ML22056A010

From kanterella
Jump to navigation Jump to search

and Salem Nuclear Generating Station, Unit Nos. 1 and 2; Correction Letter of Amendment Nos. 230, 342, and 323 Deletion of Specified Definitions and Figures
ML22056A010
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 03/04/2022
From: James Kim
Plant Licensing Branch 1
To: Carr E
Public Service Enterprise Group
Kim J
References
EPID L 2021 LLA-0171
Download: ML22056A010 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON , D.C. 20555-0001 March 4, 2022 Mr. Eric Carr President and Chief Nuclear Officer PSEG Nuclear LLC - N09 Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION AND SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 CORRECTION LETTER OF AMENDMENT NOS. 230, 342, AND 323 RE: DELETION OF SPECIFIED DEFINITIONS AND FIGURES (EPID L-2021-LLA-0171)

Dear Mr. Carr:

By letter dated February 14, 2022 (Agencywide Documents and Access System (ADAMS)

Accession No. ML22012A435), the U.S. Nuclear Regulatory Commission (NRC, the Commission) issued the Amendment Nos. 230, 342, and 323 to Renewed Facility Operating License Nos. NPF-57, DPR-70, and DPR-75 for the Hope Creek Generating Station (Hope Creek), and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem), respectively. The amendments revised the Hope Creek and Salem technical specifications (TSs) to remove TS definitions for Member(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 Title 10 of the Code of Federal Regulations, Part 20, Section 1003. The amendments also removed figures of the site and surrounding area from the TSs.

The NRC staff has identified an error on one of the Index pages. The page in question is Hope Creek Index page i, and the error is on Section 1.13 - EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME. The recently issued Amendment No. 230 shows a page number of 1-2 for this section where the correct page number should be 1-3.

The NRC staff has concluded that the error was introduced during the preparation of the license amendment. The correction does not change any of the conclusions in the safety evaluation associated with the amendment and does not affect the associated notice to the public.

E. Carr The corrected Hope Creek Index Page i of the Amendment No. 230 is enclosed with this letter.

If you have any questions, please contact me at 301-415-4125 or James.Kim @nrc.gov.

Sincerely,

/RA/

James S. Kim, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-354, 50-272, and 50-311

Enclosure:

As stated cc: Listserv

DEFINITIONS SECTION 1.0 DEFINITIONS ................................................................................................................................ PAGE 1.1 ACTION ............................................................................................................................................... 1-1 1.2 DELETED ............................................................................................................................................ 1-1 1.3 AVERAGE PLANAR LINEAR HEAT GENERATION RATE ............................................................... 1-1 1.4 CHANNEL CALIBRATION .................................................................................................................. 1-1 1.5 CHANNEL CHECK ............................................................................................................................. 1-1 1.6 CHANNEL FUNCTIONAL TEST ......................................................................................................... 1-1 1.7 CORE ALTERATION .......................................................................................................................... 1-2 1.8 DELETED ............................................................................................................................................ 1-2 1.9 CORE OPERATING LIMITS REPORT ............................................................................................... 1-2 1.10 CRITICAL POWER RATIO ................................................................................................................ 1-2 1.11 DOSE EQUIVALENT I-131 ................................................................................................................ 1-2 1.11.1 DRAIN TIME ................................................................................................................................. 1-2a 1.12 E-AVERAGE DISINTEGRATION ENERGY .................................................................................... 1-2a 1.13 EMERGENCY CORE COOLING SYSTEM (ECCS) RESPONSE TIME ........................................... 1-3 1.14 END-OF-CYCLE RECIRCULATION PUMP TRIP SYSTEM RESPONSE TIME .............................. 1-3 1.15 DELETED ........................................................................................................................................... 1-3 1.16 DELETED ........................................................................................................................................... 1-3 1.17 FREQUENCY NOTATION ................................................................................................................. 1-3 1.18 IDENTIFIED LEAKAGE ..................................................................................................................... 1-3 1.18.1 INSERVICE TESTING PROGRAM ................................................................................................ 1-3 1.19 ISOLATION SYSTEM RESPONSE TIME ......................................................................................... 1-3 1.20 LIMITING CONTROL ROD PATTERN .............................................................................................. 1-3 1.21 LINEAR HEAT GENERATION RATE ................................................................................................ 1-4 1.22 LOGIC SYSTEM FUNCTIONAL TEST .............................................................................................. 1-4 1.23 DELETED ........................................................................................................................................... 1-4 1.24 Not Used 1.25 MINIMUM CRITICAL POWER RATIO ............................................................................................... 1-4 HOPE CREEK i Amendment No. 230

ML22056A010 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME JKim KEntz JDanna JKim DATE 2/28/2022 2/28/2022 03/04/2022 03/04/2022