ML19274D653

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Monthly Operating Rept for Jan 1979
ML19274D653
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 02/09/1979
From: Bair G
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML19274D652 List:
References
NUDOCS 7902210224
Download: ML19274D653 (9)


Text

f OPERATING DATA REPORT DOCKET NO.

50-344 DATE 2/9/79 C051PLETED BY G.

G. 3 air TELEPil0NE 503/ 55n-3713 Ext. 234 OPER ATING STATUS Notes Trojan Nuclear Plant

1. Unit Name:

Janu m 1070

2. Reporting Period:

3411

3. Licensed Thermal Power (5thcl:

1216

4. Nameplate Rating (Gross.\\lwe):

1130 S. Design Electrical Rating (Net SIWE).

1122

6. Staximum Dependable Capacity (Gross SIWE):

1080

7. Staximum Dependable Capacity (Net 5the):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report.Gise Reasons:
9. Power Level To Which Restric'd. If Any (Net 31We):
10. Reasons For Restrictions. If Any:

This Slonth Yr..to-Date Cumulatise 744 744 71192

11. liours In Reporting Period 726.6 726.6 11849.0
12. Number Of flours Reactor Was Critical 8.9 8.9 2171.8
13. Reactor Reserve Shutdown Hours
14. liours Generater On-Line 698.6 698.6 11230.0 0.5 0.5 1508.7
15. Unit Reserve Shutdown flours 2250511 2250511 34139730
16. Gross T;.ennal Energy Generated (31WH) 741200 741200 11191970
17. Gross Electrical Energy Generated (N1Wil) 706025 10472624 706025
18. Net Electrical Energy Generated (St% H) 93 9 93.9 53.0
19. Unit Senice Factor 94.0 94.0 60.2
20. Unit Asailability Factor 87.0 87.o 45.o
21. Unit Capacity Factor (Using alDC Net) 84.0 84.0 41 7
22. Unit Capacity Factor (Using DER Net) 1.8 1.8 37.7
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Oser Next 6 Slonths (Type. Date.and Duration of Each1
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status tPrior to Commercial Operation):

Forecast Achiesed NA NA INITIA L CRITICA LITY NA NA INITIAL ELECTRICITY CON 1%1ERCIAL Ol'ER ATION NA NA (9/77) 7 90 2 210 M7

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-344 UNIT Troian DATE 2/9/79 G. G. Bair CONtPLETED BY 503/556-3713

~

TELEPif0NE Extension Z34 StONTil Januarv, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

(%1We-Net )

(51We-Net) 1

-36 37 1082 2

140 1079 g3 1079 3

19 540 1080 4

904 1082 5

1084 1084 6

7 1081 33 1084 1087 1081 g

3 9

882 25 1080 10 561 1080 26 h,

1085 27 1079 I2 1086 28 1080 1085 1083 13 79 1082 1086 g,g 30 15 1082 1085 33 16 1082 INSTRUCTIONS On this format. fist the aserage daily umt power levelin 51We Net for each day in the reporting month. Compute to the nearest whole megawatt.

(4/77)

s DOCKETNO. d~

UNil S!IUlDOWNS AND POWER REDUCTIONS UNIT N AME Troinn DATE 2-09-79 COMPLETED fly G. G. P.11 r REPORT MONTil Ja mia ry. 1979 TELEPilONE 503/556-3713 Ext. 234 5

E jg 4 E 7d Licensee

,E n,

$*o Cause 1 Cor restive No.

Date g

3g j

,y5 lisent g?

93 Action to Report a mV E'

Prevent Recurrence yE 3 ;f3 H

=

t u

6 78-2 780526 S

32.1 B

NA 79-1 790102 S

0.5 U

NA NA Turbine overspeed test.

Reactor remained critical at 4% power.

79-2 790109 F

12.8 A

3 NA Loss of EllC power while working on the turbine generator thrust bearing wear detector. Motor ground blew fuse in EllC.

Replaced fuse and restored EllC power.

I i

2 3

4 f: Forced Reason:

Method:

1 xinbit G - instin<tions S: S,heduled A lipopnient Fadure(Lxplain) 1 -Man ual foi Piepaiation of Daia 11 Maintenance of I'est 2-Manual Scram.

Entry Sheets for 1.isensee C-Refochng 3 Automatic Scram.

Eveni Report (1.L Rl 1:ile (NUREG-D Regniatory Resiiiction 4 Other (Ex;' lain) 0161I l~-Operator 1:aimng & lacense lixamination F AJministratne 5

G-Operational Lrior (Explain)

Estubti I - Same Source (9/77)

Il-Ot her ( E xplaud

DOCKET No:

50-344 DATE:

2-09-79 COMPLETED BY:

G. G. Bair TELEPHONE:

(503)S56-3713 Extension 234

SUMMARY

OF OPERATING EXPERIENCE OPERATION:

The month began with the reactor critical and undergoing reload startup testing.

Zero power physics tests and turbine overspeed testing was completed by 1108 on January 2, 1979 and power escalation and at-power testing began. The power escalation rate was 37. p e t-hour due to limits of fuel pellet-clad interaction.

Full power was attained at 0100 on January 6, 1979 and testing was co:.qpleted.

A primary-to-secondary lead was detected on the "B" steam generator on January 5, 1979.

Leakage rate is 1 gpd.

This leak could be the same leak detected during Cycle I, and could have resulted from a leak in the plug inserted during Cycle I-II refueling. The reactor tripped on January 9, 1979 from a loss of EHC power while working on the turbine thrust bearing wear detector and recovery was delayed due to problems with defective fuses in the rod control system.

Full pcwer was again attained at 1615 on January 10, 1979 and was maintained for the rest of the month.

MAJOR SAFETY-RELATED MAINTENA' ICE:

Work continued on improvement modifications to the plant security system. The PDP charging pump valves and oil seal that had worn out were replaced. Work continued on the installation of an additional air compressor for plant instrument and service air requirements. An improved motor for the boric acid transfer pump was installed to enhance pump reliability. Work began on the replacement of the old (21" center) spent 'uel racks with new (13.3" center) spent fuel racks.

LICENSE CHANGES:

None MISCELLANEOUS:

The control room annunciating system-for the emergency diesel generators was altered at the request of the NRC to provide an additional alarm in the control room for diesel generator trouble.

A steam leak developed and was repaired on the "C" feedwater isolation valve.