ML20153F828

Submits Response to Util 880322 Request for Relief from ASME Boiler & Pressure Vessel Code Section XI to Permit Use of non-code Const Parts in Code Classed Components.Safety Evaluation Approving Requested Relief Encl

ML20153F828
Person / Time
Site:	Wolf Creek
Issue date:	05/02/1988
From:	Oconnor P Office of Nuclear Reactor Regulation
To:	Withers B WOLF CREEK NUCLEAR OPERATING CORP.
Shared Package
ML20153F831	List: ML20153F828 ML20153F847
References
TAC-67580, NUDOCS 8805110061
Download: ML20153F828 (5)

Text

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. . %og UNITED STATES \Jc 1,C g, NUCLEAR REGULATORY COMMISSION

[ E WASHINGTON, D. C. 20555 3

e May 2,1988 4.....

Docket No. 50-482 Mr. Bart D. Withers President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, Kansas 66839

SUBJECT:

REQUEST FOR RELIEF FROM SECTION XI 0F ASME CODE REQUIREMENT (TAC NO. 67580)

The NRC staff has completed its review of your submittal dated March 22,

. 1988. Your submittal requested relief from Section XI of the ASME Boiler and Pressure Vessel Code (Code) for the Wolf Creek Generating Station to permit the following use of non-Code construction parts in Code classed components:.

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1. Use of a non-Code construction stem / disc assembly as an interim '

replacement for the required Code construction sten / disc assembly in the reactor coolant pump seal water injection throttling, valve BG V200, and; I

2. Use of a non-Code construction packing box assembly as an interim l replacement for the Code required packing box assembly in l pressurizer spray valve BB PCV 455R, l The staff has reviewed your submittal and has concluded that:

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1. In the case of reactor coolant pump seal water injection throttling -

valve BG V200, the valve was manufactured in complete accordance with the Code and is of acceptable quality, and;

2. With regard to pressurizer spray valve BB PCV 455B packing box assembly, you have adequately verified that the assembly will provide an acceptable level of safety for interim plant operation.

ee05110061 080502 DR ADOCK 0500 2

l 2-The staff has-determined pursuant to 10 CFR Part 50.55a(a)(3)(fi), that > -

compliance with the Code would result in hardship for. the licensee without a compensating increase in the level of quality and safety.

Based upon our reviews we have concluded that your requested relief may be granted and the plant ray continue to operate until the next refueling outage.

A copy of the staff's related Safety Evaluation is enclosed.

Sincerely 4

/s/

Paul W. O'Connor, Project Manager Project Directorate - IV ,

Division of Reactor Projects - III, IV, V and Special Projects

Enclosure:

As stated cc w/ enclosure:

See next page l

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DISTRIBUTION 196cket File NRC PDR Local PDR PD4 Reading l

L. Rubenstein J. Calvo P. Noonan P. O'Connor-OGC-Rockville E. Jordan J. Partlow ACRS (10) l PD4 Plant File l

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The staff has determined pursuant to 10 CFR Part 50.55a(g)(6)(i), that the I granting of this relief is authorized by law and will not endanger life or l I

property or the comon defense and security and is otherwise in the public interest. In making this detemination, ve have given due consideration to l the burden that could result if these requirements were imposed on the j facility. 1 Based upon our reviews we have concluded that your requested relief may be granted and the plant may continue to operate until the next refueling outage.

A copy of the staff's related Safety Evaluation is enclosed.

Sincerely Paul W. O'Connor, Projec Manager Project Directorate - 1 DivisionofReactorP/ojects-III, IV, Y and Special /rojects

Enclosure:

l As stated cc w/ enclosure:

See next page

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Docket File / NRC PDR Local PDR P 4 Reading L. Rubenstein / J. Calvo P. Noonan . O'Connor OGC-Rockville / E. Jorda 1 J. Partlow ACRS(10)

PD4 Plant File / 6)

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-2 The staff has determined pursuant to 10 CFR Part 50.55a(a)(3)(fi), that compliance with the Code would result in hardship for the licensee without a cottpensating increase in the level of quality and safety.

Based upon our reviews we have concluded that your requested relief ray be granted and the plant may continue to onerate until the next refueling outage.

A copy of the staff's related Safety Evaluation is enclosed.

Sincerely,

)

Paul W. O'Connor, Project Manager I Project Directorate - IV  !

Division of Rear. tor Projects - III, IV, V and Special Projects  ;

Enclosure:

As stated cc w/ enclosure:

See next page i

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Mr. Bart D. Withers Wolf Creek Generating Station Wolf Creek Nuclear Operating Corporation Unit'No. 1 cc:

Jay Silberg, Esq. Mr. Gerald Allen Siiaw, Fittman, Pctts & Trowbridge Public Health Physicist 1800 M Street, NP Bureau of Air Ouality & Radiation Washington, D.C. 20036 Control

. Division of Envirorrent Chris R. Rogers, P.E. Kansas Department of Health Manager, Electric Department and Environment Public Service Commission Forbes Field Building 321 P. O. Box 360 Topeka, Kansas 66620 Jefferson City, Missouri 65102 Mr. Gary Boyer, Plant Manager Regional Administrator, Region III Wolf Creek Nuclear Operating Corp.

U.S. Nuclear Regulatory Commission P. O. Box 411 799 Roosevelt Road Burlington, Kansas 66839 Glen Ellyn, Illinois 60137 Regional Administrator, Region IV Senior Resident Inspector / Wolf Creek U.S. Nuclear Regulatory Commission c/o U. S. Nuclear Regulatory Commission Office of Executive Director P. O. Box 311 for Operations Burlington, Kansas 66839 611 Ryan Plaza Drive, Suite 1000 Mr. Robert Elliot, Chief Engineer Utilities Division Mr. Otto Maynard, Manager Licensing Kansas Ccrporation Commission Wolf Creek Nuclear Operating Corp.

4th Floor - State Office Building P O. Box 411 Topeka, Kansas r ?.012-1571 Burlington, Kansas 66839 e

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