|
---|
Category:Graphics incl Charts and Tables
MONTHYEARML23249A2632023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2019 ML23249A2642023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2020 ML23249A2652023-09-0606 September 2023 Attachment 1: PSEG Site Hourly Meteorological Data (2019 - 2021), Salem/Hope Creek Finalized Hourly Meteorological Data 2021 ML23249A2662023-09-0606 September 2023 Attachment 2: Salem Pavan Input File ML23249A2672023-09-0606 September 2023 Attachment 3: Salem Pavan Output File ML23249A2682023-09-0606 September 2023 Attachment 4: Hope Creek Pavan Input File LR-N23-0050, Attachment 5: Hope Creek Pavan Output File2023-09-0606 September 2023 Attachment 5: Hope Creek Pavan Output File LR-N16-0112, Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal2016-12-29029 December 2016 Flood Hazards Mitigating Strategies Assessment (MSA) Report Submittal ML16320A4842016-11-15015 November 2016 Public Telecon Regarding LAR to Upgrade Power Range Neutron Monitoring System (Meeting Handout) ML16231A1102016-08-16016 August 2016 Updated Issues List for 08/16/2016 Public Telecon Regarding LAR to Upgrade Power Range Neutron Monitoring System Meeting Handout ML16116A2352016-03-15015 March 2016 Meeting Summary for Public Teleconference Between PSEG LLC and the Nuclear Regulatory Commission, Hope Creek Generating Station - Power Range Neutron Monitoring System Digital Upgrade LAR HCGS Numac Upgrade - Open Item DOC-0006-2118 Ri ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML16102A2772016-03-11011 March 2016 Submittal of Annual Incidental Take Report ML15238B6552015-09-10010 September 2015 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML15243A5022015-09-10010 September 2015 Interim Letter Tables 1 and 2 ML15030A2952014-09-22022 September 2014 Table 04, Groundwater Measurements and Elevations - First Quarter 2014 ML15030A2942014-09-22022 September 2014 Table 03, Effluent Data Tritium Activity LR-N12-0366, Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-1492012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 ML13052A6822012-11-28028 November 2012 Kld TR-499, Revision 0, Development of Evacuation Time Estimates, Appendix K-76 Through K-149 ML12284A4272012-10-0404 October 2012 PSEG Early Site Permit Application, Calculation of Multiplier Effects for Er Section 10.4 ML11181A1872011-06-29029 June 2011 Attendance Sheet for 06/29/2011 Public Meeting to Discuss Observations and Lessons Learned of the Pilot Application of the Nuclear Energy Institute'S ML0805605392008-03-0404 March 2008 Meeting Handout #7 - Graph Supporting Salem FAQ on Grassing Events ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0715002022007-05-29029 May 2007 U.S. Census Bureau Minority Data for Hope Creek Generating Station EPU ML0620201752006-07-17017 July 2006 NRC Inspection Findings ML0606600642006-02-0707 February 2006 SCWE Followup Practices - Development Timeline LR-N06-0046, PSEG Metrics for Improving Work Environment, Salem and Hope Creek, Quarterly Report2006-01-31031 January 2006 PSEG Metrics for Improving Work Environment, Salem and Hope Creek, Quarterly Report ML0509801732005-04-0505 April 2005 PSEG Nuclear LLC Hope Creek Station B-Reactor Recirculation Decontamination Connection Leak Cause Determination Report Notification No. 20230319, Event Date: March 27. 2005 ML0509801992005-04-0202 April 2005 Decontamination Port, Reactor Recirc Vibration Data Analysis ML0509801312005-04-0101 April 2005 Decontamination Port, Natural Frequency of Loop B Port ML0509801122005-04-0101 April 2005 Decontamination Port, Harmonic Stress Analysis of Loop B Port ML0521403342005-03-0909 March 2005 RIC 2005 Presentation - B3 - Michael Brothers - Objective Measures of Safety Culture ML0501202612005-01-12012 January 2005 December Monthly Report on the Status of Open TIAs Assigned to NRR ML0500600222004-12-30030 December 2004 'B' Recirculation Pump Stuffing Box Measurements Summary ML0500602562004-12-30030 December 2004 'B' Reactor Recirculation Pump Vibration Troubleshooting Summary ML0500501112004-12-12012 December 2004 H-1-FD-CEE-1879, Hope Creek HPCI Exhaust Piping Supports Analysis Reported Damage in RF12. ML0500603842004-09-0707 September 2004 C-0031 Piping Code Compliance, 9/7/2004 ML0524904612004-08-10010 August 2004 Open Branch 3 Allegation Status Summary ML0622103332004-03-0303 March 2004 Regulatory Activity Schedule ML0500600411995-12-26026 December 1995 H-1-BB-MEE-1050 Hope Creek Recirculation System Large Bore Pipe Cracking Resolution, 12/26/1995 2023-09-06
[Table view] Category:Letter
