ML20135E185

Forwards RAI Re Plant,Second 10-yr Internal ISI Program Plan & Associated Requests for Relief

ML20135E185
Person / Time
Site:	Wolf Creek
Issue date:	03/04/1997
From:	Stone J NRC (Affiliation Not Assigned)
To:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
References
TAC-M93381, NUDOCS 9703060339
Download: ML20135E185 (5)

Text

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March 4, 1997 i

Mr. Otto L. Maynard i President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation l

, Post Office Box 411 -

Burlington, Kansas 66839 i

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE WOLF CREEK

, GENERATING STATION, SECOND 10-YEAR INTERVAL INSERVICE INSPECTION j PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF (TAC NO. M93381) l

Dear Mr. Maynard:

The NRC ' staff is continuing to review and evaluate the second-ten-year interval inservice inspection program plan and associated requests for relief from the ASME B&PV Code, Section'XI requirements for Wolf Creek Generating Station. Additional information is required from Wolf Creek Nuclear Operating i Company in order for the staff to complete its review. The information required is detailed in the enclosure.

In order for the staff to meet its inservice inspection program review schedule, it is requested that a response be provided within 60 days of receipt of this letter. In addition, to expedite the review process, please send a copy of the RAI response to NRC's contractor, INEL, at the following address:

Michael T. Anderson INEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely, CEERCOM ori94nai Si9ned By James C. Stone, Senior Project Manager Project [" rectorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:

Docket File EPeyton

Enclosure:

Request for Additional PDIV-2 R/F WBateman Infarr.iation PUBLIC JStone JRoe ACRS cc w/ encl: See next page EAdensam TMcLeelan, 0-7H15 OGC AHowell, RIV ff p {3 /

DOCUMENT NAME: 93381RAI.WC4 0FC PDIV-2/PM hPDIV-2/LA NAME JStone:ye , EP W DATE 'j/ d /97 2Efl/97 0FFICIAL RECORD COPY 9703060339 970304 O PDR ADOCK 05000482 P PDR

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2 NUCLEAR REGULATORY COMMISSION WMHINGToN, D.C. 2006H001 8 March 4, 1997 k[. . . . . ,o Mr. Otto L. Maynard I President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839 I

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING THE WOLF CREEK '

GENERATING STATION, SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF (TAC NO. M93381)

Dear Mr. Maynard:

The NRC staff is continuing to review and evaluate the second ten-year interval inservice inspection program plan and associated requests for relief from the ASME B&PV Code,Section XI requirements for Wolf Creek Generating Station. Additional information is required from Wolf Creek Nuclear Operating i Company in order for the staff to complete its review. The information required is . detailed in the enclosure.

In order for the staff to meet its inservice inspection program review 1 schedule, it is requested that a response be provided within 60 days of receipt of this letter. In addition, to expedite the review process, please send a copy of the RAI response to NRC's contractor, INEL, at the following address:

Michael T. Anderson INEL Research Center 2151 North Boulevard P.O. Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely, b

ad W James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-482

Enclosure:

Request for Additional Information cc w/ encl: See next page

s Mr. Otto L. Maynard March 4,1997 l cc w/ encl: 1 Jay Silberg, Esq. Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation  ;

2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 Burlington, Kansas 66839 Regional Administrator, Region IV Supervisor Licensing U.S. Nuclear Regulatory Commission Wolf Creek Nucleat Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident Inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident Inspectors Office P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the G;vernor -

State of Kansas Topeka, Kansas 66612 Attorney General Judicial Center 301 S.W. 10th 2nd Floor Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Public Health Physicist Bureau of Air & Radiation Division of Environment Kansas Department of Health and Environment Forbes Field Building 283 Topeka, Kansas 66620

j WOLF CREEK NUCLEAR OPERATING CORPORA 110N WOLF CREEK NUCLEAR GENERATING STATION DOCKET NO. 50-482 RE0 VEST FOR ADDITIONAL INFORMATION SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN 1

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1. Scoce/ Status of Review

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The Nuclear Regulatory Commission (NRC) is responsible for the review and disposition of licensee requests relating to inservice inspection requirements contained in the Code of Federal Regulations (CFR) 10 CFR 50.55a, and the American Society of Mechanical Engineers (ASME),

Section XI. . Included within each request, licensees are required to provide both a regulatory basis (by citing the appropriate section of 10 CFR 50.55a), and a technical discussion, to support the request.

This information is used to establish the context for each evaluation.

The staff has reviewed the additional information submitted in the letter dated December 9, 1996. As a result of this review, additional information is required in order to complete the staff's review.

2. Additional Information Reauired Based on the review of the December 9, 1996 submittal, the staff has concluded that the following additional information and/or clarification is required to complete the evaluation.

1. Under Item A, the licensee provided the following additional paragraph:

"When pressure testing piping systems that contain boron for the purpose of controlling reactivity, the insulation will be removed, on the same frequency as that required for performance of the pressure test, and VT-2 visually examined, without the system at normal operating pressure. Any evidence of leakage will be evaluated in accordance with IWA-5250."

The current position that the NRC has adopted on insulation removal is consistent with Code Case N-533, Alternative Requirements for VT-2 Visual Examination of Class 1 Insulated Pressure Retaining Bolted Connections. Paragraph (2) of this Code case states: "Each refueling outage the insulation shall be removed from the bolted connection, and a VT-2 visual examination shall be performed. The connection is not required to be pressurized. Any evidence of leakage shall be evaluated in accordance with IWA-5250."

Provide the basis for the current position to remove the insulation on a per period basis only.

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2. Under Item B, the licensee noted an addition to the corrective- J

. measures as follows:

l "In addition, if the leakage is identified at a bolted connection )

tr.,t is in service and the evaluation supports continued service, 4 toe bolt removal and subsequent VT-3 may be deferred to the next component / system outage of sufficient duration."

j Later editions of the Code have provided an alternative to the

removal of all bolting at a leaking connection. The licensee's 1 approach to perform an evaluation of the bolted joint to determine.

}. the need to remove one bolt is considered too generic to be considered acceptable. An. evaluation to determine whether deferral is acceptable is not supported by ISI philosophy.

3 Therefore the licensee should consider the withdrawal of'this i paragraph.

l 3. For Item C, Request for Relief 12R-12 addresses both Categories

C-F-1 and C-F-2. However, the licensee noted that the relief does

not apply to ferritic piping (C-F-2) as inspection will continue ,

i to be performed on the longitudinal welds in ferritic piping in l accordance with the Code. It is unclear why the licensee has taken exception to ferritic pipe longitudinal welds. Is this request for austenitic piping only? ProYide the basis for the j current position.

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