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Category:E-Mail
MONTHYEARML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23177A1992023-06-26026 June 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-23-0005 - LAR to Align Certain TSs with ISTS (L-2023-LLA-0078) ML23172A0132023-06-20020 June 2023 Duke Fleet - Correction to June 2, 2023, Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23153A1892023-06-0202 June 2023 Duke Fleet - Request for Additional Information Proposed License Amendment Request to Revise Restrictive Surveillance Requirement Frequencies ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23124A1212023-05-0404 May 2023 Acceptance of Requested Licensing Action Duke Fleet Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23073A2282023-03-13013 March 2023 Duke Fleet- Adoption of TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements - Acceptance Review ML23065A0942023-03-0606 March 2023 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-22-0081 - LAR to Address Administrative Changes to the Operating License and Technical Specifications (L-2023-LLA-0020) ML23058A0562023-02-27027 February 2023 Acceptance of Amendment to Revise Surveillance Frequencies for RCS Pressure Isolation Valve Operational Leakage Testing and Reactor Trip System Instrumentation ML23048A1512023-02-16016 February 2023 Acceptance Review - Proposed Alternative for Steam Generator Welds (L-2023-LLR-0003) ML22237A1632022-08-25025 August 2022 004 Radiation Safety Baseline Inspection Information Request ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML22108A0182022-04-15015 April 2022 NRR E-mail Capture - Accepted for Review - Duke Energy Relief Request for Harris Nuclear Plant Inservice Testing Program Plan - Fourth Ten-Year Interval to Extend Type C Test to 75 Months ML22083A0702022-03-24024 March 2022 NRR E-mail Capture - Catawba Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, and McGuire Nuclear Station, Units 1 and 2 - Acceptance Review for TSTF-569 LAR ML22083A0282022-03-23023 March 2022 Email Snsb Safety Evaluation for Harris LAR to Revise Reactor Protection System TS ML22038A1572022-02-0707 February 2022 NRR E-mail Capture - Duke Energy Fleet - Acceptance of License Amendment Request Regarding Adoption of TSTF-541, Revision 2 ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML21361A0122021-12-23023 December 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Relocate Emergency Operations Facility ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21321A3782021-11-16016 November 2021 NRR E-mail Capture - Energy Harbor Fleet, Beaver Valley Units 1 and 2 and DAVIS-BESSEL Unit 1 - Acceptance of License Amendment Request Adoption of TSTF-554 EPID-L-2021-LLA-0193 ML21288A0802021-10-15015 October 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0213 - Remove Limitations to Perform Certain SRs During Shutdown (L-2021-LLA-0167) ML21295A0372021-10-0505 October 2021 NRR E-mail Capture - Accepted for Review - Duke Energy Fleet License Amendment Request to Adopt TSTF-577 Revised Frequencies for Steam Generator Tube Inspections ML21252A0112021-08-30030 August 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1- RA-21-0191 - Revised TS Related to Reactor Trip System Instrumentation (L-2021-LLA-0149) ML21189A0282021-07-0101 July 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0112 - Revise TS to Reflect Development of TRM (L-2021-LLA-0108) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21106A0112021-04-15015 April 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-21-0052 - Revise Containment Spray Nozzle Surveillance Frequency (L-2021-LLA-0058) ML21084A2492021-03-24024 March 2021 Notification of Inspection and Request for Information ML21084A2512021-03-22022 March 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-20-0252 - LAR to Remove Extraneous Content and Requirements from the OL and TS (L-2021-LLA-0027) ML21039A6382021-02-0808 February 2021 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1-RA-20-0311 - 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach (L-2021-LLA-0003) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21033A8452021-02-0202 February 2021 NRR E-mail Capture - State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revision Minimum RCS Flow Rate and Update COLR References ML21033B1062021-02-0202 February 2021 NRR E-mail Capture - (External_Sender) (External) State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revision Minimum RCS Flow Rate and Update COLR References ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML21025A2922021-01-25025 January 2021 NRR E-mail Capture - (External_Sender) State Notification of Amendment to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System ML21007A3722021-01-0707 January 2021 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-19-0352 - Proposed Alternative for Reactor Vessel Close Stud Examinations (L-2020-LLR-0156) ML21006A4302021-01-0606 January 2021 Acceptance Review - Duke Fleet RA-20-0207 Request to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML21006A4042021-01-0606 January 2021 NRR E-mail Capture - State Notification of Amendment to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System ML20345A3052020-12-10010 December 2020 NRR E-mail Capture - (External_Sender) (External) State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3.3.3.6 and TS 3.9.2 ML20344A4192020-12-0909 December 2020 NRR E-mail Capture - State Notification of Amendments to Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS 3.3.3.6 and TS 3.9.2 ML20328A0802020-11-23023 November 2020 NRR E-mail Capture - Acceptance Review - Shearon Harris Nuclear Power Plant, Unit 1 - RA-20-0312-Relief Request, Service Water Pinhole Leak in a Socket Weld, Inservice Inspection (L-2020-LLR-0143) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3102020-10-13013 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0191 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-5120, IWA-5213, IWA-5241, IWA-5242, and IWA-5250 (L-2020-LLR-0126) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20297A3082020-10-0707 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0263 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI for Repair/Replacement (L-2020-LLR-0124) ML20297A3092020-10-0606 October 2020 NRR E-mail Capture - Acceptance Review - Duke Fleet - RA-20-0262 - Request to Use a Provision of a Later Edition of the ASME B&PV Code, Section XI - IWA-4540(b) (L-2020-LLR-0125) ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation 2024-01-25
