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Category:Letter
MONTHYEARIR 05000272/20230042024-02-0505 February 2024 Integrated Inspection Report 05000272/2023004 and 05000311/2023004 ML24030A8752024-02-0101 February 2024 Operator Licensing Examination Approval IR 05000354/20230042024-02-0101 February 2024 Integrated Inspection Report 05000354/2023004 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 05000272/20234012024-01-22022 January 2024 Material Control and Accounting Program Inspection Report 05000272/2023401 and 05000311/2023401 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 ML24004A1542024-01-0808 January 2024 Notification of Conduct of a Fire Protection Team Inspection ML23307A1532023-12-15015 December 2023 NRC Investigation Report No. 1-2023-001 ML23335A1122023-12-15015 December 2023 Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers 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 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 05000272/20230032023-11-13013 November 2023 Integrated Inspection Report 05000272/2023003 and 05000311/2023003 IR 05000354/20230032023-11-0707 November 2023 Integrated Inspection Report 05000354/2023003 LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023 Core Operating Limits Report Cycle 30 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) IR 05000272/20230102023-10-12012 October 2023 Biennial Problem Identification and Resolution Inspection Report O5000272/2023010 and 05000311/2023010 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 05000272/20230052023-08-31031 August 2023 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Reports 05000272/2023005 and 05000311/2023005) IR 05000354/20230052023-08-31031 August 2023 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2023005) ML23233A0762023-08-21021 August 2023 Requalification Program Inspection 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 05000272/20230022023-08-0909 August 2023 Integrated Inspection Report 05000272/2023002 and 05000311/2023002 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 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-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023 In-Service Inspection Activities 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 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 ML23139A1472023-06-0505 June 2023 Relief Request Associated with Fourth Interval In-service Inspection Limited Examinations of Weld Coverage ML23096A1842023-05-0909 May 2023 Issuance of Amendment No. 328 Revise and Relocate Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to Pressure and Temperature Limits Report IR 05000272/20230012023-05-0303 May 2023 Integrated Inspection Report 05000272/2023001 and 05000311/2023001 ML23081A4662023-05-0202 May 2023 Issuance of Amendment Nos. 346 and 327 Revise Technical Specifications to Extend Allowable Outage Time for Inoperable Emergency Diesel Generator IR 05000272/20233012023-05-0101 May 2023 Initial Operator Licensing Examination Report 05000272/2023301 and 05000311/2023301 ML23121A1412023-05-0101 May 2023 Senior Reactor and Reactor Operator Initial License Examinations IR 05000354/20230112023-05-0101 May 2023 Commercial Grade Dedication Report 05000354/2023011 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 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 2024-02-05
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Text
rch 20, 2012
SUBJECT:
FINAL SIGNIFICANCE DETERMINATION FOR A SECURITY- RELATED GREATER-THAN-GREEN FINDING AND NOTICE OF VIOLATION; 05000272/2012201, 05000311/2012201, 05000354/2012201 SALEM AND HOPE CREEK NUCLEAR GENERATING STATIONS
Dear Mr. Joyce:
This letter provides you the final results of our significance determination of the preliminary Greater-than-Green finding identified in our previous communication dated December 19, 2011, which included the subject inspection report. This Greater-than-Green finding was discussed in detail in Section 3.4 of the subject inspection report.
At your request, a Regulatory Conference was held on February 6, 2012, to further discuss your views on this issue. During the meeting, your staff described your assessment of the significance of the finding, including the root cause, and corrective actions taken to resolve it.
After considering the information developed during the inspection, the additional information you provided in your letter dated February 21, 2012, and the information you provided at the Regulatory Conference, the U.S. Nuclear Regulatory Commission (NRC) has concluded that the inspection finding is appropriately characterized as Greater-than-Green (i.e., a finding having more than very low security significance). The finding also had a cross-cutting aspect in the area of Problem Identification and Resolution because licensee personnel failed to conduct an adequate effectiveness review (P.1(c)). The basis for the NRCs significance determination is provided, along with an evaluation of the position presented by Salem and Hope Creek at the February 6, 2012, Regulatory Conference, in Enclosure 2.
