ML20140C898

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Monthly Operating Rept for May 1997 for Big Rock Nuclear Power Plant
ML20140C898
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 05/31/1997
From: Jeanne Johnston, Shields K
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9706100120
Download: ML20140C898 (6)


Text

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l June 3,1997 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Dear Sin Enclosed please find the statist; cal data for the Big Rock Point Nuclear Plant covering the period i of May 1,1997 through May 31,1997. j Sincerely, K J Shields Reactor Engineer  !

Enclosures cc: Administrator Region Ill, Nuclear Regulatory Commission DR Hahn, Depariment of Enviromental Quality JR Padgett, Michigan Public Service Commission R Aben, Michigan Department of Labor MP Cass, American NuclearInsures B Lewis, McGraw-Hill,Inc. #

SM McIntyre, P26-201 fg KP Powers, Big Rock Point / D l GC Withrow, Big Rock Point #

NRC Resident inspector, Big Rock Point Document Control, Big Rock Point,740*22*15*10 File 9706100120 970531 * * * * * * *

  • PDR ADOCK 05000155 R PDR ,,j A CAG ENE72GYCOMPANY

._ _ _ _ - . _ _ _ - . ._ _ _ _ . _ _.-_._._ _ _ _ . _ _ . _ _ _ . - - _ . ~ . _ _ - . . _ . _ _ _ _ . .

,. FORM 16.3.H Operating Status Report - Nuclear Regulatory Commission

Prepared by
# Date: 7ade k /9k2
R
viewed b Date: b D

(Reactor Er%lneer or Altemate)

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

l Nuclear Regulatory Commission Robert Aben, Assistant Chief l Document Control Desk Bureau of Construction Codes

, Washington,DC 20555 Michigan Department of Labor 7150 Harris Drive, Box 30015 Lansing,MI 48909 4 Administrator American NuclearInsurers

! Region lli- USNRC Att: MP Cass

, 801 Warrenville Road Town Center, Suite 300S I Lisle,IL 60532 4351 29 South Main Street i West Hartford, CT 06107-2445 4

DR Hahn Barbara Lewis j Department of Enviromental Gua!ity McGraw-Hill,Inc.

3500 North Logan 1200 G Street, N.W.

4 Lansing, MI 48906 Suite 1100

Washington,DC 20005 I JR Padgett i Michigan Public Service Commission

! PO Box 30221

{ Lansing, MI 48909

! Routing Copy:

', SM McIntyre, P26-201 4

KP Powers, Big Rock Point Plant CC Withrow, Big Rock Point Plant NRC Resident inspector, Big Rock Point Plant Document Control Center, Big Rock Point Plant DCC 740*22*35*10 (740*22*10*04) Cross Reference 16.3.3-17

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causssssmarsgesygy .

NUCLEAR OPERATIONS DEPARTMENT >

Unit Shutdown and Power Reductions Report Month Docket Number Unit Date Completed by Telephone May,1997 56-160 Big Rock Point Plant June 3.1997 JR Johnston (614) 547 4 223 ,

Method of Shuttmg Duration Down Licensee Event Systery Cy Number Date Type l

(Hours) Reason 2 p ,,,,,,3 Report Number Code Code Cause and Corrective Action To Pnivent Recurrence 97 01 03/02/97 F 113.5 Hrs A 1, 2 On 034248 at 22:32; The unit was removed from service to

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Thru .. , " _ and repair leakage from MO-7071 and/or VPl403 on 0646/97 the poet incedent system. ARer the unit was removed from service, the reactor was manually scrammed to fbily insert the remaining withdrawn control rod drives. Alter repairs were complete, the reactor was taken critical on 04/20/97 and ready ,

to place the unit on line when the lir2 Reactor recirc pump inner seat failed. The turbine was placed on tuming gear and the reactor was manually cerammed (planned) to fully insert the remainmg withdrawn control rod drives. On 04/28/97 at 05:26; the 116 OCB tripped while trying to place the unit on line.

During "... _ "c" c. the unit was keep at 3000 RPMs until 04/29/97 at 10:59 when the turbine was placed on tummg gear and at 17:14 the reactor was manually scrammed (planned) to fully insert the remaining withdrawn control rod drives. On 06/05/97 at 18:32; The unit retumed to norrnal servicu after aR repairs wre completed. On 05/27/97 at 17:40; The unit ,

reached the "All Rods - AN Out" mode and started cost down  !

towards the 1997 refuelmg outage.

