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| | number = ML063390090 | | | number = ML063390090 |
| | issue date = 12/15/2006 | | | issue date = 12/15/2006 |
| | title = Hope Creek Generating Station - Final Accident Sequence Precursor Analysis of October 10, 2004 Operational Event | | | title = Final Accident Sequence Precursor Analysis of October 10, 2004 Operational Event |
| | author name = Bailey S N | | | author name = Bailey S |
| | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 | | | author affiliation = NRC/NRR/ADRO/DORL/LPLI-2 |
| | addressee name = Levis W | | | addressee name = Levis W |
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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] Category:Operating Report
MONTHYEARLR-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-N19-0093, 2019 Annual 10 CFR 50.46 Report2019-09-25025 September 2019 2019 Annual 10 CFR 50.46 Report LR-N19-0003, Report of Changes, Tests, and Experiments2019-01-29029 January 2019 Report of Changes, Tests, and Experiments LR-N18-0136, Report of 10 CFR 72.48 Changes, Tests, and Experiments2018-12-0505 December 2018 Report of 10 CFR 72.48 Changes, Tests, and Experiments LR-N13-0210, Annual 10 CFR 50.46 Report2013-09-10010 September 2013 Annual 10 CFR 50.46 Report LR-N08-0221, Submittal of Report Changes in the Application of Emergency Core Cooling System Evaluation Models as Required by 10 CFR 50.462008-09-26026 September 2008 Submittal of Report Changes in the Application of Emergency Core Cooling System Evaluation Models as Required by 10 CFR 50.46 ML0633900902006-12-15015 December 2006 Final Accident Sequence Precursor Analysis of October 10, 2004 Operational Event 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 ML0535702262005-12-15015 December 2005 November 2005 Monthly Operating Report for Hope Creek LR-N05-0197, Report of Changes, Tests and Experiments2005-03-31031 March 2005 Report of Changes, Tests and Experiments 2023-02-28
[Table view] |
Text
December 15, 2006Mr. William LevisSenior Vice President & Chief Nuclear Officer PSEG Nuclear LLC - N09 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
HOPE CREEK GENERATING STATION - FINAL ACCIDENT SEQUENCEPRECURSOR ANALYSIS OF OCTOBER 10, 2004, OPERATIONAL EVENT
Dear Mr. Levis:
The enclosure provides the final results of the Accident Sequence Precursor (ASP) analysis ofan event which occurred at the Hope Creek Generating Station (Hope Creek) as documented in Licensee Event Report 354/04-010. The subject event occurred on October 10, 2004, when a pipe failure occurred in a moisture separator reheater drain line, leading to a manual reactor scram and plant cooldown. The ASP analysis calculated a mean conditional core damage probability of 3.4 x 10
-6.The Nuclear Regulatory Commission (NRC) established the ASP Program in 1979 in responseto the Risk Assessment Review Group Report (see NUREG/CR-0400, dated September 1978).
The ASP Program systematically evaluates U.S. nuclear power plant operating experience to identify, document, and rank the operating events that were most likely to have led to inadequate core cooling and severe core damage (precursors), accounting for the likelihood of additional failures.The ASP Program has the following objectives:
- Provide a measure for trending nuclear power plant core damage risk.
- Provide a partial check on dominant core damage scenarios predicted by probabilisticrisk assessments (PRAs).*Provide feedback to regulatory activities.
- Evaluate the adequacy of NRC programs.The NRC also uses the ASP Program to monitor performance against the safety goalestablished in the agency's Strategic Plan (see NUREG-1100, Vol. 21, dated February 2005). For more information about the ASP program, see the annual ASP program report athttp://www.nrc.gov/reading-rm/doc-collections/commission/secys/2005/secy2005-0192/2005-0192scy.pdf.
