ML20135F236

Monthly Operating Rept for Feb 1997 for Big Rock Nuclear Plant

ML20135F236
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	02/28/1997
From:	Jeanne Johnston, Shields K CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703110286
Download: ML20135F236 (6)

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l Consumers Power powEmNs nlKHNEAN5 PROGRES5 I

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g March 6,1997 Nuclear Regulatory Commission Document Control Desk j Washington, DC 20555

Dear Sir:

i Enclosed plesse find the statistical data for the Big Rock Point Nuclear Plant covering the period of February 1,1997 through February 28,1997.

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.i j Sincerely,

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i I sm .

p i K J Ghields j Reactor Engineer 3

Enclosures f/

cc: Administrator Region Ill, Nuclear Regulatory Commission DRHahn, Department of Enviromental Quality

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! JRPadgett, Michigan Public Service Commission 1

RAben, Michigan Department of Labor MPCass, American Nuclear Insures O 3/

Fyost, Research Services Utility Data institute RAFenech, Palisades

, SMMcIntyre, P26-204 GCWithrow, Big Rock Point NRC Resident inspector, Big Rock Point

. Document Control, Big Rock Point,740*22*35*10 i File 9703110286 970228 PDR ADOCK 05000155 R PDR l$l{EEElEllElfE[Ellll A G5 ENE72GYCOMPANY

communersaamrgy NUCLEAR OPERATIONS DEPARTMENT

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i Unit Shutdown and Power Reductior.s l

i Report Month Docket Number UnP Date Completed by Telephone Fetwuary,1997 56-150 Big Rock Point Plant March 4,1997 JR Johnston (616)547 4 223 i

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> Method of Shuthng Duration Down Licensee Event Systery C- J Code7 i 2

Number Date Type, (Hours) Reason Reactor Report Number Code Cause and Corrective Act6on To Prevent Recurrence i

9647 12/07/96 F 37.5 Hrs A 3 On 12/07/96 at 12:10; An automatic voltage control circuit in Thru the exciter failed, which ===r8 a protective relay to "open" 1 0;,02/97 and trip the turtune ofMine; thus caussng an automatic reactor scram on high power. Alter repairs were completed and

attemptmg to return the unit to service; high turtune vitwation was noticed. The turtune was placed on turning gear for investigation repairs. The unit returned to normal service on 02/02/97 at 13

27; aRer repairs were completed.

(Total outage hours: 1,369.3) f i

1 3 Method: M G = Instructions for 1 p,p g 2%.

S o Scheduled A = Equipment FaBure (Explain) 1 = Mawal Pseparation of Data Entry Sheets B = Maintenance of Test 2 = Manual Scram For Liconese Event Report (LER)

C = Refueling 3 = Automatic Scram Flie (NUREG -0161)

- D = Regulatory Restriction 4 = Other (Fwpa=hi )

E = Regulatory M 5 Exhibit 1 = Same Source

. F = Administrative

, . G = Operational Error (rupan=t)

H = Other (Emplain) ram mes w y , , . . ,, g , ,.v.g., , , ,_.~.u- , , . . , . . , - , . , . . , . , . , , , . _ , _ , , y , y ...y-.-,. , , . , _ n, ,, . , . , , , . ..,m._, _

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. I 1 STATS VERSION 97.001: EA-B-STATS-97-01 02/06/97 RUNTIME=03/06/97 03:53:12 Page 4 of 9 GREYB00K OPERATING DATA REPORT DOCKET NO. 50-155 DATE: 3/ 6 / 97

{ BY: JR JOHNSTON

CPERATING STATUS PHONE

616-547-8223

1. UNIT NAME

BIG ROCK POINT NUCLEAR PLANT NOTES:

2. REPORTING PERIOD: 2 / 97

' 240

3. LICENSED THERMAL POWER (MWT):

4. NAMEPLATE RATING (GROSS MWE): 75

5. DESIGN ELECTRICAL RATING (NET MWE): 72 t

! 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 71.0

. 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 67.0

8. IF CHANGES OCCLR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT, GIVE REASONS:

t l l 1 9. POWER LEVEL TO WHICH RESTRICTED.IF ANY (NET MWE):

i 10. REASONS FOR RESTRICTIONS IF ANY:

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THIS MONTH YEAR-TO-DATE CUMULATIVE i

11. HOURS IN REPORTING PERIOD 672.0 1416.0 297379.0

) 12. NUMBER OF HOURS REACTOR WAS CRITICAL E51.0 651.0 216354.6

13. REACTOR RESERVE SHUTDOWN H0l'AS 0.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 634.5 634.5 213011.7 e

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

! 16. GROSS THERMm. ENERGY GENERATED (MWH) 123256.0 123256.0 41297517.0

[ 17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 39702.0 39702.0 13125371.0

