ML20212P887

Monthly Operating Rept for Dec 1986

ML20212P887
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/31/1986
From:	Hice D, Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8703160311
Download: ML20212P887 (5)

Text

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PWwer g NUCLEAR OPERATIONS DEPARTMENT Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date . Completed by Telephone December 1986 50155 Big Rock Point January 2, 1981 Don Hice 616-547 6537 ex 225 Method of Shutting Duration Down Licenese Event System Comporwnt Number Date Type I (Hours) Reason Reactor Report Number Code 4 Codo5 h W hk MW To h h 86-07 12/22/86 F* 7 A 4 None Derate - Power was reduced to allow investigation of a gradual increase in primary system unidentified leakage.

Some of the leakage was identified and I

quantified resulting in a reduction of l unidentified leak rate. The unit returned to full power (Coastdown)

12/23/86. No leakage limits were exceeded.

@ rrection:" Please note the following corrections to previcus Unit Stutdowns and Power Reduction reports.

Re port Number Correction 86-06 " Tyre" should be F" 86-05 " Type" should be F" 86-04 " Tyre" should be F" s

I 2 Reason: 3Method: 4 F = Forced Exhibit G = Instructions for S = Scheduled A = Equipment Failure (Explain) 1 - Manual Properation of Data Entry Sheets B = Maintenance of Test 2 - Manual Scram for Licensee Event Report (LER) y3 C = Refueling 3 - Automatic Scram File (NUREG-0161) 4 pi ' D = Regulatory Restriction 4 - Other (Explain) 7 E = Operator Training and License Examination S F = Administrative Exhibit I = Same Source G = Operational Error (Explain) i H = Other (Explain) 8703160311 861231 r ,are i.n2 PDR ADOCK 05000155 R PDR

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Refueling Information Request i

1. Facility name: Big Rock Point Plant

2. Scheduled date for next refueling shutdown: January 2, 1987

3. Scheduled date for restart following shutdown: February 20, 1987

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? Yes If yes, explain: New hybrid control rods containing hafnium and high purity stainless steel will require a change to the description in the Technical Specifications. A Technical Specification Change Request has been prepared and submitted.

If no, has the reload fuel design and core configuration been reviewed by Plant Safety Review Committee to determine whether any unreviewed safety questions as associated with the core reload (Reference 10 CFR, Section 50.59)?

If na review has taken place, when is it scheduled?

5. Scheduled date(s) for submittal of proposed licensing action and supporting information: Submitted l

6. Important licensing considerations associated with refueling, eg, new or different fuel design or supplier, unreviewed design or performance j analysis methods, significant changes in fuel design new operating procedures: None

7. Number of fuel assemblies in: core 84; spent fuel storage pool 192.

8. Present licensed spent fuel storage capacity: 441 Size of any increase in licensed storage capacity that hau b . eequested or is planned (in number of fuel assemblies):

'rojected date of last refueling that can be dischr.n ac nient -tel pool asuming the present license capacity: 1995

':'r u d-0993-BT01 f -----_____ _ _

i j

i Consumers Power o-Company a-~' l Sig Rock Point Nsclear Plant, som 591, Route 3, Charleroix, MI 40720 January 2, 1987 Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period December 1,1986 through December 31, 1986, Sincerely.

.[ '

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< D P Hoffman OB101T" g 2 J/

Plant Superintendent N310'JkW g/

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1 CertNpsr//

1 Enclosures cc: DEVanFarowe, Department of Public Health I RCallen, Michigan Public Service Commission Michigan Department of Labor INPO Record Center j

Resident NRC Inspector, Site Document Control, Big Rock Point, 740*22433*10 FWBuckman, P24-117B KWBerry, P24-614B File d

f' (v n P*.010-0667A-BT01

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