Letter Sequence RAI |
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CAC:MF9930, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) EPID:L-2017-LLS-0002, Clarify Application of Setpoint Methodology for LSSS Functions (Approved, Closed) |
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MONTHYEARML17188A2652016-12-31031 December 2016 Enclosure 10 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1123NP, Bounding Uncertainty Analysis for Thermal Power Determination at Hope Creek, Unit 1 Nuclear Generating Station Using the LEFM System, Revision 2 (Non-Proprietary Versi Project stage: Request ML17188A2672017-03-31031 March 2017 Enclosure 12 to LR-N17-0044 and LAR H17-03 - Cameron Document ER-1132NP, Meter Factor Calculation and Accuracy Assessment for Hope Creek Nuclear Generating Station, Revision 2, (Non-Proprietary Version) Project stage: Request ML17188A2602017-07-0707 July 2017 License Amendment Request for Measurement Uncertainty Recapture (Mur) Power Uprate Project stage: Request LR-N17-0044, Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings2017-07-0707 July 2017 Enclosure 15 to LR-N17-0044 and LAR H17-03 - LEFM Flow Meter Installation Location Drawings Project stage: Other ML17222A1182017-08-16016 August 2017 Acceptance of Requested Licensing Action License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Acceptance Review ML17235B1202017-08-28028 August 2017 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station Project stage: Withholding Request Acceptance LR-N17-0141, Transmittal of 2017 Annual 10 CFR 50.46 Report2017-09-27027 September 2017 Transmittal of 2017 Annual 10 CFR 50.46 Report Project stage: Request ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb Project stage: RAI LR-N17-0161, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-0101 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML17324A0522017-11-0909 November 2017 NRR E-mail Capture - Draft Request for Additional Information - Hope Creek Mur Chemical, Corrosion, and Steam Generator Project stage: Draft RAI ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls Project stage: RAI ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate Project stage: RAI LR-N17-0170, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-11-27027 November 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0176, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate2017-12-14014 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Uprate Project stage: Response to RAI LR-N17-0186, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0175, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0187, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0181, Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-19019 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI LR-N17-0189, Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2017-12-22022 December 2017 Transmittal of Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Response to RAI ML18011A0352018-01-11011 January 2018 Request for Withholding Information from Public Disclosure for Hope Creek Generating Station (CAC No. MF9930; EPID L-2017-LLA-0426) Project stage: Withholding Request Acceptance LR-N18-0009, Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate2018-01-22022 January 2018 Supplemental Information for the Response to Request for Additional Information Regarding License Amendment Request for Measurement Uncertainty Recapture Power Uprate Project stage: Supplement ML18096A5422018-04-24024 April 2018 Hope Creek Generating Station - Issuance of Amendment Measurement Uncertainty Recapture Power Uprate (CAC MF9930; EPID L-2017-LLS-0002) Project stage: Approval 2017-12-19
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Category:E-Mail
MONTHYEARML24002A7222023-12-29029 December 2023 NRR E-mail Capture - (External_Sender) Salem Generating Station - 2023 Annual Report - Inspection of the Circulating Water Intake Structure (Cwis) Trash Rack Bars ML23355A2732023-12-21021 December 2023 NRR E-mail Capture - (External_Sender) PSEG Response to Questions Associated with Supplement to Salem-Hope Creek Eab Reduction LAR ML23277A0482023-10-0404 October 2023 NRR E-mail Capture - 10/4/2023 Email: Acceptance Review - Hope Creek and Salem 1 and 2 - LAR to Modify Exclusion Area Boundary ML23277A0732023-09-29029 September 2023 NRR E-mail Capture - (External_Sender) 9/29/2023 Email from PSEG: Supplement to Proposed Amendment to PSEG Master Decommissioning Trust Amendment ML23129A7892023-05-0909 