MONTHYEARIR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval ML24009A1022024-01-26026 January 2024 Exemption from Select Requirements of 10 CF Part 73 (EPID L-2023-LLE-0045 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000354/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000354/2023401 ML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23270C0072023-11-29029 November 2023 Notice of Proposed Amendment to Decommissioning Trust Agreement ML23324A3072023-11-17017 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 IR 05000272/20234022023-10-12012 October 2023 and Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2023402, 05000272/2023402 and 05000311/2023402 (Cover Letter Only) LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023 Submittal of 2023 Annual 10 CFR 50.46 Report LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023 and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement ML23249A2612023-09-0606 September 2023 License Amendment Request to Modify the Salem and Hope Creek Exclusion Area Boundary IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location IR 05000354/20230022023-08-0303 August 2023 Integrated Inspection Report 05000354/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200048/2023001 IR 05000354/20230102023-08-0303 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000354/2023010 LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1 LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023 Spent Fuel Cask Registration LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) IR 05000354/20230012023-04-26026 April 2023 Integrated Inspection Report 05000354/2023001 LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023 License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023 License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains ML23087A1492023-04-17017 April 2023 NRC to PSEG Salem, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23089A0942023-04-17017 April 2023 NRC to PSEG Hope Creek, Transmittal of the National Marine Fisheries Service'S March 24, 2023, Biological Opinion GAR-2020-02842 Concerning Salem and Hope Creek ML23103A3232023-04-13013 April 2023 Submittal of Updated Final Safety Analysis Report, Rev. 26, Summary of Revised Regulatory Commitments for Hope Creek, Summary of Changes to PSEG Nuclear LLC, Quality Assurance Topical Report, NO-AA-10, Rev. 89 ML23095A3682023-04-12012 April 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Threshold Determination for Proposed Transfer of Land Ownership LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023 Submittal of Hope Creek Generating Station Technical Specification Bases Changes LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations ML23086A0912023-03-24024 March 2023 NMFS to NRC, Transmittal of Biological Opinion for Continued Operations of Salem and Hope Creek Nuclear Generating Stations LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums ML23037A9712023-03-0909 March 2023 and Salem Nuclear, Unit Nos. 1 and 2 Issuance of Amendment Nos. 233, 344, and 325 Relocate Technical Specification Staff Qualification Requirements to the PSEG Quality Assurance Topical Report IR 05000354/20220062023-03-0101 March 2023 Annual Assessment Letter for Hope Creek Generating Station (Report 05000354/2022006) LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023 and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023 Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023 Annual Property Insurance Status Report LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023 Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717 IR 05000354/20220042023-01-24024 January 2023 Integrated Inspection Report 05000354/2022004 LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023 In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023 and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022 Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments ML22335A0412022-12-0101 December 2022 Notification of Commercial Grade Dedication Inspection (05000354/2023011) and Request for Information IR 05000354/20220032022-11-0303 November 2022 Integrated Inspection Report 05000354/2022003 2024-02-01
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 10, 2015 Mr. Robert Braun President and Chief Nuclear Officer PSEG Nuclear LLC-N09 P. 0. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION- INTERIM STAFF RESPONSE TO REEVALUATED FLOOD HAZARDS SUBMITTED IN RESPONSE TO 10 CFR 50.54(f) INFORMATION REQUEST - FLOOD-CAUSING MECHANISM REEVALUATION (TAC NO. MF3789)
Dear Mr. Braun:
The purpose of this letter is to provide a summary of the U.S. Nuclear Regulatory Commission (NRC) staff's assessment of the re-evaluated flood-causing mechanisms described in the March 12, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14071A511) flood hazard reevaluation report (FHRR) submitted by PSEG Nuclear LLC (PSEG, the licensee) for Hope Creek Generating Station (Hope Creek), as well as supplemental information resulting from requests for additional information and audits.
