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Category:E-Mail
MONTHYEARML24289A1442024-10-15015 October 2024 NRR E-mail Capture - Acceptance Review - Entergy (Grand Gulf Nuclear Station and River Bend Station) - CNRO2024-00017 - Adopt TSTF-592 - CLIIP (L-2024-LLA-0133) ML24137A2702024-05-16016 May 2024 NRR E-mail Capture - Entergy Fleet - Acceptance Review of License Amendment Request to Remove Obsolete License Conditions from Operating Licenses for GGNS, RBS, and WF3 (L-2024-LLA-0062) ML24088A0092024-03-27027 March 2024 NRR E-mail Capture - Entergy Fleet - Final Request for Confirmation of Information (RCI) Re Alternative Request EN-RR-22-001 Concerning ASME Code Case N-752 (L-2022-LLR-0054) ML23348A1222023-12-14014 December 2023 NRR E-mail Capture - Grand Gulf, River Bend, and Waterford, Unit 3 - 2nd Round of Official RAIs for RR EN-RR-22-001, Use ASME Code Case N-752, Risk Informed Categorization for Class 2 and 3 Systems ML24031A2772023-11-27027 November 2023 (05000458/2024040) IP 95001 Regarding EA-23-071 Initial Request for Information ML24102A2442023-09-22022 September 2023 NRR E-mail Capture - Audit Question TSTF-505 and 50.69 ML23240A3412023-08-28028 August 2023 NRR E-mail Capture - ANO-2, Grand Gulf, and River Bend - Acceptance Review of LAR Revising TSs to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined ML23116A1462023-04-26026 April 2023 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Final RAI for Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23103A4662023-04-0404 April 2023 NRR E-mail Capture - River Bend Station, Unit 1 - Acceptance Review for LAR to Adopt TSTF-505, Rev. 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML23103A4672023-04-0404 April 2023 NRR E-mail Capture - River Bend Station, Unit 1 - Acceptance Review for LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23089A0702023-03-29029 March 2023 TSTF-505 Email Providing Reference for 0.3g HCLPF Value ML23072A3672023-03-0909 March 2023 NRR E-mail Capture - Entergy Fleet - Acceptance Review of Quality Assurance Program Manual Reduction in Commitment ML23009B6912023-01-0909 January 2023 NRR E-mail Capture - Grand Gulf, Unit 1 and River, Unit 1 - Acceptance of Requested Licensing Action Request to Update ASME Code RR SE with NRC-Approved Revision of BWRVIP Guidelines ML22206A0152022-07-21021 July 2022 NRR E-mail Capture - Entergy (Grand Gulf, River Bend, and Waterford-3) - Acceptance Review of the RR EN-RR-22-001, Case N-752, Risk-informed Cat & Treatment for Repair/Replacement Activities in Class 2 & 3 Systems ML22173A0372022-06-21021 June 2022 NRR E-mail Capture - Entergy (Grand Gulf and River Bend) - Acceptance Review of the License Amendment Request to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML21356A5882021-12-22022 December 2021 NRR E-mail Capture - Acceptance for Review: River Bend Station 1 - IST Program Relief Request for PIV Testing Frequency ML21312A4792021-11-0505 November 2021 Email: NRC Staff Preliminary Questions Regarding X Energy LLC Xe-100 Topical Report: Risk-Informed Performance-Based Licensing Basis Development ML21308A5602021-11-0404 November 2021 NRR E-mail Capture - Arkansas Nuclear One, Units 1 and 2, Grand Gulf, River Bend, and Waterford, Unit 3 - Acceptance Review of LAR to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements ML21292A0112021-10-18018 October 2021 NRR E-mail Capture - ANO, 1 and 2, Grand Gulf, River Bend, Waterford, 3 - Acceptance Review of LAR to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21218A0412021-07-19019 July 2021 NRR E-mail Capture - River Bend Unit 1 - Acceptance of License Amendment Request to Add License Condition Concerning Receipt, Possession ML21174A0342021-06-22022 June 2021 NRR E-mail Capture - Entergy Fleet (ANO, Ggulf, Rbend, & Waterford) - Acceptance Review for Relief Request to Use a Provision of a Later Edition of the ASME Code, Section XI for Periodic System Pressure Tests Exemptions ML21109A2142021-04-19019 April 2021 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Rev. Est Hours for Review of Relief Request (RR) - ASME Code RR Safety Eval with NRC-Approved Rev of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML21099A0312021-03-30030 March 2021 Email 3-30-2021 - Request for Information_ RBS EP Exercise Inspection (Week of 5_10_2021) ML21109A2132021-03-23023 March 2021 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Relief Request (RR) Associated with ASME Code RR Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML21068A4092021-03-0909 March 2021 NRR E-mail Capture - Entergy Fleet (GGNS and RBS) -Approval of TSTF-501 LAR, Relocate Sored Fuel Oil and Lube Oil Volume Values to Licensee Control ML21022A1692021-01-22022 January 2021 NRR E-mail Capture - Entergy Fleet (ANO, Grand Gulf, River Bend, and Waterford) - Acceptance Review for RR EN-20-RR-003, Proposed Alternative to Use ASME Code Case N-711-2 ML21015A3452021-01-14014 January 2021 NRR E-mail Capture - Grand Gulf and River Bend - Revised Estimated Hours for Relief Request Associated with ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20337A1382020-11-23023 November 2020 Acceptance of License Amendment Request to Adopt GL 86-10 Standard License Condition for Fire Protection ML20329A1442020-11-20020 November 2020 Terrapower QAPD Preliminary Questions Email ML20317A2922020-10-15015 October 2020 Entergy Operations, Inc. (River Bend Station, Unit 1) - Acceptance Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20289A3542020-10-14014 October 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of TSTF-563 LAR, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML20255A1892020-09-0909 September 2020 Email 09Sept2020 - RFI for RBS EP Exercise Inspection ML20260H4422020-09-0808 September 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Official RAIs for RR Associated with Updating ASME Code RR SEs with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020 and RBS-ISI-019) ML20169A3782020-06-16016 June 2020 Email-20-0196-NRC Riv Response V. Dricks to Tom Gurdziel Inquiry: Extent of Condition Flex Equipment ML20169A6752020-05-20020 May 2020 Email-20-0196, Tom Gurdziel Inquiry to NRC Chairman Resource, Extent of Condition FLEX Equipment, 05/20/2020 ML20093C3072020-04-0101 April 2020 NRR E-mail Capture - (External_Sender) Entergy Fleet - Performance-Based Cyber Security Testing Plan Fee Waiver Response Letter (EPID P-2020-PRF-0000; CAC No. 001648) ML20086J6572020-03-26026 March 2020 NRR E-mail Capture - River Bend Station, Unit 1 -Acceptance Review of the LAR Associated with Extending the Implementation Date from 5/13/2020 to 9/30/2020 for Emergency Action Level Scheme ML20079D9302020-03-19019 March 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with Adopting TSTF-501, Relocate Stored Fuel Oil and Lube Oil Volumes to Licensee Control ML20057G1752020-02-24024 February 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with TSTF-566, Revise Actions for Inoperable RHR-Shutdown Cooling Subsystems ML20057G1592020-02-24024 February 2020 NRR E-mail Capture - Entergy Fleet (Grand Gulf and River Bend) - Acceptance Review of LAR Associated with TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML20038A2092020-02-0404 February 2020 05000458 Request for Information IR2020-001 Occupational Radiation Safety ML19352F5222019-12-17017 December 2019 NRR E-mail Capture - Acceptance Review Results for License Amend Request to Revise TS 3.3.5.2 to Adopt TSTF-425, Rev 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5b, for River Bend, ML19102A0722019-04-11011 April 2019 NRR E-mail Capture - River Bend Station, Unit 1 - Final Request for Additional Information Relief Request RBS-ISI-021 ML19095B7622019-04-0303 April 2019 Acceptance Review Results for License Amendment Request to Adopt TSTF-564, Revision 2, Safety Limit MCPR (Minimum Critical Power Ratio), for Grand Gulf Nuclear Station, Unit 1 and River Bend Station, Unit 1 (EPID L-22019-LLA-0051) ML19059A1782019-02-28028 February 2019 Acceptance Review Results for Relief Request No. EN-19-RR-1 to Use ASME Code Case N-831-1 for Entergy Fleet ML19059A0292019-02-27027 February 2019 NRR E-mail Capture - Acceptance Review Results for License Amendment Request to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules, for Entergy Fleet ML19008A3592019-01-0808 January 2019 NRR E-mail Capture - Acceptance Review: RR Volumetric Exams (L-2018-LLR-0388) ML18365A1422018-12-28028 December 2018 NRR E-mail Capture - Acceptance Review Results - Removal of TS Table of Contents (L-2018-LLA-0489) 2024-05-16
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Text
NRR-DMPSPEm Resource From: Humphreys, Jerry <Jerry.Humphreys@dep.nj.gov>
Sent: Tuesday, December 12, 2017 1:05 PM To: Regner, Lisa Cc: Gubbi, Veena; Rosenfeld, Elliot; Timberman, Tanya J
Subject:
[External_Sender] Hope Creek LAR H17-02: Relocate P-T Curves to a PTLR On March 27, 2017, PSEG Nuclear LLC submitted License Amendment Request (LAR) H17-02 to the NRC. This LAR proposes to amend the Hope Creek (HC) Technical Specifications (TS) to revise and relocate the Pressure-Temperature (P-T) Limit Curves to a Pressure and Temperature Limits Report (PTLR).
According to the proposed PSEG LAR H17-02: The PTLR contains updates to the P-T limit curves for the Hope Creek reactor pressure vessel (RPV). The P-T curves were prepared using the methods documented in the Boiling Water Reactor Owners Group (BWROG) Licensing Topical Report (LTR)
(BWROG-TP-11-022-A, SIR-05-044), Pressure Temperature Limits Report Methodology for Boiling Water Reactors. This BWROG LTR satisfies the requirements of 10 CFR 50 Appendix G and the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section XI, Non-mandatory Appendix G. The guidance of NRC Generic Letter (GL) 96-03, "Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits," was applied during P-T curve development. Also, Technical Specification Task Force (TSTF) Traveler TSTF-419-A, "Revise PTLR Definition and References in ISTS 5.6.6, RCS PTLR, which has received NRC approval, was followed in development of the proposed TS changes.
