ML17157B265

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Submittal of Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases Changes, 10CFR54.37(b) Review Results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Repor
ML17157B265
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 05/09/2017
From: Duke P
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17157B235 List:
References
LR-N17-0088
Download: ML17157B265 (18)
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 LR-N 17-0088 May 9, 2017 United States Commission Document Control Desk

TS 6.15.d 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 Hope Creek Generating Station Updated Final Safety Analysis Report, Revision 22, Hope Creek Technical Specification Bases changes, 10 CFR 54.37(b) review results for Hope Creek and PSEG Nuclear LLC Quality Assurance Topical Report, NO-AA-10, Revision 86 PSEG Nuclear LLC (PSEG) hereby submits:

CD Enclosure 1, CD-1, contains Security Related Information

-Withhold Under 10 CFR 2.390. When separated from CD-1, this document is decontrolled.

Page2 LR-N17-0088 10 CFR 50.71(e.)

10 CFR 50.54(a)(3) 10 CFR 54.37(b) 10 CFR 71.106 TS 6.15.d

  • A complete updated copy of the Hope Creek Technical Specification Bases, which includes changes through May 9, 2017, 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 Revision No. 22 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 November 11, 2016, 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 . 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 November 9, 2015. 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 22 of the UFSAR for security-related information (SRI). Consequently, Revision 22 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 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.

A list of what material has been redacted is provided in Attachment

2. PSEG has developed Revision 86 of the SHC Quality Assurance Topical Report, which governs the QAP. This version of the SHC QATR, NO-AA-10, replaces the previous version submitted to you in PSEG letter LR-N17-0034 dated January 30, 2017. ' The change to the QATR is being made in accordance with the requirements of 10 CFR 50.54(a)(3) and 10 CFR 71.106(b).

The change involved no reduction in commitments and therefore did not require prior NRC approval.

10 CFR 50.54(a)(3) requires that changes that do not reduce the commitments be submitted in Page 3 t.R-N 17-0088 10 CFR 50.71 (e) 10 CFR 50.54(a)(3) 10 CFR 54.37(b) 10 CFR 71.106 TS 6.15.d accordance with 10 CFR 50.71(e).

Revision 86 is the current version of the QATR that is in use at PSEG, and became effective on February 24, 2017. A summary of the changes made to the QATR in Revision 86 is provided in Enclosure 1 of this letter. Enclosure 2 of this letter provides a copy of Revision 86 of the QATR for information purposes.

Enclosure 3 contains a complete updated copy of the Hope Creek Technical Specification Bases with changes through May 9, 2017. An evaluation was completed to determine whether any newly-identified SSCs existed in support of submitting Hope Creek UFSAR Revision 22. This evaluation involved reviewing pertinent documentation for the period subsequent to the last Hope Creek UFSAR revision.

The evaluation concluded that there were no 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 22, 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, Paul Duke Manager, Licensing PSEG Nuclear, LLC Attachments:

1. Summary Report of UFSAR Changes 2. List of Redacted Material 1111 -, I '4 Page 4 LR-N 17-0088 CD

Enclosures:

10 CFR 50.71(e) 10 CFR 50.54(a)(3) 10 CFR 54.37(b) 10 CFR 71.106 TS 6.15.d 1. CD-1, Hope Creek UFSAR Rev. 22 (withhold from public disclosure)

2. CD-2, Hope Creek UFSAR Rev. 22 (redacted version suitable for public disclosure)

Other

Enclosures:

1. Quality Assurance Topical Report, NO-AA-10, Revision 86 Summary Of Changes 2. Quality Assurance Topical Report, NO-AA-10, Revision 86 3. Hope Creek Generating Station Technical Specification Bases as of May 9, 2017 CC (Cover letter, CD enclosures 1 and 2, Other Enclosures 1 and 2 and Attachments 1 and 2) Administrator

-Region I -USNRC Licensing Project Manager -Hope Creek -USN RC USN RC Senior Resident Inspector

-Hope Creek Chief, New Jersey Bureau of Nuclear Engineering (Cover letter, Other Enclosures 1 and 2 only) Director, Division of Spent Fuel Management, Office of Nuclear Material . Safety and Safeguards

-USNRC (Cover letter, Attachment 1, Other Enclosures 1 and 2 only) USN RC Senior Resident Inspector

-Salem Licensing Project Manager -Salem -USNRC (Cover letter and Attachment 1 only) Salem Commitment Coordinator Hope Creek Commitment Coordinator Corporate Commitment Coordinator

