ML20133N388

Amend 79 to License DPR-6,re Changes to Several Tech Spec Surveillance Frequencies to Provide for Operation Between Refueling Shutdowns W/O Potential Surveillance Test Performance Interruptions

ML20133N388
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	10/22/1985
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML20133N387	List: ML20133N384 ML20133N388 ML20133N393
References
NUDOCS 8510290365
Download: ML20133N388 (19)

Text

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1. (og UNITED STATES

[ g NUCLEAR REGULATORY COMMISSION

, E "j WASHINGTON, D. C. 20555

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CONSUMEPS POWER COMPANY DOCKET N0. 50-155 BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 79 License No. DPR-6

1. The Nuclear Regulatory Commission (the Commission) has found that

A. The application for amendment by Consumers Power Company (the licensee) dated June 27, 1985 corplies with the standards and requirements o' the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and i regulations set forth in 10 CFR Chapter I; B. The facility will operate in confomity with the application, the provisions of the Act, end the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities

, authorized by this anendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compl i-ance with the Comission's regulations; D. The issuance of this amendment will not be ininical 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 Comission's regulations and all applicable requirenents have been satisfied.

0510290365 851022 i PDR ADOCK 05000155 p PDR

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2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license amendment and Paragraphs 2.C.(2) of Facility Operating License No. DPR-6 are hereby amended to read as follows:

1 (2) Technical Specifications The Technical Specificatiens contained in Appendix A as revised through Amendment No. 79, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical  ;

Specifications.

. 3. This license amendment is effective as of the date of its issuance.

FOR THE NUCLEAP PEGULATOP. C0 SSION kS' ,

. Zwolinski, Chief

[ John Operat'ng Reactors Branch #5 Division of Licensing

Attachment:

Changes to the Technical Specifications Dat? of Issuance: October 22, 1985 i

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ATTACHMENT TO LICENSE AMENDMENT NO.79 I

FACILITY OPEPATING LICENSE NO. DPR-6

! DOCKET N0. 50-155 -

Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised peces are identified

! by the captioned amendrent cur:ber and contain marginal lines indicating the area of change.

REMOVE INSERT 5-16a 5-16a 6-7 6-7 6-7a --

6-7b --

6-9 6-9 7-9 7-9 1 ,

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^!.3 Liquid Poison System The liquid poison system shall be available for operation at all time during refueling and power operation. The reactor shall be shutdcyn in any situation where the poison solution tank level drops below an equivalent of 850 gallons 19 weight percent sodium pentaborate or where the poison solution storage temperature drops to less than 5"F above saturation temperature. The maximum allow-able concentration shall be 30 weight percent of sodiun pentaborate.

The minimum worth of the licuid poison system (based on normal water level) shall be 25% a k f. Components of the system shall be checked at one to two montf5 (ntervals for proper creration except for actuation of the injection valves. The liquid poison ,

system shall be used at any time when subcriticality cannot be assured by the normal shutdown rechanism. Injection shall te continued until a minimum shutdown margin of 0.01Ak / keff 1s assured in the nost reactive core. The reactor shaif not be operated after poison has been infected until the baron concentration in the reactor water has been reduced to 100 ppn or less. Ona squib primer and trigger assembly from the equalizing line shall be rencved and test-fired at least every 18 months. These shall be tested on an alternate basis ensuring valve replacerent every 3E renths. One squib primer and trigger assenbly from the remaining five units shall be renoved and test-fired at least every 18 months.

These shall be tested en an alternate basis. In no case shall a squib prirer and trigger assembly remain in service lorger than five years. The tests shall consist of monitoring cf the input firing current and shearing of the integral inlet cap.

m 5-16a Amendment No. g , F , 79,

6.1.3 (Contd.) <

(c) With the mode switch in the " shutdown" position, both the I scram circuit and the control rod withdrawal circuit are open. The ventilating duct circuit power supply ^is transferred to a point which provides penetration closure protectinn through signals fron "high containment sphere pressure" and " low water level in reactor vessel." This permits rcretl ventilation in the containment sphere during shutdown when the control rods are held in the full-in position. None of the reactor safety system signals are bypassed since there is no need to vithdrew control rods.