16. NET ELECTRICAL ENERGY GENERATED (MWH) 37545.1 37545.1 12418806.4

19. UNIT SERVICE FACTOR 94.4% 44.8% 71.6%

j 20. UNIT AVAILABILITY FACTOR 94.4% 44.8% 71.6%

21. UNIT CAPACITY FACTOR (USING MDC NET) 83.4% 39.6% 62.1%

22. UNIT CAPACITY FACTOR (USING DER NET) 77.6% 36.8% 58.0%

23. UNIT FORCED OUTAGE RATE 5.6% 55.2%' 11.3%

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24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, & DURATION OF EACH): Refueling, August, 1997, 60 Days.

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'25. IF SHUT COWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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________._______m ...m_ _ _ . _ _ _ . . . _ . _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . . . _ _ _ _ _ _ _ _ _ , -_ , - -

1 STATS VERSICZ 97.001; EA-B-STATS-97-01 02/06/97 RUNTIME-03/06/97 06:53:12 P:ge 2 of 9 DAY AVERAGE DAILY POWER (MWT) (MWEN) ( 2/97) - CYCLE 29 1 0.00 0.00 2 25.00 3.02 3 88.88 25.84 4 129.83 40.67 5 138.88 43.10 6 173.25 53.55 7 177.13 54.95 8 178.33 55.24 9 177.54 54.99 10 179.58 55.63 11 186.54 57.63 12 184.46 56.97 13 183.83 56.63 14 191.46 58.36 15 202.54 62.47 16 221.92 67.37 17 227.54 68.96 18 226.29 68.69 19 228.08 69.15 20 226.92 68.86 21 225.38 68.37 22 223.71 68.02 23 223.08 67.57 24 221.46 67.14 25 223.75 67.92 26 223.58 67.73 27 222.96 67.70 28 223.75 67.86 D

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Refuelina information Reevest a .

1. Facility Name:

Big Rock Point Plant

2. Scheduled date for next refueling shutdown: I 2

2 August,1997.

i 3. Scheduled date for restart following shutdown:

60 Day Duration. -

4. Will refueling or resumption of operation thereafter require a technical specification change or j other license amendment?

i No.

l 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) ?

l To be performed once core loading determined for cycle 30.

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4 no review has taken place, when is it scheduled?

5. Scheduled date(s) for submittal cf proposed licensing action and supporting information: I

N/A.

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 j design new oparating procedures:

l None.

7. Number of fuelassemblies in:

i Core = 84.

1 Spent Fuel Pool Storage = 358.

New Fuel Storage = 22.

8. Present licensed spent fuel pool storage capacity:

J M1 j Size of any increase in licensed storage capacity that has been requested or planned (in number of fuel assemblies):

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9. Projected date of last refueling that can be discharged to spent fuel pool assuming the present license capacity:

Last total core off load 1996.

Last refueling 1999.

March 4,1997

4 FORM 16.3.H

, Operating Status Report - Nuclear Regulatory Commission Prepared by: M74L Date: M4&[d, UN b V (/ r R viewed by: k - #J fn/t Date: 3 / ') b (Reactor Endneer or Alternate)~

C py to be sent to the following by the seventh day of each month:

Nuclear Regulatory Commission 4 Document Control Desk l Washington,DC 20555 l J

)

Administrator

R:gion 141 - USNRC l 801 Warrenville Road j Lisle,IL 60532-4351 i

DR Hahn Department of Enviromental Quality

3500 North Logan Lansing, MI 48906 i JR Padgett

Michigan Public Service Commission l PO Box 30221 Lansing, MI 48909 1

Robert Aben, Assistant Chief Bureau of Construction Codes

j. Michigan Department of Labor 3 7150 Harris Drive, Box 30015 i Lansing, MI 48909 j American NuclearInsurers 4 Att: MP Cass

Town Center, Suite 300S  !

a 29 South Main Street West Hartford, CT 06107-2445 Fred Yost Director, Research Services j Utility Data institute

! - 1700 K Street, N.W.

! Suite 400 Washington, DC 20006 Routing Copy: >

! RA Fenech, Palisades Plant

! SM McIntyre, P26 204 CC Withrow, Big Rock Point Plant l NRC Resident inspector, Big Rock Point Plant

{ Document Control Center, Big Rock Point Plant j DCC 740*22*35*10 l (740*22*10'04) Cross Reference 16.3.3-17