ML20142A522

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Submittal of Updated Final Safety Analysis Report, Revision 24, Summary of Revised Regulatory Commitments and 10 CFR 54.37(b) Review Results
ML20142A522
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 05/21/2020
From: Duke P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML20142A521 List:
References
LR-N20-0036
Download: ML20142A522 (11)


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-N20-0036 May 21, 2020 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 24, 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. 24 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 2019 and 2020 to date in accordance with NEI 99-04.

Revision No. 24 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 November 23, 2019, 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

Page 2 LR-N20-0036 10 CFR 54.37(b)

NEI 99-04 10 CFR 50.59 but not previously submitted to the Commission is provided in. The previous revision to the Hope Creek UFSAR was issued on November 12, 2018.

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 24 of the UFSAR for security-related information (SRI). Consequently, Revision 24 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 Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRC) commitments and associated NRC notifications, PSEG performed a review of regulatory commitments to determine if there were any Hope Creek changed/closed commitments that were not reported by other means during 2019 and 2020 to date. The review concluded that there were 2 changed or closed commitments 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 Systems, Structures, or Components (SSCs) existed in support of submitting Hope Creek UFSAR Revision 24. 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 CD Enclosures and Attachments to this letter, which pertains to the Hope Creek UFSAR Revision 24, 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,

1::;}-4 Manager, Licensing PSEG Nuclear, LLC

10 CFR 50.71(e)

Page 3 10 CFR 54.37(b)

LR-N20-0036 NEI 99-04

Attachment:

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

Enclosures:

1. Hope Creek UFSAR Rev. 24 (redacted version suitable for public disclosure) 27 files submitted electronically in 3 parts due to EIE submittal size restrictions CC (Cover letter, Attachments 1 and 2, Enclosure 1)

Administrator - Region I - USNRC USNRC Project Manager USNRC Senior Resident Inspector - Hope Creek Chief, New Jersey Bureau of Nuclear Engineering

10 CFR 50.71(e)

Page 4 10 CFR 54.37(b)

LR-N20-0036 NEI 99-04 bcc:

(Cover letter, Attachments 1 and 2 only)

Plant Manager - Hope Creek Sr. Director, Regulatory Operations and Nuclear Oversight Director, Site Regulatory Compliance Manager, Licensing Site Compliance Commitment Coordinator Records Management

LR-N20-0036 Summary Report of UFSAR Changes

LR-N20-0036 Summary Report Of UFSAR Changes 1

CN #

SECTION DESCRIPTION BASIS HCN 13-003 9.2, T9.2-7 & 8 Reflect removal of the chemical addition tanks in Auxiliary Building Control Area Chilled Water System (CWS) and replacement with a side stream demineralizer.

10 CFR 50.59 screening performed for DCP 80108102.

HCN 18-002 T3.6-13 Reflect revised High Pressure Coolant Injection (HPCI) system stress levels.

10 CFR 50.59 screening performed for DCP 80120777.

HCN 18-008 Appendix 9A Reflect revised analysis of reactor overfill events caused by HPCI malfunction due to postulated Appendix R fire events.

Fire Protection Change Regulatory Review (FPCRR) performed for DCP 80118326.

HCN 18-015 6.2 Include individual MSIV leakage testing.

10 CFR 50.59 screening performed for HCN 18-015.

HCN 18-016 T9A-1, T9A-6 Update combustible fire loading in Room 3553 and Fire Area AB3.

FPCRR performed for HCN 18-016.

HCN 18-020 8.2 Reflect change to carrier line protection circuitry for the Hope Creek 5023 line.

10 CFR 50.59 screening performed for HCN 18-020.

HCN 18-021 Appendix 9A Correct room numbers and their respective fire areas.

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

HCN 18-024 Appendix 9A Clarify single spurious operation licensing basis; provide the technical basis for acceptance of unrated fire barriers between Fire Area RB5 and fire areas RB1 and RB2; revise the list of high-low pressure interface valves; identify the document containing surveillance requirements and limiting conditions for operation for alternate shutdown; and clarify cable locations.

FPCRR performed for HCN 18-024.

HCN 18-025 6 TOC, T6.3 Incorporate an additional change/error reported in the 2018 Annual 10 CFR 50.46 report, correct a typographical error, and add clarifying information.

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

HCN 18-026 2.4 Correct reference to Reg. Guide 1.59.

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

HCN 18-027 9.5 Reflect installation of a main power transformer fire protection online initiation interlock.

10 CFR 50.59 screening and FPCRR performed for DCP 80122468.

HCN 18-029 F7.1-1, 7.2, 7.6 Incorporate corrections associated with the Power Range Neutron Monitoring system.

10 CFR 50.59 screening performed for DCP 80107709.

LR-N20-0036 Summary Report Of UFSAR Changes 2

CN #

SECTION DESCRIPTION BASIS HCN 19-001 Appendix 9A, T9A-2, T9A-3, T9A-8, T9A-9 Add information to ensure consistency in description of repair actions and add components missing from the Safe Shutdown Equipment List.

