ML20065M537

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

ML20065M537
Person / Time
Site:	Millstone
Issue date:	11/30/1990
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-90-1277, NUDOCS 9012110096
Download: ML20065M537 (5)

Text

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NORTHEAST UTILITIES o.nor.i Ome.. . somen sir..e. B.mn, Conn. ucut 1 Uv'[Ndi$$,i2i Ec5.5 P O. DOX 270

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H ARTFORD. CONNECTICUT 061410270 L L J C,0"JC?l'.72.7.7, (203) 665 5000 December 7, 1990 MP-90-1277 Re: 10CFR50.71(a)

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

Reference:

Facilit perating License No NPF-49 Dock o.50-423

Dear Sir:

In accordance with reporting requirements of technical specifications 3cction 6.9.1.5, the Millstone Nuclear Power Station - Unit 3 Monthly Operating Report 90 '.2 covering opera-tien for the month of November is hereby forwarded, i

l l Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

\ / -

i ,' co<c

/ Step an E. Scace Director, Millstone Station Attachment

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

D.H. Jaffe, NRC Project Manager, Millstone Unit No. 3 l

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"""* hRC C$t rat thG $1 Afus RIPORT COMPLif ED BY kt ACTOR IWGlhittihG " *""

1. 00Ctti.... 50 423 OPERAilhG STATUS

2. FIPOR11NG PERIDO...NOV!MBIR 1990 OUT AGE + DWL l WE HOUR $ . . . 0.0

• 720.0 720.0

3. UT I L 11 V CON T ACT . . . . . . . . . . . . . . . . . A . L . ( Lus 203 4 A4 5588 4 L I CE k st D T HI RMAL P0WE R . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3411

• MILL $10Et

• E AMI Pt a it R Af t wG (GR055 M4 ) . . . . . . . . . . . . . . . . . . . , . . . . . . . . ..... 1,253 MW

• UN11 3

• 5.

Dt tlGN tit CT R IC AL R Ai!WG (hti M4) . . . . . . . . . . . . . . .............. 1,153.6 """"'"**

6.

7. MAXIKM DIPtWDAblt CAPACITY (GROS $ M4)... ........ . . . . . . . . . . 1,184 . 2

8. MAX ! MJM DE P! WD Ahlt CAP AC l1Y ( ht i MWE ) . . . . . . . . . . . . . . . . . . . . . . . . . . 1,137.0

9. I F CHANGil DCCUR ABOVt $ lkCE L A$1 RE POR T , RI A$0NS art . . . . . . . . . . .

N/A

10. PCME R Ltytt TO WHICH RtliR ICitD, I F ANY (hti M4 ). . . . . . .. . . . . . . .N/ A

11. Rf ALON FOR RilTRICil0N, if AWY....W/A MONTH YEAR 10 DATE CUMJLA1lVE 10 (>All

..... . i ........ ..................

12. HOUR $ lW RIPOR1thG Ptkl0D 720.0 8,016.0 40,392.0

13. WOMBER OF HOURS THE kt ACTOR WA$ CRillCAL 720.0 7,1 72.6 32,848.5 4

14. RfACTOR RistRVE SHUTDOWN HOUR $ 0.0 797.6 1,521.5

15. HOUR $ C*NERA10R ONLINE 720.0 7,063.9 32,228.9

16. UWit RE$tRVE SHUTb N N HOURS 0.0 0.0 0.0

17. GRost THERMAL twtRGY GENERATED (MWH) 2,450,"40.0 22,743,048.0 106018457.4

18. GR055 fttCTRICAL ENERGY GENERAftD (MWH) 844,356.0 7,792,072.5 36,474,712.5 7,418,653.7 34,774,022.4

19. WEi (LECTRICAL thtkGY GtWERATED (MWH) 810,265.0

20. UNil $ERVICE FACTOR 100.0 88.1 79.8

21. UNil AVAILABIL11Y FACTOR 100.0 88.1 75.8

22. UW11 CAPAM 'T FACTOR (U51kG MDC hET) 99.0 81.4 75.5

23. UNIT CAPAtl1Y FACTOR (UslWG DtR WET) 97.6 P0.2 74.6

24. UNIT FORrlD OUTAGE Raft 0.0 11.7 10.0

25. UWii FORCfD OU1 AGE HOURS 0.0 933.6 3,5 71.1

$HUIDOWWS SCHEDUltD OVER NEXT SIX MONTHS (1YPE, Daft, AND DURAfl0H OF EACH)..............

Refuct Outage February 1 1991 (sut> Ject to COWVtX aprovel) - 56 days IF CURRENTLY bHUTDNN, IS11 MATED ST ARTUP DATE......W/A D

1 l

- l l

l AVERAGE dally UNIT n'GWER LEVEL DOCKET NO. ,% 423 UNIT MILLSTONE UNIT 3 DATE December 4.1090 COMPLETED BY A L ELMS 20M44 53M MONTH November 1900 4 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEs.,

(MWE NET) (MWE NET)

. 1 1124 , 16 1128 2 1126 17 1127 3 1127 18 1131 4 1127 19 1129 5 1125 20 1126 6 1119 21 1124 1119 22 1131 8 1120 23 1127 9 1127 24 1133 _

10 1076 25 1131 11 1115 26 1130 12 1129 27 1132 13 1120 28 1131 14 _

1129 29 1132 15 1126 30 1131 l

DOCKET NO. 50-423

{

UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME MILLSTONE 3 DATE 12-4-90 COMPLETED BY A. ELFS TELEPHONE f203) 444-5388 e Dura- Reason Method of Licensee System Component Cause and Corrective No. Date Shut down Event Code Code Action to Prevent

(- tion (2) Prevent Rccurrence Hours Reactor (3) Rept No.

NONE '

l I

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

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

H-Other 1

.,e I(EFUEl.ING INFORMATION REOUEST November 1990

1. Name of facility: Millstone 3.

2. Scheduled date for next refueling shutdown: February 1.1991.

3. Scheduled date for restart following refueling: March 29.1991

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. lient fin.llot Channel Factor. nrid Refueline Water Storane Tank see-tions willhe reouired. Furthertpore the Fuel Storece section of Design features will br_ changed to allow continued recionalized storace of soent fuel in the sticnLIEl cool. Also, the Instrumentation section will be charined to' reflect a new Hich Flux at

~ ~

Shutdown s_c.tnclip1

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

All TechnicalSnecification changes submitted.

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design of performance analysis methu6. signifi-cant changes in fuel design, new operating procedures:

Cvele 4 fuel assemblies will be of the Westinchouse Vantate SH des [en. This design includes debris filter bottom no721es intermeiliate Dow mixine crids.16tenral fuel roci

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burnable absorbers. nnd axial blankets.

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

(a): 193 (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 sire 756, No increase requestesta

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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