ML20055F191

Monthly Operating Rept for June 1990 for Millstone Nuclear Power Station Unit 3

ML20055F191
Person / Time
Site:	Millstone
Issue date:	06/30/1990
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-673, NUDOCS 9007160057
Download: ML20055F191 (5)

Text

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i .' General offices e Seloon Street, Berlin. Connecticut i

'ErYO"nTiN'c'c"w 5 ' P.O. BOX 270 J' *,',* ,%*w'"",, HARTFORD CONNECTICUT 061410270

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f July 6, 1990' ,

MP-90-673 i Re: 10CFR50.71(a) l U.S. Nuclear Regulatory Commission Document Control Desk ,

Washington, D.C. 20555 '

2

Reference:

Facility Operating License No. NPF 49 Docket No. 50-423 i

Dear Sir:

In accordance with reporting requirements of technical specifications Section 6.9.1.'5, the  ;

Millstone Nuclear Power Station - Unit 3 Monthly Operatmg Report 90 07 covering opera-

. tion for the month of June is hereby forwarded, Very truly yours, t NORTHEAST NUCLEAR ENERGY COMPANY

'St>p s.bace Director, Millstone Station ,

Attachment cc: 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 i8r888u:ssuu PDC

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, AVERAGE DAILY UNIT POWER LEVEL b.

< DOCKET NO. M UNIT MILLSTONE UNIT 3 DATE July 3.17K) i COMPLETED BY A. L ELMS 203-444 5388 1

MONTH June 1990  :

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVED (MWE. NET) (MWE NET)  ;

1 1144 16 37 2 1139 17 489 3 1139 18 1052 4 1141 19 1138 5 1139 20 1141 6 268 21 1142 .

7 0 22 1140 1 8 46 23 1139 9 675 24 1140 10 883 25 1138 .

11 889 26 1137 12 889 27 1136 13 885 28 1111 14 886 29 1100 15 746 30 1137 i

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DOCKET NO. 50-423 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MI. LsTONE 3 DATE 7 57 0 COMPLETED BY A. ETJts TELEPHONE (2031 444-5388 No. Date Dura- Reason Method of Licensee System Component cause and corrective

( ticn (2) Shut down Event Code Code Action to Prevent Hours Reactor (3) Rept No. Prevent Recurrence Automatic reactor trip due to negative rate trip 90-07 06/06/90 F 57.7 A 3 90-019-00 AA AB CBL4 CL caused by dropped rod.

The dropped rod was BA ROD caused by a broken con-JC DET negtion in,the stationary IG gripper, coil . er, cable.

Corrective ac lon in-cluded replacino the bro-functional ken gonnector, testing, and independent evaluation of the gable by a material testing facility to asgertain the failure mechanism. Poten-tial long term corrective actions will be evaluated when the root cause analysis is complete.

Removed unit from service 90-08 06/15/90 S '

18.5 B N/A N/A SJ RV to repair thermal relief valves on #1 feedwater heat 9r. Reactor remained critical.

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

E-Operator Training & License Exam 5 previous month F-Administrative Power Reduction 5: Exhibit 1 - Same Source G-Operaticnal Error (Explain)

H-Other (Duration = 0) 9-Other (Explain) -

REFUELING INFORMATION REOUEST JUNE 1990

1. Name of facility: Millstone 3.

2. Scheduled date for next refueling shutdown: February 1.1991 (awaiting CONVEX approval 1.

3. Scheduled date for restart following refueling: March 18.1991

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

As a result of the new fuel desien. Technical Soecifications chances to the Axial Flux Difference. Heat FluK. Hot Channel Fac1or. arid Refueline Water Storane Tank ses tions will be reauired. Furthermore. the Fuel Storace section of Desien 2eatu'.es w- ll b3 chanced to allow cont'nued recionalized storace of scent fuel in the scent fuel

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cool. Also the Instrumentation section will be chanced to reflect a new Hich Flux at

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Shutdown setpoint. s

5. Scheduled date for submitting licensing action and supporting information. .

August 1.1990. l

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

Cvele 4 fuel assemblies will be of the Westinchouse Vantace 5H desien. This desien includes debris filter bottom nozzles. intermediate flow mixine crids. iritecra l fuel rod

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l burnable absorbers and axial blankets. '

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

l (a): 193- (b): 160 +

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

l assemblies:

Present size - 756.

No increase reauested.

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

End of evele 5.

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