ML20059G866

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Monthly Operating Rept for Aug 1990 for Millstone Nuclear Power Station Unit 3
ML20059G866
Person / Time
Site: Millstone 
Issue date: 08/31/1990
From: Elms A, Scace S
NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-985, NUDOCS 9009130218
Download: ML20059G866 (5)
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General' Offices

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' HARTFORD, CONNECTICUT 06141-0270

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J September 7 990 MP-90-985 Re: 10CFR50.71(a) t U.S. Nuclear Regulatory Commission r

Document Control Desk Washington. D.C. 20555

Reference:

. Facility Operating License No. NPF-49

3 Docket No. 50-423 3

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Dear Sir:

i In accordance with reporting requirements of technical specifications Section 6.9.1.5, the.

l Millstone Nuclear Power Station - Unit 3 Monthly Operatmg Report 90-09 covering opera-tion for the month of August is hereby forwarded.

Very truly yours, j

I NORTHEAST NUCLEAR ENERGY

' COMPANY t

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/ St p n E. Scace Director, Millstone Station j

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r Attachment i

I ec: ' T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 D.H. Jaffe, NRC Project Manager, Millstone Unit No. 3 g(0 i

i 9009130218 900931 PDR ADOCK 05000423

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              • NRC OPERATIM STATUS REPORT COMPLETED BY REACTOR EMINEERIM *******

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1.

DOCKET.... 50 423 OPERATIN STATUS-l 2.

REPORTING PERIOD... AUGUST 1990 CUTAGE + ONLINE NOURS...

0.0.~ + 744.0 m 744.0 l

l 3.- UTILITY CONTACT.................A. L. ELMS 203 444 5308 l

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  • MILLSTONE
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LICENSED THERMA 1. P0ER.........................................

3411.

5.

NAMEPLATE RAT I M ( GROSS MWE )............................... ;.... ' 1,253 MW

  • UNIT 3 6.

DE S I GN E LE CTR I CAL RAT I NG (WET MWE )............................. 1,153.6 '

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MAXIIRBI DEPENDABLE CAPAC I TY ( GROSS MWE )........................ 1,184. 2 8.

MAX IMUM DEPENDA8LE CAPAC I T Y (NET MWE ).......................... 1,13 7. 0

9.. IF CHANGES OCCUR ABOVE SINCE LAST REPORT, REASONS ARE...........

N/A

10. POWER LEVEL TO WHICH RESTRICTED, IF ANT (NET MWE)...............N/A
11. REASON FOR RESTRICTION, IF ANY....N/A

. MONTH YEAR 70 DATE-CtelutATIVE TO DATE.

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12. NOUR$ IN REPORTING PERIOD 744.0 5,831.0 38,207.0
13. NUMBER OF MOURS THE REACTOR WAS CRITICAL 744.0

.4,987.6 30,663.5 i

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14. REACTOR RESERVE SHUTDOWN HOURS 0.0 797.6 1,521.5
15. HOURS GENERATOR ONLINE 744.0 4,878.9 30,043.9

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16. UNIT RESERVE SMUTDOWN HOURS 0.0 0.0-0.0
17. GROSS THERMAL ENERGY GENERATED (MWM) 2,529,099.0 15,730,147.0 99,005,556.4
18. GROSS ELECTRICAL ENERGY GENERATED (MWH) 860,800.5 5,408,793.0 34,091,433.0

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19. NET ELECTRICAL ENERGY GENERATED (MWM) 025,526.5 5,138,418.1 32,493,786.8
20. UNIT SERVICE FACTOR 100.0 83.7 78.6 l
21. UNIT AVAILABILITY FACTOR 100.0 83.7 78.6 1

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22. UNIT CAPACITY FACTOR (USING MDC NET) 97.6 77.5 74.5 Y
23. UNIT CAPACITY FACTOR (USING DER NET) 96.2 76.4 73.7
24. UNIT FORCED OUTAGE RATE 0.0 16.1 10.6
25. UNIT FORCED OUTAGE HOURS 0.0 933.6 3,571.1 SMUTDOWNS SCHEDULED DVER NEXT SIX MONTHS (TYPE, DATE, AND DURATION OF EACM)..............

