ML20129D018

Discusses 960812 & 0926 Ltrs Re Relief for Grand Gulf Nuclear Station,Unit 1 from Requirements of Section XI of ASME Code for First 10-year Isi.Ser Encl

ML20129D018
Person / Time
Site:	Grand Gulf
Issue date:	10/22/1996
From:	Beckner W NRC (Affiliation Not Assigned)
To:	Hagan J ENTERGY OPERATIONS, INC.
Shared Package
ML20129D023	List: ML20129D018 ML20129D044
References
TAC-M96293, NUDOCS 9610240181
Download: ML20129D018 (4)

Text

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l. p t UNITED STATES l

g j NUCLEAR REGULATORY COMMISSION WASHING 10N, D.C. enmas aang *

• • • • • ,o

[ October 22, 1996 Mr. Joseph J. Hagan l Vice President, Operations GGNS 1 Entergy Operations, Inc.

1 P. O. Box 756 i Port Gibson, MS 39150 i

i

SUBJECT:

EVALUATION OF THE FIRST 10-YEAR INTERVAL INSPECTION PROGRAM PLAN, REVISION 1 TO RELIEF REQUEST I-00014 FOR GRAND GULF NUCLEAR STATION, UNIT 1 (TAC NO. M96293) ,

Dear Mr. Hagan:

! By letters dated August 12 and September 26, 1996, you requested relief for  !

l the Grand Gulf Nuclear Station, Unit 1 (GGNS) 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 1 Code) for the first 10-year inservice inspection (ISI) interval in accordance j- with Paragraphs 50.55a(g)(5)(iv) and (g)(6)(1) of 10 CFR Part 50. You

! requested that Relief Request No. 1-00014 be revised to incorporate ASME Code

Case N-498-1 as alternative testing in the GGNS pressure testing program, such j that the reactor pressure vessel (RPV) will be subjected to pressure testing <

! in accordan::e with the requirements of ASME Code Section XI or ASME Code i Case N-498-1, 1-

! The revision to the relief request also proposed increasing manual ultrasonic j examination of the RPV to nozzle welds for enhanced volumetric coverage of the a

weld and adjacent base metal in accessible areas to supplement the j examinations previously conducted under the provisions of the original relief i request. The Relief Request No. I-00014 was previously approved in the staff's letter of December 30, 1987.

i The ISI for ASME Code Class 1, 2, and 3 components at GGNS shall be performed i in accordance with Section XI of the ASME Code and applicable addenda as i required by 10 CFR 50.55a(g), except where specific written relief has been i granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(1). For 10 CFR 50.55a(a)(3), it states that alternatives to the requirements of 4- paragraph (g) may be used, when authorized by the Commission, if (i) the i proposed alternatives would provide an acceptable level of quality and safety

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

j e 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 exrminatien requirements, set forth in the ASME Code,Section XI.to the extent practical within the limitations of design, 90@3 NBC Hl.E CENTER COPY

,61024o1 1 ,

PDR ADOCK 0 22 416 'JDFi O PDR -

Mr. Joseph J. Hagan 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 10-year 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 addenda.

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 Comission in support of that determination and a request made for relief from the ASME Code require ent. After evaluation of the determination, pursuant to 10 CFR 50.55a(g)(6)(i), the Comission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger 1 , property, or the comon defense and security, and are otherwise in the N N er interest, giving due consideration to the burden upon the licensee ,nat could result if the requirements were imposed.

As stated in the enclosed Safety Evaluation, the staff concludes that the revision to Relief Request No. I-00014 to include the system leakage test in ASME Code Case N-498-1 for GGNS is an administrative change and you have the option to perform either the 10-year hydrostatic test or the system leakage  !

test of the RPV as allowed by the code case. The alternative of the use of  :

the code case provides an acceptable level of quality and safety. Also, the manual examination of more nozzle-to-vessel welds in the revision of the relief request provides an increased level of quality and safety in comparison to that of the automated examination. Therefore, pursuant to 10 CFR 50.55a(a)(3)(1), relief described in Revision 1 to Relief Request No. I-00014 is granted by the Comission.

Sincerely, Wb h /LJ~-~

William D. Beckner, Project Director Project Directorato IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-416

Enclosure:

Safety Evaluation cc w/ enc 1: See next page

) Mr. Joseph J. Hagan October 22, 1996 1

geometry, and materials of construction of the components. The regulations 4

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 10-year 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 i addenda. l 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)(i), the Commission may grant relief and may impose alternative requirements that are determined to be authorized by law, will not endanger life, property, or the common defense and security, and att otherwise in the public interest, giving due consideration to the burden upon the licensee that could result if the requirements were imposed.

As stated in the enclosed Safety Evaluation, the staff concludes that the 4 revision to Relief Request No. I-00014 to include the system leakage test in l ASME Code Case N-498-1 for GGNS is an administrative change and you have the j option to perform either the 10-year hydrostatic test or the system leakage test of the RPV as allowea by the code case. The alternative of the use of the code case provides an acceptable level of quality and safety. Also, the  ;

manual examination of more nozzle-to-vessel welds in the revision of the I relief request provides an increased level of quality and safety in comparison to that of the automated examination. Therefore, pursuant to 10 CFR 50.55a(a)(3)(1), relief described in Revision I to Relief Request No. I-00014 is granted by the Commission.

Sincerely, Original signed by William D. Beckrnr, Project Director  !

Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-416 DISTRIBUTION: Docket File J. Roe ACRS PUBLIC

Enclosure:

Safety Evaluation PD4-1 r/f J. Mitchell (17G21)

J. Roe G. Hill cc w/ enc 1: See next page E. Adensam (EGA1) J. Dyer, RIV W. Beckner P. Patnaik G. Bagchi P. Tressler T. McLellan J. Donohew Document Name: GG96293.REL (ECGB SE Memo Dated September 27,1996) 0FC PM:PD M1 O LA:PD4-7 _

OG(fM /'1b PD:PD4-)J, NAME JDonothsI hTksNe'r AIhm+e WBecknIr DATE /0 /i /96 /0/8/96"/n it/lb/96 10 /9/96

, COPY MNO

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ONO YES/fE0) YES/N0 OFFIC:AL RECORD COPY

Mr. Joseph J. Hagan Entergy Operations, Inc. Grand Gulf Nuclear Station cc:

Executive Vice President General Manager, GGNS

& Chief Operating Officer Entergy Operations, Inc.

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

P. O. Box 31995 Port Gibson, MS 39150 Jackson, MS 39286-1995 Attorney General Wise, Carter, Child & Caraway Department of Justice P. O. Box 651 State of Louisiana '

Jackson, MS 39205 P. O. Box 94005 Baton Rouge, LA 70804-9005 Winston & Straun 1400 L Street, L' 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 Office of the Governor Resources State of Mississippi P. O. Box 10385 Jackson, MS 39201 Jackson, MS 39209 Attorney General President, Asst. Attorney General Claiborne County Board of Supervisors State of Mississippi Port Gibson, MS 391i0 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 Caithersburg, MD 20878 i

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