ML18190A472

R.E Ginna - Correction to Amendment No. 127 Related to Request to Delete a Modification Associated with the Risk-Informed, Performance Based Fire Protection Program in Accordance with 10 CFR 50.48(c) (CAC No. MF9948; EPID L-2017-LLA-0253)

ML18190A472
Person / Time
Site:	Ginna
Issue date:	07/12/2018
From:	V Sreenivas Plant Licensing Branch 1
To:	Bryan Hanson Exelon Nuclear
Sreenivas V, NRR/DORL/LPL1, 415-2596
References
CAC MF9948, EPID L-2017-LLA-0253
Download: ML18190A472 (6)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, DC 20555-0001 July 12, 2018 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

R. E. GINNA NUCLEAR POWER PLANT - CORRECTION TO AMENDMENT NO. 127 RELATED TO REQUEST TO DELETE A MODIFICATION ASSOCIATED WITH THE RISK-INFORMED, PERFORMANCE-BASED FIRE PROTECTION PROGRAM IN ACCORDANCE WITH 10 CFR 50.48(C) (CAC NO. MF9948; EPID L-2017-LLA-0253)

Dear Mr. Hanson:

By letter dated June 25, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18114A025), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 127 to Renewed Facility Operating License (RFOL) No. DPR-18 for the R. E. Ginna Nuclear Power Plant in response to your application dated June 30, 2017, as supplemented by letters dated October 25, 2017, and June 5, 2018.

Subsequent to the issuance of this amendment, the NRC staff identified the following editorial errors on page 3 of the RFOL and page 1 of the safety evaluation (SE):

• On page 3 of the RFOL, in paragraph 2.C.(3), two dates contained underscores between the month and day instead of spaces and the change bar appeared on the left margin instead of the right margin.

• Page 1 of the SE incorrectly listed modification "ESR-12-0141" as modification "ESR-12-0131."

These errors were inadvertently introduced during the administrative processing of the license amendment. The corrections do not change any of the conclusions associated with the issuance of Amendment No. 127 and do not affect the associated notice to the public. Please replace RFOL page 3 and SE page 1 with the enclosed corrected pages. We regret any inconvenience caused by these errors.

B. Hanson If you have any questions, please contact me at 301-415-2597 or v.sreenivas@nrc.gov Sincerely, j~U~?

V. Sreenivas, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244

Enclosure:

Corrected pages for Amendment No. 127 cc: Listserv

ENCLOSURE CORRECTED PAGES FOR AMENDMENT NO. 127 DATED JUNE 25, 2018 Page 3 - Renewed Facility Operating License DPR-18 Page 1 - Safety Evaluation

(b) Exelon Generation pursuant to the Act and 10 CFR Part 70, to possess and use four (4) mixed oxide fuel assemblies in accordance with the RG&E's application dated December 14, 1979 (transmitted by letter dated December 20. 1979), as supplemented February 20, 1980, and March 5, 1980; (3) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Exelon Generation pursuant to the Act and 10 CFR Parts 30, 40, and 70 to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5) Exelon Generation pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Part 20. Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified below:

( 1) Maximum Power Level Exelon Generation is authorized to operate the facility at steady-state power levels up to a maximum of 1775 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 126 are hereby incorporated in the renewed license.

Exelon Generation shall operate the facility in accordance with the Technical Specifications.

(3) Fire Protection Exelon Generation shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee's amendment request dated March 28, 2013, supplemented by letters dated December 17, 2013; January 29, 2014; February 28, 2014; September 5, 2014; September 24, 2014; December 4, 2014; March 18, 2015; June 11, 2015; August 7, 2015; June 30, 2017; October 25, 2017; and June 5, 2018, and as approved in the safety evaluation reports dated November 23, 2015, and June 25, 2018. Except where NRC approval for changes or deviations is required R. E. Ginna Nuclear Power Plant Amendment No. 127

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 127 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-18 EXELON GENERATION COMPANY, LLC R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244

1.0 INTRODUCTION

By letter dated June 30, 2017 (Reference 1), as supplemented by letters dated October 25, 2017 (Reference 2), and June 5, 2018 (Reference 3), Exelon Generation Company, LLC (Exelon, the licensee), submitted a license amendment request (LAR) regarding the R. E. Ginna Nuclear Power Plant (Ginna). Specifically, the licensee requested to delete the modification to install overcurrent protection on its emergency diesel generators (EDGs) (modification ESR-12-0141) which is required as part of Ginna's implementation of its risk-informed, performance-based fire protection program (RI/PB FPP) in accordance with paragraph 50.48(c) of Title 10 of the Code of Federal Regulations (10 CFR) (National Fire Protection Association Standard 805 (NFPA 805)). The licensee included modification ESR-12-0141 in its revised LAR Attachment S, Table S-2, which was submitted to the U.S. Nuclear Regulatory Commission (NRC) in a letter dated June 11, 2015 (Reference 4). Portions of the letter dated June 30, 2017, contain proprietary information and, accordingly, have been withheld from public disclosure pursuant to 10 CFR 2.390.

The supplemental letters dated October 25, 2017, and June 5, 2018, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the NRC staff's original proposed no significant hazards consideration determination as published in the Federal Register (FR) on October 3, 2017 (82 FR 46097).

1.1 Background On March 28, 2013 (Reference 5), Constellation Energy Group (the previous licensee for Ginna) requested to revise the Ginna FPP in accordance with 10 CFR 50.48(c). On November 23, 2015 (Reference 6), the NRC issued Amendment No. 119 to Renewed Facility Operating License (RFOL) No. DPR-18. The amendment consisted of changes to the operating license to transition the Ginna FPP to an RI/PB program based on NFPA 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants" (2001 Edition)

(NFPA 805) (Reference 7), in accordance with 10 CFR 50.48(c). The NFPA 805 standard Enclosure 2

ML18190A472 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LSPB/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME VSreenivas JBurkhardt Joanna VSreenivas (JDanna for)

DATE 7/11/18 7/11/18 7/12/18 7/12/18