ML20133C542
| ML20133C542 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 12/31/1996 |
| From: | Donnelly P, Jeanne Johnston CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9701070220 | |
| Download: ML20133C542 (6) | |
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Consumers Power e.irica u oonn.iiy Plant Manager n9KN8GAN5 MROlHtE55 Big Rock Pomt Nuclear Plant,10269 US-31 North. Charlevoix. MI 49720 January 2, 1997 Nuclear Regulatory Commission Document Control Desk Nashington, DC 20555 Dear sirs
(
Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period of December 1,1996 through Deccaber 31, 1990, sincerely, f
/ E t
P M Donnelly Plant Manager Enclosures cca Administrator Region III, Nuclear Regulatory Commission DREsha, Department of Public Esath i
JRPadgett, Michigan Public service Commission RAben, Michigan Department of Labor MPCase, American Nuclear Insures l
FYost, Research services Utility Data Institute GLBayes, General Electric Company l
l RAFenech, Palisades
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OCNithrow, Big Rock Point
.i NRC Resident Inspector, Big Rock Point Document Control, Big Rock Point, 740/22*35*10 A,',
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9701070220 961231 PDR ADOCK 05000155 R
PDR A C46EMD?GYCOMA4NY l
Power NUCLEAR OPERATIONS DEPARTMENT
~ -
W Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Tetephone Decensber, 1996 55-150 Big Rock Point Plant January 2, 1997 JR Johnston (616) 547-8223 Method of Shutting Duration Down Licensee Event System Component I
4 Number Date Type (Hours)
Reason Reactor Report Number Code Code 5 Cause and Corrective Action To Prevent Recurrence 96-07 12/07/96 F
587.8 Hrs A
3 On 12/07/96 at 12:10; An autanatic voltage control circuit in the exciter failed, which caused a protective relay to "open" and trip the turbine off-line; thus causing an automatic reactor scrase on high power. After repairs were completed and attempting to return the unit to service; high turbine vibration was noticed. The turbine was placed on turning gear for investigation / repairs.
The unit will return to norinal service when repairs are completed.
I 2
3 F = Forced Reason:
Method:
Exhibit G = Instructions for S = Scheduled A = Equipment Failure (Explain) 1 = Mare!
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 5Exhibit i = Same Source F = Administrative G = Operational Error (Explain)
H = Other (Explain)
Form 3156 1-82
1 STATS VERSION 04.001: EA-B-STATS-94-02 12/30/94 CUNTIME=01/02/97 07:52:37 Page 4 of 9 e
GREYBDOK OPERATING DATA REPORT DOCKET NO. 50-155 DATE: 12 / 27 / 96 BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223
- 1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT NOTES:
- 2. REPORTING PERIOD:
12 / 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):
67.0
- 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POVER LEVEL TO WHICH RFSTRICTED,IF ANY (NET MWE):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YEAR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.0 8784.0 295963.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 176.9 5667.6 215703.6
- 13. REACTDR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 156.2 5573.7 212377.2
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 35835.0 1215190.0 41174261.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 11235.0 384687.0 13085669.0
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 10664.8 365323.3 12381261.3
- 19. UNIT SERVICE FACTOR 21.0%
63.5%
71.8%
?O. UNIT AVAILABILITY FACTOR 21.0%
63.5%
71.8%
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 21.4%
62.1%
62.2%
- 22. UNIT CAPACITY FACTOR (USING DER NET) 19.9%
57.8%
58.1%
- 23. UNIT FORCED OUTAGE RATE 79.0%
13.3%
10.9%
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION OF EACH): Refueling, April, 1997, 60 days.
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 01/22/97
1 STATS VERSION 94.001; EA-B-STATS-94-02 12/30/94 RUNTIME=01/02/97 07:52:37 Page 2 of 9 OAY AVERAGE DAILY POWER (MVT)
(MWEN)
(12/96) - CYCLE 29 1
226.50 68.35 2
227.00 68.73 3
225.67 67.93 4
227.33 68.42 5
226.50 68.25 6
227.00 68.55 7
116.13 34.13 8
0.00 0.00 9
0.00 0.00 10 0.00 0.00 11 17.00 0.00 12 0.00 0.00 13 0.00 0.00 14 0.00 0.00 15 0.00 0.00 16 0.00 0.00 17 G.00 0.00 18 0.00 0.00 19 0.00 0.00 20 0.00 0.00 21 0.00 0.00 22 0.0u 0.00 23 0.00 0.00 24 0.00 0.00 25 0.00 0.00 26 0.00 0.C3 27 0.00 0.00 28 0.00 0.00 29 0.00 0.00 30 0.00 0.00 31 0.00 0.00 G
9 m
e G
Kwfuelino Information Recuest f
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.
Will refueling or resumption of operation thereafter require a technical specification change or other license aseadment? No i
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 associated with the core reload (Reference 10 CFR, Section 50.59)? To be performed once core loading dstermined 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.
}>xhor of fuel assemblies ins core 84; spent fuel pool storage 358; new fuel storage O.
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.
REFUELillG.D06 January 2, 1997 w-c
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FORM 16.3.D Operating Status Report - Nuclear Regulatory C ommission O W 7
Prepared by: d M BtL/
9 vt 3
Date:
V U
/ !.1 [9 7 Reviewed by:
y O
Dates (Reactor Engineer or Alternate) l Copy to be sont to the following by the seventh day of each months i
Nuclear Regulatory Commission Document control Desk Washington, DC 20555 Administrator Region III - USNRC i
80' Warrenville Road Lisle, IL 60532-4351 DR Eahn Department of Enviromental Quality 3500 North Logan Lansing, MI 48906 JR Padgett Michigan Public Service Commission PO Box 30221 Lansing, MI 48909 Robert Aben, Assistant Chief Bureau of Construction Codes Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing, MI 48909 l
American Nuclear Insurers
[
Atts MP Cass Town Center, suite 3005 29 South Main Street West Eartford, CT 06107-2445 1
Fred Yost Director, Research Services l
Utility Data Institute 1700 K Street, N.W.
Suite 400 Washington, DC 20006 I
Routing Copy RA Fenech, Palisades Plant SM McIntyre, P26-204 GC Withrow, Big Rock Point Plant NRC Resident Inspector, Big Rock Point Plant Document control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04)
Cross Reference i
00WERSilEFT.001 Jwamor 2,1997 16.3.3 - 17 l
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