ML20050B482

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Monthly Operating Rept for Jan 1982
ML20050B482
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/06/1982
From: Harran G
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20050B476 List:
References
NUDOCS 8204050378
Download: ML20050B482 (8)
v • d • e


Text

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7 AVER AGE DAILY UNIT POWER LEVEL g

DOCKET NO. - 24s

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UNIT. $. ills tone -1 DATE 820602 COMPLETED BY Ci. Harran TELEPflONE

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Ext. 4194 MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DA!LY POWER LEVEL (MWe Net)

(MWe Net) 1 587 37 598' 2

594 is 596 3

596 39 597 4

595 592

o 5

596 21 596 594 6

22 597 7

595 598 23 g

595 24 597 9

595 10 596 595 25 26 597 Ii 594 27 595 12 594 og 567 13 591 29 473 la 597 30 596 15 598 3

596 16 i

i INSTRUCTIONS

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On this formar.hsi the aserage daily unit pow:r leselin MWe. Net for each da) in the rep the nearest whole inegawatt.

t1DC of 654 based on conmitment to flew England Power Exchange.

(9/771 SOSKOS$@@Q PDR

.a-JANUARY OPERATING HISTORY January 1982 Reactor power at 100%

January 1, 1982 2230 Hours Decreasing reactor power to 90% for a control pattern adjustment.

January 2, 1982 0300 Hours Reactor power returned to 100% power.

January 4, 1982 0015 Hours Decreasing reactor power to 90% for turbine stop valve testing.

January 4, 1982 0110 Hours Reactor power returned to 100%.

January 13, 1982 0007 Hours Decreasing reactor power to 90% for turbine stop valve testing.

January 13, 1982 0030 Hours Backwashing main condensers.

January 13, 1982 0130 Hours Reactor Power returned to 100%.

January 20, 1982 0000 Hours Decreasing reactor power to 90% for.

turbine stop valve testing.

January 20, 1982 0035 Hours Backwashing main condensers.

January 20, 1982 0155 Hours Reactor power returned to 100%.

January 28, 1982 2100 Hours Decreasing reactor power to repair steam leaks in the steam tunnel.

January 28, 1982 2225 Hours Reactor power at 50%.

January 29, 1982 0620 Hours Increasing reactor power.

January 29, 1982 0700 Hours Holding reactor power at 75% for continued steam leak repairs.

January 29, 1982 0800 Hours Increase reactor power.

January 29, 1982 2100 Hours Reactor power at 100%.

January 31, 1982 Reactor power at 100%.

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f* a OPERAT!gNG DATA REPORT

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50-245 DOCKET NO.

DATE 820602 I.

COMPLETED IJY f._ Harran TELEPilONE (203)447-1791 Ext. 4194 OPERATING STATUS lillistone tJnit 1 Notes

1. Unit Name:
2. Reporting Period:

Janua n 1982

3. Licensed Thermal Power (MWil:

2011

4. Nameplate Rating (Gro>s MWel:

662 S. Design Electrical Rating (Nc: MWe): 660

6. Masimum Dependable Capacity (Gross MWe):

684 0

7. Manimum Dependable Capacity (Nei MWe):
8. If Changes Ocent in Capacity Ratings (1: ems Number 3 Through 7)Since Last Report.Give Reasons:

tilA H/A

9. Power Lesel To which Restricted.lf Ar. (Net MWe :

Approx. 595 MUE

10. Reaions For Restrictions. lf Any:

lain tur ine comp'. e 14th stage removal This Month Ye to.Date Cumulative II. Ilours In Reporting Period 744 744 #

97968

/.

12. Number Of Ilours Reactor Was Critical 744 744 71998.1
13. Reactor Resene Shutdown flours 0

0 2775.8 I4. Ilours Generator On Line 744 744 69387.7

15. Uni Re>cne Shutdown liours

-0 0

26.5

16. Gross Thermal Energy Generated (MWil) 147.244 147.244 123,182.328
17. Cross Electrical Energy Gene:ated (MWill 461,500 461.500 41,923,496 i
18. Nt Liectrical Energ) C.cnerated (MWil) 43R.126 41R l '.) A 39,986,949
19. Unit Senice Factor 100 100 70.8 i
20. Uni Auitabinty Factor 100 100 70.9-i
21. Unit capacity ractor IU>ing MDC Neri 90.0 90.0 62.4 _
22. Unis capacity ractor (Using DER Net) 89.2 89.2 61.8-
23. Uni Forced Ourage Rate 0

0 16.0

24. Shutdowns Scheduled 0,cr Next 6 Months (T)pe.Date,and Duration of Eacht:

ti/A ti/A

25. If Shui l>own As End Of Report Period. Estimated Date of Startup:

PUA

26. thuis in Teu Status (Prior f r Omnmercial Operation):

Futecast Achiesed

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INITI AL CRillCALITY a

INill AL ELECTRICITY

^

COMMERCI AL OPER ATION rech

UNIT SHUTDOWNS AND POWER REDUCTJONS

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DOCKET NO. 50-245 i

UNIT N etE Millstone i DATE.92n602 REPORT MONTil JAI;'JARY log 2 COMPLETED BY

_G.

Harran TELEfif0NE (203) 447-1791 Ex t. 4194 1 25 E

=

L' Date E.

5 5

255 l'censee 5'.,

$*l Cause & Currective g

3.2 3

53E L'

l?

E Acthin to yO Prevent Recurrence j i72 j Report :

mu OO E

6 e

1 822001 -

S 0

B 4

ft/A tt/A ti/A Reduced power to 50% to repair a steam leak in the steam tunnel. '

I 2

3 4

F: Forced Reason:

Method:

Exhibit G. Instructions 5: Schedufed A Equipment Failure (Explain) 14f anual for Preparation of Data notaintenance of Test 2-Manual Scra m.

Entry Sheets for Licensee C.Refuehng 3 Automatic Scram.

0161)

Event ReporI(1.ER) Fue(NUREG-j D Regulatory Restriction 4Cher (Explain)

E. Operator Tsaining & Lacense Examination F Admnustranve 5

C Operational Lrrur (Esplain)

Exhibit 1 - Sanw Source (9/77)

It Other (E xplain)

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REFUEL.It;C It:F0fd'J710 : REI)UEST l.

flame of facility:

Mil! stone 1

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2.

Scheduled date for next refueling shutdown:

Fall 1982 3.

Scheduled date for res tart foll,owing refueling:

Winter 1982 4.

Will refueling or resu otion of operation thereafter require a technical

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specification chang 2 or other license acendment?

Yes. Technical Specification changes regardirg:

(1) Maximum average planar linear heat generating rate (2) Maximum critical power ratio 5.

he

,te(s) for submitting proposed licensing action and supporting Sumer 1982 6.

Important licensing considerations associated with refue:ing, e.g., new cr rnethods, significant changes in fuel design, new operatin 172 " Retrofit" 8 X 8 fuel assemblics are scheduled for insertion in Cycle 9 (Reload 8) 7.

The number of fuel asser.blies (a) in the core and (b) in the spent fuel stora pool:

(a) In Core:

580

  • (b) In SFP:

954 8.

The present licensed sper.t fuel pool storage capacity and the size of any in-crease in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

2184 Assemblies 9.

The projected date of tie last refueling that can be discharged to the spent fuel pool assuming the present licensej car.acity:

1985,J,cr.t fuel Pool, full core of f load capabil.ty is reached.

1991, Core full, spent fuel pool contains 2120 bundles UR}i:rmj

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OPER ATipG DATA REPORT

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DOCKET NO.

50-245 DATE 820602 G. Harra I-COS!PLETED BY f203)447.p1791 TEl.ENIONE Ext 4194 OPERATING STATUS fillistone Unit 1 Notes

1. Unit Name:
2. Reporting Period:

anua n M82

3. Licensed Thermal Pow er (5thil:

2011

4. Namepiste Rating (Gross h!Wel:

662

5. Design Electrical Rating (Net 51We): 660
6. h!asimum Dependable Capacity (Gross h!We):

004 654

7. hiasimum Dependable Capacity (Net 51We):
8. If Changes Occur in Capacity Ratings (!tems Number 3 Through 7)Since Last Report.Gise Reasons:

11/A H/h

9. Power Lesel To Which Restricted. If Any (Net 5twe :

Approx. 595 ftiE

10. Reasons for Restrictions. lf Any:

hain tur ine complete 14th stage removal This n!onth Yr..t o.Da t e Cumulative

11. Ifours in Reporting Period 744 744 '

f.

