ML21319A374

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Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments for Hope Creek, and 10 CFR 54.37(b) Review Results for Hope Creek
ML21319A374
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 11/15/2021
From: Montgomery R
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML21319A373 List:
References
LR-N21-0081, NEI 99-04
Download: ML21319A374 (10)


Text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 10 CFR 50.71(e) 10 CFR 54.37(b)

NEI 99-04 LR-N21-0081 November 15, 2021 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354

Subject:

Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 25, Summary of Revised Regulatory Commitments for Hope Creek, and 10 CFR 54.37(b) review results for Hope Creek PSEG Nuclear LLC (PSEG) hereby submits:

Revision No. 25 to the Hope Creek Generating Station Updated Final Safety Analysis Report (UFSAR) in accordance with the requirements of 10 CFR 50.71(e)(4) and 10 CFR 50.4(b)(6)

The results of a review performed as required by 10 CFR 54.37(b) to identify any newly-identified Structure, System or Component (SSC) that would be subjected to an aging management review or evaluation of time-limited aging analyses (TLAAs) in accordance with 10 CFR 54.21 A summary of changed/closed regulatory commitments that were not reported by other means during 2020 and 2021 to date in accordance with Nuclear Energy Institute (NEI) 99-04.

Revision No. 25 to the Hope Creek UFSAR is being submitted in its entirety electronically and contains identified text, table and figure changes required to reflect the plant configuration as of May 15, 2021, six months prior to this submittal. In addition, there are general editorial changes. In accordance with 10 CFR 50.71(e)(2)(ii), a summary of changes made under the provisions of 10 CFR 50.59 0 PSEG Nuclear LLC

10 CFR 50.71(e)

Page 2 10 CFR 54.37(b)

LR-N21-0081 NEI 99-04 November 15, 2021 but not previously submitted to the Commission is provided in Attachment 1. The previous revision to the Hope Creek UFSAR was issued on May 21, 2020.

Based on NRC Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents," PSEG has reviewed Revision 25 of the UFSAR for security-related information (SRI). Consequently, Revision 25 of the UFSAR is being provided in its entirety as two separate submittals. This submittal redacts the information that is SRI and designates it as "Security-Related Information - Withheld Under 10 CFR 2.390." This version is suitable for public disclosure. A separate submittal contains the SRI.

In accordance with the NEI process for managing NRC commitments and associated NRC notifications, PSEG performed a review of regulatory commitments to determine if there were any changed/closed Hope Creek commitments that were not reported by other means during 2020 and 2021 to date. The review concluded that there was one changed commitment during that time period and a summary of that review is provided in Attachment 2.

An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting Hope Creek UFSAR Revision 25. This evaluation involved reviewing pertinent documentation for the period subsequent to the last Hope Creek UFSAR revision. The evaluation concluded that there were no newly-identified SSCs and no changes to the Hope Creek current licensing basis that would have caused any newly-identified SSCs for which aging management reviews or time-limited aging analyses would apply.

As required by 10 CFR 50.71(e)(2)(i), I certify that to the best of my knowledge, the information contained in the files attached to this submittal and Attachments to this letter, which pertains to the Hope Creek UFSAR Revision 25, accurately reflects information and analyses submitted to the NRC, or prepared pursuant to NRC requirements as described above. There are no regulatory commitments contained in this letter.

If you have any questions or require additional information, please do not hesitate to contact Mr. Lee Marabella, at (856) 339-1208.

Sincerely, Richard Montgomery Manager, Licensing PSEG Nuclear, LLC Montgomery

, Richard Digitally signed by Montgomery, Richard Date: 2021.11.15 12:11:38

-05'00'

10 CFR 50.71(e)

Page 3 10 CFR 54.37(b)

LR-N21-0081 NEI 99-04 November 15, 2021

Attachment:

1. Summary Report of UFSAR Changes
2. Summary Report of Hope Creek Changed/Closed Regulatory Commitments

Enclosures:

1. Hope Creek UFSAR Rev. 25 (redacted version suitable for public disclosure)
  • 2 files submitted electronically CC (Cover letter, Attachments 1 and 2, Enclosure 1)

Administrator - Region I - USNRC USNRC Project Manager USNRC Senior Resident Inspector - Hope Creek Manager, New Jersey Bureau of Nuclear Engineering (without Enclosure 1)

Site Compliance Commitment Coordinator (without Enclosure 1)

Corporate Commitment Coordinator (without Enclosure 1)

LR-N21-0081 Summary Report of UFSAR Changes

LR-N21-0081 Summary Report of UFSAR Changes 1

CN #

SECTION DESCRIPTION BASIS HCN 11-002 T3.4-4, 9TOC, 9.2, F9.2-12 Site Sewage Treatment plant being replaced.

10 CFR 50.59 screening performed for DCP 80101825.

HCN 18-003 8.3 Enhance 500 kV and 13kV electrical systems with new protective relay scheme to protect against open phase condition 10 CFR 50.59 screening performed for DCP 80119206.

HCN 18-005

9TOC, T9.5-19, T9A-103 Adds new Table 9A-103 to fire hazards analysis to support addition of a new air compressor to SWIS Room 202 Fire Protection Change Regulatory Review (FPCRR) performed for EC 80120609. 10 CFR 50.59 screening performed for HCN 18-005.

HCN 18-022 T9A-1, T9A-6 Revise combustible loading in room 3219 FPCRR and 10 CFR 50.59 screening performed for HCN 18-022.

