ML20052G007

Monthly Operating Rept for Mar 1982

ML20052G007
Person / Time
Site:	Millstone
Issue date:	04/08/1982
From:	John Parillo NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20052G004	List: ML20052G003 ML20052G007
References
NUDOCS 8205140229
Download: ML20052G007 (7)

Text

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OPERATING DATA REPORT 50-336 DOCKET NO.

DATE 4-R-82 COMPLETED BY J.J. Parillo TELEPHONE (203) 447-1791 X W9 OPERATING STATUS Millstone 2 Notes Items 21 and 22 are

l. Unit Name:

March 1982 computed using a weighted

2. Reporting Period:

l

3. Licensed Thermal Power (MWt):

2700 average. Unit operated at 909 2560 MW prior to uprating to

4. Nameplate Rating (Gross MWe):

its current 2700 MW power 870

5. Design Electrical Rating (Net MWe):

level.

895

6. Maximum Dependable Capacity (Gross MWe):

864

7. Masimum Dependable Capacity (Net MWe):

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

NA NA

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

NA

10. Reasons For Restrictions.lf Any:

NA This Month Yr..to-Date Cumulatise

11. Hours In Reporting Period 774 2160 54.912

12. Number Of Hours Reactor Was Critical 484 484 39.071.3

13. Reactor Resene Shutdown Hours 0

0 2076.9

14. Hours Generator On-Line 373 373 37.374.5

15. Unit Reserve Shutdown Hours 0

0 468.2

16. Gross Thermal Energy Generated (MWH) 808,939.7 808,939.7 93,224,887

17. Gross Electrical Energy Generated (MWH) 265,650 265.650 30,267,147

18. Net Electrical Energy Generated (MWH) 248,388 _, _,

245,259 28,992,491

19. Unit Senice Factor 50.1 17.3 68.1

20. Unit Asailability Factor 50.1 17.3 68.9

21. Unit Capacity Factor (Using MDC Net) 38.6 13.1 63.5

22. Unit Capacity Factor (Using DER Net) 38.3 13.1 62.5

23. Unit Forced Outage Rate 6.0 6.0 20.3

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

NA

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

NA

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

Forecast Achiesed INITI A L CRITICALITY NA NA INITI AL ELECTRICITY NA NA CO\\l%lERCI AL OPER ATION NA NA 8205140229 820415 DR ADOCK 05000336 to/771 PDR

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AVf R AGE D ALLY L* NIT PObER LEVEL

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DOCKET No. _ 50' -3'36 WIT M&qQ,,

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DATE 4-8_-82 J. P3ril10 COMPI.ETED BY TELEPHONE..HD03) 447-1791 -

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MARCH 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY l'OWER LEVEL (MWe Nct)

- (Mwe. Net)

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1 1

0 (-3) 37 413 2

0 (-4) 466 ig 3

0 (-si 19

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E;76 0 (-5) 4 2o

- 818 0 (-2) 823 5

.6 0 (-3) 22 820 7

0 (-5) 324 23 0 (-12) 74 161 s

9 0 (-19) 2g 687 0 (-24) 7f 858 3o, l

-11 0 (-26) 27 858 0 (-25) 841 12 7s 13 03-2_5) 857 39 0 (-28) 30 860-f 14 i

t 861 i

is AS 31 l

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50-336 UNIT SilUTDCWNS AND POWER REDUCTIONS DOCKET NO.

UNIT N A3.iE Milistone Unit 2'

'DATE d R-R7 REPORT MON'DI MARCH 1982 COUi's.r.::D ny

.1 pari'in TEtullONE (203) 447 791 x 4413 y

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Report n 80 13, event Recurrence 6

11 811205 5

347' C

1 NA NA NA Completion of Refuel and Maintenance Outage 1

820323 F

24 H

3 NA IA INSTRUM.

Reactor Protecticn System Trip (TM/LP) from noise induced signals.

Noise problem was corrected and power operation resumed via normal. operatin g procedures.

i 2

820328 i S 10 B

NA NA NA NA Reduced Power to 95% to clean l

condenser water boxes.

(9/77 )

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Docket No.

