ML20043D626

Monthly Operating Rept for May 1990 for Big Rock Point Nuclear Plant

ML20043D626
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	05/31/1990
From:	Beckman W, Jeanne Johnston CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9006080321
Download: ML20043D626 (5)

Text

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.,a Consumers Power wiiiiam t sockman Iknt blanager MEM ARENBEAAr5 N Big Rock Point Nuclear Plant,10269 Ut 31 North, Charlevoix, MI 49720 i

June 1, 1990 Nuclear Regulatory Commission 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 May 1, 1990 through May 31, 1990, j

Sincerely, cffW W.L Beckman Plant Manager Enclosures cc: Administrator Region III, Nuclear Regulatory Commission DRHahn, Department of Public Health RCallen, Michigan Public Service Commission SHall. Michigan Department of Labor PDKrippner, American Nuclear Insurers

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INPO Record Center NRC Resident Inspector l'

Document Control, Big Rock Point, 740/22*35*10 DPHoffman, P24-117B KWBerry, P24-614B l

File i

9006080321,[fhhbkS6 DR ADOCF PDC

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MIO186-0667A-BT01 A CMS GV67?GYCOMPANY

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- - S power NUCLEAR OPERATIONS DEPARTMENT -

Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Telephone May 1990 55-150 Big Rock Point Plant June 1, 1990 JRJohnston (616) 5h7-6537 x223 Method of Shutting Duration Down t.icensee Event System Component l

3 4

Number Date Type 04ours)

Reason Reactor Report Number Code Code 5 Cause and Corrective Action To Prevent Recurrence

-- NONE I

2 3

4 F = Forced Reason:

Method:

Exhibit G = Instructions for S = Scheduled A = Equipment Failure (Explain) 1 = Manual Preparation'of Data Entry Sheets B = Maintenance of Test 2 = Manual Scram for Li nsee Event Report (LER)

C = Refueling 3 = Automatic Scram File (NUREG-0161)

' D = Regulatory Restriction 4 = Other (Explain)

E = Operator Training and License Examination SExhibit I = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3156 1-82

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y GREYBOOK OPERATING DATA REPORT

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" DOCKET NO. 50-155 DATE:

6/ 1 / 90

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'l OPEP,ATING STATUS-PHONE:

616-547-6537sEXT 223

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1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT' NOTES:

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% REPM T22:G_PERICO ?

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1. 96

3. LICENSED THERNL POWER (MWT):

240

4. NAMEPLATE RATING (GROSS MUE):

75

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6. MAXI!*JN DEPENDABLE CAPACITY :(GROSS MWE) :

71.0

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7. MAXIMUM DEPENDn8LE CAPACITY ~(NET MWE):

67.0 0

ct - IF_ff aur,rc ner.t te rapney w nnTvwecrvTr*.e 7 Tynts we e v*+er e ne_T p rocrtT. r,TVE_ REASONS 2 s

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9. POWER LEVEL TO WHICH RESTRICTED,IF ANY (NET MWE):

yO_ REASONS FOR_ RESTRICTIONS 4_.lF_t.NV-

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THIS MONTH YEAR-TO-DATE CU*tULATIVE O

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11. HOURS IN REPORTING PERIOD 744.0 3623.0 233218.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 744.0 3623.0 172772.6 O

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nrceTnure:c Pac-cwmnutwv acic 0.0 0.0 D.0

"_ 14. HOURS GENERATOR ON-LINE 744.0 3623.0 169912.0

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 0

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nROSS IHERta^' FNERG't_GENERATrn mew 1 A tA79y no76co,n

__._ m 71060.0

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 52250.0 257624.0 1027S272.0

18. NET ELECTRICAL ENERGY GENERATED (MWH) 49647.3 244838.3-9719271.9 O

19._ifMIT C.FPNTrF FACIOP 900.CY 100.0%

71.3Y

", 20. UNIT AVAIt '.BILITY FACTOR 100 0%

100.0%

71.3%

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21. UNIT CAPACITY FACTOR (USING MDC l','ET) 99.6%

100.9%

60.6%

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23. UNIT FORCED OUTAGE RATE 0.0%

0.0%

12.2%

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"1 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE,DATE, & Ed) RATION OF EACH) :

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25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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' AVERAGE ~- DAILY POWER (MWT)?:

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l-Refuelina Information Request e

'l 1.

Facility names Big Rock Point Plant 2,

Scheduled date for next refueling shutdown: September, 1990 1

3.

Scheduled date for restart following shutdown: October 1990 t

4.

Will refueling or resumption of operation thereafter require a technical n

specification change or other '.?nse amendment?

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

l If no review has taken place, when is it scheduled?

Next outage L

i 5.

scheduled date(s) for submittal of proposed licensing action and l

supporting information 6.

Important licensing considerations associated with refueling, eg new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design new operating procedures

.]

1 L

l 7.

Number of fuel assemblies int core 84; spent fuel storage pool 254; nev l

fuel storage 0.

8.

Present licensed spent fuel storage capacity:

441 i

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

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