ML20096C787

Monthly Operating Rept for Apr 1992 for Millstone Nuclear Power Station,Unit 3

ML20096C787
Person / Time
Site:	Millstone
Issue date:	04/30/1992
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-92-478, NUDOCS 9205140288
Download: ML20096C787 (5)

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L L 1J C%Oll$7%Z;, (2W 645000 May 11, 1992 MP-92-478 Re: 10Ci R50.71(a)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Reference:

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

Dear Sir:

In aciordance with reporting requirements of technical specifications Section 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 92-05 covering opera-tion for the month of April is hereby forwarded.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

' //-

Stephen E. Scace

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- Director, Millstone Station Attachment cc: T.T. Martin, Region I Administrator W.J. Raymond, Senior Resident ins;.ector, Millstone Unit Nos.1,2 & 3 V. L. Rooney, NRC Project M? nager, Millstone Unit No. 3 -

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920D140288 920430 // kl l: PDR -ADOCK 05000423 ' '

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. Ke_421 UNIT MILLsTONt UNIT 3 DATE b % 5.1992 COMPLETFD GYA. L Elms 20344,4d}M MONTH Aoril 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE - NET) (MWE NET) 1 1121 16 1089 2 1140 17 1082 3 1138 la 1086 4 1137 19 1085 5 '748 20 1085 6 0 21 1085 i

l 7 0 _

22 1085 8 0 23 1606 9 'O 24 1085

~10 0 25 1088 _

l 11 0- 26 1093 l

12 379 27 1094 13 814 28 1092 14 1064 29 1092 15 1062- 30 1092

.- __ .. . _ .. _ . - _ m .- . _. _ _ . . _ _ _ _ .

hr ,

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• • • • • • • NRC OPERATING STATUS RFPORT COMPLETED BY REACTOR ENGINEERING *******

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

2. REPORTING PERIOD... APRIL 1992 OUTAGE + DNLihE HOURS.. 150.7 + 568.3 = 719.0

3. UT I L I T Y CON T ACT . . . . . . . . . . . . . . . . A . L . E l ms 203 444 53S8

4. - L I CE NSED T HE R MAL P0WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3411

• MILLSTONE *

5. NAMEPLATE RATING (GROSS MWE).................... .............. 1,253 MW

• UNIT 3 *

6. DESIGN El.ECTRICAL.RAftkG (NET MWE)............................. 1,153.6

7. MAXI MUM DEPENDABLE CAPAC ITY (GRLS$ MWE ) . . . . . . . . . . . . . . . . . . . . . . . . 1,184.2

8. MAXI MUM DEPEND ABLE CAPACI TY (NET MWE ). . . . . . . . . . . . . . . . . . . . . . . . . . 1,137.0

9. -IF CHANGES OCCUR ABOVE $1NCE LAST REPORT, REASONS ARE...........

N/A

10. POWER LEVEL TO WHI CH RE S1 R I CTED , I F ANY (NET MWE ) . . . . . . . . . . . . . . 97%

11. REASON FOR RESTR!Cil0N, IF ANY.... Millstone site limitation of 2620 MWe due to grid instability.

MONTH YEAR TO DATE CUMULATIVE TO DATE amass senses ====== ===========a =====

12. HOURS IN REPORTING PERIOD 719.0 2,903.0 52,799.0

13. NUMBER OF HOURS THE REACTOR WAS CRITICAL 594.9 1,950.8 38.498.1

14. REACTOR RESERVE SHUTDOWN HOURS 0.0 828.1 6.466.5

15. HOURS GENERATOR ONLINE 568.3: 1,B82.6 37,700.4

16. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

17. GROSS THERMAL ENERGY GENERATED (MWH) 1,808,770.0 6,079,102.0 123,023,248.0

18. GROSS ELECTRICAL' ENERGY GENERATED (MWH) 628,485.0 2,104,456.5 42,455,718.0

19. NET ELECTRICAL ENERGY CENERATED (MWM) 592,270.2 1,988,240.1 40,401,701.9

20. '! NIT SERVICE FACTOR 79.0 64.9 71.4 21.' UNIT AVAILABILITY FACTOR 79.0 64.9 71.4

22. UNIT CAPACITY FACTOR (USING MDC NET) 72.4 60.2 67.1

23. UNIT CAPACITY FACTOR (USING DER NET) 71.4 59.4 66.3

24. UNIT FORCED OUTAGE RATE 21.0 35.1 18.8

25. UNIT FORCED OUTAGE HOURS 150.7_ 1,020.4 8,749.5 SHUTD0WNS SCHEDULED DVER NEXT SIX n0NTHS (TYPE, DATE, AND DURATION OF EACH) .............

N/A IF. CURRENTLY SRUTDOWN, ESTIMATED STARIUP DATE......N/A

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t Docket No.: 50-423 l

UNIT SHUTDOWNS AND POWER REDUCTIONS

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Unit Name Millstone 3 '

l Date 05/04/92 -

l Completed by A. Elms - [

. Telephone 1203) 444 - 5388  ;

N o. ' . Date Type Duration Reason! Methodof Licensee System Componerd Cause and Corrective [

(1) Hours (2) ' Shutdown Event Code Code Action to Prevent Recurrence Reactor (3) Report 92-03 04/05/92 F 150 7 F'. 1 .- 3 011 KE SCN' ManuaBy tripped. the reactor when the condensate pumps tripped..  ;

P Condenser experienced high pressure when E circulating water pump COND tripped while performing a condenser thermal backwash (F circ purr- I was offiine). The subsequentincreasein condenrrr pressure creat ,  :

a low level in the condenser hotwett. The condensate pumps alpped on  !

low level. The root cause was design deficiency. The traveling water [

screen for the.+ condenser bay can neither operate in the reverse direction nor hand:e the debris.The screens are currently being replaced and procedures were modified to allow sufficient cleaning

4 time using the present screens. 1

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1: F: Forced 2 Reasons: 3: Method 4: Exhibft G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data ,

B-Maintenarce or Test ,

2-Manual Scram Entry Sheets for Licensee C-Refueling 3- Automatt: 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 = 0)

H-Other - 9-Other (Explain)

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REFUELING INFORMATION REOUEST April 1992 1, - Name of facility: Millstone 3.

2. Scheduled date for next refueling shutdowr lune 5.1993 3.- Scheduled date for restart following refueling: Aunust 14.1991

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

BJs

5. Scheduled date for submitting licensing action and supporting information, t_ /

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

N/A-

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

(a): 121 (b): 2@

8 - The present licensed spent fuel pool storage capacity and the cize of any increase in licensed storage capacity that has been requested or is plana ut, in number of fuel assemblies:

Present size - 756.

No increase reouested.

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

End of cycle ~5.

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