ML20086L582

Monthly Operating Rept for Nov 1991 for Millstone Unit 2.W/

ML20086L582
Person / Time
Site:	Millstone
Issue date:	11/30/1991
From:	Neron G, Scace S NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
MP-91-1028, NUDOCS 9112170008
Download: ML20086L582 (5)

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(203) 66H000 ww.e.,x.n a i,,w w=*

December 10, 1991 MI'-91-1028 Re:

10CPR50.71(a) l U S. Nuclear Regulatory Commission Doctunent Control Desk Washington. D. C. 20555

Reference:

Facility Operating License No. DPR 65 Docket No. 50 336

Dear Sir:

This letter is forwarded to provide the report of operating and shutdown experience relating to M111stono Unit 2 for the month of November, 1991, in accordance with Appendix A Technical Specifications, Section 6.9.1.6.

One j

additional copy of the report is enclosed.

Very truly yours, NORTilEAST NUCLEAR ENERGY COMPANY f t.

(rcu

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'. Stephen E. Scaco Station Director Millstone Nuclear Power Station SES/CN c: T. T. Martin, Region I Administrator C. S. Vissing, URC Project Manager, Millstone Unit No. 2 V. J. Raymond, Senior Resident Inspector, Millstone Unit Nos. 1, 2 6 3

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9112170008 9111?O_6 ppR ADOCK 050023g PDn

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OPEPATING DATA ItEPORT DOCP.ET NO.

,,,1Qd 6. _

m DATE _lliQfdL COMPLETED BY J J ]ri gn._ _,

TELEPHONE _ R !)1 L y d l l21 EXT. Js)).

QPERATING STATUS Notes: Iums 21 and 22 1.

Unit Name:

Millstone Unit 2 cumulative are volghte.i 2.

Reporting Period:

N,22e:tber 1991 averages. Unit operated 3.

Licensed Thermal Power (MWt):

2700 or 2560 MUTil prior to ita 4.

Nameplate Rating (Cross MVe)-

009 uprating to the current 5.

Design Electrical Rating (Net MWe):

870 2700 MVTil power level; 6.

Maximum Depet.dable Capacity (Cros: MUe):

893.83

=-

--=

7.

Maximum Dependable Capacity (Net MVe):

862.88 8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

N/A 9.

Power Level To Vhich Restricted. If any (Net MVe):

N/A

10. Reacc,ns For Restrictions, If Any:

N/A This Month Yr. To Date Cumulative

11. !!ours In Reporting Period

._._.720.0 8016.0 139656.0

12. Number Of Hours Reactor Vas Crit!. cal 126.8 5032.3 101944.9

13. Reactor Reserve Shutdown llours 03 0. ';

2@j

14. Hours Generator On-Line 126.8 4742.3 97086.1

15. Unit Reserve Shutdown Hours

_f)LQ 0.0 468.2 16 Cross Thermal Energy Generated (MVil) 342421J 12}DMJ3_A 267361583.4

11. Cross Electrical Energy Generated (!NH) 114663.Q 4085139.0_ _

8 Dl4838. 5

18. Net Electrical Energy Generated (!NH) 104620J 3901692.0_

78202741.5

19. Unit Service Factor 17.6 59.2 69.5

20. Unit Availability Factor 17 1 59.2 69.9

21. Unit Capacity Factor (Using MDC Net) 16.B

$ 6._4 ;

65.7

22. Unit Capacity Factor (Using DER Net) 16.7 55.9 64.5

23. Unit Forced Outage Rate 82.4 40.6 15.1 24 Shutdowns Scheduled Over Next 6 Months (Ty'pe, Date, and Duration of Each):

EOC 11 Refuel and Steam Generator Replacement Outage. Anr11 - 1992. 160 days.

25. If Unit Shutdown At End Of Report Period, Estimated Date of Startup:

12/11/91

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A

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AVEPAGE DAILY UNIT POWER LEVEL DOCKET NO.

