LR-N21-0007, Report of Changes, Tests, and Experiments
ML21028A788 | |
Person / Time | |
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Site: | Hope Creek ![]() |
Issue date: | 01/28/2021 |
From: | Mannai D Public Service Enterprise Group |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
LR-N21-0007 | |
Download: ML21028A788 (3) | |
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Category:Letter type:LR
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ML13266A2972013-11-18018 November 2013 Audit Report Regarding Flooding Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13052A6752012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary LR-N12-0366, Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary2012-11-28028 November 2012 Attachment to LR-N12-0366 - Study Kld TR-499, Rev 0 - 10CFR 50.54 (8) Summary ML12220A2502012-08-10010 August 2012 Closeout of Bulletin 2011-01, Mitigating Strategies ML12159A3552012-06-0808 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML11203A0782011-07-13013 July 2011 Independent Spent Fuel Storage Installation, 10 CFR 72.212 Evaluation Report, Revision 6 LR-N11-0090, 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations2011-04-0808 April 2011 2010 10 CFR 20.2206 Report - Apportion the 2010 Site Dose Between Salem and Hope Creek Stations ML11061A0052011-03-30030 March 2011 Ncsa Hope Creek Observations Rev. 4 LR-N10-0355, Salem, EAL Technical Bases Supporting Documents2010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML1100602392010-10-14014 October 2010 Salem, EAL Technical Bases Supporting Documents ML11263A0302010-09-20020 September 2010 E-mail with Attachment from B. Pham, NRR to L. Perkins, NRR, on Forward Salem/Hope Creek Chapter 5 SAMA Input ML11263A0282010-09-16016 September 2010 E-mail with Attachment from T. Ghosh, NRR, to C. Eccleston, NRR Et Al, on Reaction Hope Creek SAMA Transmittal Memo LR-N10-0306, 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S2010-08-10010 August 2010 50.59 Review Coversheet Form for Hope Creek Unit 1 DCP 80102144, Revise Dose Analysis Calculations & Update UFSAR to Remove 120 Second Isolation Time for Pciv'S LR-N09-0206, Special Report - North Plant Vent Radiation Monitoring System (Rms)2009-08-24024 August 2009 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N08-0224, Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit2008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit ML0831008272008-10-31031 October 2008 Attachments 3 and 4 - Hope Creek Extended Power Uprate Power Ascension Test Report and Affidavit LR-N08-0247, Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action2008-10-30030 October 2008 Stations, Report of HHS-Certified Laboratory Testing Error Investigation and Corrective Action ML0826005732008-09-0202 September 2008 NFS-0255, Revision 0, Hope Creek Generating Station - Initial Implementation of WCAP-15942-P-A (Formerly CENO-287), Fuel Assembly Mechanical Design Methodology for Boiling Water Reactors Supplement to CENP-287, Evaluation of Control Blade I ML0732300962007-11-0909 November 2007 Discharge Confirmation Report - Retraction of Reported Discharge to the Delaware River HCH-2007-052, Notice of Noncompliance and Affirmative Defense of Laboratory Error2007-05-23023 May 2007 Notice of Noncompliance and Affirmative Defense of Laboratory Error LR-N07-0040, Special Report - North Plant Vent Radiation Monitoring System (Rms)2007-02-20020 February 2007 Special Report - North Plant Vent Radiation Monitoring System (Rms) LR-N06-0401, Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models2006-09-28028 September 2006 Submittal of 10CFR50.46 Report Regarding Changes in the Application of the Emergency Core Cooling System Evaluation Models ML0626900642006-09-0101 September 2006 Attachment 26, C.D.I. Report No. 06-16NP, Rev 1, Estimating High Frequency Flow Induced Vibration in the Main Stream Lines at Hope Creek Unit 1: a Subscale Four Line Investigation of Standpipe Behavior. ML0622805562006-07-27027 July 2006 Groundwater Protection - Data Collection Questionnaire LR-N06-0216, Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report2006-05-0404 May 2006 Letter to Samuel Collins, Dtd May 04, 2006, from PSEG (LR-N06-0216) Regarding Safety Conscious Work Environment Peer Assessment Report ML0607204372006-03-0707 March 2006 Redacted Response to Request for Information Regarding Executive Review Board Commitments; PSEG ML0606703012006-02-0707 February 2006 PSEG-News Document Detailing Chris Bakken Will Succeed Anderson as President and CNO of PSEG Nuclear ML0605801622006-02-0101 February 2006 Performance Themes for Use After Inspection Exits (Regarding Poor Equipment Reliability, Corrective Action Ineffectiveness) and Organizational Issues (Regarding Engineering, Maintenance & Work Control, Operations, and Licensing/Regulatory C ML0524901582005-08-31031 August 2005 Allegation Receipt Report Regarding Facility: Hope Creek ML0526302272005-08-23023 August 2005 Communication Plan & Notification Sequence Regarding Receipt & Docketing of PSEG Assessment Reports ML0531803762005-04-30030 April 2005 NEDO-33186, Revision 1, MELLLA Tracg Divom Evaluation for Hope Creek at Cppu Conditions. 2023-12-15 |
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PSEG Nuclear UC P.O. Box 236, Hancock& Bridge, New Jersey 08038--0236 0 PSEG Nurlenr /,LC 10 CFR 50.59 LR-N21-0007 January 28, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555-001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 Docket No. 50-354
Subject:
Report of Changes, Tests, and Experiments Pursuant to the requirements of 10 CFR 50.59, UChanges, Tests, and Experiments," paragraph (d) (2), Hope Creek Generating Station (HCGS) is providing the required report (Attachment 1) for Renewed Facility Operating License No. NPF-57. This report provides a summary of 10CFR50.59 evaluations for activities implemented under 10CFR50.59 at HCGS during the period of January 1, 2019, through December 31, 2020.