HCN 18-028 3.9, 5.2, T5.2-1, T5.2-7, F5.2-8 Replacement of the 13 remaining Target Rock 2-stage Main Steam Safety Relief Valves (SRVs) with 3-stage valves.

10 CFR 50.59 screening performed for DCP 80122932.

HCN 19-012 2.2, T2.2-5, T2.2-6, T9.5-3, 10.4.5.2, T10.4-6 Installs the Purate (chlorine dioxide) biocide water treatment system design to treat the Circulating Water (CW) System.

10 CFR 50.59 screening performed for DCP 80124128.

HCN 19-015 9.5 Modify Diesel and electric motor driven fire pumps circuitry by lifting leads from the remote control panel 10C682 in the control room and local panels 00C530 and 00C531 to eliminate the remote start option.

FPCRR performed for DCP 80125227.

HCN 20-001 T9A-1, T9A-75 The proposed change creates a fire hazard analysis for Rooms 5702 and 5706 in Fire Area CD60. In addition, Table 9A-1 will be revised to include Rooms 5702 and 5706, and Table 9A-75 page 1 is revised to reflect the full floor area and average fire loading for Fire Area CD60.

FPCRR performed for HCN 20-001.

LR-N21-0081 Summary Report of UFSAR Changes 2

CN #

SECTION DESCRIPTION BASIS HCN 20-004 T9A-1, T9A-25 Incorporates transient storage for the Operations Department in the caged area of Rooms 5315/5308.

FPCRR performed for HCN 20-004.

HCN 20-010 9.1 Revise UFSAR Sections 9.1.1.3.1 &

9.1.2.3.1, "Criticality Control", to document compliance with 10 CFR 50.68 and 10 CFR 70.24, Criticality Accident Requirements.

10 CFR 50.59 screening performed for HCN 20-010.

HCN 21-002 1.8 Updates the Revision to which PSEG Nuclear conforms in Section 1.8 for NRC Regulatory Guides 1.21 from Revision 1 to Revision 2, and RG 1.23 from Revision 0 to Revision 1.

10 CFR 50.59 screening performed for HCN 21-002.

HCN 21-004 1.8 Add an exception to the regulatory guide 1.140 section of the UFSAR. The leak testing frequency of the activated carbon absorber section will be conducted in accordance with the Preventative Maintenance (PM) program.

10 CFR 50.59 screening performed for HCN 21-004.

HCN 21-006 T7.7-4 Change Seismic Monitoring Instrumentation channel calibration frequency to be controlled under the Preventative Maintenance Program.

10 CFR 50.59 screening performed for HCN 21-006.

HCN 21-007 T3.6-10, T3.6-11 Mark table data as historical information and refer to applicable stress calculations for current data.

The changes meet the NEI 98-03 criteria for a non-regulatory change.

HCN 21-008 15.1, Appendix 15D, F15D, T15D Incorporates cycle specific reload analysis results for Cycle 24 and non-regulatory changes.

10 CFR 50.59 screening performed for FCP 80126636.

The additional changes meet the NEI 98-03 criteria for a non-regulatory change.

HCN 21-009 Appendix A Revise the BWRVIP-48-A to "BWRVIP-48-A or later revision".

The change meets the NEI 98-03 criteria for a non-regulatory change.

LR-N21-0081 Summary Report of UFSAR Changes 3

CN #

SECTION DESCRIPTION BASIS HCN 21-013 8.2 Revise description of Red Lion line primary and backup protection schemes.

Delete carrier equipment failure from the system monitoring and annunciation section. Revise switchyard fault recorder parameter status inputs for the Red Lion (61X) line.

10 CFR 50.59 screening performed for DCP 80127900.

HCN 21-016 9.5, Appendix 9A Remove and delete redundant and duplicate information associated with equivalent fire severity for the Main Control Room and peripheral rooms.

The change meets the NEI 98-03 criteria for a non-regulatory change.

HCN 21-017 9.2 Corrects an error in incorporating previously evaluated change to description of equipment cooled by Turbine Auxiliaries Cooling System.

The change meets the NEI 98-03 criteria for a non-regulatory change.

LR-N21-0081 Summary Report of Hope Creek Changed/Closed Regulatory Commitments

LR-N21-0081 Summary Report of Hope Creek Changed/Closed Regulatory Commitments 1

Original Commitment Revised Commitment Description Justification for Change Original Commitment:

Any component testing or maintenance that increases the likelihood of a plant transient shall be avoided during the extended 14 day AOT. This encompasses work activities categorized as Production Risk.

Source Document:

Amendment No. 188 to Facility Operating License No. NPF-57 for the Hope Creek Generating Station.

Issuance of Amendment re:

Emergency Diesel Generators A and B Allowed Outage Time Extension (TAC No. ME3597).

References:

CM-HC-2011-816 70215722 / 0010 80128524 / 0060 Date of Change:

05/29/2021 Component testing or maintenance of safety systems and important non safety equipment in the offsite power systems that can increase the likelihood of a plant transient (unit trip) or LOOP will be avoided. In addition, no discretionary switchyard maintenance will be performed.

Hope Creek Regulatory Commitment CM.HC.2011-816 was revised to align with NRC expectations listed in NUREG-0800, Branch Technical Position 8-8, Onsite (Emergency Diesel Generators) and Offsite Power Sources Allowed Outage Time Extensions.

The existing commitment was broader than necessary when NRC recently approved license amendment 216 (April 2019).

1 to LR-N21-0081 Hope Creek UFSAR Rev. 25 (redacted version suitable for public disclosure) 2 files submitted electronically