LR-N18-0123, Submittal of Hope Creek Generating Station, Revision 23 to Updated Final Safety Analysis Report

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Submittal of Hope Creek Generating Station, Revision 23 to Updated Final Safety Analysis Report
ML18334A151
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 11/12/2018
From: Duke P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML18334A137 List:
References
LR-N18-0123
Download: ML18334A151 (10)
v • d • e


Text

Security Related Information - Withhold Under 10 CFR 2.390 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)

TS6.15.d NEI 99-04 LR-N18-0123 November 12, 2018 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 23, Hope Creek Technical Specification Bases changes, 2018 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:

  • A complete updated copy of the Hope Creek Technical Specification Bases, which includes changes through November 12, 2018, in accordance with the requirements of Hope Creek Generating Station Technical Specification 6.15.d
  • 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 AP5 ~

J CD Enclosure 1, CD-1, contains Security Related Information - Withhold Under 10 CFR 2.390. When separated from CD-1, this document is decontrolled.

NOV 12 2018 10 CFR 50.71 (e)

Page 2 10 CFR 54.37(b)

LR-N 18-0123 TS 6.15.d NEI 99-04 Revision No. 23 to the Hope Creek UFSAR is being submitted in its entirety electronically via CD-ROM and contains identified text, table and figure changes required to reflect the plant configuration as of May 11, 2018, 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 . Hardcopy pages containing the revised material and associated insert/remove instructions will no longer be provided . The previous revision to the Hope Creek UFSAR was issued on May 9, 2017 .

Based on NRG 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 23 of the UFSAR for security-related information (SRI). Consequently, Revision 23 of the UFSAR is being provided in its entirety as two separate versions each on its own CD. One version ,

on CD-1, contains SRI and should be withheld from public disclosure under 10 CFR 2.390. The information that is SRI is designated by the statement "Security-Related Information - Withhold Under 10 CFR 2.390" at the top of the page. The second version, on CD-2, redacts the information that is SRI and designates it as "Security-Related Information - Withheld Under 10 CFR 2.390 ." The version on CD-2 is suitable for public disclosure. contains a complete updated copy of the Hope Creek Technical Specification Bases with changes through November 12, 2018 .

In accordance with the Nuclear Energy Institute (NEI) process for managing Nuclear Regulatory Commission (NRG) commitments and associated NRG 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 2016 and 2017 . The review concluded that there were no changed or closed commitments during that time period .

An evaluation was completed to determine whether any newly-identified Systems, Structures , or Components (SSCs) existed in support of submitting Hope Creek UFSAR Revision 23 . 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 23, accurately reflects information and analy~e~ submitted to the NRC, or prepared purs ant to NRC requirements as described above. There are no regulatory commitments contained in this letter.

NOV 1 2 2018 10 CFR 50.71(e)

Page 3 10 CFR 54.37(b)

LR-N 18-0123 TS 6.15.d NEI 99-04 If you have any questions or require additional information, please do not hesitate to contact Mr. Lee Marabella, at (856) 339-1208.

Sincerely, Paul Duke Manager, Licensing PSEG Nuclear, LLC Attachments:

1. Summary Report of UFSAR Changes CD

Enclosures:

1. CD-1, Hope Creek UFSAR Rev. 23 (withhold from public disclosure)
2. CD-2, Hope Creek UFSAR Rev. 23 (redacted version suitable for public disclosure)

Other

Enclosures:

1. Hope Creek Generating Station Technical Specification Bases as of November 12,2018 CC (Cover letter, CD enclosure 1 and 2, and Attachment 1 only)

Administrator - Region I - USNRC Licensing Project Manager - Hope Creek - USNRC USNRC Senior Resident Inspector - Hope Creek Chief, New Jersey Bureau of Nuclear Engineering (Cover letter, Attachment 1 only)

Hope Creek Commitment Coordinator

LR-N 18-0123 Attachment 1 Summary Report of UFSAR Changes

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 14-016 9.5 9.5-107 UFSAR change reflects the Design Change package 80107326 instituted .

replacement of 20kVA UPS Associated 50 .59 screening is included in the 180484, power supply to the Hope HCN 14-016 package.

