ML20009D413

Monthly Operating Rept for June 1981

ML20009D413
Person / Time
Site:	Millstone
Issue date:	07/07/1981
From:	Harran G NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20009D410	List: ML20009D409 ML20009D413
References
NUDOCS 8107240044
Download: ML20009D413 (8)

Text

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• f AVERAGE DAILY UNIT POWER LEVEL 50-245 DOCKET NO.

UNIT _ Millstone l DATE l,

G. Ha nan COMPLETED IlY

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TELEPilONE x-655 June MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net) 1 0

37 gg 0

2 is 118 3

0 147 39 l-4 0

20 468 I

0 S

2 565 0

6 22 585 7

0 23 585 8

0 582 24 0

25 583 10 0

26 583 11 0

27 583 12 0

582 28 13 0

29 581 14 0

580 30 15 0

NM 3,

16 0

INSTRUC110NS On this format. list the averat; daily unit power leselin MWe Net for each day in the reporting manth. Compute to l

the nearest whole rnegawatt.

MDC of 654 based on comitment to New England Power Exchange.

l (9/77) 8107240044 010714 PDR ADOCK 05000245 R

PDR t.

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OPERATING HISTORY June 1, 1981 Unit remains shutdown for turbine repairs June 12, 1981 0304 Hours Reactor Critical, Rod Group II, Rod 22-19, notch 6, period 216 see moderator temp. 170 F June 13, 1981 0700 Hours Unit rer o:s off-line due to continued turbine vibration.

reactor power at 1%.

June 15, 1981 0121 Hours Reactor SCRAM due to reactre mode switch failure.

1323 Hours Reac* r Critical, Rod Group IV, Rod 20-31 notch 8, period 26 sec, 3

temp. 293 F.

1955 Hours Reactor Power at 10%

2210 Hours Turbine on-line.

2315 Hours Turbine off-line due to continued vibration.

June 16, 1981 2350 Hours Reactov Dower at 10%

June 17, 1981 0403 Hours Turbine On-Line 0645 Hours Reactor Power at 25%

1112 Hours Turbine Off-Line for the overspeed-trip-test.

1248 Hours Turbine on-line.

Increasing Reactor Power.

June 18, 1981 0000 Hours Reactor Power at 38%

l 0117 Hours Turbine trip manually on high vibration.

2105 Hours Reducing Reactor Power to 10%

June 19, 1981 0920 Hours Turbine On-Line

1100 Hours Reactor Power at 40%

June 20, 1981 0015 Hours Reactor Power at 67%

June 21, 1981 1130 Hours Reactor Power at 100%

June 25, 1981 Reactor Power at 98%

June 30, 1981 Reactor Power at 98%

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e OPERATING DATA REPORT DOCKET NO.

50-245 DATE 810707 I

COMPLET ED 11Y G. Harran I

TELEPilONE (?n't) 447_]791

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OPERATING STATUS Millstone Unit 1 Notes

1. Unit Name:

2. Reporting Period:

June 1981

3. Licensed Thermal Power (h!Wt): 2011 662

4. Nameplate Rating (Gross MWe):

5. Design Electrics

• Rating (Net MWe): 660

6. Maximum Dependable Capacity (Gross MWe): 684

7. Maximum Dependable Capacity (Net MWe):

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

N/A N/A

9. Power Level To which Restricted,If Any (Net MWe): N/A

10. Reasons For Restrictions.lf \\ny: N/A N/A N/A This Month Yr. to-Date Cumulatise II. Hours in Reporting Period 720 4,343

' i 92,807

12. Number Of Hour, Reactor Was Critical 441 515 66,974

13. Reactor Reserve Shutdown Hours 267 1,248.5 2,775.8

14. Hours Generator On Line 308.5 346.5 64.472.7'

15. Unit Reserve Shutdown llours 0

0 26.5

16. Gross Thermal Energy Generated (MWH) 551,748 567,002 114,997,129.

17. Gross Electrical Energy Generated (MWH) 167,700 172,200 38,957,603

18. Net Electrical Energy Generated (MWH) 157,207 148,733 37,178,687

19. Unit Senice Factor 42.8 8.0 69.5

20. Unit A,ailability Factor 42.8 8.0 69.5 33.4 5.2 61.3

21. Unit Capacity Factor (Using MDC Net) 33.1 5.2 60.7

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 57.2 65.3 16.8

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each1:

N/A N/A

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

N/A

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

Forecast Achiesed INITIA L CRITICALITY INITl A L ELECTRICITY gjg COMMERCI A L OPER ATION (9/771

UNITSliUTDOWNS AND POWER REDUCTIONS DOCKET NO.

5Y2O UNIT NAME

.,;1,stcne i DATE RIO70/

REPORT MONTli June COMPLETED BY G. Wrrn TELEPl!ONE I?03' /+47-1791 x-655 e.

