GNRO-2008/00072, Report of Changes and Errors to 1OCFR50.46

Report of Changes and Errors to 1OCFR50.46

ML083190090
Person / Time
Site:	Grand Gulf
Issue date:	11/12/2008
From:	Larson M Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2008/00072
Download: ML083190090 (3)

Text

..Entergy

-===- Entergy Operations, Inc.

PO Box 756 Port Gibson, MS 39150 Tel 601 437 2800 GNRO-2oo8/oo072 November 12, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001

Subject:

Report of Changes and Errors to 10CFR50.46 Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29

References:

1. Letter GNRD-2oo7/oo074, "Report of Changes and Errors to 10CFR50.46," dated October 25,2007

2. Letter GNRD-2oo7/00071, "License Amendment Request (LAR) Changes to Technical Specification 5.6.5 - Core Operating Limits Report (COLR)," dated December 5, 2007

3. Letter GNRO-2oo8-00061, "Supplement 2 to Amendment Request Changes to Technical Specification 5.6.5, "Core Operating Limits Report (COLR)," dated August 28,2008.

4. Letter GNRI-2oo8loo083, "Issuance of Amendment Re: Changes Technical Specification 5.6.5 - Core Operating Limits Report (COLR)," dated October 16, 2008 (TAC # MD 7493)

Dear Sir or Madam:

In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to the Commission, at least annually, the estimated effect on the limiting Emergency Core Cooling System (ECCS) analysis caused by changes to or errors discovered in acceptable ECCS evaluations for information.

Since the last 10 CFR50.46 report provided to the NRC [Reference 1], GGNS loaded a new fuel type (GE14) and began using GElGNF's approved analytical methods to perform licensing calculations. GGNS submitted a License Amendment Request (LAR) [Reference 2] to revise TS 5.6.5 to add a reference to a new analytical method to be used to determine core operating limits. GGNS also provided supplemental information [Reference 3] describing the approved ECCS evaluation model to be used to determine the Peak Clad Temperature (PCT) for both the new GE14 fuel and legacy ATRIUM-1 0 fuel types and the quantitative results of the analysis. The new

GNRO-2008/00072 Page 2 ATRIUM-10 Analysis of Record (AOR) used in the LAR resulted in a decrease in the ATRIUM-10 Peak Clad Temperature of 15°F. The ATRIUM-10 is the fuel type with the limiting PCT. The LAR was approved by the NRC in Reference 4. There have been no changes or errors associated with the GGNS ECCS Performance analysis since the implementation of the new AOR described above.

The Table below summarizes the current ECCS Performance analysis performed by GNF for the limiting ATRIUM-10 fuel using their NRC approved methodology.

Notification Nature of change Estimated peT Effect None New Analysis (New Methodology) N/A Sum of absolute magnitude of changes during this period 0 Cumulative sum of absolute magnitude of changes and errors prior 0*

to this period Cumulative sum of absolute magnitude of changes and errors 0 including this period

• There have been no changes or errors affecting PCT since the new Analysis of Record (AOR) as established by References 3 and 4.

This letter does not contain any commitments. Should you have any questions or require additional information, please contact Steve Osborn at 601-437-2344.

Yours truly, pa 1>>2P/ f, lJw~l~rm~j i

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Michael J. Larson Acting Licensing Manager MJLlSDO cc: (See next page)

GNRO-2008/00072 Page 3 cc: NRC Senior Resident Inspector Grand Gulf Nuclear Station Port Gibson, MS 39150 U.S. Nuclear Regulatory Commission ATTN: Mr. Elmo E. Collins, Jr. (w/2) 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005 U. S. Nuclear Regulatory Commission ATTN: Mr. Carl F. Lyon, NRR/ADRO/DORL (w/2)

ATTN: ADDRESSEE ONLY ATTN: U. S. Postal Delivery Address Only Mail Stop OWFN/8 81 Washington, DC 20555-0001