Letter Sequence Acceptance Review |
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MONTHYEARL-PI-12-102, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values2012-11-0808 November 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Submittal of Lnternal Flooding Peer Review Final Results and Revised Total Plant Risk Values Project stage: Supplement ML12335A1832012-11-29029 November 2012 11/29/12 E-mail, Acceptance Review Questions Regarding NFPA 805 License Amendment Request Project stage: Acceptance Review L-PI-12-117, Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions2012-12-18018 December 2012 Supplement to License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Acceptance Review Questions Project stage: Supplement L-PI-13-044, Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request2013-05-0303 May 2013 Commitment to Submit a Supplement to the PINGP NFPA 805 License Amendment Request Project stage: Supplement ML13282A5382013-10-0909 October 2013 Status of Review of National Fire Protection Association Standard 805 Application Project stage: Approval L-PI-13-093, NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement2013-10-17017 October 2013 NFPA 805 License Amendment Request- Milestone Schedule for Submittal of Supplement Project stage: Supplement ML15062A1502015-03-0303 March 2015 NRR E-mail Capture - Prairie Island Nuclear Plant, Units 1 and 2 - NFPA 805 Pre-Audit Draft Requests for Additional Information Project stage: Draft RAI ML15089A1572015-03-30030 March 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - NFPA 805 Requests for Additional Information and Response Timeline Project stage: RAI L-PI-15-041, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2015-05-28028 May 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI L-PI-15-052, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses2015-06-19019 June 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information - 90-Day Responses Project stage: Response to RAI ML15243A4092015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Second Round) from Apla LAR to Adopt NFPA 805 Project stage: RAI ML15243A4102015-08-28028 August 2015 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Final Requests for Additional Information (Fire Modeling - Second Round) LAR to Adopt NFPA 805 Project stage: RAI L-PI-15-059, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round)2015-10-22022 October 2015 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Information (PRA-Second Round) Project stage: Request L-PI-16-004, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-01-20020 January 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information Project stage: Response to RAI L-PI-16-005, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information2016-05-24024 May 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors - Response to Request for Additional Information Project stage: Response to RAI 2015-10-22
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Category:E-Mail
MONTHYEARML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23207A1962023-07-26026 July 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions ML23075A2802023-03-16016 March 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda ML23065A0592023-02-27027 February 2023 NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) ML22167A0452022-06-16016 June 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277 ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22045A4972022-02-14014 February 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21302A1252021-10-29029 October 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0152021-09-0202 September 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21133A2502021-05-13013 May 2021 NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20253A2782020-09-0909 September 2020 E-Mail Submitting Proposed New License Condition ML20254A1162020-09-0909 September 2020 Draft License Transmittal E-Mail ML20223A0632020-08-10010 August 2020 Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20163A4282020-06-10010 June 2020 Email from MPCA Comment Letter - Prairie Island ISFSI ML20154K7632020-06-0202 June 2020 NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20135G8212020-05-14014 May 2020 NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20112F4582020-04-21021 April 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection ML20083F4202020-03-20020 March 2020 NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20052C7582020-02-21021 February 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05 ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML20022A1762020-01-22022 January 2020 NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML20021A1832020-01-21021 January 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2 ML19316A0172019-11-0101 November 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request ML19253B9642019-09-10010 September 2019 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3 ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19193A0142019-07-0909 July 2019 NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals) ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML19057A4212019-02-26026 February 2019 NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request ML19008A3562019-01-0707 January 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69 ML18351A0142018-12-14014 December 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment ML18347A3282018-12-12012 December 2018 E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018) ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18233A3692018-08-21021 August 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Adoption of 10 CFR 50.69 ML18201A4132018-07-20020 July 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-439 ML18159A3052018-06-0808 June 2018 NRR E-mail Capture - Monticello - Acceptance of Requested Relief Request RR-012: Lnservice Inspection Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval ML18113A2252018-04-23023 April 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-425 2023-09-05