Creek Radio System.

HCN 14-018 1.14, 3.9, App 38, 1.14-11, -61, -89, 3.9-52, -76, - UFSAR change reflects Design Change package 80107006 instituted.

5.2, App 9A, 14.2, 111, -112, -120, -121, -123, 38-2 , replacement of 1 of the 14 Target Associated 50.59 screening and Fire 15.1 38-3, 5.2-17, -17a, -17b, -17c, - Rock 2-Stage Main Steam Safety Protection Change Regulatory Review 17d, -18 thru -27, T5.2-1 sh1, Relief Valves (SRVs) with a Target (FPCRR) are included in the HCN 14-018 T5.2-7 sh7a, F5.2-8, F5.2-8A, Rock 3-Stage valve. It also package.

T9A-1 sh29, T9A-8 sh17, 14.2- removes a portion of EPU vibration 217, 15.1-16 monitoring cable and vibration monitoring equipment HCN 15-009 9.5, Appdx 9A 9.5-4, 27, -31, -32, -33, -34, -39, - UFSAR change reflects removal of Design Change package 80112931 instituted.

40, -40a, -40b, -41, -43, -44, -45,

  • Foxboro transponder panels and Associated 50.59 screening is included in the 54, -78, -78a, T9.5-19 sh1 & 2, the Pyrotronics System 3 panel and HCN 15-009 package.

9A-38, -59, -60 thru -65, -70, -71, replaces them with Siemens XLS

-75, -76, T9A-1 sh25 thru 36 , fire alarm panels.

T9A-8 sh2 thru 11, sh13 thru 19, sh21 thru 25, T9A-9 sh2 thru 17, sh20 thru 26, T9A-12 sh2 , 4, 8, 9, 10, 11 , 12, 15, 17, 22 - 25, 27, 28, 32 - 35, 39-42 HCN 15-010 Appendix 9A T9A-1 sh43, 48, T9A-50 sh1, UFSAR change reflects addition of Design Change package 80111348 instituted.

T9A-60 sh1, 10, T9A-61 sh1, 3 combustible load to rooms 5403 Associated 50 .59 screening and FPCRR are and 5515 to support replacement of included in the HCN 15-010 package.

PRNM system with GE NUMAC.

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 16-006 1.2, 1.6, T1 .13 , 1.2-22 , 1.6-2 , -8, T1 .13-1 sh 1, 2, UFSAR change reflects Design Change package 80107709 instituted .

1.14, T3.2 , T3.10, 7 3, 6, 8, 1.14-58, T3 .2-1 sh27, 36, replacement of the Power Range Associated 50.59 screening and FPCRR are TOC , T7.1, F7 .1, T3.10-4 sh2, 7-ii, -viii, T7.1-1 Neutron Monitoring System with a included in the HCN 16-006 package.

7.2, T7.2, 7.6, T7 .6, sh3, T7.1-2 sh2, 4, 6, F7.1 -1, 7.2- Nuclear Measurement Analysis and F7 .6, 7.7, Appendix 7 thru -13 , -20, -29 , -33, -36, -37, Control (NUMAC) based system .

9A, 15.4, Appdx T7 .2-2 sh1 , T7.2-3 sh1 , 7.6-11 150 thru -18b, -43, -44, -4 7 thru -49, T7.6-2 sh1 & 2, T7.6-3 sh1, T7.6-7 sh1, F7 .6-5, 7.7-8, -9, -12, -14, -

57, T9A-1 sh48, T9A-60 sh1 , 10, T9A-61 sh1 , 3, 15.4-5, -20, 15D-5, -8, -10 HCN 16-012 Appendix 9A T9A-1 sh 54, T9A-100 sh1 &2, UFSAR change reflects the addition Design Change package 80107617 instituted.

T9A-101 sh1 , 2 of combustible load for the Associated FPCRR is included in the HCN 16-fiberglass duplex panels being 012 package.

installed in the Hope Creek Service Water building to operate the Service Water Intake Structure (SWIS) .