May 2023 NRR E-mail Capture - Acceptance Review - Hope Creek - Revise Trip and Standby Auto-Start Logic Associated with Safety Related HVAC Trains ML23122A1672023-05-0202 May 2023 NRR E-mail Capture - Acceptance Review - Hope Creek and Salem 1 and 2 - Revise TS to Delete TS Section 5.5 - Meteorological Tower Location ML23079A0032023-03-17017 March 2023 NRR E-mail Capture - Hope Creek, Salem 1 and 2 - Evacuation Time Estimate Review ML23065A0452023-02-23023 February 2023 NRR E-mail Capture - (External_Sender) Salem & Hope Creek Generating STATIONS-ANNUAL Incidental Take REPORT-STATION & REMP ML22194A0522022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review - Hope Creek, Salem 1 and 2 - Relocate Staff Qualification Requirements to Licensee Quality Assurance Topical Report ML22038A1552022-02-0404 February 2022 NRR E-mail Capture - (External_Sender) Salem & Hope Creek Generating STATIONS-ANNUAL Incidental Take REPORT-STATION & REMP ML22021A7012022-01-21021 January 2022 NRR E-mail Capture - Acceptance Review - Hope Creek -Relief Request HC-I4R-220 Regarding Partial Penetration Nozzle Repairs (L-2022-LLR-0003) ML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21334A1182021-11-30030 November 2021 NRR E-mail Capture - Acceptance Review - Hope Creek -Revise SRs for Electric Power Monitor Channels for RPS and Power Range Neutron Monitoring System ML21154A0102021-05-28028 May 2021 NRR E-mail Capture - Acceptance Review - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML20293A1832020-10-19019 October 2020 NRR E-mail Capture - Acceptance Review - Hope Creek - Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20289A7062020-10-15015 October 2020 NRR E-mail Capture - Acceptance Review - Hope Creek - Revise Low Pressure Safety Limit to Address GE Part-21 Safety Communication SC05-03 ML20246G5952020-09-0202 September 2020 Acceptance Review - Hope Creek - Adopt TSTF-427, Allowance for Non TS Barrier Degradation ML20191A0202020-07-0202 July 2020 NRR E-mail Capture - Acceptance Review - Hope Creek - Revise ECCS TS with Respect to HPCI System Inoperability ML20153A3782020-06-0101 June 2020 NRR E-mail Capture - Acceptance Review - Hope Creek - Revise TS Actions for Suppression Pool Cooling ML20006E2802020-01-0606 January 2020 NRR E-mail Capture - Acceptance Review - Hope Creek: LAR Regarding Proposed Adoption of 10 CFR 50.69, Risk- Informed Categorization and Treatment of SSCs for Nuclear Power Plants ML19280A0002019-10-0303 October 2019 NRR E-mail Capture - Hope Creek, Salem 1 and 2 - Final RAI Emergency Plan Staffing Requirements (L-2019-LLA-0145) ML19267A1622019-09-24024 September 2019 NRR E-mail Capture - Hope Creek - Acceptance Review: Alternative for Exam of ASME Section XI, Exam Category B-G-1, Item Number B6.40, Threads in Flange (L-2019-LLR-0090) ML19226A3932019-08-14014 August 2019 NRR E-mail Capture - Salem 1 & 2, Hope Creek - Acceptance Review: Delete License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19198A0992019-07-17017 July 2019 NRR E-mail Capture - Salem 1 & 2, Hope Creek - Acceptance Review: Changes to Emergency Plan Staffing ML19186A3842019-07-0505 July 2019 NRR E-mail Capture - Acceptance Review - Hope Creek, Revise TS to Adopt TSTF-563, Revise Instrumentation Testing Definition ML19123A2172019-05-0303 May 2019 NRR E-mail Capture - Re Acceptance Review - Hope Creek, Revise TS to Adopt TSTF-564, Safety Limit MCPR ML19081A1532019-03-22022 March 2019 NRR E-mail Capture - Acceptance Review: Hope Creek - Revise TS to Adopt TSTF-546 (L-2019-LLA-0032) ML19046A2382019-02-15015 February 2019 NRR E-mail Capture - Acceptance Review Result: Hope Creek-Relief Request to Use ASME Code Case OMN-17 (L-2019-LLR-0010) ML18323A0252018-11-16016 November 2018 NRR E-mail Capture - Acceptance Review: Hope Creek - Remote Shutdown System I & C Amendment (L-2018-LLA-0295) ML18288A2512018-10-15015 October 2018 NRR E-mail Capture - Acceptance Review Result: Hope Creek-Relief Request Associated with Third 10-Year ISI Interval (L-2018-LLR-0124) ML18271A0342018-09-13013 September 2018 Receipt of Stephen Comley, We the People, September 6, 11 and 12 2018 Voicemail and Email ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18206A7302018-07-27027 July 2018 (50-272, 50-311, 50-354), Transmittal Email 26.717 Updates ML18201A1112018-07-20020 July 2018 NRR E-mail Capture - Acceptance Review Results: Hope Creek, Salem 1 & 2 Revise TS to Adopt TSTF-529 (L-2018-LLA-0185) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18128A3862018-05-0808 