The enclosures transmitted herewith contain Official Use Only - Security-Related Information. When separated from the enclosures, this transmittal document is decontrolled.
OFFICAL USE ONLY OFFICAL USE ONLY You have 30 calendar days from the date of this letter to appeal the staff's determination of significance for the identified Greater-than-Green finding. Such appeals should be addressed to the U.S. Nuclear Regulatory Commission, ATTN: Director, Office of Nuclear Security and Incident Response, Washington, DC 20555-0001 and will be considered to have merit only if they meet the criteria given in the NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC has also determined that the condition discussed is a violation of Title 10 of the Code of Federal Regulations (10 CFR) 73.55(i)(5)(iii), as cited in the enclosed Notice of Violation (Notice, Enclosure 1). In accordance with the NRC Enforcement Policy, the Notice is considered escalated enforcement action because it is associated with a Greater-than-Green finding.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response.
Because plant performance for this issue has been determined to be beyond the licensee response band, we will use the NRCs Security Action Matrix to determine the most appropriate NRC response for this event. We will notify you, by separate correspondence, of that determination.
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
However, the material enclosed herewith contains Security-Related Information in accordance with 10 CFR 2.390(d)(1) and its disclosure to unauthorized individuals could present a security vulnerability. Therefore, the material in the enclosure will not be made available electronically for public inspection in the NRC Public Document Room or from the NRC's document system ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. If security-related information is necessary to provide an acceptable response, please mark your entire response Security-Related Information in accordance with 10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1).
OFFICAL USE ONLY OFFICAL USE ONLY In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Patricia K. Holahan, Director Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-354, 50-272, and 50-311 License Nos. DPR-70, DRP-75, and NPF-57 Enclosures:
1. Notice of Violation (OUO-SRI)
2. Evaluation of Regulatory Conference Information (OUO-SRI)
cc w/encl: P. Tocci, Salem and Hope Creek Nuclear Generating Stations cc w/o encl: C. Fricker, PSEG Nuclear, LLC J. Perry, PSEG Nuclear, LLC P. Duke, PSEG Nuclear, LLC OFFICAL USE ONLY OFFICAL USE ONLY In accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your response.
Sincerely,
/RA/
Patricia K. Holahan, Director Division of Security Operations Office of Nuclear Security and Incident Response Docket Nos. 50-354, 50-272, and 50-311 License Nos. DPR-70, DRP-75, and NPF-57 Enclosures:
1. Notice of Violation (OUO-SRI)
2. Evaluation of Regulatory Conference Information (OUO-SRI)
cc w/encl: P. Tocci, Salem and Hope Creek Nuclear Generating Stations cc w/o encl: C. Fricker, PSEG Nuclear, LLC J. Perry, PSEG Nuclear, LLC P. Duke, PSEG Nuclear, LLC DISTRIBUTION W/O ENCL:
H. Harrington, OPA N. Sheehan, OPA N. McNamara, RI D. Screnci, OPA D. Tifft, RI DISTRIBUTION W/ENCL:
J. Trapp, RI B. Desai, RII R. Skokowski, RIII M. Hay, RIV HARDCOPY W/ENCL:
D. Brady, SPEB ADAMS ACCESSION NO.: ML120670585 (Package)
OFFICE NSIR/DSO/SPEB NSIR/DSO/SPEB RI OE BC:DSO/SPEB NSIR/DSO NAME CGrigsby KBrooks C. Miller D. Furst RJohnson PHolahan DATE 3/9/12 3/8/12 3/ /12 3/13/12 via 3/9/12 3/20/12 E-mail OFFICIAL RECORD COPY OFFICAL USE ONLY