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21258A3652021-09-15015 September 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2021011) and Request for Information (RFI) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation ML19331A4002019-11-27027 November 2019 Request for Additional Information Regarding Licensing Action to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19204A2682019-07-23023 July 2019 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for the Escw System TS AOT Extension and Removal of an Expired Note in TS Risk Informed LAR (L-2019-LLA-0025) ML19136A2712019-05-28028 May 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19060A0912019-03-18018 March 2019 Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18332A4392018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for EAL Scheme Changes ML18337A1272018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding the Rts/Esfas Trip Setpoints Modification LAR ML18264A0282018-10-0909 October 2018 RAI Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization Aad Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18145A1812018-06-18018 June 2018 Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18058B2242018-02-26026 February 2018 Emailed Radiation Safety RFI ML18005A5482018-01-0808 January 2018 Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996; EPID L-2017-LLA-0303) ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17289A3062017-10-23023 October 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements (CAC No. MF9828; EPID L-2017-LLA-0244) ML17250B0172017-09-18018 September 2017 Shearon Harris, Unit 1 - Request for Additional Information Re: License Amendment Request Proposing New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods that Exceed the LHGR Limit Detailed in RG 1.183, Table 3 (CAC No. MF9740) ML17241A0182017-08-30030 August 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17123A1332017-05-0909 May 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Re: License Amendment Request to Relocate Specific TS Parameters to the COLR, Remove Reference to a Plant Procedure as it Pertains to the COLR in TSs, etc. (CAC No. MF8894) ML17109A2912017-04-19019 April 2017 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Final Request for Additional Information Concerning LAR to Adopt TSTF-339, TSTF-5 and Other Administrative Changes ML16363A0112016-12-27027 December 2016 Notification of Shearon Harris Nuclear Power Plant Design Basis Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2017007 ML16335A0462016-12-0606 December 2016 Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements (CAC No. MF7775) ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16288A0042016-10-26026 October 2016 Shearon Harris Nuclear Plant, Unit 1 - Request For Additional Information Regarding License Amendment Request To Relocate The Explosive Gas Mixture And Liquid Holdup Tanks Technical Specifications Requirements (CAC No. MF8067) ML16223A4172016-08-0808 August 2016 Notification of Inspection and Request for Information ML16209A2642016-08-0202 August 2016 Shearon Harris Nuclear Plant, Unit 1 - Second Request For Additional Information Regarding License Amendment Request For A Temporary Change To Technical Specifications For The 'A' Emergency Service Water Pump Replacement (CAC No. MF7017) ML16028A1972016-02-0808 February 2016 Request for Additional Information Regarding License Amendment Request for a Temporary Change to Technical Specifications for the 'A' Emergency Service Water Pump Replacement ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) ML15320A3862015-11-19019 November 2015 RAI LAR to Adopt TSTF-523 ML15314A3592015-11-10010 November 2015 Duke Energy Draft RAIs Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) ML15314A3562015-11-10010 November 2015 E-mail from J. Whited to A. Zaremba Duke Energy Draft RAIs License Amendment Request to Adopt TSTF-523 (CAC Nos. MF6413-MF6422) 2024-01-25
[Table view] |
Text
NRR-DMPSPEm Resource From: Barillas, Martha Sent: Wednesday, November 28, 2018 3:35 PM To: Robertson, Jeffrey N; 'Arthur.Zaremba@duke-energy.com'; McDaniel, Sarah A; Earp Jr.,
Dennis
Subject:
Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information regarding the RTS/ESFAS Trip Setpoints Modification LAR Attachments: Harris RTS and ESFAS Setpoints LAR RAI L-2018-LLA-0203.pdf Mr. Robertson, By letter dated July 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A546), as supplemented by letter dated September 24, 2018 (ADAMS Accession No. ML18267A102), Duke Energy Progress, LLC (the licensee) submitted a license amendment request for the Shearon Harris Nuclear Power Plant (HNP), Unit 1. The proposed amendment would modify Technical Specification (TS) Table 2.2-1, Reactor Trip System Instrumentation Trip Setpoints, and TS Table 3.3-4, Engineered Safety Features Actuation System Instrumentation Trip Setpoints, to optimize safety analysis margin in the Final Safety Analysis Report Chapter 15 transient analyses. The U.S. Nuclear Regulatory Commission (NRC) staff has determined that additional information is needed to complete its review. The attached Request for Additional Information (RAI) was e-mailed to the licensee in draft form on November 19, 2018. A clarification call was held on November 28, 2018. The licensee agreed to provide responses to the final RAI by December 28, 2018. A publicly-available version of this final RAI and email will be placed in the NRCs ADAMS.
