View source for NEI 99-04, 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

{{Adams
| number = ML21319A374
| issue date = 11/15/2021
| title = 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
| author name = Montgomery R
| author affiliation = PSEG Nuclear, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000354
| license number = NPF-057
| contact person = 
| case reference number = LR-N21-0081, NEI 99-04
| package number = ML21319A373
| document type = Letter type:NEI
| page count = 10
}}

=Text=
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC 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

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, Montgomery Digitally              signed by Montgomery, Richard
, Richard                 Date: 2021.11.15 12:11:38
                          -05'00' Richard Montgomery Manager, Licensing PSEG Nuclear, LLC

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 Attachment 1 Summary Report of UFSAR Changes

LR-N21-0081           Summary Report of UFSAR Changes CN #     SECTION       DESCRIPTION                                 BASIS HCN      T3.4-4,       Site Sewage Treatment plant being           10 CFR 50.59 11-002   9TOC, 9.2,    replaced.                                   screening performed F9.2-12                                                   for DCP 80101825.
HCN      8.3           Enhance 500 kV and 13kV electrical          10 CFR 50.59 18-003                 systems with new protective relay           screening performed scheme to protect against open phase        for DCP 80119206.
condition HCN      9TOC,         Adds new Table 9A-103 to fire hazards       Fire Protection 18-005   T9.5-19,      analysis to support addition of a new air   Change Regulatory T9A-103       compressor to SWIS Room 202                 Review (FPCRR) performed for EC 80120609. 10 CFR 50.59 screening performed for HCN 18-005.
HCN      T9A-1,        Revise combustible loading in room 3219 FPCRR and 10 CFR 18-022   T9A-6                                                     50.59 screening performed for HCN 18-022.
HCN      3.9, 5.2,     Replacement of the 13 remaining Target 10 CFR 50.59 18-028   T5.2-1,       Rock 2-stage Main Steam Safety Relief       screening performed T5.2-7,       Valves (SRVs) with 3-stage valves.          for DCP 80122932.
F5.2-8 HCN      2.2, T2.2-5,  Installs the Purate (chlorine dioxide)      10 CFR 50.59 19-012   T2.2-6,       biocide water treatment system design to    screening performed T9.5-3,       treat the Circulating Water (CW) System. for DCP 80124128.
10.4.5.2, T10.4-6 HCN      9.5           Modify Diesel and electric motor driven     FPCRR performed for 19-015                 fire pumps circuitry by lifting leads from  DCP 80125227.
the remote control panel 10C682 in the control room and local panels 00C530 and 00C531 to eliminate the remote start option.
HCN      T9A-1,        The proposed change creates a fire          FPCRR performed for 20-001   T9A-75        hazard analysis for Rooms 5702 and          HCN 20-001.
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.
1

LR-N21-0081         Summary Report of UFSAR Changes CN #     SECTION     DESCRIPTION                               BASIS HCN      T9A-1,      Incorporates transient storage for the    FPCRR performed for 20-004   T9A-25      Operations Department in the caged        HCN 20-004.
area of Rooms 5315/5308.
HCN      9.1         Revise UFSAR Sections 9.1.1.3.1 &         10 CFR 50.59 20-010               9.1.2.3.1, "Criticality Control", to      screening performed document compliance with 10 CFR 50.68     for HCN 20-010.
and 10 CFR 70.24, Criticality Accident Requirements.
HCN      1.8         Updates the Revision to which PSEG        10 CFR 50.59 21-002               Nuclear conforms in Section 1.8 for NRC   screening performed Regulatory Guides 1.21 from Revision 1    for HCN 21-002.
to Revision 2, and RG 1.23 from Revision 0 to Revision 1.
HCN      1.8         Add an exception to the regulatory guide  10 CFR 50.59 21-004               1.140 section of the UFSAR. The leak      screening performed testing frequency of the activated carbon for HCN 21-004.
absorber section will be conducted in accordance with the Preventative Maintenance (PM) program.
HCN      T7.7-4      Change Seismic Monitoring                 10 CFR 50.59 21-006               Instrumentation channel calibration       screening performed frequency to be controlled under the      for HCN 21-006.
Preventative Maintenance Program.
HCN      T3.6-10,    Mark table data as historical information The changes meet the 21-007   T3.6-11     and refer to applicable stress            NEI 98-03 criteria for a calculations for current data.            non-regulatory change.
HCN      15.1,       Incorporates cycle specific reload        10 CFR 50.59 21-008   Appendix    analysis results for Cycle 24 and non-    screening performed 15D, F15D,  regulatory changes.                       for FCP 80126636.
T15D                                                  The additional changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN      Appendix A  Revise the BWRVIP-48-A to                 The change meets the 21-009               "BWRVIP-48-A or later revision".          NEI 98-03 criteria for a non-regulatory change.
2

