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| | number = ML16279A479 | | | number = ML16279A479 |
| | issue date = 09/29/2016 | | | issue date = 09/29/2016 |
| | title = Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) | | | title = Flood Hazard Reevaluation Report - Response to Requested Information |
| | author name = Gunderson L | | | author name = Gunderson L |
| | author affiliation = Northern States Power Company, Minnesota, Xcel Energy | | | author affiliation = Northern States Power Company, Minnesota, Xcel Energy |
| | addressee name = Gibson L K | | | addressee name = Gibson L |
| | addressee affiliation = NRC/NRR/JLD | | | addressee affiliation = NRC/NRR/JLD |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
| | license number = | | | license number = |
| | contact person = Gibson L K, NRR/JLD, 415-1056 | | | contact person = Gibson L, NRR/JLD, 415-1056 |
| | case reference number = CAC MF7710, CAC MF7711 | | | case reference number = CAC MF7710, CAC MF7711 |
| | package number = ML16279A476 | | | package number = ML16279A476 |
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| | page count = 2 | | | page count = 2 |
| | project = CAC:MF7710, CAC:MF7711 | | | project = CAC:MF7710, CAC:MF7711 |
| | stage = RAI | | | stage = Other |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:From:Gunderson, Lynne To:Gibson, Lauren Cc:Eckholt, Gene F. | | {{#Wiki_filter:From: Gunderson, Lynne To: Gibson, Lauren Cc: Eckholt, Gene F.; Rohrer, Rick J.; Fields, John S. |
| ; Rohrer, Rick J. | |
| ; Fields, John S. | |
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| ==Subject:== | | ==Subject:== |
| [External_Sender] Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) | | [External_Sender] Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) |
| Date:Thursday, September 29, 2016 5:04:58 PM Ms. Gibson, | | Date: Thursday, September 29, 2016 5:04:58 PM Ms. Gibson, On August 18, 2016, a joint audit call was held between the NRC and Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, related to the Prairie Island Nuclear Generating Plants (PINGP) Flood Hazard Reevaluation Report (FHRR) |
| | | (dated May 12, 2016; ADAMS Accession No. ML16133A030). This audit call was held in accordance with the audit plan (ADAMS Accession No. ML16152A126). As a result of the call, the NRC requested on August 30, 2016, that information be submitted on the docket by October 28, 2016. The information request is repeated below along with a response to the request. |
| On August 18, 2016, a joint audit call was held between the NRC and Northern States | | Requested Information for Prairie Island: |
| | | * Local Intense Precipitation - General request related to HEC-RAS modeling The schematic diagram (Figure 5.3.2-2 in LIP calculation package) shows a general overview of the HEC-RAS modeling structure. However, detailed information about where the river reaches receive their water from and what are the corresponding drainage basins is missing. Review of the model shows that there is a total of 32 subbasins, 10 river reaches, and 18 storage areas, which should have more reach boundary conditions (including the missing data for subbasin #205), storage area boundary conditions, and connections between these features. However, none of these conditions were specified or discussed in the FHRR or the LIP calculation package. |
| Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, related to the Prairie | | Please provide revised figure(s) to include all critical door opening locations, river reaches, and cross section associated with each of the critical door locations using appropriate annotations and legends. Please send as a .jpeg or .tiff attachment to an e-mail. The e-mail and attachment will be docketed. |
| | | Northern States Power - Minnesota (NSPM) Response: |
| Island Nuclear Generating Plant's (PINGP) Flood Hazard Reevaluation Report (FHRR) | | Three (3) figures are attached, which provide the location of the critical door opening locations, river reaches, and cross section associated with each of the critical door locations including appropriate annotations and legends. The figures for this response reflect corrections performed in Calculation 180461.51.1005, Revision 1, which is discussed in a separate submittal supplementing the PINGP FHRR. The calculation revision is provided to the NRC Staff for audit on DVD. |
| | |
| (dated May 12, 2016; ADAMS Accession No. ML16133A030). This audit call was held in | |
| | |
| accordance with the audit plan (ADAMS Accession No. ML16152A126). As a result of the | |
| | |
| call, the NRC requested on August 30, 2016, that information be submitted on the docket | |
| | |
| by October 28, 2016. The information request is repeated below along with a response to | |
| | |
| the request. | |
| | |
| Requested Information for Prairie Island | |
| : ~ Local Intense Precipitation - General request related to HEC
| |
| -RAS modeling The schematic diagram (Figure 5.3.2-2 in LIP calculation package) shows a general | |
| | |
| overview of the HEC-RAS modeling structure. However, detailed information about | |
| | |
| where the river reaches receive their water from and what are the corresponding | |
