NRC-23-0060, Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)

Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (Eecw)/Emergency Equipment Service Water (Eesw) System and Ultimate Heat Sink (UHS)

ML23237B402
Person / Time
Site:	Fermi
Issue date:	08/25/2023
From:	Peter Dietrich DTE Electric Company
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
NRC-23-0060
Download: ML23237B402 (1)

Text

Peter Dietrich Senior Vice President and Chief Nuclear Officer DTE Electric Company 6400 N. Dixie Highway, Newport, MI 48166 Tel: 734.586.6515 Email: peter.dietrich@dteenergy.com DTE August 25, 2023 10 CFR 50.90 NRC-23-0060 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43

Subject:

Supplemental Information to Exigent License Amendment Request for Technical Specification 3.7.2,Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS)

References:

1) DTE Letter NRC-23-0050, Exigent License Amendment Request for Technical Specification 3.7.2, Emergency Equipment Cooling Water (EECW)/Emergency Equipment Service Water (EESW) System and Ultimate Heat Sink (UHS), dated August 10, 2023 (ML23222A037)

In Reference 1, DTE Electric Company (DTE) submitted an Exigent license amendment request to revise the Fermi 2 Technical Specifications (TS). This supplement to the Reference 1 is provided to address a typographical error. There is an occurrence of acronym EECS in Reference 1, Section 4.3, No Significant Hazards Consideration, Question 3. DTE has determined that this was a typo and should have read Emergency Equipment Cooling Water (EECW). This page has been corrected and is included with this letter as Enclosure 1. The supplemental information does not impact the conclusions of the Regulatory Analysis, including the No Significant Hazards Consideration, documented in Reference 1.

No new commitments are being made in this submittal.

Should you have any questions or require additional information, please contact Mr. Eric Frank, Manager - Nuclear Licensing, at (734) 586-4772.

USNRC NRC-23-0060 Page 2 I declare under penalty of pe1jury that the foregoing is true and correct.

Peter Dietrich Senior Vice President and Chief Nuclear Officer : Corrected Page 11 for NRC-23-0050 cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III Michigan Department of Environment, Great Lakes, and Energy

Enclosure 1 to NRC-23-0060 Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43 Corrected Page 11 for NRC-23-0050 to NRC-23-0050 Page 11 The proposed changes do not alter the plant design, nor do they affect the assumptions contained in the safety analyses. Specifically, there are no changes being made to the MDCT fan design. The proposed changes have been evaluated and margins of safety ascribed to Emergency Equipment Cooling Water (EECW) availability and to plant risk have been determined to be not significantly reduced. The risk impact of the proposed changes is acceptable to the compensatory measures and other requirements, as outlined in outlined Section 3.2 above and in Enclosure 4. As analyzed in the UFSAR, the loss of the Division I MDCT fans would not cause a significant reduction in safety because the MDCT system is redundant and can perform its function with one division unavailable.

The evaluation provided above shows that the proposed changes will not significantly increase the probability or the consequences of any accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in the margin of safety. Therefore, the proposed changes meet the criteria of 10 CFR 50.92(c) and no significant hazard consideration is involved.

4.4 Conclusion In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

5.0 ENVIRONMENTAL CONSIDERATION

A review has determined that the proposed amendment would provide a one-time extension of the Completion Time to repair of the Division I MDCT A and C fan pedestals while online. The proposed amendment does not involve: (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.

Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.

6.0 REFERENCES

6.1 U.S. Nuclear Regulatory Commission, Regulatory Guide 1.177, Revision 1, An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications,