Text

Amend 26 to License NPF-42,revising Tech Spec 3/4.3.1, Reactor Trip Sys Instrumentation
	ML20236A082
Person / Time
Site:	Wolf Creek
Issue date:	03/01/1989
From:	Calvo J; Office of Nuclear Reactor Regulation
To:	;
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	NUDOCS 8903160362
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UNITED STATES j

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1 WOLF CREEK NUCLEAR CPERATINC CORPORATION WOLF CREEK GENERATING STATION DOCKET NO. 50-482 AMENDMENT TO FACILITY OPERATING LICENSE 1

Amendment No. 26 License No. NPF-42 1.

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

A.

The application for amendment to the Wolf Creek Generating Station (the facility) Facility Operating License No. NPF-42 filed by the Wolf Creek Nuclear Operating Corporation (the Corporation),

dated June 29, 1987, complies with the standards and requirerr.ents of the 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 i

amended, the provisions of the Act, and the rules and regulations i

l of the Comission; C.

There is reasonable assurance:

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

and safety of the public, and (ii) that such activities will be conducted in compliance with the Cossnission's regulations; D.

The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR part 51 of the Cosmission's regulations and all applicable requirements have been satisfied.

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l 8903160362 890301 PDR ADOCK 050004S2 P

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. 2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment 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 through Amendment No. 26, and the Environmental Protection Plan 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 Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Q'0 la Aso

/

Jose A. Calvo, Director l

Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects l

Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 1, 1989 l

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I ATTACHMENT TO LICENSE AMENDMENT NO. 26 l

FACILITY OPERATING LICENSE NO. NPF 42 DOCKET NO. 50-482 Revise Appendix A Technical Specifications by renoving the pages identified below and inserting the enclosed pages. The revised pages are identifiec ty arcndrent nun.ber and contain r.arginhl lines indicating the area of change.

The corresponding overleaf pages are else provided to naintain dccument i

completeness.

REMOVE PAGES INSERT PAGES 3/4 3-4 3/4 3-4 3/4 3-6 3/4 3-6 3/4 3-9 3/4 3-9 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-12a

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,TAljJLL3 3-1_ (Continued)

A TABLE NOTATIONS 80nly if the Reactor Trip System breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.

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- The boron dilution flux doubling signal may be blocked during reactor startup in accordance with norsal operating procedures.

The provisions of Specification 3.0.4 are not applicable.

H Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

fMBelow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)The applicable MODES and ACTION statements for these channels noted in 1

Table 3.3-3 are more restrictive and therefore applicable.

ACTION STATEMENTS

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ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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ACTION 2 - With the number of OPERA 8LE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION say proceed provided the following conditions are satisfied:

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a.

The Inoperable channel is placed in the tripped condition l

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; l

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b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel say be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months i

for surveillance testing of other channels per Specification 4.3.1.1; and j

c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip 5etpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

ACTION 3 - With the number of channels OPERA 8LE one less than the Minimum Channels 0PERABLE requirement and with the THERMAL POWER level:

a.

Below the P'6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERA 8LE status prior to increasing THERMAL POWER above the P 6 Setpoint; or b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 105 of RATED THERMAL POWER, restore the inoperable channel to OPERA 8LE status prior to increasing THERMAL. POWER above 105 of PATED THERMAL POWER.

ACTION 4 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement suspend all operations involving positive reactivity changes.

WOLF CREEK - UNIT 1 3/4 3-5 Amendment No.12

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TABLE 4.3-1 (Continued)

TABLE NOTATIONS (13) CHANNEL CALIBRATION shall ir.clude the RTO bypass loops flow rate.

(14) Each channel shall be tested at least every 92 days on a STAGGERED TEST BASIS.

(15) The surveillance frequency and/or MODES specified for these channels in Table 4.3-2 are more restrictive and, therefore, applicable.

(16) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(17) local manual shunt trip prior to placing breaker in service.

(18) Automatic undervoltage trip.

l 1

i WOLF CREEK - UNIT 1 3/4 3-12a Amendment No.12,26

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ML20236A082

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