Refuel Outage

  • February 1 1991 (subject to CONVEX approve l) 56 days IF CURRENTLY SHUTDOWN, ESilHATED STARTUP DATE......N/A i

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P AVERAGE DAILY UNIT POWER LEVEL DOCKETNO.

21:31J

.l UNIT MII IRTONE UNIT 3 DATE September 5.1990 COMPLETED BY A. L ELMS 2(B-444-5388 i

MONTH August 1990 DAY AVERAGE DAILY POWER LEVEL.

DAY. AVERAGE DAILY POWER LEVEL (MWE. NET) =

(MWE NET) q l'

1115 16 1117 2

1122

.17 1118 l

3-1115 18

'1116 4

1116 19 1118 5-1113 20 1117 6

1116 21 1089 7

1113 22 1079 8

1117 23 1089' 9

1113 24 1082-10 1113 25 1117' 11 1050 26 1114 12 1119 27

'1118 13, 1116

-28 1114 14 1117 29 1111' 15 1119 30 1115 31 1110

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s DOCKET NO. 50-423 UNIT SF0TDOWNS AND POWER REDUCTIONS UNIT NAME Minu wNE 3 DATE 9-4-90 COMPLETED BY A.

ET2ES l

TELEPHONE (2031 444-5388

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No.

Date Dura-Reason Method of Licensee System.

Component-Cause and Corrective

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tion (2)

Shut down Event Code.

Code Action to Prevent i

Hours Reactor (3)

Rept No.

Prevent Recurrence C

NONE l-I

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'ltiF: Forced 2: Reasons:

3: Method 4:" Exhibit G - Instructions S: Scheduled A-Eqgipment Failure (Explain) 1-Manual

-.for Preparation of Data B-Maintenance.or Test 2-Manual Scram

' Entry Sheets for Licensee _

C-Refueling 3-Automatic Scram Event Report (LER): File D-Regulatory R9striction 4-Continued from-(NUREG-0161)

.E-Operator-Training Er License Exam 5 previous ~monph i

F-Administrative Power Reduct.on 5: Exhibit Sane Source G-Operational Error (Explain)

(Duration = 0 H-Other

. 9-Other-(Explain))

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REFUELING INFORMATION REQUEST I-AUGUST 1990 l

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Name of Ncility: Millstone 3.

2.

Scheduled date for next refueling shutdown: February 1.1991 (awaitinn CONVEX approvall 3.

. Scheduled'date for restart following refueling: March 29.1991

' 4.

Will refueling or resumption of operation thereafter require a technical specific p change or otherlicense amendments?

As a result of the new ft el desinn. Technical Specifications channes to the Axial Flux

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Difference. Heat P1x H ot Channel Factor. and Refuelina Water Storane Tank sec-tions will be reauirec.. Furthermore. the Fue: Storane sectEon of Desian 7eatures wil

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be charined to illiow cont nued regionalize:i storahe of spent fuel 16 the scelt fue nool. Aso.the nstrumentation section will M channed to reflect a new Hinh Plux at.

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Shutdown setooint.

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5.

Scheduled date for submitting licensing action and supporting information.

l September 15.1990,

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6.

Important licensin considerations associated with refueling, e.g., new or different fuel design or sup ier, unreviewed design of perfc,rmance analysis methods, signifi-a cant changes in fu design, new operating procedures:

Cvele 4 fuel assemblies will be'of the Westinnhouse Vantane 5H desinn. Tl'is desian includes <%is filter bottom nozzles. intermediate flow mixinn erids. i6tenra fuel rod l

hunlP'sle abSorbtts. and axial biankets.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:

(a): 192 (b): lfi0 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 planned, in number of fuel assemblies:

1 Pasent size - 756.

No increase requested.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assummg the present licensed capacity:

End of cycle 5.

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