May 2018 NRR E-mail Capture - Acceptance Review Results: Hope Creek Revise Inverter AOT TS Actions (L-2018-LLA-0101) ML18122A2392018-05-0202 May 2018 NRR E-mail Capture - Acceptance Review Results: Revise Emergency Diesel Generator Technical Specifications Action to Remove Salem Unit 3 Gas Turbine Generator (L-2018-LLA-0079) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17340B2682017-12-0606 December 2017 NRR E-mail Capture - Notification to State of New Jersey of Impending License Amendment Issuance for Hope Creek (MF9501; EPID L-2017-LLA-0183) ML17338A2742017-12-0404 December 2017 NRR E-mail Capture - State of New Jersey: Notification of Impending Amendment Issuance for Hope Creek - Relocate Pressure-Temperature Limits Curves to the Pressure-Temperature Limits Report ML17338A2752017-12-0404 December 2017 NRR E-mail Capture - Acceptance Review - Hope Creek License Amendment Request to Revise the Safety Limit Minimum Critical Power Ratio ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17324A0522017-11-0909 November 2017 NRR E-mail Capture - Draft Request for Additional Information - Hope Creek Mur Chemical, Corrosion, and Steam Generator 2023-09-29
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML22006A3212022-01-0606 January 2022 NRR E-mail Capture - Final RAI - Hope Creek - Revise TS Limits for Ultimate Heat Sink ML21300A0222021-10-27027 October 2021 Notification of Conduct of a Fire Protection Team Inspection ML21041A3972021-02-18018 February 2021 Request for Additional Information Revise Low Pressure Safety Limit to Address General Electric Part-21 Safety Communications (Non-Proprietary) ML20295A4922020-10-21021 October 2020 NRR E-mail Capture - Hope Creek - Final RAI Revise ECCS TS with Respect to HPCI System Inoperability (L-2020-LLA-0131) ML18263A1442018-09-12012 September 2018 NRR E-mail Capture - Final RAI from Apla: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18250A3142018-09-0606 September 2018 NRR E-mail Capture - Final RAI: Revise Technical Specifications to Increase Inverter AOT Extension (L-2018-LLA-0101) ML18150A6912018-05-30030 May 2018 NRR E-mail Capture - Hope Creek - Final RAI Revise TS to Adopt TSTF-542 ML18120A2482018-04-27027 April 2018 Information Request for the Cyber-Security Inspection, Notification to Perform Inspection 05000354/2018403 ML18094B0832018-04-0505 April 2018 Enclosurequest for Additional Information (Letter to P. Duke RAI Regarding Entergy Operations, Inc.'S Decommissioning Funding Plan Update for Salem and Hope Creek, and Peach Bottom ISFSIs Docket Nos. 72-48 and 72-29) ML17349A0812017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Reactor Systems Branch (Srxb) - Hope Creek Mur ML17348A9972017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17348A6242017-12-14014 December 2017 NRR E-mail Capture - Final Request for Additional Information for Human Factors Associated with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17331A0072017-11-21021 November 2017 E-mail Regarding Final Eicb Request for Additional Information - Hope Creek Power Uprate ML17348A6282017-11-21021 November 2017 NRR E-mail Capture - Draft Request for Additional Information for Steam Dryer Analysis with the Hope Creek Measurement Uncertainty Recapture Uprate Request (L-2017-LLS-002) ML17324A2602017-11-17017 November 2017 NRR E-mail Capture - Final Request for Additional Information - Hope Creek Mur Electrical Instrumentation and Controls ML17320A2152017-11-16016 November 2017 NRR E-mail Capture - Hope Creek Measurement Uncertainty Recapture Application Review - Electrical Engineering (Eeob) Request for Additional Information (L-2017-LLS-0002) ML17290B0132017-10-17017 October 2017 NRR E-mail Capture - Hope Creek Mur Request for Additional Information for Apla and Snpb ML17222A1652017-08-10010 August 2017 NRR E-mail Capture - Hope Creek: Final Request for Information, Pressure-Temperature Limit Report Request (MF9502) ML17181A1352017-06-29029 June 2017 NRR E-mail Capture - Request for Additional Information Related to Hope Creek and Salem Emergency Action Level Scheme Change License Amendment Request (MF9268/69/70) ML17164A4062017-06-13013 June 2017 NRR E-mail Capture - Hope Creek - Final Request for Additional Information Concerning ILRT (MF8462) ML17027A3282017-02-27027 February 2017 Request for Additional Information Regarding License Amendment Request to Permanently Extend Type a and Type C Leak Rate Test Frequencies ML16321A4642016-11-21021 November 