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)

.Y Licensee E-r, Caux & Corrective

--o No.

Date g

3 Ej g

,g g 5 Event

T 8.T Action to o

H oE 3@g Report 2, r#G gu Prevent Recurrence o

e o

3b 810421 F

398.7 A

4 N/A CA ZZZZZ Balancing problems caused continued l'

Turbine turbine outages.

j Trips i

j i

1 i

s 4

8106$5 F

12.8 A

3 N/A N/A N/A Reactor Mode Switch Failure 4

I 2

3 4

F: Forced Reason:

S: Scheduled A Equipment Failure (Explain).

Method:

Edubit G. Instructions 1 Manual for Preparat.on of Data B. Maintenance of Test 2-Manual Seram.

Entry Sheets for Licensee C-Refueling 3 Automatic Scram.

Event Report (LER) Fue (NUREG.

D Regularory Restriction 4-Other (Explain) 0161)

E Operator Tuining & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit I. Same Source (9/77)

Il-OLher (Explain)

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Page 1 of 2 Dock;t No. 50-245 Dato 810707 Unit Name Millstone 1 Completed By G. Harran Telephone (203) 447-1791 x-655 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month April 1981 DATE SYSTEM COMPONENT MAINTENANCE ACTION 810401 Condensate I.P. Heater "A" Vent Valve Replaced a 1 inch C/S Gate Valve.

810402 Control Rod Drive Module 42-27 Replaced numbers 134, 135 and 136 on the directional control unit.

810402 Control Rod Drive Module 38-39 Disassembled the accumulator and replaced it with a QA spare S/N H1705.

810403 Control Rod Drive Module 42-27 Replaced number 120 sticking valve.

810404 Misc.

Hydraulic. Snubber Rebuilt the snubbe.r to meet the new blaed HSS-38 and lockup set points.

810404 Misc.

Hydraulic Snubber Disassembled and replaced both poppets and HSS-32 seal kits.

810404 Misc.

Hydraulic Snubber Disassembled and replaced the cylinder, piston,

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HSS-44 cylinder, piston, rings and seal kit.

810404 Condensate "B" Condensate Booster Pump 7placed a mechanical seal.

810404 Control Rod Drive Mo'dule 18-03 Replaced number.120 valve.

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810409 Condensate 1-AC-6 Air Actuator Install a new actuator spring.

810411 Shutdown Cooling 1-SD-5 Operator Rep' laced mounting bolts on the operator to yoke with nyloc bolts.

810413 RBCCW

'A'-RBCCW Heat Exchanger Plugged one leaking tube, t

w Is w e --o m e. -~- -,_.. ~ _ _,

Page 2 cf _2 Docket No.

50-245 Date 810707

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Unit Name Millston 1 Completed By G. Harran Telephone (203) 447,1791 x-655

• CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month April 1981 GATE SYSTEM COMPONENT MAINTENANCE ACTION 810413 Service Water

'C" Service Water Pump Replaced both lip seals in the tube

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tension nut of the pump 810415 Control Rod Drive' CRD Cooling Water Header Installed two (2) 1-1/2 inch check valves in the cooling water header 810415 Emergency Service 1 Inch Drain Line Replaced nipples and one (1) elbow with

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' Watet QA material.

810416 Control Rod Drive Module O'2-23 Replaced the o-rings in the scram solenoid val ve.s.

810416 Control Rod Drive Module 18-03 Removed directional control manifold and replaced it with a QA unit.

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REFUELIrlG IfiFORi'ATI0f' REQUEST 1.

flame of facility:

Millstone 1 I

2.

Scheduled date for next refueling shutdown:

Fall 1982 i

3.

Scheduled date for restart foll,owing refueling:

Winter 1982 l

i 4.

Will' refueling or resumption of operation thereafter require a technical f

specification change or other license amendment?

Yes.

Technical Specification changes regarding:

t'l (1) Maximum average planar linear heat generating rate (2) Maximum critical power ratio 6

5.

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

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information.

Summer 1982

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r' Important licensing considerations associated with refueling, e.g., new or i

6.

different fuel design or supplier, unreviewed design or performance analysis i

p methods, significant changes in fuel design, new operating procedures:

172 " Retrofit" 8 X 8 fuel ass'emblies are scheduled for insertion in C.fcle 9

[i (Reload 8)

N U

7.

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

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(a) In Core:

580 (b) In SFP:

954 1

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8.

The present licensed spent fuel pool storage capacity and the size of any in-1 crease in licensed storage capacity that has been requested or is planned, in

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number of fuel assemblies:

I 2184 Assemblies j

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9.

The projected date of the last refueling that cha be discharged to the spent

.i fuel pool assuming the present licensed capacity 1985, Spent Fuel Pool, full core off ioad capability is reached.

I 1991, Core Full, spent fuel pool contains 2120 bundles t

(1b i

b II;i

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