NRC-10-0072, Submittal of Revision 6 to Safety Analysis Report

Submittal of Revision 6 to Safety Analysis Report

ML103270414
Person / Time
Site:	Fermi
Issue date:	11/15/2010
From:	Plona J Detroit Edison, DTE Energy
To:	Document Control Desk, NRC/FSME
References
NRC-10-0072
Download: ML103270414 (4)

Text

Joseph H. Plona Site Vice President 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.5910 Fax: 734.586.4172 DTE Energy-10 CFR 50.71(e) 10 CFR 50.4(b)(6)

November 15, 2010 NRC-10-0072 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D.C. 20555-0001

References:

1) Enrico Fermi Atomic Power Plant, Unit No. 1 NRC Docket No. 50-16 NRC License No. DPR-9

2) Fermi 1 Letter to NRC (NRC-09-0051) dated August 27, 2009, "Enrico Fermi Atomic Power Plant, Unit No. 1 Annual Report Period Ending June 30, 2009"

3) Fermi 1 Letter to NRC (NRC-10-0064) dated August 30, 2010, "Enrico Fermi Atomic Power Plant, Unit No. 1 Annual Report Period Ending June 30, 2010"

Subject:

Submittal of Revision 6 to the Fermi 1 Safety Analysis Report Pursuant to 10 CFR 50.71(e) and 10 CFR 50.4(b)(6), Detroit Edison hereby submits Revision 6 to the Fermi 1 Safety Analysis Report (F1SAR).

One signed original of the F1SAR, Revision 6, is being submitted to the Document Control Desk.

In addition, one copy will be submitted to Region III. Changes associated with Revision 6 are annotated by revision bars in the appropriate margin. The entire document has been updated to Rev. 6. All pages are marked "Rev. 6, 11/10" in the-lower right-hand comer. All pages are also marked "Security-Related Information - Withhold Under 10 CFR 2.390" at the top of each page per the requirements of NRC Regulatory Issue Summary 2005-31 (RIS 2005-31), "Control of

USNRC November 15, 2010 NRC 10-0072 Page 2 Security-Related Sensitive Unclassified Non-Safeguards Information Handled by Individuals, Firms, and Entities Subject to NRC Regulation of the Use of Source, Byproduct, and Special Nuclear Material", issued 12/22/05. Based on a review of the F1SAR, information contained on Pages 4-7 and 4-8 titled Table 4.1, Summary of Activation Analysis - January, 2001 (Page 4-7, first page and Page 4-8, continuation page) and Figures 4.4 through 4.11 on pages 4-12 through 4-19, meet the screening criteria contained in RIS 2005-31, Attachment 2, Section 2A and require that a header and editorial text block is added to each page per Attachment 1, Section A. , Section A also requires that the header appears on each page of the affected document.

In accordance with 10 CFR 50.71(e) the information provided in this submittal describes the plant configuration through May 2010, as a minimum and reflects changes made since the Revision 5 submittal that were made under the provisions of 10 CFR 50.59 and/or following NRC approval.

Two activities during the period were screened as requiring a 50.59 evaluation, which are addressed in References 2 and 3. Reactor Vessel cutting, segmentation, and removal was evaluated under 08-050-SE, 08-050-SE, Rev. 1, and 08-050-SE, Rev. 2 to determine whether activities associated with the Reactor Vessel removal could result in higher accident dose rates or whether the current accident calculations contained in Section 8.4 bound Reactor Vessel removal.

The evaluation determined the proposed activity was bounded by the existing analyses in Section 8. The activity which included cutting the primary system nozzles and vessel itself, is underway. A Fermi 1 Corrective Action Document (EF1-CAR-09-013) identified it would be more appropriate to use the dose to activity correlation based on the correlation between effluent concentration and public dose in 10 CFR 20, App. B, Table 2 than the correlation between DAC and occupational exposure in 10 CFR 20, App. B, Table 1 for postulated airborne accident releases. This change was evaluated under 09-01 1-SE, and resulted in recalculating the consequences of the postulated accidents with airborne releases contained in Section 8.4.

F1SAR, Revision 6, does not include any changes to the Fermi 1 Quality Assurance Program described in Section 6, "Administrative Controls"; therefore a 10 CFR 50.54(a) review is not required.

USNRC November 15, 2010 NRC 10-0072 Page 3 Should you have any questions or require additional information, please contact Ms. Lynne S. Goodman of my staff at (734) 586-1205.

Sincerely, JHP/CAN/lj d Attachment cc: NRC Regional Administrator, Region III T. Smith, NRC (Washington, D.C.)

NRC Resident Inspector- Fermi 2 P. Lee, NRC Region III T. Strong (Michigan Dept of Natural Resources and Environment)

USNRC November 15, 2010 NRC 10-0072 Page 4 I, Joseph H. Plona., do hereby affirm that the foregoing statements are based on facts and circumstances which are true and accurate to the best of my knowledge and belief.

Jos ' na Site Vice President, Nuclear Generation On this 16 day of November , 2010 before me personally appeared Joseph H.

Plona, being first duly sworn and says that he executed the foregoing as his free act and deed.

Notary Public AC .4 8' rM n 14,-23