ML20128M212

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Forwards RAI Re Second 10-yr Interval Inservice Insp Program Plan & Associated Requests for Relief.Response Requested within 60 Days of Receipt of Ltr
ML20128M212
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 10/10/1996
From: Stone J
NRC (Affiliation Not Assigned)
To: Carns N
WOLF CREEK NUCLEAR OPERATING CORP.
References
TAC-M93381, NUDOCS 9610160024
Download: ML20128M212 (7)


Text

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October 10, 1996 Mr. Neil S. Carns President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839

SUBJECT:

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

Dear Mr. Carns:

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 Boiler & Pressure Vessel Code,Section XI requirements for the Wolf Creek Generating Station. Additional information is required from Wolf Creek Nuclear Operating Corporation in order for the staff to complete its review.

Enclosed is a list of additional conditions that must be met when implementing the referenced requests for relief.

In order to meet the staff's. inservice inspection program plan review schedule, it is requested that a response be provided within sixty 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 PO Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely,

b..Ninek9iONmN f James C. Stone, Senior Project Manager Project Directorate IV-2 Division of Reactor Projects III/IV i

Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:

Docket File PUBLIC

Enclosure:

Request for Additional Information PDIV-2 r/f JRoe EAdensam WBateman cc w/ encl:

See next page EPeyton JStone OGC ACRS DOCUMENT NAME:ISIRAI2.WC JDyer, RIV TMcLellan, 0-7-H-15 To,ooelve e copy of this f------2-4, indicate in the box:

"C" - Copy without enclosures *E" = Copy with enclosures "M" = No copy 0FFICE PDIV-2 o n o D PDIV-2 l

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NAME E. Peyton/tlh J. Stone (/ %

'd DATE 10/C1/96 10/(q96 0FFICIAL RECORD COPY i

9610160024 961010 PDR ADOCK 050004G2 O

PDR NBC FILE CENTER COPY

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4 October 10, 1996 4

Mr. Neil S. Carns i

President and Chief Executive Officer 1

Wolf Creek Nuclear Operating Corporation l

Post Office Box 411 i

Burlington, Kansas 66839

SUBJECT:

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

Dear Mr. Carns:

i The NRC staff is continuing to review and evaluate the second ten-year i

interval inservice inspection program plan and associated requests for relief l

from the ASME Boiler & Pressure Vessel Code,Section XI requirements for the Wolf Creek Generating Station.

Additional information is required from Wolf Creek Nuclear Operating Corporation in order for the staff to complete its review.

{

Enclosed is a list of additional conditions that must be met when implementing 1

the referenced requests for relief.

In order i meet the staff's inservice inspection program plan review schedule, it is requested that a response be provided within sixty 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:

1 Michael T. Anderson l

INEL Research Center 1

2151 North Boulevard i

PO Box 1625 1

1 Idaho Falls, Idaho 83415-2209 Sincerely, krlSl?nek'..70Nm!$

9 fruJamesC. Stone,SeniorProjectManager Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-482 DISTRIBUTION:

i Docket File:

PUBLIC

Enclosure:

Request for Additional Information PDIV-2 r/f JRoe EAdensam WBateman cc w/ enc 1:

See next page EPeyton JStone i

OGC ACRS DOCUMENT NAME:ISIRAI2.WC JDyer, RIV TMcLellan, 0-7-H-15 To reeehe a espy of thie desument. Indloses in the box: *C' = Copy without enclosuree "E" = Copy with enclosu se *N* = No copy i

0FFICE PDIV-2 o_sm, )

PDIV-2 l

NAME E. Peyton/tlh J. Stone (/%

DATE 10/ cl/96 10/ (q96 0FFICIAL RECORD COPY i

oq A nc Al UNITED STATES p

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,j NUCLEAR REGULATORY COMMISSION i

WASHINGTON, D.O. 2056tHM101 o

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October 10, 1996 i

Mr. Neil S. Carns President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 i

l Burlington, Kansas 66839 SU8 JECT:

REQUEST FOR ADDITIONAL INFORMATION, SECOND 10-YEAR INTERVAL 4

INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF, WOLF CREEK GENERATING STATION (TAC NO. M93381)

Dear Mr. Carns:

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 Boiler & Pressure Vessel Code,Section XI requirements for the Wolf Creek Generating Station. Additional information is required from Wolf Creek Nuclear Operating Corporation in order for the staff to compl.ete its review.

Enclosed is a list of additional conditions n must be met when implementing the referenced requests for relief.

In order,o meet the staff's inservice inspection program plan review schedule, it is requested that a response be provided within sixty days of receipt of this letter.

