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Category:Letter
MONTHYEARIR 05000272/20240032024-10-30030 October 2024 Integrated Inspection Report 05000272/2024003 and 05000311/2024003 ML24296B1932024-10-23023 October 2024 Project Manager Assignment ML24295A3742024-10-23023 October 2024 Project Manager Assignment IR 05000354/20240032024-10-23023 October 2024 Integrated Inspection Report 05000354/2024003 LR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024 Core Operating Limits Report - Cycle 28 ML24291A0572024-10-17017 October 2024 License Amendment Request (LAR) – Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 1 LR-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-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24267A1082024-09-23023 September 2024 Submittal of the Reactor Vessel Material Surveillance Program Capsule Technical Report IR 05000272/20244022024-09-23023 September 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Security Baseline Inspection Report 05000354/2024402, 05000272/2024402, and 05000311/2024402 (Cover Letter Only) ML24255A8042024-09-11011 September 2024 Notification of Conduct of a Fire Protection Team Inspection LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities 05000354/LER-2024-001-01, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement2024-09-0505 September 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) Supplement ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000354/20240052024-08-29029 August 2024 Updated Inspection Plan for Hope Creek Generating Station (Report 05000354/2024005) IR 05000272/20240052024-08-29029 August 2024 Updated Inspection Plan for Salem Nuclear Generating Station, Units 1 and 2 (Report 05000272/2024005 and 05000311/2024005) LR-N24-0044, Relief Request VR-042024-08-0606 August 2024 Relief Request VR-04 IR 05000354/20240022024-07-30030 July 2024 Integrated Inspection Report 05000354/2024002 IR 05000272/20240022024-07-30030 July 2024 Integrated Inspection Report 05000272/2024002 and 05000311/2024002 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 ML24200A0572024-07-18018 July 2024 Request for Withholding Information from Public Disclosure for License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves NUREG-1433, – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 52024-07-16016 July 2024 – Acceptance of License Amendment Request Concerning Technical Specification Conversion to NUREG-1433, Revision 5 ML24197A0552024-07-15015 July 2024 Requalification Program Inspection ML24145A1772024-07-15015 July 2024 And Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 236, 349, and 331 Modify Exclusion Area Boundary 05000354/LER-2024-001, Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT)2024-07-0202 July 2024 Invalid Primary Containment Integrated Leak Rate As-Found Test (ILRT) LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024 License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves IR 05000272/20245012024-06-12012 June 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Emergency Preparedness Biennial Exercise Inspection Report 05000354/2024501, 05000272/2024501 and 05000311/2024501 ML24099A1572024-05-29029 May 2024 Issuance of Amendment Nos. 348 and 330 Permanent Extension of Type a and Type C Containment Leak Rate Test Frequencies ML24150A0032024-05-28028 May 2024 Request for Exemptions from 10 CFR 50.82(a)(8)(i)(A) and 10 CFR 50.75(h)(1)(iv) and Proposed Amendment to the Decommissioning Trust Agreement ML24150A1002024-05-28028 May 2024 Core Operating Limits Report, Reload 25, Cycle 26, Revision 23 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-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024 License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle ML24142A4072024-05-20020 May 2024 License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5 IR 05000272/20240102024-05-16016 May 2024 Fire Protection Team Inspection Report 05000272/2024010 and 05000311/2024010 05000272/LER-2024-001, 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 IR 05000354/20240012024-05-0808 May 2024 Integrated Inspection Report 05000354/2024001 IR 05000354/20240102024-05-0707 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000354/2024010 IR 05000272/20240012024-05-0707 May 2024 Integrated Inspection Report 05000272/2024001 and 05000311/2024001 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-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024 2023 Annual Radioactive Effluent Release Report (ARERR) LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024 2023 Annual Radiological Environmental Operating Report (AREOR) 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 IR 05000354/20243012024-04-10010 April 2024 Initial Operator Licensing Examination Report 05000354/2024301 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 IR 05000272/20240112024-04-0101 April 2024 And Salem Nuclear Generating Station, Units 1 and 2 - Plant Modification and Annual Problem Identification and Resolution Inspection Report 05000354/2024011, 05000272/2024011, and 05000311/2024011 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 IR 05000272/20244032024-03-20020 March 2024 And Hope Creek Generating Station - Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000272/2024403, 05000311/2024403, and 05000354/2024403 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 05000354/LER-2023-003-01, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram 2024-09-05
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See also: IR 05000272/2012201
Text
SAFEGUARDS INFORMATION
December 19, 2011
EA-11-269
Mr. Thomas Joyce, President and CNO
PSEG Nuclear, LLC
P.O. Box 236 N-09
Hancocks Bridge, NJ 08038
SUBJECT: NRC SECURITY INSPECTION REPORT 05000272/2012201,
05000311/2012201 AND 05000354/2012201; PRELIMINARY
GREATER-THAN-GREEN FINDING, SALEM AND HOPE CREEK NUCLEAR
GENERATING STATIONS
Dear Mr. Joyce:
This letter transmits a finding that has preliminarily been determined to be Greater-than-Green
(i.e., a finding of greater than very low safety significance) that may result in the need for further
evaluation to determine significance, and therefore the need for additional U.S. Nuclear
Regulatory Commission (NRC) action. The finding is described in the enclosed inspection
report. The finding assessed is based on the best available information using the Physical
Security Significance Determination Process (SDP).
