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| | number = ML16326A353 | | | number = ML16326A353 |
| | issue date = 11/18/2016 | | | issue date = 11/18/2016 |
| | title = Draft Request for Information Related to Prairie Island NFPA-805 License Amendment (CAC No. ME9734 and ME9735) | | | title = NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment |
| | author name = Kuntz R F | | | author name = Kuntz R |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Eckholt G F | | | addressee name = Eckholt G |
| | addressee affiliation = Northern States Power Co | | | addressee affiliation = Northern States Power Co |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
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| =Text= | | =Text= |
| {{#Wiki_filter:1 NRR-PMDAPEm Resource From: Kuntz, Robert Sent: Friday, November 18, 2016 9:20 AM To:Eckholt, Gene F. | | {{#Wiki_filter:NRR-PMDAPEm Resource From: Kuntz, Robert Sent: Friday, November 18, 2016 9:20 AM To: Eckholt, Gene F. |
| Cc: Hazelhoff, Amy | | Cc: Hazelhoff, Amy |
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| ==Subject:== | | ==Subject:== |
| DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735) | | DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735) |
| Mr. Eckholt, By letter dated September 28, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12278A405), as supplemented by letters dated November 8 and December 18, 2012; May 3 and October 17, 2013; April 30, 2014; May 28, June 19, October 6, and October 22, 2015; January 20, May 24, and August 17, 2016 (ADAMS Accession Nos. ML12314A144, ML12354A464, ML13126A115, ML13291A367, ML14125A106, ML15153A018, ML15174A139, ML15280A044, ML15296A259, ML16020A375, ML16152A046, ML16230A554, respectively); Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) to transition its fire protection licensing basis at the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2, from paragraph 50.48(b) of Title 10 of the Code of Federal Regulations (10 CFR) to 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805). Supplemental information has | | Mr. Eckholt, By letter dated September 28, 2012 (Agencywide Documents Access and Management System (ADAMS) |
| | | Accession No. ML12278A405), as supplemented by letters dated November 8 and December 18, 2012; May 3 and October 17, 2013; April 30, 2014; May 28, June 19, October 6, and October 22, 2015; January 20, May 24, and August 17, 2016 (ADAMS Accession Nos. ML12314A144, ML12354A464, ML13126A115, ML13291A367, ML14125A106, ML15153A018, ML15174A139, ML15280A044, ML15296A259, ML16020A375, ML16152A046, ML16230A554, respectively); Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) to transition its fire protection licensing basis at the Prairie Island Nuclear Generating Plant (PINGP), |
| been requested by the NRC staff and provided NSPM. | | Units 1 and 2, from paragraph 50.48(b) of Title 10 of the Code of Federal Regulations (10 CFR) to 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805). Supplemental information has been requested by the NRC staff and provided NSPM. |
| A DRAFT requests for additional information (RAI) is provided below. If clarification is requested on the RAI contact me and I will arrange a teleconference with the NRC staff. If no clarification is required, then this DRAFT RAI will become a final RAI and a response will be expected within 30 days of this e-mail. | | A DRAFT requests for additional information (RAI) is provided below. If clarification is requested on the RAI contact me and I will arrange a teleconference with the NRC staff. If no clarification is required, then this DRAFT RAI will become a final RAI and a response will be expected within 30 days of this e-mail. |
| | | Robert Kuntz Senior Project Manager (Monticello and Prairie Island) |
| Robert Kuntz Senior Project Manager (Monticello and Prairie Island) NRC/NRR/DORL/LPL3-1 | | NRC/NRR/DORL/LPL3-1 (301)415-3733 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM, THE LICENSEE) |
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| (301)415-3733 | |
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| REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM, THE LICENSEE) | |
| PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP), UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 (TAC NOS. ME9734 AND ME9735) | | PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP), UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 (TAC NOS. ME9734 AND ME9735) |
| Probabilistic Risk Assessment (PRA) Request for Additional Information (RAI) 21 Very Early Warning Fire Detection System Credit | | Probabilistic Risk Assessment (PRA) Request for Additional Information (RAI) 21 Very Early Warning Fire Detection System Credit 1 |
| | |
| 2Section 2.4.3.3 of National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, states that the probabilistic safety analysis (PSA) (PSA is also referred to as probabilistic risk assessment (PRA)) approach, methods, and data shall be acceptable to the authority having jurisdiction, which is the Nuclear Regulatory Commission (NRC). Section 2.4.4.1 of NFPA 805 further states that the change in public health risk arising from transition from the current fire protection program to an NFPA 805 based program, and all future plant
