ML20132G178
| ML20132G178 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/31/1985 |
| From: | Dugan J, Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8510010491 | |
| Download: ML20132G178 (7) | |
Text
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BOILING W 3YATUS 0F SPENT FUEL 3TORASE CAPABILITY u
NATER M
U REACTORS u
- Ce)
REMAININO CAPACITY umennnnununnesu CORE SIZE PRESENT AUTN.
NO. OF IF PENDINO REQUEST (b)
(NO. OF STORAGE POOL CAP. ASSEN3 LIES REMAINING CAPACITY APPROVED NEXT REFUEL MILL FILL PRESENT FACILITY ASSEMBLIES) (FUEL ASSEMBLIES)
STORED (NO. OF ASSEMBLIES) (NO. OF ASSEMBLIES) SCHED. DATE AUTH. CAPACITY mennnanns mennusanneum ummenniummuumunu muuuununum usuuuuuuuuuuuuuum umensuuuuuuuuuuuun muusunnunum unuunusunnusunnunt BIO ROCK POINT 1 84 441 172 249 WS Y(U[
BROMNS FERRY 1 744 3471 1968 2403 es-85 M
BRotees FERRY 2 764 3471 1652 77(m) 1819 WS 1985 BROMISS FERRY 3 764 3471 1904 2467(m)
N/S 1985 BRUNSMICK 1 Set (f) 160PWR+454BNR 2116 04-85 1986 i
ERUIISNICK 2 540 144PMR+544BNR 2204 N/S 1984
~
COOPER STATION 548 2344 985 1381 09-45 1996 DRESDEM 1 444 472 221 451
.WS 1998
)
DRESDEN 2 724 2659Ce) 2014 (e) 996(c) 4129(c)
N/S 1985 DRESDEN 3 724 I
N/S DUANE ARIIOLD -
348 2059 941 1989 WS 1998 FITZPATRICK 54e 2244 954 1288 WS 1991 ORAND OULF 1 a
NATCM 1 540 3021 140 2881 10-85 1999 NATCM 2 540 2750 1284 1466 04-85 1999 NUNDOLUT BAY 17 2 487 251 236 WS LA CROSSE 72 449 207 215 WS 1992 f
LASALLE 1 39-85 LASALLE 2 NILLSTONE 1 588 2t44 1544 968 N/S 1991 i
NONTICELLO
- 484, 2237-914 1521 N/S 1991 MIME MILE POINT 1 532 2774 1244 1532 1788 03-84 1996 OYSTER CREEE 1 540 2600 1078 1522 WS 1999 PEACM SOTTOM 2 764 2816 1552 1264 WS 1993 J
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Report Peeled RAR 1985 PAet 3-4 4 Fcs (1Pr 8510010491 850731 PDR ADOCK 05000155 R
PDR f68 I
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@ CellSnittt NUCLEAR OPERATIONS DEPARTMENT Unit Shutdowns and Power Roductions Report Month Docket Number Unit Date Completed by T ITTSET 6537 X 180 -
S July 1985 50-155 Big Rock Point Plant Ausust 2, 1985 JSougan Method of Shutting Duration Down Ucensee Event System Com t
Number Date Type' IHours)
Reason Reactor Report Numbar Code Code Cause end Corrective Action To Prevent Recurrence d
's NONE 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 1 - Same Source F = Administrative G = Operational Error (Explain)
H = Other (Explain)
Form 3166 1-82
O GREYHOOK GPERATING DATA RtPORT 00CKFT No. 50-155 OATF3 e/- 1 / A5
,Q OYt
- r. HOSS PH'pH t
- 8. t a, *. 4 T - 8,9 ) f e t 9 i I80 N'l 9 411t4G S T A ttn i
- 1. Ur4!T NAME: BIG puck POlt4T NUCLEAR PLANT NOTES:
) !
- 2. atPORTING PERIOD:
7 / 85
- 3. LICENSE 0 THERMAL POWER (MWTit 240
,S 4.
Ta AMEPL ATE R ATIt4G IGRt155 MWElf 75 l
- 5. LESIG's ELECTRICAL RATING INET MwEls 72 l
- 6. "AXIMUM DEPENDAulE CAPACITY IGROSS MdElf 73 0 7.
'4 A x ! MUM DEPENDA14LE C AP ACITV tr4ET MWEI:
09.0 l 9 l
8.
IF CHANGE 5 OCCUR l *4 CAPACITY RATING 54tTEMS 3 THRU Tl SINCE LAST REPORT. GivE REASON 5!
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- 9. l'O.4ER LEVEL 70 wHICH RESTRICTE0 elf ANY (NET MwElf 0.0
- 10. FEASONS FOR RESTRICTIONS, IF ANY
!O THis MONTH.
YFAR-TO-DATF CUMULATIVE
- e
.744.0 5087.0 195858.0 l
- 11. hours IN REPORTING PERIOD-.
- 12. huMSER 05 HOURS REACTOR WAS CRITICAL 744.0 4549.9 139242 2 l
- 13. REACTOR RESERVL 5HrJT00wN HOURS 0.0 00 0.0
_14. HOURS GENERATOR ON-LINE 744.0 4505.0 136703.3
- 15. UNIT RESERVE Shui 0 awn HOUR $
0.0 0.0 0.0
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- 16. t,ROSS THFRMAL tNrRf.Y GENERATED IMWHI 120030 0 a79777.0 257312812.0
{$
_ J 7. GR055 ELCCTRICAL LNLnGY GENERATED IMWH4
.38895 0 282709.0 0139960.0 i
- 16. '4ET ELECTRICAL ENERGY GENERATED IMwHI 36410.2 26T212.4 7696953.3
- 19. UNIT SERVICE FACTOR
'!00.0%
88.6%
69.82 l $
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_20. UNIT AV AILABILITY F-ACTOR
.100.05 88.6%
69.9t l
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- 21. UNIT CAPACITY FACTGR (USING MDC NETI 70.9%
76.1%
58.5%
- 22. UNIT CAPACITY FACTUR IUSING DER NETI 68.0%
73 0%
54.6%
h '.t
_23. UNIT FORCEO OUTAGE RATE
.0.0%
0.8%
15 3%
[)-
'1
- 24. %UT00hN5 SCHEDULEn OVER NEXT 6 MONTH 5tTYPi,0 ATE. C OURATION OF EACHit I
- 25. IF 5 HUT 00wN AT END OF REPORT PERIOD. ESTIMaff0 OATE OF STARTUPI O
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sVE7 r's :41LY P.iWh ( G T)
( 'A.' " )
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LA(
1 171 2 52 74 2
l'1 21 52 57 3
173 54 52 2t 1*.S.75 31.04 5
156.5s 31.$'
167.67 51 40' 7
167.25 51 37 E
1*J7.27 51.22 9
156.5*
90.43 10 167 04 51.14 I
11 144 12
- 3 32 12 1o6.21 51.15 13 153 37
- 7.40 1*
161.12 49.54 15 162.79 4'.23 16
.lc2.4?
49.04 17 160.25-4B.55-la 161 53 46 33 19 160.62 69.41 20 159.70 4B.03 21 159 12 47.75 22 15?.29 47.46 23 157.71 47.37 24 156 5G 47 17-25 156.25 46.91 26 155.E7 43.74 27 154.33 46.53 23 154.5) 45.33 27 153 53 46.02 30 153 59 95.94 31 152.25 65.$8
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Refuelina Information Request 1.
Facility asse: Big Rock Point Plant 2.
' Scheduled date for mest refueling shutdown: August 1985 3.
Scheduled date for restart following shutdown: October 1985 4.
Vill refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Ho 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 I
t If no review has taken place, when is it scheduled?
{
Prior to startup 5.
Scheduled date(s) for submittal of proposed licensing action and supporting information:
6.
Important licensing considerations associated with refueling, eg, new 'or I
different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design new operating procedures:
l' Reload Il has higher MAPLHGER limits allowing higher power levels.
Licensing approval vill prevent an unnecessary power reduction.
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):
t l
9.
Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:
1993 1
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BP0385-0458A-BT01 l
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1 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?
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 s'cheduled?
Prior to startup 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:
Reload Il has higher MAPLHGER licits allowing higher power levels.
Licensing approval will prevent an unnecessary power reduction.
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 assembif es):
9.
Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:
1993 BP0385-0458A-BT01 l
CODSum813 POW 8r a e " '<- -
C0mpBDy Big Rock Polet Nuc4 ear Plant, Bow 591, Route 3, charlevola, MI 49720 August 2, 1985 Director Office of Inspection and Enforcement United States Nuclear Regulatory Commissien Washington, DC 20555
Dear Sir:
Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period July 1 through July 31, 1985 Sincerely, D P Hoffcan Plant Superintendent DPH:llb Enclosures cc:
DEVA.Farowe, Department of Public Health RCallen,-Michigan Public Service Commission Michigan Department of Labor INFO Records Center Resident NRC Inspector, Site l
Document Control, BRP, 740*22*35*10 E3DeWitt, P24-ll?B DJVandeWalle, P24-115 gsa,r24-610
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