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| | number = ML12215A252 | | | number = ML12215A252 |
| | issue date = 08/07/2012 | | | issue date = 08/07/2012 |
| | title = Prairie Island Nuclear Generating Plant, Units 1 and 2 - Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes | | | title = Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes |
| | author name = Wengert T J | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Molden J E | | | addressee name = Molden J |
| | addressee affiliation = Northern States Power Co | | | addressee affiliation = Northern States Power Co |
| | docket = 05000282, 05000306 | | | docket = 05000282, 05000306 |
| | license number = DPR-042, DPR-060 | | | license number = DPR-042, DPR-060 |
| | contact person = Wengert T J | | | contact person = Wengert T |
| | case reference number = TAC ME6984, TAC ME6985 | | | case reference number = TAC ME6984, TAC ME6985 |
| | document type = Request for Additional Information (RAI), Letter | | | document type = Request for Additional Information (RAI), Letter |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company -Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985) Dear Mr. Molden: By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML 12139A 198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012. The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985) |
| J. Molden -If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. Sincerely, Docket Nos. 50-282 and 50-306 Enclosure: Request for Additional Information cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION (RAI) PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML 12139A 198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review. This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response"). Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading. A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading. NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis. RAI-SRXB-2: The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G. Enclosure | | |
| -2 The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh What is the basis for 4 percent 235U assumption? What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis? RAI-SRX8-4 (Axial blankets): Show that neglecting the hollow annular pellets in the blankets is always conservative. RAI-SRX8-5 (Axial Provide the analysis results that support the selection of the axial burnup profiles used in analysis (e.g., k-effective results and corresponding "shape depletion RAI-SRX8-6 (Operation with control In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design cases and the "Rodded" RAI-SRX8-7 (Criticality code validation fission product The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance. | | ==Dear Mr. Molden:== |
| J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 Enclosure: Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION: PUBLIC LPL3-1 RtF RidsNrrPMPrairielsland Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource RidsNrrDorlLpl3-1 Resource RidsNrrLABTully Resource RidsOgcRp Resource RidsNrrDorlDpr Resource TNakanishi, NRR KWood, NRR ADAMS Accession Number: ML 12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A) BTully/SRohrer IfI SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy | | |
| }} | | By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2. |
| | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012. |
| | The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. |
| | |
| | J. Molden - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. |
| | Sincerely, Docket Nos. 50-282 and 50-306 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via ListServ |
| | |
| | REQUEST FOR ADDITIONAL INFORMATION (RAI) |
| | PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review. |
| | This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response"). |
| | Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading. |
| | A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading. |
| | NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis. |
| | RAI-SRXB-2: |
| | The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G. |
| | Enclosure |
| | |
| | -2 RAI-SRX8-3: |
| | The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh fuel. |
| | : a. What is the basis for 4 percent 235U assumption? |
| | : b. What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis? |
| | RAI-SRX8-4 (Axial blankets): |
| | Show that neglecting the hollow annular pellets in the blankets is always conservative. |
| | RAI-SRX8-5 (Axial profile): |
| | Provide the analysis results that support the selection of the axial burnup profiles used in the analysis (e.g., k-effective results and corresponding "shape depletion factors"). |
| | RAI-SRX8-6 (Operation with control rods): |
| | In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design basis" cases and the "Rodded" cases? |
| | RAI-SRX8-7 (Criticality code validation fission product bias): |
| | The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show that the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance. |
| | |
| | J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037. |
| | Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306 |
| | |
| | ==Enclosure:== |
| | |
| | Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION: |
| | PUBLIC LPL3-1 RtF RidsNrrDorlLpl3-1 Resource RidsNrrDorlDpr Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource TNakanishi, NRR RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource KWood, NRR RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource ADAMS Accession Number: ML12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A) |
| | BTully/SRohrer IfI SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy}} |
Letter Sequence RAI |
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|
|
MONTHYEARML11236A1342011-07-31031 July 2011
Westinghouse WCAP-17400-NP, Rev. 0, Prairie Island, Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis, Enclosure 4
Project stage: Request
L-2011-409, Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts2011-10-14014 October 2011
Revision to Extended Power Uprate License Amendment Request Proposed Technical Specification Regarding Fuel Loading Curve and Areal Density Criteria for Metamic Inserts
Project stage: Request
ML1125602172011-10-25025 October 2011
Request for Withholding of Proprietary Information from Public Disclosure
Project stage: Withholding Request Acceptance
ML1206203892012-03-20020 March 2012
Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes
Project stage: RAI
L-2012-132, Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References2012-03-31031 March 2012
Extended Power Uprate License Amendment Request - Supplement to Proposed Technical Specification Changes Related to Spent Fuel Storage Requirements and Core Operating Limits Report (COLR) References
Project stage: Supplement
L-PI-12-038, Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.2012-05-0303 May 2012
Westinghouse, Affidavit - CE-12-3 16, Revision 1, Westingliouse Suggested Responses to the Requests for Additional Information Presented in ML120620389.
