ML22298A054
| ML22298A054 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 10/24/2022 |
| From: | Montgomery R Public Service Enterprise Group |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| Shared Package | |
| ML22298A053 | List: |
| References | |
| LR-N22-0086, NEI 99-04 | |
| Download: ML22298A054 (1) | |
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC 10 CFR 71.106(b) 10 CFR 50.71(e) 10 CFR 54.37(b)
NEI 99-04 LR-N22-0086 October 24, 2022 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Salem Generating Station - Unit 1 and Unit 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Submittal of Salem Generating Station Updated Final Safety Analysis Report, Revision 33, 10 CFR 71.106 review results and 10 CFR 54.37(b) review results for Salem PSEG Nuclear LLC (PSEG) hereby submits:
Revision No. 33 to the Salem 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 2021 and 2022 to date in accordance with NEI 99-04.
10 CFR 71.106 10 CFR 50.71(e) 10 CFR 54.37(b)
October 24, 2022 NEI 99-04 Page 2 LR-N22-0086 The results of a review performed as required by 10 CFR 71.106 to identify changes made to the quality assurance (QA) program related to packaging and transportation of radioactive material that did not required previous NRC approval.
Revision No. 33 to the Salem 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 18, 2022, within 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 but not previously submitted to the Commission is provided in Attachment 1. The previous revision to the Salem UFSAR was issued on June 17, 2021.
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 33 of the UFSAR for security-related information (SRI). Consequently, Revision 33 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 Salem changed/closed commitments that were not reported by other means during 2021 and 2022 to date. The review concluded that there were 3 changed or closed commitments during that time period and a summary of that review is provided in .
An evaluation was completed to determine whether any newly-identified Systems, Structures, or Components (SSCs) existed in support of submitting Salem UFSAR Revision 33. This evaluation involved reviewing pertinent documentation for the period subsequent to the last Salem UFSAR revision. The evaluation concluded that there were no newly-identified SSCs and no changes to the Salem current licensing basis that would have caused any newly-identified SSCs for which aging management reviews or time-limited aging analyses would apply.
An evaluation was completed to determine whether any changes were made to the Packaging and Transportation of Radioactive Material QA Program in the last two years that did not require previous NRC approval as required per 10 CFR 71.106.
The evaluation concluded that there were no such changes made.
10 CFR 71.106 10 CFR 50.71(e) 10 CFR 54.37(b)
October 24, 2022 NEI 99-04 Page 3 LR-N22-0086 As required by 10 CFR 50.71 (e)(2)(i), I certify that to the best of my knowledge, the information contained in the Enclosure and Attachments to this letter, which pertains to the Salem UFSAR Revision 33, 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.
Sine~ ..
~/~L Richard Montgomery Manager, Licensing PSEG Nuclear, LLC
Attachment:
- 1. Summary Report of UFSAR Changes
- 2. Summary Report of Salem Changed/Closed Regulatory Commitments
Enclosures:
- 1. Salem UFSAR Rev. 33 (redacted version suitable for public disclosure)
- One file submitted electronically CC (Cover letter, Attachments 1 and 2, Enclosure 1)
Administrator - Region I - USN RC USNRC Project Manager USN RC Senior Resident Inspector - Salem USNRC Senior Resident Inspector- Hope Creek Chief, New Jersey Bureau of Nuclear Engineering
10 CFR 71.106 10 CFR 50.71(e) 10 CFR 54.37(b)
October 24, 2022 NEI 99-04 Page 4 LR-N22-0086 bcc: (Cover letter, Attachments 1 and 2 only)
Plant Manager - Salem Plant Manager - Hope Creek Sr. Director, Regulatory Operations and Nuclear Oversight Director, Site Regulatory Compliance Manager, Licensing Site Compliance Commitment Coordinator Records Management
LR-N22-0086 Attachment 1 Summary Report of UFSAR Changes
LR-N22-0086 Summary Report Of UFSAR Changes CN # SECTION DESCRIPTION BASIS SCN 16-016 3.9 Revised Section 3.9.1.5 to align The change with Sections 3.6.1.1 and meets the NEI 5.2.1.7.1. Section 3.9.5 is revised 98-03 criteria for to add references to a 1994 Leak- a non-regulatory Before-Break letter and WCAP- change.
13659 SCN 19-014 2.2, T2.2-2, T2.2-4, 6.4 Reflects the installation of the 10 CFR 50.59 Purate (chlorine dioxide) biocide screening water treatment system design by performed for NALCO to treat the Circulating DCP 80124128.
Water System at Hope Creek.
SCN 20-002 8.1 Reflects the deletion of the words The change "and Nuclear Oversight performs meets the NEI independent assessment (as 98-03 criteria for defined in Chapter 18 of the a non-regulatory QATR) of randomly selected change.
safety-related cable installations, to ensure proper installation. As an unnecessary requirement.
SCN 20-012 7.10, 8.3 Reflects upgrades to the Salem 1 10 CFR 50.59 Plant Computer and combines the screening Plant Computer and SPDS. performed for DCP 80112043 SCN 21-004 9.5 Reflects an update to non-PSEG Fire Protection engineer requirements in fire drills Change and removal of a reference to a Regulatory superseded document. Review performed by Engineering Services SCN 21-006 2.3, T2.3-16, F2.3-7, F2.3- Reflects UFSAR update for MET 10 CFR 50.59 8 Tower equipment replacement. screening performed for DCP 80128616 SCN 21-007 5.2 Reflects deletion of the description The change of automatic rod withdrawal which meets the NEI was inadvertently omitted under a 98-03 criteria for previously approved change a non-regulatory notice. change.
SCN 21-008 6.2 Reflects implementation of a plant 10 CFR 50.59 change to add permanent screening scaffolding inside the containment performed for is Salem Units 1 and 2. DCP 80128286.
1
LR-N22-0086 Summary Report Of UFSAR Changes CN # SECTION DESCRIPTION BASIS SCN 21-009 3.6, T3.6-1, F3.6-1, T4.1-1, Reflects changes related to the NRC Safety 4.4, T4.4-1, 5.2, 15TOC, Salem Unit 2 Upflow Conversion Evaluation for TS 15.1, 15.4, T15.4-1, -6, - Project and the implementation of Amendments 336 12, -13, -14, -24, -15C, - extended Leak-Before-Break & 317.
15D, -16A, -17A, -18A, - (eLBB).
19A, -22A, -23A, -24, -25A,
-28A, -29A, -30A, -31A, -
32A, -33A, -35, F15.4-68, -
69, -70, -76, -77, -78A, -
78B, -112, thru -117, Appdx. B SCN 21-010 4.3 Reflects fuel burnup update to 10 CFR 50.59 specify the maximum lead rod evaluation burnup limit of 62,000 MWD/MTU. performed by Nuclear Fuels and approved by FRC.
SCN 21-013 9.1 Removes the reference to S-C-SF- 10 CFR 50.59 MDC-2383 (a bounding screen performed calculation) and allow for either a by Nuclear Fuels bounding calculation or an outage-specific calculation to determine the minimum requirement for reactor subcriticality necessary to meet the SFP water temperature requirements.
SCN 21-014 8.3 Add description of Open Phase 10 CFR 50.59 Protection to Section 8.3.1.2, screening Electric Circuit Protection System performed for for permanent monitoring and DCP 80119205 alarm only function based on risk assessment of manual operator action to respond to an open phase condition.
SCN 21-015 4.3 Testing Section was revised to 10 CFR 50.59 include PWROG-20039, Rod screening Worth Measurement Elimination. performed for SCN 21-015.
SCN 22-004 9.4, T10.4 Modifies the reliance of the turbine 10 CFR 50.59 driven Aux Feed pump design screening basis function on availability of its performed for associated area room cooler. SCN 22-004.
SCN 22-009 9 TOC, 9.2 Provides clarification that the 10 CFR 50.59 Traveling Water Screens do not evaluation need to be in Automatic performed for operation/rotation to maintain SCN 22-009 and functionality for the purposes of approved by establishing Service Water Pump FRC.
operability.
2
LR-N22-0086 Attachment 2 Summary Report of Salem Changed/Closed Regulatory Commitments 1
LR-N22-0086 Original Commitment Revised Commitment Justification for Change Description Original Commitment: Salem Generating Stations Unit The current SFP mitigation Salem Generating Station will Include the No. 1 and Unit No. 2 measures consist of a single-path SFP external makeup strategy and Spent Implements a two-path strategy of dispersing discharged Fuel Pool external spray strategy as mitigation strategy for Spent fuel assemblies in an approved described In the general description in Fuel Pool (SFP) mitigation pattern until they have been In plant procedures (Tables measures, The preferred subcritical for more than 295 days.
A.2 A.2-6). method credits Time Critical This strategy results in a significant Actions for SFP external number of irradiated fuel assembly Source Document: makeup and SFP external spray movements in the SFP every cycle Salem Generating Station Unit No. 1 implementation within 120 to allow for discharged fuel Renewed Facility Operating License DPR-70 minutes. The alternate method assemblies to be placed in an I 2.C(16)(b)7, "Spent fuel pool mitigation disperses discharged fuel approved pattern. Each movement measures" Salem Generating Station Unit assemblies In an approved of an irradiated fuel assembly No. 2 Renewed Facility Operating License pattern until they have been represents risk.