W. Levis-2-The enclosure is provided for your information and no response is requested. If you have anyquestions about the analyses, please contact me at (301) 415-1321 or at snb@nrc.gov.Sincerely,/RA/Stewart N. Bailey, Senior Project ManagerPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-354
Enclosure:
Final ASP Analysiscc w/encl: See next page
ML063390090OFFICELPL1-2/PMLPL1-2/LALPL1-2/BCNAMESBaileyCRaynorHChernoffDATE12/31/0612/13/0612/15/06 Hope Creek Generating Station cc:
Mr. Dennis WinchesterVice President - Nuclear Assessments PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George P. BarnesSite Vice President - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. George H. GellrichPlant Support Manager PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Michael J. MassaroPlant Manager - Hope Creek PSEG Nuclear P.O. Box 236 Hancocks Bridge, NJ 08038Mr. James MallonManager - Licensing 200 Exelon Way - KSA 3-E Kennett Square, PA 19348Jeffrie J. Keenan, EsquirePSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038Mr. Michael JesseManager - Regulatory Assurance P.O. Box 236 Hancocks Bridge, NJ 08038Township ClerkLower Alloways Creek Township Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038Mr. Paul Bauldauf, P.E., Asst. DirectorRadiation Protection Programs NJ Department of Environmental Protection and Energy
CN 415 Trenton, NJ 08625-0415Mr. Brian BeamBoard of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102Regional Administrator, Region IU.S. Nuclear Regulatory Commission
475 Allendale Road King of Prussia, PA 19406Senior Resident InspectorHope Creek Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038
SUMMARY
OF FINAL ACCIDENT SEQUENCE PRECURSOR ANALYSISPIPE FAILURE AND SCRAM ON OCTOBER 10, 2004HOPE CREEK GENERATING STATIONPSEG NUCLEAR LLCManual reactor scram due to moisture separator reheater drain line failure at Hope Creek(October 2004). This event is documented in Licensee Event Report LER 354/04-010, datedDecember 9, 2004.The Region I office of the Nuclear Regulatory Commission conducted a Special Inspection andissued Inspection Report (IR) 05000354/2004013 on February 4, 2005. A Notice of Violation was issued for this event under EA-05-001 on February 28, 2005. Event summary. On October 10, 2004, at 17:39 hours, a pipe failure occurred in a moistureseparator reheater drain line of the Hope Creek Nuclear Generating Station. A power reduction to 80-percent power was initiated at 17:59 hours due to reports of a steam leak in the turbine building. At 18:14 hours, the reactor recirculation pumps were reduced to minimum speed and the reactor was manually scrammed. Operators initially began to reduce the reactor pressure vessel (RPV) pressure using the turbine bypass valves to allow for use of the condensate and feedwater pumps for RPV makeup. Due to the continued degradation of condenser vacuum, the reactor feedwater pumps all tripped. At this point, RPV makeup and pressure control was provided by manually initiating the high pressure coolant injection (HPCI) and reactor core isolation cooling (RCIC) systems. At 18:17 hours, the control room supervisor directed the reactor operator to close the turbine bypass valves. As the bypass valves closed, RPV level decreased causing an isolation signal.With the RCIC system injecting into the RPV and water levels trending upwards, HPCI injectionwas terminated. Condenser vacuum continued to degrade and operators manually closed the main steam isolation valves (MSIVs) and main steam line drain valves prior to automatic closure on low condenser vacuum. Following MSIV closure, HPCI was placed in the pressure control mode. While placing HPCI in the pressure control mode, operators were initially unable to open the HPCI full-flow test line motor-operated valve. At 18:31 hours, the A and B residual heat removal trains were placed in the suppression pool cooling mode. At 18:46 hours, RPV level dropped and the RPV Level 3 scram setpoint was again actuated. RCIC flow was manually increased to restore water levels above the RPV Level 3 scram setpoint. Following this, at approximately 18:50 hours, the feedwater system was restarted (with flow being provided by the condensate pumps) with the startup feedwater level control valve set in the automatic mode.At 20:48 hours, the operators commenced a plant cooldown using HPCI, RCIC, andsafety/relief valves (SRVs). This effort was complicated by repeated trips of the HPCI barometric vacuum pump, a non-safety support system which maintains a slight vacuum on the HPCI steam discharge line. This led operators to secure the HPCI system and rely on a combination of SRVs and RCIC to maintain RPV level and depressurize the system. At approximately 22:03 hours, the Level 3 setpoint was again reset and feedwater startup levelEnclosure control valve setpoint raised from 25 inches to 35 inches (with flow being provided by thecondensate pumps). The plant reached cold shutdown conditions at 05:09 hours on October 12, 2004.Results. This initiating event resulted in a conditional core damage probability (CCDP) of3.4x10-6. An uncertainty analysis for this operating condition resulted in a mean CCDP of3.4x10-6 with 5% and 95% uncertainty bounds of 4.7x10
-8 and 1.2x10
-5, respectively.SDP/ASP comparison. The result of the Significance Determination Process (SDP) analysiswas a White finding. The White finding was based on a SDP Phase 3 assessment assuming an unavailability of 25 days and an estimated increase in core damage frequency (CDF) of1.8x10-6 for internal events. Since the SDP did a CDF calculation and the AccidentSequence Precursor (ASP) analysis did an initiating event assessment (i.e., calculated the CCDP), the two analytic results are not numerically comparable. The analytic assumptions and dominant risk contributors are similar in the two analyses.The ASP analysis can be found in the Agencywide Documents Access and ManagementSystem at Accession number ML062710037. If you have any questions about the analysis, please contact Gary DeMoss (301-415-6225).