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| {{#Wiki_filter:REQUESTS FOR ADDITIONAL INFORMATION Point Beach Nuclear Plant (PBNP), Units 1 and 2 License Amendment Request (LAR-261) dated April 7, 2009 Extended Power Uprate (TAC Nos. ME1044 and ME1045) | | {{#Wiki_filter:REQUESTS FOR ADDITIONAL INFORMATION Point Beach Nuclear Plant (PBNP), Units 1 and 2 License Amendment Request (LAR-261) dated April 7, 2009 Extended Power Uprate (TAC Nos. ME1044 and ME1045) |
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| The following requests for additional information are associated with the NRC staff review of LAR-261 associated with the extended power uprate for the PBNP, Units 1 and 2. | | The following requests for additional information are associated with the NRC staff review of LAR-261 associated with the extended power uprate for the PBNP, Units 1 and 2. |
| IHPB-1 Please verify that motor control centers (MCCs) 1B32, 2B32, 1B42 and 2B42 are being replaced, or have been replaced, with models that auto load following start of the emergency diesel generator such that resetting these MCCs is no longer considered a vital action as defined in NUREG 0737, item II.B.2. | | IHPB-1 Please verify that motor control centers (MCCs) 1B32, 2B32, 1B42 and 2B42 are being replaced, or have been replaced, with models that auto load following start of the emergency diesel generator such that resetting these MCCs is no longer considered a vital action as defined in NUREG 0737, item II.B.2. |
| | | IHPB-2 Please verify that resetting MCCs 1B42 and 2B42 was the only vital action needed at panel C59 so that replacing these MCCs, as described in the response to IHPB-1 above, eliminates the need to access panel C59 during the course of the accident (i.e., C59 would no longer be considered a vital area as defined in NUREG 0737, item II.B.2). |
| IHPB-2 Please verify that resetting MCCs 1B42 and 2B42 was the only vital action needed at panel C59 so that replacing these MCCs, as described in the response to IHPB-1 above, eliminates the need to access panel C59 during the course of the accident (i.e., C59 would no longer be considered a vital area as defined in NUREG 0737, item II.B.2). | |
| IHPB-3 Please provide the technical basis for originally concluding that accessing panel C59 to manually isolate the spray additive (NaOH) tank discharge valves was needed during the course of a Design Basis Accident, including any calculations and/or technical rationale for subsequently concluding that this action is not needed to mitigate the consequences of the accident. | | IHPB-3 Please provide the technical basis for originally concluding that accessing panel C59 to manually isolate the spray additive (NaOH) tank discharge valves was needed during the course of a Design Basis Accident, including any calculations and/or technical rationale for subsequently concluding that this action is not needed to mitigate the consequences of the accident. |
| IHPB-4 Please provide documentation of the NRC staff's acceptance for allowing TSC evacuation as a compensatory measure in lieu of meeting the habitability criteria in NUREG 0737, item II.B.2. | | IHPB-4 Please provide documentation of the NRC staffs acceptance for allowing TSC evacuation as a compensatory measure in lieu of meeting the habitability criteria in NUREG 0737, item II.B.2. |
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| IHPB-5 In response to the discussion related to the Waste Gas Decay Tank (WGDT) release/rupture event, please demonstrate how the licensee is maintaining dose acceptance criteria consistent with Branch Technical Position (BTP) 11-5 in NUREG 0800 by either, 1. Demonstrating that the consequences of this postulated release are within the dose limits of the current 10 CFR Part 20, or | | IHPB-5 In response to the discussion related to the Waste Gas Decay Tank (WGDT) release/rupture event, please demonstrate how the licensee is maintaining dose acceptance criteria consistent with Branch Technical Position (BTP) 11-5 in NUREG 0800 by either, |
| | : 1. Demonstrating that the consequences of this postulated release are within the dose limits of the current 10 CFR Part 20, or |
| : 2. Demonstrating that the consequences of this postulated release are within a small fraction (i.e., 10 percent) of the 10 CFR Part 100 limits for whole body dose if the gaseous radwaste system is designed to withstand the effects of a hydrogen explosion and earthquakes for gaseous wastes produced during normal operation and anticipated operational occurrences.}} | | : 2. Demonstrating that the consequences of this postulated release are within a small fraction (i.e., 10 percent) of the 10 CFR Part 100 limits for whole body dose if the gaseous radwaste system is designed to withstand the effects of a hydrogen explosion and earthquakes for gaseous wastes produced during normal operation and anticipated operational occurrences.}} |
Letter Sequence Draft RAI |
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TAC:ME1044, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) TAC:ME1045, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement
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MONTHYEARNRC-2008-0086, License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum2008-11-25025 November 2008 License Amendment Request 258 Incorporate Best Estimate Large Break Loss of Coolant Accident (LOCA) Analysis Using Astrum Project stage: Request NRC 2009-0030, License Amendment Request 261, Extended Power Uprate2009-04-0707 April 2009 License Amendment Request 261, Extended Power Uprate Project stage: Request NRC 2009-0068, License Amendment Request 261 Supplement 2 Extended Power Uprate2009-06-17017 June 2009 License Amendment Request 261 Supplement 2 Extended Power Uprate Project stage: Supplement NRC 2009-0066, License Amendment Request 261 Supplement 1 Extended Power Uprate2009-06-17017 June 2009 License Amendment Request 261 Supplement 1 Extended Power Uprate Project stage: Supplement NRC 2009-0094, License Amendment Request 261 Extended Power Uprate Expedited Review Request2009-09-11011 September 2009 License Amendment Request 261 Extended Power Uprate Expedited Review Request Project stage: Request NRC 2009-0098, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2009-09-25025 September 2009 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2009-0116, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2009-11-21021 November 2009 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2009-0115, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2009-11-21021 November 2009 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2009-0124, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information2009-11-30030 November 2009 License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information Project stage: Response to RAI NRC 2009-0120, License Amendment Request 261, Supplement 3 Extended Power Uprate2009-12-0808 December 2009 License Amendment Request 261, Supplement 3 Extended Power Uprate Project stage: Supplement NRC 2009-0122, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2009-12-16016 December 2009 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2009-0128, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2009-12-21021 December 2009 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0013, License Amendment Request 264 - Diesel Fuel Oil Storage Requirements2010-01-27027 January 2010 License Amendment Request 264 - Diesel Fuel Oil Storage Requirements Project stage: Request NRC 2010-0022, License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-02-25025 February 2010 License Amendment Request 261, Extended Power Uprate & Transmittal of Proposed Technical Specifications for Reactor Protection System & Engineered Safety Features Setpoints Not Associated with Extended Power Uprate Project stage: Request NRC 2010-0012, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation2010-03-0303 March 2010 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Lnformation Project stage: Request NRC 2010-0037, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2010-04-29029 April 2010 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0060, License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information2010-04-30030 April 2010 License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI ML1013401032010-05-13013 May 2010 License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0063, License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information2010-06-11011 June 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0039, License Amendment Request 261 Extended Power Uprate, Transmittal of Attachments 3 and 4 to NRC 2010-00392010-07-15015 July 2010 License Amendment Request 261 Extended Power Uprate, Transmittal of Attachments 3 and 4 to NRC 2010-0039 Project stage: Request ML1020401382010-07-21021 July 2010 License Amendment Request 261 Extended Power Uprate, Transmittal of Sample Reactor Protection System/Engineered Safety Features Actuation System Instrumentation Setpoint Calculations Project stage: Request NRC 2010-0105, License Amendment Request 261, Supplement 6 Extended Power Uprate2010-07-28028 July 2010 License Amendment Request 261, Supplement 6 Extended Power Uprate Project stage: Supplement ML1021702352010-08-0202 August 2010 Email Attachment: Point Beach Nuclear Plant, Units 1 and 2 - Draft RAIs Extended Power Uprate and Associated with Diesel FO Storage Requirements Project stage: Draft RAI NRC 2010-0112, License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-08-0202 August 2010 License Amendment Request 261, Extended Power Uprate Transmittal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate Project stage: Request ML1022406372010-08-11011 August 2010 Draft RAIs Extended Power Uprate (TAC Nos. ME1044 & ME1045 Project stage: Draft RAI NRC 2010-0133, License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change2010-08-12012 August 2010 License Amendment Request 261, Extended Power Uprate, Regulatory Commitment Change Project stage: Request NRC 2010-0116, License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information2010-08-23023 August 2010 License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0123, Response to Request for Additional Information on License Amendment Request 261 Extended Power Uprate2010-08-26026 August 2010 Response to Request for Additional Information on License Amendment Request 261 Extended Power Uprate Project stage: Response to RAI ML1025603032010-09-0303 September 2010 Summary of Teleconference to Clarify RAI Response Regarding Dynamic Analysis of Feedwater Valve Fast Closure Project stage: Meeting NRC 2010-0148, License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information2010-09-27027 September 2010 License Amendment Request 261 Extended Power Uprate Response to Request for Additional Information Project stage: Response to RAI NRC 2010-0146, License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate2010-09-28028 September 2010 License Amendment Request 261, Extended Power Uprate, Withdrawal of Proposed Technical Specifications for Reactor Protection System and Engineered Safety Features Setpoints Not Associated with Extended Power Uprate Project stage: Withdrawal ML1028002632010-10-0404 October 2010 AFW Modification LAR Requests for Additional Information - Scvb Project stage: RAI ML1028105912010-10-0808 October 2010 Request a Conference Call to Discuss Some Issues Found in Recent Submittals Re. Extended Power Uprate Project stage: Other NRC 2010-0161, License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Lnformation2010-10-15015 October 2010 License Amendment Request 261 Extended Power Uprate, Response to Request for Additional Lnformation Project stage: Request ML1031906532010-11-0808 November 2010 Draft Requests for Additional Information, (Srxb) EPU LAR Review Project stage: Draft RAI NRC 2010-0189, License Amendment Request 261, Extended Power Uprate Response to Request for Clarification2010-12-21021 December 2010 License Amendment Request 261, Extended Power Uprate Response to Request for Clarification Project stage: Request NRC 2010-0195, License Amendment Request 261 Extended Power Uprate Response to Request for Clarification2010-12-21021 December 2010 License Amendment Request 261 Extended Power Uprate Response to Request for Clarification Project stage: Request ML1101103532011-01-0707 January 2011 Comment (4) of Dennis Dums and Katie Nekola, on Point Beach, Units 1 & 2 Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed Extended Power Uprate Project stage: Draft Other NRC 2011-0003, License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information2011-01-13013 January 2011 License Amendment Request 261, Extended Power Uprate, Response to Request for Additional Information Project stage: Response to RAI NRC 2011-0013, License Amendment Request 261 Extended Power Uprate, Response to Request for Clarification2011-01-21021 January 2011 License Amendment Request 261 Extended Power Uprate, Response to Request for Clarification Project stage: Request ML1103200602011-03-25025 March 2011 (Pbnp), Units 1 and 2 - Issuance of License Amendments Revision of Reactor Protection System (RPS) and Engineered Safety Feature Actuation System (ESFAS) Instrumentation Setpoints Project stage: Approval 2010-04-29
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Category:Request for Additional Information (RAI)
MONTHYEARML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML23173A1522023-06-22022 June 2023 Request for Additional Information NextEra Fleet Emergency Plan Amendment Request ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 ML23136A2802023-05-0505 May 2023 SLRA Second Annual Update RAI Set 1 ML23122A0132023-05-0101 May 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding Risk-Informed Approach to Address GSI-191 ML23033A0292023-01-31031 January 2023 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI (Volume 2) - License Amendment Request Regarding TSTS-505 ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22354A1612022-12-20020 December 2022 NRR E-mail Capture - Point Beach 1 & 2 - Final RAI - License Amendment Request Regarding TSTS-505 ML22311A5582022-11-22022 November 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Cep ML22266A0872022-09-23023 September 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML22172A1192022-06-27027 June 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request to Adopt TSTF-505 Provide Risk Informed Extended Complete Times - RITSTF Initiative 4B ML22130A5712022-05-12012 May 2022 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21362A6812021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final ML21362A6822021-12-17017 December 2021 SLRA Safety RAIs Set 14 Final Email ML21362A6712021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final Email ML21362A6702021-12-15015 December 2021 SLRA