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

-

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 Comgde t

I 2

4 Number Date Type (Hours)

Reeson Reactor Report Number Code Co Cause and Corrective Action To Prevent Recurrence 04/05 S

292.7 A

1 SF VALVEX Scheduled outage for repair of RDS s a n va ves to enable perfomance

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

8507170279 850430 PDR ADOCK 0500 5

R I

2 F = Forced Reason:

3 4

Method:

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 SExhibit 1 = Same Source F = Administrative 93 G = Operational Error (Explain)

H = Other (Explain)

Form 3156 1-82

OCCKET NO. 50-155 OATE:

5 / 1 / G 5' ~ ~ ' ~ ~

~~~~~ ~~

4.

GY LINDA DALCH

()

OPECATING STATUS PHONFs 616-547-6537, EXT 180

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

GF

[

eD 1

li

• O DAY AVERAGE 3AILY POWERt"WT1

( M sE*ll

( 4/35) 2 1

211 21 64.81 6_,

2 211 75 64.45 3_

211.54 64.12

{

4 212.21 63 96 (i

5 87.67 25.68 6

0.0 0.0 7

0.0 00

, O 8

0.0 0.0 l'

9 0.0 0.0 10 0.0 0.0 NO 11 0.0 0.0 J

12 0.0 0.0 l

13 0.0 0.0 iO 14 0.0 0.0 15 0.0 0.0 16 0.0 p.0 t C 17 29.42 6.62

)

18 175.17 53.61 19 203.71 61.97 O

20 210.67 63.75 21 210.87 63.97 22 214.00 64.70 0

23 215.92 65.43 24 217.83 65.81 j

~216.21 65.56

_25 O

26

-316.50 65.42 27 716.12 65 31 28 214.22 64.97 C

29 214.96 64 86 30 214 42 64.79 C

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1 5O 1

4 (2

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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

$PtMT PWtL STeeAtE C4PABILITT a

aes T Es a 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) ASSOsBLIts estatatus CAPACITY APPseves mETT etPUtt ti!LL SILL PttSElff Staats (me, op AS esseesse saeasseems samassaanseeses essaansase emesseemas$2McLIESS (us. OF AS$aetIES) SCNet. SA TEAdfM. CAP ACITY eessoas essaammenessasses esmessessee aussessameseemase Ste toCE PetNT t 44 446 17 2

- 269

- m teenseS Fttav t 764 547 t 1844 teos meS 2010 ASenAt3 FERWT 2 764 34 F 8 449 03-83 Semer$ FERRY 3 F44 5475 9764 IS4(e) 9793 E/ S 9989 s t regel 2S82 EVS 1985 teve$sstCE 9 See (93 to tPtee496 3mm 23 4 94-81 1986 BeutriastCE 2 Se t toertee Set ted 2298 COOPEA STAf!Olt Sea 2344 985 isa t II/ S e946 DAE SDEN e 44 4 6F2 221 49 N/ S 1998 49-4S 1996 SNES9tM 2 F24 24S9(c) 2414 (g) 994(s) 429(s3 eVS 1985 DaESDEN $

F24 DUAer ARe0L3 34a 2890 174 1474 EV S FITif alt 1CE Se t 2244 4 14 3424 42-45 199L 82-89 1998 GAA40 GULF e MA TCM i See 5821 940 244:

MATCM 2 Se t 2TSS 1284 88-89 9999 peUM90L97 BAT 97 2 447 ISS 2 34 1444 94-41 1999 LA CROSSE F2 444 20F 233 03-45 1992 LASALLt t IV S

' ' [9 E+

L ASAllt 2 C

d MILL ST0ut t

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

1. 455 Er8 1998 s

A y

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A 9

Esport Ported JAN 1943 PAGE 3-4 M.

. _ ~. _

p-

_ g y

y u

80!Line a STATU$

0P SPENT PWEL

$TSRAeE CAPABIL1YY usammessenssam AtMAINIl0G CAPACITY (b) a seAf te a

e REAC10RS e (a)

$$ Ptuptuo attutST NEIT REFUEL IIILL FILL PRESENT PRESENT ALffM.

WO. DF APPROVEt AUTN CAPACITT masunnenamenna CORE SIZE STORA0f POOL CAP. ASSEMBLIES REMAINING CAPACITY (no. OF ASSEMBLIJS3 (so. OF FACILITY ASSEMBLIES) (FUEL ASSEMBLIES)

STeats mammassuaananamma namammes asseassene samassmassumana suunannues semammuseassamana 04-85 1999

.s' PEACM DOTTOM S 764 2814 1292 e6e4 R/S 1999 PILORIM e 544 2520 1924 442(a)

IL/ S 2003 4UAB CITits t 724 5457 1758 9927 IV S 2005 GUAD CITIES 2 724 3897 412 5489

$2*85 1997

$U$tVEMANNA 9 764 2848 9

2844 E#S 1992 SUSOUEMA18mA 2 WERMouf YANKEE 9

$44 2008 9974 824 teAsniN010m NUCLEARE INDEPENDENT SPENT Futt STORAGE IN;f ALLATIowS(h)

MonatS OPERATIONS FSt MTU(j) St?

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

At each refueltne estage specentestely (a) Sees of these daise have been adjusted by staff ooeveptlene.

IVS = Ilot Sche &1ed (b)

(c) Thle t o the total for teth wette.

(d) Plent not la ceaserstat operetten.

Brune st et.

(el Some spent fuel stored atAuttero ged a tetel 2772 SMR and 1232 Pl8tesseeblies for both peele.

i, for st o r e go.

(f) Robineen 2 eseeablies betag shipped to BewamenetI MTU

• 2 PWE asseabitos er S BNR esse.htles.

(g)

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

3 Rected for 70s MyTU (i)

(( 3 Reserved.

(1) Thle le the stetten total.

le less then that autherlaed Installed tapetity e out%rlaed to eccoot Oconee feet esse htles.

P ACE 5-S (a)

(a) Mc Gui r e e, pert' Period J All 1983 e

O*

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}