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

HCN 19-002 4.6, 10.4 Delete control rod drive system surveillance frequencies and add reference to the Surveillance Frequency Control Program.

The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)

HCN 19-003 1.8, T1.8-1 Adopt Revision 4 of Regulatory Guide 1.31, Control of Ferrite Content in Stainless Steel Weld Metal.

10 CFR 50.59 screening performed for HCN 19-003.

HCN 19-004 Appendix 9A, T9A-4, T9A-6 Include basis for acceptance of unrated floor between fire areas and correctly identify rooms containing safe shutdown cables.

FPCRR performed for HCN 19-004.

HCN 19-005 6.3 Correct the calculated HPCI pump available net positive suction head.

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

HCN 19-006 1.8, 8.3 Add reference to the Surveillance Frequency Control Program as an exception to conformance with Regulatory Guide 1.129, Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants.

The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)

HCN 19-007 13 TOC, 13.1, T13.1-1, F13.1-1, -2, -3,

-4 Remove organizational information that is duplicated in the Quality Assurance Topical Report or that contains excessive detail not important to providing an understanding of the plant's design and operation.

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

HCN 19-008 1.8 Add exception to conformance with Regulatory Guide 1.108, Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants.

The change was implemented in accordance with the Hope Creek Surveillance Frequency Control Program. (Applicability Review)

HCN 19-011 10.2 Replace turbine valve testing frequencies with a reference to the Preventative Maintenance Program.

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

LR-N20-0036 Summary Report Of UFSAR Changes 3

CN #

SECTION DESCRIPTION BASIS HCN 19-013 F6.2-47 sh. 1 and 2 Correct error introduced in HCN 15-026 on subject figures.

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

HCN 19-014 Appendix 15D TOC, 15D, T15D-1, -2, -3,

-4, -5, -8, -9, F15D-1, -2, -3,

-4 Incorporates cycle specific reload analysis results for Cycle 23 and non-regulatory changes.

10 CFR 50.59 screening performed for FCP 80122683.

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

LR-N20-0036 Summary Report of Hope Creek Changed/Closed Regulatory Commitments

LR-N20-0036 Summary Report Of Hope Creek Changed/Closed Regulatory Commitments 1

Original Commitment Revised Commitment Description Justification for Change Original Commitment:

Hope Creek Generating Station will Include the SFP external makeup strategy and SFP external spray strategy as described In the general description in Attachment 1 In plant procedures (Tables A.2 A.2-6).

Source Document:

Hope Creek Generating Station Renewed Facility Operating License NPF-57 / 2.C(16)(b)7, Spent fuel pool mitigation measures Hope Creek Safety Evaluation for Order EA-02-026 dated August 9, 2007

References:

CM-HC-2007-41 80124591 / 0080 Date of Change:

12/04/2019 Hope Creek Generating Station Implements a two-path mitigation strategy for Spent Fuel Pool (SFP) mitigation measures, The preferred method credits Time Critical Actions for SFP external makeup and SFP external spray implementation within 120 minutes. The alternate method disperses discharged fuel assemblies In an approved pattern until they have been subcritical for more than 295 days.

The current SFP mitigation measures consist of a single-path strategy of dispersing discharged fuel assemblies in an approved pattern until they have been subcritical for more than 295 days.

This strategy results in a significant number of irradiated fuel assembly movements in the SFP every cycle to allow for discharged fuel assemblies to be placed in an approved pattern. Each movement of an irradiated fuel assembly represents risk.

The new SFP mitigation measures designate this path as the alternate path and establish the preferred path as one that credits the Time Critical Actions for SFP external makeup and external spray implementation. This two-path strategy results in an improvement in nuclear safety by significantly reducing the number of irradiated fuel assembly movements in the SFP Original Commitment:

Hope Creek Generating Station will fully implement the BWR mitigation strategies as described in the general description in Attachment 1 in plant procedures (Tables A.5-1 --

A.5-10).

Source Document:

Hope Creek Generating Station Renewed Facility Operating License NPF-57 / 2.C(16)(b)7, Spent fuel pool mitigation measures Hope Creek Safety Evaluation for Order EA-02-026 dated August 9, 2007

References:

CM-HC-2007-43 80124591 / 0210 Date of Change:

03/12/2020 Hope Creek Generating Station will fully implement the BWR mitigation strategies as described in the general description in Attachment 1 in plant procedures (Tables A.5-1 -- A.5-10).

Commitments related to SFP Mitigation Measure are described in CM-HC-2007-41, SFP Mitigation Measures.

CM-HC-2007-41 addresses Spent Fuel Pool Mitigation Measures. It is unnecessary to duplicate them in CM-HC-2007-43. CM-HC-2007-43 is being revised to reference CM-HC-2007-41 for Spent Fuel Pool Mitigation Measures. HC.RE-FR.ZZ-0001 is being removed as an Implementing Document from CM-HC-2007-43 since it was associated with Spent Fuel Pool Mitigation Measures.

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