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| changes to the program, shall be acceptable to the NRC. Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,"
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| Revision 2, (RG 1.174) provides quantitative guidelines on core damage frequency (CDF), large early release frequency (LERF), and identifies acceptable changes to these frequencies that result from proposed changes to the plant's licensing basis and describes a general framework to determine the acceptability of risk-informed
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| changes. The NRC staff's review of the information in the license amendment r equest identified additional information that is required to fully characterize the risk estimates. | | Section 2.4.3.3 of National Fire Protection Association (NFPA) Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, states that the probabilistic safety analysis (PSA) (PSA is also referred to as probabilistic risk assessment (PRA)) approach, methods, and data shall be acceptable to the authority having jurisdiction, which is the Nuclear Regulatory Commission (NRC). Section 2.4.4.1 of NFPA 805 further states that the change in public health risk arising from transition from the current fire protection program to an NFPA 805 based program, and all future plant changes to the program, shall be acceptable to the NRC. Regulatory Guide 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, (RG 1.174) provides quantitative guidelines on core damage frequency (CDF), large early release frequency (LERF), and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staffs review of the information in the license amendment request identified additional information that is required to fully characterize the risk estimates. |
| New guidance on the credit taken for very early warning fire detection system (VEWFDS) is available in NUREG-2180, "Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities, (Delores-VEWFIRE)" of which the pre-publication final version is available at Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML16286A000 and ML16286A002 (note that the accession numbers may change when the final version is published). The methodology in NUREG-2180 is acceptable to the NRC because it is currently the best available guidance. The guidance provided in frequently asked question (FAQ) 08-0046, "Closure of National Fire Protection Association 805 Frequently Asked Q uestion 08-0046 Incipient Fire Detection Systems" (ADAMS Accession No. ML093220426), has been retired and alternative approaches for staff evaluation are necessary to complete the safety evaluation. | | New guidance on the credit taken for very early warning fire detection system (VEWFDS) is available in NUREG-2180, Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities, (Delores-VEWFIRE) of which the pre-publication final version is available at Agencywide Documents Access and Management System (ADAMS) Accession Nos. |
| | | ML16286A000 and ML16286A002 (note that the accession numbers may change when the final version is published). The methodology in NUREG-2180 is acceptable to the NRC because it is currently the best available guidance. The guidance provided in frequently asked question (FAQ) 08-0046, Closure of National Fire Protection Association 805 Frequently Asked Question 08-0046 Incipient Fire Detection Systems (ADAMS Accession No. ML093220426), has been retired and alternative approaches for staff evaluation are necessary to complete the safety evaluation. |
| Explain how credit (e.g., approach, methods, data, and assumptions) taken in the fire PRA (FPRA) for the proposed VEWFDS is consistent with the guidance in NUREG-2180 or bounds the risk results (i.e., CDF, LERF, change in CDF, and change in LERF) that would be obtained had the guidance in NUREG-2180 been applied. If credit taken for VEWFDS in the FPRA is not consistent with or bounded by NUREG-2180, provide: | | Explain how credit (e.g., approach, methods, data, and assumptions) taken in the fire PRA (FPRA) for the proposed VEWFDS is consistent with the guidance in NUREG-2180 or bounds the risk results (i.e., CDF, LERF, change in CDF, and change in LERF) that would be obtained had the guidance in NUREG-2180 been applied. If credit taken for VEWFDS in the FPRA is not consistent with or bounded by NUREG-2180, provide: |