(

  • LR-N17-0088 Attachment 1 Summary Report of UFSAR Changes LR-N17-0088 Attachment 1 CN # SECTION HCN 10-013 Appendix 9A HCN 10-016 7.5 HCN 12-011 Appendix 9A HCN 13-001 Appendix 9A HCN 13-004 11.5 HCN 13-016 Appendix 9A HCN 14-005 10.4 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES 9A-84, T9A-1 sh55, T9A-102 sh1 T7.5-1 sh1 T9A-1 sh16, T9A-6 sh1 T9A-1 sh33, T9A-12 sh1 11.5-21, 22, T11.5-1 st:i 3, 4, 5 & 6 T9A-1sh40, 48, T9A-41 sh1, T9A-61 sh1, 3 10.4-37, 38 DESCRIPTION DCP adds combustible loads to SW intake structure.

UFSAR change reflects replacement of existing control room recorder on HPCI panel with a new design digital indicator.

UFSAR change reflects the addition of combustable load due to cable insulation.

UFSAR change reflects an upgrade of the RWCU Filter/Dem in System Control Panels and Instrument Rack. UFSAR change reflects modification of the Rad monitor system with new detectors/samplers and updates to local Rad processors.

UFSAR change reflects installation of 2 level measuring instruments for continuous wide range Spent Fuel Pool level. UFSAR change reflects FFWTR changes adding extraction steam drain lines and throttle valves in condensate lines. 1 BASIS Design Change packages 80101055 ins.tituted.

Associated 50.59 screening and FPCRR are included in the HCN 10-013 package. Design Change package 80098173 ins.tituted.

Associated 50.59 screening is included in the HCN 10-016 package. Design Change package 80106473 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 12-011 package. Design Change package 80106771 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 13-001 package. Design Change package 80107149 instituted.

Associated 50.59 screening is included in the HCN 13-004 package. Design Change package 80109771 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 13-016 package. Design Change package 80110870 instituted

.. Associated 50.59 screening is included in HCN 14-005 package.

LR-N 17 -0088 Attachment 1 CN# HCN 14-006 HCN 14-020 HCN 15-001 HCN 15-005 HCN 15-006 HCN 15-018 8.3, 9.3 9.5 1.13, 9.5, Appendix 9A 8.2 8.2 Appendix 9A Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES &

  • FIGURES 8.3-10, 14, 9.3-2, -3, -4, -6, T9.3-1 sh2, 3, 4 9.5-26 1.13-4, 9.5-40, T9A-1sh?,8, 11, 37, 46, 8.2-1 8.2-1 T9A-1 sh25, 31, T9A-8 sh1, 22, T9A-9 sh1, 4 DESCRIPTION UFSAR change reflects replacement of existing Emergency Instrument Air Compressor and Instrument Air Dryers. UFSAR change updates the description of the valve connecting Salem Fire Protection water supply system to the HC Fire Protection yard loop. UFSAR change reflects removal of 42 C02 Hose Reels which were abandoned in place by DCP 80075623.

UFSAR change reflects revision of the description of the Salem-Hope Creek 500 kV tie line protective relays. UFSAR changes reflect the revision of the description of the Hope Creek 500 kV tie line trip signal initiating signal initiating conditions.

UFSAR changes reflect revision of the Fire Hazzard Analysis to account for addition of lube oil in FLEX pumps and air compressor installed in Room 4104. 2 BASIS Design Change package 8011077 4 instituted.

Associated 50.59 is included in the HCN 14-006 package. Design Change Package 80111494 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 14-020 package. Design Change package 80112930 instituted.

Associated 50.59 screening is included in the HCN 15-001 package. Design Change package 80105810 instituted.

Associated 50.59 screening is included in the HCN 15-005 package. Design Change package 80112861 instituted.

Associated 50.59 screening is included in the HCN 15-006 package. Design Change Package 80112012 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 15-018 package.

LR-N 17-0088 Attachment 1 CN # SECTION HCN 15-019 7.3 HCN 15-020 1 .14 HCN 15-021 9.1 HCN 15-023 Appendix 9A Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES T7.3-16 sh2 1.14-105 9.1-136 T9A-1 sh14, 18, 22, 47, T9A-6 sh1, T9A-60 sh1, 3 DESCRIPTION UFSAR change replaces reference to deleted TS Table 3.6.3-1 with reference to TRM Table 3.6.3-1. UFSAR change removes a reference to deleted TS 4.1.3.2 and replaces it with* a reference to the current applicable TS. UFSAR change corrects an inconsistency between UFSAR Section 9.1.5.3.3 and TS 3.5.1 Action C.1. UFSAR change reflects the addition of combustible loading to several rooms associated with the DCP. 3 BASIS This change was reviewed and approved by Plant Engineering who concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 15-019 package. This change was reviewed and approved by Regulatory Compliance who concluded that the changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 15-020 package. This change was reviewed and approved by Reactor Engineering who concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 15-021 package. Design Change package 80114148 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 15-023 package.

1 * -LR'N17-0088 I Attachment 1 I i CN # SECTION HCN 15-024 9.3, 10.4 HCN 15-025 6.2 HCN 15-026 6.2, 7.6 HCN 15-027 7.5 HCN 16-001 9.5 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES 9.3-32, 10.4-34 F6.2-27 sh31 T6.2-26 sh1, 3, F6.2-47 sh 1, 2, 7.6-34, -35 7.5-8 9.5-110 DESCRIPTION UFSAR change replaces references to Tech Specs information that was relocated to UFSAR section 5.2. UFSAR change reflects revision of figure to show the torus vent discharging vertically.

UFSAR changes reflect plant configuration to maintain core cooling and heat removal and spent fuel pool cooling in support of Beyond Design Bases (Fukushima) event required by NRG Enforcement Action EA-12-049.

Change reflects replacement of 3D Monicore computer with GNF supplied ACUMEN Process Computer.

Change reflects replacement of light fixtures from fluorescent to LED. 4 BASIS This change was reviewed and approved by Plant Engineering who concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 15-024 package. Design Change package 80115583 instituted.

Associated 50.59 screening is included in the HCN 15-025 package. Design Change package 80110321 instituted.

Associated 50.59 screening is included in the HCN 15-026 package. Design Change package 80114728 instituted.

Associated 50.59 screening is included in the HCN 15-027 package. Design Change package 80116185 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 16-001 package.

LR-N17-0088 Attachment 1 . CN # SECTION HCN 16-002 Appendix 9A HCN 16-003 Appendix 9A HCN 16-005 9.5 HCN 16-007 13.2 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES 9A-32, T9A-8 sh18, T9A-9 sh20 T9A-14 sh1 9.5-111, -112, -113, -114, -115, -117 13.2-1 DESCRIPTION UFSAR change provides clarifying information and updates procedure information in App. 9A. UFSAR change deletes reference to fire pre plans procedures and replaces them with a reference to procedure HC.OP-AB.FIRE-0001.

Additional changes to text for clarification are also made. UFSAR change re-names "8-hr battery-backed lights" to contained battery-backed Shutdown lighting units" to improve clarity and eliminate unnecessary detail. UFSAR change revises wording for description of Supervisory Training to reflect replacement of ACAD 90-. 010 with a new ACAD. 5 BASIS This change was reviewed and approved by Design Engineering who concluded that the changes were controlled by the Fire Protection Program and therefore no 1 OCFR50.59 screening was required.

The FPCRR is included in the HCN 16-002 package. This change was reviewed and approved by Design Engineering who concluded that the changes were controlled by the Fire Protection Program and therefore no 1 OCFR50.59 screening was required.

The FPCRR is included in the HCN 16-003 package. This change was reviewed and approved by Design Engineering which concluded that the chan*ges met the NEI 98-03 criteria for a regulatory change arid therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 16-005 package. This change was reviewed and approved by Training who concluded that the changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 16-007 package.

LR-N 17-0088 Attachment 1 CN # SECTION HCN 16-008 Appendix A HCN 16-009 6.2 HCN 16-010 6.4, 7.3 HCN 16-011 13.5 HCN 16-013 Appendix 9A Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES T9A-1 sh 43, T9A-15 sh 5 T6.2-30 sh8 6.4-15, 7.3-56 13.5-1 T9A-1 51, 53, T9A-7 4 sh1, T9A-98 sh1 DESCRIPTION UFSAR change reflects removal of fire extinguisher 83425-1 from Room 3425 and replacement with alternate extinguisher already installed.

UFSAR change eliminates a duplicate entry of GS-V080 containment side flange. UFSAR change adds information for manual trip of CREF fans prior to manual initiation of deluge flow and deletes information related to deluge trip indication.

UFSAR change removes requirement for LS-AA-106 Att 4 procedures to receive PORC approval.

UFSAR change revises tables to correct identification of water spray fire suppression systems for CREF units as manual vs. current description as automatic.

6 BASIS This change was reviewed and approved by Engineering Programs who concluded that the changes were controlled by the Fire Protection Program and therefore no 1 OCFR50.59 screening was required.

The FPCRR is included in the HCN 16-008 package. This change was reviewed and approved by Design Engineering which concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 10CFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 16-009 package. Design Change package 80117295 instituted.

Associated 50.59 screening and FPCRR are included in the HCN 16-010 package. This change was reviewed and approved by Operations who concluded that the changes were controlled by the Quality Assurance Program and therefore no 1 OCFR50.59 screening was required.

The 1 OCFR50.54(a) evaluation is included in the HCN 16-011 package. This change was reviewed and approved by Programs Engineering which concluded that the changes met the NEI 98-03 criteria for a non-regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 16-013 package.

LR-N 17-0088 Attachment 1 CN # SECTION HCN 16-014 1.15 HCN 16-015 1.8, 7.5 HCN 16-016 9.5, 12.113TOC, 13.1 HCN 16-017 Appendix 9A HCN 16-018 1.8, 1.10, 9.5, 13.1 HCN 16-019 1.8, 8.1 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES 1.15-2 1.8-93, -103, -104, -105, -106, -107, T7.5-1 sh2, 2a, 3, 3a, 23 9.5-61, -62, 12.1-1, 13-1, 13.1-1, -2, -3, -9, -10, -11, T13.1-1 sh1, F13.1-2, -3, -4 T9A-2 sh?, 8, T9A-3 sh6, 9, 14, T9A-12 sh1 1.8-4, 1.10-19, 9.5-62, 13.1-10, F13.1-3

-59, 8.1-27 DESCRIPTION UFSAR change adds wording to state that the GOTHIC computer program can be used to determine room temperature upon loss of ventillation.

UFSAR change removes Neutron Monitoring from the RG 1.97 conformance description.

UFSAR change reflects organizational and job title changes. UFSAR change includes justification for tubing associated with redundant Rx press and level instrumentation credited for Safe Shutdown in fire area RB5. UFSAR change reflects oganizational changes affecting Nuclear Oversight (NOS). UFSAR change adds a statement to indicate conformance to IEEE 384-1992 endorsed by RG 1. 75 R3 in support of the DCR to exempt testable check valves from the EQ Program. 7 BASIS Design Change package 80117351 instituted.

Associated 50.59 screening is included in the

  • HCN 16-014 package. Design Change package 80117905 instituted.

Associated 50.59 screening is included in the HCN 16-015 package. Associated 50.59 screening is included in the HCN 16-016 package. This change was reviewed and approved by Design Engineering who concluded that the changes were controlled by the Fire Protection Program and therefore no 10CFR50.59 screening was required.

The FPCRR is

  • included in the HCN 16-017 package. This change was reviewed and approved by Corporate Licensing, Engineering Programs and Human Resources who concluded that the changes were controlled by the Quality Assurance Program and therefore no 1 OCFR50.59 screening was required.

The 1 OCFR50'.54(a) evaluation is included in the HCN 16-018 package. Design Change package 80117908 instituted.

Associated 50.59 screening is included in the HCN 16-019 package.

LR-N17-0088 Attachment 1 CN# SECTION HCN 16-021 1.8, 8.3 HCN 16-022 Appendix 9A HCN 16-023 4.2, 4.3, 4.4, 6TOC, 6.3, 15.3, 15.8 HCN 16-024 Appendix 9A HCN 16-025 11.5 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES 1.8-133, 8.3-34 T9A-1 sh31, T9A-9 sh1, 26 4.2-1, -3, 4.3-1, 4.4-1, 6-xxi, -xxiii, 6.3-42, -43, -44, -51, T6.3-2 sh4, 6, T6.3-3 sh1, T6.6-3a sh1, T6.3-7 sh1, F6.3-14, -20, -21, -22, -23, -38, -39, -40, -41, 15.3-11, 15.8-1, -7 9A-61, -62, T9A-1 sh31, T9A-8 sh1, 21 11.5-27, T11.5-1 sh5 DESCRIPTION UFSAR change removes the specific 18 month frequency requirement for testing EDG lockout features.

UFSAR change incorporates additional combustible loading of the Operations locker in the Fire Plan. UFSAR change incorporates the transition from GE-14 to GNF2 nuclear fuel design. UFSAR change reconciles discrepancies identified and corrects floor area for rooms 4626 and 4333 and removes duplicate information.

UFSAR change reflects the replacement of the hardened torus vent rad monitor from GM tube to ion chamber detector which is qualified for a higher total integrated dose. 8 BASIS This change was reviewed and approved by Design Engineering. A 1 OCFR50.59 screening is included in the HCN 16-021 package. This change was reviewed and approved by Programs Engineering who concluded that the changes were controlled by the Fire Protection Program and therefore no 1 OCFR50.59 screening was required.

The FPCRR is included in the HCN 16-022 package. Design Change package 80105965 instituted.

Associated 50.59 screening is included in the HCN 16-023 package. This change was reyiewed and approved by Programs Engineeri_ng who concluded that the changes were contrplled by the Fire Protection Program and therefore no 1 OCFR50.59 screening was required.

The FPCRR is included in the HCN 16-024 package. Design Change package 80113942 instituted.

Associated 50.59 screening is included in the HCN"16-025 package.

LR-N17-0088 Attachment 1 CN # SECTION HCN 16-026 6.4, 15.4, 15.6, 15.7 HCN 16-027 Appendix 150 HCN 16-028 MTOC HCN 17-002 12.5, 13.2 HCN 17-003 12 TOC, 12.3, 12.4, 12.5 Summary Report Of UFSAR Changes AFFECTED PAGES, TABLES & FIGURES T6.4-4 sh1, T15.4-10 sh1, T15.6-16 sh1-, T15.7-8 sh1 150-i, -iv, -1, -2, -4 thru 10, T150-1, -2, -4, -8, -9, F150-1, -2, -3 vi 12.5-22, -23, 13.2-2 12-xix, 12.3-15, -32, -51, -52, 12.4-10, 12.5-1, -6, -7, -8, -10, -11, -15, -20, T12.5-1 sh1, T12.5-2 sh1 DESCRIPTION UFSAR change reflects revised dose rates associated with the implementation of FFWTR and changes due to the addition of GNF2 fuel. UFSAR change incorporates cycle specific reload analysis results for Cycle 21. UFpAR change incorporates corrections created by a previous HCN. UFSAR change reflects the implementation of NEI EB 16-26b, "Standardization of lnprocessing Training", to eliminate reference to annual requal training.

UFSAR change updates Section 12 information erroneously made -historical in a previous change. 9 BASIS Design Change package 80116066 instituted.

Associated 50.59 screening and evaluation are included in the HCN 16-026 package. Fuel Change package 80114953 instituted.

Associated 50.59 screening is included in the HCN 16-027 package. This change was reviewed and approved by Corporate Licensing which concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 10CFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 16-028 package. This change was reviewed and approved by Nuclear Training and Radiation Protection.

A 1 OCFR50.59 screening is included in the HCN 17 -002 package. This change was reviewed and approved by Radiation Protection which concluded that the changes met the NEI 98-03 criteria for a regulatory change and therefore no 1 OCFR50.59 screening was required.

The Attachment 5 review form for non-regulatory changes is included in the HCN 17-003 package.

"'j* . :' '

17-0088 Attachment 2 List of Redacted Material LR-N 17-0088 Attachment 2

  • UFSAR Chapter 2.2 2.2 2.2 2.2 2.2 2.2 2.4 2.4 2.4 2.4 2.4 2.4 3.3 3.5 3.5 3.5 3.5 3.5 3.5 3.5 List of Redacted Material Section 2.2.3.1 (Determination of Design Basis Events) 2.2.3.1.1 (Explosions) 2.2.3.1.2 (Flammable Vapor Clouds) Table 2.2-4 (Hazardous Chemicals Stored at Salem Generating Station) Table 2.2-5 (Estimates of Hazardous Chemical Traffic) Table 2.2-6 (Chemicals Stored at Hope Creek
  • Site) 2.4.4.1.1 (Single Dam Failures) 2.4.4.2.1

((Single Dam Failures) 2.4.4.2.2 (Multiple Dam Failures)

Table 2.4-8 (Single Dam Failures)

Table 2.4-17 (Private Wells in Vicinity of the Site) Figure 2.4-28 (Known Water Wells In Vicinity Of the Site) Table 3.3-2 (Tornado Protected Structures, Systems, and Components) 3.5.1.6.4 (Effective Impact Area) 3.5.1.6.6 (Helicopter Impact Methodology) 3.5.3 (Barrier Design Procedures)

Table (Target Parameters)

Table 3.5-5 (Turbine Barrier Data) Table 3.5-6 (Target Barrier Data) Figure 3.5-6 (Target and barrier Geometry) 1 Page{s} 2.2-9 and 2.2-1 O 2.2-11 and 2.2-12 2.2-12 and 2.2-13 Sheet 1 of 1 Sheets 1 and 2 of 2 Sheet 1 of 1 2.4-17 2.4-21 and 2.4-22 2.4-22 Sheet 1 of 1 Sheets 1, 2 and 3 of 3 Sheet 1 of 1 Sheets 1 and 2 of 2 3.5-51 and 3.5-52 3.5-53, 54, 55, 57 3.5-58 Sheets 1 and 2 of 2 Sheet 1 of 1 Sheet 1 of 1 Sheet 1 of 1 I I\ LR-N 17-0088 Attachment 2 UFSAR Chapter 3.5 3.5 3.5 3.5 6.4 8.2 8.2 8.2 8.2 8.2 Appendix 9A Appendix 9A 11.2 12.3 12.3 12.3 12.3 12.3 12.3 Section Page(s} Figure 3.5-10 (Target and Barrier Geometry)

Sheet 1 of 1 Figure 3.5-17 (Helicopter Glide Paths) * *Sheet *1 0f 1 Figure 3.5-18 (Helicopter Glide Distances)

Sheet 1 of 1 Figure 3.5-19 (Schematic of Heliport Flight Sheet 1 of 1 Path and BuildinQ of Concern) Figure 6.4-2 (Plant Layout with Respect to Sheet 1 of 1 Control Room Intake) 8.2.1.1 (Transmission Systems) 8.2-1 and 8.2-2 8.2.1.3 (Main Transformer Leads) 8.2-3 8.2.1.4 (Switchyard) 8.2-3 thru 8.2-6 8.2.1.5.1 (Switchyard Control House) 8.2-8 8.2.2 (Analysis) 8.2-10 Figure 9A-12 (Lower Control Equipment Sheet 1 of 1 Room, Elevation 102'-0") Figure 9A-12 (Upper Control Equipment Sheet 1 of 1 Room, Elevation 163'-6")

Figure 11.2-6 (Liquid Radwaste Drain and Sheet 1 of 1 CoolinQ Tower Slowdown Pipe Locations)

Figure 12.3-22 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 Plan -El. 155'-6") Figure 12.3-23 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 Plan -El. 77'-0") Figure 12.3-24 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of.1 Plan -El. 102'-0") Figure 12.3-25 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 Plan -El. 124' -0", 130' -0") Figure 12.3-26 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 Plan -El. 137'-0", 150'-0") Figure 12.3-27 (Control*&

Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 Plan -El. 178'-0") 2 LR-N 17-0088 Attachment 2 UFSAR Chapter 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.3 12.5 Section Page(s) Figure 12.3-28 (Control & Diesel Generator Area Shielding

& Radiation Zoning Drawing Sheet 1 of 1 . F?.lan "."" !;I. 54'-0") Figure 12.3-29 (Site Plan Shielding

& . Sheet 1 of 1 Radiation Zoning Drawing) Figure 12.3-60 (Equipment Location Turbine Sheet 1 of 1 Building Plan EL. 137'-0" Figure 12.3-61 (Equipment Location Turbine Sheet 1 of 1 Building Plan EL. 102'-0") Figure 12.3-62 (Equipment Location Turbine Sheet 1 of 1 Building Plan EL. 77'-0") Figure 12.3-63 (Equipment Location Turbine Sheet 1 of 1 Building Plan EL. 54'-0") Figure 12.3-65 (Equipment Location Turbine Sheet 1 of 1 Building Plan EL. 145'-0") Figure 12.3-67 (Equipment Location Reactor Sheet 1 of 1 Building Unit 1 -Plan EL. 102'-0") Figure 12.3-68 (Equipment Location Reactor Sheet 1 of 1 Building Unit 1 -Plan EL. 77'-0") Figure 12.3-69 (Equipment Location Service & Sheet 1 of 1 Radwaste Area -Plan EL. 102' -0) Figure 12.3-70 (Equipment Location Service & Sheet 1 of 1 Radwaste Area -Plan EL. 124' -0") Figure 12.3-71 (Equipment Location Service & Sheet 1 of 1 Radwaste Area -Plan EL. 54'-0")

  • Figure 12.5-3 (Access Control -Radiation Sheet 1 of 1 Protection and Chemistry Facilities) 3
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