ML20011E899

Monthly Operating Rept for Jan 1990 for Millstone Nuclear Power Station Unit 3.W/900212 Ltr

ML20011E899
Person / Time
Site:	Millstone
Issue date:	01/31/1990
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-151, NUDOCS 9002220742
Download: ML20011E899 (5)

Text

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,e s '_ ,; C

.4= , i General Offices

• Seiden Street, Berlin, Connecticut 1 UIId[cNeetSIEc5"*'

i P.o. BOX 270

• H ARTFoRD, CONNECTIOUT 061410270

' J ,%**1'Z'.7L, o, .m % . i .. co,., (203) 665-5000 i February 12, 1990

• MP-90-151 Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission j Document Control' Desk Washington, D.C. 20555 l -

Reference:

Facility Operating License No. NPF-49 l

Docket No. 50-423 ,

1

Dear Sir:

In accordance with reporting requirements of technical specifica-tions Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 90-02 covering operation for the month ,

of January is hereby forwarded. i Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY v . p

x. 7  % 6 Steph E. Scace Director, Millstone Station Attachment cc: W.T.. Russell, 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 1

1 .

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I 900222074g 900333 ,

_kDR ADOCK 0500 3 ,,_

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88:8IIINRCOPERA11NSSTATUSREPORTCOMPLETEDBYREACTOREN61NEERINGIIIIIIi

1. DOCKET.... 50-423 OPERATING STATUS

2. REFORilNB FER100...#NUARY 1990 OUTABE 4 DNLINE HOURS.. 45.8 + 698.2 = 744.0

3. U11LiiY CONT ACT. . . . . . . . . . . . . . . . . A. L. ELMS 203-444 53BB 4 IItIttttiIt

4. LICENSED THERMAL P0WER......................................... 3411 i MILLSTONE I-

5. N AMEPL AT E R ATINS (BRCSS MWE ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1,253 MW t UNii 3 8

6. DESIGN ELECTRICAL RAi!NB (NET MWE)............................. 1,153.6 88 IIIIIttIt

7. MAllMUM DEFENDABLE CAPAtlTV (6ROSS MWE)........................ 1,164.2

8. MAtlMUM DEPENDABLE CAFAtliY (NET MWE).......................... 1,137.0

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

N/A

10. POWER LEVEL 10 WHICH RESTRitiED, IF ANY (NET MWE)...............N/A

11. REASON FOR RESTRICT 10N, IF ANY....N/A MONTH YEAR 10DATE CUMULAllVE 10 DATE EE233 E321313:3333 333313335533333333 12.HOURSINREPORTINGFERIOD 744.0 744.0 33,120,0

13. NUMBER OF HOURS THE REACTOR WAS CRlilCAL 706.0 706.0 26,381.9

14. REAC10R RESERVE SHUTDOWN HOURS 38.0 36.0 761.9

15. HOURS 6ENERATOR ONLINE 698.2 698.2 25,863.2

16. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

17. GROSS THERMAL ENERGY SENERATED (MWH) 2,261,764.0 2,261,764.0 85,537,193.4 18.GROSSELECTRICALENERBYGENERATED(MWH) 703,720.0 783,720.0 29,466,360.0 19.NETELECTRICALENER6YGENERATED(MWH) 747,066.1 747,066.1 28,102,434.0

20. UN11 SERVICE FACTOR 93.8 93.8 78.1

21. UNIT AVAILABILITY FACTOR 93.0 93.0 78.1

22. UNIT CAPACITY FACTOR (USING MDC NET) 89.3 88.3 74.3

23. UNii CAPACITY FACTOR (USING DER kET) 87.0 B7.0 73.6

24. UNIT FORCED DUTAGE RATE 6.2 6.2 9.4 25.UNITFORCEDOUTAGEHOURS 45.8 45.8 2,683.3 SHUIDOWNS SCHEDULED OVER NEIT 511 MONTHS (iYFE, DATE, AND DURAi!0N OF EACH)..............

N/A IF CURRENTLY SHUTDOWN, ESilMATED STARTUP DATE......N/A 1

• gg?" )

AVERAGE DAILY UNIT KMER LEVEL DCCKET NO. 50-421 UNIT M111ntone Unit 3 DATE 02-08-1990 00tTLETED BY 1. L. EtMS 203-H4 53BB MONTH JANUARY DAY AVER /GE DAILY KMER LEVEL DAY AVERAGE DAILY KMER LEVEL (tME-NET)- (MWE-NET) 1 1.137 16 1.141 _

2 1.145 17 1.139  !

3 1.131 18 350  !

4 1 142 19 0  ;

}

5 1.139 20 255 i G 1.138 21 928 7 1.139 22 1.138 8 1.144 23 1.140 9 1.133 24 1.118 10 1.127 25 1.140 11 1.133 26 1.108 12 1.139 27 810 13 1.139 28 888 14 1.138 29 1.108 15 1.139 30 1.138 31 1.140

i DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE 3 JANUARY 1990 DATE 02-05-90 COMPLETED BY A. t,LMS TELEPHONE (203) 444-5388 No. Date pe Dura- Reason Method of Licensee System Component Cause and Corrective W(1) tion (2) Shut down Event Code Code Action to Prevent Hours Reactor (3) Rept No. Prevent Recurrence 90-01 01/18/90 F 45.8 A 2 90-005-00 SJ CPLG Manual Reactor trip due to loss of SG level caused by loss of B turbine driven feed pump-coupling. Changes have been made to the couplin installation procedure. g Additignally, the vibration alarm setpoint-will be lowered.

90-02 01/26/90 F 0 A 5 N/A- SJ PSP Decreased power to remove motor driven feed pump.

from service to repair pipe leak.

1: F: Forced S: Schedules 2: Reasons: 3: Method 1-Manual 4: Exhibit G - Instructions for Preparation of Data A-Equipment FailureB-Maintenance or Test (Explain) 2-Manual Scram Ent W Sneets for Licensec C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-0161)

E-Operator Training & License Exam previous month F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source G-Operational Error (Explain) (Duration 9-Other =0 (Explain))

H-Other

• . REFUELING INFORMATION REOUEST

~

JANUARY 1990

1. Name of facility: Millstone 3. 1

2. Scheduled date for next refueling shutdown: November 17, 1990.

3.- Scheduled date for restart following refucling: Jan. 15, 1991

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

As a result of the new fuel desian. Technical Soecifications channes to the Axial Flux Difference. Heat Flux Hot Channel Factor, and Refuelina Water Storaae Tank sections will be Ip_q,u i re d . Furthermore, the Fuel Storace section of Desian Features will be chanced to allow continued recionalized storace of scent fuel in the scent fuel cool. Also, the Instrumentation section will be chanced to reflect a new Hiah Flux at Shutdown setooint.

5. Scheduled date for submitting licensing action and supporting "

information.

Auaust 1. 1990.

6. Important licensing considerations associated with refueling, e.g., new of different fuel design or supplier, unreviewed design.of performance analysis methods, significant changes in fuel design,-new operating procedures:

Cycle 4 fuel assemblies will be of the Westinahouse Vantaae SH desian. This desian includes debris filter bottom nozzles, intermediate flow mixina arids, intearal fuel rod burnable absorbers, and axial blankets.

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

(a): 121 (b): 15Q.

8. The present~ licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has l- been requested or is planned, in number of fuel assemblies:

L Present size - 756, 11 No increase reauested.

9. The projected _date of the last refueling that can be dis-charged to the spent fuel pool assuming the present licensed capacity:

End of cycle 5.