Please note that if a response to this email is not received by this date, or an acceptable alternate date with a justification for an extension is not provided in writing, we may deny the application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Part 2, Section 108, "Denial of application for failure to supply information."
If you have any questions, please contact me at 301-415-2760 or via email at Martha.Barillas@nrc.gov.
Sincerely, Martha Barillas Project Manager NRR/DORL/Licensing Branch II-2 US Nuclear Regulatory Commission 301-415-2760 1
Hearing Identifier: NRR_DMPS Email Number: 687 Mail Envelope Properties (Martha.Barillas@nrc.gov20181128153400)
Subject:
Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information regarding the RTS/ESFAS Trip Setpoints Modification LAR Sent Date: 11/28/2018 3:34:38 PM Received Date: 11/28/2018 3:34:00 PM From: Barillas, Martha Created By: Martha.Barillas@nrc.gov Recipients:
"Robertson, Jeffrey N" <Jeffrey.Robertson@duke-energy.com>
Tracking Status: None
"'Arthur.Zaremba@duke-energy.com'" <Arthur.Zaremba@duke-energy.com>
Tracking Status: None "McDaniel, Sarah A" <Sarah.McDaniel@duke-energy.com>
Tracking Status: None "Earp Jr., Dennis" <Dennis.Earp@duke-energy.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 1843 11/28/2018 3:34:00 PM Harris RTS and ESFAS Setpoints LAR RAI L-2018-LLA-0203.pdf 113846 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DUKE ENERGY PROGRESS, LLC SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO MODIFY REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS EPID: L-2018-LLA-0203 By letter dated July 30, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A546), as supplemented by letter dated September 24, 2018 (ADAMS Accession No. ML18267A102), Duke Energy Progress, LLC (the licensee) submitted a license amendment request (LAR) for the Shearon Harris Nuclear Power Plant (HNP), Unit 1.
The proposed amendment would modify Technical Specification (TS) Table 2.2-1, Reactor Trip System Instrumentation Trip Setpoints, and TS Table 3.3-4, Engineered Safety Features Actuation System Instrumentation Trip Setpoints, to optimize safety analysis margin in the Final Safety Analysis Report Chapter 15 transient analyses. The U.S. Nuclear Regulatory Commission (NRC) staff has determined the following request for additional information (RAI) is needed in order to complete its review.
Regulatory Basis 10 CFR 50.36(c)(1) requires that the TS include safety limits and limiting safety system settings.
Safety limits are limits upon important process variables that are found to be necessary to reasonably protect the integrity of certain of the physical barriers that guard against the uncontrolled release of radioactivity. Limiting safety system settings are settings for automatic protective devices related to those variables having significant safety functions.
The regulation at 10 CFR 50.36(c)(2) requires that limiting conditions for operation (LCO), which are the lowest functional capability or performance levels of equipment required for safe operation of the facility, be established.
10 CFR Part 50, Appendix A, General Design Criterion (GDC) 10, Reactor design, requires that the reactor core and associated coolant, control, and protection systems 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.
GDC 15, Reactor coolant system design, states that the reactor coolant system and associated auxiliary, control, and protection systems be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded Page 1 of 4
during any condition of normal operation, including the effects of anticipated operational occurrences.
10 CFR 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactor, as it relates to the acceptable loss-of-coolant accident analysis.
NUREG-0800, Chapter 15 of Standard Review Plan, for the review guidance of transients and accident analyses for light-water reactor designs.
