ML20198M762

Forwards SER Accepting Util Request That NRC Approve risk-informed Alternative to Requirements of ASME Boiler & Pressure Vessel Code Section Xi,Div 1 for Inservice Insp of Piping Welds at Arkansas Nuclear One,Unit 2

ML20198M762
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/29/1998
From:	Hannon J NRC (Affiliation Not Assigned)
To:	Hutchinson C ENTERGY OPERATIONS, INC.
Shared Package
ML20198M766	List: ML20198M762 ML20198M784
References
FACA, TAC-M99756, NUDOCS 9901050347
Download: ML20198M762 (4)

Text

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p $$ UNITED STATES j

s NUCLEAR REGULATORY COMMISSION

, a WASHINGTON, D.C. enmaa anni

% / December 29, 1998 Mr. C. Randy Hutchinson Vice President, Operations ANO Entergy Operations, Inc.

1448 S. R. 333 Russellville, AR 72801

SUBJECT:

REQUEST TO USE A RISK-INFORMED ALTERNATIVE TO THE REQUIREMENTS OF ASME CODE SECTION XI, TABLE IWX-2500 AT ARKANSAS NUCLEAR ONE, UNIT NO. 2 (TAC NO. M99756)

Dear Mr. Hutchinson:

By letters dated September 30,1997 (2CAN099706), March 31,1998 (OCAN039809), l October 8,1998 (2CAN109801), November 25,1998 (2CAN119804), and December 8,1998  !

(2CAN129803), you requested that the NRC approve a risk-informed attemative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Cc,de Section XI, Division 1 for the inservice inspection of piping welds at Arkansas Nuclear One, Unit No. 2 (ANO-2).~ This submittal proposed an alternative to ASME Section XI Table IWX-2500 which was based on ASME Code Case N-578, " Risk-Ir. formed Requirements for Class 1, 2, and 3 Piping - Method B," and the Electric Power Research Institute (EPRI) Technical Report No. TR-106706, " Risk-informed Inspection Evaluation Procedure, Interim Report," as augmented by ANO-2 plant-specific methodologies. Specifically, you proposed to redistribute the piping inspections to focus on high-risk piping segments of safety-related piping systems while minimizing the number of inspection performed on low-risk systems and piping segments. In addition, the types of inspections were considered from a risk-informed perspective favoring volumetric examinations over surface exams. The result of this redistribution was an overall reduction in the number of piping examinations performed from the original value of 336 examinations conducted in accordance with the current ASME Section XI inservice inspection program to the 167 examinations that you have proposed.

We have reviewed the proposed request as a site-specific altemative applicable only to ANO-2.

The results of our review indicated that you have provided an acceptable attemative to the requirements of ASME Section XI and have shown that implementation of this program would result in an insignificant change in risk even with fewer inspections, since the inspections will take place where degradation mechanisms are more likely to occur, and procedures and personnel will target these specific locations using improved techniques and expanded volumes. \g We have determined that the alternative method described in your submittal provides equivalent i or better examination criteria for piping inspections than the method provided by the current Section XI requirements.

We therefore conclude that authorization of your proposed attemative for piping systems would provide an acceptable level of quality and safety. Pursuant to 10 CFR 50.55a(a)(3)(i), the p6oh attemative is authorized. It should be noted that the EPRI report is still under development and is the subject of a separate evaluation and that this safety evaluation does not constitute approval of the EPRI methodology in any manner, in addition, this authorization does not 9901050347 981229 PDR ADOCK 05000368 m r , r ~7! F P- PDR fm y{ r[ f '~ , _ ; J' d

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i Mr. C. Randy Hutchinson December 29, 1998 constitute an NRC approval of Code Case N-578 for generic use. The suitability of Code Case N-578 for generic use will be determined following the staff's review of the case. It is expected that the results of the staff's review will be documented in Regulatory Guide 1.147, " Inservice Inspection Code Case Applicability - ASME Section XI, Division 1." Our detailed evaluation and  ;

conclusions are documented in the enclosed safety evaluation. l l

Sincerely, i

Original signed by: l John N. Hannon, Director Project Directorate IV-1  !

Division of Reactor Projects lil/lV Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosure:

As stated cc w/ encl: See next page DISTRIBUTION: j Docket File PUBLIC PD4-1 r/f '

C. Hawes T. Gwynn, RIV C. Nolan OGC ACRS E. Adensam (EGA1)

S. Dinsmoro T. McLellan T. Harris (TLH3)

J.Hannon i' DOCUMENT NAME: G:\anc2fina\A2M99756.rlf

• See Previous Concurrence l Ta receive a copy of this document, indcate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy I OFFICE PM:PDIV-1 l6 LA:PDIV-1 ECGB* SPSB* OGC*

NAME CNolan F CHawes OfiU/ GBagchi RBarrett MYoung DATE 12/ L6 /98 ff 12/ 14 /98 12/14/98 12/17/98 12/24 /98

l. OFFICE ' D:PDIV-1 r[/ 6 I' NAME JHannon '(

DATE 12/?Q /98 '

L

/ OFFICIAL RECORD COPY 4-

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1 Mr. C. Randy Hutchinson l t

constitute an NRC approval of Code Case N-578 for generic use. The suitability of Code Case

]

l N-578 for generic use will be determined following the staff's review of the case. It is expected -l that the results of the staff's review will be documented in Regulatory Guide 1.147, " Inservice i inspection Code Case Applicability - ASME Section XI, Division 1." Our detailed evaluation and  !

conclusions are documented in the enclosed safety evaluation.

i Sincerely, 1

I

= -

John N. Hannon, Director Project Directorate IV-1 Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation Docket No. 50-368

Enclosure:

As stated cc w/ encl: See next page l

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. . - - - = -- - . ~ - . . -.

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l Mr. C. Randy Hutchinson l Entergy Operations, Inc. Arkansas Nuclear One, Unit 2

~ cc:

Executive Vice President Vice President, Operations Support

& Chief Operating Officer. - Entergy Operations, Inc.

Entergy Operations, Inc. P. O. Box 31995 P. O. Box 31995 . Jackson, MS 39286-1995 Jackson, MS' 39286-199 l Wise, Carter, Child & Caraway Director, Division'of Radiation P. O. Box 651 l Control and Emergency Management Jackson, MS 39205

'Arkarsas Department of Health 4815 West Markham Street, Slot 30 l

- Little Rock, AR 72205-3867 Winston & Strawn 1400 L Street, N.W.

Washington, DC 20005-3502 Manager, Rockville Nuclear Licensing Framatone Technologies 1700 Rockville Pike, Suite 525 Rockvillo, MD 20852 Senior Resident inspector i 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 County Judge of Pope County Pope County Courthouse Russellville, AR 72801

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