LR-N21-0081         Summary Report of UFSAR Changes CN #     SECTION     DESCRIPTION                               BASIS HCN      8.2         Revise description of Red Lion line       10 CFR 50.59 21-013               primary and backup protection schemes. screening performed Delete carrier equipment failure from the for DCP 80127900.
system monitoring and annunciation section. Revise switchyard fault recorder parameter status inputs for the Red Lion (61X) line.
HCN      9.5,        Remove and delete redundant and           The change meets the 21-016   Appendix 9A duplicate information associated with     NEI 98-03 criteria for a equivalent fire severity for the Main     non-regulatory Control Room and peripheral rooms.        change.
HCN      9.2         Corrects an error in incorporating        The change meets the 21-017               previously evaluated change to            NEI 98-03 criteria for a description of equipment cooled by        non-regulatory Turbine Auxiliaries Cooling System.       change.
3

LR-N21-0081 Attachment 2 Summary Report of Hope Creek Changed/Closed Regulatory Commitments

LR-N21-0081                Summary Report of Hope Creek Changed/Closed Regulatory Commitments Original Commitment             Revised Commitment Justification for Change Description Original Commitment:                  Component testing or       Hope Creek Regulatory Any component testing or              maintenance of safety      Commitment CM.HC.2011-816 was maintenance that increases the        systems and important      revised to align with NRC likelihood of a plant transient shall non safety equipment in    expectations listed in NUREG-0800, be avoided during the extended 14     the offsite power systems  Branch Technical Position 8-8, day AOT. This encompasses work        that can increase the      Onsite (Emergency Diesel activities categorized as Production  likelihood of a plant      Generators) and Offsite Power Risk.                                 transient (unit trip) or   Sources Allowed Outage Time LOOP will be avoided. In   Extensions.
Source Document:                      addition, no discretionary Amendment No. 188 to Facility         switchyard maintenance     The existing commitment was Operating License No. NPF-57 for      will be performed.         broader than necessary when NRC the Hope Creek Generating Station.                               recently approved license amendment 216 (April 2019).
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 1

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

=Text=
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 0 PSEG Nuclear LLC 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

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, Montgomery Digitally              signed by Montgomery, Richard
, Richard                 Date: 2021.11.15 12:11:38
                          -05'00' Richard Montgomery Manager, Licensing PSEG Nuclear, LLC

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 Attachment 1 Summary Report of UFSAR Changes

LR-N21-0081           Summary Report of UFSAR Changes CN #     SECTION       DESCRIPTION                                 BASIS HCN      T3.4-4,       Site Sewage Treatment plant being           10 CFR 50.59 11-002   9TOC, 9.2,    replaced.                                   screening performed F9.2-12                                                   for DCP 80101825.
HCN      8.3           Enhance 500 kV and 13kV electrical          10 CFR 50.59 18-003                 systems with new protective relay           screening performed scheme to protect against open phase        for DCP 80119206.
condition HCN      9TOC,         Adds new Table 9A-103 to fire hazards       Fire Protection 18-005   T9.5-19,      analysis to support addition of a new air   Change Regulatory T9A-103       compressor to SWIS Room 202                 Review (FPCRR) performed for EC 80120609. 10 CFR 50.59 screening performed for HCN 18-005.
HCN      T9A-1,        Revise combustible loading in room 3219 FPCRR and 10 CFR 18-022   T9A-6                                                     50.59 screening performed for HCN 18-022.
HCN      3.9, 5.2,     Replacement of the 13 remaining Target 10 CFR 50.59 18-028   T5.2-1,       Rock 2-stage Main Steam Safety Relief       screening performed T5.2-7,       Valves (SRVs) with 3-stage valves.          for DCP 80122932.
F5.2-8 HCN      2.2, T2.2-5,  Installs the Purate (chlorine dioxide)      10 CFR 50.59 19-012   T2.2-6,       biocide water treatment system design to    screening performed T9.5-3,       treat the Circulating Water (CW) System. for DCP 80124128.
10.4.5.2, T10.4-6 HCN      9.5           Modify Diesel and electric motor driven     FPCRR performed for 19-015                 fire pumps circuitry by lifting leads from  DCP 80125227.
the remote control panel 10C682 in the control room and local panels 00C530 and 00C531 to eliminate the remote start option.
HCN      T9A-1,        The proposed change creates a fire          FPCRR performed for 20-001   T9A-75        hazard analysis for Rooms 5702 and          HCN 20-001.
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.
1