The licensee promptly implemented compensatory measures for the deficiency, and the site
was in compliance with applicable physical protection and security requirements within the
scope of the inspection before the inspectors left the site. The finding is also an apparent
violation of NRC requirements and is being considered for escalated enforcement action in
accordance with the Enforcement Policy, which can be found on the NRCs website at
http://www.nrc.gov/reading-rm/doc-collections/enforcement.
In accordance with NRC Inspection Manual Chapter (IMC) 0609, we intend to complete our
evaluation using the best available information and issue our final determination of safety
significance within 90 days of the date of this letter. The SDP encourages an open dialogue
between the NRC staff and the licensee, however, the dialogue should not impact the
timeliness of the staffs final determination.
Before we make our final significance determination, we are providing you with an opportunity
to attend a Regulatory Conference where you can present to the NRC your perspective on the
facts and assumptions the NRC used to arrive at the finding and assess its significance. The
Regulatory Conference will be held within 30 days of the receipt of this letter and we encourage
you to submit supporting documentation at least 1 week prior to the conference in an effort to
make the conference more efficient and effective. In the interest of protecting sensitive,
The enclosure transmitted herewith contains Safeguards Information. When separated from
the enclosure, this transmittal document is decontrolled.
SAFEGUARDS INFORMATION
SAFEGUARDS INFORMATION
T. Joyce -2-
security-related information, the Regulatory Conference will not be open for public observation.
If you decline to participate in a Regulatory Conference, you relinquish your right to appeal the
final SDP determination, in that, you fail to meet the appeal requirements stated in the
Prerequisite and Limitation sections of Attachment 2 of IMC 0609.
Please contact Mr. Robert C. Johnson, Branch Chief, at (301) 415-6640 and in writing within 10
business days from the issue date of this letter to notify the NRC of your intentions. If we have
not heard from you within 10 business days, we will continue with our significance determination
and enforcement decision. The final resolution of this matter will be conveyed in a separate
correspondence.
Because the NRC has not made a final determination in this matter, no Notice of Violation is
being issued for this inspection finding at this time. In addition, please be advised that the
number and characterization of the apparent violation described in the enclosed inspection
report may change as a result of further NRC review.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390 of the NRC's
"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 component of NRC's
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 Safeguards Information as defined by
10 CFR 73.21 and its disclosure to unauthorized individuals is prohibited by Section 147 of the
Atomic Energy Act of 1954, as amended. 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 website at
http://www.nrc.gov/reading-rm/adams.html. If Safeguards Information is necessary to provide
an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Otherwise, if Security-Related Information is necessary to provide an acceptable response,
please mark your entire response Security-Related Information in accordance with
SAFEGUARDS INFORMATION
SAFEGUARDS INFORMATION
T. Joyce -3-
10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In
accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your
response.
Sincerely,
/RA/
James W. Clifford, Acting Director
Division of Security Operations
Office of Nuclear Security and Incident Response
Docket Nos.: 50-272, 50-311, and 50-354
License Nos.: DPR-70, DPR-75, and NPF-57
Enclosure: Inspection Report No. 05000272/2012201; 05000311/2012201; and
05000354/2012201
cc w/encl: M. Bruecks, 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
SAFEGUARDS INFORMATION
SAFEGUARDS INFORMATION
T. Joyce -3-
10 CFR 2.390(d)(1) and follow the instructions for withholding in 10 CFR 2.390(b)(1). In
accordance with 10 CFR 2.390(b)(1)(ii), the NRC is waiving the affidavit requirements for your
response.
Sincerely,
/RA/
James W. Clifford, Acting Director
Division of Security Operations
Office of Nuclear Security and Incident Response
Docket Nos.: 50-272, 50-311, and 50-354
License Nos.: DPR-70, DPR-75, and NPF-57
Enclosure: Inspection Report No. 05000272/2012201; 05000311/2012201; and
05000354/2012201
cc w/encl: M. Bruecks, 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
HARD COPY W/ ENCL
D. Brady, NSIR SLES
ADAMS ACCESSION NO.: ML11342A013
OFFICE NSIR/DSO/SPEB TL:DSO/SPEB RI NSIR/DSO/SPEB NSIR/DDSO NSIR/DSO
NAME C. Grigsby K. Brooks J. Trapp R. Johnson B. Westreich J. Clifford
DATE 12/9/11 12/9/11 12/8/11 12/15/11 12/16/11 12/19/11
OFFICIAL RECORD COPY
SAFEGUARDS INFORMATION