ML20137P039

Monthly Operating Rept for Mar 1997 for Big Rock Point Nuclear Plant

ML20137P039
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/31/1997
From:	Jeanne Johnston, Shields K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9704090122
Download: ML20137P039 (6)

Text

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Consumers

. _ Power POWER &NG 4 . M N N5 Peassaat April 1,1997 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 March 1,1997 through March 31,1997, d

1

. Sincerely, L L K J Shields Reactor Engineer f G ,

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Enclosures ,

cc: Administrator Region lit, Nuclear Regulatory Commission DRHahn, Department of Enviromental Quality JRPadgett, Michigan Public Service Commission RAben, Michigan Department of Labor \

MPCass, American NuclearInsures FYost, Research Services Utility Data institute gi

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RAFenech, Palisades SMMcIntyre, P26-204 KP Powers, Big Rock Point GCWithrow, Big Rock Point NRC Resident inspector, Big Rock Point Document Control, Big Rock Point,740*22*35*10 File hD DO 0500 55 l5,ElES%,EEJE j R PDR ;  ;

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J' CMS 6VERGYCOMPANY

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l i . FORM 16.3.H l

, . Operating Status Report - Nuclear Regulatory Commission

, Prepared by: AM/E V

- NE Date: /

(,/

Reviewed by: h & Date: b !/M1 (Reactor En@ineer or Alternate)

!' Copy to be sent to the following by the seventh day of each month:

' Nuclear Regulatory Commission Robert Aben, Assistant Chief 4

Document Control Desk Bureau of Construction Codes Washington, DC 20555 Michigan Department of Labor 7150 Harris Drive, Box 30015 i Lansing, MI 48909 l Administrator American Nuclearinsurers >

Region lli- USNRC Att: MP Cass 801 Warrenville Road - Town Center, Suite 3008 i Lisle,IL 60532 4351 29 South Main Street West Haitford, CT 06107-2445 DR Hahn Fred Yost Department of Enviromental Quality Director, Research Services 3500 North Logan Utility Data institute Lansing, MI 48906 1700 K Street, N.W.

Suite 400 Washington,DC 20006 JR Padgett Michigan Public Service Commission PO Box 30221 i' Lansing,MI 48909 d

Routing Copy:

RA Fenech, Palisades Plant SM McIntyre, P26-204 KP Powers, Big Rock Point Plant l

CC Withrow, Big Roci; Point Plant NRC Resident inspector, Dig Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference I

16.3.3 -17

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NUCLEAR OPERATIONS DEPARTMENT

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Unit Shutdown and Power Reductions Docket Number Unft Date Completed by Tetophone .

Report Month '

March,1987 56-150 Big Rock Point Plant Apr51,1997 JR Johnston ($16) 547 8223 Method of Shestling Type i Duration Reason 2

Down Reactor3 Licensee Event Report Number Sq Code gCode c==== md Corrective W To Prevent Recurrence Number ~ Date (Hours) 9741 8342/97 F 897.5 Hrs A 1. 2 On 0342/96 at 22:32; The unit was rernoved from service to  ;

i Thru investigate and repe'sIsakage stem MO.7871 andfor VPI-303 on 03f31/97 the poet ipe=4=est system. After the unit was vernoved frown service, the reacter was manually scrammed to fully insert the remseneng withdrawn control rod drives. After repairs are complete, the unit will return to normal service.

(Total outage hours: 897.5)

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i 1 2 M dhod: kxhibit G = hstructions b F = Forced Reason:

S = Scheduled A = Equepment Failure (Explain) 1 = Manual Preparabon 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 = Regulatory Restriction 5 Exhibit 1 = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3156 247

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- I ESTATS VERSION 97.001; EA-B-STATS-97-01-- 02/06/97 .RU:" TIME =04/01/97 13:15:39 Page 4 cf S .

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.'GREYBOOK OPERATING DATA REPORT ,

--DOCKET NO. 50-155 .DATE: 4 /-'l / 97: '.

BY: 'JR JOHNSTON

. OPERATING STATUS PHONE: 616-547-8223

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

= 2. REPORTING PERIOD: 3 / 97

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

11. HOURS IN REPORTING PERIOD 744.0 2160.0 298123.0 12; NUMBER OF HOURS REACTOR WAS CRITICAL 46.5 697.5 ~ 216401.1

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14.' HOURS GENERATOR ON-LINE 46.5 681.0 213058.2 15.' UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 9500.0 132756.0 41307017.0

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 3016.0 42718.0 13128387.0

18. NET ELECTRICAL ENERGY GENERATED (MWH) 2854.4 40399.5 12421660.8

'19. UNIT SERVICE FACTOR 6.3% 31.5% 71.5%

20. UNIT AVAILABILITY FACTOR 6.3% 31.5% 71.5%

21. UNIT CAPACITY FACTOR (USING MDC NET) 5.7% 27.9% 61.9% :

22. UNIT CAPACITY FACTOR (USING DER NET) 5.3% - 26.0% 57.9%

23. UNIT FORCED OUTAGE RATE 93.8% 68.5% 11.7%

24. SHUTDOWNS SCHEf)ULED OVER NEXT 6 MONTHS (TYPE. DATE. & DURATION OF EACH): Refueling, August 31, 1997, 60 days.

e 25,. IF SHUT DOWN AT END OF REPORT PERIOD ESTIMATED DATE OF STARTUP: April 5, 1997.

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Refuelina information Reauest

1. Facility Name:

Big Rock Point Plant

2. Scheduled date for next refueling shutdown:

August,1997.

3. Scheduled date for restart following shutdown:

60 Day Duration.

4. Will refueling or resumption of operation thereafter 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 ast.ociated with the core reload (Reference 10 CFR, Section 50.50) ?

To be performed once esse ioading determined for cycle 30.

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

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

N/A.

6. Important licensing considerations associated with refueling, eg. new or 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 in

1 Core = 84, i

, Spent Fuel Pool Storage = 358.

New Fuel Storage = 22.

8. Present licensed spent fuel pool storage captcity:

l 441 )

Size of any increase in licensed storage capacity that has been requested or planned (in number of fuelassemblies):

0 4

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.

4 ' AprH 1.1997