Project stage: Other
ML12139A1982012-05-16016 May 2012
Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes (TAC Nos. ME6984 and ME69851)
Project stage: Response to RAI
ML12215A2522012-08-0707 August 2012
Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes
Project stage: RAI
L-PI-12-066, Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure2012-08-27027 August 2012
Enclosure 2 to L-PI-12-066 - Westinghouse Affidavit, Application for Withholding Proprietary Information from Public Disclosure
Project stage: Request
ML12249A0692012-09-0404 September 2012
Response to Requests for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes
Project stage: Response to RAI
ML13011A3162013-01-22022 January 2013
Request for Additional Information Related to License Amendment Request for Spent Fuel Pool Criticality Changes
Project stage: RAI
L-PI-13-002, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-02-0808 February 2013
Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes
Project stage: Response to RAI
ML13197A3972013-06-25025 June 2013
NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI
Project stage: Draft Other
L-PI-13-067, Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes2013-07-17017 July 2013
Response to Request for Additional Information (RAI) Associated with Spent Fuel Pool Criticality Changes
Project stage: Response to RAI
ML13241A3832013-08-29029 August 2013
Issuance of Amendments Spent Fuel Pool Criticality Changes
Project stage: Approval
2012-08-27
[Table View] |
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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
[Table view]
Category:Letter
MONTHYEARML24277A1012024-10-0303 October 2024
Closure of Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software
ML24241A1682024-09-23023 September 2024
Transmittal Letter Amendment No. 13 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
05000282/LER-2024-001, Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies2024-09-16016 September 2024
Auxiliary Building Special Ventilation System Inoperable During Movement of Irradiated Fuel Assemblies
IR 05000282/20243012024-09-13013 September 2024
NRC Initial License Examination Report 05000282/2024301 and 05000306/2024301
IR 05000282/20240052024-08-28028 August 2024
Updated Inspection Plan and Assessment Follow-Up Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2024005 and 05000306/2024005)
L-PI-24-040, Post-Submittal Package Letter2024-08-23023 August 2024
Post-Submittal Package Letter
IR 05000282/20245012024-08-0505 August 2024
Emergency Preparedness Inspection Report 05000282/2024501 and 05000306/2024501
ML24213A1592024-07-31031 July 2024
Operator Licensing Examination Approval - Prairie Island Nuclear Generating Plant
IR 05000282/20240022024-07-30030 July 2024
Integrated Inspection Report 05000282/2024002 and 05000306/2024002
ML24208A1502024-07-26026 July 2024
Independent Spent Fuel Storage Installation - Submittal of Quality Assurance Topical Report (NSPM-1)
ML24197A2012024-07-15015 July 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000282/2024004
L-PI-24-036, – Preparation and Scheduling of Operator Licensing Examinations2024-06-28028 June 2024
– Preparation and Scheduling of Operator Licensing Examinations
IR 05000282/20240102024-06-28028 June 2024
Comprehensive Engineering Team Inspection Report 05000282/2024010 and 05000306/2024010
ML24158A5912024-06-0606 June 2024
CFR 50.46 LOCA Annual Report
L-PI-24-031, Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-06-0505 June 2024
Independent Spent Fuel Storage Installation, Supplement to License Amendment Request to Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)
L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption2024-06-0303 June 2024
License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption
ML24155A1952024-05-31031 May 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
ML24155A1922024-05-31031 May 2024
Refueling Outage Unit 2 R33 Owners Activity Report for Class 1, 2, 3 and Mc Inservice Inspections
ML24149A3712024-05-29029 May 2024
(Ping) - Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection
ML24262A1992024-05-29029 May 2024
L-PI-24-018 PINGP 75 Day Letter
L-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
ML24141A1292024-05-22022 May 2024
Northern States Power Company - Use of Encryption Software for Electronic Transmission of Safeguards Information
ML24141A0452024-05-20020 May 2024
Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection
ML24128A2572024-05-16016 May 2024
ISFSI A13 Acceptance Letter
IR 05000282/20240012024-05-15015 May 2024
Integrated Inspection Report 05000282/2024001 and 05000306/2024001
ML24130A2392024-05-0909 May 2024
2023 Annual Radioactive Effluent Report
