|
|
Line 14: |
Line 14: |
| | document type = Request for Additional Information (RAI) | | | document type = Request for Additional Information (RAI) |
| | page count = 1 | | | page count = 1 |
| | project = TAC:ME2610, TAC:ME2609 | | | project = TAC:ME2609, TAC:ME2610 |
| | stage = Draft RAI | | | stage = Draft RAI |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter: REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-282 AND 50-306 By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098, respectively), Northern States Power Company, a Minnesota corporation (the licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2. The PINGP Updated Safety Analysis Report (USAR) Tables 7.10-1 and 7.10-2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10-2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev. 2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate. Please include a marked-up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation. | | {{#Wiki_filter:REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50 |
| }} | | -282 AND 50 |
| | -306 By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. |
| | ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098 , respectively), Northern States Power Company, a Minnesota corporation (t he licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2. |
| | In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2. |
| | The PINGP Updated Safety Analysis Report (USAR) |
| | Tables 7.10 |
| | -1 and 7.10 |
| | -2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10 |
| | -2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev. |
| | : 2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate. |
| | Please include a marked |
| | -up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation.}} |
Letter Sequence Draft RAI |
---|
TAC:ME2609, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) TAC:ME2610, Control Room Habitability, Deletion of E BAR Definition and Revision to RCS Specific Activity Tech Spec (Approved, Closed) |
Results
Other: L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5, L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology, L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement, ML102300296, ML102300297, ML102300298, ML111822669
|
MONTHYEARL-PI-09-114, License Amendment Request to Adopt the Alternative Source Term Methodology2009-10-27027 October 2009 License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request ML0935704512009-12-23023 December 2009 Acceptance Review of LAR to Adopt Alternative Source Term Methodology (TAC Nos. ME2609 & ME2610) Project stage: Acceptance Review L-PI-10-041, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-04-29029 April 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-046, Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology2010-05-25025 May 2010 Response to Requests for Additional Lnformation License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Request L-PI-10-054, Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology2010-06-23023 June 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI L-PI-10-076, Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 52010-07-23023 July 2010 Calculation No. GEN-PI-083, Revision 1, Locked Rotor Accident (LRA) Analysis Using AST, Attachment 5 Project stage: Other ML1023002982010-07-23023 July 2010 Calculation No. GEN-PI-082, Revision 1, Control Rod Ejection Accident - AST, Attachment 4 Project stage: Other ML1023002972010-07-23023 July 2010 Calculation No. GEN-PI-081, Revision 1, Eab, LPZ, and CR Doses Due to Steam Generator Tube Rupture Accident - AST, Attachment 3 Project stage: Other ML1023002962010-07-23023 July 2010 Calculation No. GEN-PI-078, Revision 1, Main Steam Line Break (MSLB) Accident Analysis Using AST, Attachment 2 Project stage: Other ML1022200872010-08-10010 August 2010 Forthcoming Meeting with Northern States Power Company - Minnesota (Nspm), to Discuss the Prairie Island Nuclear Generating Plant Steam Generator Margin-to-Overfill Analysis as It Relates to Pingp'S License Amendment Request to Adopt... Project stage: Meeting ML1023002952010-08-12012 August 2010 Response to Requests for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology Project stage: Response to RAI ML1023805712010-08-25025 August 2010 Meeting Presentation Alternative Source Term Steam Generator Tube Rupture Margin to Overfill Evaluation - Prairie Island Nuclear Generating Plant Project stage: Request ML1025903972010-09-23023 September 2010 Prairie Island, Summary of Meeting with Northern States Power Company to Discuss the Alternative Source Term License Amendment Request Project stage: Meeting ML1032205572010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI ML1032205552010-11-15015 November 2010 Draft RAI Concerning AST SGTR Mto Analysis Project stage: Draft RAI L-PI-10-112, Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102)2010-12-17017 December 2010 Prairie Lsland Nuclear Generating Plant Units 1 and 2, Response to Request for Additional Information License Amendment Request to Adopt the Alternative Source Term Methodology (TAC Nos. ME2609 and ME26102) Project