ML20043H887

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Amend 39 to License NPF-42,revising Tech Spec 4.8.4.1 to Delete Refs to Table 3.8-1 Previously Removed from Tech Specs in Amend 28
ML20043H887
Person / Time
Site: Wolf Creek 
Issue date: 05/30/1990
From: Hebdon F
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20043H886 List:
References
NUDOCS 9006270027
Download: ML20043H887 (7)


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NUC6 EAR RE@ULATORY COMMISSION n

5-r mamwatow. o. c. nous e.,.....j WOLF CREEK NUCLEAR OPERATING CORPORATION l

WOLF CREEK GENERATING STATION f

DOCKET NO. 50-482 i

AMENDMCNTTOFACILITY'0PERATING'LICENS,J,.

E Amendment No. 39 License No. NPF-42 I

1.

The Nuclear Regulatory Comission (the Comission) has found that:

i A.

The application for amendment to the' Wolf Creek Generating Station l

(the facility) Facility Operating License No. NPF-42 filed by the WolfCreekNuclearOperatingCorporation(theCorporation), dated Harch 2, 1990, complies with the standards and requirements of the i

Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, as amended, the provisions of the Act, and the. rules and regulations of the Comission; i

C.

There is reasonable assurance:

(i)thattheactivitiesauthorized by this anendment can be conducted without endangering the health i

and safety of the public, and (ii) that such activities will be ccnducted in complicace with the Cowimission's' regulations; L

0.

The issuance of this license nendment will not be inimical to the I

common defense and security or te the health and safety of the public; and E.

The issuanco of this emendment is in accordance with 10 CFR Part 51 l

of the Comission's regulattor,s ar#all appitcable requirements have 7

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l 9006270027 900530 ADOCK0500gp2 DR o

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1 2.

Accordingly, the license is amended by changes to the Technical Specif t-cations as indicated in the attachnent to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-42 is hereby amended to read as follows:

2.

Technical Specifications The Technical Specifications contained in Appendix A, as revised 1

through Amendment No. 39 and the Environmental Protection Plan

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contained in Appendix B, both of which are attached hereto, are hereby incorporated in the license. The Corporation shall operate the facility in accordance with the Technical Specifications and the l

Environmental Protection Plan, i

3.

The license amendnent is effective as of its date of issuance.

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i FOR THE NUCLEAR REGULATORY COMMISSION

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Frederick J. Heydon, Director Project Directorate IV Division of Reactor Projects - Ill, IV, Y and Special Projects Office of Nuclear Reactor Regulation Attachrent:

Charges to the Technical l

Specifications l

Date of Issuance:

May 30, 1990 i

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ATTACHMENT TO LICENSE AMENDMElli H0. 39 FACILITY OPERATING LICENSE NO. NPF-42 DOCKET No. 50-482 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginal lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE DAGES INSERT PAGES XI XI 3/4 8-16 3/4 8-16 I

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',' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS i

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FAG {

- PLANT SYSTEMS (Continued) f 3/4.7.1D DELETED i

l TABLE 3.7-3 DELETED L

3/4.7.11 DELETED L

3/4.7.12 AREA TEMPERATURE MDNIT0 RING..............................

3/4 7-27 ic TABLE 3.7-4 AREA TEMPERATURE MONITORING...........................

3/4 7-28 I

l-3/4.8 ELECTRICAL POWER SYSTEMS i

3/4.8.1 A.C. SOURCES Operating................................................

3/4 8-1 j

TABLE 4.8 1 DIESEL GENERATOR TEST SCHEDULE........................

3/4 8-7 l

Shutdown.................................................

3/4 8-8 3/4.8.2 D.C. SOURCES l

Operating................................................

3/4 8-9 TABLE 4.8 2 BATTERY SURVEILLANCE REQUIREMENTS.....................

.3/4 8-11 Shutdown................................................,

3/4 8-12 3/4.8.3 ONSITE POWER DISTRIBUTION i

0perating................................................

3/4 8-13 Shutdown.................................................-

3/4 8-15 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent i

Protective Devices.....................................

3/4 8-16 i

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WOLF CREEK - UNIT 1 XI Amendment No. 25,39

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LIMITING CONDITIONS FOR OPERATION AND $URVEILLANCE REQUIREMENT $

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3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION......................................

3/4 9-1 3/4.9.2 INSTRUMENTATION..........................................

3/4 9-2 3/4.9.3 DECAY TIME..................................'.............

7/4 9-3 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS........................

3/4 9-4 3/4.9.5 COMMUNICATIONS...........................................