4 (dl With the mode switch in the refuel position ard the crane 3 ,

positioned over the reactor vessel, crane operation is preverted if any one rod is withdrawn from full-in position.

i I (e) High condenser pressure reactor trip is automatically bypassed any time steam drun pressure is below a set point raximum of

, 500 psig.

6.1.4 Related Systems (a) Emergency Condenser Control I A pressure switch shall initiate automatic operation of the emergency condenser if the reactor pressure reaches 10010 psi above the reactor operating pressure.

I 6.1.5 Operatinn Renuirements (a) Except as otherwise provided in these Technical Specifications, the reactor safety system shall be operable during power J

operation as indicated in Section 6.1.2. This system shall be functionally tested during each major refueling shutdowr, but

! not less frequently than once every 18 months and in addition i

shall be tisted not less frequently then once a month using the I

switches provided to simulate sensor trips.

(b) The enercer.cy condenser system control initiation sensors shall l be functionally tested at each major refueling shutdown but ret less frequently than once every 18 months.

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6-7 Amendment No. JkI. }#',' 79, 8

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6.2 CONTROL R0D WITHDRAWAL PERMISSIVE SYSTEM 6.2.1 Interlocks Interlocks shall prevent control rod withdrawal when any cf the following conditions exist:

(a) When any two of the thirty-tuo scram accumulators are at pressure below 700 psig.

(b) When two of the three pcwer range channels read below 5 percent en their 0 to 125 percent scales (or below 2 Dercent on their 0-40 percent scales) when reactor power is above the minimum operating range of these channels. This interlock may be bypassed when all three of the power range channels are set on the r:infrum operable range.

(c) When the scram dump tank is bypassed.

(d) When the mode selector switch is in the shutdown j position.

6.2.2 Operating Pecuirements The control rod withdrawal permissive interlocks shall always be operable. No further withdrawal of control rods will be pemitted if or.e of these circuits is found to be I, inoperable.

Permissive circuits shall. pe functionally tested prior to each ra,for refueling but no less fre,quently than every 18 nonths. However, the refueling interlocks will be functionally tested prior to each refer refuelino. 7 6.3 REFUELING OPERATION INTERLOCK SYSTEM l

6.3.1 Reactor Pefueling System All of the trip devices not bypassed by the mode selector switch in the refuel position shall be operative during all refuelinc crerations. This shall include the sensors and trip devices of the reactor safety systen as specified for power operation as follows:

High Reactor Pressure Low Reactor Water Level Hich Containment Sphere Pressure High Scram Dump Tank Level loss of Auxiliary Power Supply High Neutron Flux Short Period l Manual Scran i

i 6-9 Amendment No. Jd',79

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7. 6, (Ccqtd)

System or Function Reference Procedure Frequency of Within These Undergoing Test Routine Tests Specifications Containment sphere access 6 months or less airlocks leakage rate -

Control rod performance At each major refueling Seetion 5.2.2 shutdown **

Liquid poison system Two months or less during Section 5.2.3 component operability power operation. One equalizing line squib and one remaining squib assembly test fired at least every

, 18 months.

Reactor safety system At each major refueling Section*6.1.5 scram circuits requiring shutdown

• plant shutdown to check Reactor safety system scram One month or less Section 6.1.5 circuits not requiring plant shutdown to check Containment sphere isola- At each major refueling Section 6.1.5 tion trip circuits shutdown

• Energency Condenser At each major refueling Section 6.1.5 Trip Circuits shutdown

• Centrol rod withdrawal'per- Prior to each major Section 6.2.2 missive interlocks function refueling shutdown

• Refueling operation At each major refueling controls function Section 6.3.3 shutdown j

Calibration and functional Per Table 13-2 Section 13.2 test of air ejector off-gas and stack-gas monitors

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Calibration of emergency One month or less condenser vent monitors Section 6.4.1 Calibration of process Per Table 13-2 liquid monitors Section 13.2

• But no less than once every 18 months

• • But no less than once every 20 months

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7-9 Amendment No. 49, 73, 77,79' 1

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