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Wengert, Thomas From: Wengert, Thomas Sent: Thursday, November 29, 2012 11 :42 AM To: 'Chesnutt, Samuel' Cc: Eckholt, Gene F. Subject: Prairie Island NGP -Acceptance Review Questions Regarding NFPA 805 License Amendment Request (TAC Nos. ME9734 and ME9735) Attachments: Prairie Island NFPA 805 LAR Acceptance Review Questions.pdf By letter dated September 28,2012, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12278A405), as supplemented by letter dated November 8,2012 (ADAMS Accession No. ML 12314A144), Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, submitted a license amendment request for Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The proposed amendment would transition the PINGP fire protection program to a new Risk-Informed, Performance-Based alternative in accordance with 10 CFR 50.48(c), which incorporates by reference National Fire Protection Association Standard 805 (NFPA 805). The Nuclear Regulatory Commission (NRC) staff has completed its initial review of the submitt9ls. In order to make the application complete, the NRC staff requests that NSPM supplement the application to address the information contained in the attachment to this e-mail by December 18, 2012. The information requested and the associated timerrame identified in this e-mail were discussed*with*NSPMin a teleconference with NRC staff on November 28, 20'12. If you have any questions, please contact me at (301) 415-4037 or at Thomas.Wengert@nrc.gov. Regards, Tom Wengert Project Manager US Nuclear Regulatory Commission NRRIDORULPL3-1. (301) 415-4037 ACCEPTANCE REVIEW QUESTIONS LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR GENERATING PLANTS PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 (TAC Nos. ME9734 and ME9735) The following issues have been identified by the Nuclear Regulatory Commission staff during the acceptance review of the September 28, 2012, license amendment request (LAR) for which supplemental information may be necessary in order to complete the acceptance review: (1) Modifications described in Table S-2, Items 1-4, address separation of Train A and B equipment in Fire Areas 31 and 32, which contain auxiliary feedwater components, remote shutdown panels, and other redundant train equipment. Each of these modifications is described similarly as follows: modify equipment in FA 31 (or 32) to ensure that Train "A" (or "B) equipment is available for fire safe shutdown. It is unclear from these descriptions what specifically the modification will be and, thus, it is unclear if the final plant configuration has been determined. The plant modifications need to be developed to the level of detail that can support an independent review of the efficacy of the proposed plant changes (e.g., re-route cables from specific fire areas, what equipment will be installed, etc.). Furthermore, these modifications are risk-ranked High, and are modeled in the FPRA, and are relied upon to yield an acceptable change in risk. Therefore, these modifications for transition need to be described and, as appropriate, modeled in the PRA to properly estimate the change in risk associated with transition. Provide a more explicit description of modifications identified in Attachment S of the lAR as Items 1, 2, 3, and 4, and how these modifications are treated in the PRA. (2) The impact on the PRA results of implementing incipient detection (very early warning fire detection system -VEWFDS) in the Relay Room and Shutdown Reactor Coolant . Pump seals is presented as a sensitivity study in Section W.2 of the LAR as a risk reduction of about 2.50E-04/yr (Unit 1) and 2.41 E-04/yr (Unit 2) for CDF and 2.35E-05/yr (Unit 1) and 3.10E-05/yr (Unit 2) for LERF, which implies current risk leve.ls at or above these values. Describe how this risk reduction is calculated. If the results are correctly presented, 1) describe what additional compensatory actions have been implemented to lower the risks to acceptable ranges prior to the installation of the two modifications, and 2) discuss why the risk reduction is greater than the remaining COr-:: and lERF from all hazards. 1 (3) Inconsistencies were identified between scenario.-specific CDF/LERF results reportep in Tables W-1 through W-4 and the fire area CDF/LERF results reported in Tables W-5 and W-6 which are potentially significant: (1) Table W-1, Fire Scenario U1FDS-41GRP, reports, a CDF of 6.25E-07, whereas Table W-5 reports a CDF of epsilo.n for Fire Area 41; (2) Table W-,3 provides the CDF for 5 fire scenarios for Fire Area 59 thClt sum to a total CDF of 5.8E-06, which is greater than the CDF of 1.24E-06. for Fire Area 59 reported in Table W-6; (3) similarly, Table W-4 provides the LERF for 11 fire scenarios for Fire ArE.?a 59 that sum to a total LERF of .1.4E-06, which is greater than the LERF of 1.9E-07 for Fire Area 59 reported in Table W-6). Clarify the discrepancies between the scenario-specific CDF/lERF results provided in Tables W-1 through W-4 and the fire area CDF/lERF results provided in Tables W-5 and W-6. Provide revised tables if necessary. (4) The resolutions to peer review Findings for SRs CS*B1 (self assessed as CC-I) and C4 (self assessed as "Not Met") in Table V-2 of the LAR describe that these cannot be completely addressed until a breaker coordination study is compieted and that the PRA assumes that there are no coordination issues. It is noted that Implementation Item #34 in Table S-3 of the LAR is to complete the breaker fuse coordination study and Modification #20 in Table S-2 of the LAR is to install appropriate fuses and/or breaker to fix issues identified in the study. Engineering analyses needed to support the LAR and fire PRA should be completed prior to LAR submittal since the final results from such studies/analyses could impact the risk results presented in the LAR. * * ' j
- Provide justification for why the lAR is acceptable without a completed breaker fuse coordination study. (5) The resolution to the peer review Finding for SR PRM-A 1-01 in Table V-1 of the LAR concludes, for fire scenarios that damage only the component from which the fire originates, that loss of the component and any resulting plant transient (including a reactor trip) is encompassed by the internal events PRA and are therefore appropriately screened from. the fire PRA. Describe the analysis performed to draw this conclusion. Also discuss whether NUREG/CR-6850 guidance in "Section 8.5.3 Step 3: Verification of Screened Fixed Ignition Sources" was considered.