HCN 17-004 12.3 12.3-52 UFSAR change reflects the deletion This change was reviewed and approved by of a sentence that references a the Radiation Protection Group who concluded table that was deleted in a previous that the changes met the NEI 98-03 criteria for change notice (HCN 17-003). a non-regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regulatory changes is included in the HCN 17~004 package.

HCN 17-005 8.1 8.1-27 UFSAR change clarifies that Class Design Change package 80120205 instituted.

1E DC power also feeds non-class Associated 50 .59 screening is included in the 1E loads as well as Class 1 E AC HCN 17-005 package.

power.

2

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 17-006 11 .5 11 .5-20 UFSAR change provides Design Change Package 80111494 instituted.

clarification as to what sources of Associated 50.59 screening is included in the dilution water are available for liquid HCN 17-006 package.

radwaste releases during outages when the cooling tower is OOS and to align with changes being made to the ODCM .

HCN 17-007 5.2 5.2-20 UFSAR change revises Section This change was reviewed and approved by 5.2.2.4.2.1.3.2 to eliminate Plant Engineering who concluded that the unnecessary detail. changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 10CFR50.59 screening was required. The Attachment 5 review form for non-regulatory changes is included in the HCN 17-007 package.

HCN 17-009 1.1, F1.1-1, 1.2, 1.1-1, F1 .1-1, 1.2-33, 4-vi, 4.4-4, - UFSAR changes reflect design Design Change package 80116382 instituted.

4.4, F4.4-1, F4.4- 5, -6, -11, F4.4-1, -1a, 5.4-14, 6.2- changes to support measurement Associated 50.59 screening and FPCRR are 1a, 5.4, 6.2, 7 .5, 5, -13, -16, -18, 7.5-8, 7.6-47, - uncertainty recapture (MUR) uprate. included in the HCN 17-009 package.

7.6, 7.7, 10.1, 10.2, 50, 7.7-24, -25, -30, -49, -51, 14.2, App9A T9A-1 sh16, T9A-6 sh1 , 10.1-3, 10.2-1, 14.2-207 HCN 17-010 9.5 9.5-31, -84 UFSAR changes reflect the This change was reviewed and approved by extension of inspection frequency Programs Engineering . A FPCRR is included for valve position verification of in the HCN 17-010 package.

class 1 and non-class 1 valves.

HCN 17-013 8.3 8.3-62, F8.3-16 UFSARchanges reflect the addition Design Change Package 80120892 instituted.

of new 250 voe HPCI System Associated 50.59 screening is included in the Analysis Calculation . HCN 17-013 package.

3

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 17-014 12.5 12.5-22 UFSAR change makes a correction This change was reviewed and approved by to page 12.5-22 which was not the Radiation Protection Group who concluded updated during the Rev. 22 update that the changes met the NEI 98-03 criteria for submittal. a non-regulatory:change and therefore no 10CFR50.59 screening was required. The Attachment 5 review form for non-regulatory thanges is inclu~ed in the HCN 17-014 package. i i

I HCN 17-015 4.2, 15.8 4.2-3, 15.8-7 UFSAR change modifies the This change was reviewed and approved by reference to the GNF-2 Compliance Nuclear Fuels who concluded that the changes Report to reflect latest revision vs. met the NEI 98-03 criteria for a non-regulatory specific revision number and date. change and therefore no 10CFR50.59 screening was required. ,The Attachment 5 review form for rion-regulatory changes is included in the HCN 17-015 package.

I I I  :

I HCN 17-016 Appendix 9A T9A-1 sh33, 34, 55, T9A-13 sh1, UFSAR change quantifies Design Change package 80120545 instituted.

2, 3 combustible loading changes from Associated FPCRR is included in the HCN 17-the Technical Support Center 016 package. :

expansion effort.

HCN 17-017 5.4, 7.6, 7.7,8.1, 5.4-3, -5, 7.6-58, 7.7-25 thru -33, UFSAR change reflects Design Change package 80115139 instituted.

