ML20135B201

Monthly Operating Rept for June 1985

ML20135B201
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	06/30/1985
From:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8509100470
Download: ML20135B201 (6)

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mennnnnnannnnat a DOILING N 3YATUS 0F SPENT FUEL 5 TORA 0E CAPABILITY u HATEt u REACTORS u ' (a) REMAINING CAPACITY O

PRESENT AUTN. NO. OF IF PENDING REGUEST (b) uneneumanneusansN CORE SIZE APPROVED NEXT REFUEL MILL FILL PRESENT (NO. OF STORAGE POOL CAP. ASSEMBLIES REMAINING CAPACITY AUTN. CAPACITY FACILITY ASSEMBLIES) (FUEL ASSEMBLIES) STORED (NO. OF ASSEMBLIES) (NO. OF ASSEMBLIES) SCHED. DATE unuununus musumansuun muuuuuuuuuuuuun muunnununu muuuuuuuuuuuuuuum unuuuuuuuuuuuuuum uunummununu muuuuuuuuuuuuuuun BI7 ROCK POINT 1 BROMNS FERRY 1 44 764 441 3471 172 1968 269 2403 N/S 03-85 M1985 Y IT7[

764 3471 1652 77(m) 1819 WS BROWNS FERRY 2 WS 1945 Bu0 Mets FERRY 3 744 3471 1004 2467(m)

BRUNSMICK 1 560 (f) 16OPMR+454BWR 2116 04-85 1986 -

144PHR+5649WR 2208 N/S 1986 BRustSMICK 2 560 09-45 1996 COOPER STATION 344 2366 985 1581 672 221 451 N/$ 1990 BRESDM 1 464 WS 1985 DRESDEN 2 724 2659Cc) 2014 (c) 996(c) 6129(c) 724 i WS DRESDEN 3 N/$ 1994 DUANE AR100L3 368 2050 941 1089 .

560 2244 954 1288 WS 1991 FITZPATRICK ORAND OULF 1 10-85 1999 MATCM 1 540 3021 140 2881 '

2750 1284 1466 04-85 1999 MATCN 2 560 WS NUMBOLWT BAY 17 2 447 251 256 72 440 207 215 WS 1992 LA CROSSE 09-85 LASALLE 1 LASALLE 2 968 N/S 1991 MILLSTONE 1 580 2184 1546 484, 2237 916 1321 N/S 1991 MostTICELLO 1788 03-86 1996 NINE MILE POINT i 532 2774 1244 1532 540 2600 1078 1522 N/S 1990 OYSTER CREEK 1 N/S 1990 PEACN BOTTOM 2 764 2816 1552 1264 i

1 Repset Period MAR 1985 , PAGE 5-4 s-~ A . F C G (1 9.t-'

k 8509100470 850630 D. e PDR ADOCK 05000155 PDR l7 R

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@ CNSW5 NUCl. EAR OPERATIONS DEPARTMENT Unit Shutdowns and Power Reductions Date Completed by Telephone Report Month Docket Number Unit June 1985 50-155 Big Rock Point Plant July 5, 1985 JSDugan (616)S47 6537 X 180 Method of Shutting Duretion Down Licensee Event Systg t 2 3 Report Number Code Code Cause and Corrective Action To Prevent Recurrence Nurnbar Date Type, (Hours) Reason Reactor NONE 3 Method: 4 I F = Forced 2 Reason: Exhibit G = Instructions for A = Equipment Failure (Explain) 1 = Manual Preparation of Data Entry Sheets S = Scheduled 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 I = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain) c.m _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

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Is UNIT NAME: PIG muck K IIT NUCLEIO PLCNT C33 f E 5 8 9 i

43 C E P04T ING C E~.;IGOs C / 85 , ,

32 LICENSFT; THE1. mat innta emwil 240 ">

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c, haut; LOTE 8.". TING IC 55 mwE l s TS 5 Dell %e ELECT;tCCL 91 TING tNET E:WEls 72 l' 0., mast 4um DE ENDATLE CisACITV IGRISS MwEle 75 0 O'3 Ta mattmOM DEPENDABLE C AP ACITV (NET MwEls 69.0 C3 IF CHANGES OCCUR IN CAPACITY #ATING5t!TEMS ) THRU Tl SINCE LAST RF80tT. GivF #E AS%5 9

