capture - LIC-109 Acceptance Review - Callaway Plant, Unit 1 - License Amendment Request to Clarify Support System Requirements for the RHR & Crac Systems - ML22346A0132022-12-0909 December 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of LAR to Revise TS 5.5.16, Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies - EPID L-2022-LLA-0165 ML22322A0062022-11-17017 November 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) Callaway - LAR for Proposed Changes to TS and Exemption Request Use of Framatome Gaia Fuel - L-2022-LLA-0150 & L-2022-LLE-0030 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 ML22280A1322022-10-0707 October 2022 NRR E-mail Capture - Final - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway - License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-0 ML22278A0122022-10-0404 October 2022 NRR E-mail Capture - Draft - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway License Amendment Request for Proposed Changes to Tech Spec Changes for Spent Fuel Pool Storage - EPID L-2022-LLA-013 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information NRC-2100-2022, EN 55999 Valcor Coil Shell Assemblies Final Notification (004)2022-09-12012 September 2022 EN 55999 Valcor Coil Shell Assemblies Final Notification (004) ML22251A0122022-09-0707 September 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Application to Revise TS to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections - EPID L-2022-LLA-0110 NRC 2110-2022, EN 55999 - Valcor Engineering Corporation (009)2022-07-18018 July 2022 EN 55999 - Valcor Engineering Corporation (009) ML22216A0072022-07-0808 July 2022 NRR E-mail Capture - Callaway Plant, Unit No. 1 - Draft Acceptance Review (Unacceptable for Review with Opportunity to Supplement) for Framatome Fuel Transition LAR and Exemption - EPIDs L-2022-LLA-0083 and L-2022-LLE-0019) 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 ML22157A0102022-06-0303 June 2022 NRR E-mail Capture - NRC Acceptance Review of Braidwood Ultimate Heat Sink Temporary Temperature Increase to 102.8 Degrees Fahrenheit 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) ML22089A0222022-03-29029 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LAR to Adopt TSTF-505 and TSTF-439 - Follow Up Clarifications for the Audit Questions - EPID L-2021-LLA-0197 ML22087A4022022-03-28028 March 2022 NRR E-mail Capture - Callaway - Draft RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to Generic Letter 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML22070A1362022-03-10010 March 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request for Proposed Revision to Radiological Emergency Response Plan Regarding Response and Notification Goals - EPID L-2022-LLA-0024 ML22047A2312022-02-11011 February 2022 Email Between NRC NSIR and FEMA Regarding Callaway Sirens 021122 ML22003A0852022-01-0303 January 2022 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of License Amendment Request to Adopt TSTF-529, Clarify Use and Application Rules - EPID L-2021-LLA-0225 ML21334A5172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21335A0172021-11-30030 November 2021 NRR E-mail Capture - Callaway Plant, Unit 1 - LIC-109 Acceptance of Requested Licensing Action - Application to Adopt TSTF-439 and TSTF-505 - EPID L-2021-LLA-0197 ML21308A0692021-11-0404 November 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Unit 1 - License Amendment Request - Adoption of Alternate Source Term and Revision of TSs - 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 ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21125A0452021-05-0404 May 2021 NRR E-mail Capture - LIC-109 Acceptance Review (Unacceptable for Review with Opportunity to Supplement) - Callaway Plant, Unit 1 - License Amendment Request - Final Resolution to Address Concerns of GSI-191 - EPID L-2021-LLA-0059 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 ML20342A1802020-12-0606 December 2020 NRR E-mail Capture - Callaway - LIC-109 Acceptance Requested Licensing Action - Application to Adopt 10 CFR 50.69, Risk-Informed Categorization & Treatment of Structures, Systems & Components for Nuclear Power Reactors EPID L-2020-LLA-0235 ML20296A6332020-10-22022 October 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Exemption from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Section VI (EPID L 2020 Lle 0140 (Covid 19)) - Revised Completion Schedule ML20205L4252020-07-22022 July 2020 NRR E-mail Capture - Callaway Plant, Unit 1 - Acceptance of Requested Licensing Action Request for One-Time License Amendment to Defer Upcoming Steam Generator Inspection (EPID L-2020-LLA-0142)(COVID-19) 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 ML20153A7902020-05-29029 May 2020 Emai: RFI for Callaway EP Program Inspection ML20133K6742020-05-11011 May 2020 05000483, Request for Information 2020-002 ML20099G2422020-04-0808 April 2020 NRR E-mail Capture - Acceptance Callaway Containment Tendon COVID-19 Relief Request 2024-07-10
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From: Valentin-Olmeda, Milton To: Huhmann, Bruce E Cc: Philpott, Stephen; Hiller, Justin W
Subject:
Request for supporting information for the Callaway SPRA audit review Date: Thursday, January 02, 2020 9:23:00 AM
- Bruce, The purpose of this email is to solicit that the following supporting information associated with the Callaway 50.54(f) seismic probabilistic risk assessment (SPRA) submittal (ADAMS Accession No. ML19225D321) and associated supplemental information (ADAMS Accession No. ML19325D662) is made available in the ePortal (IMS Certrec) audit folder:
Audit questions on Topic #15 - Documentation of the Seismic PRA (SPID Section 6.8)
The NRC staff identified apparent inconsistencies and anomalies in the documentation and the risk results that appear have the potential to impact the conclusions of this submittal. First, based on statements in the submittal and results reported in the submittal and other SPRA documentation, it is unclear whether or to what extent FLEX equipment or actions were credited in the SPRA. Second, there appears to be inconsistencies between the CDF and LERF importance measure listed for fragility groups presented in the submittal and in the fragility ranking tables presented in the submittal supplement when compared to the top CDF and LERF important measures listed in the results section of the SPRA quantification notebook provided on the document ePortal. The third concerns unfeasible importance measure results reported in SPRA quantification notebook.