| | |
| drainage basins is missing. Review of the model shows that there is a total of 32 | |
| | |
| subbasins, 10 river reaches, and 18 storage areas, which should have more reach | |
| | |
| boundary conditions (including the missing data for subbasin #205), storage area | |
| | |
| boundary conditions, and connections between these features. However, none of these | |
| | |
| conditions were specified or discussed in the FHRR or the LIP calculation package. | |
| Please provide revised figure(s) to include all critical door opening locations, river | |
| | |
| reaches, and cross section associated with each of the critical door locations using | |
| | |
| appropriate annotations and legends. | |
| Please send as a .jpeg or .tiff attachment to an e | |
| - | |
| mail. The e-mail and attachment will be docketed. | |
| | |
| Northern States Power - Minnesota (NSPM) Response | |
| : | |
| Three (3) figures are attached, which provide the location of the critical door opening | |
| | |
| locations, river reaches, and cross section associated with each of the critical door | |
| | |
| locations including appropriate annotations and legends. The figures for this response | |
| | |
| reflect corrections performed in Calculation 180461.51.1005, Revision 1, which is | |
| | |
| discussed in a separate submittal supplementing the PINGP FHRR. The calculation | |
| | |
| revision is provided to the NRC Staff for audit on DVD. | |
| | |
| Please contact me if you have any questions. | | Please contact me if you have any questions. |
| | Thank you, Lynne Gunderson Xcel Energy l Responsible By Nature |
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|
| Thank you,
| | Fukushima Response Project - Licensing Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East, NPD Welch, MN 55089 P: 651.267.7421 C:612.396.0173}} |
| | |
| Lynne Gunderson Xcel Energy l Responsible By Nature Fukushima Response Project - Licensing Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East, NPD
| |
| | |
| Welch, MN 55089 | |
| | |
| P: 651.267.7421 C:612.396.0173}} | |
Letter Sequence Other |
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MONTHYEARML16133A0412016-05-0909 May 2016 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report Project stage: Request ML16152A1262016-06-0707 June 2016 Nuclear Regulatory Commission Plan for the Audit of Northern States Power Company Minnesota'S Flood Hazard Reevaluation Report Submittal Relating to the Near-Term Task Force Recommendation 2.1-Flooding Prairie Island Nuclear Generating Plan Project stage: Other ML16189A4022016-07-0707 July 2016 Xcel Energy - 6/29/16 Webinar Summary for Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report Interim Actions Project stage: Other ML16248A0062016-09-16016 September 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation (CAC Nos. MF7710 and MF7711) Project stage: Other ML16245A7632016-09-16016 September 2016 MSFHI Tables Final 8-31-2016 Project stage: Other ML16279A4792016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information Project stage: Other ML16280A0352016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 1 of 3 Project stage: Other ML16280A0372016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 2 of 3 Project stage: Other ML16280A0422016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711) - Figure 3 of 3 Project stage: Other ML17097A1962017-04-18018 April 2017 Audit Report Relating to the Flood Hazard Reevaluation Report Project stage: Other ML17144A1542017-05-26026 May 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request - Flood-Causing Mechanism Reevaluation (CAC Nos. MF7710 and MF7711 - Redacted Version Project stage: Other 2016-09-16
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Category:E-Mail
MONTHYEARML24185A0912024-07-0101 July 2024 Acceptance of LAR to Revise TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions in the Accident Analyses ML24116A2532024-04-25025 April 2024 Final Request for Additional Information for LAR to Revise SR 3.8.1.2 Note 3 (EPID: L- 2023-LLA-0135) ML24045A1502024-02-15015 February 2024 Verbal Authorization for Alternative Relief Request-09 ML24045A0862024-02-12012 February 2024 Final RAI for Alternative RR-09 ML23348A3472023-12-12012 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 2024-07-01
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARL-PI-24-030, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.12024-05-22022 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 L-PI-24-009, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing2024-02-13013 February 2024 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-09 Safety Injection System and Volume Control System Category C Check Valve Quarterly Testing L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23262B0372023-09-19019 September 2023 Response to NRC Request for Additional Information Regarding the 2023 Monticello and Prairie Island Plant Decommissioning Funding Status Reports L-PI-22-034, Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing2022-07-14014 July 2022 Response to RAI, Alternative RR-08 Related to Pressure Isolation Valve Monitoring