50-336 Date 4-8-82

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Unit Name Millstone Unit 2 Completed By J. J. Parillo Telephone

(?no 447 17o1 Ext. 4419 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month FEBRUARY 1982 DATE SYSTEM' COMPONENT MAINTENANCE ACTION 2/1/82 Control Rod Drive CEA Extension Shafts Replaced 1 single and 1 Dual Shaft ESAS "B" LPSI Pump Replace Relay 2/2/82 Main Steam Ir.let Blowdown Header on the Steam Replace Generator Blowdown Ouench Tank 2/3/82' Reactor Coolant System "D" Reactor Coolant Pump Change Mechanical Shaft Seal Cartridge Reactor Coolant Syster, PORV Block Valve 2-RC-403 Repair Body to Bonnet Leak RBCCW "A" RBCCW Pump Replace Pump Bearing Reactor Protection Temperature Transmitters TT-ll2HA, Repair System TT-122HC and TT-122HA 2/5/82 Reactor Protection TM/LP Channel "A" Bistable Trip Replace System Unit 2/6/82 Reactor Protection Channel "A" G-2 Mcdule in Core Replace System Protection Calculator #1 2/8/82 CVCS Reroute CVCS Relief Valve (CH-345)

Reroute Discharge Drain Line 2/9/82 Incore Detectors Detector Location L-18 Install Hydroplug e

e 4

9

Dock;t No.

50-336 Date 4-8-82 Unit Name Millstone Unit 2 Completeo By J. J. Parillo Telephone (203) 447-1791 x 4419 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month FEBRUARY 1982 DATE SYSTEM' COMPONENT MAINTENANCE ACTION 2/15/82 Containment Spray Containment Spray Pump P43A Repair Mechanical Seal Leak Aux. Feedwater Flow indicator FI-5277 Replace A-1 & B-1 2/18/82 CVCS Charging Pump Suction Pressure Replace Switches PC 224X & PC 224Y 2/25/82 Service Water Strainer "C" Backwash Piping

~2/1 thru 2/20 Steam Generators S.G. Tubes Plugged 425 tubes in #1 Generator Plugged 284 tubes in #2 Generator e

6 e

e 0

e

Dock;t No.

50-336 Date 4-8-82 Unit Name Millstone Unit 2.

Completed By J. Parillo Telephone (203) 447-1791 i

x 4419 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT I

Report Month f1 ARCH 1982 DATE SYSTEM' COMPONENT MAINTENANCE ACTION 3/2/82 Containment Personnel Access Hatch Replace inner door gasket Service Water "A" Service Water Pump Rebuild l

3/8/82 S.F.P. Cooling "A" SFP Cooling Pump Change tiotor Bearing 3/9/82 Various Snubbers 413011 & 413041 Removed & Reinstalled satisfactory stroke test S/10/82 Aux. Feedwater Terry Turbine Overspeed Test 3/13/82 Reactor Protection Channel "D" Trip Inhibit Module Replace System Bridge Rectifier MDA 970-2

'3/25/82 Reactor Protection Scaling Amplifier F4,5 in Core Replace System Protection Calculator 2 - Channel "A"

'3/30/82 CVCS "C" Charging Pump Repack 3/31/82 Reactor Protection RCS RTD's Perform response time testing System O

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9

Dockit No.

50-336 bate:

4-8-82 Completed by J. J. Parillo Telephone (203) 447-1791 x 4419 REFUELING INFORMATION REQUEST 1.

Name of facility:

Millstone 2 2.

Scheduled date for next refueling shutdown:

Consnence refuel outage March 26, 1983.

3.

Schedule date for restart following refueling: May 14, 1983 4.

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

It is not anticipated that Cycle 6 operations will require Technical Specification changes or other License amendments.

5.

Scheduled date(s) for submitting lic'ensing action and supporting information:

N/A 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design er, supplier, unreviewed design or perfonnance analysis methods, significant 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) In Core:

217 (b) 288 l

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:

1985, Spent Fuel Pool, full core off load capability is reached.

1987. Ccre Full, Spent Fuel Pool contains 648 bundles.

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