ML20132G178

Monthly Operating Rept for Jul

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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o n BOILING W 3YATUS 0F SPENT FUEL 3TORASE CAPABILITY u NATER M REMAININO CAPACITY U REACTORS u

• Ce) (b) umennnnununnesu CORE SIZE PRESENT AUTN. NO. OF IF PENDINO REQUEST

. . (NO. OF STORAGE POOL CAP. ASSEN3 LIES REMAINING CAPACITY APPROVED NEXT REFUEL MILL FILL PRESENT ,

STORED (NO. OF ASSEMBLIES) (NO. OF ASSEMBLIES) SCHED. DATE AUTH. CAPACITY FACILITY ASSEMBLIES) (FUEL ASSEMBLIES) umensuuuuuuuuuuuun muusunnunum unuunusunnusunnunt mennnanns mennusanneum ummenniummuumunu muuuununum usuuuuuuuuuuuuuum BIO ROCK POINT 1 84 441 172 249 2403 WS es-85 M Y(U[ .

BROMNS FERRY 1 744 3471 1968 764 3471 1652 77(m) 1819 WS 1985 BRotees FERRY 2 N/S 1985 BROMISS FERRY 3 764 3471 1904 2467(m) 2116 04-85 1986 -

BRUNSMICK 1 Set (f) 160PWR+454BNR N/S 1984 ERUIISNICK 2 540 144PMR+544BNR 2204 i

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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 a ORAND OULF 1 10-85 1999 NATCM 1 540 3021 140 2881

• 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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l. Report Peeled RAR 1985 . PAet 3-4 4 Fcs (1Pr 8510010491 850731 PDR R ADOCK 05000155 PDR f68 I '

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@ CellSnittt NUCLEAR OPERATIONS DEPARTMENT Unit Shutdowns and Power Roductions Report Month Docket Number Unit Date Completed by July 1985 50-155 Big Rock Point Plant Ausust 2, 1985 JSougan TS ITTSET 6537 X 180 -

Method of Shutting Duration Down Ucensee Event System Com t Number Date Type' IHours) Reason Reactor Report Numbar Code d Code Cause end Corrective Action To Prevent Recurrence s

NONE I F = Forced ' 2 Reason: 3 Method: 4 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 5 Exhibit 1 - Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3166 1-82

GREYHOOK GPERATING DATA RtPORT O

00CKFT No. 50-155 OATF3 e/- 1 / A5 OYt r. HOSS ,Q PH'pH t 8. t a, *. 4 T - 8,9 ) f e t 9 i I80 N'l 9 411t4G S T A ttn

1. Ur4!T NAME: BIG puck POlt4T NUCLEAR PLANT NOTES:

i $

)! 2. atPORTING PERIOD: 7 / 85 240

3. LICENSE 0 THERMAL POWER (MWTit

4. Ta AMEPL ATE R ATIt4G IGRt155 MWElf 75 ,S 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!  :

ie 0.0 .

j 9. l'O.4ER LEVEL 70 wHICH RESTRICTE0 elf ANY (NET MwElf *$

10. FEASONS FOR RESTRICTIONS, IF ANY  :

!O YFAR-TO-DATF CUMULATIVE THis MONTH.

e 5087.0 195858.0 l

.744.0

11. hours IN REPORTING PERIOD-. 744.0 4549.9 139242 2 l

12. huMSER 05 HOURS REACTOR WAS CRITICAL 0.0 00 0.0 . $

13. REACTOR RESERVL 5HrJT00wN HOURS  :

744.0 4505.0 136703.3

_14. HOURS GENERATOR ON-LINE 0.0 0.0 0.0

15. UNIT RESERVE Shui 0 awn HOUR $

120030 0 a79777.0 257312812.0 {$

) 16. t,ROSS THFRMAL tNrRf.Y GENERATED IMWHI

.38895 0 282709.0 0139960.0

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• _ J 7. GR055 ELCCTRICAL LNLnGY GENERATED IMWH4 36410.2 26T212.4 7696953.3 ,

i 16. '4ET ELECTRICAL ENERGY GENERATED IMwHI 88.6% 69.82 l $

19. UNIT SERVICE FACTOR '!00.0% l

)8 i _20. UNIT AV AILABILITY F- ACTOR .100.05 88.6%

76.1%

69.9t 58.5%

70.9%

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• 21. UNIT CAPACITY FACTGR (USING MDC NETI 68.0% 73 0% 54.6%  !. $

22. UNIT CAPACITY FACTUR IUSING DER NETI 0.8% 15 3%  !

.0.0%

h '.t _23. UNIT FORCEO OUTAGE RATE

[

)- 24. %UT00hN5 SCHEDULEn OVER NEXT 6 MONTH 5tTYPi,0 ATE. C OURATION OF EACHit

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25. IF 5 HUT 00wN AT END OF REPORT PERIOD. ESTIMaff0 OATE OF STARTUPI O j :. e

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, LA( .

sVE7 r's :41LY P.iWh ( G T) ( 'A .' " ) ( 7/ r ;. )

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.03 159 12 21 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 different fuel design or supplier, unreviewed design or performance I 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

( BP0385-0458A-BT01  !

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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 ,,01acui o 6/fr corsute " / ,p : '

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