IR 05000354/2025011
| ML25085A116 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  (NPF-057) |
| Issue date: | 03/26/2025 |
| From: | Erin Carfang Division of Operating Reactors |
| To: | Mcfeaters C Public Service Enterprise Group |
| References | |
| IR 2025011 | |
| Download: ML25085A116 (1) | |
Text
March 26, 2025
SUBJECT:
HOPE CREEK GENERATING STATION - LICENSE RENEWAL PHASE 2 INSPECTION REPORT 05000354/2025011
Dear Charles McFeaters:
On March 13, 2025, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Hope Creek Generating Station and discussed the results of this inspection with Eric Larson, Site Vice President, and other members of your staff. The results of this inspection are documented in the enclosed report.
No findings or violations of more than minor significance were identified during this inspection.
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Erin E. Carfang, Chief Engineering Branch 1 Division of Operating Reactor Safety
Docket No. 05000354 License No. NPF-57
Enclosure:
As stated
Inspection Report
Docket Number:
05000354
License Number:
Report Number:
Enterprise Identifier: I-2025-011-0008
Licensee:
Facility:
Hope Creek Generating Station
Location:
Hancocks Bridge, NJ
Inspection Dates:
February 24, 2025 to March 13, 2025
Inspectors:
N. Floyd, Senior Reactor Inspector
L. Cline, Senior Reactor Inspector
J. Cunningham, Reactor Inspector
K. Mangan, Senior Reactor Inspector
A. Patel, Senior Reactor Inspector
Approved By:
Erin E. Carfang, Chief
Engineering Branch 1
Division of Operating Reactor Safety
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting a license renewal phase 2 inspection at Hope Creek Generating Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors.
Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
OTHER ACTIVITIES
- TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
===71003 - Post-Approval Site Inspection for License Renewal
From February 24 to March 13, 2025, the NRC conducted a post-approval site inspection for License Renewal - Phase 2 at the Hope Creek Generating Station in accordance with the license renewal inspection program. This inspection took place prior to the period of extended operation (PEO), which will begin on April 12, 2026. Per IMC 2516, the license renewal inspection program is the process used by NRC staff to verify the adequacy of aging management programs (AMPs), time-limited aging analyses (TLAAs), and other activities associated with an applicants request to renew an operating license of a commercial nuclear power plant beyond the initial licensing period under 10 CFR 54, Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
Post-Approval Site Inspection for License Renewal===
- (1) License Conditions and Commitments for License Renewal, Implementation of Aging Management Programs and Time-Limited Aging Analyses
There are a total of 54 regulatory commitments linked to the renewed operating license for Hope Creek Generating Station, discussed in NUREG-2102, "Safety Evaluation Report Related to the License Renewal of Hope Creek Generating Station," issued in June 2011, consisting of the following: 17 commitments to enhance existing AMPs; 14 commitments to implement new AMPs; 16 commitments to implement existing AMPs; 6 commitments for TLAA activities; and 1 stand-alone commitment (not associated with an AMP or TLAA). During the inspection, the team reviewed 39 of these commitments in order to assess the adequacy and effectiveness of the license renewal program. For each commitment selected, the inspectors reviewed the applicable license renewal program documents, a sample of implementing procedures and records, conducted interviews with licensee staff, and performed walkdowns of structures, systems, and components (SSCs) to verify that the licensee completed the actions necessary to comply with the conditions listed in the renewed facility operating license. For those license renewal action items that were not completed at the time of this inspection, the team verified that there was reasonable assurance that such action items were on track for completion prior to the PEO or in accordance with an established implementation schedule consistent with the license renewal application, the NRC Safety Evaluation Report, and the Updated Final Safety Analysis Report (UFSAR) supplement.
The regulatory commitments selected for the inspection sample are listed below along with the completion status of the item at the time of the inspection. The full description of each commitment is available in the UFSAR supplement for license renewal, as revised, and the NRC Safety Evaluation Report (NUREG-2102).
Commitments (by number):
- Commitment #7: Enhance existing Boiling-Water Reactor Stress Corrosion Cracking Program. Status: Complete.
- Commitment #10: Develop and implement new Thermal Aging and Neutron Embrittlement of Cast Austenitic Stainless Steel Program. Status: Complete.
- Commitment #12: Enhance existing Bolting Integrity Program. Status:
Complete.
- Commitment #13: Implement existing Open-Cycle Cooling Water System Program. Status: Complete.
- Commitment #14: Enhance existing Closed-Cycle Cooling Water System Program. Status: Incomplete, one license renewal action item has not been completed. Specifically, the licensee plans on completing new recurring tasks to establish performance monitoring of the closed-cycle cooling and chilled water systems (Work Order (WO) 70237542) prior to PEO. Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #14.