| : a. The risk results (i.e., CDF, LERF, change in CDF, and change in LERF): (1) without credit for VEWFDS, (2) that would be obtained had the guidance in NUREG-2180 been applied, or that would be obtained had an alternative method been used, along with a description and justification for the alternative method. Development and use of an alternative proposal may extend the time required to complete the review. The new risk results can be generated from a sensitivity study type evaluation insofar as formal incorporation of the new method into the PRA model of record is not required. | | : a. The risk results (i.e., CDF, LERF, change in CDF, and change in LERF): (1) without credit for VEWFDS, (2) that would be obtained had the guidance in NUREG-2180 been applied, or that would be obtained had an alternative method been used, along with a description and justification for the alternative method. Development and use of an alternative proposal may extend the time required to complete the review. The new risk results can be generated from a sensitivity study type evaluation insofar as formal incorporation of the new method into the PRA model of record is not required. |
| : b. Explain how the total risk and increases in risk are consistent with the guidelines in RG 1.174. | | : b. Explain how the total risk and increases in risk are consistent with the guidelines in RG 1.174. |
| : c. If additional method and model modifications to the PRA are used and discussed in response to item a. above, explain how they will be incorporated into the PRA model of record that will be used to determine whether the as-built modifications meet the RG 1.174 guidelines and to support the self-approval of post-transition changes. | | : c. If additional method and model modifications to the PRA are used and discussed in response to item a. |
| | above, explain how they will be incorporated into the PRA model of record that will be used to determine whether the as-built modifications meet the RG 1.174 guidelines and to support the self-approval of post-transition changes. |
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| Hearing Identifier: NRR_PMDA Email Number: 3172 Mail Envelope Properties (e62ef7aef70b4ccab2dbdae68a22b7d8) | | Hearing Identifier: NRR_PMDA Email Number: 3172 Mail Envelope Properties (e62ef7aef70b4ccab2dbdae68a22b7d8) |
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| ==Subject:== | | ==Subject:== |
| DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735) Sent Date: 11/18/2016 9:19:45 AM Received Date: 11/18/2016 9:19:45 AM From: Kuntz, Robert Created By: Robert.Kuntz@nrc.gov Recipients: "Hazelhoff, Amy" <Amy.Hazelhoff@xenuclear.com> Tracking Status: None "Eckholt, Gene F." <Eugene.Eckholt@xenuclear.com> Tracking Status: None | | DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735) |
| | | Sent Date: 11/18/2016 9:19:45 AM Received Date: 11/18/2016 9:19:45 AM From: Kuntz, Robert Created By: Robert.Kuntz@nrc.gov Recipients: |
| Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 5748 11/18/2016 9:19:45 AM | | "Hazelhoff, Amy" <Amy.Hazelhoff@xenuclear.com> |
| | | Tracking Status: None "Eckholt, Gene F." <Eugene.Eckholt@xenuclear.com> |
| Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:}} | | Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 5748 11/18/2016 9:19:45 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: |
| | Recipients Received:}} |
Letter Sequence Draft RAI |
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CAC:ME9734, Control Room Habitability (Approved, Closed) |
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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:Request for Additional Information (RAI)
MONTHYEARML24197A2012024-07-15015 July 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004
ML24149A3712024-05-29029 May 2024
(Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
ML24141A0452024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
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)
ML24045A0862024-02-12012 February 2024
Final RAI for Alternative RR-09
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
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
ML23214A2032023-08-0202 August 2023
Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000282/2024010; 05000306/2024010
ML23199A0922023-07-18018 July 2023
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000306/2023004
ML23096A3082023-04-0707 April 2023
Notification of Inspection an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information
ML23055B0562023-02-27027 February 2023
Request for Information for NRC Commercial Grade Dedication Inspection Inspection Report 05000282/2023010 and 05000306/2023010
ML23053A1432023-02-22022 February 2023
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant
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
ML22145A4152022-05-25025 May 2022
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000282/2022402 05000306/2022402
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
ML22130A5792022-05-11011 May 2022
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML21321A0452021-11-10010 November 2021
Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request
ML21305A0102021-10-29029 October 2021
NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment
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
ML21147A5232021-06-0303 June 2021
Prarie Island Nuclear Generating Plant, Units 1 and 2 - Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML21131A0752021-05-10010 May 2021
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2021004; 05000306/2021004
