ML20042G967

Monthly Operating Rept for Apr 1990 for Millstone Nuclear Power Station,Unit 3.W/900430 Ltr

ML20042G967
Person / Time
Site:	Millstone
Issue date:	04/30/1990
From:	Elm A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-466, NUDOCS 9005160346
Download: ML20042G967 (5)

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- d NORTDELEr UTILITIES o.nor.i ome.. . s.io.n sir..i. B.,nn. connecucut Un as is$sNNa* P.O. BOX 270

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HARTFORD. CONNECTICUT 061410270 L L J 7,[**pj','$j,"*g'j" (203) 665-5000 _

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May 8,.1990 MP-90-466

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l l' Re: 10CFR50.71(a)

U.S. Nuclear Regulatory Commission ,

0 l~ Document Control Desk Washington, D.C. 20555 -

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Reference:

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

Dear Sir:

In accordance with reporting, requirements of technical specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthl tion for the month of Aprilis hereby forwarded. y Operating Report 90-05 coveri Very truly yours,

. t NORTHEAST NUCLEAR EMSGY l COMPANY L  !

l l'W 1: Steph n E> cace Director, Millstone Station Attachment 1.

cc: T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1,2 & 3 1

- D.H. Jaffe, NRC Project Manager, Millstone Unit No. 3 9005160346 900430 PDR

.R ADOCK 05000423 PDC fMY '

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• • • • • • • NRC OPERAtlNG Staf 0S RIPORT CollPLti!D Bf RIACTOR INGIRIIRIH *******

1. DOCI!f.... 50-423 OPillflIGSTATOS

2. RIPORflRG PIR10D... APRIL 1990 0071G1+ONiill!100RS..485.7 1233.3 :719.0 3; OflLiff C0lfACf.................A. L. ELHS 2034445388 *************. l

4. LIC ERSID THRH AL F0HR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 411

• HILLSf0H *

5. - IAHIPLATI RAflpG (GROSS HI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1,253 4

• Hlf 3 *

6. DtSIGN ELICTRICAL RAfilG (187 HI) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1,15). *************

7. 1111808 DEP!HABLI CAPAClf f (GROSS HI) . . . . . . . . . . . . . . . . . . . . . . . . 1,18 4.2

8. HAIIHOR DIPIRABLE CAPAClf f (Hf HI) . . . . . . . . . . . . . . . . . . . . . . . . . . 1,13 7. 0

9. IF CHillGIS OCCOR AB0f! S!HCI LAST RIPORT, RIASONS ARI..........,

11 / 1

10. P0HR Lif!L TO HICH RISTRICf!D, if AH (HIf HI)...............ll/A '

11. RIASON FOR RISTRICfl0ll, IF ANT....ll/A H0lifH f!AR70DAf! 00HLAfit!TODAf!-

12. BOURS Ill RIP 0RflNG PIRIOD 719.0 2,879.0 35,255.0

13. HHBIR OF B00RS THI R110708 NASCRIflCA!, 214.2 2,320.0 27,995.9

14. RIACTOR IISIRif SHOTD0H BOURS 444.8 559.0 1,282.9 15.BOORSGINIRATOROllLlHE 233.3 2,259.7 27,424.1 16.0817 RESIRf! SH0fD0H E00RS' O.0 0.0 0.0

17. GROSS THHMAL HIRGY GHIRATED (H2) 403,460.0 7,106,337.0 90,381,746.4

18. GROSS ILICTRICAL HIRGY GillIRAf!D (HH) 125,571.0 2,450,823.0 31,133,463.0

19. Hf ILICfRICAL HIRGY GHIRATID (HB) 96,791.9- 2,317,019,4 29,672,388.1

20. Hlf SilflCE FACTOR 32,4 78.5 77.8 ,

21. Ulf AfAllABILiff TACTOR 32.4 78.5 77.8

22. Olilf CAPAClf! FACTOR (USlH 200 Hf) 11.8 70.8 73.1

23. 0111f CAPAClff FACTOR (USlHG DIR Hf) 11.7 69.8 73.0

24. Ulf FORCID 00fAGI RATI 67.6 21.5 10.6-

25. 011f FORCID 00fMI BOURS 485.7 619.3 3,256.8- ,

SH0fDOHS SCHEDULIO CR XIIf Sl! HONTHS (fff!, DATI, AH DORATIO!l 0F IACH)..............

X/A Il CURRHfLf SH0fD0H, ISilHaflD Sf1Rf0P DAf!. ....H/A t

.-,, ' 44 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-423

. UNIT MILLSTONE UNIT 3 DATE May 2.1990 COMPLETED BY A. L ELMS 203-444-5388 MONTH April 1990 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE - NET) (MWE - NET) 1 _,

0 16 157 2 0 17 0 3 0 18- 0 4; O 19 0

-5 0 20 0 6 0 21 3 7 0 22 250 8 0 23 252 9 0 24 257 10 0 25 257

'11 0 26 258

12. 0 27 365 13 0 28 667 14 0 29 1130 15 0 30 1124 1

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REFUELING INFORMATION REOUEST APRIL 1990

1. Name of facility: Millstone 3.

2. Scheduled date for next refueling shutdown: November 17.1990.

3. Scheduled date for restart following tefueling: Jan.15.1991

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

As a resullpf the new fuel desien. Technical Snecifications chances to the Axinl Flux Difference. Heat Flux Hot Chiinnel Facior. and Refuelina Water Storane Tank ss2 tions will be reouired. Furthermore. the Fuel Storace sect on of Desien ?catures will be chanced to allow continued recionalized storace of soent fuelin the soent fuel~

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

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Shutdown setooint.

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

August 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 c,perating procedures:

Cycle 4 fuel assemblies will be of the Westinchouse Vantace SH desien. This desien neludes debris filter bottom nozzles. intermelliate flow mixing crids. integral f,uel rod surnable absorbers. and axial blankets.

7. The number of fuel assemblies (a)in the core and (b) in the spent fuel storage pooh (a): 123 (b): 160 ,

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:

Present size - 756.

No increase reouested.

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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• DOCKET NO. 50-423 UNIT SHUTEOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE 3 DATE 5-2-90 COMPLETED BY A. EIJfS TELEPHONE _f203) 444-5388 No. Date e Du2a- Reason lMethod of Licensee System Component Cause and Corrective

(. tion (2) Shut down Event Code Code Action to Prevent Hours Reactor (3) Rept No. Prevent Recurrence i Tyrbine and regctor trip High differential level 90-04 04/01/90 F 353.2l F '4 90-011 KE SCN on the intake structure screens caused A and B circulating water pumps to trip. Manually tripped j

the reactor and turbine in anticipation of low condenser pressure.

Manual reactor and tur-bine trip due to loss of 90-05 04/16/90 F f 127.5' A 1 90-013 KE SCN con'.anser 'racuum caused by 2 curcuClating water pump trip. High differen-tial level on the intake screens caused the cir-culating water pump to trip.

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1: F: Forced 2: Reasons: 3: Method 4: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of, Data B-Maintenance or Test 2-Manual Scram Entry Sne<?ts for Licensee-C-Rafueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continued from (NUREG-O1G1)

E-Op rator Training & License Exam previous month F-Administrative 5-Power Reduction 5: Exhibit 1 - Same Source G-O~erational Error _(Explain)

H-CEher (Duration = Q) 94ther (Explain) 7, y.. - . , _ . . . . . ,g_ ,e - , . _ - _ _ , . . . , , , _ ____.__m_ . __..m .__._- ___ _ -