There are no regulatory commitments contained in this letter.
If you have any questions or require additional information, please contact Ms. Bernadette Humphrey at (856) 339-1308.
Si7~;---
David Mannai Senior Director - Regulatory Operations PSEG Nuclear LLC : Report of Changes, Tests, and Experiments
1-R-N21-00P7 Page2 cc: Mr. Davic1 Lew, Regional Administrator - NR.C ~eg;on 1 Mr. James Kim, Project Manager - U~NRC Mr. Jjgar Patel, USNRC Senior ~esident Inspector - HQpe CreeJ<
Mr. Patrick Mulligan, Manager IV, NJBNJ=
Mr, Lee Marabella, Corporate Commitment Tracking CQordinator Mr. Thomas Cachaza, Hope Creek Commitment Tracking Coordinator
LR-N21-0007 Attachment 1 Hope Creek Generating Station Renewed Facility Operating License NPF-57 Docket No. 50-354 Report of Changes, Tests, and Experiments C-SSW Strainer Backwash Valve Open In May 2019, Temporary Configuration Control Process (TCCP) 4HT-19-Q03 was implemented.
The TCCP fails open Service Water System strainer backwash valve H1EA-EA-HC-2197C.
The TCCP was implemented to defeat the auto-close feature until repairs or replacement can be performed.
The 50.59 evaluation was performed utilizing a prepared technical evaluation that clarified Hope Creek Service Water System {SWS) design and licensing basis. It concluded that having H1EA-EA-2197C in a failed open position is bounded by existing analyses and configurations previously evaluated. Consequently, compensatory measures were not required to assure the SSW/SACS design bases are met and changes to design basis calculations were not required.
While considered an off-normal condition versus what is stated in the UFSAR descriptive material, this configuration would not be considered adverse from a system/thermal hydraulic standpoint The SSWS system remains capable of fulfilling its design/licensing basis functions with or without the TCCP installed. Therefore, the TCCP was implemented without a license Amendment.
Hope Creek control Room HVAC Veritrak Controller Replacement The Hope Creek Control Room Safety Related HVAC controllers were replaced due to obsolescence in November 2020. The Design Change replaced the Main Control Room differential pressure (dp) controllers and alarm cards, originally supplied by Westinghouse, with digital, microprocessor-based single loop controllers supplied by Yokogawa. The replacement was performed on both the A and B trains of Main Control Room HVAC.
The 50.59 evaluation was performed in order to evaluate the impact of a digital failure, specifically a common cause failure. A qualitative assessment was performed in accordance with the guidance of Regulatory Information Summary 2002-22 Supplement 1. It concluded that the likelihood of a systematic failure due to a design defect of the Yokogawa controllers is sufficiently low; i.e., much lower than other failures that are considered in the UFSAR. The failure modes of the new equipment due to random hardware failures, including new failure modes due to combination of functions, are bounded by failure modes of the existing equipment. System-level failure modes described in the UFSAR remain bounding. The assessment concluded that the replacement controllers are qualified to the design environment, including environmental capability and Seismic qualification. There is no increase in the likelihood of occurrence of a malfunction of an SSC important to safety, and a malfunction with a different result is not created. Thus, replacement of the Main Control Room dp controllers with new digital controllers did not require a license amendment.
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