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request to Remove Certain Training Requirements ML16277A5142016-11-0303 November 2016 Request for Additional Information Regarding License Amendment Request to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16271A2052016-11-0202 November 2016 Request for Additional Information Regarding Request to Delete Technical Specifications Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML16231A4272016-08-24024 August 2016 Request for Additional Information Regarding Relief Request VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16217A4302016-08-17017 August 2016 Request for Additional Information Regarding Digital Power Range Neutron Monitoring System Upgrade ML16007A1742016-05-31031 May 2016 Request for Additional Information Regarding Review of Post-EPU Steam Dryer Stress Calculation Acoustic Circuit Model Software Error ML16089A0792016-05-0505 May 2016 Request for Additional Information Regarding Relief Requests GR-01, PR-01, PR-02, VR-01, and VR-02, Associated with the Fourth 10-Year Inservice Test Interval ML16124A5802016-05-0303 May 2016 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Redacted - Request for Additional Information Review of Security Plan Revision 17 Changes ML15055A3772015-03-10010 March 2015 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information Request to Update Appendix B to Renewed Facility Operating License DPR-70, DPR-75 and NPF-57 ML14197A6192014-07-24024 July 2014 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding Cyber Security Plan Milestone 8 Implementation Schedule (Tac Nos. MF3384, MF3385 and MF3386) ML14168A2352014-07-0202 July 2014 Request for Additional Information Regarding Flooding Hazard Reevaluation ML13309B5922013-11-22022 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13304B4182013-11-0101 November 2013 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Seismic Walkdowns ML13168A2762013-08-12012 August 2013 Peach Bottom, Units 2 and 3, Request for Additional Information Decommissioning Funding Status Report (TAC No. MF2202; MF2227; MF2228) ML13193A2912013-07-22022 July 2013 Request for Additional Information Regarding Overall Integrated Plan for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) TAC MF1031 ML13204A2532013-07-19019 July 2013 Draft RAIs - Decommissioning Funding Status Report for Hope Creek and Peach Bottom ML13190A2212013-07-0202 July 2013 RAIs for Hope Creek Regarding Response to Order EA-12-051 ML13154A4952013-06-0404 June 2013 Rai'S Following Ifib Analysis of Pseg'S 2013 Decommissioning Funding Status Report for Hope Creek Generating Station ML12334A3102012-12-0505 December 2012 Request for Additional Information Request to Correct Technical Specification and Facility Operating License Editorial Items ML12310A1672012-11-0101 November 2012 Draft RAI to License Amendment Request Regarding Average Power Range Monitoring Operability Requirements in Operational Condition 5 ML1227901012012-10-0505 October 2012 Clarifying Information for Question No. 4 (with Attachment) ML12212A1032012-08-0808 August 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Request for Additional Information ML12216A1792012-08-0303 August 2012 Draft RAI Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML12213A6162012-07-30030 July 2012 Draft Request for Additional Information Related to Request for Exemption from Certain Requirements of the Fitness for Duty Rule ML1209002372012-03-29029 March 2012 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, Draft Request for Additional Information ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic 2022-01-06
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1NRR-PMDAPEm Resource From:Regner, Lisa Sent:Tuesday, October 17, 2017 11:39 AM To:Thomas, Brian J.
Cc:Paul.Duke@pseg.com
Subject:
Hope Creek MUR - Final Request for Additi onal Information (CAC: MF9930 EPID:
L-2017-LLS-0002)
Attachments:
Final MUR RAI APLB SNPB.docxFinal Request for Additional Information On September 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) staff sent PSEG (the licensee) the draft Request for Additional Information (RAI) provided in the attached document. These RAI questions relates to a license amendment request (LAR) that proposes to increase the rated thermal power level from 3840 megawatts thermal to 3902 megawatts thermal, and make technical specification changes as necessary to support operation at the uprated power level. This is referred to as a measurement uncertainty recapture (MUR) uprate.