ML24130A2362024-05-0909 May 2024
Independent Spent Fuel Storage Installation - 2023 Annual Radiological Environmental Monitoring Program Report
ML24071A1162024-05-0101 May 2024
Issuance of Amendment Nos. 244 and 232 Revise TS 3.7.8, Cooling Water (Cl) System
ML24128A0882024-04-30030 April 2024
Submittal of Updated Safety Analysis Report (Usar), Revision 38
ML24089A2382024-04-29029 April 2024
Summary of Nuclear Property Insurance
ML24121A0432024-04-29029 April 2024
Reactor Trip and Auto-Start Actuation of Auxiliary Feedwater Due to Loss of Suction to the 22 Main Feedwater Pump
IR 05000282/20244012024-04-25025 April 2024
– Security Baseline Inspection Report 05000282/2024401 and 05000306/2024401
ML24100A8042024-04-24024 April 2024
– Alternative Request RR-09 for Safety Injection and Volume Control System Category C Check Valve Inservice Testing
ML24114A0882024-04-23023 April 2024
Annual Report of Individual Monitoring for the Prairie Island Nuclear Generating Plant (PINGP)
ML24113A1182024-04-12012 April 2024
NRC Letter Re NRC Office of Investigations Report No. 3-2023-004
ML24100A1212024-04-0909 April 2024
Submittal of Revised Pressure and Temperature Limits Report
L-PI-24-012, Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)2024-04-0202 April 2024
Independent Spent Fuel Storage Installation - License Amendment Request: Revise Independent Spent Fuel Storage Installation (ISFSI) License Conditions 23(a), 24(A)(2), and 24(B)(2)
ML24093A2832024-04-0202 April 2024
Nuclear Material Transaction Report
ML24089A2402024-03-29029 March 2024
Guarantee of Payment of Deferred Premiums
ML24060A1232024-03-27027 March 2024
to Request 1-RR-5-10 and 2-RR-5-10 Regarding Reactor Pressure Vessel Welds and Nozzle Welds
ML24081A1532024-03-21021 March 2024
Reactor Trip, Auxiliary Feedwater and Emergency Service Water System Actuation Due to Electrical Transient in DC Control Power Cables
ML24262A1512024-03-15015 March 2024
L-PI-24-011 150 Day Letter 2024 PINGP ILT NRC Exam
ML24010A0582024-03-0505 March 2024
Amendment No. 12 to Materials License No. Special Nuclear Material-2506 for the Prairie Island Independent Spent Fuel Storage Installation
L-PI-24-004, Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 20232024-02-29029 February 2024
Independent Spent Fuel Storage Installation - Annual Effluent Report, January Through December 2023
IR 05000282/20230062024-02-28028 February 2024
Annual Assessment Letter for Prairie Island Nuclear Generating Plant, Units 1 and 2 (Report 05000282/2023006 and 05000306/2023006)
ML24088A1102024-02-25025 February 2024
Fairbanks Morse (Fm) Part 21 Notification Report Number 23-01 Re Asco Stainless Steel Solenoid Valves
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
ML24040A1712024-02-0909 February 2024
Interim Report of a Potential Deviation or Failure to Comply Associated with Bentley Systems Incorporated Autopipe Software
IR 05000282/20230042024-02-0101 February 2024
Integrated Inspection Report 05000282/2023004 and 05000306/2023004
ML23356A1232024-01-29029 January 2024
Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)
2024-09-23
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 7, 2012 Mr. James E. Molden Site Vice President Prairie Island Nuclear Generating Plant Northern States Power Company - Minnesota 1717 Wakonade Drive East Welch, MN 55089-9642 SUB~IECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR SPENT FUEL POOL CRITICALITY CHANGES (TAC NOS. ME6984 AND ME6985)
Dear Mr. Molden:
By letter dated August 19, 2011, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company (NSPM, the licensee), a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant, Units 1 and 2.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. On July 19, 2012, Mr. Glenn Adams of your staff agreed that you would provide a response to this request by September 5, 2012.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
J. Molden - 2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, Docket Nos. 50-282 and 50-306
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION (RAI)
PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated August 19, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112360231), as supplemented by letter dated May 16, 2012 (ADAMS Accession No. ML12139A198), Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy, requested approval from the U.S. Nuclear Regulatory Commission (NRC) for amendments to technical specifications (TS) 3.7.17, "Spent Fuel Pool Storage" and TS 4.3.1, "Fuel Storage Criticality," for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. The NRC staff has reviewed this request and has determined that the following information is required to complete its review.