Safety RAIs Set 13 Final ML21287A0852021-10-14014 October 2021 SLRA Safety RAI Set 11 Final Email ML21286A6032021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final Email ML21286A6042021-10-0505 October 2021 SLRA Safety RAIs Set 10 Final ML21287A0862021-09-29029 September 2021 SLRA Safety RAI Set 11 Final ML21273A0222021-09-29029 September 2021 SLRA Safety RAI Set 9 Final ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 ML21242A2282021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 ML21242A2292021-08-27027 August 2021 SLRA Draft Safety RAI Set 9 Email ML21242A2472021-08-26026 August 2021 SLRA Safety RAIs Set 8 Final ML21242A2232021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 Email ML21242A2222021-08-23023 August 2021 SLRA Draft Safety RAI Set 8 ML21242A2192021-08-20020 August 2021 SLRA Safety RAI Set 7 Final Email ML21242A2202021-08-20020 August 2021 SLRA Safety RAI Set 7 Final ML21242A2132021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft Email ML21242A2142021-08-13013 August 2021 SLRA Safety RAIs Set 7 Draft ML21242A2032021-08-12012 August 2021 Srla Safety RAIs Set 5 Final ML21242A2382021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final Email ML21242A2392021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A2042021-08-12012 August 2021 SLRA Safety RAIs Set 5 Final Email ML21242A0152021-08-12012 August 2021 SLRA Safety RAIs Set 6 Final ML21242A0122021-08-0909 August 2021 SLRA Draft Safety RAIs Set 6 ML21242A1992021-08-0505 August 2021 Srla Draft Safety RAIs Set 5 ML21242A2002021-08-0505 August 2021 SLRA Draft Safety RAIs Set 5 Email ML21285A1212021-08-0505 August 2021 SLRA Public Meeting Discussion Questions August 5 2021 ML21238A2332021-08-0404 August 2021 SLRA Safety RAI Set 4 Final ML21238A2322021-08-0404 August 2021 SLRA Safety RAI Set 4 Final Email ML21237A0062021-08-0202 August 2021 SLRA Draft Safety RAIs Set 4 ML21214A0842021-07-27027 July 2021 SLRA Safety RAIs Set 3 Final ML21208A1892021-07-27027 July 2021 SLRA Safety RAIs Set 2 Final ML21172A2382021-07-21021 July 2021 (Pbn) Subsequent License Renewal Application (SLRA) Draft Requests for Additional Information (Rais) Safety - Set 2 ML21214A0722021-07-20020 July 2021 Subsequent License Renewal Application Draft Safety RAIs Set 3 ML21161A1192021-06-10010 June 2021 RAIs Set 1 Final Aging Management of Irradiated Concrete and Steel Reactor Vessel Supports Final ML21134A0582021-05-14014 May 2021 Final Request for Additional Information and Requests for Confirmation of Information - Point Beach SLRA Environmental Review (EPID No. L-2020-SLE-0002) - Email 2024-01-30
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REQUESTS FOR ADDITIONAL INFORMATION Point Beach Nuclear Plant (PBNP), Units 1 and 2 License Amendment Request (LAR-261) dated April 7, 2009 Extended Power Uprate (TAC Nos. ME1044 and ME1045)
The following requests for additional information are associated with the NRC staff review of LAR-261 associated with the extended power uprate for the PBNP, Units 1 and 2.
IHPB-1 Please verify that motor control centers (MCCs) 1B32, 2B32, 1B42 and 2B42 are being replaced, or have been replaced, with models that auto load following start of the emergency diesel generator such that resetting these MCCs is no longer considered a vital action as defined in NUREG 0737, item II.B.2.
IHPB-2 Please verify that resetting MCCs 1B42 and 2B42 was the only vital action needed at panel C59 so that replacing these MCCs, as described in the response to IHPB-1 above, eliminates the need to access panel C59 during the course of the accident (i.e., C59 would no longer be considered a vital area as defined in NUREG 0737, item II.B.2).
IHPB-3 Please provide the technical basis for originally concluding that accessing panel C59 to manually isolate the spray additive (NaOH) tank discharge valves was needed during the course of a Design Basis Accident, including any calculations and/or technical rationale for subsequently concluding that this action is not needed to mitigate the consequences of the accident.
IHPB-4 Please provide documentation of the NRC staffs acceptance for allowing TSC evacuation as a compensatory measure in lieu of meeting the habitability criteria in NUREG 0737, item II.B.2.
IHPB-5 In response to the discussion related to the Waste Gas Decay Tank (WGDT) release/rupture event, please demonstrate how the licensee is maintaining dose acceptance criteria consistent with Branch Technical Position (BTP) 11-5 in NUREG 0800 by either,
- 1. Demonstrating that the consequences of this postulated release are within the dose limits of the current 10 CFR Part 20, or
- 2. Demonstrating that the consequences of this postulated release are within a small fraction (i.e., 10 percent) of the 10 CFR Part 100 limits for whole body dose if the gaseous radwaste system is designed to withstand the effects of a hydrogen explosion and earthquakes for gaseous wastes produced during normal operation and anticipated operational occurrences.