ML20210P165

Amend 84 to License DPR-6,adding Condition to CRD Surveillance Testing Requiring Testing Prior to Startup Following Outages of More than 120 Days

ML20210P165
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/06/1986
From:	Zwolinski J Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210P163	List: ML20210P158 ML20210P165 ML20210P176
References
NUDOCS 8605130105
Download: ML20210P165 (5)

Text

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'..-p ahog#o UNITED STATES

~g 8 n NUCLEAR REGULATORY COMMISSION  ;

WASHINGTON, D. C. 20555 G j

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' 5 CONSUMERS POWER COMPANY -

DOCKET NO. 50-155 l

BIG ROCK POINT PLANT AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 .,

License No. DPR-6 '

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1. The Nuclear Regulatory Comission (the Comission) has found that: ,  ;

A. The application for amendment by Consumers Power Company i (the licensee) dated April 15, 1985, complies with the standards and requirements 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 confomity with the application, the provisions of the Act, and the rules and regulations of  !

the Comission; ,

C. There is reasonable assurance (1) that the activities i authorized by this amendment can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compli- l ance with the Comission's regulations; D. The issuance of this amendment will not be inimical to ,

the common 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 requirements have been satisfied.

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t 2. Accordingly, the license is amended by changes to the Technical  !

i Specifications as indicated in the attachment to this license

- amendment and Paragraphs 2.C.(2) of Facility Operating License .

No. DPR-6 are hereby amended to read as follows:

I (2) Technical Specifications

, The Technical Specifications contained in Appendix A

as revised through Amendment No. 84, are hereby ,

incorporated in +,he license. The licensee shall _

operate the facility in accordance with the Technical i

Specifications. '

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

FOR T E NUCLEAR RECOLATCRY COMMISSION

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John . Zwolinski, Director

, BWR roject Directorate #1 Division of BWR Licensing

Attachment:

Changes to the Technical Specifications Date of Issuance: May 6, 1986.

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ATTACHMENT TO LICENSE AMENDMENT NO. 84 FACILITY OPERATING LICENSE NO. DPR-6 ,

DOCKET NO. 50-155 Revise Appendix A Technical Specifications by removino the pages identified below and inserting the attached pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.

REMOVE INSERT 5-13 5-13 ~

7-9 7-9 i

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5.2.2 Control Rod System j (a) Control Rod Performance j The following limits shall apply to any control rod which can 1 be withdrawn. It shall be permissible to tag and valve out the ,,

hydraulic drive water to a fully inserted control rod which is defective or does not meet these limits provided the remaining rods do meet the limits. l The following tests shall be performed at each ma.ior refueling but not less often than once every 20 months, and prior to startup following any outage greater than 120 days in length. ,

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(i) Withdrawal of each drive, stopping at each locking pos'ition to check latching and unlatching operations ,

and the functioning of the position indication system. (

(11) Scram of each drive from full withdrawn position.

Maximum scram time from system trip to 90 percent of i insertion shall not exceed 2.5 seconds. r f

(111) Insertion of each drive over its entire stroke with reduced hydraulic system pressure to determine that  ;

drive friction is normal.  !

t (iv) Continuous withdrawal and insertion of each drive over its stroke with normal hydraulic system pressure. '

Minimum withdraw time shall be 23 seconds. ,

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5-13 Amendment No. 11, fe, 13, 84 '

7.6 (Contd)

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

Control rod performance At each major refueling Section 5.2.2

! shutdown ** and prior to startup following any out- ~

age greater than 120 days.

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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 4 circuits not requiring

, plant shutdown to check Containment sphere isolation At each major refueling Section 6.1.5 trip circuits shutdown

• Emergency condenser trip At each major refueling Section 6.1.5 circuits shutdown

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

• Refueling operation At each major refueling Section 6.3.3 controls function shutdown Calibration and functional Per Table 13-2 Section 13.2 test of air ejector off-gas and stack-gas monitors Calibration of emergency One month or less- Section 6.4.1 condenser vent monitors Calibration of process Per Table 13-2 Section 13.2 liquid monitors

• But no less than once every 18 months

• • But not less often than once every 20 months l 7-9 Amendment No. 77, 79, 84

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