ML19274D944

Monthly Operating Rept for Jan 1979

ML19274D944
Person / Time
Site:	Millstone
Issue date:	02/08/1979
From:	Young R NORTHEAST UTILITIES
To:
Shared Package
ML19274D941	List: ML19274D940 ML19274D944
References
NUDOCS 7902270265
Download: ML19274D944 (7)

Text

"

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-245 UNIT Millstone 1 790208 DATE COMPLETED BY R. Youno

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TELEPIIONE 203-447-1792 X-47 January MONTII DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 653 149

_1

,7 2

,654 18 455 3

652 19 31 654 4

20 176 625 5

21 SFT 6

15 22 628 7

0 (-6) 497 33 g-0 (-6)

-24 652 9

0 (-5) 25 653 to 0 (-5) 551 26 0 (-6) 11 27 600 12 0 (-5) 28 652

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13 0 (-5) 29 653 14 0 (-5) 30 6R?

0 (-5) 31 649 15 16 0 (-6)

INST 11UC110NS On this format. list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

fl0TE: MDC of 654 f1We-flet is based on commitment to the flew England Power Pool.

(9/77)

'! 9 0 2 2 7 0 2 /c5 k

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,. -OPERATING DATA REPORT

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DOCKET NO.

50-245 DATE 790209 A.-

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COSIPLETED BY R. Young TELEPIIONE 20 k447-1792 X-r; u.

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OPERATING STATUS r.

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- 1. Unit Name:

Mill <; tonn 1 Notes

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,2. Reporting Period:

Januarv l979

..,n. a.

3. Licensed Thermal Power (.\\1W:):

2011

4. Nameplate Rating (Gross 51We):

662

'. '"?-

'.T i 6 5- !

5. Design Electrical Rating (Ne-51We): 660

6. hiaximum Dependable Cap city (Gross 51We):

W

~ j,4 - ',

7. hiaximr.m Dependable Capacity (Net 51We):

664

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

NA

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9. Power Level To Which Restricted,if Any (Net 51We):

NA 10.' Reasons For Restrictions,If Any:

NA

'_.... f, ' ' '

This hionth Yr.-to.Date Cumulative

11. Ilours In Reporting Period 744 744 71,664

12. Number OfIlours Reacter Was Critical 473 473 53,960

13. Reactor Reserve Shutdown flours 0

0' 892

'14. Ilours Generator On.Line 444.5 444.5 51,764.8

15. Unit Resene Shutdown flours 0

0 0

16. Gross Thermal Energy Generated (51Wil) 797.053 797,053 91,860,341

17. Gross Electrical Energy Generated (.N!Wil) 271.300 271,300 31,076,396

18. Net Electrical Energy Generated (SIWII) 257,294 257,294 29,675,812

19. Usut Senice Factor 59.7 59.7 72.2

'20. Unit Availability Factor 59.7 b9./

72,2

21. Unit Capacity Factor (Using SIDC Net) 52.9 52.9 63.3

22. Unit Capacity Factor (Using DER Net) 52.4 52.4 62.7

23. Unit Forced Outage itate 40.3 40.3 18.2

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

Annual refuel and maintenance outage tentatively scheduled for nine weeks commencino Apri: 28, 1979.

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

NA'

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

Forecast Achiesed INITIA L CRITICA LITY

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INITIA L ELECTRICITY CO.\\151ERCIAL Ol'ER ATION i.;

'(9/77)

< i DOCKET NO. 50-245 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Millstone 1 DATE 70n?no REPORT MONT11 January f COMPLETED BY R_ Ynemo e

TELEPilONE 203-447-1792 X-475 u

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.$ g

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$.Y Ii Licensee E t, Cause & Corrective No.

Date g

3g js&

Event p

gg J

Action to I-yE 5

Ji dj =g Report #

mU Prevent Recurrence o

e u

C 19 790106 F

269.2 A

1&3 79-1/IP CG Pipe XX On Jan. 6, during drywell inspection 79-1/lT a circumferential crack was discovered i

in a section of the clean up. return line.

The occurrence was attributed to intergrannular stress corrosion cracking.

The affected section of the pipe was removed and a new more re-sistant section was added (see LER for more detail) 20 790119 F

30.3 F

1 NA SF Valve OP On Jan.19, the unit was removed from service to change the "A" automatic pressure relief valve topworks.

The APR lifted prematurel. during power ascension mentioned above.

21 790122 F

NA B

NA NA HC HT Exch Reduced powar for main condenser]

maintenance, Power was increased ~

following ir,intenance. -

2 3

4 F: Forced Reason:

Method:

Exhibit G. Instructions 4

S: Scheduled A Equipment Failure (Explain) 1 -Manual -

for Preparation of Data B-Maintenance or Test 2 Manual Scram.

Entry Sheets for Licensee

'f 3-Automstic Scram.

Event Report (LER) File (NUREG.,

C Refueling D Regulatory Restrictior' 4-Other (Explain) 0161)

E-Operator Training & License Examination t-F-Ad minist rative

- s.

- 5 G-Operational Error (Explain).

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-Exhibit !- Same Source

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(9/77) li Ot her ( Explain)

-0PERATING HISTORY-January 1,1979:

Reactor power at 100%.

