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| | number = ML13197A397 | | | number = ML13197A397 |
| | issue date = 06/25/2013 | | | issue date = 06/25/2013 |
| | title = Ngp - Sfpc LAR Draft RAI (TAC Nos. ME6984 and ME6985) | | | title = NRR E-mail Capture - Prairie Island Ngp - Sfpc LAR Draft RAI (TAC Nos. ME6984 and ME6985) |
| | author name = Wengert T | | | author name = Wengert T |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
Revision as of 12:48, 5 December 2019
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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
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Category:E-Mail
MONTHYEARML23348A3472023-12-12012 December 2023 NRR E-mail Capture - (External_Sender) NRC Notification to the State of Minnesota Regarding a Prairie Island Nuclear Generating Plant, Units 1 & 2, Amendment ML23335A1152023-12-0101 December 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Request for Additional Information LAR to Revise TS 3.7.8 Required Actions ML23312A0882023-11-0808 November 2023 Acceptance of Request to Revise Alternatives 1-RR-5-10 and 2-RR-5-10 ML23248A3462023-09-0505 September 2023 NRR E-mail Capture - Request for Additional Information for Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant - Decommissioning Funding Status Reports ML23207A1962023-07-26026 July 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Requested Licensing Action Request to Revise Technical Specification 3.7.8 Required Actions ML23075A2802023-03-16016 March 2023 NRR E-mail Capture - Prairie Island Units 1 and 2 - Acceptance of Relief Requests 1-RR-5-15 and 2-RR-5-15 to Use Subsequent ASME Code Edition and Addenda ML23065A0592023-02-27027 February 2023 NRR E-mail Capture - (External_Sender) Prairie Island Request for Pre-application Meeting for Proposed LAR to Change TS 3.7.8, Condition B Required Actions ML23018A2952023-01-18018 January 2023 Acceptance of Requested Licensing Action to Revise Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) (EPID L-2022-LLA-0184) (Email) ML22167A0452022-06-16016 June 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Request to Adopt TSTF-277 ML22166A4112022-06-15015 June 2022 NRR E-mail Capture - Request for Additional Information Prairie Island Nuclear Generating Plant, Unit 2, Alternative RR-08, PIV Leakage ML22160A6022022-06-0909 June 2022 NRR E-mail Capture - Draft Request for Additional Information Prairie Island Nuclear Generating Plant, Units 1 and 2, 24-Month Operating Cycle Amendment ML22131A2652022-05-11011 May 2022 NRR E-mail Capture - Request for Additional Information Xcel Energy Amendment Request to Create a Common Eplan and EOF for Monticello and Prairie Island ML22045A4972022-02-14014 February 2022 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Unit 2 - Acceptance of Alternative Request Alternative Related PIV Leakage Monitoring ML21347A0082021-12-10010 December 2021 NRR E-mail Capture - Monticello and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested License Amendment Standard Emergency Plan and Consolidated Emergency Operations Facility ML21321A0452021-11-10010 November 2021 Request for Additional Information: Prairie Island 24-Month Cycle Amendment Request ML21302A1252021-10-29029 October 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action RTS Power Range Amendment ML21305A0102021-10-29029 October 2021 NRR E-mail Capture - Request for Additional Information Prairie Island Cooling Water Amendment ML21252A0152021-09-0202 September 2021 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Change in the Maximum Surveillance Intervals from 24 Months to 30 Months ML21252A0122021-08-30030 August 2021 NRR E-mail Capture - Request for Additional Information Amendment Request to Adopt TSTF-471 and 517-T for Prairie Island ML21133A2502021-05-13013 May 2021 NRR E-mail Capture - Prairie Island - Acceptance Review of TSTF-471 and TSTF-571-T ML20343A1292020-12-0808 December 2020 NRR E-mail Capture - Request for Additional Information ML20253A2782020-09-0909 September 2020 E-Mail Submitting Proposed New License Condition ML20254A1162020-09-0909 September 2020 Draft License Transmittal E-Mail ML20223A0632020-08-10010 August 2020 Email Shpo Comment Letter: Proposed License Amendment for the Prairie Island Independent Spent Fuel Storage Installation ML20192A1442020-07-0707 July 2020 NRR E-mail Capture - Request for Additional Information