By letter dated March 12, 2012, the NRC issued a request for information pursuant to Title 1O of the Code of Federal Regulations, Section 50.54(f) (hereafter referred to as the 50.54(f) letter)
(ADAMS Accession No ML12053A340). The request was issued as part of implementing lessons-learned from the accident at the Fukushima Dai-ichi nuclear power plant. Enclosure 2 to the 50.54(f) letter requested licensees to re-evaluate flood-causing mechanisms using present-day methodologies and guidance. Concurrently, with the reevaluation of flooding hazards, licensees were required to develop and implement mitigating strategies in accordance with NRC Order EA-12-049, "Requirements for Mitigation Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML12054A735). On March 30, 2015, the Commission provided Staff Requirements Memoranda (SRM) (ADAMS Accession No. ML15089A236) to COMSECY-14-0037, "Integration of Mitigating Strategies for Beyond-Design-Basis External Events and the Reevaluation of Flooding Hazards," dated November 21, 2014 (ADAMS Accession No. ML14309A256), affirming that licensees need to address the reevaluated flooding hazards within their mitigating strategies for beyond-design-basis external events.
The NRC staff has reviewed the information submitted by the licensee and has summarized the results of the review in the tables provided as an Enclosure to this letter. Table 1 provides the current design-basis flood hazard mechanisms. Table 2 provides the reevaluated flood hazard mechanisms; however, the reevaluated flood hazard mechanisms bounded by the current design-basis (Table 1) are not included.
R. Braun The NRC staff has concluded that the licensee's reevaluated flood hazards information, as summarized in the Enclosure, is suitable for the assessment of mitigating strategies developed in response to Order EA-12-049 (i.e., defines the mitigating strategies flood hazard information described in guidance documents currently being finalized by the industry and NRC staff) for Hope Creek. Further, the staff has concluded that the licensee's reevaluated flood hazard information is a suitable input for other assessments associated with Near-Term Task Force Recommendation 2.1 "Flooding". The NRC staff plans to issue a staff assessment documenting the basis for these conclusions at a later time.
In addition, NEI 12-06 "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide" is currently being revised. This revision will include a methodology to perform a Mitigating Strategies Assessment (MSA) with respect to the reevaluated flood hazards. Once this methodology is endorsed by the NRC, flood event duration parameters and applicable flood associated effects should be considered as part of the Hope Creek MSA. The NRC staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood-related associated effects developed by the licensee during the NRC staff's review of the MSA.
As stated above, Table 2 of the enclosure to this letter describes the reevaluated flood hazards that exceed the current design-basis. In order to complete its response to the information requested by Enclosure 2 to the 50.54(f) letter, the licensee is expected to submit an integrated assessment or a focused evaluation, as appropriate, to address these reevaluated flood hazards, as described in the NRC letter, "Coordination of Request for Information Regarding Flooding Hazard Reevaluation and Mitigating Strategies for Beyond-Design-Basis External Events" (ADAMS Accession No. ML15174A257). This letter describes the changes in the NRC's approach to the flood hazard reevaluations that were approved by the Commission in its SRM to COMSECY-15-0019, "Closure Plan for the Reevaluation of Flooding Hazards for Operating Nuclear Power Plants" (ADAMS Accession No. ML15209A682).
