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| | number = ML17219A001 | | | number = ML17219A001 |
| | issue date = 08/03/2017 | | | issue date = 08/03/2017 |
| | title = 2017/08/03 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845) | | | title = NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program |
| | author name = Williams S | | | author name = Williams S |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = McElroy G K | | | addressee name = Mcelroy G |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
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| {{#Wiki_filter:1NRR-PMDAPEm Resource From:Williams, Shawn Sent:Thursday, August 03, 2017 5:53 AM To:'gkmcelro@southernco.com' Cc:Jackson, Nicole D. | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Williams, Shawn Sent: Thursday, August 03, 2017 5:53 AM To: 'gkmcelro@southernco.com' Cc: Jackson, Nicole D. |
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| ==Subject:== | | ==Subject:== |
| Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. 5(b), | | Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. 5(b), |
| 5(c), and 6 related to License Amendment R equest to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845) | | 5(c), and 6 related to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845) |
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| ==Dear Mr. McElroy,== | | ==Dear Mr. McElroy,== |
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| By letter dated November 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16320A540), the Southern Nuclear Operating Company, Inc., (SNC) submitted an amendment request to revise the Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2, Technical Specifications, related to a request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." By letter dated June 22, 2017 (ADAMS Accession No. ML17173A652), SNC provided a partial response to an NRC request for additional information (RAI) letter dated March 15, 2017 (ADAMS Accession No. ML17058A113). In the June 22, 2017, letter, SNC stated that the remaining RAIs will be provided by August 31, 2017. | | By letter dated November 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16320A540), the Southern Nuclear Operating Company, Inc., (SNC) submitted an amendment request to revise the Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2, Technical Specifications, related to a request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." By letter dated June 22, 2017 (ADAMS Accession No. ML17173A652), |
| | SNC provided a partial response to an NRC request for additional information (RAI) letter dated March 15, 2017 (ADAMS Accession No. ML17058A113). In the June 22, 2017, letter, SNC stated that the remaining RAIs will be provided by August 31, 2017. |
| | Staff has reviewed the June 22, 2017, letter, and has determined that additional information is needed related to SNCs response to RAI No. 6. Please address the supplemental RAI to No. 6 in the supplement to be provided by August 31, 2017. This information was discussed with your staff on July 31, 2017. |
| | Supplement to RAI No. 6 - Service Water Pond Dam Failure In RAI No. 6, the NRC Staff requested the following: |
| | In the application for NFPA 805, an F&O related SR IE-A 10 cited the need to address the probability of dam failure using newer techniques, possibly with inclusion of loss of the SW pond dam to the model. The resolution cited a sensitivity evaluation for which the estimated CDF and LERF were approximately 1 E-5/yr and 1 E-7/yr, respectively, for each unit. Table 6-2 of Attachment 1 for the Permanent ILRT Interval Extension Risk Impact Assessment cites screened out for Other External Risk, which presumably would include this dam failure. |
| | Address whether this dam failure analysis has been updated or not. If updated, discuss whether the screened out citation still applies. If not, revise Table 6-2 to include the results of the cited sensitivity evaluation and address the effect on risk and delta-risk metrics. |
| | The NRC Staff reviewed SNCs response contained in the June 22, 2017, letter. In RAI No. 4, SNC provided their resolved F&O for IE-A10-02 along with the F&O Table Appendix information for F&O IE-A10-02 for Service Water Pond Dam Failure. SNC provided additional information in RAI No. 6. |
| | SNC is taking maximum credit for the integrity of its dam (Category 1 for all four evaluation scales) but still cites an apparently subjective reduction factor of 100 to use the SR IR E-C6 screening criteria to dismiss modeling this initiator. SNC is using qualitative arguments to justify this maximum credit. This approach may be applicable to selecting the lowest generic frequency (Category 1) among the different evaluation scales, but does not translate into additional credit for plant-specific reduction below the Category 1 frequency. Using the Category 1 rating, a total internal dam generic failure frequency is estimated as 1.25E-5/year, appropriate as a final plan-specific factor. |
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| Staff has reviewed the June 22, 2017, letter, and has determined that additional information is needed related to SNC's response to RAI No. 6. Please address the supplemental RAI to No. 6 in the supplement to be provided by August 31, 2017. This information was discussed with your staff on July 31, 2017.
