ML15022A416

Correction to Safety Evaluation Pages for Authorization of Relief from the Requirements of the ASME Code Extension of the Reactor Vessel Inservice Inspection Interval

ML15022A416
Person / Time
Site:	Braidwood
Issue date:	03/18/2015
From:	Joel Wiebe Plant Licensing Branch III
To:	Bryan Hanson Exelon Generation Co
Joel Wiebe, NRR/DORL 415-6606
References
TAC MF3596
Download: ML15022A416 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 M:iro'i 18, 2015 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNIT NO. 1 -CORRECTION TO SAFETY EVALUATION PAGES FOR AUTHORIZATION OF RELIEF FROM THE REQUIREMENTS OF THE ASME CODE RE: EXTENSION OF THE REACTOR VESSEL INSERVICE INSPECTION INTERVAL (TAC NO. MF3596)

Dear Mr. Hanson:

By letter dated December 10, 2014, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14303A506), the U.S. Nuclear Regulatory Commission (NRC) authorized the use of alternatives to certain American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, requirements, for the Byron Station Unit No. 1. The associated safety evaluation (SE) contained a typographical error. Specifically, the date on page 8 of the SE was incorrect.

A corrected copy of page 8 of the associated SE is enclosed. This correction does not change any of the conclusions in the SE associated with the authorized use of alternatives.

B. Hanson We apologize if this error has caused any inconvenience. If you have any questions regarding this matter, please contact the Senior Project Manager, Joel S. Wiebe, at (301) 415-6606 or by e-mail at Joel.Wiebe@nrc.gov.

Sincerely, oel S. Wiebe, Senior Project Manager Plant Licensing Branch 111-2 and Planning and Analysis Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. STN 50-456

Enclosure:

Corrected SE page cc w/enclosures: Distribution via Listserv

ENCLOSURE Byron Station, Unit 1 Corrected Page for Authorization of Relief from Requirements of the ASME Code Dated December 10, 2014

transients, per the Westinghouse pilot plant study. Therefore, the staff finds that Plant-Specific Information Item (4) is not applicable to Byron, Unit No. 1, and no plant-specific evaluation is required for this item.

Regarding Plant-Specific Information Item (5), the NRC staff noted that the RTMAX-FO value for Byron, Unit 1, is less than 240 °F. This item is only applicable to plants with RTMAX-FO values exceeding 240 °F (regardless of the number of cladding layers). Therefore, the staff finds that Plant-Specific Information Item (5) is not applicable to Byron, Unit 1, and no plant-specific evaluation is required for this item.

Regarding Plant-Specific Information Item (6), the NRC staff finds that this item is not applicable to Byron, Unit No. 1, because the licensee's application requested deferral of the subject RPV weld examinations for only the third 10-year ISi interval.

Based on its review of the licensee's submittal, and its findings regarding Plant-Specific Information Items (1), (2), (3), (4), (5), and (6), as documented above, the NRC staff has determined that the licensee adequately demonstrated that the Byron, Unit No. 1, RPV is bounded by Westinghouse pilot plant study from the WCAP-A. Consequently, the licensee has demonstrated that the proposed alternative will provide an acceptable level of quality and safety, and it meets the guidance provided by RG 1.174, Revision 1, for risk-informed decisions.

4.0 CONCLUSION

The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed SE, that the proposed alternative provides an acceptable level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(i). Therefore, the staff authorizes use of the proposed alternative until the expiration of the facility operating license or, if the license renewal application is approved, until the end of 2025.

All other ASME Code,Section XI, requirements for which relief was not specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.

Principal Contributor: C. Sydnor Date of issuance: December 10, 2014

• .. ML13113A016 OFFICE LPL3-1/PM LPL3-2/PM LPL 1-2/LA LPL3-2/BC LPL3-2/PM NAME ADietrich JWiebe SRohrer TT ate JWiebe DATE 1/14/15 1/27/15 1/28/15 3/17/15 3/18/15