ML20207C726
| ML20207C726 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/30/1986 |
| From: | Bielinski M, Hoffman D, Johnston CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8607210425 | |
| Download: ML20207C726 (5) | |
Text
D.
Consumers Power company NUCLEAR OPERATIONS DEPARTMENT Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by
'(eterf7$h7 6537 Ex228 April 1986 50-155 Big Rock Point May 5, 1986 MJBielinski olu Method of Shutting Duration Down Licensee Event System Com nt Number Date Type (Hours)
Reason Reactor Report Number Code 4 Code Cause and Corrective Action To Prevent Recurrence 86-02 03/01/86 F
0 A
N/A N/A Self imposed power reduction as a result of a high pressure turbine steam seal problem. The plant will continue to operate at reduced power until the next appropriate opportunity to mcke repairs.
- The durantion 1;ours for ever t 86-0:
have bc en changed to rerain consistent witl1 prev ious rerorted power reLuction duratior. hours.
E L_-
bd 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 N
B = Maintenance of Test 2 = Manual Scram fo 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) 8607210425 860430 DR ADOCK 0000 5
Form 3156 1-82
DOLk t. l NO.
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JtHINS TON HF i l,' A I I Nt. S I A filY PHONE:
616-54 7--6537, EX T 1H0 1.
IINI I NAME'
!* I t. ROCK POINT NUCLEAR PLANT NOTES:
?.
RF POR t !M. PERIOD:
4 / Hi
- 3. L i t:E NSE D THERNAL POWER (NWT):
240
- 4. HAMEFLATE RATING (GROSI HWE):
75
- 5. DESIGN ELECTRICAL RATING (NET NWE):
72 4.
NAXINUM DEPENDAfiLE CAPACITY (GROSS NWE):
73.0 7.
NAXINUM DEPENDABLE CAPACITY (NET NWE):
69.0 H.
IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS-
- 9. I'OWER LEVEL TO WHICH RESTRICTED,IF ANY (NET NWE):
63.0.
- 10. REASONS FOR RESTRICTIONS, IF ANY: STEAN SEAL REG PRESSURE PROBLENS.
THIS NONTH YEAR-TO-DATE CUNULATIVE
- 11. HotJRS IN RE' PORTING PERIOD 719.0 2879.0 202410.0
- 12. HIJNBf R OF HOURS REACTOR WAS CRITICAL 719.0 2751.4 143983.2
- 13. RFACTOR RESERVL SHUTDOWN HOURS O.0 0.0 0.0
- 14. HOtJRS GENERATOR ON-LINE 719.0 2741.0 141381.8 l 'I. LJN!T RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. EROSS IHERNAL ENERGY GENERATED (NWH) 148406.0 573084.0 26618355.0
- 17. GROSS ELECTRICAL _ ENERGY GENERATED (NWH) 47620.0 183304.0 0424491.0
- 10. NEI ELECTRICAL ENERGY GENERATED (NWH) 45152.0 173767.0 7965939.2
- 19. UNIT SERVICE FACTOR 100.0%
95.2%
69.0%
- 20. UNIT AVAILADILITY FACTOR 100.0%
95.2%
69.0%
?1. UNIT CAPACITY FACTOR (USING NDC NET) 91.0%
07.5%
50.6%
- 22. LINII CAf'ACI TY F ACTOR (USING DER NET) 87.2%
83.8%
54.7%
.' 3. LINIT FORCED OUTAGE RATE O.0%
4.0%
14.9%
- 24. SilUTDOWNI SCHEDtJLED OVER NEXT 6 NONTHS(TYPE,DATE, & DURATION OF EACH):
?*i. IF Shill DOWN AT FND OF T:EPORT F ERIOD, ESTINATED DATE OF STARTUP:
p-,
[
DAY AVERAGE DAILY POWER (MWT)
(MWEN)
( 4/86)
~
i 205.17 62.20 2
203.92 62.08 3
207.42 62.77 4
205.83 62.45 5
205.33 62.29 6
205.67 62.42 7
206.71 62.72 8
205.83 62.47 9
205.21 62.26 10 204.71 62.22 11 204.12 62.06 12 206.54 62.61 13 205.50 62.42 14 209.00 63.31 15 207.79 63.02 16 207.71 62.90 17 208.71 63.85 18 209.92 63.60 19 209.42 63.37 20 208.54 63.20 21 207.83 62.84 22 204.92 62.71 23 204.67 63.19 24 209.67 63.57 25 207.21 63.32 26 205.87 63.20 27 205.96 63.06 28 205.67 62.83 29 204.50 62.62 30 202.83 62.42 1
I
Refueling Information Request 1.
Facility name: Big Rock Point Plant 2.
Scheduled date for next refueling shutdown: October 24, 1986 3.
Scheduled date for restart following shutdown: December 12, 1986 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)? No If no review has taken place, when is it scheduled?
5.
Scheduled date(s) for submittal of proposed licensing action and supporting information:
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:
7.
Number of fuel assemblies in: core 84; spent fuel storage pool 192.
8.
Present licensed spent fuel storage capacity: 441 Size of any increase in licensed storage capacity that has been requested or is planned (in number of fuel assemblies):
9.
Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:
1995 l
MIO385-0458A-BT01
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Plant Superintendent Big Rock Point Nucle.r Plant, Box 591, Route 3, Charlevoix, MI 49720 May 5, 1986 Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period April 1,1986 through April 30, 1986.
Sincerely,
%?
D P Hoffman Plant Superintendent Enclosures cc: DEVanfarowe, Department of Public Health RCallen, Michigan Public Service Commission Michigan Department of Labor INPO Record Center Resident NRC Inspector, Site Document Control, Big Rock Point, 740*22*35*10 FWBuckman, P24-117B KWBerry, P24-614B File 9v,p MIO10-0667A-BT01
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