9.2, 9.4, Appendix F?.7-6, 8.1-18, -23, T9.2-4 sh1, replacement of Recirc Pump MG Associated 50.5~ screening and evaluation are 9A, 15.3, 15.4, 15.9 1a, 1b, 2c, 9.4-69, -74, T9A-1 Sets with Variable Frequency Drive included in the HCN 17-017 package.

sh?, 8, 16, 38, T9A-6 sh 1, T9A- Units.

31 sh1, 15.3-6 thru -9, 15.4-7, -9,

-10, -11, 15.9-48, F15.9-18 4

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN # SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 18-001 12.3 12.3-52 UFSAR change reflects clarification This change was reviewed and approved by of air sampling requirements for Radiation Protection who concluded that the continuous air monitors changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regulatory changes is included in the HCN 18-001 package.

HCN 18-004 4 toe, 4,3, 5 toe, 4-ii, -v, 4.3-2, -3, -4, T4.3-1 sh1, UFSAR changes reflect the removal License Amendment 209 implemented .

5.3, Appendix 5A 5-xii, 5.3-6, -8, -11, -11a, -11b, - of old Pressure - Temperature (P-T) Associated 50.59 applicability and NRC Safety 17, -18, -34, F5.3-1A, -1B, -1C, Curves to correspond with TS Evaluation is included in the HCN 18-004 5A-9 Amendment 209. package.

HCN 18-006 Appendix 9A T9A-1 sh16, T9A-6 sh1 UFSAR change reflects This change was reviewed and approved by incorporation of the dress-out area Programs Engineering . A FPCRR is included into the Fire Hazards Analysis to in the HCN 18-006 package.

eliminate the need for transient combustible permits.

HCN 18-007 6.3, Appendix 150 T6.3-7 sh1 , 2, 3, 150-i, 150-1, - UFSAR change reflects Fuel Change Package 80119250 instituted .

2, -4, -6, -7 , -9 , T150-1 sh1, -2, incorporation of cycle specific Associated 50.59 screening is included in the T150-2 sh1, T150-3 sh1, T150- reload analysis results for Cycle 22 . HCN 18-007 package .

8 sh1, T150-9 sh1 , F150-1, -2, -

3 HCN 18-009 13 toe, 13.1 13-i, 13-1 thru 13-12, F13.1-2, -3, UFSAR change reflects Engineering This change was reviewed and approved by

-4 and Training organizational Human Resources and Licensing . A 10 CFR changes. 50.54( q) evaluation is included in the HCN 18-009 package.

HCN 18-010 Appendix 9A T9A-1 sh41, T9A-25 sh 1 & 6 UFSAR change incorporates This change was reviewed and approved by additional fire loading in room 5315. Programs Engineering . A FPCRR is included in the HCN 18-010 package.

5

LR-N18-0123 Summary Report Of UFSAR Changes Attachment 1 CN# SECTION AFFECTED PAGES, TABLES & DESCRIPTION BASIS FIGURES HCN 18-011 Appendix 9A T9A-1 sh16, T9A-6 sh1 UFSAR change incorporates new This change was reviewed and approved by plastic material added under DCP Programs Engineering . A FPCRR is included 80048294 into Room 3449 and Fire in the HCN 18-011 package.

Area AB3.

HCN 18-017 Appendix 9A 9A-55 UFSAR change corrects an This change was reviewed and approved by inconsistency discovered during Programs Engineering who concluded that the response to NRC triennial fire changes met the NEI 98-03 criteria fo r a non-inspection . regulatory change and therefore no 10CFR50.59 screening was required . The Attachment 5 review form for non-regu latory changes is included in the HCN 18-017 package.

HCN 18-018 9.5 9.5-159 UFSAR change removes the words, This change was reviewed and approved by "in accordance with Station Plant Engineering which concluded that the Administrative Procedures", from changes met the NEI 98-03 criteria for a non-Diesel Generator 55 gal lube oil regulatory change and therefore no drum storage requirement 10CFR50.59 screening was required . The statement to eliminate excessive Attachment 5 review form for non-regulatory detail. changes is .included in the HCN 18-018 package.

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