_1Q-13 6 UNIT:

_1R Unt_one Unit 2 DATEt 12/06/91 COMPLETED BY:

_ U leron TELEFHONE:

(203) 447-1791 EXT:

4417 MONTH:

NOVDiBER 1991 DAY AVG. DAILY F0Vr.R II. VEL DAY AVG. DAILY POVER LEVEL (MVe-Net)

(MVe-Net) 1 874 17 0

2 873 18 0

3 873 19 f,

4 873 20 0

5 874 21 0

6 226 22 0

7 0

23 0

8 0

2t 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 16 0

INSTRUCTIONS On this format, list the average daily unit power level in MVe Net for each day in the reporting month, Compute to the nearest whole megawatt.

l

+

DOCKET $50.

50-336 UNIT SHITTDOWS AND POWiiR REDUCTIONS.

UNIT NAME Millstone 2 4

DATE 12/06/91 COMPLCTED BY.

G. Neron l'

TELEPHONE (203) 447-1791 REPORT HONTH NOVEMBER 1901 EXT.-

4417 l-2 No.

Date Type Duration Reason Method of License Systgn Compgnent Cause & Corrective (flours)

Shutting Event Code Code Action to 3

Down Reactor Report #

Prevent Recurrence T

. 10 911106 F

593.2 A

2 91-012 SN PSF on November 6. 1991, with the unit opera-ting at 100t power, a drain line (eight inch pipe) from the first stage re-heater drain tank no. 1B.t_2 the IB high pressure feed-4 water heater ruptured. Control cperators obsereed control room instrumentation to determine the affects on plant systems.

In addition, the steam discharging into l

the turbine building caused activation of numerous alarms in the control room.

A manual reactor trip was then i

ordered, based upcn control room alarms and indications.

A NDE inspection progran, of turbine building and auxiliary building secondary plant piping was init'.ted and expanded to include the EPRI CHr.CMATE inspection program. The plant remains shutdown and inspections are engoing at this time.

See LER.

1 I-i

' Reason:

' Method

' Exhibit G - Instructions F:

Forced j

S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data i

B-Maintenance or Test 2-Manual Scram Entry Sheets for License i

C-Refueling 3-Automatic Scram Event Report (LER) File i

D-Regulatcry Restriction 4-Continued from (NUFEG-0161) l E-Operator Training & License Examination Previous month 5

l F-Administrative 5-Power Reduction Exhibit 1 -Same Source G-Cperational Error-(r.xplain)

(Duration -0) j H-Other (Explain) 6-Other (Explain) l l

i t

n.

,e

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REFUELING IllFORMATIOli REQU.13T 1.

Name of facility:

lilllaigne 2 2.

Scheduled dato for next refueling shutdown:

.Aoril, 1292 3.

Scheduled date for restart following refueling:

..H/ A 4.

Will refueling or resumption of oporation thereafter require a technical spe 4.fication change or other licenso amendment?

Nono at this timo 5.

Scheduled date(s) for submitting licensing action and supporting informations yone 6.

Important licensing considorations associated with rofueling, e.g.,

now or different fuel design or supplier, unroviewed design or performanco analysis methods, significant changos in fuel design, now operating procedures:

M11Lstone 2 will.be replacina the Steam Generator sub-assemblies dur: na the up.gominc _Qnd of Cyg.le 11 ref.uglina outage.

It is R qipated this will be accomollahed under 10CFR 50.59.

7.

The number of fuel assemblics (a) in the coro and (b) in the spent fuel storago pool In Cores (a) all In Spent Fuel Pools (b) 112

~

liq?E: "hfED_ numbers recrop3nt the total f ug l a s semblign. 3ni_g.g. ag.gl-

~dat t fdtgl Eigrage boxes in the.ge two (a) Item Centrol Ar_ tag 0.

The present licensed spent fuel pool storago capacity and the sizo

-of any increase in licensed storage capacity that has been requested or is planned, in number of fuel ascomblios:

Currentiv 12.77 9..

The projected date of the last refueling that can bo discharged to the spent fuel pool assuming the present licensed capacity:

129.1,_. Spent.J.us) Pool Full, core off load capacity is reached 'With-

-out consolidation 1.

1998. _ Coro Fulb. Jngat_fgel Poollull.

2009, Snont Fuel Pool Full, core off load capacity is reached-contingent upon_ full scale storage of consolldated_Lu21 in tho' Spent Fuel Pool.

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