ML20129B639

Forwards Evaluation of First 10-year Interval Insp Program Plan & Addl Requests for Relief for Plant,Unit 1

ML20129B639
Person / Time
Site:	Grand Gulf
Issue date:	10/18/1996
From:	Beckner W NRC (Affiliation Not Assigned)
To:	Hagan J ENTERGY OPERATIONS, INC.
Shared Package
ML20129B644	List: ML20129B639 ML20129B875
References
TAC-M95433, NUDOCS 9610230074
Download: ML20129B639 (5)

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NUCLEAR RESULATORY COMMISSION WASHINGTON, D.C. 30eeH001

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October 18, 1996 Mr. Joseph J. Hagan Vice President, Operations GGNS Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150

SUBJECT:

EVALUATION OF THE FIRST 10-YEAR INTERVAL INSPECTION PROGRAM PLAN, ADDITIONAL REQUESTS FOR RELIEF FOR GRAND GULF NUCLEAR STATION, UNIT I (TAC HD. M95433)

Dear Mr. Hagan:

By letters dated May 21 and July 31, 1996, you requested relief from the requirements of Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) for the first 10-year inservice inspection (ISI) interval in accordance with Paragraphs 50.55a(g)(5)(iv) and (g)(6)(i) of 10 CFR Part 50. The ISI for ASME Code Class 1, 2, and 3 components at Grand Gulf Nuclear Station, Unit 1 (GGNS) shall be performed in accordance with Section XI of the ASME Code and applicable addenda as required by 10 CFR 50.55a(g), except where specific written relief has been granted by the Comission pursuant to 10 CFR 50.55a(g)(6)(i). The 10 CFR 50.55a(a)(3) states .

that alternatives to the requirements of paragraph (g) may be_used, when l authorized by the Consission, if (i) the proposed alternatives would provide '

an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI to the extent practical within the limitations,of design, geometry, and materials of construction of the components. The regulations require that inservice examination of components and system pressure tests conducted during the first 10-year interval and subsequent intervals comply with the requirements in the latest edition and addenda of Section XI of the ASME Code incorporated by reference in 10 CFR 50.55a(b) 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable edition of Section XI of the ASME Code for the GGNS first 10-year ISI interval is the 1977 edition through the summer 1979 l addenda. The GGNS first 10-year interval commenced on July 1,1985.

Pursuant to 10 CFR 50.55a(g)(5), if the licensee determines that conformance with an examination requirement of Section XI of the ASME Code is not practical for its facility, information shall be submitted to the Commission in support of that determination and a request made for relief from the ASME Code requirement. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(1), the Commission may grant relief and may impose

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Mr. Joseph J. Hagan l

! alternative requirements that are determined to be authorized by law, will not i endanger life, property, or the common defense and security, and are otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.

The staff, with technical assistance from its contractor, the Idaho National Engineering Laboratory (INEL), has reviewed and evaluated the information

provided in your letters of May 21 and July 31, 1996, related to a new first 10-year interval inservice inspection program plan request for relief and 14 revised requests for relief. The staff's evaluation and conclusions are

contained in Enclosure 1 and the INEL Technical Evaluation Report is l Enclosure 2. This letter and its enclosures completes the technical review to j be performed under TAC No. M95433.

! For the latest revisions of Requests for Relief I-00002, I-00007, I-00008, l I-00009,1-00010, I-00012, I-00015, and I-00018, the staff concludes that the i technical content of the request for relief has not changed, and that the i relief remains granted pursuant to 10 CFR 50.55a(g)(6)(i), as determined in l the previous Safety Evaluations dated July 22, 1986; August 5, 1986; July 22,

1986; April 15, 1992; May 25, 1993; July 22, 1986; September 29, 1986, and l August 15, 1986, respectively.

! In the latest revisions of Requests for Relief I-00004, I-00005, and I-00006,

! these requests for relief have been deleted from the GGNS first 10-year

! inservice inspection program plan, because the reliefs addressed Category B-A, Item Bl.10 welds and are revoked pursuant 10 CFR 50.55a(g)(6)(ii)(A)(1). You have stated in the letters that the augmented requirements of 10 CFR 50.55a(g)(6)(ii)(A)(2) for Requests for Relief I-00004 and I-00005 have not been met and are not possible, and will be addressed in future correspondence. In this correspondence, you should include the information that Request for Relief I-00006 would provide an acceptable level of quality and safety without imposing augmented examination requirements.

