ML20135E510

Monthly Operating Rept for Nov 1996 for Big Rock Point Nuclear Plant

ML20135E510
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	11/30/1996
From:	Donnelly P, Jeanne Johnston CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9612110325
Download: ML20135E510 (5)

Text

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Power Patrick M Donnetty Plant Manager POWERING nlKNNEAN5 PROGRESS Big Rock Point Nuclear Plant,10269 US-31 North. Charlevois MI 49720 1

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December 2, 1996 Nuclear Regulatory Commission Document Control Desk washington, DC 20555 Dear Sirs Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period of November 1, 1996 through November 30, 1996.

Sincerely, e,

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P M Donnelly

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Plant Manager Enclosures cc: Administrator Region III, Nuclear Regulatory Commission DRHahn, Department of Public Seath JRPadgett, Michigan Public Service Commission RAben, Michigan Department of Labor MPCass, American Nuclear Insures FYost, Research Services Utility Data Institute j

GLBayes, General Electric Company f

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i RAFenech, Palisades GCWithrow, Big Rock Point

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f NRC Resident Inspector, Big Rock Point Document Control, Big Rock Point, 740/22*35*10 File fr

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t 9612110325 961130 PDR ADOCK 05000155 R

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NUCLEAR OPERATIONS DEPARTMENT Company Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Telephone November. 1996 55-150 Big Rock Point Plant December 2,1996 A Johnston (616) 547-8223 Method of Snutting Duration Down Licensee Event System Component Number Date Type' (Hours)

Reason Reactor Report Number Code Code 5 4

Cause and Corrective Action To Prevent Recurrence 96-06 10/23/96 F

60.8 Hrs H

4 On 10/23/96 at 17:17; The unit was rancved from thru service before manually scransning the reactor to 11/03/96 fully insert the resnaining withdrawn control rod drives (planned). The Electrical Equipment Qualifications (EEQ) concerns was the reason for the outage. After resolving the EEQ concerns the unit was returned to service on 11/03/96 at 12:48.

(Total hours out of service was 260.5)

I 2

3 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 Licensee 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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1 STATS VERSION 94.001; EA-B-STATS-94-02 12/30/94 RUNTIME=12/02/96 11:54:36 Pcge 4 of 9 GREYB00K OPERATING DATA REPORT DOCKET NO. 50-155 DATE: 12 / 2 / 96 l

BY: JR JOHNSTGN OPERATING STATUS PHONE: 616-547-8223

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

2. REPORTING PERIOD:

11 / 96 i

3. LICENSED THERMAL POWER (MWT):

240

~

4. NAMEPLATE RATING (GROSS MWE):

75

5. DESIGN ELECTRICAL RATING (NET MWE):

72

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE):

71.0

7. MAXIMUM DEPENDABLE CAPACITY (NET MWE):

67.0

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS:

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

10. REASONS FOR RESTRICTIONS. IF ANY:

+

THIS MONTH YEAR-TO-DATE CUMULATIVE

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11. HOURS IN REPORTING PERIOD 720.0 8040.0 295219.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 67S.4 5490.7 215526.7

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

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14. HOURS GENERATOR ON-LINE 659.2 5417.5 212221.0 l

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 t

16. GROSS THERMAL ENERGY GENERATED (MWH) 146236.0 1179355.0 41138426.0

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17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 46119.0 373452.0 13074434.0

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18. NET ELECTRICAL ENERGY GENERATED (MWH) 43845.8 354658.5 12370596.5 t

19. UNIT SERVICE FACTOR 91.6%

67.4%

71.9%

20. UNIT AVAILABILITY FACTOR 91.6%

67.4%

71.9%

21. UNIT CAPACITY FACTOR (USING MDC NET) 90.9%

65.8%

62.3%

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22. UNIT CAPACITY FACTOR (USING DER NET) 84.6%

61.3%

58.2%

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23. UNIT FORCED OUTAGE RATE 8.4%

7.2%

10.6%

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. & DURATION OF.EACH): Refueling. April, 1997. 60 Days.

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

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1 STATS VERSION 94.001; EA-B-STATS-94-02 12/30/94 RUNTIME=12/02/9S 11:54:36 Page 2 of 9 DAY AVERAGE DAILY POWER (MWT)

(RWEN)

(11/96) - CYCLE 29 e, -

1 0.00 0.00 2

0.00 0.00 3

28.04 5.18 4

168.38 50.20 5

219.38 65.92 6

228.13 68.52 7

228.92 68.71 8

228.75 68.88 9

228.92 68.71 10 227.29 68.46 11 226.88 67.95 12 226.13 67.99 13 227.58 68.28 14 229.46 68.80 15 228.29 68.75 16 227.50 68.21 17 227.92 68.66 18 226.92 68.35 19 227.79 68.43 20 228.00 68.35 21 227.29 68.38 22 226.88 68.20 23 228.83 68.70 24 226.54 68.29 25 225.88 67.87 26 225.71 67.54 27 222.33 67.00 28 226.33 67.67 29 224.67 67.47 30 224.46 67.41 t

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j R*fuelina Information Recuest I

1.

Facility Names Big Rock Point Plant i

2.. Scheduled date for next refueling shutdown: April, 1997.

j 3.

scheduled date for restart following shutdowns 60 Day Duration.

1 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No i

1 If yes, explain 4

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If no, has the reload fuel design and core configuration been reviewed by Plant safety Review Committee to determine whether any unreviewed safety "1

questions as associated with the core reload (Reference 10 CFR, Section 50.59)? To be performed once core loading determined for cycle 30.

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If no review has taken place, when is it reheduled?

5.

Scheduled date(s) for submittal of proposed licensing action and supporting 1

information: N/A e

6.

Important licensing considerations associated with refueling, eg. new or I

different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design new operating procedures None 7.

Number of fuel assemblies ins core 84; spent fuel pool storage 358; new 1

fuel storage O.

1 8.

Present licensed spent fuel pool storage capacity:

441 i

size of any increase in licensed storage capacity that has been requested j

j or planned (in number of fuel assemblies):

0 i

i 9.

Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity: Last total core off load 1996; Last refueling 1999.

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f December 2.1996 ll l

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