ML033100287

Relief, Reactor Pressure Vessel Closure Head Nozzles

ML033100287
Person / Time
Site:	Arkansas Nuclear
Issue date:	11/06/2003
From:	Gramm R NRC/NRR/DLPM/LPD4
To:	Anderson C Entergy Operations
Minns J, NRR/DLPM, 415-3166
Shared Package
ML033100298	List: ML033100287 ML033100302
References
TAC MB6599
Download: ML033100287 (5)

Text

November 6, 2003 Mr. Craig G. Anderson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

ARKANSAS NUCLEAR ONE, UNIT NO. 1 - RE: RELIEF REQUEST TO USE ALTERNATIVE TECHNIQUES FOR REACTOR PRESSURE VESSEL CLOSURE HEAD NOZZLES (TAC NO. MB6599)

Dear Mr. Anderson:

By letter dated October 28, 2002, as supplemented by letters dated November 26 and December 16, 2002, Entergy Operations, Inc. (Entergy), submitted two requests for relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code) Sections III and XI as applied to reactor pressure vessel closure head nozzles at Arkansas Nuclear One, Unit 1 (ANO-1). Specifically, in ANO1-R&R-003 and ANO1-R&R-004, Entergy proposed using an alternative temper bead welding requirement and alternatives to ASME Code non-destructive examinations and flaw evaluation requirements.

The U.S. Nuclear Regulatory Commission (NRC) staff has completed its review as documented in the enclosed safety evaluation. The NRC staff determined that Entergy has demonstrated that the proposed alternatives to the Code requirements provide an acceptable level of quality and safety and that it is impractical for the licensee to comply with the requirements. Further, the NRC staff finds that the alternatives provide reasonable assurance of structural integrity.

Therefore, pursuant to 10 CFR 50.55a(a)(3)(i) and 10 CFR 50.55a(g)(6)(i), the NRC staff authorizes the relief requests for the third 10 year interval through the fall 2005 refueling outage. NRCs review and acceptance of these relief requests is limited to this time period because the licensee has scheduled to replace the reactor vessel closure head during the fall 2005 refueling outage.

Granting relief pursuant to 10 CFR 50.55a(a)(g)(6)(i) is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest given due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.

In its review of the need for the reliefs during the past refueling outage, the NRC staff verbally authorized the use of ANO1-R&R-003 and ANO1-R&R-004 on November 6, 2002, due to the undue regulatory burden associated with the delay inherent in a written authorization. This letter documents our written authorization for the relief request.

Mr. Craig G. Anderson Pursuant to 10 CFR 2.790, we have determined the enclosed Safety Evaluation (SE) does not contain proprietary information.

However, we will delay placing the SE in the public document room for five working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects only. If you believe that any information in the enclosure is proprietary, please identify such information line by line and define the basis pursuant to the criteria of 10 CFR 2.790.

Sincerely,

/RA/

Robert Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

As stated cc w/o encl: See next page

Mr. Craig G. Anderson Pursuant to 10 CFR 2.790, we have determined the enclosed Safety Evaluation (SE) does not contain proprietary information.

However, we will delay placing the SE in the public document room for five working days from the date of this letter to provide you with the opportunity to comment on the proprietary aspects only. If you believe that any information in the enclosure is proprietary, please identify such information line by line and define the basis pursuant to the criteria of 10 CFR 2.790.

Sincerely,

/RA/

Robert Gramm, Chief, Section 1 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

As stated cc w/o encl: See next page DISTRIBUTION:

PUBLIC PDIV-1 Reading RidsNrrDlpmLpdiv1 (HBerkow)

RidsNrrDlpmLpdiv1 (RGramm)

RidsNrrPMJMinns RidsNrrLADJohnson RidsOgcRp RidsAcrsAcnwMailCenter GHill (2)

ATKeim

Mr. Craig G. Anderson EVAndruskiewicz ABoland, EDO/RIV Plants RidsRgn4MailCenter (AHowell)

• No significant change from SE input Accession No. ML033100287 **See previous concurrence OFFICE PDIV-1/PM PDIV-1/LA DE/EMCB OGC PDIV-1/SC NAME JMinns DJohnson** TChan/SCoffin* RHoefling** RGramm w/changes DATE 11/1/03 11/5/03 08/18/2003 09/12/2003 11/6/03 OFFICIAL RECORD COPY

Arkansas Nuclear One cc:

Executive Vice President County Judge of Pope County

& Chief Operating Officer Pope County Courthouse Entergy Operations, Inc. Russellville, AR 72801 P. O. Box 31995 Jackson, MS 39286-1995 Director, Division of Radiation Control and Emergency Management Arkansas Department of Health 4815 West Markham Street, Slot 30 Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Mr. Mike Schoppman Framatome ANP, Richland, Inc.

Suite 705 1911 North Fort Myer Drive Rosslyn, VA 22209 Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 310 London, AR 72847 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064

Vice President, Operations Support Entergy Operations, Inc.

P. O. Box 31995 Jackson, MS 39286-1995 Wise, Carter, Child & Caraway P. O. Box 651 Jackson, MS 39205 March 2001