ML20203F029

Forwards Bases Pp Rev Re TSs 3/4.8.1,3/4.8.2 & 3/4.8.3 AC Sources,Dc Sources & Onsite Power Distribution as Provided by .Nrc Has Reviewed Changes & Finds Rev Acceptable

ML20203F029
Person / Time
Site:	Wolf Creek
Issue date:	12/09/1997
From:	Thomas K NRC (Affiliation Not Assigned)
To:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
References
TAC-M99932, NUDOCS 9712170267
Download: ML20203F029 (5)

Text

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(D December 9,1997 - '

• I 4 Mr. Otto L. Maynard

' President and Chief Executive Officer Wolf, Creek Nuclear Operating Corporation Post Office Box 411 '

Burlington Kansas 66B39

SUBJECT:

WOLF CREEK GENERATING STATION - TECHNICAL SPECIFICATION BASES -

CHANGE.-INSTALLATION OF SPARE BATTERY CHARGERS (TAC NO. M99932)

Dear Mr. Maynard:

The staff has incorporated the revision of the Bases for Technical Specifications 3/4.8.1, 3/4.8.2. and 3/4.8.3 "A.C. Sources. D.C. Sources and Onsite Power Distribution" as provided by your letter dated November 6. 1997, into the Wolf Creek Generating Station Technical Specificat. ions. This revision 3rovides the_ appropriate details of operatica of the installed spare battery clargers to ensure consistent application of the Limiting Condition-for Operations and Action Statement.

The staff has reviewed the change and finds the revision to the associated technical specification Bases to be acceptable. The overleaf page is provided to maintain document completeness.

Sincerely.

ORIGINAL SIGNED BY Kristine Thomas. Project-Manager Project Directorate IV-2 Division of Reactor Projects lil/IV Office Sf Nuclear Reactor Regulation Docket No. 50-482 )lSTRIBUT: ON:

)ocket F1 e . KThomas

Enclosure:

Bases Pages PUBLIC .

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OFFICIAL RECORD COPi . . . .

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Mr. Otto L. Maynard - 2-cc w/ enc 1:

Jay 511 berg. 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 i U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation i 611 Ryan Plaza Drive. Suite 1000 P.O. Box 411 Arlington.. Texas 76011 Burlington, Kansas 66839 l Senior Resident Inspector U.S. Nuclear Regulatory Commission  ;

U.S. Nuclear Regulatory Coenission Resident Inspectors Office P. O. Box 311 8201 NRC Road l Burlington.-Kansas 66839 Steedman. Missouri 65077-1032

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-Chief Engineer-Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road i

Topeka. Kansas 66604 4027  ;

Otfice of the Governor  :

1 State of Kansas Topeka, Kansas 66612 i Attorney General '

Judicial Center 301 S.W. 10th 2nd Floor Tepeka. Kansas 66612 County Clerk Coffey County Courthouse Burlington, kansas 66839

, Vick L. Cooper. Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation  :

Forbes F1 eld Building 283 .

4 Topska. Kansas 66620 i

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3/4 8 ELECTRICAL POWER SYSTEMS BASES 3/4 L1. 3/4,8 2. and 3/4.8.3 A.C. SOURCES. D C. SOURCES. AND ONSITE POWER DISTRIBUTION The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety related equipment required for: (1) the safe shutdown of the facility, and (2) the mitigation and control of eccident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. >ower sources and distribution systenG utisfy the requirements of General )esign Criterion 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation comensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial condition assumptions of the safety anal A.C.yses andpower and D.C. are based sourcesupon and maintaining at least one associated distribution redundant set of onsite systems-OPERABLE during accident conditions coincident with an assumed h of offsite power and single failure of the other onsite A.C. source. The C. source and D.C.

source allowable out of service times are based on Regulac.ry Guide 1.93.

" Availability of Electrical Power Sources". December 1974. When one diesel generator is inoperable, there is an additional ACTION requirement to verify-that all required systems. subsystems, trains, components and devices, that depend on the remaining OPERABLE diesel generator as a source of emergency power, are also OPERABLE and that the steam driven 6uxiliary feedwater pump is OPERABLE. This requirement is intended to provide assurance that a loss-of offsite power event will not result in a complete loss of safety function of critical systems during the period one of the diesel generators is inoperable. The term verify as used in this context means to administratively check by examining logs or other information to determine if certain components are out of-service for maintenance or other reasons. It does not mean to perform the Surveillance Requirements needed to demonstrate the OPERABILITY of the component.

The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that:

(1) the facility can be maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability are available for monitoring and maintaining the unit status.