Therefore, address the following:
- a. It is unclear whether or to what extent FLEX equipment or actions were credited in the SPRA submittal. Section 5.3.2 of the submittal states (on page 48 of 92) that conservatively, the internal events and S-PRAs do not credit FLEX implementation. Concerning crediting FLEX, Section 5.7.6 of the submittal also states (on page 69 of 92) that the SPRA model currently includes minimal credit for this equipment in the baseline model (flags set to 0.99).
However, Table 5-6 of the submittal, which is a summary of top seismic LERF cutsets, indicates that three of the top ten cutsets includes the event: FLEXAFWFAIL (FLEX AFW to Steam Generator Fails). The contribution of this FLEX event in the top cutsets may indicate that more than minimal credit was taken for FLEX equipment and/or actions in the SPRA.
Additionally, Table 4-11 of PRA-SPRA-002, Draft Revision 0-E, Seismic Probabilistic Risk Assessment, Quantification Analysis Notebook (non-public) provided on the document portal presents a high Risk Reduction Worth (RRW) importance measure for this event. In light of these observations, address the following:
- i. Clarify whether and to what extent FLEX equipment and actions were credited in the baseline SPRA model used to support the submittal. Include explanation for why FLEX failures appear in the list of the top 10 seismic LERF cutsets and why the failure, FLEXAFWFAIL, is listed in the quantification notebook as having a high RRW importance value.
ii. If FLEX equipment and actions were credited in the baseline SPRA model used to support the applications, then clarify what impact this credit has on the seismic CDF and LERF estimates corresponding importance measures estimates. The sensitivity study discussed in Section 5.7.6 of the submittal indicates that any credit taken for FLEX would have small impact on the seismic CDF and LERF. Confirm this is true after clarifying to what extent FLEX was credited in the SPRA.
- b. There appears to be inconsistencies in the CDF and LERF importance measures listed for events presented in the submittal and in the supplement dated September 4, 2019 compared against importance values presented in the SPRA quantification report provided on the document portal. For example, there are failures such as FLEXAFWFAIL and RELAY_2.6 with high Risk Reduction Worth (RRW) values presented in Table 4-11 of the PRA-SPRA-002, Draft Revision 0-E, quantification notebook that do not appear in Table 5-3 or Table 5-7 of the submittal or in the importance ranking tables provided at the end of the supplement. NRC staff recognizes that the importance measures listed in the SPRA quantification report on the portal are presented as RRW values, whereas the importance values presented in the submittal and the supplement are expressed as Fussell-Vesely (F-V) values. However, the NRC staff has accounted for this difference by converting the RRW values to F-V values. After performing this conversion, the NRC staff observed that importance values presented in the SPRA quantification report are not consistent with either the submittal or supplement for the same seismic events. Accordingly, reconcile the inconsistencies noted above by addressing the following:
- i. Justify why failure events with high importance values (e.g., FLEXAFWFAIL and RELAY_2.6) are identified in in the PRA-SPRA-002 quantification notebook and are not identified in the submittal dated August 12, 2019 or supplement dated September 4, 2019.
ii. Justify why RRW values presented in the PRA-SPRA-002 quantification notebook when converted to F-V values were not completely consistent for the same failure events listed in the submittal and supplement.
- c. Section 5.7.8 of the submittal discusses a sensitivity study on operator error bin (i.e., SH1, SH2, SH3, and SH4) definitions. It appears from the information provided in the submittal that operator error bins are defined by ground motion levels (i.e., seismic hazard intervals),
and that the Human Error Probability (HEP) for a given operator error in the same operator bin (i.e., SH1, SH2, SH3, and SH4) is same even though the error may be used in more than one seismic hazard interval. Section 5.7.8 of the submittal provides the results for three cases in which the operator error bins were defined differently. The results show that the seismic CDF and LERF are relatively insensitive to the operator error bin definitions except Case 2 in which the seismic CDF increased by 171.4%. The submittal does not justify this significant increase except to state that operator error bins used in the base case were defined to be realistic based on the relevant component fragilities used to define plant damage states. In light of these observations, address the following:
- i. Explain the approach used to perform the sensitivity on operator error bin definition in Case 2 and given the impact on seismic CDF of operator error bin definition in Case 2, justify that the operator error bin definitions for the sensitivity Case 2 are unrealistic for use in the base case and do not significantly impact the conclusions of the submittal.
ii. If the operator error bin definitions for sensitivity Case 2 cannot be justified as being unrealistic for the base case, provide updated list of dominant risk contributors for SCDF and SLERF for that sensitivity. Also, determine whether there may be a cost justified plant modification that significantly reduces seismic CDF based on this information.
This information will help the staff to continue filling in the technical checklist used for our audit review (ADAMS Accession No. ML18173A017).
Please let me know when the information is available for audit or if we need to discuss this request.
Respectfully, Milton Valentín, PM Beyond Design Basis Management (Fukushima)
US NRC NRR/DORL/LPMB Milton.Valentin@nrc.gov 301-415-2864