| | The Peer Review questioned the validity of the factor of 100 reduction in the derived dam failure frequency, which is necessary to lower the frequency sufficiently such that the cited screening criterion from SR IE-C6 can be used. The licensee does not address the peer review issue regarding validating the factor of 100. |
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| Supplement to RAI No. 6 - Service Water Pond Dam Failure
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| In RAI No. 6, the NRC Staff requested the following:
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| In the application for NFPA 805, an F&O related SR IE-A 10 cited the need to address the probability of dam failure using newer techniques, possibly with inclusion of loss of the SW pond dam to the model. The resolution cited a sensitivity evaluation for which the estimated CDF and LERF were approximately 1 E-5/yr and 1 E-7/yr, respectively, for each unit. Table 6-2 of Attachment 1 for the Permanent ILRT Interval Extension Risk Impact Assessment cites "screened out" for "Other External Risk," which presumably would include this dam failure. Address whether this dam failure analysis has been updated or not. If updated, discuss whether the "screened out" citation still applies. If not, revise Table 6-2 to include the results of the cited sensitivity evaluation and address the effect on risk and delta-risk metrics.
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| The NRC Staff reviewed SNC's response contained in the June 22, 2017, letter. In RAI No. 4, SNC provided their resolved F&O for IE-A10-02 along with the F&O Table Appendix information for F&O IE-A10-02 for Service Water Pond Dam Failure. SNC provided additional information in RAI No. 6.
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| SNC is taking maximum credit for the integrity of its dam (Category 1 for all four evaluation scales) but still cites an apparently subjective reduction factor of 100 to use the SR IR E-C6 screening criteria to dismiss modeling this initiator. SNC is using qualitative arguments to justify this maximum credit. This approach may be applicable to selecting the lowest generic frequency (Category 1) among the different evaluation scales, but does not translate into additional credit for plant-specific reduction below the Category 1 frequency. Using the Category 1 rating, a total internal dam generic failure frequency is estimated as 1.25E-5/year, appropriate as a final plan-specific factor.
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| 2The Peer Review questioned the validity of the factor of 100 reduction in the derived dam failure frequency, which is necessary to lower the frequency sufficiently such that the cited screening criterion from SR IE-C6 can be used. The licensee does not address the peer review issue regarding validating the factor of 100.
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| Please perform a sensitivity analysis incorporating the dam failure at the generic frequency (i.e., without the 100-fold reduction) to demonstrate negligible effect upon the acceptability of the risk metrics for this application. The sensitivity results should be incorporated with any others arising from changes/enhancements requested in the other RAIs. | | Please perform a sensitivity analysis incorporating the dam failure at the generic frequency (i.e., without the 100-fold reduction) to demonstrate negligible effect upon the acceptability of the risk metrics for this application. The sensitivity results should be incorporated with any others arising from changes/enhancements requested in the other RAIs. |
| Supplement to RAI Nos. 5(b) and 5(c) | | Supplement to RAI Nos. 5(b) and 5(c) |
| The NRC staff is aware that SNC is in the process of updating the Farley FPRA for its NFPA-805 "true up" License Condition and that SNC will provide a re sponse to RAI 5(a) by August 31, 2017. | | The NRC staff is aware that SNC is in the process of updating the Farley FPRA for its NFPA-805 true up License Condition and that SNC will provide a response to RAI 5(a) by August 31, 2017. |
| In RAI Nos. 5(b), and 5(c), the NRC Staff requested the following: | | In RAI Nos. 5(b), and 5(c), the NRC Staff requested the following: |
| In Section 6.3 "Potential Impact from External Events Contribution", Table 6-2 provides core damage frequency (CDF) and large early release frequency (LERF) values for Fi re Events from the FNP Fire PRA (FPRA) that credits pending modifications for NFPA 805 that will be implemented by the end of 2017. Please state if the fire CDFs (and LERFs) reflect changes to FPRA methods made since the safety evaluation (SE) was issued for NFPA 805 including the following: | | In Section 6.3 Potential Impact from External Events Contribution, Table 6-2 provides core damage frequency (CDF) and large early release frequency (LERF) values for Fire Events from the FNP Fire PRA (FPRA) that credits pending modifications for NFPA 805 that will be implemented by the end of 2017. Please state if the fire CDFs (and LERFs) reflect changes to FPRA methods made since the safety evaluation (SE) was issued for NFPA 805 including the following: |
| : b. Changes (generally increases) in fire ignition frequencies and non-suppression probabilities from NUREG-2169. For example, the frequency of fires in the Main Control Board is now twice as high as in the original NUREG/CR-6850 and six times higher than in its Supplement 1. The mean time to suppress a welding fire is nearly twice as long as in both the original NUREG/CR-6850 and its Supplement 1. | | : b. Changes (generally increases) in fire ignition frequencies and non-suppression probabilities from NUREG-2169. For example, the frequency of fires in the Main Control Board is now twice as high as in the original NUREG/CR-6850 and six times higher than in its Supplement 1. The mean time to suppress a welding fire is nearly twice as long as in both the original NUREG/CR-6850 and its Supplement 1. |
| : c. Possible increases in spurious op eration probabilities from NUREG/CR-7150, Vol. 2. For example, intra-cable spurious operation for an ungrounded AC, with individual control power transformers, single-break control circuit for a solenoid-operated valve has a probability of 0.64, slightly higher than the value of 0.6 from NUREG/CR-6850. | | : c. Possible increases in spurious operation probabilities from NUREG/CR-7150, Vol. 2. For example, intra-cable spurious operation for an ungrounded AC, with individual control power transformers, single-break control circuit for a solenoid-operated valve has a probability of 0.64, slightly higher than the value of 0.6 from NUREG/CR-6850. |
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| The NRC Staff reviewed the response contained in the June 22, 2017, letter. | | The NRC Staff reviewed the response contained in the June 22, 2017, letter. |
| SNC responded to RAI 5(b) with a statement about Fire Human Reliability Analysis (which was not the subject of this part of the RAI). SNC did not address the question related to changes in fire ignition frequencies and non-suppression probabilities from NUREG-2169. Please address this in the August 31, 2017, supplement, including updated calculations related to the risk and delta-risk metrics. | | SNC responded to RAI 5(b) with a statement about Fire Human Reliability Analysis (which was not the subject of this part of the RAI). SNC did not address the question related to changes in fire ignition frequencies and non-suppression probabilities from NUREG-2169. Please address this in the August 31, 2017, supplement, including updated calculations related to the risk and delta-risk metrics. |
| SNC responded to the RAI 5(c) by stating that NUREG/CR-7150, Vol 2, has not been applied to the Farley Fire PRA, and CDF's and LERF's presented in this LAR do not reflect NUREG/CR-7150, Vol. 2. | | SNC responded to the RAI 5(c) by stating that NUREG/CR-7150, Vol 2, has not been applied to the Farley Fire PRA, and CDFs and LERFs presented in this LAR do not reflect NUREG/CR-7150, Vol. 2. |
| | If any spurious operation probabilities would be higher using NUREG/CR-7150, Vol 2, than currently used, please address this in the August 31, 2017, supplement including updated calculations related to the risk and delta-risk metrics. If none are higher, please provide a statement. |
| | Sincerely, Shawn Williams NRR/DORL/LPL2-1 V.C. Summer and Farley PM 301-415-1009 2 |
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| If any spurious operation probabilities would be higher using NUREG/CR-7150, Vol 2, than currently used, please address this in the August 31, 2017, supplement including updated calculatio ns related to the risk and delta-risk metrics. If none are higher, please provide a statement.