A D.C. electrical source consists of a battery bank, associated full capacity chi..ger and the D.C. bus. The associated full capacity charger is the charger that is supplying )ower to the bus and battery bank (NK21 for NK11. NK23 for NK13. NK22 for 9K12. NK24 for NK14) or (NK25 for NK11 or NK13 or NK26 for NK12 or NK14). LC0 3.8.2.1 and 3.8.2.2 are met by restoring the required full capacity charger to OPERABLE status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> by either 1) providing the normal supply to its associated battery bank and bus or 2) by supplying the battery bank and bus using the spare charger (powered from its safety related bus) in that train. The spare charger is maintained energized (except during maintenance activities) when not in service to allow immediate

. WOLF CREEK - UNIT 1 B 3/4 8 1 Agndmentg.(5g55.101 DAeder 9[16hE

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ELECTRICAL POWER SYS1 EMS FEES _ I A_C SOURCES. D C= SOURCES. AND ONSITf POWER DISTRIBUTION (Contit.ued)

(< 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) alignment to the battery bank and bus when the associated full capacity charger is inoperable. Surveillance Requirement 4.8.2.la applies only to those chargers connected to a battery bank and bus. The preferred D.C electrical source alignment consists of the normal chargers (NK21. NK22.

NK23 and NK24) supplying the associated battery bank and bus.

When determining compliance with action statement requirements. addition to the RCS of borated water with a concentration greater than or equal to the minimum required RWST concentration shall not be considered to be a positive

.4ctivity change.

The surveillance requirements of Technical Specification 3/4.8.1 are based upon, in part, the guidance of Generic Letter 94-0). " Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators from Plant Technical Specifications." Generic Letter 93-05 "Line-ltem Technical Specif1 cat 1ons improvements to Reduce Surveillance Requirements for festing During Power Operation." Regulatory Guide 1.9. " Selection, Design.

Qualification, and Testing of lmergency Diesel Generator Units Used as Class 1E Onsite Electrical Power Systems at Nuclear Power Plants." Revision 3. and WOLF CREEK - UNIT 1 B 3/4 8-la December 9, 1997 l

ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. AND ONSITE POWER DISTRIBUTION (Continued)

NUREG-1431, " Standard Technical Speci'ications - Westinghouse Plants." Also, the guidance of NUMARC 87-00, "Geldelines and Technical Bases for NUMARC Initiatives Addressing Station Blackout at Light Water Reactors," Revision 1, and Regulatory Guidt 1.160 has been adopted to formulate a comprehensive Emergency Dict.el Generator Reliability Program.

Technical Specification 3.8.1.1, Action b and c, require, in part, the demonstratio.1 of the operability of the remaining operable emergency diesel generator by performing Technical Specification 4.8.1.1.2a.4. This test is required to be completed regardless of when the inoperable emergency diesel generator is restored to operable status unless the emergency diesel generator was declared inoperable to do preplanned preventative maintenance, testing, or maintenance tc correct a condition whir $', if left uncorrected, would not affect the operability of the emergency diesel generator. The requirement to test the remaining operable emergency diesel generator when one emergency diesel generator is inoperable is limited to those situations where the cause for inoperability cannot be conclusively demonstrated ir, order to preclude the potential for common mode failures. The test is not required to be accomplished if the emergene; ;i(*? generator was declared inoperable due to an inoperable support system u m h4 pendently testable component. When such a test is required, it is i s h d to be performed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for ACTION b and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for ACTION c of having determined that the ecergency diesel generator is inoperable.

Technical Specification 4.8.1.1.2a.4 is considered to be a " Start Test" as described in Regulatory Guide 1.9, Revision 3. A " Start Test" is performed to demonstrate proper startup from standby conditions and to verify that the required design voltage and frequency is attained. For thes) tests.

Regulatory Guide 1.9, Revision 3, recommends that the emergency diesel generators be slow started and allowed to reach rated speed on a prescribed schedule that is selected to minimize stress and wear.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2a.5 to be a " Load-Run Test". A " Load-Run Test" demonstrates 90 to 100 percent (5580 to 6201 kilowatts) of the continuous rating (6201 kilowatts) of the emergency diesel generator for an interval of not less than I hour and until temperature equilibrium has been attained. This test may be accomplished by synchronizing the generator with offsite power and the loading and unloading of a diesel generator during this test should be gradual and based on a prescribed schedule that is selected to minimize stress and wear on the diesel generator.

Regulatory Guide 1.9, Revision 3, considers Technical Specification 4.8.1.1.2f to be a " Fast-Start Test". A " fast-Start Test" demonstrates that l each emergency diesel generator starts from standby conditions, if a plant normally has in operation keep warm systems designed to maintain lube oil and jacket water cooling at certain temperatures or prelubrication systems or both, this would constitute normal standby conditions for that plant.

Verification that the emergency diesel generator reaches required voltage and frequency within acceptable limits and time is also required, WOLF CREEK - UNIT 1 B 3/4 8-2 Amendment No. 101 )

April 24, 1997 l

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