Prairie Island License Amendment Request to Adopt TSTF-505 ML20163A4282020-06-10010 June 2020 Email from MPCA Comment Letter - Prairie Island ISFSI ML20154K7632020-06-0202 June 2020 NRR E-mail Capture - Revision 2 to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20135G8212020-05-14014 May 2020 NRR E-mail Capture - Revision to the Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20112F4582020-04-21021 April 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Low Temperature Overpressure Protection ML20083F4202020-03-20020 March 2020 NRR E-mail Capture - Plan for the Audit of the Prairie Island Nuclear Generating Plant TSTF-505 License Amendment Request (Epdi: L-2019-LLA-0283) ML20077L4632020-03-17017 March 2020 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 -Acceptance of Requested Licensing Action Request to Adopt TSTF-529 ML20052C7582020-02-21021 February 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Westinghouse NSAL-09-05 and NSAL-09-05 ML20035F1552020-02-0404 February 2020 NRR E-mail Capture - Request for Additional Information Monticello and Prairie Island Alternative Requests to Adopt Code Cases N-786-3 and N-789-3 (Epids: L-2019-LLR-0078 and L-2019-LLR-0079) ML20022A1762020-01-22022 January 2020 NRR E-mail Capture - Prairie Units 1 and 2 - Acceptance of Requested Licensing Action Application to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements ML20021A1832020-01-21021 January 2020 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2 ML19316A0172019-11-0101 November 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Integrated Leak Rate Test Extension Request ML19253B9642019-09-10010 September 2019 NRR E-mail Capture - Monticello Nuclear Generating Plant and Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Relief Request Adoption of Code Case N-786-3 ML19233A0032019-08-14014 August 2019 NRR E-mail Capture - Request for Additional Information Prairie Island Relief Requests 1-RR-10 and 2-RR-10 ML19193A0142019-07-0909 July 2019 NRR E-mail Capture - Acceptance of Prairie Island Nuclear Generating Plant, Units 1 and 2 Relief Request Nos. 1-RR-5-10 and 2-RR-5-10 Related to Reactor Vessel Inspection Intervals) ML19057A1652019-02-26026 February 2019 NRR E-mail Capture - Request for Additional Information Prairie Island 50.69 Amendment Request ML19057A4212019-02-26026 February 2019 NRR E-mail Capture - Acceptance of Prairie Island Reactor Vessel Capsule Removal Schedule Request ML19008A3562019-01-0707 January 2019 NRR E-mail Capture - Prairie Island Nuclear Generating Plant - Audit Plan Related to the License Amendment Request to Implement 10 CFR 50.69 ML18351A0142018-12-14014 December 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Classification of Certain Fuel Handling Equipment ML18347A3282018-12-12012 December 2018 E-Mail from M. Krick/Sses SSES ISFSI (Conversation Held on December 12, 2018) ML18313A0832018-11-0707 November 2018 NRR E-mail Capture - Request for Additional Information Prairie Island NFPA-805 License Condition Modification Amendment Request ML18235A2982018-08-23023 August 2018 NRR E-mail Capture - Request for Additional Information Prairie Island TSTF-425 License Amendment Request ML18233A3692018-08-21021 August 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Adoption of 10 CFR 50.69 ML18201A4132018-07-20020 July 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-439 ML18159A3052018-06-0808 June 2018 NRR E-mail Capture - Monticello - Acceptance of Requested Relief Request RR-012: Lnservice Inspection Impracticality in Accordance with 10 CFR 50.55a(g)(5)(iii) During the Fifth Ten-Year Interval ML18113A2252018-04-23023 April 2018 NRR E-mail Capture - Prairie Island Nuclear Generating Plant, Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Adopt TSTF-425 2023-09-05
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Text
NRR-PMDAPEm Resource From: Wengert, Thomas Sent: Tuesday, June 25, 2013 11:39 AM To: Adams, Glenn D. (Glenn.Adams@xenuclear.com)
Cc: Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)
Subject:
Prairie Island NGP - SFPC LAR Draft RAI (TAC Nos. ME6984 and ME6985)
Attachments: PINGP Draft RAI Round 04 Rev 0A .pdf
- Glenn, Please see the attached draft RAI concerning the Prairie Island spent fuel pool criticality license amendment request. Please review and lets arrange for a conference call at your earliest convenience for the NRC staff to clarify this request.
