ML20036A316
| ML20036A316 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/30/1993 |
| From: | Donnelly P, Jeanne Johnston, Mort T CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9305110080 | |
| Download: ML20036A316 (6) | |
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Plant Manager POWERING nlKNIGAN'S PRDGRESS Big Rock Point Nuclear Plant.10269 US-31 North, Charlevoix, MI 49720 May 2, 1993' T
Nuclear Regulatory Commission I'
Document' Control Desk Washington, DC 20555
Dear Sir:
Enclosed please find the statistical data for the-Big Rock Point Nuclear Plant covering the period of April 1, 1993 through April 30, 1993.
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M P M Donnelly Plant Manager Enclosures cc Administrator Region--III, Nuclear Regulatory Commission DRHahn, Department of Public. Heath JRPadgett, Michigan Public Service Commission RAben, Michigan' Department.of' Labor MPCass,lAmerican Nuclear Insures FYost,'Research Services Utility Data Institute, INPO Records Center NRC Resident Inspector Document. Control, Big Rock Point, 740/22*35*10 DPHoffman, P24-ll7A-RJAlexander, Big Rock Point File 3
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FORM 16.3.H Operating Status Report - Nuclear Regulatory Commission Prepared by: bwes A
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Date: Meu 3. /9M Reviewed by:
a Date:
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(Reactor Engirteer or Alternate)
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Copy to be sent to the following by the seventh day of each month:
Nuclear Regulatory Commission Fred Yost Document Control Desk Director, Research Services Washington, DC 20555 Utility Data Institute 1700 K Street, N.W.
Administrator Suite 400 Region III - USNRC Washington, DC 20006 799 Roosevelt Road Glen Ellyn, IL 60137 DR llaim, NFEM Division of Radiological Health Department of Public Health 3500 North Logan Lansing, MI 48906 JR Padgett Michigan Public Service Commission PO Box 30221 Lansing, MI 48909 Institute of Nuclear Power Operations Plant Analysis Department 700 Galleria Parkway Atlanta, GA 30339-5957' Robert Aben, Assistant Chief Bureau of Construction Codes Michigan Department of Labor 7150 Harris Drive, Box.30015 Lansing, MI-48909 American Nuclear Insurers Att: MP Cass Town Cent.er, Suite 3008 29 South Main Street West Hartford, CT 06107-2445 Routing Copy:
DP Hoffman, P26-117A SM McIntyre, P13-121 JL Lampman, Big Rock Point Plant RC Joba - Big Rock Point Plant NRC Resident Inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference covrasurrr.not april as, asas 16.3.3 - 17
Power NUCLEAR OPERATIONS DEPARTMENT C0fRp3Ry Unit Shutdowns and Power Reductions
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Report Month Docket Number Unit Date Completed by Telephone April 1993 55-150 Big Rock 1% int Plant
!any 3, 1993 JR JORNSNM (626) 547-8223 Method of Shutting Duration Down Licensee Event System Compone..t 2
4 Number Date Type (Hours)
Reason Reactor Report Number Code Code 5 Cause and Corrective Action To Prevent Recurrence IWwer mas twduced to about 60 NifEg due a suspected C3-06 04/03/93 F
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4 Mrs failure of the turbine adelssion valve 97.
The decession has been nede to operate at thin lower vomwr level until Lhe up coming refueling outage that is plasswd for June 26, 1993.
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Exhibit G = Instructions for F = Forced Reason:
S = Scheduled A = Equipment Failure (Explain) 1 = Manual Preparation of Data Entry Sheets B = Maintenance of Test 2 = Manual Scram for Licensee Event Report (LER)
C = Refueling 3 = Automatic Scram File (NUREG-0161)
D = Regulatory Restriction 4 = Other (Explain)
E = Operator Training and License Examination 5Exhibit I = Same Source F = Administrative G P Operational Error (Explain!-
H = Other (Explain)
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Refueling Information Heauest 1.
Facility Name: Big Rock Point Plant 2.
Scheduled date for next refueling shutdown: June, 1993 3.
Scheduled date for restart following shutdown: August, 1993 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment? No If yes, explain:
?
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)? Yes If no review has taken place, when is it scheduled?
5.
Scheduled date(s) for submittal of proposed licensing action and supporting information:
i 6.
Important licensing considerations associated with refueling, eg. new or different fuel design or supplier, unreviewed design or performance -
l analysis methods, significant changes in fuel design new operating procedures:
r 7.
Number of fuel assemblies in: core 84 ; spent fuel pool storage 294; new fuel storage 22.
8.
Present licensed spent fuel pool storage capacity: 441 Size of any increase in licensed storage capacity that has been requested or planned (in number of fuel ' assemblies): 0
- 9. - projected date of last refueling that can be discharged to spent fuel pool.
assuming the present license capacity:
1996 EEFUELINC. DOS Hay 3, 1993 6
64_
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