- Commitment #15: Enhance existing Inspection of Overhead Heavy Load and Light Load (Related to Refueling) Handling Systems Program. Status:
Complete.
- Commitment #16: Implement existing Compressed Air Monitoring Program.
Status: Complete.
- Commitment #17: Enhance existing Fire Protection Program. Status:
Complete.
- Commitment #18: Enhance existing Fire Water System Program. Status:
Incomplete, some license renewal action items have not been completed.
Specifically, the licensee plans on completing a representative sample of the 50-year sprinkler head inspections and testing (WO 80126117) prior to PEO.
Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #18.
- Commitment #19: Enhance existing Aboveground Steel Tanks Program.
Status: Incomplete, the action to complete the insulation removal and inspection of the external surfaces for both fire water storage tanks is incomplete and is scheduled to be completed in May 2025 (WOs 30360755 and 30360756). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #19.
- Commitment #20: Enhance existing Fuel Oil Chemistry Program. Status:
Complete.
- Commitment #21: Enhance existing Reactor Vessel Surveillance Program.
Status: Complete.
- Commitment #22: Develop and implement new One-Time Inspection Program. Status: Incomplete, some license renewal action items remained to be completed. Specifically, the licensee has scheduled 13 inspections for gray cast iron and stainless steel components in treated water environments to be completed during the Fall 2025 refueling outage (WOs 60157866, 60146359, 60146361, 60146360, 60146364, 60146363, 60146362, 60146095, 60146094, 60146096, 60146200, 60146098, and 601462939). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #22.
- Commitment #23: Develop and implement new Selective Leaching of Materials Program. Status: Incomplete, some license renewal action items have not been completed. Specifically, the licensee plans on completing the required selective leaching examinations on 1A-P-206, A core spray pump (WO 60157866), 1EAV-552, service water loss of offsite power A emergency makeup downstream isolation valve (WO 60134925), and A reactor auxiliary cooling system pump (WO 60162023) prior to the PEO. Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #23.
- Commitment #24: Enhance existing Buried Piping Inspection Program. Status:
Complete.
- Commitment #25: Develop and implement new External Surfaces Monitoring Program. Status: Incomplete, one outstanding action remains to address industry operating experience by revising applicable program maintenance plans to include periodic inspections of piping under insulation susceptible to corrosion (Procedure Change Requests 70228878-010 and 24-000512).
Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #25.
- Commitment #26: Develop and implement new Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program. Status: Complete.
- Commitment #27: Implement existing Lubricating Oil Analysis Program.
Status: Complete.
- Commitment #28: Enhance existing American Society of Mechanical Engineers,Section XI, Subsection IWE Program. Status: Complete.
- Commitment #30: Implement existing 10 CFR 50, Appendix J Program.
Status: Complete.
- Commitment #31: Enhance existing Masonry Wall Program. Status:
Complete.
- Commitment #32: Enhance existing Structures Monitoring Program. Status:
Complete.
- Commitment #33: Enhance existing Regulatory Guide 1.127, Inspection of Water-Control Structures Program. Status: Complete.
- Commitment #35: Develop and implement new Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program. Status: Complete.
- Commitment #36: Develop and implement new Electrical Cables and Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Used in Instrumentation Circuits Program. Status: Complete.
- Commitment #37: Develop and implement new Inaccessible Medium Voltage Cables Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program. Status: Complete.
- Commitment #38: Develop and implement new Metal-Enclosed Bus Program.
Status: Incomplete, one license renewal action item remains to be completed.
Specifically, the licensee scheduled inspection of Section 02 of bus 10-A-109 to be completed during the Fall 2025 refueling outage (WO 30265465). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #38.
- Commitment #39: Develop and implement new Electrical Cables Connections Not Subject to 10 CFR 50.49 Environmental Qualification Requirements Program. Status: Complete.
- Commitment #40: Develop and implement new High Voltage Insulators Program. Status: Complete.
- Commitment #41: Develop and implement new Periodic Inspection Program.
Status: Incomplete, one license renewal action item remains to be completed.
Specifically, the licensee is in the process of visually inspecting the B emergency diesel generator exhaust silencer inlet (WO 30165031). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #41.
- Commitment #42: Develop and implement new Aboveground Non-Steel Tanks Program. Status: Complete.
- Commitment #43: Enhance existing Buried Non-Steel Piping Inspection Program. Status: Complete.
- Commitment #44: Enhance existing Boral Monitoring Program. Status:
Incomplete, one license renewal action item remains to be completed.
