ML20129F228

Monthly Operating Rept for Apr 1985

ML20129F228
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/30/1985
From:	Balch L, Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8507170279
Download: ML20129F228 (6)

Text

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4 CORSumell NUCLEAR OPERATIONS DEPARTMENT ,

9 Unit Shutdowns and Power Reductions Report Month Docket Number Unit Date Completed by Telephone Anril. 1985 50-155 Big Rock Point Plant May 3, 1985 LLBalch :616)Sh7 6537 x 180 Method of Shutting Duration Down Licensee Event System t Number Date Type I (Hours) Reeson 2 Reactor Report Number Code 4 Comgde Co Cause and Corrective Action To Prevent Recurrence 292.7 A 1 SF VALVEX Scheduled outage for repair of RDS 04/05 S s a n va ves to enable perfomance

- h/17 Subcode E of surveillance test on RDS isolation valves.

8507170279 850430 5 PDR ADOCK 0500 R

I F = Forced 2 Reason: 3 Method: 4 Exhibit G = lostructions 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 S Exhibit 1 = Same Source F = Administrative 93 G = Operational Error (Explain)

H = Other (Explain)

Form 3156 1-82

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OCCKET NO. 50-155 OATE: 5 / 1 / G 5' ~ ~ ' ~ ~

4.

OPECATING STATUS GY PHONFs LINDA DALCH 616-547-6537, EXT 180

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1. UNIT NAME: BIG ROC" 70!NT NUCLEA2 PLANT NOTES:

ep 2. REPORTING PERICO 4/ 85 ap .

3. LICEN$ED THERMAL POWER IMWTI: 240

4. NAMEPLATE RATING (GROSS MWEls 75 e 5. DESIGN ELECTRICAL RATING (NET MWEls 72 ep

4. MAXIMUM DEPENDABLE CAPACITY (GROS $ MWEls 73.0 ,

7. MAXIMUM DEPENDASLE CAPACITY INET MWEls 69 0 gp 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 71 SINCE LAST REPORT. GIVE REASONS:

gp ep

+ GD

9. POWER LEVEL TO WHICH RESTRICTED.IF ANY INET 4WEls 0.0 gy 10. REASONS FOR RESTRICTIONS, IF ANrt gp 8P GD THIS MONTH YEAR-TO-DATE , CUMULATIVE

11. HOURS IN REPORTING PERIOD 719.0 2874.0 193650.0

12. NUMBER OF HOURS REACTOR WAS CRITICAL 438.2 2441.6 137133.9 gy 13. REACTOR RESERVE SHUT 00WN HOURS 0.0 0.0 0.0 gy

14. HOURS GENERATOR ON-LINE 426.3 2417.4 134615.7

15. UNIT RESERVE SHUT 00WN HOURS 0.0 0.0 0.0 gy 16. GROSS THERMAL ENERGY GENERATED IMWHI 98691.0 524837 0 25377392.0 gy

17. CROSS ELECTRICAL ENERGY GENERATED (MWHI 28351.0 168022 0 9025273.0

18. NET ELECTRICAL ENERGY GENERATED (MWHI 26809.9 159250.3 7588991.2 gy 19. UNIT SERVICE FACTOR 59.3% 84 0% 69.5% gp

20. UNIT AVAILABILITY FACTOR 59.3% R4 0% 69.5%

21. UNIT CAPACITY FACTOR (USING MOC NET) 54.0% 90 27 58.4%

) 22. UNIT CAPACITY FACTOP (USING DER NET) 51.R% To.at 54.4% gy

23. UNIT FORCEO OUTAGE RATE 0.0% 0.0% 15.7%

24. SHUTOOWNS SCHEDULE 0 OVER NEXT 6 MONTHSITYPE,0 ATE, C OURATION OF EACHl:

4P gp

25. IF SHUT 00WN AT END OF REPORT PERIO0e ESTIMATED DATE OF STARTUP 4D dp dP ED 9

ep e

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AVERAGE 3AILY POWERt"WT1

• O DAY 2

1 211 21 64.81 6_, 2 211 75 64.45 3_ 211.54 64.12 _

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4 212.21 63 96 -

5 87.67 25.68 (i

0.0 0.0 6

' 7 0.0 00 0.0 0.0

, O 8 0.0 0.0 l' 9 0.0 0.0

,: 10 0.0 0.0 NO 11 12 0.0 0.0 J 13 0.0 0.0 l 0.0 iO 14 0.0 0.0 0.0

15 16 0.0 p.0 29.42 6.62 t C 17 18 175.17 53.61

) 61.97 19 203.71 210.67 63.75 O 20 63.97 21 210.87 22 214.00 64.70 65.43 0 23 215.92 24 217.83 65.81 j

> _25 ~216.21 65.56 26 -316.50 65.42 O 716.12 65 31 27 28 214.22 64.97 29 214.96 64 86 C 214 42 64.79 30 ..

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Refuelina Information Request

1. Facility name: Big Rock Point Plant ,

2. Scheduled date for next refueling shutdown: August 1985

3. Scheduled date for restart foi owing 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.

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)?