The Requests for Relief I-00011 and 1-00017 are stated to be no longer required and the revisions of the reliefs have removed them from the GGNS I first 10-year inservice inspection program plan. I As stated in the enclosed Safety Evaluation, the staff concludes that the Code examination requirements are impractical for the welds contained in Request for Relief I-00019, and the Commission grants relief pursuant to 10 CFR 50.55a(g)(6)(i). j For the request, in Request for Relief I-00024, to perform the pump / valve i internal examination in accordance with the requirements of Table IWB-2500-1, Examination Categories B-L-2 and B-M-2 contained in the 1989 Edition of the ASME Code in lieu of the 1977 edition through the summer 1979 addenda, the staff concludes that the licensee's proposed use of later editions of ASME

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Mr. Joseph J. Hagan October 18, 1996 Section XI is an acceptable level of quality and safety for requirements contained in Request for Relief I-00024, provided all related requirements of the respective editions or addenda are met. Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), relief is granted by the Commission in that the use of the 1989 Edition ASME Code,Section XI is approved for Request for Relief I-00024 provided.that all associated requirements of the 1989 Code are met.

Sincerely, Original signed by William D. Beckner, Director Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosures:

1. Safety Evaluation

2. Technical Evaluation Report cc w/encls: See next pace b

DISTRIBUTION:

Docket File. PUBLIC PD4-1 r/f G. Hill (2)

J. Roe E. Adensam (EGAl) J. Donohew J. Mitchell J. Dyer, RIV ACRS OGC (15B18) C. Bagchi C. Hawes WBeckner T. McLellan Document Name: Gr "433.SER *See previous concurrence i 0FC PM/PDf-l(1 (A)LA/PD4-1 BC/ECGB* OGC* l t!AME JDonohrM CHawesOMM GBachi MYoung DATE  %/ th6 10/IS/96 09/18/96 10/10/96 i COPY (fEh/NG (fES)N0 YES/NO YES/N0 0FFICIAL RECORD COPY Y

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Mr. Joseph J. Hagan Section XI is an acceptable level of qt... ity and safety for requirements contained in Request for Relief I-00024, provided all related requirements of the respective editions or addenda are met. Therefore, pursuant to 10 CFR 50.55a(g)(4)(iv), relief is granted by the Commission in that the use of the 1989 Edition ASME Code,Section XI is approved for Request for Relief I-00024 provided that all associated requirements of the 1989 Code are met.

Sincerely,

g d' - o & V l William D. Beckner, Director i Project Directorate IV-1 j Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-416 i

Enclosures:

1. Safety Evaluation l 2. Technical Evaluation' Report cc w/encls: See next page e

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! Mr. Joseph J Hagan Entergy Op a ions, Inc. Grand Gulf Nuclear Station i

! cc:

J Executive Vice President General Manager, GGNS i & Chief Operating Officer Entergy Operations, Inc.

i Entergy Operations, Inc. P. O. Box 756 i

P. O. Box 31995 Port Gibson, MS 39150

Jackson, MS 39286-1995

! Attorney General

! Wise, Carter, Child & Caraway Department of Justice

P. O. ' 651 State of Louisiana i Jackson, MS 39205 P. O. Box 94005 l _

f.aton Rouge, LA 70804-9005

Winston & Strawn i 1400 L Street, N.W. - 12th Floor State Health Officer

- Washington, DC 20005-3502 State Board of Health

P. O. Box 1700 Director Jackson, MS 39205 Division of Solid Waste Management Mississippi Department of Natural c Office of the overnor Resources State of Missi ippi P. O. Box 10385 Jackson, MS  ;.el Jackson, MS 39209 Attorney General President, Asst. Attorney General claiborne County Board of Supervisors State of Mississippi Port Gibson, MS 39150 P. O. Box 22947 Jackson, MS 39225 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Vice President, Operations Support 611 Ryan Plaza Drive, Suite 1000 Entergy Operations, Inc.

Arlington, TX 76011 P.O. Box 31995 Jackson, MS 39286-1995 Senior Resident Inspector U. S. Nuclear Regulatory Commission Director, Nuclear Safety Route 2, Box 399 and Regulatory Affairs Port Gibson, MS 39150 Entergy Operations, Inc.

P.O. Box 756 Nuclear Operating Plant Services Port Gibson, MS 39150 Bechtel Power Corporation 9801 Washington Boulevard Gaithersburg, MD 20878 D

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