| | Hearing Identifier: NRR_PMDA Email Number: 3636 Mail Envelope Properties (1fda63da38524be2b2a7ad8e6284f522) |
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| Sincerely, Shawn Williams NRR/DORL/LPL2-1 V.C. Summer and Farley PM 301-415-1009
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| Hearing Identifier: NRR_PMDA Email Number: 3636 Mail Envelope Properties (1fda63da38524be2b2a7ad8e6284f522) | |
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| ==Subject:== | | ==Subject:== |
| Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. 5(b), 5(c), and 6 related to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845) | | Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. |
| Sent Date: 8/3/2017 5:53:14 AM Received Date: 8/3/2017 5:53:15 AM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov | | 5(b), 5(c), and 6 related to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845) |
| | | Sent Date: 8/3/2017 5:53:14 AM Received Date: 8/3/2017 5:53:15 AM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov Recipients: |
| Recipients: "Jackson, Nicole D." <NDJACKSO@southernco.com> Tracking Status: None "'gkmcelro@southernco.com'" <gkmcelro@southernco.com> Tracking Status: None | | "Jackson, Nicole D." <NDJACKSO@southernco.com> |
| | | Tracking Status: None |
| Post Office: HQPWMSMRS06.nrc.gov Files Size Date & Time MESSAGE 6371 8/3/2017 5:53:15 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | | "'gkmcelro@southernco.com'" <gkmcelro@southernco.com> |
| | Tracking Status: None Post Office: HQPWMSMRS06.nrc.gov Files Size Date & Time MESSAGE 6371 8/3/2017 5:53:15 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
Letter Sequence RAI |
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CAC:MF8844, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) |
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MONTHYEARNL-16-1128, License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-0404 October 2016 License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Project stage: Request NL-16-2335, Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-11-15015 November 2016 Re-Submittal of License Amendment Request to Revise Technical Specification Section 5.5.17 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies Project stage: Request ML16340A1772016-12-0505 December 2016 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Requested Licensing Action Regarding TS 5.5.17, Extension of Type a and Type C Leak Rate Test Frequencies Project stage: Acceptance Review ML17058A1132017-03-15015 March 2017 Request for Additional Information Project stage: RAI NL-17-0480, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information2017-06-22022 June 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Responses to NRC Requests for Additional Information Project stage: Response to RAI ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program Project stage: RAI NL-17-1443, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information2017-10-12012 October 2017 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program Final Response to NRC Requests for Additional Information Project stage: Response to RAI ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) Project stage: RAI NL-17-2135, License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information2018-02-0909 February 2018 License Amendment Request to Revise Technical Specification Section 5.5.17 Containment Leakage Rate Testing Program, Response to NRC Request for Additional Information Project stage: Response to RAI ML17261A0872018-02-28028 February 2018 Issuance of Amendments to Revise Actions of TS 5.5.17, Containment Leakage Rate Testing Program (CAC Nos. MF8844 and MF8845; EPID No. L-2016-LLA-0015) Project stage: Approval 2017-12-20
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Category:E-Mail
MONTHYEARML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23223A0142023-08-10010 August 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Exemption to 10 CFR 73.2, Physical Barriers ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23135A0922023-05-11011 May 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Request to Use Specific Provision of a Later Edition of the ASME BPV Code, Section XI (L-2023-LLR-0016) ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23073A0252023-03-13013 March 2023 NRR E-mail Capture - Fyi - Closeout the Evacuation Time Estimate (ETE) Reviews for SNC Fleet ML23045A0782023-02-13013 February 2023 NRR E-mail Capture - Fyi - Revised Estimated Hours - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML23009A0152023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR ML23009A0062023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22354A0112022-12-19019 December 2022 NRR E-mail Capture - Acceptance Review - Requested Licensing Action Regarding TS Revision to Adopt WCAP-17661-P-A, Improved Relaxed Axial Offset Control and Constant Axial Offset Control Fq Surveillance TS (L-2022-LLA-0148 and L-2022-LLA-01 ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22285A2532022-10-12012 October 2022 NRR E-mail Capture - Acceptance Review - Farley Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 ML22285A0082022-10-11011 October 2022 NRR E-mail Capture - Acceptance Review - Farley TS 4.3 LAR (L-2022-LLA-0138) ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22213A2692022-08-0101 August 2022 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specification 3.4.10, Pressurizer Safety Valves ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22020A0662022-01-13013 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-269-A LAR (L-2021-LLA-0234) ML22012A0632022-01-11011 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TS 5.5.16 LAR (L-2021-LLA-0235) ML22010A2402022-01-10010 January 2022 NRR E-mail Capture - Farley 1 and 2 - Acceptance of Requested Licensing Action Revise TS 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21292A1562021-10-19019 October 2021 NRR E-mail Capture - Acceptance Review - SNC Operating Fleet TSTF-554 LAR ML21274A0462021-10-0101 October 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-577 LAR (L-2021-LLA-0163) ML21236A3142021-08-24024 August 2021 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Remove Sump Recirculation Valve Encapsulation ML21180A2002021-06-28028 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle - Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System (L-2021-LLA-0109) ML21174A1182021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet - Remove Table of Contents LAR (L-2021-LLA-0115) ML21174A1152021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle Exemption Requests from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (L-2021-LLE-0031) ML21132A0132021-05-11011 May 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet QATR Reduction in Commitment Licensing Action - L-2021-LLQ-0002 ML21105A0132021-04-14014 April 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet LAR to Change TS 5.7, High Radiation Area (L-2021-LLA-0052) ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20318A0212020-11-12012 November 2020 NRR E-mail Capture - Fyi - Acceptance Review - SNC Fleet TSTF-541 LAR (L-2020-LLA-0232) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20289A1152020-10-0909 October 2020 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Requested Licensing Action Request for One-Time Exemption from 10 CFR 50, Appx E, Biennial EP Exercise Requirements Due to COVID-19 Pandemic NL-20-0713, Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic2020-09-21021 September 2020 Request for One-Time Exemption from 10 CFR 50, Appendix E, Biennial Emergency Preparedness Exercise Requirements Due to COVID-19 Pandemic ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20245E2842020-09-0101 September 2020 NRR E-mail Capture - Acceptance Review - SNC Fleet EP LAR (L-2020-LLA-0150 and L-220-LLA-151) ML20199M2572020-07-17017 July 2020 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Acceptance of Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20181A4072020-06-29029 June 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSI-191 Issues ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests NL-20-0640, Response to Request for Additional Information for Exemption Request2020-05-27027 May 2020 Response to Request for Additional Information for Exemption Request 2023-08-31
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate ML20055E9752020-02-28028 February 2020 Request for Additional Information Update the Spent Fuel Pool Criticality Safety Analysis (EPID L-2019-LLA-0212) Non-Proprietary Version ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) ML19066A0422019-03-0707 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 ML19056A2142019-02-25025 February 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18239A1542018-08-24024 August 2018 Emergency Preparedness Inspection and Request for Information ML18087A1462018-05-0101 May 2018 Request for Additional Information TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 ML17010A0142017-01-19019 January 2017 Request for Additional Information Regarding License Aging Management Program ML16243A1992016-08-30030 August 2016 Notification of Inspection and Request for Information ML16222A2952016-08-29029 August 2016 Request for Additional Information ML16204A0422016-07-26026 July 2016 Acceptance Letter, Unacceptable, with Opportunity to Supplement ML16187A3082016-06-28028 June 2016 Requalification Program Inspection - Joseph M. Farley Nuclear Plant 2024-01-12
[Table view] |
Text
NRR-PMDAPEm Resource From: Williams, Shawn Sent: Thursday, August 03, 2017 5:53 AM To: 'gkmcelro@southernco.com' Cc: Jackson, Nicole D.
Subject:
Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No. 5(b),
5(c), and 6 related to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845)
Dear Mr. McElroy,
By letter dated November 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16320A540), the Southern Nuclear Operating Company, Inc., (SNC) submitted an amendment request to revise the Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2, Technical Specifications, related to a request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." By letter dated June 22, 2017 (ADAMS Accession No. ML17173A652),
SNC provided a partial response to an NRC request for additional information (RAI) letter dated March 15, 2017 (ADAMS Accession No. ML17058A113). In the June 22, 2017, letter, SNC stated that the remaining RAIs will be provided by August 31, 2017.
Staff has reviewed the June 22, 2017, letter, and has determined that additional information is needed related to SNCs response to RAI No. 6. Please address the supplemental RAI to No. 6 in the supplement to be provided by August 31, 2017. This information was discussed with your staff on July 31, 2017.
Supplement to RAI No. 6 - Service Water Pond Dam Failure In RAI No. 6, the NRC Staff requested the following:
In the application for NFPA 805, an F&O related SR IE-A 10 cited the need to address the probability of dam failure using newer techniques, possibly with inclusion of loss of the SW pond dam to the model. The resolution cited a sensitivity evaluation for which the estimated CDF and LERF were approximately 1 E-5/yr and 1 E-7/yr, respectively, for each unit. Table 6-2 of Attachment 1 for the Permanent ILRT Interval Extension Risk Impact Assessment cites screened out for Other External Risk, which presumably would include this dam failure.
Address whether this dam failure analysis has been updated or not. If updated, discuss whether the screened out citation still applies. If not, revise Table 6-2 to include the results of the cited sensitivity evaluation and address the effect on risk and delta-risk metrics.
The NRC Staff reviewed SNCs response contained in the June 22, 2017, letter. In RAI No. 4, SNC provided their resolved F&O for IE-A10-02 along with the F&O Table Appendix information for F&O IE-A10-02 for Service Water Pond Dam Failure. SNC provided additional information in RAI No. 6.
SNC is taking maximum credit for the integrity of its dam (Category 1 for all four evaluation scales) but still cites an apparently subjective reduction factor of 100 to use the SR IR E-C6 screening criteria to dismiss modeling this initiator. SNC is using qualitative arguments to justify this maximum credit. This approach may be applicable to selecting the lowest generic frequency (Category 1) among the different evaluation scales, but does not translate into additional credit for plant-specific reduction below the Category 1 frequency. Using the Category 1 rating, a total internal dam generic failure frequency is estimated as 1.25E-5/year, appropriate as a final plan-specific factor.
1
The Peer Review questioned the validity of the factor of 100 reduction in the derived dam failure frequency, which is necessary to lower the frequency sufficiently such that the cited screening criterion from SR IE-C6 can be used. The licensee does not address the peer review issue regarding validating the factor of 100.
Please perform a sensitivity analysis incorporating the dam failure at the generic frequency (i.e., without the 100-fold reduction) to demonstrate negligible effect upon the acceptability of the risk metrics for this application. The sensitivity results should be incorporated with any others arising from changes/enhancements requested in the other RAIs.
Supplement to RAI Nos. 5(b) and 5(c)
The NRC staff is aware that SNC is in the process of updating the Farley FPRA for its NFPA-805 true up License Condition and that SNC will provide a response to RAI 5(a) by August 31, 2017.
In RAI Nos. 5(b), and 5(c), the NRC Staff requested the following:
In Section 6.3 Potential Impact from External Events Contribution, Table 6-2 provides core damage frequency (CDF) and large early release frequency (LERF) values for Fire Events from the FNP Fire PRA (FPRA) that credits pending modifications for NFPA 805 that will be implemented by the end of 2017. Please state if the fire CDFs (and LERFs) reflect changes to FPRA methods made since the safety evaluation (SE) was issued for NFPA 805 including the following:
- b. Changes (generally increases) in fire ignition frequencies and non-suppression probabilities from NUREG-2169. For example, the frequency of fires in the Main Control Board is now twice as high as in the original NUREG/CR-6850 and six times higher than in its Supplement 1. The mean time to suppress a welding fire is nearly twice as long as in both the original NUREG/CR-6850 and its Supplement 1.
- c. Possible increases in spurious operation probabilities from NUREG/CR-7150, Vol. 2. For example, intra-cable spurious operation for an ungrounded AC, with individual control power transformers, single-break control circuit for a solenoid-operated valve has a probability of 0.64, slightly higher than the value of 0.6 from NUREG/CR-6850.
The NRC Staff reviewed the response contained in the June 22, 2017, letter.
SNC responded to RAI 5(b) with a statement about Fire Human Reliability Analysis (which was not the subject of this part of the RAI). SNC did not address the question related to changes in fire ignition frequencies and non-suppression probabilities from NUREG-2169. Please address this in the August 31, 2017, supplement, including updated calculations related to the risk and delta-risk metrics.
SNC responded to the RAI 5(c) by stating that NUREG/CR-7150, Vol 2, has not been applied to the Farley Fire PRA, and CDFs and LERFs presented in this LAR do not reflect NUREG/CR-7150, Vol. 2.
If any spurious operation probabilities would be higher using NUREG/CR-7150, Vol 2, than currently used, please address this in the August 31, 2017, supplement including updated calculations related to the risk and delta-risk metrics. If none are higher, please provide a statement.
Sincerely, Shawn Williams NRR/DORL/LPL2-1 V.C. Summer and Farley PM 301-415-1009 2
Hearing Identifier: NRR_PMDA Email Number: 3636 Mail Envelope Properties (1fda63da38524be2b2a7ad8e6284f522)
Subject:
Joseph M. Farley Nuclear Plant, Units 1 and 2 - Supplemental RAI request No.
5(b), 5(c), and 6 related to License Amendment Request to revise TS 5.5.17 "Containment Leakage Rate Testing Program." (CAC Nos. MF8844, MF8845)
Sent Date: 8/3/2017 5:53:14 AM Received Date: 8/3/2017 5:53:15 AM From: Williams, Shawn Created By: Shawn.Williams@nrc.gov Recipients:
"Jackson, Nicole D." <NDJACKSO@southernco.com>
Tracking Status: None
"'gkmcelro@southernco.com'" <gkmcelro@southernco.com>
Tracking Status: None Post Office: HQPWMSMRS06.nrc.gov Files Size Date & Time MESSAGE 6371 8/3/2017 5:53:15 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
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