and Testing L-PI-22-033, Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles2022-06-10010 June 2022 Response to Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, Amendment to Adopt 24-Month Operating Cycles ML22161A9152022-06-10010 June 2022 and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Response to a Request for Additional Information Xcel Energy Amendment Request to Create a Common Emergency Plan and Emergency Operations. L-PI-21-047, Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 22021-12-0707 December 2021 Response to Request for Additional Information 24-Month Cycle Amendment Prairie Island Nuclear Generating Plant, Units 1 and 2 L-PI-21-045, Response to Request for Additional Information Cooling Water System License Amendment Request2021-11-0404 November 2021 Response to Request for Additional Information Cooling Water System License Amendment Request L-PI-21-032, Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island2021-09-30030 September 2021 Response to Request for Additional Information Amendment Request to Adopt TSTF-471 and 571-T for Prairie Island L-PI-20-026, Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiativ2020-09-0101 September 2020 Response to Request for Additional Information: License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 L-PI-20-023, Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI)2020-06-10010 June 2020 Independent Spent Fuel Storage Installation, Response to Request for Additional Information: License Amendment Request to Expand the Storage Capacity of the Independent Spent Fuel Storage Installation (ISFSI) ML20045E8942020-02-14014 February 2020 Response to a Request for Additional Information for Proposed 10 CFR 50.55a(z)(2) Alternatives to Utilize ASME Code Case N-786-3, Alternative Requirements for Sleeve Reinforcement of Class 2 and 3 Moderate-Energy Carbon Steel Piping, and AS ML20127J0002019-11-0707 November 2019 Xcel Reply to PIIC Expansion Application L-PI-19-037, Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals2019-09-16016 September 2019 Response to Request for Additional Information: 10 CFR 50.55a Requests Nos. 1-RR-5-10 and 2-RR-5-10, Proposed Alternative to Reactor Vessel Inservice Inspection (ISI) Intervals L-PI-19-029, Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For...2019-08-0505 August 2019 Supplement to Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components For... L-PI-19-014, Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-04-29029 April 2019 Response to Request for Additional Information: Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors L-PI-18-063, Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 8052018-12-0606 December 2018 Response to Request for Additional Information: Revise License Condition Associated with Implementation of NFPA 805 L-PI-18-051, Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program2018-09-17017 September 2018 Response to Request for Additional Information: Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program L-PI-18-038, Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 8052018-07-10010 July 2018 Supplement to License Amendment Request to Revise License Condition Associated with Implementation of NFPA 805 ML18131A2232018-05-11011 May 2018 Prairie and Monticello - Response to Request for Additional Information Regarding Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Di L-PI-17-042, Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices2017-11-0606 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise the NDE Inspection Interval for Special Lifting Devices ML17279A1212017-10-0404 October 2017 Enclosure 2 to L-PI-17-041, Westinghouse-Prepared RAI Responses CE-17-3, Rev. 1, Attachment 2 and Enclosure 3, Marked-Up Technical Specification Page 4.0-7 L-PI-17-035, License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information2017-09-27027 September 2017 License Amendment Request to Revise the Emergency Action Level (EAL) Scheme - Supplement and Response to Requests for Additional Information L-PI-17-032, Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times2017-09-20020 September 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Emergency Plan Staff Augmentation Response Times L-PI-17-007, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2017-03-0606 March 2017 Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors L-PI-17-002, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action2017-02-16016 February 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action L-PI-16-100, Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes2017-02-16016 February 2017 Response to NRC Request for Information - License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes L-PI-16-090, Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors2016-12-14014 December 2016 Response to Request for Additional Information on License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors ML16351A2102016-12-13013 December 2016 External Flooding Assessment Focused Evaluation. (Redacted) ML16288A0972016-10-14014 October 2016 and Monticello - Response to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML16279A4792016-09-29029 