In addition, to expedite the review process, please send a copy of the RAI response to the NRC's contractor, INEL, at the following address:

Michael T. Anderson INEL Research Center 2151 North Boulevard PO Box 1625 Idaho Falls, Idaho 83415-2209 Sincerely, MW (h@wca_(f) i 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 Inforretion cc w/ encl:

See next page j

o s

Mr. Neil S. Carns October 10, 1996 cc w/ encl:

Jay Silberg, Esq.

Vice President Plant Operations 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 Nuclear 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 Sunervisor Regulatory Compliance Utilities Division Wolf Creek Nuclear Operating Corporation 1.

Kansas Corporation Commission P.O. Box 411 1500 SW Arrowhead Road Burlington, Kansas 66839

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Topeka, Kansas 66604-4027 i

Office of the Governor State of Kansas 1

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

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i WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION.

DOCKET NO. 50-482 REQUEST FOR ADDITIONAL INFORMATION SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN 1

l 1.

Scone / Status of Review Throughout the service life of a water-cooled nuclear power facility, l

10 CFR 50.55a(g)(4) requires that components (including supports) that are classified as American Society of Mechanical Engineers (ASME) Boiler i

and Pressure Vessel Code Class 1, Class 2, and Class 3 meet the j

requirements, except design and access provisions and preservice j

examination requirements, set forth in ASME Code Section XI, " Rules for Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components.

This section of the regulations also requires that inservice examinations of components and system pressure tests conducted during successive 120-month inspection intervals comply with the requirements in the latest edition and addenda of the Code incorporated by reference in 10 CFR 50.55a(b) on the date 12 months prior to the start of a successive 120-montn interval, subject to the limitations and modifications listed therein.

The components (including supports) may meet requirements set forth in subsequent editions and addenda of the Code that are incorporated by reference in 10 CFR 50.55a(b) subject to the limitations and modifications listed therein and subject to Nuclear Regulatory Commission (NRC) approval. The licensee, Wolf Creek Nuclear Operating Corporation (WCNOC), has prepared the Wolf Creek Generating Station, Second 10-Year Interval Inservice Inspection Program Plan to meet the requirements of the 1989 Edition of Section XI of the ASME Code. As required by 10 CFR 50.55(g)(5), if the licensee determines that certain Code examination requirements are impractical and requests relief, the licensee shall submit informatioit to tP NRC to support that determination.

The staff has reviewed the available information in the Wolf Creek Generating Station, Second 10-Year Interval Inservice Inspection Progran Plan, submitted August 30, 1995, including the requests for relief from the ASME Code Section XI requirements that the licensee has determined to be impractical. As a result of this review, a request for additional information (RAI) was prepared describing the information and/or clarification required from the licensee in order to complete the review.

The licensee provided the requested information in a submittal dated May 3, 1996. After review of this information, it was determined that further clarification is required to complete the review of the second ten-year program plan.

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i 2.

Additional Information Reauired Based on the above review, the staff has concluded that, in order to authorize the licensee's alternative to the Code requirements, incorporation of the following conditions into the applicable request for relief is necessary. WCNOC is requested to confirm that the conditions stated below will be incorporated into the second ten year ISI program 4

for the referenced relief requests.

A.

Request for Relief 12R-01, IWA-5242(a), System Pressure Tests for Insulated Components:

(1) The licensee perform a VT-2 visual examination of bolted J

connections, without removing the insulation, after satisfying the requirements of IWA-5213, Test Conditfon Holding Time.

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(2) The licensee shall remove all insulation at bolted connections in borated systems during each refueling outage and perform a i

VT-2 visual examination; the connection is not required to be pressurized. Any evidence of leakage shall be evaluated in accordance with IWA-5250.

B.

Request for Relief 12R-02, IWA-5250(a)(2), System Pressure Test Corrective Measures:

(1)

If the initial evaluation indicates the need for a more in-depth evaluation, the bolt closest to the source of leakage i

shall be removed, VT-1 examined, and evaluated in accordance with IWA-3100(a).

C.

Request for Relief 12R-12, Examination Categories C-F-1 and C-F-2, Items C5.12, C5.22, C5.42, C5.52, C5.62, and C5.82, Class 2 Longitudinal Piping Welds:

(1)

For ferritic welds, scanning for reflectors transverse to the weld shall be performed.

(2) Where the longitudinal weld cannot be identified, 100% of the J

circumferential weld shall be examined for flaws parallel and transverse to the weld to ensure that the longitudinal /circumferential weld intersection is examined.

D.

Request for Relief 12R-13, Table IWC-5250-1, Examination Category C-H, Items C7.30, C7.40, C7.70, and C7.80, Pressure Testing of Class 2 Components at Containment Penetrations:

(1) The Appendix J, Type C test will be conducted at the peak calculated containment pressure.

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(2) Where air or gas is used as a testing medium, the test t

procedure shall include methods for detection and location of l

through-wall leaks in system components.

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