ML20134H338
| ML20134H338 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 10/31/1996 |
| From: | Donnelly P, Johnston Jr CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9611140065 | |
| Download: ML20134H338 (6) | |
Text
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@ C011SumerS 1
POWB Patrick M Donneny Plant Afanaw POWERING l
MIEN 0GAN5 PROGRE55 Big Rock Point Nuclear Plant.10269 US 31 North, Charlevom, MI 49720
(
November 1, 1996 l
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 October 1, 1996 through October 31 1996.
l Sincerely, P
/
i
/
05 P M Donnelly Plant Manager Enclosures cc: Administrator Region III, Nuclear Regulatory Commission DRHahn, Department of Public Esath JRPadgett, Michigan Public Service Commission RAben, Michigan Department of Labor MPCass, American Nuclear Insures FYost, Research Services Utility Data Instituto GLHayes, General Electric Company RAFenech, Palisades GCWithrow, Big Rock Point l
NRC Resident Inspector, Big Rock Point Document Control, Big Rock Point, 740/22*35*10 4
File k
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9611140065 961031 PDR ADOCK 05000155 R
PDR 14000s A CMSENERGYCOMPANY i
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FORM 16.3.E j
operating status Report - Nuclear Regulatory Commission Prepared by: Anuv R k ZQ bAOA l h[
Date D
d x
il Reviewed bys s-Dates b
Q (Reactor Engineer or Alternate)
]
Copy to be sent to the following by the seventh day of each month:
l cNuclear.-Regulatory _ Commission-Fred Yost e Document controin Desk' Director, Research Services 1
Washington, DC 20555 Utility Data Institute 1700 K Street, N.W.
Administrator Suite 400 i
l Region III - USNRC Washington, DC 20006 l
801 Warrenville Road Lisle, IL 60532-4351 DR Bahn l
Department of Enviromental Quality 3500 North Logan Lansing, MI 48906 JR Padgett Michigan Public Service Commission l
PO Box 30221 j
Lansing, MI 48909 j
Robert Aben, Assistant Chief Bureau of Construction Codes Michigan Department of Labor 7150 Harris Drive, Box 30015 l
Lansing, MI 48909 American Nuclear Insurers Atta MP Cass Town Center, suite 3008 29 South Main street West Hartford, CT 06107-2445 GL Bayes General Electric 2311 West 22 st.
suite 201 oak Brook, IL 60540 Routing copy RA Fenech,. Palisades Plant l
SM McIntyre, P26-204 l
GC Withrow, Big Rock Point Plant l-NRC Resident Inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 1
(740*22*10*04)
Cross Reference 3
a 4
COWER $NEET.001 november 1, 1996 16.3.3 - 17 r
r v
l CORS81R8f5 NUCLEAR OPERATIONS DEPARTMENT Colnpany l
Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Telephone October, 1996 55-150 Big Rock Point Plant Novai6er 1, 1996 JR Jotwiston (616) 547-8223 Method of Shutting Duration Down Licensee Event System Component I
4 5
Number Date Type 1 Hours)
Reason Reactor R* port Number Code Code Cause and Corrective Action To Prevent Recurrence 96-05 10/10/96 F
39.7 Hrs A
4 On 10/10/96 at 13:20; Power was reduced to allow repairs on #1 Reactor Feedwater pump (packing gland leak). After repairs were completed, the unit was returned to nonnal power operation.
96-06 10/23/96 F
199.7 Hrs H
4 On 10/23/96 at 17:17: The unit was removed from thru service before manually scransaing the reactor to
'10/31/96 fully insert the remaining withdrawn control rod drives (planned). The Electrical Equipmerit Qualifications (EEQ) concerns was the reason for the outage. When the EEQ concerns are resolved, the unit will be returned to service.
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 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 i-82
1 STATS VERSION 94.001; EA-B-STATS-94-02 12/30/94 RUNTIME=11/01/96 10:01:56 Ptge 4 of 9 GREYBOOK OPERATING DATA REPDRT DOCKET NO. 50-155 DATE: 11 / 1 / 96
~
BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223
- 1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT NOTES:
- 2. REPORTING PERIOD:
10 / 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 MVE):
67.0
- 8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LFVEL TO VHICH RESTRICTED,IF ANY (NET MVE):
- 10. REA?ONS FOR RESTRICTIONS, IF ANY:
i THIS MONTH YEAR-TO-DATE CUMULATIVE II. HOURS IN REPORTING PERIOD 745.0 7320.0 294499.0
- 12. NUMBER OF HOURS REACTDR VAS CRITICAL 545.3 4815.3 214851.3
- 13. REACTOR RESERVE SHUTDDWN HOURS 0.0 0.0 0.0 1
- 14. HOURS GENERATDR ON-LINE 545.3 4758.3 211561.8
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 121080.0 1033119.0 40992190.0
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 38281.0 327273.0 13028255.0
- 18. NET ELECTRICAL ENERGY GENERATED (MVH) 36376.6 310812.7 12326750.7
- 19. UNIT SERVICE FACTOR 73.2%
65.0%
71.8%
- 20. UNIT AVAILABILITY FACTOR 73.2%
65.0%
71.8%
21 UNIT CAPACITY FACTOR (USING MDC NET) 72.9%
63.4%
62.2%
- 22. UNIT CAPACITY FACTOR (USING DER NET) 67.8%
59.0%
58.1%
- 23. UNIT FORCED OUTAGE RATE 26.8%
7.0%
10.6%
2-
SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE & DURATION OF EACH): REFUELING, APRIL, 1996, 60 DAYS.
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: NOVEMBER 3, 1996.
o 1 STATS VERSION C4.001: EA-B-STATS-94-02 12/30/94 RUNTIMEo11/01/96 10:01:56 Pcge 2 of 9 OAY AVERAGE DAILY POWER (MWT)
(MWEN)
(10/96) - CYCLE 29 1
224.71 67.79 t
2 226.67 68.32 3
228.25 68.76 4
227.29 68.41 5
225.92 68.12 6
227.46 68.50 7
226.50 68.24 8
228.04 68.69 9
226.75 68.28 10 189.75 56.92 11 175.88 53.00 12 223.46 67.20 13 224.17 67.42 14-223.04 67.05 15 228.04 68.81 16 227.21 68.03 17 227.63 69.14 18 227.21 68.29 19 227.42 68.60 20 228.13 68.59 21 226.79 68.54 22 229.13 69.07 23 145.58 39.92 24 0.00 0.00 25 0.00 0.00 26 0.00 0.00 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
S Bifuelina Information Reauest 1.
Facility Names Big Rock Point Plant l
l 2.
Scheduled date for next refueling shutdown: April, 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 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?
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 int 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):
O l
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.
REFUELING.D06 Noweu6er 1, 1996 i
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