The NRC has approved similar license amendments to relocate the P-T limit curves to a PTLR.
Recent examples for BWR plants include the Hatch, Cooper, Duane Arnold and Nine Mile Point Stations.
The New Jersey Bureau of Nuclear Engineering (NJ BNE) has reviewed LAR H17-02 and has no comments as a result of the following:
- 1. The P-T Curves are based on a BWROG Licensing Topical Report that meets the requirements of 10 CFR 50, Appendix G and ASME Code,Section XI, Non-mandatory Appendix G. These documents are used as part of the licensing/design bases for Hope Creek. Therefore, the licensing/design bases are being maintained.
- 2. The proposed TS were developed under the guidance of NRC GL 96-03 and in accordance with the NRC approved TSTF-419-A.
- 3. Other operating BWRs have been approved by the NRC to relocate the P-T curves to a PTLR.
If you have any questions, please feel free to contact me via the info below.
Jerry Humphreys Bureau of Nuclear Engineering New Jersey Department of Environmental Protection 1
33 Arctic Parkway, Mail Code 33-01, Trenton New Jersey 08625-0420 (609) 984-7469 Office (609) 372-5304 Cell Save a tree... Please consider the environment before printing this e-mail.
NOTE: This e-mail is protected by the Electronic Communications Privacy Act, 18 U.S.C. Sections 2510-2521.
This E-Mail and its contents may be Privileged & Confidential due to the Attorney-Client Privilege, Attorney Work Product, Deliberative Process or under the New Jersey Open Public Records Act.
If you are not the intended recipient of this e-mail, please notify the sender, delete it and do not read, act upon, print, disclose, copy, retain or redistribute it.
From: Regner, Lisa Sent: Monday, December 4, 2017 9:43 AM To: Humphreys, Jerry Cc: Regner, Lisa
Subject:
Notification of Impending License Amendment Issuance for Hope Creek Nuclear Generating Station and Request for Comments Good Morning, Jerry.
I hope this finds you well and enjoying the season.
I expect to issue a license amendment to Hope Creek by the end of the year that involves allowing it to move its Pressure-Temperature (PT) Limit Curves to a licensee-controlled document: the PT Limits Report (PTLR).
This is not a new or unusual amendment, but if you have any questions, feel free to give me a call. More details are below.
Thank you, and have a great day.
Lisa Regner Lisa M. Regner Senior Project Manager Branch 4, Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Lisa.Regner@NRC.gov
' 301-415-1906 OWFN 9D14 By letter dated March 27, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17086A364), as supplemented by letters dated April 28, 2017, and September 5, 2017 (ADAMS Accession Nos.
ML17118A092 and ML17248A127, respectively), PSEG Nuclear, LLC (PSEG, the licensee) submitted a license amendment request (LAR) for Hope Creek Generating Station (Hope Creek). The amendment requested changes to the Hope Creek Technical Specifications (TSs) to relocate the reactor coolant system (RCS) pressure-temperature (P-T) limits from the TSs to a new licensee-controlled document called the Pressure and Temperature Limits Report (PTLR). The LAR also proposed revisions to the 32 effective full power years (EFPY) P-T limit curves and proposed new P-T curves applicable through 44 EFPY and 56 EFPY through the end of the license renewal term. The revisions to the curves were required due to the results of a recently pulled and tested reactor pressure vessel (RPV) surveillance capsule. The proposed Hope Creek P-T limit curves to be incorporated in the PTLR were developed based on the U.S. Nuclear Regulatory Commission (NRC or the Commission)-approved methodologies described in the Boiling Water Reactor Owners Group (BWROG)
Topical Report BWROG-TP-11-022-A (SIR-05-044), Revision 1, Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," August 2013 (ADAMS Accession No. ML13277A557). This guidance will be referred to as BWROG-TP-11-022-A, Revision 1, or the BWROG PTLR methodology in this safety evaluation (SE).
2
Hearing Identifier: NRR_DMPS Email Number: 42 Mail Envelope Properties (BL0PR0901MB245186FBB2BBF1B1EC14E19EDC340)
Subject:
[External_Sender] Hope Creek LAR H17-02: Relocate P-T Curves to a PTLR Sent Date: 12/12/2017 1:05:03 PM Received Date: 12/12/2017 1:06:34 PM From: Humphreys, Jerry Created By: Jerry.Humphreys@dep.nj.gov Recipients:
"Gubbi, Veena" <Veena.Gubbi@dep.nj.gov>
Tracking Status: None "Rosenfeld, Elliot" <Elliot.Rosenfeld@dep.nj.gov>
Tracking Status: None "Timberman, Tanya J" <Tanya.Timberman@pseg.com>
Tracking Status: None "Regner, Lisa" <Lisa.Regner@nrc.gov>
Tracking Status: None Post Office: BL0PR0901MB2451.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 5644 12/12/2017 1:06:34 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: