LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS

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Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS
ML21323A016
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 11/18/2021
From: Jennings J
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR H21-06, LAR S21-04, LR-N21-0078
Download: ML21323A016 (7)


Text

10 CFR 50.90 LR-N21-0078 LAR S21-04 LAR H21-06 November 18, 2021 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Salem Generating Station 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:

Supplement to License Amendment Request to Revise Salem and Hope Creek Generating Station Technical Specifications (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS

Reference:

1. PSEG letter to NRC, License Amendment Request - Revision of Salem and Hope Creek Generating Station Technical Specification (TS) to Delete Definitions found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS, dated September 29, 2021 (ADAMS Accession No. ML21272A184)

In the Reference 1 letter, PSEG Nuclear LLC (PSEG) submitted a license amendment request (LAR) to Renewed Facility Operating License Nos. DPR-70 and DPR-75 for Salem Generating Station Units 1 and 2 respectively and NPF-57 for Hope Creek Generating Station. The proposed amendment would revise Technical Specifications (TS) to remove Definitions for Members(s) of the Public, Site Boundary, and Unrestricted Area which are already present in the definitions found in the Offsite Dose Calculation Manual for each site as well as 10 CFR 20.1003.

The Reference 1 LAR inadvertently overlooked explicit descriptions of changes to associated TS Sections that require revision as a result of the removal of the above three terms from the Definitions section of TS in the list of proposed changes. In addition, although the attachments to Reference 1 depicted all the required TS changes in the TS markups, use of capitalization was not consistent in the mark ups as discussed below.

LR-N21-0078 10 CFR 50.90 Page 2 Based on the above oversights, PSEG is providing this supplement to Reference 1 to identify the following corrections. Added text is shown in bold underlined italics and deleted text is shown as a strikethrough.

Reference 1 Section 2.3:

o The first bullet should read as follows:

TS INDEX to remove deleted DEFINITIONS, change the Index title for TS Section 5.1 from SITE to SITE LOCATION and delete line items in the Index for Section 5.1 associated with deleted TS Figures.

o Add a new bullet to read:

TS Section 6.8.4.h - Radiological Environmental Monitoring Program

- Replace capitalized font for the term SITE BOUNDARY that is referenced within TS 6.8.4.h with normal (non-capitalized) font to reflect its deletion from TS DEFINITIONS.

Reference 1 Section 2.6:

o Correct the first and second bullet to read:

TS 5.1.1 - EXCLUSION AREA AND MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADIOACTIVE GASEOUS AND LIQUID EFFLUENTS - Deleted and replaced with new Section 5.1 - SITE DESCRIPTION LOCATION TS 5.1.2 - LOW POPULATION ZONE - Deleted and replaced with new Section 5.1 - SITE DESCRIPTION LOCATION o Add new bullets to read:

TS INDEX to remove deleted DEFINITIONS, change the Index title for TS Section 5.1 from SITE to SITE LOCATION and delete line items in the Index for Section 5.1 associated with deleted TS Figures.

TS Section 6.8.4.h - Radiological Environmental Monitoring Program

- Replace capitalized font for the term SITE BOUNDARY that is referenced within TS 6.8.4.h with normal (non-capitalized) font to reflect its deletion from TS DEFINITIONS.

of Reference 1 provided markups of the Salem Unit 2 TS to reflect the proposed changes. The markup of Unit 2 TS Index Section 5.1 for SITE LOCATION did not use upper case font. Attachment 1 to this supplement provides a corrected markup of this TS page.

of Reference 1 provided markups of the Hope Creek TS to reflect the proposed changes. The markup of Hope Creek TS Index Section 5.1 for SITE LOCATION did not use upper case font. Attachment 2 to this supplement provides a corrected markup of this TS page.

PSEG has determined that the information provided does not alter the conclusions reached in the 10 CFR 50.92 no significant hazards determination previously submitted. In addition, the information provided in this submittal does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.

There are no regulatory commitments contained in this letter.

LR-N21-0078 Page 3 10 CFR 50..90 If you have any questions or require additional information, please contact Mr. Michael Wruel at 856-339-7907.

I declare under penalty of perjury that the foregoing is true and correct Executed on

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(Date)

Respectfully, f !};/

Jason Jennings Director -Site Regulatory Compliance PSEG Nuclear : Corrected Mark-up of Proposed Salem Unit 2 Technical Specification Page : Corrected Mark-up of Proposed Hope Creek Technical Specification Page cc:

Administrator, Region I, NRC NRC Project Manager NRC Senior Resident Inspector, Salem NRC Senior Resident Inspector. Hope Creek Ms. A. Pfaff, Manager, NJBNE PSEG Corporate Commitment Tracking Coordinator Station Commitment Tracking Coordinator

LR-N21-0078 10 CFR 50.90 Corrected Mark-up of Proposed Salem Unit 2 Technical Specification Page The following Technical Specification page for Renewed Facility Operating License DPR-75 is affected by this supplement:

Technical Specification Page INDEX XVII

DESIGN FEATURES

=================================================================

SECTION 5.l SITE Exclus'ion Area 5-1 Low Population zone 5-1 Unrestricted Areas for Radioactive Gaseous and Liquid Effluents 5-1 5

  • 2 CONTAINMENT Configuration 5-l Design Pressure and Temperature 5-4 5.3 REACTOR CORE Fuel Assemblies 5-4 Control Rod Assemblies 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature 5-4
5. 5 METEOROLOGICAL TOWER LOCATION
  • 5-5 5.6 FUEL STORAGE
  • Criticality

.. 5-5 Drainage 5-5b Capacity.

5-5b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5-5b SALEM -

UNIT 2 XVII Amendment No. 250 SITE LOCATION........................................................................5-1

LR-N21-0078 10 CFR 50.90 Corrected Mark-up of Proposed Hope Creek Technical Specification Page The following Technical Specification page for Renewed Facility Operating License NPF-57 is affected by this supplement:

Technical Specification Page INDEX xxiii

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area and Map Defining Unrestricted Area and Site Boundary for Radioactive Gaseous and Liquid Effluents............................5-1 Figure 5.1.1 1 Exclusion Area and Unrestricted Areas and Site Boundary for Radioactive Gaseous and Liquid Effluents........................................................5-2 Low Population Zone..................................................................................5-1 Figure 5.1.2 1 Low Population Zone................................................5-3 5.2 CONTAINMENT Configuration..............................................................................................5-1 Design Temperature and Pressure.............................................................5-1 Secondary Containment.............................................................................5-1 5.3 REACTOR CORE Fuel Assemblies.........................................................................................5-4 Control Rod Assemblies.............................................................................5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature.............................................................5-4 Volume.......................................................................................................5-5 5.5 METEOROLOGICAL TOWER LOCATION...........................................................5-5 5.6 FUEL STORAGE Criticality.....................................................................................................5-5 Drainage.....................................................................................................5-5 Capacity.....................................................................................................5-5 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT...................................................5-5 Table 5.7.1 1 Component Cyclic or Transient Limits.......................5-6 HOPE CREEK xxiii Amendment No. 184 SITE LOCATION............................................................................5-1