ML19325F225
| ML19325F225 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/31/1989 |
| From: | Elward T, Jeanne Johnston CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8911170095 | |
| Download: ML19325F225 (5) | |
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. Plant Manager M$M
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si9 Rock Point Nuclear Plant,10269 US 31 North, Charlevoix. MI 49720 November 2, 1989 i
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' Nuclear Regulatory Commission 1
Document Control Desk
. Washington, DC 20555 Dear Sir Enclosed pleare find the statistical data for the Big Rock Point Nuclear Plant covering the period of October 1,1989 through October 31, 1989, I
Sincerely, c
T'W Elward Plant Manager Eaclosures.
cc: Administrater Region III Nuclear Regulatory Commission DRHahn, Department of Public Health RCallen, Mit.higan Public Service Commission SHall, Michigan Department of Labor PDKrippner, American Nuclear Insurers
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INPO Record Center NRC Resident Inspector Document Control, Big Rock Point, 740/22*35*10 DPHoffman, P24-117B j
KWBerry, P24-614B File 8911170093 891031 PDR ADOCK 05000155 R
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MIO186-0667A-BT01 A CXf5 ENG7?GYCOMPANV
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NUCLEAR OPERATION DEPARTMDIT Unit Shutdowns and Power Reductions e *._
Report Month Docket Number Unit Date Completed by Telephone October, 1989 55-150 Big Rock Point Plant November 3, 1989 JRJohnston (616) 547-6537 ext 223 Methcd of Shutting Duration Down License Event Systgm C
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Number Date Type (Hours)
Reason Reactor Peport thnber Code Code Cause and Corrective Action to Prevent L u 1 w 89-10 10/09/89 F
0 hrs A
4 The plant load was reduced to allow the clearing -
thru of the turbine thrust bearing wear indicator alarm. Auxiliary gesauze sensing 10/12/89 instrumentation was installed to where " mills" of thrust bearing clearance can be correlated to hydraulic nozzle pressure.. It is thought that the wear indication is not a true reading since it is blown that the thrust bearing wear indication reference point was moved (or lost) when the number 1 bearing cap was recently retightened. We are closely monitoring the indicated wear instrumentation and carrying reduced plant load so that the annunciator is not "in".
89-11 10/21/89 F
0 hrs A
4 The plant load was reduced to allow repairs to the thru steam and water leaks on the turbine. It was successful in restricting or sealing 10/23/89 leaks on the HP casing. - The water leak is on the IP to LP crossover line and will require more planning to make repairs to it. The unit was returned to normal power-until plans are completed to make temporary repairs.
89-12 10/25/89 F
0 hrs A
4 The plant load was reduced to make temporary thru repairs to the expansion joint on the west side crossover pipe. The leak was found 10/27/89 to be split on the second (from the botton) serration in the north quadrant. After repairs are completed the plant will return to normal power.
89-13 10/27/89 F
100.2 A
1 While raising power following repairs to the turbine crossover piping, it was discovered that the turbine bypass valve would not open. The valve was isolated and troubleshooting is in progress. The control circuit and components have checked out okay and the problems appear to be in either the actuating cylinder or the valve itself. The unit will be returned to normal power after repairs are completed.
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" Exhibit G = Instructioris for F = Forced Reason:
Method:
S = Scheduled A = Equipment Failure (Explain) 1 = Mar.ual Preparation of Data Entry Sheets B = Maintenance of Test 2 = Manual Scram for Licensee Erent Report (LDt)
C = Refueling 3 = Automatic Scram File (NUREG-0161)
D = Regulatory Restriction 4 = Other (Explain)
E = operator Training and License Examination 5
F = Administrative Exhibit 1 = Same Source G = Operational Error (Explain)
H = Other (Explain)
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Refueling Information Request 1
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. Facility. names Big Rock Point Plant 2.
Scheduled date for next refueling shutdown -September, 1990 5
i 3.
Scheduled date for. restart following shutdown: October, 1990 W
4.
Will refueling or resumption of operation thereafter require a tecnnical 1
specification change or other license amendment?
No
- If yes, explaita t
ilf no, has the reload feel design and core configuration been reviewed by i
jc Plant Safety Review Committee to determine whether any unreviewed safety ~
questions as, associated with the cure reload (Reference 10 CFR, Section
.1 50.59)? No-f If no review has taken place, when is it scheduled?
Next outage 5.
Scheduled'date(s) for submittal of proposed licensing action and supporting information:
1 1
6.
Important licensing considerations associated with refueling, eg, new or L
different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design new operating l
l procedures:
.7.' Number of fuel assemblies in: core 84; spent fuel storage pool 254; new fuel storagc 0.
8.
Present licensed spent fuel storage capacity:
441 Size of any increase.in licensed storage capacity that has been requested or is 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:
1995 MIO886-0993A-BT01 BRP029 06/01/86 s
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