PSEG subsequently informed the NRC staff that questions APLA-1 and APLA-2 in the attached RAI were understood and an additional clarification was not necessary. Mr. Brian Thomas agreed to provide a response to this final RAI within 30 days from the date of this correspondence.
PSEG requested a clarification call for SNPB-1 and SNPB-2, which was held on October 10, 2017. At the conclusion of the call, the licensee stated it understood the questions. Mr. Brian Thomas agreed to provide a response to these final questions no later than December 8, 2017. Please note that if PSEG does not respond by this date, the requested completion date for the MUR decision may not be met by the NRC.
The NRC staff also informed the licensee that a publicly av ailable version of this final RAI would be placed in the NRC's Agencywide Documents Access and Management System (ADAMS). Question No. SNPB-2 contains proprietary information that has been withheld.
By letter dated July 7, 2017, (ADAMS package Accession No. ML17188A259), the licensee requested an amendment to the Operating License for Hope Creek Generating Station. The proposed amendment requests a MUR uprate for Hope Creek. The NRC staff requires additional information to complete its review of this request as detailed in the attached document.
Lisa M. Regner Senior Project Manager Branch 4, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
Hearing Identifier: NRR_PMDA Email Number: 3775 Mail Envelope Properties (5fa6eae6fa9e4f8090b04b55f334fb4e)
Subject:
Hope Creek MUR - Final Request for Additional Information (CAC: MF9930 EPID: L-2017-LLS-0002) Sent Date: 10/17/2017 11:39:11 AM Received Date: 10/17/2017 11:39:12 AM From: Regner, Lisa Created By: Lisa.Regner@nrc.gov Recipients: "Paul.Duke@pseg.com" <Paul.Duke@pseg.com> Tracking Status: None "Thomas, Brian J." <Brian.Thomas@pseg.com> Tracking Status: None
Post Office: HQPWMSMRS01.nrc.gov Files Size Date & Time MESSAGE 2161 10/17/2017 11:39:12 AM Final MUR RAI APLB SNPB.docx 33612 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: Recipients Received:
1 REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST FOR MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE Hope Creek Generating Station Docket No. 50-354 CAC No. MF9930
APLB-1 The staff notes that Hope Creek Generating Station License Amendment Request, Enclosure 6, GE-Hitachi Nuclear Energy, Document NEDC-33871P, Revision 0, "Safety Analysis Report for Hope Creek Generating Station, Thermal Power Optimization," April 2017, Section 6.7, "Fire Protection," states that "-There is no change in the physical plant configuration and the potential for minor changes to combustible loading as result of TPO
[thermal power optimization] Uprate are addressed by controlled design changes procedures-" Per Section 9.5.1.2, "Administrative Controls," of NUREG-1048, the licensee should summarize any changes to the combustible loading, however minor, and discuss the impact of these changes on the plant's compliance with the fire protection program licensing basis, Title 10 of
the Code of Federal Regulations Part 50 (10 CFR 50.48), or applicable portions of 10 CFR 50, Appendix R. NUREG-1048, "Safety Evaluation Report related to the operation of Hope Creek Generating Station," October 1984 and its Supplements 1 through 6 describe the approved fire protection program at Hope Creek Generating Station and explain how it complies with the requirements of 10 CFR 50.48, "Fire protection," and the guidelines of Branch Technical Position (BTP) Chemical Engineering Branch (CMEB) 9.5-1 and Appendix A to BTP Auxiliary and Power Conversion Systems Branch (APCSB) 9.5-1. NUREG-1048 and its Supplement 1 through 6 are cited in the Hope Creek operating license condition 2.C.7.
APLB-2 Some nuclear power plants credit aspects of thei r fire protection system for other than fire protection activities for the increased power operating conditions and total decay heat. For example, utilizing the fire water pumps and water supply as backup cooling or inventory for non-primary reactor systems.
If the Hope Creek Generating Station credits its fire protection system in this way, the licensee should identify the specific situations and discuss to what extent, if any, the MUR power uprate affects these "non-fire-protection" aspects of the plant fire protection system. In your response discuss how any non-fire suppression use of fire protection water will impact the ability to meet the fire protection system design demands per NUREG-1048, Section 9.5.1.5, "Fire Detection and Suppression." If the Hope Creek Generating Station does not take such credit, the licensee needs to verify this as its response to this question.
