ML20059K978

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Monthly Operating Rept for Aug 1990 for Arkansas Nuclear One Unit 2.W/900917 Ltr
ML20059K978
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 08/31/1990
From: James Fisicaro, Whitt M
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
2CAN099006, 2CAN99006, NUDOCS 9009260002
Download: ML20059K978 (7)
v • d • e


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- RussenvWe,.AR 72801 Te; 5019N 3100 -

0 September 17, 1990

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-U.-:S. Nuclear. Regulatory Commission  ;)

' Document Control Desk ol

, Mail-Stop P1-137; 2:' -Washington,.D.C.. 20555-

SUBJECT:

. Arkansas: Nuclear One --Unit 2 3 Docket No. 50-368

' License No. NPF-6 Monthly Operating Report e

jc. . Gentlemen: , 'j -

.i Tho' Arkansas' Nuclear One

. Unit 2. Monthly Operating . Report for . :1

. August, 1990 is; attached.

-Veryftruly yours.,.

, )Mf.&

James J. 'isicato ,

Manager, Licensing .

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JJF/SAB/1r

. Attachment.

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, l 9009260002,90'0031- '

. PDR! ; ADOCK :05000368 '

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4 U. S. NRC-- ,

. Ssptcabar. 17, 1990 lp ,?';l: L} l ' ' "'  ?

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'll: - cc: Mr. Robert'D. Martin i

Regional Administrator '! '

U. S.-Noclear Regulatory Commission t.

, Region IV _

F 611-Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

, -NRC. Senior Resident Inspescor

.!i Arkansas Nuclear One - ANO-1 & 2

-Number.1, Nuclear; Plant Road, fi Russellville, AR 72801 l-1 f# Hr. Thomas W. Alexion '

NRR Project Manager, Region IV/ANO-1 ,

U. S. Nuclear Regulatory Commission NRR' Mail Stop 11-B s One White Flint: North  :

10 11555 Rockville Pike

-Rockville' Maryland _20852

, 4 6 Mr. Chester;Poslusny g NRR Project Manager, Region IV/ANO-2 U. S.1 Nuclear. Regulatory Commission '

NRR Mail Stop 11-B-19 l g; . ,

One White Flint North

"" 11555-Rockville Pike

Rockville, Maryland 20852 k

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  • C L OPERATING DATA REPORT D

vg DOCKET NO: _ 10-368 DATE: August. 1990 COMPLETED BY: M. S. Whitt TELEP110NE: C5011 964-3743 OPERATING STATUS m 1 ~. Unit Names' Arkansas Nuclear One - Unit 2

-2. Reporting Period:: _ August 1-31. 1990

3. Licensed Thermal Power (MWt): 2.815 4.- Nameplate Rating (Gross MWo): 942.57
5 .~ Design Electrical Rating-(Net MWe):: 912
6. Maximum Dependable Capacity (Gross-HWe): 897 7., -Maximum Dependable Capacity (Not MWe): 358
8. . If. Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted. If Any (Net MWe): None 10.- Reasons For Restrictions. .If Any: None j

s MONTH YR-TO-DAIE CUMULATVE 11 3 llours in Reporting Period .... 744.0 5,831.0 -91,463.071 12.L. Number of Ilours Reactor was C r i t ica l ' . . . . . . . . . . . . . . . . . . . . . . 716.3 5,338.8 . 67,703.1,

,13.- Reactor Reserve Shutdown llours ........................ 0.0 0.0 1,430.1 11 4 . Ilours Generator On-Line ...... 711.7 5,307.8 66,088.5 2

' 15. Unit Reserve Shutdown liours .. 0.0 0.0 75.0= j z l6. Gross Thermal Energy' Generated

.(HWII) ........................ 1,984,154.0 14,463,562.0 172,672,092.0 j L\ <

17., Gross Electrical Energy L e n e r a t ed = ( MWII) . . . . . . . . . . . . . . 650,630.0 4,764,380.0 56,721,856.0j

=18. Net-Electrical Energy

. G enera t ed > (MWil) . . . . . . . . . . . . . . 620,359.0 4,540,464.0 53,917,434.0]

19. Unit Service factor .......... 95.7 91.0 72.3 a
20. Unit: Availability Factor ..... 95.7 91. 72.3~j

~ 21. Unit Capacity Factor. .

. -(Using MDC Not) .............. 97.2 90.8 68.7- l

22. Unit Capacity Factor . .l (Using DER Not) .............. 91.4' 85.4 64.64
23. Unit Forced Outage Rate ...... 4.3 5.3 13.2 ,

. 24 . - Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of- l Each): D8 Refueling Outage is scheduled to begin February. - 1991; - 1

_and ti- heduled date for restart is April,1991.

-25. If Shu , wn At End 'of Report Period. Estimated Date of l

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Startup l

' , 26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION  !