(Total outage hours: 1,530.9)

L I

E i

1 F o Forced 2 Reason: Method: kxhiNt G = Instructions for l

S = Scheduled A = Equipment Failure (Explain) i = Manual Pieparation of Data Entry Sheets f B = Maintenance of Test 2 = Manual Scram For t.icensee Event Report (LER)

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

D = Regulatory Restriction 4 = Other (Explain)  :

E = Regu: story Restnctiori 5 Exhibit 1 = Same Source F = Administrative G = Operational Error (Explain)

H = Other (Explain)

Form 3156 247

1 STATS VER* ION 97.001: EA-8-STATS-97-01 02/06/97 RE]TIMEo06/03/97 07:52:26 Page 4 of 9 b

GREY 800K OPERATING DATA REPORT

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DOCKET NO. 50-155 DATE: 6/ 3 / 97 BY: JR JOHNSTON OPERATING STATUS PHONE: 616-547-8223

1. UNIT NAME: BIG ROCK POINT NUCLEAR PLANT NOTES: -
2. REPORTING PERIOD: 5/97
3. LICENSED THERMAL POWER (MWT): 240
4. NAMEPLATE RATING (GROSS MWE): 75

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5. DESIGN ELECTRICAL RATING (NET MWE): 72
6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 71.0
7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 67.0
8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS 3 THRU 7) SINCE LAST REPORT. GIVE REASONS:
9. POWER LEVEL TO WHICH RESTRICTED IF ANY (NET MWE):
10. REASONS FOR RESTRICTIONS IF ANY:

THIS MONTH YEAR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744.0 3623.0 299586.0
12. NUMBER OF HOURS REACTDR WAS CRITICAL 644.5 1398.5 217102.1
13. REACTDR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
14. HOURS GENERATDR ON-LINE 630.5 1311.5 213688.7
15. UNIT RESERVE SHUTDOVN HOURS 0.0 0.0 0.0
16. GROSS THERMAL ENERGY GENERATED (MVH) 128084.0 262004.0 41436265.0
17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 41016.0 83734.0 13169403.0
18. NET ELECTRICAL ENERGY GENERATED (MWH) 38881.4 79280.9 12460542.2
19. UNIT SERVICE FACTOR 84.7% 36.2% 71.3%
20. UNIT AVAILABILITY FACTOR 84.7% 36.2% 71.3%
21. UNIT CAPACITY FACTOR (USING MDC NET) 78.0% 32.7% 61.8%
22. UNIT CAPACITY FACTOR (USING DER NET) 72.6% 30.4% 57.8%
23. UNIT FORCED OUTAGE RATE 15.3% 63.8% 12.1%
24. SHUTD0VNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. & DURATION OF EACH): Refueling, August 31, 1997 60 days.
25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

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1 STATS VERSIC 97.001: EA-8-STATS-97-01 02/06/97 RUNTIME=06/03/97 07:52:26 Ptge 2 of 9 DAY AVERAGE DAILY POWER (MWT) (MWEN) ( 5/97) - CYCLE 29 ,

1 0.00 0.00 2 0.00 0.00 .

3 0.00 0.00 4 0.00 0.00 5 14.92 1.05

  • 6 68.42 19.79 7 74.67 21.78 8 149.46 46.25 9 209.67 63.95 10 219.21 66.77 11 217.92 66.45 12 217.79 66.28 13 216.54 66.04 14 217.88 66.29 15 221.29 67.10 16 221.92 67.38 17 220.79 67.43 18 222.67 67.52 19 222.54 67.55 20 221.83 67.44 21 221.75 67.27 ,

22 219.96 66.86 23 218.83 66.71 24 219.13 66.33 25 218.92 66.71 26 217.88 66.63 27 218.92 66.43 28 217.58 66.39 29 216.71 66.01 30 216.17 65.71 31 214.50 15.43

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, ,e Refuelina information Reauest
1. Facility Name:

i Big Rock Point Plant j f 2. Scheduled date for next refueling shutdown:

August 31,1997.
3. Scheduled date for restart following shutdown:

60 Day Duration.

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4. Will refueling or resumption of operation thereafter require a technical specification change or )

other license amendment?

. No.

i 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) ?

To be perfom ed once core loading determined for cycle 30.

e if no review has taken place, when is it scheduled? l

5. Scheduled date(s) for submittal of proposed licensing action and supporting information: 1 N/A.

i ,

6. Important licensing considerations associated with refueling, eg. new or different fuel dasign l

} or supplier, unreviewed design or performance analysis methods, significant changes in fuel j design new operating procedures:

l None.

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7. Number of fuel assemblies in:

Core = 84.

Spent Fuel Pool Storage = 358.

New Fuel Storage = 22.

8. Present licensed spent fuel pool storage capacity:

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

0 .

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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.

May 1,1997