ML20244E167

Monthly Operating Rept for May 1989 for Millstone Nuclear Power Station Unit 3

ML20244E167
Person / Time
Site:	Millstone
Issue date:	05/31/1989
From:	Elms A, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-13193, NUDOCS 8906200185
Download: ML20244E167 (5)

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.D NORTHEAST UTILITIES o.n r.i ome. s.ioen street. Boriin. connecticut i.e cowictu 6ee

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. min,. wanaces ucme.:ow-P.O. BOX 270

.avou. cia aowaa cowea" HAHTFORD, CONNECTICUT 061410270 l

g (203) 665-5000 noni.eas, aves sewer c ""

mort. Matt wcJewInfnGYCoWaw I

June 12, 1989 MP-13193 Re:

10CFR50.71 (a)

U.S. Nuclear Regulatory Commission i

l Document Control Desk Washingten, D. C. 20555

Reference:

Tacility Operating License No. NFF-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 Monthly Operating Report 89-06 covering operatings for the month of May is hereby forearded.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

/

if (A V St en. Scace Station Superintendent Millstone Nuclear Power Station SES/AE:d1r Attachment ec: W. T. Russell, Region I Administrator W. J. Raymond, Senior Resident Inspector, Millstone Unit Nos.1, 2 & 3 8906200185 890531

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e AVERAGE DAILY UNIT KMER LEVEL DOCKET NO.

50-423 UNIT Millstone Unit 3 DATE 06-06-1989 00MPLETED BY A. L. nM!; 203 444-5388 MONTH M DAY AVERAGE DAILY K WIR LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-lET) 1 1_J08 16 0

2_

1.109 17 0

3 1.108 18 0

4 1.108 19 _.

0 5

1.103 20 0

6 303 21 0

7 143 22 0

8 496 23 0

9 1.008 24 0

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10 1.101 25 0

11 682 26 0

12 0

27 0

I 13 0

28 0

14 0

29 0

i 15 0

30 __

0 l

31 0

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• • • • • • • HC OPERAflNG STAf0S I? PORT C0HPLtfD E! REACTOR HGil!!!!IG *******

1. DOCitt.... 50-423 0PIRAflWGSTATUS

2. h PORflBG PERIOD...Hlf 1989 DUTAGE 4 H L1 H B00RS.. 517.8 +226.2 :744.0;

3. UflLiff CONTACf................A. L. ILHS 203-444-5388

4. LICENSID TIERH AL POUR....................................... 3 411

• HILLSf0H 8.

5. HAutflatt RAflRG (GROSS H H)............................

..... 1,253 H

• Hlf 3

6. DESIGN ELECf tlCAL RAflHG (Hf HI)............................. 1,153.6

7. MAI!HDH DIPHMBLE CAPAClff (GROSS HI)....................... 1.197.0 q

8. HAIIHUM HPHD ABLE CAPAClf f ( Hf BH)......................... 1,141. 9

9. If CHANGES OCCOR AB0VE SIRCI LAST REPORT, REASONS A H...........

N/A

10. POVH L!itL 70 H!CE HSfRICfD, IF AH (Hf HI)...............R/A

11. REASH FOR HSf!Itfl08, if Hf....f/A' HHTH.-

f!AR TO MTR WLAflVI TO Mft

12. B0HS IN HPORflIG Pill 0D 744.0

'3,623.0 27,239.0

13. NHHH OF E0HS TH REACTOR HS CRiflCAL 240.7 2,732.1 21,741.9'

h. HACTOR HSHit S10fD0H HORS 29.0 29.0 723.9 15 HOUS 6tHIAf0R ORLINE 226.2 2,724.3-21,270.9

16. Ulf US!RVE SHUfD0H HOUS 0.0 0.0-0.0

17. GROSS THHAL HERGY GtHRAfD (HH) 105,110.0; 8,981,073.0 70,529,214.4-

18. GROSS HECTRICAL IHRGY GHERAfD (HH) 234,840.0 3,056,879.5 24,315,273.0

19. HT HECTRICAL IHRGY GUERAfD (HU) 217,651.1 2,911,621.9 23,189,883.8

20. Ulf S HilCE FACTOR 30.4 75.2 78.1

21. H lf AVAILABILiff FACTOR 30.4 75.2 78.1

22. Ulf CAPAClff FACTOR (USING D C Hf) 25.6 70.4 74.5

23. Ulf CAPAClff FACTOR (OSING MR Mf) 25.4 69.7 73.8

24. Ulf F0 RCD OUTAGE RATE 25.6' 14.4

.10.2 1

25. Ulf FORCD ODfAGE HOURS 77.B 458.7 2,406.7 520fD0HS SCEDDLD DVER HIf SII HONTES (ffPt Mft, AD MRAfl0N Of HCE).

E/A IF CHHEftf SHUfD0H, ISf!HAfD SfLRTUP Mit.....hly 41989

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s REFUELING INFORMATION REQUEST May 1989 1.

Name of facility: Millstone 3 2.

Scheduled date for next refueling shutdown:.N/A 3.

Schedule date for restart following refueling:

July 4, 1989 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

NONE 5.

Scheduled date(s) for submitting licensing action and supporting information:

N/A 6.

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

1.

Cvele 3 fuel enrichment is hiaher than the present fuel rack analysis.

2.

New fuel desian to implement use of Intearal Fuel Burnable Lbsorbers anc Natural Uranium Axial Blankets.

7.

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

(a)

In Core:

(a) 193 (b) 84 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 reauested.

l 9.

The projected 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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