2 The PROPRIETARY INFORMATION in Question SNPB-2 has been removed
. The Proprietary information was enclosed within double-brackets. This sentence is an example of the proprietary portion marking.
SNPB-1 Title 10 of the U.S. Code of Federal Regulations (10 CFR), part 50, appendix A, "General Design Criteria for Nuclear Power Plants," criterion 10 (i.e., GDC 10) states, "The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences."
In order to provide assurance that 99.9 percent of the fuel rods in the core do not enter transition boiling in the event of an anticipated operational occurrence, the safety limit (SL) minimum critical power ratio (MCPR) is established as a specified acceptable fuel design limit. The SLMCPR is a limit placed on the critical power ratio (CPR). If a fuel rod has a CPR of 1.0, it would be predicted to enter transition boiling. The SLMCPR provides a margin to account for uncertainties associated with the correlation used to estimate the critical power ratio (CPR),
small variations in the pin- and bundle-radial power distribution in the core, and instrument monitoring.
The uncertainties associated with the methods used to estimate the effect of small variations in the radial power distribution in the core are sensitive to the void conditions in the fuel bundles. This sensitivity is evaluated for plants operating in high-bundle-power, high-exit-void-fraction conditions in General Electric - Hitachi (GEH) Licensing Topical Report (LTR) NEDC-33173P-A, Revision 4, "Applicability of GE Methods to Expanded Operating Domains" (ADAMS Package No. ML123130130). This report, which is approved for use by the NRC staff, is also known as the Interim Methods LTR (IMLTR).
Figures 2-1, 2-3, and 2-4 of the Thermal Power Optimization (TPO) Safety Analysis Report (TSAR) indicate that challenging void conditions may exist at HCNGS upon implementation of
the measurement uncertainty recapture upr ate (MUR) (ADAMS Accession Nos. ML17188A263 (publicly available) and ML17188A270 (proprietary)). First, HCNGS is predicted to have bundle power levels that are higher than the other plants shown in the experiential database. Second, the bundle exit void fractions are similarly high, approaching 90 percent.
- Justify the application of the nuclear and thermal-hydraulic design uncertainties in the GESTAR-II analytic process without the IMLTR penalties that are required of plants that operate in the high bundle power, high maximum channel exit void fraction conditions that appear to be associated with the HCNGS MUR. In particular, the plots shown indicate that HCNGS will be operating with bundle exit void conditions that would require the application of the penalty suggested by Limitation 5 as contained in the IMLTR. A comparison of the attributes, displayed in the figures listed above, to other plants operating with qualitatively similar characteristics (e.g., domestically licensed, Maximum Extended Load Line Limit Analysis, Extended Power Uprate, Thermal Power Optimization) would suffice for this purpose.
- Provide evidence that, in light of the significantly different operating conditions between extended power uprate implementation and MUR, the dispositions contained in the TPO LTR (TLTR, i.e., NEDC-32938P-A, "Generic Guidelines and Evaluations for General Electric Boiling Water Reactor Thermal Power Optimization" (ADAMS Package No. ML17076A207)) relative to fuel design, operation, and thermal margin assessment, are applicable. Analytic results of two or several potentially limiting anticipated operational occurrences in the MUR operating conditions may provide such evidence.
3 SNPB-2 GDC 10 requires that the reactor core be designed with appropriate margin to assure that specified acceptable fuel design limits (SAFDLs) are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. GDC 12 requires that the reactor core be designed to assure that power oscillations, which can result in conditions exceeding SAFDLs, are not possible or can be reliably and readily detected and suppressed. 10 CFR 50.36 defines limiting system safety settings (LSSS) and requires their inclusion in facility Technical Specifications.
At HCNGS, the LSSS that protect the core from conditions that would challenge conformance to GDC 10 and 12 are required to be operable above a threshold value for monitoring margin to the thermal limits that assure compliance with these GDC.
The thermal limits monitoring threshold is based on
[[
.]] HCNGS provided an evaluation, in section 2.2 of the TSAR, demonstrating that - . Then, in Section 2.4.2 of the TSAR, the license states that HCNGS will maintain its thermal limits monitoring threshold at 24 percent for operational convenience, and based on a judgment of adequacy. This is inconsistent with the basis - for the TLTR.
In light of not [[ ]], provide a detailed analysis or evaluation supporting a thermal limits monitoring threshold that exceeds the [[
- ]] value.