Letter Sequence Acceptance Review |
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MONTHYEARML16007A4602016-01-0707 January 2016 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for License Amendment Request Supporting Spent Fuel Pool Criticality TS Changes Project stage: Acceptance Review ML16144A8052016-05-23023 May 2016 Supplement to License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes: Cover Letter Response to RAI Project stage: Response to RAI ML16160A0772016-06-24024 June 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance 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 Project stage: Response to RAI ML17066A3732017-03-0909 March 2017 Spent Fuel Pool Criticality Technical Specification Changes Round 2 Request for Additional Information Public Meeting: March 9, 2017 Project stage: Meeting ML17093A6012017-04-0606 April 2017 March 9, 2017, Summary of Meeting with Northern States Power Company, Doing Business as Xcel Energy, Related to the Spent Fuel Pool Criticality License Amendment Request Project stage: Meeting L-PI-17-014, Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121...2017-04-19019 April 2017 Summary of Public Meeting and Plan for NRC Request for Additional Information Regarding License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121... Project stage: Meeting ML17279A1242017-09-30030 September 2017 Enclosure 5 to L-PI-17-041, Westinghouse WCAP-17400-NP, Supplemental 1, Revision 2, Spent Fuel Pool Criticality Safety Analysis Supplemental Analysis Including the Storage of Ifba Bearing Fuel Project stage: Supplement ML17279A1202017-10-0404 October 2017 Response to Request for Additional Information Re License Amendment Request for Spent Fuel Pool Criticality Technical Specification Changes Project stage: Response to RAI L-PI-17-041, Enclosure 6 to L-PI-17-041, Westinghouse Affidavits2017-10-0404 October 2017 Enclosure 6 to L-PI-17-041, Westinghouse Affidavits Project stage: Other 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 Project stage: Other ML17313B1902017-11-13013 November 2017 Request for Withholding Information from Public Disclosure (CAC Nos. MF7121 and MF7122; EPID L-2015-LLA-0002) Project stage: Withholding Request Acceptance ML17334A1782017-11-30030 November 2017 Issuance of Amendment Request Related to Spent Fuel Pool Criticality Technical Specification Changes (CAC Nos. MF7121 and MF7122, EPID L-2015-LLA-0002) Non-Proprietary Project stage: Approval 2017-11-30
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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
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1NRR-PMDAPEm ResourceFrom:Beltz, TerrySent:Thursday, January 07, 2016 12:22 PMTo:'Adams, Glenn D.'Cc:Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com); 'marc.pearson@xenuclear.com'; Carlson, Glenn A. (Glenn.Carlson@xenuclear.com); Patel, Amrit; Wood, Kent; Pelton, David; Kuntz, Robert; Oesterle, Eric; RidsNRRLIC109 Resource
Subject:
Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for LAR Supporting SFP Criticality TS Changes (CAC Nos. MF7121 and MF7122)
Dear Mr. Adams:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated November 17, 2015 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML15327A244), Northern States Power Company - Minnesota (the licensee), doing business as Xcel Energy, Inc., submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The licensee proposes to revise PINGP Technical Specification (TS) 3.7.16, "Spent Fuel Storage Pool Boron Concentration," and TS 4.3.1, "Fuel Storage Criticality," to allow spent fuel pool storage of nuclear fuel containing a boron-based neutron absorber in the form of zirconium diboride IFBA [integral fuel burnable absorber]. The proposed change involves an explicit change to the criticality analysis methodology, and also introduces two changes to the licensing basis as inputs to the models used in the spent fuel criticality analysis.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The purpose of this e-mail is to provide the final results of the NRC staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your application and concluded that there appears to be sufficient technical information, both in scope and depth, to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the LAR in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact Rob Kuntz at (301) 415-3733.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 2Mail Stop: O-8D15 Phone: (301) 415-3049 Terry.Beltz@nrc.gov Confidentiality Notice: This email message, including any attachments, contains or may contain confidential information intended only for the addressee. If you are not an intended recipient of this message, be advised that any reading, dissemination, forwarding, printing, copying or other use of this message or its attachments is strictly prohibited. If you have received this message in error, please notify the sender immediately by reply message and delete this email message and any attachments from your system.
