ML19263C986

Monthly Operating Rept for Feb 1979

ML19263C986
Person / Time
Site:	Millstone
Issue date:	03/14/1979
From:	Young R NORTHEAST UTILITIES
To:
Shared Package
ML19263C981	List: ML19263C980 ML19263C986
References
NUDOCS 7903200397
Download: ML19263C986 (6)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. _50-245 j

UNIT Millstone - 1 dan _790314 C05fPLETED 11Y. R. Younc TELEPIIONE __203-447-1792 ext. 475 h!ON711 February DAY AVERAGE DAILY POWER LEVEL (MWe. Net)

DAY AVERAGE DAILY POWER LEVEL (hiwe. Net)

I 652 37 656 2

652 3

654 33 654 19 4

654 654 5

654 20 653 21 628 6

655 22 I7 7.

655 23 0 F6) g 651 24 148 9

654 25 523 10 653 11 654 57 26 12 655 2s

%0 13 654 29 14 652 30 15 M4

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654 16 INSTRUCTIONS the nearest whole megawatt.On this format. list the average daily unit power l r ng month. Compute to Note:

MDC of 654 tUe-Net is based on commitment to the flew England Power (9/77) 790329o337

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OPERATING DATA REPORT

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50-245 DOCKET NO.

DATE 790314 CO.\\lPLETED BY R. Youna TELEPl!ONE ?n7 c47 1792

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ext. 475 OPERATING STATUS Notes Millstone-1

1. Unit Name:

2. Reporting Period: _ rnhrm cy 2011

3. Licensed Thermal Power (5fWr):

662 l

4. Nameplate Rating (Gross 5tWe):

660

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5. Design Electrical Rating (Net SIWE):

684

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6. blaximum Dependable Capacity (Gross 51We):

N4 l

7. blaximum Dependable Capacity (Net 51We):

l S. If Chan;;es Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Give Reasons:

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IN

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

M 10.' Reasons For Restrictions,if Any:

_ 'Ihis hionth -

Yr. to-Date

. Cumulative l,

672 1.41 6 72,336

11. Ilours in Reporting Period

_605 1.078 54.565

12. Number Of flours Reactor Was Critical 0

0 892

13. Reactor Resene Shutdown flours 583.7 1.028.2 52,348.5

14. Ilours Generator On-Line 0

0 0

15. Unit Reserve Shutdown flours 1.121.740 1 019.n??

02.07').110

16. Gross Thermal Energy Generated (51Wil)

17. Gross Electrical Energy Generated (31Wil) 187 702.-.

E54.000

___31.459,096 355,279 622,573 30,041,091

18. Net Electrical Energy Generated l'51Wil) 86.07 72.6" 72.47,

19. Unit Senice Factor 86.9%

72.6%

72.4%

20. Unit Availability Factor 83.1%

67.2%

63.5%

21. Unit Capacity Factor (Using SIDC Net) -

82.4%

66.6%

62.9%

' 22. Unit Capacity Factor IUsing DER Net) 67' 24.6*'

18 [1 Y.

23. Unit Forced Outa;e Rate

24. Shutdowns Scheduled Oser Next 6 31onths(Type.Date.and Duration of Each1:

Annual refuel outage scheduled for nine weeks conrencing April 28, 1979.

IN

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

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

Forecast Achiesed iS

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INITIAL CRITICALITY INITI AL ELECTRICITY CONINlERCI \\ L OPERATION s..

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-(9pH

UNIT S!!UTDOWNS AND POWER REDUCTIONS -

DOCKETNO.

50-245 UNIT NAME W I k tar'a-1 DATE 700"A REPORT MONT11 February -

COMPLETED BY -203-447-1793 D

Vne'na TELEPilONE n.

's o 5 3^

e ri E _e g

g.c '4 Licensee p,

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Cause & Corrective a

o No.

Date g

3 sj g

,c g 5 Event u?

yU" o.