- Regards, Tom Wengert Project Manager USNRC NRR/DORL/LPL3-1 (301) 415-4037 1
Hearing Identifier: NRR_PMDA Email Number: 762 Mail Envelope Properties (Thomas.Wengert@nrc.gov20130625113900)
Subject:
Prairie Island NGP - SFPC LAR Draft RAI (TAC Nos. ME6984 and ME6985)
Sent Date: 6/25/2013 11:39:21 AM Received Date: 6/25/2013 11:39:00 AM From: Wengert, Thomas Created By: Thomas.Wengert@nrc.gov Recipients:
"Eckholt, Gene F. (Eugene.Eckholt@xenuclear.com)" <Eugene.Eckholt@xenuclear.com>
Tracking Status: None "Adams, Glenn D. (Glenn.Adams@xenuclear.com)" <Glenn.Adams@xenuclear.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 365 6/25/2013 11:39:00 AM PINGP Draft RAI Round 04 Rev 0A .pdf 85797 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
REQUEST FOR ADDITIONAL INFORMATION NORTHERN STATES POWER COMPANY - MINNESOTA 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. ML11236A133), as supplemented by letters dated May 16, 2012 (ML12139A198), September 4, 2012 (ML12249A069), and February 8, 2013, (ML13039A306)
Northern States Power Company, a Minnesota corporation, doing business as Xcel Energy (the licensee), requested changes to the Technical Specifications (TSs) for Prairie Island Nuclear Generating Plant, Units 1 and 2 (PINGP). Approval of this license amendment request (LAR) will correct non-conservatisms in the spent fuel pool (SFP) nuclear criticality safety (NCS) analysis of record and the associated Technical Specifications (TSs).
The February 8, 2013, letter contained the following revised commitment:
In conjunction with implementation of the proposed TS, procedures will be revised to require an assessment of a fuel assembly's exposure to rodded power operation in the core prior to moving that fuel assembly into the spent fuel pool (SFP) storage racks. If an assembly experiences more than 100 megawatt days per metric ton uranium (MWd/MTU) of core average full-power rodded operation exposure in the cycle immediately prior to discharge to the spent fuel pool, this exposure experienced while rodded will not be credited for determining the coefficients used to categorize fuel assemblies as described in WCAP-17400-P. In addition if an assembly experiences more than 1 gigawatt day per metric ton uranium (GWd/MTU) of core average rodded operation lifetime exposure, the assembly shall be either treated as Fuel Category 1 or evaluated to determine which Fuel Category is appropriate for safe storage of the assembly.
The second sentence of the commitment would require a fuel assembly that receives between 100 megawatt days per metric ton uranium (MWd/MTU) and 1 gigawatt day per metric ton uranium (GWd/MTU) of rodded operation during a cycle (aka cycle N) to have that portion of its depletion discounted when determining which fuel categories it satisfies for storage. However, that burnup would not have to be discounted for storage determinations following subsequent cycles of operation (i.e., cycles N+1 or N+2). NUREG-6759 indicates that once a positive reactivity effect occurs due to rodded operation, it probably does not ever burnout to zero; therefore any penalty that was incurred would have to follow that fuel assembly for its entire life. Even without that, if the affected fuel assemblies had to be offloaded within a few days of the start of the N+1 cycle, the positive reactivity caused by the rodded operation would not have had time to burnout. Therefore the NRC staff requests that the licensee provide justification for not continuing the rodded operation penalty for the entire life of each affected fuel assembly.
The NRC staff believes that storing any fuel assembly that has more than 1 GWd/MTU of rodded operation as a fresh fuel assembly to be conservative and acceptable. However the phrase or evaluated to determine which Fuel Category is appropriate implies an acceptable methodology for making that evaluation. The NRC staff has been unable to discern the methodology the licensee would use to make this evaluation from the currently submitted
information. Therefore, the NRC staff requests the licensee to either provide the rodded operation evaluation methodology for review or strike the phrase from the commitment.