97968

12. Number Of liours Reactnr was Critical 744 7d4 71999.1
13. Reactor Resene Shutdown llours 0

0 2775.8 1.f. linurs Generator On.Line 744 744 69387.7

15. Unit Resene Shutdow n Ifour, 0

0 26.5

16. Gross Thermal Energy Generated (MWil) 147,244 147,244

__123,182,328 17 Gron Electrical Energy Generated istwili 461,500 461.500 41,923,496

18. N: Electrical Energ) Gener.ited pihil) 43R.l?6 a an.1 n; 39,986,949
19. Unit Scnice ractor 100 100 70.8
20. Unit Aui! ability factoe 100 100
21. Unit Capacity factor (Using 5f DC Net) 90.0 90.0 70.9 62.4
22. Unit Capacity factor (Using DER Neil 89.2 89.2 61.8
23. Unit forced Outa;c Rate 0

0 16.0

24. Shutdouns Scheduled Oscr Nest 6 >!onths (Type.Date.and Duration of Eachl:

U/A i

N/A

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

N/A

26. Unns in Test Status (Psior io Commercial Operationi:
Forecas, Achined nNITI Al. CRillCA t.lTY INiil%L Fl LCTRICITY COAIMI.RCI A L Ol'I R ATION U/A h

e UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. _50-245 UNIT N.utE _ Mills tone 1 DATE 82060?

REPORT MONT11.dAMUARY 1982 COMPLETEi.) By G. Harran TELEPilONE (203) 447-179)

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Ex t. 4194 Q

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jYi Licensee 5%

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Cause & Corrective E

N..

Date g

3g 255 Event

?

o3 H

c5 3 5

Ji 5 g Report

$O Action io Prevent Recurrence u

O 1

822801 -

5 0

B 4

ft/A fl/A ft/A Reduced power to 50% to repair a steam leak in the steam tunnel.

r I

2 3

F: Forced Reasun:

4 Method:

S: Scheduled A Lyu:pment Fai'ure(Explain) 1 Manual Exhibit C. Instructions 11 Maintenance or Test for Preparation of Data 2 Manu21 Scram.

c.ltefueling I). Regulatory Restriction 3-Automatic Scram.

Entry Sheets l'or Licensee Event Report (LER) File (NUREG.

E. Operator Training & Ucense Examination 4-Other (Explain) 0161)

F Administrative

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C. Operational Error (E < plain) 5 I

(9/77)

Il Other (Explain)

Exhibit I. Same Source 1

t REFUELlt;G I;iFCTd'?T10!: ~ REQUEST 1.

Name of facility: _

Millstone 1 2.

Scheduled date for next refueling shutdown:

Fall.1982 Sch'eduled date for restart foll,owing refueling:

3.

Winter 1982 4.

Will refueling or resu. ption of operation thereafter require a technical specification change or other license acendment?

Yes.

Technical Specification changes regarding:

(1) Maximum average planar 1jear heat generating rate (2) Maximum critical power ratio 5-che d te(s) for submitting proposed licensing action and supporting Sumer 1982 6.

Important licensing considerations associated with refueling, e.g., new or methods, significant changes in fuel design, new oper 172

  • Retrofit" 8 X 8 fuel assemblies are scheduled for insertion in Cycle 9 (Reload 8) 7.

The number of fuel asser.blies (a) in the core and (b) in the spent fuel s (a) In Core:

580

'(b) In SFP:

954 8.

The present licensed spent fuel pool storage capacity and the site of any in-crease in license s torage capacity that has been requested or is planned, in number of fuel asser.blies:

2184 Asse.?.blies l

9.

The projected date of tr e last refueling that can be discharged to the spent _.

fuel pool assuming the present licensed capacity:

1985 s

u per.t Fuel Pool, full core off load capability it reached.

1991. Core full, spent fuel pool contains 2120 bundles GKH:rrnj

.

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