ML11206A001

RAI, Proposed ISI Alternative HNP-ISI-ALT-11

ML11206A001
Person / Time
Site:	Hatch
Issue date:	07/28/2011
From:	Patrick Boyle Plant Licensing Branch II
To:	Ajluni M Southern Nuclear Operating Co
Boyle P, NRR/DORL/LPL2-1, 415-3936
References
TAC ME6290
Download: ML11206A001 (3)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 28, 2011 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.

40 Inverness Center Parkway P.O. Box 1295, Bin - 038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 - REQUEST FOR ADDITIONAL INFORMATION (RAI), PROPOSED INSERVICE INSPECTION (lSI) ALTERNATIVE HNP-ISI-ALT-11 (TAC NO. ME6290)

Dear Mr. Ajluni:

By letter dated May 17, 2011 (Agencywide Documents Access and Management System, Accession No. ML111380211), Southern Nuclear Operating Company, Inc., submitted a request for alternative for the lSI Program. Responses to the enclosed RAI are needed for us to continue our review.

Please provide a response within thirty (30) calendar days of the date of this letter.

Sincerely,

~

~.""-<:lLnck G. Boyle, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-366

Enclosure:

RAI cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION PROPOSED ALTERNATIVE HNP-ISI-ALT-11 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO.2 DOCKET NO. 50-366 TAC NO. ME6290 By letter dated May 17, 2011 (Agencywide Documents Access and Management System, Accession No. ML111380211), Southern Nuclear Operating Company, Inc., the licensee, submitted a request for alternative (RA) from the American Society of Mechanical Engineers, Boiler and Pressure Vessel Code,Section XI requirements in accordance with the provisions of Title 10 of the Code of Federal Regulations, Part 50, paragraph 50.55a(a)(3)(i). This RA pertains to the period extending from July 31, 2007, to June 13, 2038.

In order to complete its review of the licensee's submittal, the Nuclear Regulatory Commission (NRC) staff requires a response to the following questions:

1. Confirm that the neutron fluence calculations used in the application conform to the requirements set forth in the NRC safety evaluation pertaining to the Radiation Analysis Modeling Application (RAMA) code, dated May 13, 2005. Specifically confirm that:

The best-estimate [reactor pressure vessel] neutron fluence prediction is determined using the RAMA transport code, detailed plant-specific geometry, core operating history, and the BUGLE-96 nuclear data library with a minimum of a P3 Legendre polynomial approximation in the iron inelastic scattering.

If this is not the case, detail how the neutron fluence calculations used in the application are acceptable.

2. The mean nil-ductility transition reference temperature (RT NOT) values reported in Tables 1 and 2 of the submittal are based on delta RT NOT values from "SIA ART Calculation[s]." Explain in detail how these calculations are, or are not, consistent with the guidance provided in Regulatory Guide (RG) 1.99, Rev. 2, "Radiation Embrittlement of Reactor Vessel Materials." If they are not consistent with the guidance in RG 1.99, Rev. 2, please indicate whether these proposed values (Le., the delta RTNOT values used in the calculation of the mean RT NOT values in this submittal) have been previously reviewed and accepted by the staff.

Enclosure

'.. ML11206A001 *via e-mail OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCVIB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME PBoyle MO'Brien MMitchell* GKulesa PBoyle (RMartin for)

DATE 7/26/11 7/26/11 07/19/11 7/28/11 7/28/11