ML20196K032

Informs That Staff Has Incorporated Rev of Bases for TS 3/4.4.4, Relief Valves, Requested by .Rev Clarifies Bases to Be Consistent with Amend 63 to Wolf Creek TSs .Rev Acceptable.Bases Page Encl

ML20196K032
Person / Time
Site:	Wolf Creek
Issue date:	12/08/1998
From:	Thomas K NRC (Affiliation Not Assigned)
To:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
References
TAC-MA4197, NUDOCS 9812110170
Download: ML20196K032 (4)

Text

.. . . .. _ - - - .. .-.

P * ,

December 8, 1998 Mr. Otto L, Maynard President and Chief Executive Officer Wolf Creek Nuclear Coerating Corporation Post Office Box 411 i Burlington, Kansas 66839 1 l

SUBJECT:

WOLF CREEK NUCLEAR GENERATING STATION - TECHNICAL SPECIFICATION BASES CHANGE, RELIEF VALVES (TAC NO. MA4197)

Dear Mr. Maynard:

The staff has incorporated the revision of the Bases for Technical Specification 3/4.4.4," Relief Valves" requested by your letter dated November 6,1998, into the Wolf Creek Nuclear Generating Station Technical Specifications. The revision clarifies the Bases to be consistent with Amendment No. 63 to me Wolf Creek Technical Specifications dated June 23,1993, l regarding maintaining power to closed, power-operated relief valve (PORV) block valves when  ;

the associated PORV is experiencing excessive seat leakage.

The staff has reviewed the change and finds the revision to the Bases to be acceptable. The )

corresponding overleaf page is provided to maintain document completeness.

Sincerely,

• Original Signed By Kristine M. Thomas, Project Manager

Project Directorate IV-2 i Division of Reactor Projects Ill/IV Office of Nuclear Reactor Regulation t Docket No. 50-482 DISTRIBUTION Docket File

Enclosure:

Bases Pages PUBLIC PDIV-2 Reading cc w/ encl: See next page EAdensam (EGA1)

OGC WBateman KThomas ACRS PGwynn, RIV j WJohnson, RIV i EPeyton WBeckner GHill(2)

DOCUMENT NAME: WCA4197.LTR *See Previous Concurrence Sheet Q(o\

OFC PDIV-2/PM PDIV-2/LA NRR:TSB*

vrvt . oe s t NAME KThomas EPeytdn WBeckner i DATE 12/8 /98 12/8 /98 12i3.98 ,

OFFICIAL RECORD COPY ,

9812110170 981208 PDR ADOCK 05000482 P ,

PDR -

] {}.{T hfp[p eg f

l l

Mr. Otto L. Maynard December 8, 1998 cc w/ encl:

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 66639 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 Regu:atory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 650'77-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the Governor 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 i

Vick L. Cooper, Chief l Radiaticn Control Program j l Kansas Department of Health 1 and Environment l l Bureau of Air and Radiation Forbes Field Buildirig 283  ;

Topeka, Kansas 66620 1

4 l

1 I

l

e : -

3/4.4 REACTOR COOLANT SYSTEM BASES 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION The plant is designed to operate with all reactor coolant loops in operation and maintain DNBR above the safety analysis limit DNBR (1.32) during all normal operations and anticipated transients. In MODES I and 2 with one reactor coolant loop not in operation this s.pecification requires that the plant be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

In MODE 3, two reactor coolant loops provide sufficient heat removal capability for removing decay heat even in the event of a bank withdrawal accident; however, single failure considerations require that three loops be OPERABLE. A single reactor coolant loop provides sufficient heat removal if a bank withdrawal accident can be prevented; i.a., by opening the Reactor Trip System breakers.

In MODE 4, and in MODE 5 with reactor coolant loops filled, a single reactor coolant loop or RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations require that at least two loops (either RHR or RCS) be OPERABLE.

In MODE 5 with reactor coolant loops not filled, a single RHR loop provides sufficient heat removal capability for removing decay heat; but single failure considerations, and the unavailability of the steam generators 1 as a heat removing component, require that at least two RHR loops be OPERABLE. '

The operation of one reactor coolant pump (RCP) or one RHR pump provides adequate flow to ensure mixing, prevent stratification and produce gradual reactivity changes during boron concentration reductions in the Reactor Coolant System. The reactivity change rate associated with boron reduction will, therefore, be within the capability of operator recognition and control.

Addition of borated wate: with a concentration greater than or equal to the minimum required RWST concentration but less than the actual RCS boron concentration shall not be considered a reduction in boron concentration.

The restrictions on starting a reactor coolant pump in MODES 4 and 5 are provided to prevent RCS pressure transients, caused by energy additions from the Secondary Coolant System, which could exceed the limits of Appendix G to 10 CFR Part 50. The RCS will be protected against overpressure transients and will not exceed the limits of Appendix G by restricting starting of the RCPs to when the secondary water temperature of each steam generator is less than 50*F above each nf the RCS cold leg temperatures.

3/4.4.2 SAFETY VALVES The pressurizer Code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 420,000 lbs per. hour of saturated steam. I WOLF CREEK - UNIT 1 8 3/4 4-1 Amendment No. M ,89 W -