LR-N21-0081         Summary Report of UFSAR Changes CN #     SECTION     DESCRIPTION                               BASIS HCN      T9A-1,      Incorporates transient storage for the    FPCRR performed for 20-004   T9A-25      Operations Department in the caged        HCN 20-004.
area of Rooms 5315/5308.
HCN      9.1         Revise UFSAR Sections 9.1.1.3.1 &         10 CFR 50.59 20-010               9.1.2.3.1, "Criticality Control", to      screening performed document compliance with 10 CFR 50.68     for HCN 20-010.
and 10 CFR 70.24, Criticality Accident Requirements.
HCN      1.8         Updates the Revision to which PSEG        10 CFR 50.59 21-002               Nuclear conforms in Section 1.8 for NRC   screening performed Regulatory Guides 1.21 from Revision 1    for HCN 21-002.
to Revision 2, and RG 1.23 from Revision 0 to Revision 1.
HCN      1.8         Add an exception to the regulatory guide  10 CFR 50.59 21-004               1.140 section of the UFSAR. The leak      screening performed testing frequency of the activated carbon for HCN 21-004.
absorber section will be conducted in accordance with the Preventative Maintenance (PM) program.
HCN      T7.7-4      Change Seismic Monitoring                 10 CFR 50.59 21-006               Instrumentation channel calibration       screening performed frequency to be controlled under the      for HCN 21-006.
Preventative Maintenance Program.
HCN      T3.6-10,    Mark table data as historical information The changes meet the 21-007   T3.6-11     and refer to applicable stress            NEI 98-03 criteria for a calculations for current data.            non-regulatory change.
HCN      15.1,       Incorporates cycle specific reload        10 CFR 50.59 21-008   Appendix    analysis results for Cycle 24 and non-    screening performed 15D, F15D,  regulatory changes.                       for FCP 80126636.
T15D                                                  The additional changes meet the NEI 98-03 criteria for a non-regulatory change.
HCN      Appendix A  Revise the BWRVIP-48-A to                 The change meets the 21-009               "BWRVIP-48-A or later revision".          NEI 98-03 criteria for a non-regulatory change.
2

LR-N21-0081         Summary Report of UFSAR Changes CN #     SECTION     DESCRIPTION                               BASIS HCN      8.2         Revise description of Red Lion line       10 CFR 50.59 21-013               primary and backup protection schemes. screening performed Delete carrier equipment failure from the for DCP 80127900.
system monitoring and annunciation section. Revise switchyard fault recorder parameter status inputs for the Red Lion (61X) line.
HCN      9.5,        Remove and delete redundant and           The change meets the 21-016   Appendix 9A duplicate information associated with     NEI 98-03 criteria for a equivalent fire severity for the Main     non-regulatory Control Room and peripheral rooms.        change.
HCN      9.2         Corrects an error in incorporating        The change meets the 21-017               previously evaluated change to            NEI 98-03 criteria for a description of equipment cooled by        non-regulatory Turbine Auxiliaries Cooling System.       change.
3

LR-N21-0081 Attachment 2 Summary Report of Hope Creek Changed/Closed Regulatory Commitments

LR-N21-0081                Summary Report of Hope Creek Changed/Closed Regulatory Commitments Original Commitment             Revised Commitment Justification for Change Description Original Commitment:                  Component testing or       Hope Creek Regulatory Any component testing or              maintenance of safety      Commitment CM.HC.2011-816 was maintenance that increases the        systems and important      revised to align with NRC likelihood of a plant transient shall non safety equipment in    expectations listed in NUREG-0800, be avoided during the extended 14     the offsite power systems  Branch Technical Position 8-8, day AOT. This encompasses work        that can increase the      Onsite (Emergency Diesel activities categorized as Production  likelihood of a plant      Generators) and Offsite Power Risk.                                 transient (unit trip) or   Sources Allowed Outage Time LOOP will be avoided. In   Extensions.
Source Document:                      addition, no discretionary Amendment No. 188 to Facility         switchyard maintenance     The existing commitment was Operating License No. NPF-57 for      will be performed.         broader than necessary when NRC the Hope Creek Generating Station.                               recently approved license amendment 216 (April 2019).
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 1

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