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Ce C OWER LEVEL TO wMICH AE STo tCTED,IF ANY tNET Mwfit 0.0 10, CE ASONS F04 RESTR!CTIONS. IF ANya

• 9 THis MONTH TEAR-TO-$ATF COMULAT!vF 11, HCH45 IN REPORTING PF A100 720.0 e145.0 195114.0 g 123 4u488R OF HOUn5 aEACT0a was CalTICAL 720.0 3n05.9 139498.2 133 CEACT0e eE5Envf Swuf00wk HOURS 0.0 0.n 0.0 l*>e HOV45 CENE4ATn4 ON-LINF 720.0 1761 0 119959.1 .

g 153 UNIT 4F5ftvE 5HUTOOwN MOURS 0.0 0.0 0.n 13, GROSS TntamAL thERGY GENERATED IMwHI 192489.0 758A97.0 24611292.0 17 CaOSS ELECT 4tCAL ENERGY GENERATED IMwHS 43187.0 24s814 0 8801065.0 g 18, NET ELECTRIC AL ENERGY GENERATED InwMB 40725.2 230902 2 7660543 1 tce UNIY SERvlCE F ACTO 4 100.04 86 6% 69.7%

20e UNIT AVAILA8ILITY FACTOR 100.0% 86.6% 69.Tt g 21 UNIT C APACITY FACTOR t uSING MDC NET) 82 04 77.74 5s.91 223 UNIT CAPA(ITY FACT 04 tOSING DER NETS 78.64 T3.9t 54.5%

23 UNIT FOACEO OUTAGE aATE 0 0% 10t 15.At 9 20e SMUT'10wh5 SCME0utfC Ovf 4 Neuf 6 =0 NTH 5t TYPE,0 ATE, C OUp ATION 08 EACHit g b

25s IF 5'4UT PO=4 A T END OF RFPORT Pest 00. ESTtnATFD DaTE OF STAATUP8 9

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1 202.37 62.00 2 197 17 60.50

o* 3 196.71 60.11 4 195.17 59.78 -

5 193 79 59.50 in 6 171 46 59 20 7 192.21 58.87 8 187.87 58.67

> e) 9 188.42 58.27 10 197.71 59.05 11 187.79 57.77

' ri 12 184.54 57.47 13 187.71 57.19 14 184 46 56.90 iO 15 184 17 56.58 16 182.71 56.38 17 181 92 56.08

51 18 181.42 55'.75 19 130.33 55.53 20 183 17 55.41 0 21 177.54 55.59 22 180.29 55.44 23 178.83 55.07 iO 24 176.79 54.85 25 178.21 54.60 26 177.29 54.39

27 152.67 45.72 2B 179.75 55.05 29 173.25 53 17 Q 30 172.62 53.01 O

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Befuelina Informaties Reemest

1. Facility name: Big Rock Point Plant

2. " Scheduled date for mest refueling shutdown: Angest 1985 .

l 3. Scheduled date for restart following shutdown: October 1985  :

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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.

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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 _

50.5~9)?

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! If no review has taken place, when is it scheduled?

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l 5. Scheduled date(s) for submittal of proposed licensing action and i supporting information:

6. Important licensing considerations associated with relueling, es, new or different fuel design er supplier, unreviewed design or performance analysis methods, significant changes in fuel design new operating i procedures:

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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 assuming the present license capacity: 1993 BP0385-0458A-BT01

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5Y'*W CORSum8tS Power o e a '<- -

Plant Superintendent Big Rock Point Nuc4eer Plant, Box 591, Route 3, Charlevola, MI 49720

. July 5, 1985 ,

i Director Office of Inspection and Enforcement, ,

United States Nuclear Regulatory Commission Washington, DC 20555

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Dear Sir:

Enclosed please find the statistical data for the Big Rock Point Nuclear Plant covering the period of June 1 through June 30, 1985 Sincerely,

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a D P Hoffman Plant Superintendent DPH:llb Enclosures 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-il7B I DJVandeWalle, P24-115 .

! WGFogg, P24-610

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