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AVERAGE D'.ILY-UNIT. POWER LEVEL DOCKET.NO: 50-368-UNIT: Two DATE: . August. 1990 COMPLETED BY: M. S. Whitt TELEPil0NE: (501F 964-3743 MONTH Aunust. 1990 DAY ' AVERAGE DAILY POWER LEVEL-~

(MWe-Net) f 1 ............. 884-ji 2 ............. :882

.3 ............. 880 G' 41...-.......... 881 5 ............. 882

'6 ............. 888 7.-............. 891

" '81.............- 891 J. 9 ............. 887 10 ............ '885-

,11:............ 883 1 -121............. 884 13~............ 882

-144~............ 883 15 .......'..... 882

_16_-............ 880 17 ............ 878-18...........'.. 879:

19c........... 880 20 ............ 880~

21 ............  : 55' 22.....'.'......- 261 23 .........'.... 874 E '24 ....'........ 875

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'25 ............ 2876

.26 ............ -868

>, 27c............ 871:

28 ..a......... 873-

,' '29'............ 872 30'............. 881 31*............ 883 e -

AVGSt. -834-

. INSTRUCTION O.

On this' format, list the average daily unit power level in MWe-Net for each day in reporting month. Compute to the nearest whole megawatt.

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'NRC MONTIILY 0PERATING REPORT-g OPERATING

SUMMARY

h AUGUST, 1990 .

UNIT TWO )

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.The unit began the month operating at 100% full power (FP). -

On-the twenty-first at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, tho' reactor was. manually tripped due to- ,

a solenoid valve. failure causing "B" Main Steam isolation Valve (MSIV)=to [

~ close. After replacing the solenoid valve, the unit was placed back '{

on-line on the twenty-second.at 1031 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.922955e-4 months <br />. ,

Y The unit attained 100% power.on the twenty-second at 2435 hours0.0282 days <br />0.676 hours <br />0.00403 weeks <br />9.265175e-4 months <br />, and operated at this level through the end of the month. l

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UNIT SHUTDOWNS AND POWER REDUCTIONS -

REPORT FOR AUGUST, 1990 DOCKET NO.- 368 UNIT NAME- ~Two DATE Auaust; 1990 COMPLETED BY M. S. Whitt-

-TELEPHONE 501-964-3743 Method of Licensee Cause & Corrective Shutting Event ~ . System Component Action to Duration Code' Prevent Recurrangg Type 2 (Hours) Reason

  • Down Reactor 8 ' Report # _ Code' h Date 2-90-019 SB PSV The reactor was manually.

F 32.3- 'A 2-

'90-05 900821 -tripped'after the "B" Main Steam Isolation Valve'(MSIV) closed due to a failure in a solenoid. valve. 'The '

solenoid valve was replaced; further investigation is being-conducted to determine.

the root cause of the failure.

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Reason: Method: Exhibit G --Instructions l F: Forced. for' Preparation of Data -

S: Scheduled A-Equipment' Failure (Explain) 1-Manual

~B-Maintenan'ec or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File-(NUREG-D-Regulatory Restriction 4-Continuation 1022)

-E-Operator Training & 5-Load Reduction 5 License Examination 9-Other-

'F-AdministrativeJ Exhibit I - Same Source

- G-Operational Error (Explain)

H-Other (Explain) iI

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  • DATE: ~Aunurt. 1990 t

D REFUELING INFORMATION-4 

         ,                                                       1..                   Name of. facility: Arkansas Nuclear One - Unit 2 2.-                    Scheduled date for next refueling shutdown. February 1991
   <                                                                                     (Beninnine of Cycle 8 criticality was 11/18/891:

[ 23. Scheduled date for restart following refueling._Aeri'.'1991

4. Will refueling or resumption of operation thereafter require a .

technical specification- change or other license amendment? 11f answer is yes, what, in general, will thers be? If answer ~is no, has the' i reload-fuel design and core configuration been reviewed by'your plant Safety Review Committee to determine whether;any unreviewed safety questions are associated with the core reload.(Ref. 10:CFR Section 50.59)? None Eroected. Reload fuel desinn is in ororress. 5 .1 Scheduled date(s) for submitting proposed licensing. action and ') supporting information. None Reauired

6. ;Important licensing considerations associated with refueling, e.g., new i or different fuel design or supplier, unreviewed design or-performance .;

ir analysis methods, significant changes in fuel design, new operating --! procedures. To ob'tain the cresentiv'olanned evele 8 lennth of 420 EFPD. It will-be-necessary to raise the current ocak rod burnur limits. A report justifyino an increase was submitted in July. 1989.

7. The number of fuel assemblies (a) in the core and (b)Jin the spent fuel
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storage pool, a) 177 b) 421 .j i 8.- .The present licensed spent fuel pool' storage' capacity and the. size of. .; any increase in licensed storage capacity that has been requested or is , 

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planned,~1n number of fuel assemblics. present 1988 increase size by 0  ;

9. The projected date-of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: 1996 (Loss of fu11 core offload capability) f ' , 8 _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ ._m _}}

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