ML19282C004

Monthly Operating Rept for Feb 1979

ML19282C004
Person / Time
Site:	Millstone
Issue date:	03/01/1979
From:	Howlett G NORTHEAST UTILITIES
To:
Shared Package
ML19282C002	List: ML19282C001 ML19282C004
References
NUDOCS 7903190252
Download: ML19282C004 (6)

Text

.-

OPERATING DATA REPORT

~

50-336 DOCKET NO.

DATE 3/1/79 COMPLETED BY G.H. Howlett TELEPilONE 701/447-1791 X364 OPERATING STATUS Millstone 2 Notes

1. Unit Name:

2. Reporting Period: Februarv

3. Licensed Thermal Power (MWt): 2560 909

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

830 842

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

810

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

None

9. Power Lesel To Which Restricted,If Any (Net MWe):

None

10. Reasons For Restrictions,if Any:

None

~

This Month Yr to-Date Cumulative 672 1,416 27,864 l1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 672 1,351.1 20,878.8

13. Reactor Reserve Shutdown flours 0

64.9 2,065.6

14. Hours Generator On-Line 672 1,335.5 19,767.2

15. Unit Reserve Shutdown Hours 0

0 226

16. Gross Thermal Energy Generated (MWil)

I.692.785 3.355.312 47.237.545

17. Gross Electrical Energy Generated (MWH) 557.900 1,105,210 15,134,011

18. Net Electrical Energy Generated (MWH) 537,123 1,061,997 14,478,688

19. Unit Service Factor 100 94.3 70.9

20. Unit Availability Factor 100 94.3 71.8

21. Unit Capacity Factor (Using MDC Net) 98.7 92.6 64.2

22. Unit Capacity Factor (Us'ng DER Net) 96.3 90.4 62.6

23. Unit Forced Outage Rate 0

0 23.1

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

Refueling, March 10,1979

~10 Weeks

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

N/A

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

Forecast Achieved N/A N/A INITIAL CRITICALITY INITIA L ELECTRICITY N/A N/A COMMERCIA L OPERATION N/A N/A 790319098 }

AVER \\GE D ALLY UNIT POhER t.EVEL DOCKET NO.

50-336 Millstone 2 t.Nir

_3/3/79 3

DAIE CO\\tPLE EED BY G.H. Howlett T ELEPilONE _20_3/447-1791 X364 s!ONTil February 1979 DAY AVER AGE DAILY POWER LEVEi.

DAY AVER AGE DAILY POhER LEVEL OlWe Net)

O!We. Net) 813 685 i7 2

812 703 is 3

812 775 i9 4

81 3 20 801 5

J14 21 811 81 3 812 6

22 813 811 7

23 8

8L3 24 811 9

813 810 23 811 809 10 3

11 813 27 809 12 81 3 806 23 813 13 39 14 812 3o is 813 3

746 16 INSTR UCTIONS On this for:r.at.hst the ascr ge dady u:.it pe er leselin N1WeNet for each day in the reporting ::nmth. Compate to the nearest wh'Ic rneges at t.

(9/77)

'6 i

s r

50-336 UNIT SilUTDOWNs AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Mil 1 stone 2 DATE 3/3/79 REPORT MONT11 February 1979 COMPLETED BY G.H. Howlett TELEPilONE 203/447-1701 X364 g.,3

=

c

=

E Cause & Corrective Licensee

,Et, 8."3

.E E g

g.s X o

No.

Date g

gg y

,c g 5 Event

2 Action to 5E 5

j di j Report #

rN 0 0

Prevent Recuirence d

02 79 02 16 F

0 H

1 79-03 RB CRDRVE While moving group 7 rods for Axial Shape Index control, C.E.A. #68 dropped.

Reactor power was reduced to below 70% per procedure.

The rod was realigned with group 7 with.a subsequent return to full power opera-tions.

Reason for dropped C.E.A. is unknown.

L.E.R. to be submitted.

' Suntiary[ The unit operated at or near full power throughout the month except for the power reduction on the

~

15th through 19th.

The unit commenced coasting down, or, the 28th, to Cycle 3 refueling outage.

9 e

Docket No. 50-336 Page 1 of 2 Date 3/3/79 Unit Name Millstone 2 Completed By G.H. Howlett Telephone 203/447-1791 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month January 1979 DATE SYSTEM COMP 0NENT MAINTENANCE ACTION 1/2/79 Service Water Vital

'A.C.'

switchgear room Replaced corroded plugs and cooler heads.

cooler X-183 1/6/79 Engineering Safeguards Channel

'D' containment pressure Replaced current to current amp.

Actuation isolation amplifier.

1/6/79 Engineering Safeguards Channel

'D' S/G pressure Replaced current to current amp.

Actuation transmitters.

1/6/79 Reactor Protection R.P.S. Channel

'D' Aux. Logic Replaced transformer.

drawer, T-2 transformer.

1/7/79 Vital Regulated 120V Inverter INV-4 Replaced 12 filter capacitors.

Instrument 'A.C.'

1/8/79 Servica Water RBCCW HX X18A, Drain Valve Replaced failed valve.

2-SW-63A 1/10/79 Reactor Protection RPS Channel

'D' Isolated assembly Replaced the power supply.

power supply.

PS A0 Location Al-2.

1/16/79 Main Steam Main Steam Isolation Valve Replaced valve actuation cylinder.

2-MS-64B 1/16/79 Main Steam Main Steam Isolation Valve Replaced valve actuator.

2-MS-64A 1/17/79 Service Water Temp. Control Valve to RBCCW Replaced and repositioned valve boot.

heat exchanger

'A', 2-SW-8.1 1/18/79 Chemical & Volume Charging Pump P-18B Replaced suction valves.

Control

Docket No. 50-336 Page 2 of 2

Date 3/3/79

~

Unit Name Millstone 2 Complet2d By G.H. Howlett Telephone 203/447-1791 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month January 1979 DATE SYSTEM COMPONENT MAINTENANCE ACTION 1/22/79 Chemical & Volume Charging Pump P-18A Replaced suction valves.

Control f

1/24/79 Service Water Service Water Pump P-5A Replace motor upper bearing.

1/25/79 Diesel Generator Fuel Outlet assembly 'B' D/G Replaced fuel outlet assembly and gasket.

1/26/79 Service Water

'B' Hdr. Iso Valve, service Rebuilt failed valve.

water supply to ' A' D/G coolers, 2-SW-12B.

Docket No.

50-336 Date:

3/3/79 Completed By: G.H. Howlett III Telephone:

203/447-1971 X364 REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown: March 10,1979 3.

Schedule date for restart following refueling: May 15, 1979 4.

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

Because the Spring, 1979 refueling will be only the second at Millstone Unit No. 2., Technical Specification Changes are anticipated, especially in the area of reactor engineering specifications.

Inspections of the CEA guide tubes and the steam generators are scheduled for the second refueling outage; the results of these inspections may ultimately involve a license amendment.

Review of the reload design is scheduled for January,1979.

5.

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

" Licensing submittals are scheduled as outlined in the November 1, 1978 letter from W. G. Counsil to R. Reid."

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:

Serious consideration has been given to uprate the thermal output for cycle 3 from 2560 MWT to 2700 MWT.

Further schedular details will be forwarded as they developed.

7.

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

(a)

In Core:

217 (b) 72 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:

667 9.

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

1983, Spent F ml Pool, full core off load capability is reached.

1986, Core Fuil, Spent Fuel Pool contains 648 bundles.