View source for 2CAN080501, Supplement to License Amendment Request Criticality Analysis for Cask Loading Restrictions

{{Adams
| number = ML052230282
| issue date = 08/04/2005
| title = Supplement to License Amendment Request Criticality Analysis for Cask Loading Restrictions
| author name = James D
| author affiliation = Entergy Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000368
| license number = NPF-006
| contact person = 
| case reference number = 2CAN080501
| document type = Letter type:
| page count = 3
| project = 
| stage = Supplement
}}

=Text=
{{#Wiki_filter:Entergy Operations, Inc.
- Entergy                                                                        1448 SR. 333 Russellville. AR 72802 Tel 479-858-4619 Dale E. James Acing Director, Nuclear Safety Assurance Proprietary Information Enclosed 2CAN080501 August 4, 2005 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

==SUBJECT:==
Supplement to License Amendment Request Criticality Analysis for Cask Loading Restrictions Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

==REFERENCES:==
: 1. Entergy letter to the NRC dated July 21, 2005, License Amendment Request To Add Cask Loading Restrictions (2CAN070503)
: 2. NRC Regulatory Issue Summary 2005-05, Regulatory Issues Regarding Criticality Analyses for Spent Fuel Pools and Independent Spent Fuel Storage Installations

==Dear Sir or Madam:==

By letter (Reference 1), Entergy Operations, Inc. (Entergy) proposed a change to the Arkansas Nuclear One, Unit 2 (ANO-2) Technical Specifications (TSs) in response to NRC Regulatory Issue Summary 2005-05 (Reference 2). The proposed change modifies TS 3.9.12, Fuel Storage, to define spent fuel loading restrictions for the Holtec International HI-STORM 100 Cask System for 32 assembly Multi-Purpose Canisters (MPC-32).
On July 26, 2005, members of your staff requested that Entergy provide a copy of the criticality analysis that was performed in support of the application. Portions of the calculation are considered proprietary in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding. Attachment 1 is the proprietary version of the criticality analysis which is requested to be withheld from public disclosure. Attachment 2 contains a redacted non-proprietary version of this criticality analysis. Attachment 3 contains the Holtec affidavit substantiating the basis for withholding the document from public disclosure.
The original no significant hazards consideration included in Reference 1 is unaffected by the information contained in this letter. There are also no new commitments contained in this letter.
Proprietary Information Enclosed

2CAN080501 Page 2 of 2 If you have any questions or require additional information, please contact Dana Millar at 601-368-5445.
I declare under penalty of perjury that the foregoing is true and correct. Executed on August 4, 2005.
Sincerely, D J/D ttachments:
: 1. Part 50 Criticality Analysis of the MPC-32 for ANO Unit 2 - Proprietary
: 2. Part 50 Criticality Analysis of the MPC-32 for ANO Unit 2 - Non-Proprietary
: 3. Holtec Affidavit Regarding Withholding from Public Disclosure cc:       Dr. Bruce S. Mallett Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Drew Holland MS 0-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street Little Rock, AR 72205

Attachment I 2CAN080501 Part 50 Criticality Analysis of the MPC-32 for ANO Unit 2 - Proprietary}}