3/4 9-5 3/4.9.6 REFUELING MACHINE........................................

3/4 9-6 3/4.9.7 CRANE TRAVEL - $ PENT FUEL STORAGE FACILITY...............

3/4 9 8 i

3/4.9.8 RESIDUAL HEAT REMOVAL AND C0OLANT CIRCULATION l

High Water Leve1.........................................

3/4 9-9 Low Water Lrre1..........................................

3/4 9-10 3/4.9.9 CONTAINMENT VENTILATION SYSTEM...........................

3/4 9 11 3/4.9.10 WATER LEVEL - REACTOR VESSEL Fuel Assemb11es..........................................

3/4 9-12.

Control Rods,...........................................

3/4 9-13 3/4.9.11 WAT E R LEVE L - STORAGE P00L..............................

3/4 9-14 3/4.9.12 SPENT FUEL ASSEMBLY ST0 RAGE..............................

3/4 9-15 FIGURE 3.9 1 MINIMUM REQUIRED FUEL ASSEP*LY EXNSURE AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGION 2........................................

3/4 9-16 3/4.9.13 EMERGENCY EXHAUST SYSTEM.................................

3/4 9-17 l

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l WOLF CREEK - UNIT 1 XII lw -

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~ ELECTRICAL: POWER SYSTEMS L

DN$1TE POWER DI57RIBLff!0N.

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$NUTDOWN LIMITING CONDITION FOR OPERATION 3.8.3.2 As a minimum, one of the following divisions of electrical busses shall be energized in the specified manner:

1j Division 1, consisting of:-

a.

2) 4160 Volt Emergency Bus #NB01, and 2) 480 Volt Emergency Susses #NG01, NG03 and N005E, and j

3) 120 Volt A.C. Vital Busses fMN01 and NNO3 energized from their j

. associated inverter conpected to D.C. Busses #NK01 and NK03, and i

4) 125 volt D.C. Susses #NK01 and NK03 energized from Batteries i

  1. NK11 and NK13 and Chargers #NK21 and NK23, or b.

Division 2 consisting of:

1) 4160 Volt Emergency Bus #N802, and 2) 480 Volt Emergency Busses #NG02, NG04 and NG0$E, and 3) 120 Volt A.C. Vital Busses #NN02 and NN04 anergiaod free their associated inverter connected to 0.C. Busses #NK02 and NK04, and 4) 126 Volt 0.C. Busses #NK02 and NK04 energized free Batteries

  1. NK12 and NK14 and Chargers #NK22 and #NK24 APPLICA?1LITY:

MODES 5 and 8.

ACTION:

Without one of the above required divisions of electrical busses energized 1n the required manner immediately sus

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T10NS, positive reac,tivity changes, pend all operations involving CORE ALTERA-or movement of irradiated fuel; initiate corrective action to energite at least one division of the required busses in the specified manner.

$URVE!LLANCE REQUIREMENTS o

'4.8.3.2 The specified busses shall be detemined energized in the required manner at least once per 7 days by verifying correct breaker alignment and indicated voltage on the busses.

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-WOLF CREEK - UNIT 1 3/4 4 15

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ELECTRICAL POWER SYSTEMS 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LINITING CONDITION FOR OPERATION 3.8.4.1 For each containment penetration provided with a penetration con'Juctor overcurrent protective device (s), each device shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, and 4.

ACTION:

With one or more of the above required containment penetration conductor overcurrent protective device (s) inoperable:

Restoretheprotectivedev(ce(s)toOPERABLEstatusordoenergite a.

the circuit (s) by tripping the associated backup circuit breaker or racking out or removing the inoperable circuit breaker within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, declare the affected system or component inoperable, and verify the backup circuit breaker to be tripped or the inoperable circuit breaker racked out, or removed, at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their backup circuit breakers tripped, their inoperable circuit breakers racked out, or removed, or b.

Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUsREMENTS 4.8.4.1 Protective devices required to be OPERABLE as containment penetration conductor overcurrent protectivo devices shall be demonstrated OPERABLE.

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a.

At least once per 18 months:

1)

By verifying that the 13.8 kV circuit breakers are OPERABLE by i

selecting, on a rotating basis, at least 10% of the circuit breakers, and performing the following:

l a)

A CHANNEL CALIBRATION of the associated protective relays, b)

An integrated system functional test which includes simulated automatic actuation of the system and verifying that each i

relay and associated circuit breakers and control circuits function as designed, and

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WOLF CREEK - UNIT.1 3/4 8-16 Amendment No. 28,39

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