stage: Response to RAI ML1110400212011-04-0404 April 2011 NRR E-mail Capture - Prairie Island - Revised Alternative Source Term LAR Draft RAI 4-4-2011 Project stage: Draft RAI ML1035404332011-05-12012 May 2011 Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term Project stage: RAI L-PI-11-060, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-06-22022 June 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1118226692011-06-29029 June 2011 PINGP - AST Methodology - ME2609 and ME2610 Project stage: Other L-PI-11-068, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-07-11011 July 2011 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1120819672011-07-20020 July 2011 E-mail Prairie Island - Request for Clarification of June 22, 2011 Request for Additional Information (RAI) Response Project stage: RAI L-PI-11-079, Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2011-08-0909 August 2011 Response to Requests for Additional Lnformation (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Other ML1125503562011-09-0101 September 2011 Ngp - Draft RAI Concerning SGTR Instrumentation for Alternative Source Term LAR Project stage: Draft RAI ML1125503572011-09-0101 September 2011 PINGP Draft RAI - AST Instrumentation Project stage: Draft RAI ML1131100842011-11-0202 November 2011 Alternative Source Term Draft Request for Additional Information Project stage: Draft RAI ML1131100942011-11-0202 November 2011 RAI Prairie PINGP, Units 1 and 2 Project stage: RAI L-PI-11-099, Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology2011-12-0808 December 2011 Response to Requests for Additional Information Regarding Regulatory Guide 1.97 Instrumentation Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI L-PI-12-010, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology2012-02-13013 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term Methodology Project stage: Response to RAI L-PI-12-013, Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology2012-02-24024 February 2012 Response to Requests for Additional Information Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI L-PI-12-082, Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology2012-09-13013 September 2012 Response to Requests for Additional Information (RAI) Associated with Adoption of the Alternative Source Term (AST) Methodology Project stage: Response to RAI ML1125212892013-01-22022 January 2013 Issuance of Amendments Adoption of Alternative Source Term Methodology Project stage: Approval L-PI-13-111, Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement2014-01-13013 January 2014 Notification of Alternative Source Term (AST) Implementation and Unit 2 Steam Generator Replacement Project stage: Other 2011-12-08
[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 ML22130A5792022-05-11011 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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] |
Text
REQUEST FOR ADDITIONAL INFORMATION FOR CHANGES RELATED TO ADOPTION OF ALTERNATIVE SOURCE TERM PRAIRIE ISLAND NUCLEAR GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50
-282 AND 50
-306 By letter dated October 27, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No.
ML093160583), supplemented by letters including those dated June 22, 2011, and August 9, 2011, (ADAMS Accession Nos. ML111740145 and ML112220098 , respectively), Northern States Power Company, a Minnesota corporation (t he licensee) requested Technical Specifications changes related to adoption of an Alternative Source Term Methodology for the Prairie Island Nuclear Generating Plant (PINGP), Units 1 and 2.
In response to the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAIs), the licensee, by letters dated June 22, 2011 and August 9, 2011, provided a list of instrumentation required to cope with a Steam Generator Tube Rupture (SGTR) event. The NRC staff has reviewed these responses and requests further clarification regarding the classification of these instrument loops as they relate to the criteria in Regulatory Guide (RG) 1.97, Revision 2.
The PINGP Updated Safety Analysis Report (USAR)
Tables 7.10
-1 and 7.10
-2 identifies the RG 1.97, Rev. 2 variables applicable to Units 1 and 2 respectively, which have been previously reviewed and approved by the NRC in various safety evaluations. Please revise the previously docketed list of instrumentation (i.e., instrument loops) credited for coping with a SGTR and indicate which instrument loops are contained within these USAR tables. Also, if any instrument loops credited for a SGTR are not contained within the USAR Tables 7.10-1 and 7.10
-2, please indicate the specific Plant Variable Type and Design and Qualification Category applicable to these instrument loops, as specified in RG 1.97, Rev.
- 2. This instrumentation is relied upon by the operators during accident situations, therefore the NRC staff expects these instruments to be incorporated into PINGP's RG 1.97 Post Accident Monitoring Instrumentation commitments, and documented in the USAR as appropriate.
Please include a marked
-up copy of the USAR documenting these new instrument loops as RG 1.97, Rev. 2 instrumentation.