Similar Documents at Salem |
---|
Category:Letter type:LR
MONTHYEARLR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024 Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024 Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response LR-N24-0038, Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger2024-05-0909 May 2024 Pressure Boundary Leakage Through a Reactor Coolant Pump Thermal Barrier Heat Exchanger LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024 Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024 Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024 Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024 and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024 and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024 Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024 Spent Fuel Cask Registration LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024 In-Service Inspection Activities LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023 Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 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 LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023 Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023 Emergency Plan Document Revisions Implemented June 28, 2023 LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023 License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report (ARERR) 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-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023 Core Operating Limits Report Cycle 27 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-N23-0006, 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 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 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-N23-0012, 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 LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023 Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211 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-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022 LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022 Emergency Plan Document Revisions Implemented November 21, 2022 LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022 Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG 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 LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022 Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095) LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022 Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022 Emergency Plan Evacuation Time Estimate LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022 License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM) LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022 Spent Fuel Cask Registration LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022 License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022 Spent Fuel Cask Registration LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022 License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022 License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022 Emergency Plan Document Revisions Implemented November, 2021 LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022 Core Operating Limits Report - Cycle 29 2024-07-24
[Table view] Category:Licensee Response to Notice of Violation
[Table view] |
Text
William Levis P. 0. Box 236, Hancocks Bridge, NJ 08038 President and CNO tel: 856.339.1100 fax: 856.339.1104 email: wifliam~levis@pseg.com OPSEG NuclearL. L. C.
March 7, 2007 LR-N07-0044 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Nuclear Generating Station Units 1 and 2 Facility Operating License Nos. DPR-50 and 75 NRC Docket Nos. 50-272 and 50-311
Subject:
Reply to Notice of Violation EA-06-205 On January 25, 2007, the NRC issued a Notice of Violation (NOV) to PSEG Nuclear (PS EG) concerning events surrounding a service water accumulator overpressure condition on July 3, 2003. The reply due date of this NOV was extended to March 7, 2007 per conversation between Mr. Steve Mannon of my staff and Mr. Arthur Burritt, Chief Reactor Projects Branch 3 Division of Reactor Projects. Attachment 1 to this letter contains the violation as cited in the EA-06-205 and Attachment 2 provides PSEG's response to that NOV.
Should you have any questions concerning this submittal, please contact J. Keenan at 856-339-5429.
Sincerely, CzQQ Attachments (2)
MAR07200 Document Control Desk LR-N07-0044 Mr. Samuel Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 USNRC Senior Resident Inspector - Hope Creek (X24)
USNRC Resident Inspector Office - Salem (X24)
Mr. R. Ennis, Project Manager - Hope Creek and Salem U. S. Nuclear Regulatory Commission Mail Stop 08132 11555 Rockville Pike Rockville, MD 20852 Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P.O0. Box 415 Trenton, NJ 08625 LR-N07-0044
- 1. VIOLATION 10 CFR-50.9(a) requires, in part, that information required by license conditions to be maintained by the licensee shall be complete and accurate in all material respects.
10 CFR Part 50, Appendix B, Criterion XVI, "Corrective Action,"
requires, in part, that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
Public Service Enterprise Group (PSEG) Procedure NC.WM-AP.ZZ-0000(Q), "Notification Process," Revision 6, dated June 24, 2003, Section 3.1, required PSEG personnel to identify and document a condition adverse to quality in the corrective action program by using a notification. Section 7.2 of this-procedure defined a condition adverse to quality, in part, as a condition that has the potential to affect a safety-related function of systems, structures, or components.
Contrary to the above, on July 3, 2003, PSEG personnel did not promptly identify a condition adverse to quality that had the potential to affect a safety-related function of the service water system when a system valve alignment error led to the 12 service water accumulator pressure exceeding limits specified in Technical Specification 3.6.1.1. Specifically, a gas charging valve was inadvertently left open (misaligned) after a work task causing the accumulator pressure to exceed the technical specification limits for the system. The failure to identify the condition adverse to quality was (1) a result of the nuclear equipment operators, who identified the valve misalignment, providing incomplete and inaccurate information to control room personnel regarding the accumulator maximum pressure and the cause of the valve misalignment and (2) a failure by the control room supervisor to recognize the condition adverse to quality based on personal knowledge of the work task and the information provided by the equipment operators, even though some incomplete or inaccurate information was described. Neither the equipment operators nor the control room supervisor ensured that this condition adverse to quality was promptly identified and corrected by documenting the condition using a notification report.
This is a Severity Level IV violation (Supplement 1).
1 LR-N07-0044 Il. PSEG REPLY TO THE VIOLATION 1.- Admission or Denial of the Alleged Violation:
PSEG admits the alleged violation.
- 2. Reason(s) For The Alleged Violation:
PSEG performed an extensive and comprehensive investigation immediately upon learning of the event. PSEG determined that less than adequate human performance standards by the employees, including inadequate personal responsibility, accountability, and integrity directly resulted in the violation. Since the time of the event in 2003, PSEG has undertaken significant efforts to improve site human performance, including putting in place the proven Fundamentals Tool Kit that has been successfully implemented at other Exelon sites. These efforts have improved individual performance at the station.
PSEG would like to make one clarification regarding notifying the NRC of the accumulator overcharging event. The NRC noted in the NOV that PSEG "did not inform the NRC of the occurrence when it was finally identified." Once PSEG became aware of the event, an extensive investigation was initiated. PSEG's
.investigation was actively proceeding when identified by the NRC, and relevant information was unavailable because interviews of key witnesses were significantly delayed due to witness unavailability and coordination with witness counsel. Once PSEG efforts were completed, the company fully and completely cooperated with the NRC Office of Investigation, including supplying all requested reports and files associated with this matter.
- 3. Corrective Steps That Have Been Taken and the Results Achieved:
PSEG promptly initiated a comprehensive investigation immediately upon learning of the July 3, 2003 service water accumulator incident. At the conclusion of that investigation, PSEG took significant remedial action, commensurate with the circumstances to prevent recurrence.
Numerous improvements in the Corrective Action Program.(CAP) have taken place since this event occurred in 2003. Though the overpressurization issue was not entered into the CAP at the time, reviews performed since this event have confirmed that station personnel have app Iropriate knowledge of the CAP and enter identified problems into the program at a low threshold.
1 LR-N07-0044
- 4. Corrective Steps To Avoid Further Violations:
No additional steps required.
- 5. Date When Full Compliance Will Be Achieved:
PSEG is in full compliance 2