September 2016 Flood Hazard Reevaluation Report - Response to Requested Information L-PI-16-076, Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report2016-09-29029 September 2016 Supplement to the Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report L-PI-16-067, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information2016-08-17017 August 2016 License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactors- Response to Request for Additional Information L-PI-16-063, Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2016-08-17017 August 2016 Seventh Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events 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 L-PI-16-040, Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4)2016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Westinghouse-Prepared Response to RAI, CE-16-237, Attachment 2 (Enclosure 4) ML16144A8062016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Response to RAI-2 (Enclosure 1) & Marked-Up Technical Specification Page (Enclosure 2) ML16133A0412016-05-0909 May 2016 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 2, Flood Hazard Reevaluation Report L-08-001, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated..2016-04-14014 April 2016 Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated.. L-PI-16-029, Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated..2016-03-31031 March 2016 Response to Requests for Additional Information - License Amendment Request to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2,,Using the Consolidated.. 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 L-PI-16-001, Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report2016-01-14014 January 2016 Enclosure 2: Responses to Open and Pending Items from the NRC Audit Report L-PI-15-105, License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request..2015-12-30030 December 2015 License Amendment Request (LAR) to Revise Technical Specifications (TS) to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process - Response to Request.. 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 L-PI-14-113, Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-01-16016 January 2015 Updated Final Response to NRC Request for Information Per 10CFR50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 2024-05-22
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From: Gunderson, Lynne To: Gibson, Lauren Cc: Eckholt, Gene F.; Rohrer, Rick J.; Fields, John S.
Subject:
[External_Sender] Prairie Island Nuclear Generating Plant Flood Hazard Reevaluation Report - Response to Requested Information (CAC Nos. MF7710 and MF7711)
Date: Thursday, September 29, 2016 5:04:58 PM Ms. Gibson, On August 18, 2016, a joint audit call was held between the NRC and Northern States Power Company, a Minnesota corporation (NSPM), d/b/a Xcel Energy, related to the Prairie Island Nuclear Generating Plants (PINGP) Flood Hazard Reevaluation Report (FHRR)
(dated May 12, 2016; ADAMS Accession No. ML16133A030). This audit call was held in accordance with the audit plan (ADAMS Accession No. ML16152A126). As a result of the call, the NRC requested on August 30, 2016, that information be submitted on the docket by October 28, 2016. The information request is repeated below along with a response to the request.
Requested Information for Prairie Island:
- Local Intense Precipitation - General request related to HEC-RAS modeling The schematic diagram (Figure 5.3.2-2 in LIP calculation package) shows a general overview of the HEC-RAS modeling structure. However, detailed information about where the river reaches receive their water from and what are the corresponding drainage basins is missing. Review of the model shows that there is a total of 32 subbasins, 10 river reaches, and 18 storage areas, which should have more reach boundary conditions (including the missing data for subbasin #205), storage area boundary conditions, and connections between these features. However, none of these conditions were specified or discussed in the FHRR or the LIP calculation package.
Please provide revised figure(s) to include all critical door opening locations, river reaches, and cross section associated with each of the critical door locations using appropriate annotations and legends. Please send as a .jpeg or .tiff attachment to an e-mail. The e-mail and attachment will be docketed.
Northern States Power - Minnesota (NSPM) Response:
Three (3) figures are attached, which provide the location of the critical door opening locations, river reaches, and cross section associated with each of the critical door locations including appropriate annotations and legends. The figures for this response reflect corrections performed in Calculation 180461.51.1005, Revision 1, which is discussed in a separate submittal supplementing the PINGP FHRR. The calculation revision is provided to the NRC Staff for audit on DVD.
Please contact me if you have any questions.
Thank you, Lynne Gunderson Xcel Energy l Responsible By Nature
Fukushima Response Project - Licensing Prairie Island Nuclear Generating Plant 1717 Wakonade Drive East, NPD Welch, MN 55089 P: 651.267.7421 C:612.396.0173