Hearing Identifier: NRR_PMDA Email Number: 2581 Mail Envelope Properties (5ff12c11e5fa40528fee25ae5e8a3f04)
Subject:
Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for LAR Supporting SFP Criticality TS Changes (CAC Nos. MF7121 and MF7122) Sent Date: 1/7/2016 12:21:48 PM Received Date: 1/7/2016 12:21:00 PM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com> Tracking Status: None
"'marc.pearson@xenuclear.com'" <marc.pearson@xenuclear.com> Tracking Status: None "Carlson, Glenn A. (Glenn.Carlson@xenuclear.com)" <Glenn.Carlson@xenuclear.com>
Tracking Status: None "Patel, Amrit" <Amrit.Patel@nrc.gov> Tracking Status: None "Wood, Kent" <Kent.Wood@nrc.gov> Tracking Status: None "Pelton, David" <David.Pelton@nrc.gov>
Tracking Status: None "Kuntz, Robert" <Robert.Kuntz@nrc.gov> Tracking Status: None "Oesterle, Eric" <Eric.Oesterle@nrc.gov> Tracking Status: None "RidsNRRLIC109 Resource" <RidsNRRLIC109.Resource@nrc.gov> Tracking Status: None "'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com>
Tracking Status: None Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 3463 1/7/2016 12:21:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: ZZZ 1NRR-PMDAPEm ResourceFrom:Beltz, TerrySent:Thursday, January 07, 2016 12:22 PMTo:'Adams, Glenn D.'Cc:Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com); 'marc.pearson@xenuclear.com'; Carlson, Glenn A. (Glenn.Carlson@xenuclear.com); Patel, Amrit; Wood, Kent; Pelton, David; Kuntz, Robert; Oesterle, Eric; RidsNRRLIC109 Resource
Subject:
Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for LAR Supporting SFP Criticality TS Changes (CAC Nos. MF7121 and MF7122)
Dear Mr. Adams:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated November 17, 2015 (Agencywide Documents Access and Management System (ADAMS) Package Accession No. ML15327A244), Northern States Power Company - Minnesota (the licensee), doing business as Xcel Energy, Inc., submitted a license amendment request (LAR) for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The licensee proposes to revise PINGP Technical Specification (TS) 3.7.16, "Spent Fuel Storage Pool Boron Concentration," and TS 4.3.1, "Fuel Storage Criticality," to allow spent fuel pool storage of nuclear fuel containing a boron-based neutron absorber in the form of zirconium diboride IFBA [integral fuel burnable absorber]. The proposed change involves an explicit change to the criticality analysis methodology, and also introduces two changes to the licensing basis as inputs to the models used in the spent fuel criticality analysis.
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. The purpose of this e-mail is to provide the final results of the NRC staff's acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your application and concluded that there appears to be sufficient technical information, both in scope and depth, to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the LAR in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. Should you have any questions regarding this review, please contact Rob Kuntz at (301) 415-3733.
Sincerely, TERRY A. BELTZ, SENIOR PROJECT MANAGER U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738 2Mail Stop: O-8D15 Phone: (301) 415-3049 Terry.Beltz@nrc.gov Confidentiality Notice: This email message, including any attachments, contains or may contain confidential information intended only for the addressee. If you are not an intended recipient of this message, be advised that any reading, dissemination, forwarding, printing, copying or other use of this message or its attachments is strictly prohibited. If you have received this message in error, please notify the sender immediately by reply message and delete this email message and any attachments from your system.
Hearing Identifier: NRR_PMDA Email Number: 2581 Mail Envelope Properties (5ff12c11e5fa40528fee25ae5e8a3f04)
Subject:
Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance Review for LAR Supporting SFP Criticality TS Changes (CAC Nos. MF7121 and MF7122) Sent Date: 1/7/2016 12:21:48 PM Received Date: 1/7/2016 12:21:00 PM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients: "Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com> Tracking Status: None
"'marc.pearson@xenuclear.com'" <marc.pearson@xenuclear.com> Tracking Status: None "Carlson, Glenn A. (Glenn.Carlson@xenuclear.com)" <Glenn.Carlson@xenuclear.com>
Tracking Status: None "Patel, Amrit" <Amrit.Patel@nrc.gov> Tracking Status: None "Wood, Kent" <Kent.Wood@nrc.gov> Tracking Status: None "Pelton, David" <David.Pelton@nrc.gov>
Tracking Status: None "Kuntz, Robert" <Robert.Kuntz@nrc.gov> Tracking Status: None "Oesterle, Eric" <Eric.Oesterle@nrc.gov> Tracking Status: None "RidsNRRLIC109 Resource" <RidsNRRLIC109.Resource@nrc.gov> Tracking Status: None "'Adams, Glenn D.'" <Glenn.Adams@xenuclear.com>
Tracking Status: None Post Office: HQPWMSMRS05.nrc.gov Files Size Date & Time MESSAGE 3463 1/7/2016 12:21:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received: ZZZ