DPR-75 / .C(32)(b)7, "Spent fuel pool subcritical for more than 295 mitigation measures" days. The new SFP mitigation measures designate this path as the alternate Salem Generating Station Units 1 and 2 path and establishes the preferred Safety Evaluation for Order EA-02-026 dated path as one that credits the Time August 9, 2007 Critical Actions for SFP external
References:
makeup and external spray CM-SC-2007-64 implementation. This two-path 80124591 / 0081 strategy results in an improvement Date of Change: in nuclear safety by significantly 12/04/2019 reducing the number of irradiated fuel assembly movements in the SFP.
Original Commitment: This commitment Is being CM-SC-2007-23 addresses Spent Operations to mitigate fuel damage deleted. Fuel Pool Mitigation Measures. It Is considering the following: Spent fuel pool being deleted because CM-SC-mitigation measures [Guidance Document 2007-64 addresses Spent Fuel Pool Elements: B.2.m.1, B.2.m.2, B.2.m.3, Mitigation Measures as required by B.2.m.4, B.2.m.5] SFP thermal mgmt. the Salem Generating Station Unit No. 1 and Unit No. 2 Renewed Source Document: Facility Operation License 2.C(16)
Salem Generating Station Unit No. 1 and 2.C(32)1 respectively. CM-SC-Renewed Facility Operating License DPR-70 2007-23 ls unnecessary and Is I 2.C(16)(b)7, "Spent fuel pool mitigation being deleted.
measures" Salem Generating Station Unit No. 2 Renewed Facility Operating License DPR-75 / 2.C(32)(b)7, "Spent fuel pool mitigation measures" Salem Generating Station Units 1 and 2 Safety Evaluation for Order EA-02-026 dated August 9, 2007
References:
CM-SC-2007-23 80124591 / 0211 Date of Change:
02/19/20 1
LR-N22-0086 Original Commitment: PSEG will submit to the NRC for The justification for changing the PSEG will submit to the NRC for review and review and approval a best commitment is based on the approval a best estimate LBLOCA analysis estimate LOCA analysis using uncertainty related to the NRC's that applies NRC approved methods that FSLOCA (Westinghouse Full approval of 10CFR50.46(c). With include the effects of fuel Thermal Spectrum LOCA) for Salem the current commitment due at the Conductivity Degradation (TCD) for Salem Units 1 & 2 consistent with the end of 2020, it is prudent to extend Units 1 & 2. The date for the analysis implementation requirements of the commitment to 2022 to provide submittal is contingent on the following 10CFR50.46(c). FSLOCA sufficient time between NRC milestones which must be completed in order requires PAD 5 (Westinghouse approval and PSEG submitting a to perform a revised licensing basis Large fuel schedule for compliance to the Break Loss Of Coolant Accident (LBLOCA) performance analysis NRC.
analysis with an NRC approved ECCS-EM methodology) which explicitly that explicitly accounts for TCD: includes the effects of fuel
- 1) NRC approval of a fuel performance Thermal Conductivity analysis methodology that includes the Degradation (TCD).
effects of TCD.
The new methodology for developing inputs Earlier submittal may occur to the LBLOCA-EM would replace the current based on plant modifications licensing basis methodology for Salem that is affecting the current LOCA described in WCAP-15063-P-A, Revision 1 analysis or the decision to with Errata, Westinghouse Improved recover Peak Clad Temperature Performance Analysis and Design Model (PCT) margin by implementing (PAD 4.0), July 2000 (Ref. 3). FSLOCA. Implementation of
- 2) NRC approval of a best estimate FSLOCA would remove LBLOCA-EM model that includes the effects limitations and conservatisms of TCD and accommodates the rulemaking associated with our current associated with the proposed 10CFR50.46c. LOCA analysis, including those The new methodology would replace the which address fuel TCD.
current licensing basis methodology that is described in WCAP-10266-P-A, Rev.2, The Commitment Date: December 1981 Version of Westinghouse ECCS 15, 2022.
Evaluation Model Using the Bash Code, March 1987 (Ref. 4).
Commitment Date: December 15, 2017.
Source Document:
LR-N12-0328 Salem Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - 30 Day Report, October 19, 2012.
References:
CM-U1-2012-860 and CM-U2- 2012-861 80107550 / 0081 Date of Change:
7/28/2020 2