Action tn H

$E 5

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Report a N0 Prevent Recurrence o

04 790222 S

55.8 ASB 1

79-08/3L CE VALV0P l-IC-1 was declared inoperable due to loss of position indication while returnina to normal valve

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lineup following routine surveillance (see LER).

The unit was returned to service 2-24-79'.

05 790226 F

32.5 A&B 2

79-05/IP SF VALVEY "F" Tarcet Rock safety relief valve lif ted prematurely and failed to re-seat at the reset pressure during the above power ascension.(see LER).

The unit was returned to service 2-27-79.

• Note:

Shutdowns / Power Rgo. Numbers for. January were in error. 3 Correct Nu2 ers are,W, 02,4& 03 Respectively.

F: Forced Reason:

Method:

Exhibit G -Instructions S: Schedu!ed A Equipment Failure (Explain) 2 Manual Scram. _

for Preparation of Data

! Manua!'

B-Maintenance or Test Entry Sheets for Licensee C-Refueling

3. Automatic Scram.

Event Report (LER) File (NUREG.,

D-Regulatory Restriction 4 Other (Explain) 016I)

' E Operator Training & Ucense Examination e

F-Administrative

-S C-Operational Error (Exph

n).

-Exhibit I-Same Source -

(9/77)

!!-Ot her ( E xplain)

i l5 Operating. History

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February 1,1979:

Reactor power at 100%

February 8,1979:

0005 hr - Reduced power to 90% for turbine stop valve test 0120 hr - Reactor power at 100%

February 21, 1979:

2l00 hr - Commenced power reduction for 1-IC-1 repair 2230

- Performed turbine stop valve testing February 22, 1979:

0305 hr - Turbine off line 1430 hr - Reactor in cold shutdown February 24, 1979:

0442 hr - Reactor critical #373, Sequence B, Rod 26-11, notch 10, temperature 2150F, period 128 seconds.

1050 hr - Turbine on line February 26, 1979:

0205 hr "F" APR lifted at 98% power 0212 hr - Reactor manual scrammed February 27,.1979:

0337 hr - Reactor critical #374, seguence B, Rod 10-19, notch 05, temperature 192, period 84 seconds.

1040 hr - Turbine on line February 28, 1979:

2115 hr - Reactor power at 100%

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REFUEllf!G IllFORf!ATI0fl REQUEST 1.

flame of facility:

Millstone 1 2.

Scheduled date for next refueling shutdown:

790428 3.

Scheduled date for restart following 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' cencrating rate.

(2) Minimum critical power ratio.

(3) Automatic pressure relief valve mod. including new settings.

(4) Remove the 1.3% AK requirement' from rod dror, 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 148 retrofit 8x8 fuel assemblies purchased from General Electric.

7.

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

(a) In Core:

580 (b) In SFP:

29 8.

The present licensed spent 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:

Modification complete present storape caoacity for 2184 assemblies.

9.

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

1986 RilY:rmj b

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Docket No.

50-245 Date 790314 Page.1 of 1.

Unit Name Millstone - 1 e

Completed.By

a. ynync i

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Telephone 203 447-1792 ext. 475 CORRECTIVE MAINTENANCE

SUMMARY

FOR SAFETY RELATED EQUIPMENT Report Month February DATE SYSTEM COMPONENT MAINTENANCE ACTION 90212 Diesel Generator

' Jacket Water Pump Replaced mechanical seal 790222 Rx. Bldg.. Bridge Control Potentiometer Replaced' control potentiometer Crane 790223 Main Steam 1.-MS-lc & 1-MS-10 Replaced position. indicating micro-switches

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790223 -

Main Steam 1-MS-3A Replaced fitting on air tubing to bellows test solenoid.

790224 Isolation Condenser 1-IC-l Replaced valve operator'due to broken gear casing (R0-79-08/3L) 790227 Automatic Pressure _

l-MS-3F' Removed actuation b'ase assembly and replaced,

~ith spare (RO-79-05/1T) w Rel.i e f.

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