ML21099A0972021-04-0909 April 2021
Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000282/2021012 and 05000306/2021012
ML21062A0532021-03-0202 March 2021
Information Request to Support Upcomng Problem Identification and Resolution (Pi&R) Inspection at the Prairie Island Nuclear Generating Plant
ML21033A6112021-02-0101 February 2021
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team); Inspection Report 05000282/2021010 and 05000306/2021010
ML20343A1292020-12-0808 December 2020
NRR E-mail Capture - Request for Additional Information
ML20192A1442020-07-0707 July 2020
NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505
ML20189A1782020-07-0606 July 2020
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2020004; 05000306/2020004
ML20133K0692020-05-14014 May 2020
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML20077K6242020-04-13013 April 2020
License Amendment Request - Request for Additional Information
ML20052F4102020-02-21021 February 2020
Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information
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)
ML19233A0032019-08-14014 August 2019
NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10
ML19057A1652019-02-26026 February 2019
NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request
ML18313A0832018-11-0707 November 2018
NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request
ML18264A1912018-09-19019 September 2018
NRC Information Request (9/19/2018); Part B Items (Onsite) IP 71111.08 - E-Mailed 09/19/18 (DRS-M.Holmberg)
ML18235A2982018-08-23023 August 2018
NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request
ML18169A4202018-06-25025 June 2018
Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Modify Renewed Facility Operating License Paragraph 2.C(4)(c)
ML18025C0152018-01-24024 January 2018
Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000282/2018011; 05000306/2018011 (DRS-A.Dunlop)
ML17277B3332017-10-0404 October 2017
NRR E-mail Capture - Request for Additional Information Prairie Island Special Heavy Lifting Devices LAR
ML17249A9232017-09-0606 September 2017
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2017004; 05000306/2017004 (Exf)
ML17235A9982017-08-23023 August 2017
NRR E-mail Capture - Request for Additional Information Prairie Island EAL Scheme Change
ML17221A3892017-08-0909 August 2017
NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization
ML17219A0762017-08-0707 August 2017
NRR E-mail Capture - Request for Additional Information for Prairie Island Nuclear Generating Plant License Amendment Request Dated February 23, 2017 Emergency Response Organization
ML17038A5132017-02-0707 February 2017
NRR E-mail Capture - Prairie Island NFPA 805 LAR, PRA RAI 21.01
ML17018A4272017-01-18018 January 2017
NRR E-mail Capture - Request for Additional Information: Prairie Island License Amendment Request to Revise Technical Specification 3.8.7 to Remove Non-Conservative Required Action
ML16326A3532016-11-18018 November 2016
NRR E-mail Capture - Draft Request for Information Related to Prairie Island NFPA-805 License Amendment
ML16265A1652016-09-20020 September 2016
Notification of an NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000282/2016004; 05000306/2016004 (Gfo)
ML16189A2052016-07-0707 July 2016
Notification of NRC Inspection and Request for Information
ML16113A1612016-04-21021 April 2016
Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Prairie Island Nuclear Generating Plant, Units 1 and 2
2024-07-15
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NRR-PMDAPEm Resource From: Kuntz, Robert Sent: Friday, November 18, 2016 9:20 AM To: Eckholt, Gene F.
Cc: Hazelhoff, Amy
Subject:
DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735)
Mr. Eckholt, By letter dated September 28, 2012 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML12278A405), as supplemented by letters dated November 8 and December 18, 2012; May 3 and October 17, 2013; April 30, 2014; May 28, June 19, October 6, and October 22, 2015; January 20, May 24, and August 17, 2016 (ADAMS Accession Nos. ML12314A144, ML12354A464, ML13126A115, ML13291A367, ML14125A106, ML15153A018, ML15174A139, ML15280A044, ML15296A259, ML16020A375, ML16152A046, ML16230A554, respectively); Northern States Power Company, a Minnesota corporation (NSPM, the licensee), doing business as Xcel Energy, submitted a license amendment request (LAR) to transition its fire protection licensing basis at the Prairie Island Nuclear Generating Plant (PINGP),
Units 1 and 2, from paragraph 50.48(b) of Title 10 of the Code of Federal Regulations (10 CFR) to 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805 (NFPA 805). Supplemental information has been requested by the NRC staff and provided NSPM.
A DRAFT requests for additional information (RAI) is provided below. If clarification is requested on the RAI contact me and I will arrange a teleconference with the NRC staff. If no clarification is required, then this DRAFT RAI will become a final RAI and a response will be expected within 30 days of this e-mail.