This RAI concerns the licensee's May 16, 2012 RAI response (hereafter referred to as "the response").
Reactor Systems Branch (SRXB) RAls RAI-SRXB-1 During a June 21, 2012, teleconference, the licensee provided clarifications on the KENO model supporting the gadolinia sensitivity analysis in terms of assumed burnup distribution and axial poison loading.
A review of NUREG/CR-6760 shows that the axial effects were not considered for the gadolinia burnable absorber. NUREG/CR-6760 appears to suggest that a 2-D model may under-predict the integral fuel burnable absorber effects relative to a 3-D model that includes an axial burnup distribution and actual poison loading. To ensure that the no-gadolinia assumption remains valid for the full range of credited burnup, provide a quantitative analysis modeling the effects of axially-distributed burnup and appropriate axial poison loading.
NUREG/CR-6760 also appears to indicate that the spectral hardening due to the presence of strong neutron absorbers may also affect the results. Therefore, include both borated and unborated conditions in the analysis.
RAI-SRXB-2:
The response to RAI-SRXB-2 does not appear to adequately address Array G (3x3 with a rod cluster control assembly). Show that the selected design basis assembly remains limiting for Array G.
Enclosure
-2 RAI-SRX8-3:
The response to RAI-SRX8-3 shows the optimum condition for 4 percent 235U fresh fuel.
- a. What is the basis for 4 percent 235U assumption?
- b. What accounts for the difference in k-effective results between Table 3-1 (12x12 case) and Figure 3-2 at the volume fraction used in the final analysis?
RAI-SRX8-4 (Axial blankets):
Show that neglecting the hollow annular pellets in the blankets is always conservative.
RAI-SRX8-5 (Axial profile):
Provide the analysis results that support the selection of the axial burnup profiles used in the analysis (e.g., k-effective results and corresponding "shape depletion factors").
RAI-SRX8-6 (Operation with control rods):
In Figures 6-1 through 6-10, what are the differences in assumptions between the "Design basis" cases and the "Rodded" cases?
RAI-SRX8-7 (Criticality code validation fission product bias):
The specifics of the referenced Turkey Point analysis differ from the PINGP analysis. Show that the approach used in the PINGP analysis is conservative relative to the method described in the interim staff guidance.
J. Molden -2 If circumstances result in the need to revise the requested response date, please contact me at (301) 415-4037.
Sincerely, IRAJ Thomas J. Wengert, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-282 and 50-306
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 RtF RidsNrrDorlLpl3-1 Resource RidsNrrDorlDpr Resource RidsNrrPMPrairielsland Resource RidsNrrLABTully Resource TNakanishi, NRR RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource KWood, NRR RidsRgn3MailCenter Resource RidsNrrDssSrxb Resource ADAMS Accession Number: ML12215A252 NRR/LPL3-1/PM NRR/LPL3-1/LA NRRlSRXB/BC(A)
BTully/SRohrer IfI SMiranda 08/06/12 08/06/12 LPL3-1/PM NAME SFrankl TWengert DATE 08/07/12 08/07/12 OFFICIAL RECORD COpy
