ML20128F982

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

ML20128F982
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	09/30/1996
From:	Donnelly P, Johnston Jr CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9610080301
Download: ML20128F982 (6)

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! Consumers Power e.irick u oonn.nv Plant Manager POWERING hiKNNEAN'S PROGRESS Beg Rock Point Nuclear Plant.10269 US 31 North. Charlevoem, MI 49720 October 1, 1996 Nuclear Regulatory Commission Document control Desk washington, DC 20555 i

Dear Sirs Enclosed please find the statistical data for the Big Rock Point Nuclear Plant

! covering the period of September 1, 1996 through September 30, 1996, 1

i sincerely, i

/n

/ -

i P M Donnelly Plant Manager 1

i Enclosures cca Administrator Region III, Nuclear Regulatory Commission DRHahn, Department of Public Beath i l

JRPadgett, Michigan Public Service Commission RAben, Michigan Department of Labor MPCass, American Nuclear Insures '

l FYost, Research Services Utility Data Institute GLHayes, General Electric Company RAFenech, Palisades GCWithrow, Big Rock Point NRC Resident Inspector, Big Rock Point Document control, Big Rock Point, 740/22*35*10 File Q l 9610080301 960930 PDR ADOCK 05000155 R PDR A C%G F.NERGYCOMB4NY

CORSUNitf5 Power NUCLEAR OPERATIONS DEPARTMENT C05% Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Telephone September, 1996 55-150 Big Rock Point Plant October 1, 1996 JR Johnston (616) 547-8223 Method of Shutting Duration Down Licensee Event System Component Number Date Type (Hours) Reason Reactor Report Number Code 4 Mb Cause and Corrective Action To Prevent Recurrence 96-03 09/10/96 F 115.9 Hrs A 4 -----

On 09/10/96 at 10:45: The unit was removed frtan t* service due to a packing leak on CV-4183 (Reactor 09/L % Depressurization Systen). After the unit was taken off-line, the reactor was manually scramed to fully insert the remaining withdrawn rods. The unit was returned to service on 09/15/96 at 06:38 hrs after repairs were coupleted.

96-04 09/16/96 F 44.3 Hrs A 3 On 09/16/96 at 02:51; The reactor scrammed on high thru pressure when the turbine generator inital pressure 09/17/96 regulator (IPR) bellows failed. The unit was returned to service after the replaanent of the IPR bellows on 09/17/96 at 23:09.

I F = Forced 2 3 Method: 4 Reason: 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 5 Exhibit I = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3156 1-82

1 STATS VERSION 94.001; EA-D-STATS-94-02 12/30/94 RUNTIr2=10/01/96 11:04:44 Page 4 of 9 GREYBOOK OPERATING DATA REPORT ,

DOCKET NO. 50-155 DATE: 10 / 1 / 96 BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223

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

2. REPORTING PERIOD: 9 / 96

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.t.

8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) $1NCE LAST REPORT, GIVE REASONS:

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

10. REASONS FOR RESTRICTIONS, IF ANY:

THIS MONTH YEAR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 720.0 6575.0 293754.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL $77.2 4270.0 214306.0

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 559.9 4213.0 211016.5

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 117808.0 912039.0 40871110.0

17. GROSS ELECTRICAL EhERGY GENERATED (%'H) 36974.0 288992.0 12989974.0

18. NET ELECTRICAL ENERGY GENERATED (MWH) 34988.1 274436.1 12290374.1

19. UNIT SERVICE FACTOR 77.8% 64.1% 71.8%

20. UNIT AVAILABILITY FACTOR 77.8% 64.1% 71.8%

21. UNIT CAPACITY FACTOR (USING MDC NET) 72.5% 62.3% 62.2%

22. UNIT CAPACITY FACTOR (USING DER NET) 67.5% 58.0% 58.1%

23. UNIT FORCED OUTAGE RATE 22.2% 3.7% 10.5%

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE.DATE. & DURATION OF EACH):

25. IF SHUT 00VN AT END OF REPORT PERIOD, ESTIMATED DATE OF START UP:

1 STATS VERSION 94.001: EA-B-STATS-94-02 12/30/94 RUNTIME=10/01/93 11:04:44 Pege 2 of 3 OAY AVERAGE OAILY PDWER(MWT) (MWEN) ( 9/96) - CYCLE 29 .

I 225.00 67.10 =

2 224.00 66.93 3 223.08 66.51 '

4 223.67 66.55 5 226.17 67.30 6 225.38 67.09 7 228.92 68.11 8 226.00 67.63 9 226.17 67.29 10 64.33 18.07 11 0.00 0.00 12 0.00 0.00 13 0.00 0.00 14 1.88 0.00 15 58.71 14.66 16 17.33 3.41 17 4.13 0.00 18 67.46 17.68 j

19 173.63 52.40 20 221.67 66.01 21 226.13 67.82 22 227.83 68.40 i 23 227.50 68.28 24 229.08 68.36 25 227.63 68.06 26 227.58 68.17 27 227.50 68.20 28 226.50 67.89 29 225.29 67.92 30 226.13 67.95 i

Refuelina Information Recuest j 1

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1. Facility Names Big Rock Point Plant

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

i

3. Scheduled date for restart following shutdown: 60 Day Duration.

4

4. Will refueling or resumption of operation thereafter require a technical

specification change or other license amendment? No 4

If yes, explain If no, has the reload fuel design and core configuration been reviewed by l Plant Safety Review Committee to determine whether any unreviewed safety questions as associated with the core reload (Reference 10 CFR, Section 50.59)? To be performed once core loading determined ,for cycle 30.

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

l

5. Scheduled date(s) for submittal of proposed licensing action and supporting information: N/A

6. Important licensing consideracions 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 ins core 84; spent fuel pool storage 358; new fuel storage D.

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: Last total core off load 1996; Last refueling 1999.

l I

l REfMELits.M6  !

October 1. 1996

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FORM 16.3.H operating Status Report - Nuclear Regulatory Commission Prepared by: #7/2/4/ Dates (*

Reviewed by:

Dates / C6 / b (Reactor Engineer or Alternate) '

I

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

l 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 801 Warrenville Road Lisle, IL 60532-4351 DR Hahn Department of Enviromental Quality 3500 North Logan I

Lansing, MI 48906 JR Padgett Michigan Public Service Commission PO Box 30221 Lansing, MI 48909 l

Robert Aben, Assistant Chief i Bureau of Construction Codes l Michigan Department of Labor r 7150 Harris Drive, Box 30015 l Lansing, MI 48909 American Nuclear Insurers Atts MP Cass Town Center, Suite 3005 29 south Main street West Hartford, CT 06107-2445 GL Hayes General Electric 2311 West 22 St.

Suite 201 Oak Brook, IL 60540 Routing Copy PA Fenech, Palisades Plant Ji McIntyre, P26-204 j JC Withrow, Big Rock Point Plant NRC Resident Inspector, Big Rock Point Plant Document control Center, Big Rock Point Plant i DCC 740*22*35*10 (740*22*10*04) Cross Reference COWER $ MEET.D01 octaber 1, 1996 16.3.3 - 17