Robert Kuntz Senior Project Manager (Monticello and Prairie Island)
NRC/NRR/DORL/LPL3-1 (301)415-3733 REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM, THE LICENSEE)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT (PINGP), UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 (TAC NOS. ME9734 AND ME9735)
Probabilistic Risk Assessment (PRA) Request for Additional Information (RAI) 21 Very Early Warning Fire Detection System Credit 1
Section 2.4.3.3 of National Fire Protection Association (NFPA) Standard 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, states that the probabilistic safety analysis (PSA) (PSA is also referred to as probabilistic risk assessment (PRA)) approach, methods, and data shall be acceptable to the authority having jurisdiction, which is the Nuclear Regulatory Commission (NRC). Section 2.4.4.1 of NFPA 805 further states that the change in public health risk arising from transition from the current fire protection program to an NFPA 805 based program, and all future plant changes to the program, shall be acceptable to the NRC. Regulatory Guide 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Revision 2, (RG 1.174) provides quantitative guidelines on core damage frequency (CDF), large early release frequency (LERF), and identifies acceptable changes to these frequencies that result from proposed changes to the plants licensing basis and describes a general framework to determine the acceptability of risk-informed changes. The NRC staffs review of the information in the license amendment request identified additional information that is required to fully characterize the risk estimates.
New guidance on the credit taken for very early warning fire detection system (VEWFDS) is available in NUREG-2180, Determining the Effectiveness, Limitations, and Operator Response for Very Early Warning Fire Detection Systems in Nuclear Facilities, (Delores-VEWFIRE) of which the pre-publication final version is available at Agencywide Documents Access and Management System (ADAMS) Accession Nos.
ML16286A000 and ML16286A002 (note that the accession numbers may change when the final version is published). The methodology in NUREG-2180 is acceptable to the NRC because it is currently the best available guidance. The guidance provided in frequently asked question (FAQ) 08-0046, Closure of National Fire Protection Association 805 Frequently Asked Question 08-0046 Incipient Fire Detection Systems (ADAMS Accession No. ML093220426), has been retired and alternative approaches for staff evaluation are necessary to complete the safety evaluation.
Explain how credit (e.g., approach, methods, data, and assumptions) taken in the fire PRA (FPRA) for the proposed VEWFDS is consistent with the guidance in NUREG-2180 or bounds the risk results (i.e., CDF, LERF, change in CDF, and change in LERF) that would be obtained had the guidance in NUREG-2180 been applied. If credit taken for VEWFDS in the FPRA is not consistent with or bounded by NUREG-2180, provide:
- a. The risk results (i.e., CDF, LERF, change in CDF, and change in LERF): (1) without credit for VEWFDS, (2) that would be obtained had the guidance in NUREG-2180 been applied, or that would be obtained had an alternative method been used, along with a description and justification for the alternative method. Development and use of an alternative proposal may extend the time required to complete the review. The new risk results can be generated from a sensitivity study type evaluation insofar as formal incorporation of the new method into the PRA model of record is not required.
- b. Explain how the total risk and increases in risk are consistent with the guidelines in RG 1.174.
- c. If additional method and model modifications to the PRA are used and discussed in response to item a.
above, explain how they will be incorporated into the PRA model of record that will be used to determine whether the as-built modifications meet the RG 1.174 guidelines and to support the self-approval of post-transition changes.
2
Hearing Identifier: NRR_PMDA Email Number: 3172 Mail Envelope Properties (e62ef7aef70b4ccab2dbdae68a22b7d8)
Subject:
DRAFT Request for Information related to Prairie Island NFPA-805 license amendment (CAC No. ME9734 and ME9735)
Sent Date: 11/18/2016 9:19:45 AM Received Date: 11/18/2016 9:19:45 AM From: Kuntz, Robert Created By: Robert.Kuntz@nrc.gov Recipients:
"Hazelhoff, Amy" <Amy.Hazelhoff@xenuclear.com>
Tracking Status: None "Eckholt, Gene F." <Eugene.Eckholt@xenuclear.com>
Tracking Status: None Post Office: HQPWMSMRS02.nrc.gov Files Size Date & Time MESSAGE 5748 11/18/2016 9:19:45 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
