ML20138G202

Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6

ML20138G202
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/30/1997
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML20138G190	List: ML20138G186 ML20138G196 ML20138G202
References
NUDOCS 9705060214
Download: ML20138G202 (4)

Text

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ATTACMENT 2 CONSUNERS ENERGY CONPANY BIG ROCK P0 INT PLANT DOCKET 50-155 CURRENT FACILITY OPERATING LICENSE MARKED UP TO ILLUSTRATE CHANGE Submitted April 30, 1997 l

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I 9705060214 970430 3 Pages PDR ADOCK 05000155 P PDR .

NUCLEAR REGULATORY CONIISSION

- WASHINGTON, DC 20555 EacM4 CONSUMERS +0WEA-COMPANY DOCKET NO 50-155 BIG ROCK POINT PLANT FACILITY OPERATING LICENSE License No DPR-6 A. This license applies to the Big Rock Point Plant, a boiling water reactor and associated equipment (the facility), owned by the Consumers fewerENtag

' Com>any (the licensee). The facility is located in Charlevoix County, Miciigan, and is described in the licensee's application dated January 14, 1960, and the Final Hazards Summary Report; as supplemented and amended by subsequent filings by the licensee.

B. Subject to the conditions and requirements incorporated herein, the Consission hereby licenses Consumers fewer Company:

fat.41 (1) Pursuant to Section 104b of the Act and 10 CFR Part 50, ' Licensing of Production and Utilization Facilities" to possess, use and operate the facility at the designated location in Charlevoix County, Michigan, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, "Special Nu' clear Material,"

toreceive, possess,anduseatanyonetimeupto(a)2500 kilograms of contained uranium 235 as fuel, (b) 10.32 grams of uranium 235 as 150* kilograms of plutonium contained contained ininPu0 fission

-UO counters, (c) d (d) 5 curies of plutonium fuel rods, an encapsulated as $ p1Intonium-beryllium neutron source, all in connection with operation of the facility, subject to the following conditions:

(a) A technical specification will be instituted to assure that the plant will not operate if the capacity of the makeup line to remove heat from the spent fuel pool is insufficient for the heat generating capacity of the pool inven. tory, considering the power history of each assembly in the pool, the number of assemblies in the pool and the effect of lake temperature on the heat-removal capacity of the makeup water system.

Cecsmcas &c46y CarPwv

• Note: (For internal GP-Go clarification.) AmendmentNo4 dated 12/6/72 established that CP Co could have 150 Kg of Pu in mixed-oxide fuel bundles. However, this was limited to 50 Kg until the GESMO question was finalized. Reference 10/13/75 letter and NRC order dated 8/11/75.

Amendment 107 February 19, 1992 LICENSE.JLL

f 7.0 OPERATING PROCEDURES This section describes those basic operating principles and procedural  !

safeguards which have a potential effect on safety. Operating l

principles and procedures are presented for normal and emergency '

operation of the plant, for Phase II testing within the Research and  !

Development Program, and for operational testing of the nuclear '

i safeguards systems of the plant.

l (Section 7.1 through 7.2.3 deleted by Amendment No. 9 dated 12/19/751 / )

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7.2.4 Administrative and Procedural Controls Relatina to Hiah Performance Fuel l i

In addition to normal operating procedures, the following additional l precautions shall be observed during irradiation of the centermelt fuel l assemblies: 1 1

(a) In tha event of suspected coolant system leaks, reactor power will i be immediately reduced to permit entry for inspection purposes and '

an evaluation of the suspected leak will be made. If the evaluation reveals leakage in the primary cooling system, the reactor shall be shut down immediately, except when it has been established that the leaks are in valves, packing or pumps where some leakage can be tolerated.

(b) The Plant Manager or his designated alternate shall be /

notified immediately of all reactor scrams and shall approve subsequent start-ups. Start-up of the reactor following a scram shall not proceed until the cause of the scram has been determined j and the necessary corrective action taken. The evaluation and '

approval of the Consumers Company General Office shall be required for all start-ups fo ing and unexplained scram.

(c) Technical Specialists On-Site: Ed'*f (1) The General Electric Company shall have a physicist familiar with the Big Rock Point Plant present at the facility for each initial start-up following refueling. He shall be present during the initial approach to criticality  ;

and shall remain until at least 10% of rated power is l reached. ,

mu41 i (2) Consumers fewer Company shall have a Reactor Engineer or his designated alternate who shall be a licensed senior operator in the control room for all start-ups, special tests or significant power changes. ,

7.3 NORMAL OPERATION  ;

7.3.1 General I Detailed operating procedures for each normal mode of plant operation shall be prepared prior to operation. i 61 i Amendment 107 February 19, 1992 i TS7.JLL

[ADMINISTRATIVECONTROLS

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' 6.5.2.4.2 (Continued)

1. The Process Control Program and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months.

1 Audit reports encompassed by 6.5.2.4.2 above shall be l forwarded to the Director, NPAD, and management positions / l responsible for the areas audited within thirty (30) days after completion of the audit. j 6.5.2.4.3 NPAD review of the subjects in Faecifications 6.5.2.4.1 and / l 6.5.2.4.2 shall be performed by in assigned Nuclear Performance / l Specialist selected on the basis of technical expertise / ;

relative to the subject on the basis of technical expertise / l being reviewed. If the assigned Nuclear Performance / l Specialist determines the need for interdisciplinary review, a /

committee consisting of the Director, NPAD, or his designate, /

, and at least four Nuclear Performance Specialists, shall be /

assigned. Such committee shall meet as conditions requiring / 1 interdisciplinary review arise, but no less than twice yearly. / l AUTHORITY  !

1 6.5.2.5 The NPAD shall report to and advise the Vice President - Nuclear / I 3 Operations of significant findings associated with those areas of '

responsibility specified in Section 6.5.2.4.1 and Section 6.5.2.4.2.

RECORDS '

a 6.5.2.6 Records of NPAD activities shall be maintained. Reports shall / ;

be prepared and distributed as indicated below: '

a. The results of reviews performed pursuant to Section 6.5.2.4.1 and Section 6.5.2.4.2 shall be reported to the ,

Vice President - Nuclear Operations at least monthly.

I b. A report assessing the overall nuclear safety performance of the Big Rock Point Plant shall be provided to senior Consumers Power-Company management annually.

C4.56Y SJ (Deleted)

6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a safety limit is i

violated:

a. The reactor shall be shut down immediately and not restarted until the Commission authorizes resumption of operation (10 CFR 50.36(c)(1)(1)(A)).

80 Amendment 109 May 24, 1993