Specifically, the licensee is in the process of reviewing test results from initial boral coupon testing (WO 60156523). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #44.
- Commitment #45: Develop and implement new Small-Bore Class 1 Piping Inspection Program. Status: Incomplete, some license renewal action items have not been completed. Specifically, the licensee plans on completing the remaining socket weld inspections in the Fall 2025 refueling outage (WOs 60146359, 60146361, 60146360, 60146364, 60146363, 60146362, 60146095, 60146094, 60146096, 60146200, 60146098, 60146239, and 60161594). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #45.
- Commitment #46: Enhance existing Metal Fatigue of the Reactor Coolant Pressure Boundary Program. Status: Complete.
- Commitment #49: Request relief for reactor pressure vessel circumferential weld volumetric examinations (TLAA). Status: Incomplete, one license renewal action item remains to be completed. Specifically, the licensee performed the analysis related to circumferential welds relief request and plans to submit the request prior to April 11, 2025 (Order 80096881-5300), in accordance with 10 CFR 50.55(a). Based on the review of licensee actions completed at the time of this inspection and the administrative controls in place to track the pending actions, the inspectors determined that there was reasonable assurance that the licensee would complete the necessary actions to meet Commitment #49.
- Commitment #50: Operating Experience Review at Extended Power Uprate Conditions. Status: Complete.
- Commitment #51: Core Plate Rim Hold-Down Bolts (TLAA). Status: Complete.
- Commitment #54: Metal Fatigue of the Reactor Coolant Pressure Boundary (TLAA). Status: Complete.
- (2) Newly Identified Structures, Systems, and Components
The team discussed with the licensees staff their evaluations of newly identified SSCs to determine on a sampling basis compliance with the provisions of 10 CFR 54.37(b). The team reviewed licensee evaluations performed for newly identified structures within the scope of license renewal to verify that the aging management review was performed in accordance with 10 CFR 54.37. The team also reviewed a list of plant modifications performed from the time the license renewal application was submitted to the time the renewed operating license was issued, to identify any potentially new SSCs that would have been subject to aging management review at the time the NRC was reviewing the license renewal application. Additionally, the team reviewed a sample of licensee procedures to verify that adequate guidance was provided to ensure that SSCs within the scope of 10 CFR 54.37(b) were identified, evaluated, and reported.
- (3) Description of Aging Management Programs in the UFSAR Supplement
As part of the review of implementation activities for the selected AMPs, the team reviewed the corresponding UFSAR sections to verify that the program descriptions were consistent with the license renewal application and the corresponding section of the NRC Safety Evaluation Report. The team reviewed three versions of the UFSAR supplement for license renewal as follows:
- The team reviewed the UFSAR supplement submitted with the license renewal application, as revised, to identify the program attributes and future inspection activities that were originally relied upon for the approval of the renewed operating license.
- The team reviewed the revision of the UFSAR submitted to the NRC pursuant to the requirements in 10 CFR 50.71(e)(4) following the issuance of the renewed operating license to verify that the UFSAR supplement for license renewal was included with the UFSAR as required by the condition of the renewed operating license.
- The team reviewed the latest revision of the UFSAR supplement for license renewal to verify that the program attributes and inspection activities were consistent with the AMPs as originally approved by the NRC and subsequent revisions performed under the provisions of 10 CFR 50.59. The team also verified that any changes caused by the inclusion of newly identified SSCs were included in the UFSAR supplement.
- (4) Changes to License Renewal Commitments and the UFSAR Supplement for License Renewal
As part of the review of license renewal commitments, AMPs, and TLAAs described in this report, the inspectors reviewed license renewal commitment change documents to verify the licensee followed the guidance in Nuclear Energy Institute 99-04, Guidelines for Managing NRC Commitment Changes, for any change to the commitments, including their elimination. The team verified on a sampling basis that the licensee properly evaluated, reported, and approved where necessary, changes to license renewal commitments listed in the UFSAR in accordance with 10 CFR 50.59.