January 3,1979:

0001 Hrs. - Reduced power to 90% for turbine stop valve test.

0052 Hrs. - Reactor power at 100%.

January 5,1979:

2028 Hrs. - Reduced power for containment entry for repair of drywell equipment drain valve.

January 6,1979:

0311 Hrs. - Main Generator off line.

0341 Hrs. - Mode switch to start up.

0955 Hrs. - Reactor scram due to inadvertent shift of mode switch to "RUN."

January 16, 1979:

1815 Hrs. - Reactor critical #370.

Sequence CCC, Group 4, Rod 10-31, Position 6, temp. 193 F, T = 53.3 sec.

January 17, 1979:

0003 Hrs. - Reactor scram during plant start up on low level.

0155 Hrs. - Reactor critical #371.

Sequence CCC, Group 6. Rod 34-15, Position 24, temp. 408 F, T = 174 sec. 0825 Hrs. - Generator on line.

January 18, 1979:

0000 Hrs. - Reactor power at 73%.

0415 Hrs.

"A" Automatic Pressure Relief Valve momentarily lifted prematurely.

January 19, 1979:

0001 Hrs. - Commenced power reduction for inspection / repair of "A."

0348 Hrs. - Main Generator off line.

0635 Hrs. - All rods at 00.

January 20, 1979:

0140 Hrs. - Commenced start up.

0330 Hrs. - Reactor critical #373.

Sequence CCC, Group 7, Rod 26-39, Position 4, temp. = 152 F, T = 100 sec. 1005 Hrs. - Main Generator on line.

1600 Hrs. - Reactor power at 40%.

2400 Hrs. - Reactor power at 71%.

Jaauary 21, 1,979.

2010 Hrs. - Reactor power at 100%.

I January 22, 1979:

2150 Hrs. - Decreased power for repairs to 'ain condenser.

2315 Hrs. - Reactor at 40% pcwer.

January' 23, 1979:

0535 Hrs. - Repairs completed, increased power.

1900 Hrs. - Reactor power at 10'J%.

Janua ry 25, 1979:

1600 Hrs. - Contrcl rod 22-07 stuck between position 46-48 during weekly control rod exercise.

2245 Hrs. - Control rod 22-07 declared inop.

(Analysis pending for shutdown margin spec.)

January 28, 1979:

Reactor at 100%.

...... i. o....

Docket No. 50-245 Page 1 of 2 Date 790212 Unit Name Millstone 1 Completed By R. Young Telephone 203-447-1792 X-475' CORRECiIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month January 1979 DATE SYSTEM COMP 0NENT MAINTENANCE ACTION 90104 Refuel Control Potentiometer Removed old potentiometer and installed new,

(Rx. Bldg. Crane) potentiometer.

90105 Liq. Radwaste Sys.

Drywell Equip. Drain Isolation Installed new 0-Rings and diaphragms in valves (1-SS-13,1-SS-14) valve operators.

90107 Condensate Sys.

"A" Cond. Booster Pump Installed new valve.

Drain Valve 90109 Automatic Pressure Automatic Pressure Relief Removed valve internals and replaced with Relief Valve 1-MS-3A Operator rebuild kit.

90110 Liq. Radwaste Sys.

Drywell Floor Drain Isolation Installed new 0-Rings and diaphragms in Valves (1-SS-3, 1-SS-4) valve operators.

90110 Core Spray 1-CS-21A Replaced broken resistor in valve operator starter controller.

90111 Standby Liquid SBLC Heat Tracing Transformer Installed new transformer and redistributed Control loads.

Control Rod Drive CRD Accumulator 14-19 Removed pitted accumulator and installed new one.

90113 Condensate "B" Cond. Booster Pump

' Completely rebuilt pump-renewed inboard and outboard seals.

90115 Condensate "A" Intermediate Pressure Installed new disc and seat.

Heater.

(Tube Side) Relief Val ve 90115 Condensate "B" Intermediate Pressure Installed new metal gasket.

Heater flanway Cover

. Docket No.

50-245 Page 2 of 2 Date 790212 Unit Name Millstone 1

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Completed By R. Young

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Telephone 203-447-1792 X47d CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month January DATE SYSTEM' COMPONENT f4AINTENANCE ACTION 90115 Isolation Condenser 1-IC-49 Lapped seat and disc.

90120 Automatic Pressure Automatic Pressure Relief Installed new rebuilt base.

Relief Valve 90125 Refueling Bearing on Main Hoist Installed new bearing.

(Rx. Bldg. Crane).

90127 Fire Protection CKT.13 - Reserve Station Dried out water in heat sensor and reinstalled.

Service Transformer Deluge System.

f~ Refueling Interlocking Braking Installed new auxiliary contact.

90130 (Rx. Bldg. Crane)

Circuit

. REFUELING INFORPATION REQUEST i'.

Name of facility:

Millstone 1

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2.

Scheduled date for next refueling shutdown:

790428 3.

Scheduled date for restart foll,owing refueling:

790623 4.

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

Yes! ~ Tech. Spec. changes regarding:

(1) Maximum average planar linear heat generating rate.

(2) Minimum critical pov.ar ratio (3) Automatic pressure relief valve mod. including new settings (4)

Remove the 1.3% AK requirement from rod drop analysis.

5.

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

February 1979 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:

Yes!

Proposed 143 retrofit 8x8 f el assemblies purchased from General Electric.

7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel ttorage pool:

500 E29 (a)InCore:

(b) In SFP:

8.

The present licensed spent fuel pool storage capacity ar.d the size of any in-crease in licensed storage ccpacity that has been requested or is planned, in number of fuel assemblies:

Modification currently in progress.

Approximately 95% complete, to increase storage capacity to 2184 assemblies.

9.

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

March 1978 s

RHY:rmj

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