ML20110A005

Correction to Amendment No. 267 Issued April 10, 2020, Changes to Technical Specifications for a Permanently Defueled Condition

ML20110A005
Person / Time
Site:	Indian Point
Issue date:	04/27/2020
From:	Richard Guzman NRC/NRR/DORL/LPL1
To:	Entergy Nuclear Operations
Guzman R
References
EPID L-2019-LLA-0081
Download: ML20110A005 (4)

Text

1 April 27, 2020 Vice President, Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 450 Broadway, GSB P.O. Box 249 Buchanan, NY 10511-0249

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NOS. 2 AND 3 CORRECTION TO AMENDMENT NO. 267 ISSUED APRIL 10, 2020, RE: CHANGES TO TECHNICAL SPECIFICATIONS FOR A PERMANENTLY DEFUELED CONDITION (EPID L-2019-LLA-0081)

Dear Sir or Madam:

By letter dated April 10, 2020, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 292 and 267 to Renewed Facility Operating License Nos. DPR-26 and DPR-64 for Indian Point Nuclear Generating Unit Nos. 2 and 3 (Indian Point 2 and Indian Point 3), respectively. The amendments were in response to your application dated April 15, 2019. The amendments revised certain organization, staffing, and training requirements contained in the Technical Specifications that will not be applicable to a permanently defueled facility once Indian Point 2, and subsequently Indian Point 3, are permanently defueled.

Subsequent to issuance of these amendments, the licensee informed the NRC that there were two errors on page 5.0-8 of the clean Technical Specification pages for Indian Point 3 included with the approval letter. Specifically, the header and the subtitle on the page read Reporting Requirements, rather than Programs and Manuals, and indicated Section 5.6 rather than 5.5.

The corrected Technical Specification page 5.0-8 for Indian Point 3 is enclosed. This correction does not change any of the conclusions in the safety evaluation associated with the issuance of the amendments and does not affect the associated notice to the public.

If you have any questions, please contact me at 301-415-1030 or Richard.Guzman@nrc.gov.

Sincerely,

/RA/

Richard V. Guzman, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-247 and 50-286

Enclosure:

Corrected Unit No. 3 Technical Specification page 5.0-8 for DPR-64 cc: Listserv

ENCLOSURE CORRECTED UNIT NO. 3 TECHNICAL SPECIFICATION PAGE 5.0-8 FOR DPR-64

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued) in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2 Primary Coolant Sources Outside Containment Deleted (continued)

INDIAN POINT 3 5.0-8 Amendment No. 267

ML20110A005 OFFICE NRR/DORL/LPL1/PM NRR/DORL/LPL1/LA NRR/DORL/LPL1/BC NRR/DORL/LPL1/PM NAME RGuzman LRonewicz JDanna RGuzman DATE 04/20/2020 04/20/2020 04/27/2020 04/27/2020