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 methoda significant changes in fuel design new operating 3

l procedures:

l 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 assuring the present license capacity: 1993 BP0385-0458A-BT01

nsessenesesena a esILine e STAT 4S 8P a aes T Es a $PtMT PWtL STeeAtE C4PABILITT e etACTSRS e (el l seausseessenes CORE Silt PttSE117 AUTW. ut. $p seestatius CaraCTTY (MS. Of STOGAGE PSOL CAP. gp Ptmetas argutST (b)

FACIL ITY ASSEMSLIESB (Futt ASSE.MalltS)Staats ASSOsBLIts CAPACITY APPseves esseesse saeasseems (me, estatatus op AS mETT etPUtt ti!LL SILL PttSElff samassaanseeses essaansase emesseemas$2McLIESS eessoas (us. OF AS$aetIES) SCNet. SA TEAdfM. CAP ACITY Ste toCE PetNT t 44 446 essaammenessasses esmessessee aussessameseemase

- m teenseS Fttav t 764 547 t 17 2 - 269 meS 2010 ASenAt3 FERWT 2 764 1844 teos 34 F 8 449 03-83 Semer$ FERRY 3 F44 5475 9764 s t regel 2S82 EVS 1985 teve$sstCE 9 See (93 IS4(e) 9793 E/ S 9989 BeutriastCE 2 Se t to tPtee496 3mm 23 4 toertee Set ted 2298 94-81 1986 COOPEA STAf!Olt Sea 2344 985 II/ S e946 DAE SDEN e 44 4 6F2 isa t 49-4S SNES9tM 2 221 49 1996 F24 24S9(c) 2414 (g) N/ S 1998 DaESDEN $ F24 994(s) 429(s3 eVS 1985 DUAer ARe0L3 34a 2890 174 EV S FITif alt 1CE Se t 2244 1474 82-89 GAA40 GULF e 4 14 3424 1998 MA TCM i 42-45 199L See 5821 940 MATCM 2 Se t 2TSS 244: 88-89 peUM90L97 BAT 1284 1444 9999 97 2 447 ISS 94-41 1999 LA CROSSE F2 444 2 34 IV S 20F

' ' [9C E+ d LASALLt t L ASAllt 2 233 03-45 1992

- MILL ST0ut t $44 2144 1344 MONTICtL L O 444 124; 948 1R/S mint MIL E PolNT t stSF stee 1998 S32 2774 1244 42-45 1991 OYSTER CREER 9 Se t 1890 IS32 1734 03-84 PEACM 80Tf 0M 2 1515 429 1996 764 241a tie s 1225 E#1 t947

1. 455 Er8 1998 s

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A Esport Ported JAN 1943 9 PAGE 3-4

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y usammessenssam 0P SPENT PWEL $TSRAeE CAPABIL1YY u

a 80!Line a STATU$

seAf te a AtMAINIl0G CAPACITY (b) e REAC10RS e (a) WO. DF $$ Ptuptuo attutST NEIT REFUEL IIILL FILL PRESENT PRESENT ALffM. APPROVEt AUTN CAPACITT masunnenamenna (so. OF CORE SIZE STORA0f STeatsPOOL CAP. ASSEMBLIES REMAINING CAPACITY (no. OF ASSEMBLIJS3 FACILITY ASSEMBLIES) (FUEL ASSEMBLIES) mammassuaananamma

'.' ' namammes asseassene samassmassumana suunannues semammuseassamana 1999

.s' 04-85 1292 e6e4 R/S 1999 764 2814 442(a) 2003 PEACM DOTTOM S 2520 1924 IL/ S PILORIM e 544 1758 9927 IV S 2005 724 5457 4UAB CITits t 724 3897 412 5489 $2*85 1997 GUAD CITIES 2 2848 9 2844

$U$tVEMANNA 9 764 E#S 1992 SUSOUEMA18mA 2 2008 9974 824 WERMouf YANKEE 9 $44 teAsniN010m NUCLEARE INDEPENDENT SPENT Futt STORAGE IN;f ALLATIowS(h) tete MTU(j)

FSt MTU(j) St? 389 MTU(j)

MonatS OPERATIONS 250 MTU 17e NTU 80 MTU NFS(t) t/3 of e PWR core end t/4 of a BWR core le off-leeded.

(a) At each refueltne estage specentestely (b) Sees of these daise have been adjusted by staff ooeveptlene. IVS = Ilot Sche &1ed (c)

(d) Plent tnot Thle o the total for teth la ceaserstat wette.

operetten.

Brune st et .

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Some spent fuel stored atAuttero ged a tetel 2772 SMR and for 1232 st o r Pl8tesseeblies e go. for both peele. i, (g) Robineen 2 eseeablies betag shipped to BewamenetI MTU

• 2 PWE asseabitos er S BNR esse.htles.

th) Cepeti.ty l e la, metric tens o.f urentwe8 (i) % ion e, euet e nt <. .

( 3 Rected for 70s MyTU

( 3 Reserved.

(1) Thle le the stetten total.

Installed tapetity le less then that autherlaed (a) e out%rlaed to eccoot Oconee feet esse htles. P ACE 5-S (a) Mc Gui r e e, pert' Period J All 1983 e

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l Consumem fggg( D P Hoffman Plant Superintendsnt Big Rock Point Nuclear Plant, Box 591, Route 3, Charlevols, MI 49720 May 3, 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 April 1 through April 30, 1985. Please note the indicated error in the " Status of Spent Fuel Storage Capability" reported for January, 1985.

t D P Hoffma Plant Superintendent DPH:llb Enclosures cc: DEVanFarowe, Departirent 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, P24-117B DJVandeWalle, P24-115 WGFogg, P24-610 File 9

'f/

. OC0585-0544A-BT01

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