The renewed operating license for Hope Creek Generating Station, Condition 2.C.(24), states, in part, that the licensee may make changes to the programs and procedures described in the UFSAR supplement submitted with the license renewal application, as revised, provided the licensee evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
INSPECTION RESULTS
No findings were identified.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On March 13, 2025, the inspectors presented the license renewal phase 2 inspection results to Eric Larson, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
71003
Corrective Action
Documents
Resulting from
Inspection
20987217
20987275
20987413
20987456
20987457
20987458
20987459
20987461
20987467
20987537
20987587
20987588
20987593
20987596
20987597
20987598
20987721
20987722
20987778
20987779
20987781
20987782
20987783
20987784
20987785
20988023
20988058
20988080
20988084
20988135
20988136
Miscellaneous
- 07
License Renewal Results Book for BWR Stress Corrosion
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Cracking AMP
- 10
License Renewal Results Book for Thermal Aging Irradiation
Embrittlement of Cast Austenitic Stainless Steel AMP
Revision 0
- 12
License Renewal Results Book for Bolting Integrity AMP
Revision 0
- 13
License Renewal Results Book for Open-Cycle Cooling
Water System AMP
Revision 0
- 14
License Renewal Results Book for Closed-Cycle Cooling
Water System AMP
Revision 0
- 15
License Renewal Results Book for Overhead Heavy Load
and Light Load Handling Systems AMP
Revision 0
- 16
License Renewal Results Book for Compressed Air
Monitoring AMP
Revision 0
- 17
License Renewal Results Book for Fire Protection AMP
Revision 0
- 18
License Renewal Results Book for Fire Water System AMP
Revision 0
- 19
License Renewal Results Book for Aboveground Steel Tanks
Revision 0
- 20
Fuel Oil Chemistry AMP
Revision 0
- 21
License Renewal Results Book for Reactor Vessel
Surveillance AMP
Revision
- 22
License Renewal Results Book for One-Time Inspection
Revision 0
- 23
License Renewal Results Book for Selective Leaching of
Materials
Revision 0
- 24
License Renewal Results Book for Buried Piping Inspection
Revision 0
- 25
License Renewal Results Book for External Surfaces
Monitoring AMP
Revision 0
- 26
License Renewal Results Book for Inspection for Internal
Surfaces in Miscellaneous Piping and Ducting Components
Revision 0
- 27
License Renewal Results Book for Lubricating Oil Analysis
Revision 0
- 28
License Renewal Results Book for ASME Section XI
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
- 30
License Renewal Results Book for 10 CFR Part 50 Appendix J AMP
Revision 0
- 31
License Renewal Results Book for Masonry Wall AMP
Revision 0
- 32
License Renewal Results Book for Structures Monitoring
Program AMP
Revision 0
- 33
License Renewal Results Book for RG 1.127 Inspection of
Water-Control Structures AMP
Revision 0
- 35
License Renewal Results Book for Electrical Cables and
Connections Not Subject to 10 CFR 50.49 Environmental
Qualification Requirements AMP
Revision 0
- 36
License Renewal Results Book for Electrical Cables and
Connections Not Subject to 10 CFR 50.49 Environmental
Qualification Requirements Used in Instrumentation Circuits
Revision 0
- 37
License Renewal Results Book for Inaccessible Medium
Voltage Cables Not Subject to 10 CFR 50.49 Environmental
Qualification Requirements AMP
Revision 0
- 38
License Renewal Results Book for Metal-Enclosed Bus AMP
Revision 0
- 39
License Renewal Results Book for Electrical Cable
Connections Not Subject to 10 CFR 50.49 Environmental
Qualification
Requirements AMP
Revision 0
- 40
License Renewal Results Book for High Voltage Insulators
Revision 0
- 41
License Renewal Results Book for Periodic Inspection AMP
Revision 0
- 42
License Renewal Results Book for Aboveground Non-Steel
Tanks AMP
Revision 0
- 43
License Renewal Results Book for Buried Non-Steel Piping
Inspection AMP
Revision 0
- 44
License Renewal Results Book for Boral Monitoring AMP
Revision 0
- 45
License Renewal Results Book for Small-Bore Class 1 Piping
Inspection AMP
Revision 0
- 46
License Renewal Results Book for Metal Fatigue of the
Reactor Coolant Pressure Boundary AMP
Revision 0
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
- 49
License Renewal Results Book for Reactor Pressure Vessel
Circumferential Weld Volumetric Examinations TLAA
Revision 0
- 50
License Renewal Results Book for Operating Experience
Review at Extended Power Uprate Conditions
Revision 0
- 51
License Renewal Results Book for Core Plate Rim Hold-
Down Bolts TLAA
Revision 0
- 54
License Renewal Results Book for Metal Fatigue of the
Reactor Coolant Pressure Boundary TLAA
Revision 0
Procedures
Operating Experience Program
Revision 22
MA-AA-716-010-
1000
Maintenance Planning
Revision 19
Self-Assessments 80137455
License Renewal Program NRC Inspection Readiness FASA
11/27/2024
PSEG-00125-
REPT-001
Hope Creek Generating Station License Renewal
Implementation - Aging Management Gap Analysis
Revision 0