GNRO-2013/00073, Criticality Safety Analysis License Amendment Request - Supplemental Information

Criticality Safety Analysis License Amendment Request - Supplemental Information

ML13260A084
Person / Time
Site:	Grand Gulf
Issue date:	09/16/2013
From:	Ford B Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2013/00073
Download: ML13260A084 (2)

Text

Entergy Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213 Bryan S. Ford Senior Manager, Licensing Tel. (601) 368-5516 GNRO-2013/00073 September 16, 2013 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

Criticality Safety Analysis License Amendment Request -

Supplemental Information Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29

REFERENCES:

1. Entergy Operations, Inc. letter to the NRC (GNRO-2011/00076),

License Amendment Request - Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, September 9, 2011 (ADAMS Accession No. ML1125321287)

2. Entergy Operations, Inc. letter to the NRC (GNRO-2013/00050),

Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information, July 2, 2013 (ADAMS Accession No. ML13190A043)

Dear Sir or Madam:

In Reference 1, Entergy Operations, Inc. (Entergy) submitted to the NRC a license amendment request (LAR), which proposes to: 1) revise the criticality safety analysis (CSA) for the spent fuel and new fuel storage racks; 2) impose additional requirements for the spent fuel and new fuel storage racks in Technical Specification (TS) 4.3.1, Criticality; and 3) delete the spent fuel pool loading criteria Operating License (OL) condition.

In Reference 2, Entergy submitted to the NRC responses to Requests for Additional Information (RAIs) pertaining to Reference 1.

In a telephone call with the NRC staff on September 13, 2013, Entergy identified that the response to RAI 3.a.1, provided in Attachment 3 of Reference 2, required additional, clarifying information and that Table 3-2 provided in that response contained an error. The clarifying information and the correction are provided below.

• Clarifying Information The values given in Table 3-2 of the RAI response were determined by treating the 95/95 Boraflex configuration uncertainty (see RAI 3.c.2 provided in Reference 2) as a bias.

GNRO-2013/00073 Page 2 of 2

• Correction Table 3-2 denotes the value of KLD Bias as 0.00287. Entergy discovered this value to be incorrect; the correct value is 0.00278. The last two digits of the value were inadvertently transposed when the table was developed. The remaining values in the table were checked and determined to be correct. This error has no impact on any result presented in the RAI response.

This letter contains no new commitments.

If you have any questions or require additional information, please contact Guy Davant at (601) 368-5756.

I declare under penalty of perjury that the foregoing is true and correct; executed on September 16, 2013.

Sincerely, BSF/ghd cc: Mr. Steven A. Reynolds State Health Officer Regional Administrator (acting), Region IV Mississippi Department of Health U. S. Nuclear Regulatory Commission P. O. Box 1700 1600 East Lamar Blvd. Jackson, MS 39215-1700 Arlington, TX 76011-4511 U. S. Nuclear Regulatory Commission NRC Senior Resident Inspector ATTN: Mr. A. B. Wang, NRR/DORL (w/2) Grand Gulf Nuclear Station ATTN: ADDRESSEE ONLY Port Gibson, MS 39150 ATTN: Courier Delivery Only Mail Stop OWFN/8 B1 11555 Rockville Pike Rockville, MD 20852-2378