SRXB RAI 1 High Neutron Flux Trip - NI System Component Uncertainty In Section 3.2 of the LAR dated July 30, 2018, the licensee discussed the use of a nuclear instrumentation (NI) system component uncertainty (SCU) in determining the high neutron flux trip setpoint. It indicated that a 5% NI SCU was used to determine the current high neutron flux trip setpoint in TS Table 2.2-1 as functional unit 2. This NI uncertainty encompassed the reactor vessel downcomer water density and radial power redistribution effects. For the safety analysis, the NRC-approved Duke Energy methodologies explicitly modelled effects such as downcomer attenuation, rod shadow, and power tilt. The licensee claimed that when the Duke Energy methodologies are implemented at HNP, the 5% SCU would be overly conservative. Based on its evaluation, the licensee proposes a NI SCU of 3.2% span reduced from the current 5% span SCU.
Please provide a discussion to explain how the proposed NI SCU of 3.2% span is derived and justify the acceptance of the derivation of the proposed 3.2% uncertainty used to determine the TA for the high neutron flux trip setpoint.
SRXB RAI 2 Dropped Rod Analysis without Crediting the High Power Range Negative Neutron Flux Rate Trip In Section 3.5 of the LAR dated July 30, 2018, the licensee indicates that the high power range negative neutron flux rate trip is currently credited in the dropped rod analysis of record (AOR) in Final Safety Analysis Report (FSAR) Section 15.4.3.1. After Cycle 22, when the NRC-approved Duke Energy methodologies are implemented at HNP, this negative flux rate trip would no longer be credited in the analysis for any Chapter 15 events, and the trip currently designed as functional unit 4 in TS Table 2.2-1, would be deleted from the TS table.
Please provide a discussion of the analysis of the dropped rod event performed with the Duke Energy methodologies and demonstrate that for cases without crediting the high power range negative neutron flux rate trip, the results of the dropped rod analysis meet the applicable Chapter 15 accident analysis acceptance criteria.
Page 2 of 4
SRXB RAI 3 Effects of the TS Changes on the FSAR Chapter 15 Analysis In the supplemental information dated September 24, 2018, the licensee identifies the following safety analysis limits (SALs) used to determine the total allowance (TA) for the following functional units in TS Table 2.2-1 or TS Table 3.3-4:
Functional Unit No.12 - Reactor Coolant Flow - Low (SAL = 88.0% RCS Flow)
Functional Unit No. 2.a - Power Range, Neutron Flux - High (SAL = 113.5% RTP)
Functional Unit No. 9 - Pressurizer Pressure - Low (SAL = 1923 psig)
Functional Unit No. 10 - Pressurizer Pressure - High (SAL = 2422 psig)
Functional Unit No. 7 - Overtemperature T (K3 = 0.1% RTP/psig)
Functional Unit No. 8 - Overpower T (SAL = 115% RTP)
Functional Unit No.1.d - Safety Injection, Pressurizer Pressure - Low (SAL = 1742 psig)
The staff notes the values of the above SALs are different from those assumed in the FSAR Chapter 15 analysis. Please provide a discussion to address the effects of each of the above SALs on the analysis of the FSAR Chapter 15 events and demonstrate that the safety analysis limits are acceptable in meeting the Chapter 15 acceptance criteria.
STSB RAI 1 One of the proposed changes to the TS is deletion of the high power range negative neutron flux rate trip (Functional Unit 4 of Table 2.2-1, Reactor Trip System Instrumentation Trip Setpoints). Sections 2.4 and 3.5 of the LAR discuss this proposed change. The LAR states that this trip function is currently credited in the dropped rod analysis of record, but will no longer be credited in any FSAR Chapter 15 accident analysis following the replacement of the current dropped rod analysis with a revised analysis performed in accordance with Duke Energy methodologies.
The LCO 3.3.1 specifies that as a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1, shall be operable. Table 3.3-1, Reactor Trip System Instrumentation, specifies the total number of channels, channels to trip, minimum channels operable, applicable mode, and a reference to the Action statement if the LCO is not met. The Power Range, Neutron Flux High Positive Rate, is included in this Table as Functional Unit 3.
The LAR does not propose changes to this requirement.
Currently, Table 2.2-1 specifies the total allowance, statistical summation of analysis errors, trip setpoint and allowable value for the Reactor Trip System Instrumentation automatic trip setpoints. Equation 2.2-1 is used to provide a threshold for evaluation of operability of an instrument channel. With the proposed deletion of the high power range negative neutron flux rate trip from Table 2.2-1, the threshold value for determining proper channel performance would no longer be specified in the TS and it is not clear to the staff what controls will be established to manage the trip setpoint and allowable value in the future.
Page 3 of 4
- a. Please provide a description of the controls that will be applied to manage the trip setpoint and allowable value in the future.
- b. Please also provide additional information to describe how the requirements of LCO 3.3.1 will be satisfied for this RTS function. Specifically, please explain what value will provide the threshold for evaluating operability, and, if applicable, explain why the threshold for operability is not being retained in the TS. Please also provide an explanation of how this value will be administratively controlled.
Page 4 of 4