ML20133H265
| ML20133H265 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/31/1985 |
| From: | Bartosik S, Dugan J, Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8508090266 | |
| Download: ML20133H265 (5) | |
Text
Cgggg3 NUCLEAR OPERATIONS DEPARTMENT xy Unit Shutdowns and Power Reductions 20 CD O
>4 Report Month Docket Number Unit Date Completed by Telephone 80 May, 1985 50-155 Big Rock Point Plant June 7, 1985 JSDugan (616)5h7 6537 X 180 n o-70' OCD cG Method of CO Shutting
]gJ Number G
Duration Down Licensee Event System ent j
3 4
Date Type (Hours)
Reason
- Reactor Report Number Code Code Ceues and Correcthe Action To Prewnt Recurrenos zo 05/15 -
S 73.8 A
1 CB PUMPXX Scheduled outage for repair of 05/18 SUBCODE B recirculating pump seal 05/25 -
F 25.8 A
1 CB VALVEX Shutdown to repair leak in packing on 05/26 SUBCODE F motor operated valve on 3/h" heat exchanger on recirculating. pump Reducec 05/01 -
0 A
h CB PUMPXX This was a power reduction due to Power 05/15 SUBCODE B removing one recirculating pump from service which had a packing leak 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 q
F = Administrative G = Operational Error (Explain)
H = Other (Explain)
Form 3156 1-82
BY: SA aLRTNSIX OPERATING STt.TUS PHONE: 616 "47-9537, EXT 193 l'
- 1. UNIT NA*c GIG ROCx P11NT NUCLcAR DLANT SOTES:
- 2. DEP0aTING PExtDO:
5 / R$
- 3. LICE'4 SED THER"AL PJ'2FR I42TI:
240
- 4. NACEptATF PATING (GROSS M4ct:
75 S. DESIGN ELECTRICAL RATING INET "wEls 72
- 6. "AtIMUM DEPENDABLE CAPACITY (GROSS MdEl:
T3.0
- 7. "ANIMUM DEPENDABLE CAPACITY INFT MWEI:
69.0 n.
IF CH A*.GE S OCCUR 1*4 CAPACITY PATINGSt!TEMS 3 T*4RU 71 SINC 8 LAST REPCPT, GIVC RE ASONS:
9 POWER LEVEL TO WHICH RCSTRICTED,IE ANY INET *nrl:
C.0
- 10. PFASONs r0R RESTRICTIONS, IF ANY:
THIS MONTH YEAR-TO-DATE CUMULATIVE
!!. HOUNS Ir4 RFP0aTING PERIOD 744.0 3623.0 194304.0
- 12. SUMBED OF HOURS REACTOR WAS CRITICAL 644.3 30 M. )
137774 2
- 13. PEACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 623.6 3041.3 135239.3
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 00 0.0
- 16. r.p nS S THERMAL ENERGY GENERATED ("wH) 99515.0 624352.0 2%76907.0
- 17. GROSS rLFCTRICAL ENERGY GENERATED (MWHI 32605.0 200627.0 a757a73.0
- 18. '. E T cLECTRICAL ENEEGY GFNEPAT50 tww4) 30*26.7 190077 3 7619917.1 19 UNIT SERVIC E F ACTOR 83.9%
93.7%
$9.6%
- 20. UNIT AVAILABILITY FACTOR 83.8%
43.71 69.6%
- 21. UNIT CAPACITY FACTOR IUSINr,MOC NET) 60.0%
76.3%
58.42
- 22. UNIT CAPACITY FACTOR IUSIN". DER NET) 57.5%
72 4%
54.4%
- 23. t!N I T FGRCEO OUTAGE RATS, 8.9t 1.2%
- 14. 9 24 SHUT 90hNS SCHEDULE 9 CvFR NerT 6 "0NTHSITYPE,0 ATE, C DURATION OF EACHl:
- 25. IF SHUT DO N AT SND OF REPORT PERIOD, ESTIMATED DATF Or STARTUp:
3 e
)
DAY.
AVERAGE DAILY-POWER (MWil (MUEN)
( 5/85) p.
1 120.29 33.33 2-119.46 36.37 3
152.29 47.55 4
157.54 48.12 5
155.42 48.02 6
157.42 47.93 7
153.37 47.67 8
155.54 47.67 9
157.54 48.43 10 156.92 43.47 11 156 58 48.36 12 156.50 48.19 13
'156.79 48.37 14 156.50 48.30 15 107.08 32.41 16 0.0 0.0 17 0.0 0.0 18 0.0 0.0 19 111 71 31.55 20 161.42 49.37 21 167.42 51.31 22 172.58 53.20 23 199.12 60.98 24 204.96 62.30 25 43.42 11 31 26 6 42 0.0 27 153.17 46.00 28 202 25 61 63 29 201.04 61 33 30 198.62 61 14 31 105.08 55.05 k-3 >
Refuelina Information Request 1.
Facility name: Big Rock Point Plant 2.
Scheduled date for next refueling shutdown: August 1985 3.
Scheduled date for restart following shutdown:
October 1985 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes If yes, explain: Addition of " Appendix R" commitments and Il Reload.
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)?
2 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 l
different fuel design or supplier, unreviewed desiga or performance analysis methods, significant changes in fuel design new operating
[
procedures:
I 7.
Number of fuel assemblies in: core 84; spent fuel storage pool 172.
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 1
~
assuming the present license capacity:
1993 l
BP0385-0458A-BT01
O
^
60-l6Y Consumers Power o r we'<- -
PLmt Superintendent Big Rock Point Nuclear Plant, Box 591, Route 3, Charlevoix, MI 49720 June 7, 1985 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 of May 1 through May 31, 1985 Sincerely, D P Hoffman Plant Superintendent DPH:llb Enclosures i
cc:
DEVanFarowe, Department of Public Health RCallen, Michigan Public Service Commission Michigan Department of Labor INPO Records Center Resident NRC Inspector, Site Document Control, BRP, 740*22*35*10 RBDeWitt, P24-ll7B DJVandeWalle, P24-ll5 WGFogg, P24-610 File rely
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