R. Braun If you have any questions, please contact me at (301) 415-6197 or e-mail at tekia.govan@nrc.gov.
Sincerely, J;u~v.~~
Tekia V. Govan, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Summary of Results of Flooding Hazard Re-Evaluation Report cc w/encl: Distribution via Listserv
ENCLOSURE:
SUMMARY
TABLES OF REEVALUATED FLOOD HAZARD LEVELS
Hope Creek, Unit 1 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference I Elevation Run up Hazard I Elevation i Local Intense Precipitation I
12.1 ft Minimal 12.1 ft FHRR Table 3-1 NAVD88 NAVD88 Streams and Rivers I Powerblock/Service Water Intake 7.5 ft 12.5 ft 20.0 ft FHRR Section 1.2.2 Structure NAVD88 NAVD88 Failure of Dams and Onsite Water Control/Storage Structures Multiple Failures of Connonsville, 12.7ft 12.8 ft 25.5 ft FHRR Section 1.2.3 Pepacton and Tocks Island Dams NAVD88 NAVD88 Storm Surge Powerblock A 24.0 ft NAVD88
+-
6.2 ft I
30.2 ft NAVD88 FHRR Table 3-1 Powerblock 8 24.0 ft 10.6 ft 34.6 ft FHRR Section 1.2.4 NAVD88 NAVD88 Service Water Intake Structure 24.0 ft 20.6 ft 44.6 ft FHRR Section 1.2.4 NAVD88 NAVD88 Seiche I
No Impact No Impact No Impact FHRR Section 1.2.5 on the Site on the Site on the Site Identified Identified I Identified Tsunami 5.2 ft 12.1 ft 17 .3 ft FHRR Section 1.2.6 NAVD88 NAVD88 Ice-Induced Flooding No Impact No Impact No Impact FHRR Section 1.2.7 on the Site on the Site on the Site Identified Identified Identified
Hope Creek, Unit 1 Table 1. Current Design Basis Flood Hazards for Use in the MSA Mechanism Stillwater Waves/ Design Basis Reference ***----i Elevation Run up Hazard Elevation I Channel Migrations/Diversions No Impact No Impact No Impact FHRR Section 1.2.8 on the Site on the Site on the Site Identified Identified Identified Note 1: Reported values are rounded to the nearest one-tenth of a foot.
Note 2: Based on the NRG staff's independent (deterministic) hazard assessment using present-day regulatory guidance and methodologies of storm surge, the staff concludes that the site's current design basis remains bounded. For this reason, the staff concludes it is appropriate to utilize the current design basis storm surge elevation in conjunction with the mitigating strategies assessment.
Hope Creek, Unit 1 Table 2. Reevaluated Flood Hazards for Flood-Causing Mechanisms for Use in the MSA I !
Mechanism Stillwater I I Waves/ Reevaluated i i Reference I
Elevation Run up Hazard I I
Elevation II I
Local Intense Precipitation 12.8 ft Minimal 12.8ft FHRR Section 3.1 NAVD88 NAVD88 I
I I
j Note 1: The licensee is expected to develop flood event duration parameters and applicable flood associated effects to conduct the MSA. The staff will evaluate the flood event duration parameters (including warning time and period of inundation) and flood associated effects during its review of the MSA.
Note 2: Reevaluated hazard mechanisms bounded by the current design basis (see Table 1) are not included in this table.
Note 3: Reported values are rounded to the nearest one-tenth of a foot.
PKG ML152388660; LTR: ML152388655; ENCL: ML15243A502 *via email OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRO/DSEA/RHM1/TR* NRO/DSEA/RHM1/TL*
NAME TGovan Slent MLee KErwin DATE 09/02/15 09/01/15 09/09/15 09/09/15 OFFICE NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME MShams TGovan DATE 09/10/15 09/10/15