ML19329G294
| ML19329G294 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 07/01/1980 |
| From: | Bair G PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19329G292 | List: |
| References | |
| NUDOCS 8007140315 | |
| Download: ML19329G294 (5) | |
Text
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OPERATING DATA REPORT DOCKET NO.
50-344 DATE 7-1-Ro
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COMPLETED BY c c n,4r TELEPHONE 503/556-3713 Ext. 234 OPERATING STATUS
- 1. Unit Name:
Trainn Nuc1anr l'1 ant 3"ne lo80
- 2. Reporting Period:
- 3. Licensed ThermsI Power'(MWt):
1411 1216
- 4. Nameplate Rating (Gross MWe):
1130
- 5. Design Electrical Rating (Net MWe):
.~
- 6. Maximum Dependable Capscity (Gross MWe):
J199 1080
- 7. Maximum Dependsble Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
0
' 9. Power Level To Which Restricted.-If Any (Net MWe): questions regardine seismic intergrity of NRC licensing
- 10. Reasons For Restrictions.lf Any:
~
- 18. 1980.
,"v414 nn kn41d4ne un11s.has nandated shutdown bevond June
' Iliis Month Yr.-to-Date Cumulative
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790 4367 33575
- 11. Hours in Reporting Period 0
2422 18720
- 12. Number Of Hours Reactor Was Critical 2171.8 0
0
- 13. Reactor Reserve Shutdown Hours 0
2416.7 18044.5
. - 14. Hours Generstcr On.Line 0
0 1508.7
- 15. Unit Reserve Shutdown Hours 6
6839434 55735043
- 16. Gross Therms! Energy Generated (MWH) 0 2203790 18189205
- 17. Gross Electrical Energy Generated (MWH)
-3638 2088895 17122214
- 18. Net Electrical Energy Generated (MWH) n 99 3 53.7
' 19. Unit Service Factor 0
55.3 58.2
- 20. Unit Availability Factor 44.3-47.3 0
- 21. Unit Capacity Factor (Using MDC Net) n 42.3 45.1
- 22. Unit Capscity Factor (Using DER Net) 100 8.2 28.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date'.snd Duration of Esch):
3
% e4~_, mnaffic,rinns from TMI. October 1980. 30 davs T"tv 12. 1980
- 25. If Shut Down At End Of Report Period. Estimated Date of Stsrtup:
- 26. Units In Test Status (Prior to Commercial Operstion):
Forecast
- Achieved m
n INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION
-(9/77) f 8007140.3/5-
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-344 UNIT Troian DATE July 1, 1980 COMPLETED ilY C-C-
Rair TELEPl10NE 503/556-3713 Extension 234 MONTil T"~
10R0 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 1
-5 37
-6*
2'
-4 Ig
-6 3
-4 19
-6
~6 4
-6 20
-6
-5 3
21 6
-6 22
-2 23
-6 7
8
-2 24
-6 9
-9 25
-6 10
-5 26
-6 11
-5 27 12
-6 28
-6 13
-4 29
-5 14
-5 30
-5 15
-4 NA 31 16
' -6 INSTRUCTIONS On this format. list the averaSe daily unit power level in MWe Net for each - y in the rep >rting month. Compute to the nearest whole nwgswatt.
(9/77)
UNIT SIIUTDOWNS AND POWER REDUCTIONS '
DOCKET NO. 50-344 UNIT NAME Troinn DATE Tuly 1_
1onn _,
COMPLETED IlY G G.
Bair REPORT MONTIf June 1980 TELEPIIONE sn1/ss6 171t Extension 234 u -
"t.
o
,5. ?
3 3 55 Licensee Et,
$k Cause & Corrective
))
3g n
g5 Event u?
9 Action to No.
Daic o.N
$=
5 jg g.
. Report #
At Prevent Recurrence 5
80-04 800411 S
528 C
1 NA NA NA; NA NA 800622 F
192 D
NA LER -80207 NA NA NA i
I 2
3 4-F: Forced Reason:
Method:
Exhibit G-Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data 2 Manual Scram.
Entry Sheets for Licensee B-Maintenance of Test C. Refueling 3-Automatic Sc.am.
Event ReporI(LER) File (NUREG-D-Regulatory Restrie ion 4 Other(Explain) 0161),
r E-Operator Training & License Examinatiori
~
G-Operational Error (Explain)
~ 5 F-Administrative Exhibit I Same Sourec (9/77) ll-Other (Explain)
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o ; 3*
DOCKET NO:
50-344.
DATE: July 1, 1980 COMPLETED BY:
G. G. Bair TELEPHONE:
5034556-7313 EXT. 234
SUMMARY
OF OPERATING EXPERIENCE OPERATION:
The plant began the month in Refueling shutdown and ended the nonth in Cold shutdown.
The plant is ready to begin heatup on June 18, 1980, but was prevented from doing so by the NRC due to problems identified with the seismic
' integrity ' of ~ the Auxiliary building walls.
MAJOR SAFETY-RELATED MAINTENANCE:
J Work continued on improvement modifications to the Plant Security and' Fire Protection Systems.
Work completed on the: removal of 29 steam generator D row 1 tubes for analysis.
Work completed on stemm generator eddy current testing and resulted in the plugging of 15 tubes in addition to the 29 cut-out tubes.
Work completed on Local Leak Rate Testing.
Work continued on modification of walls and pipe restraints.
Work continued on several TMI-related design modifications-(RV head vent, RV water level, containment water level, post LOCA environment electrical equipment, safe shutdown remote instrumentation and decouple switches, separate power supply to steam PORV and AFWP. pressure instrument.)
Work completed on steam-driven auxiliary feedwater pump wheel and self-cooling
. modification.
Work. completed on endurance testing of the emergency diesel generators and auxiliary.feedwater diesel.
Work completed on-the repair of the RHR pump shaft damage that had occurred when a weld rod in the coolant mechanically interfered with the pump rotating parts.
LICENSE CHANGES:
Amendment #44;revisedthepowerdistributionlimits,F[HandF and changed xy the control rod insertion limits.
Amendment #45; revised fuel design specification to allow two region E 4
assemblies to be loaded with stainless-steel pins in place of three periphery pins.
MISCELLANEOUS:
The south main feedwater pump was repaired after having previously thrown a turbine blade.
The motor driven auxiliary feedwater pump was installed.
The Reactor Coolant Pump oil drip pan modification was installed. partially.
Mt.'St. Helens continued to exhibit small amounts of volcanic activity with no impact on the Irojan Plant.
,r
C 9
Dockst No.
50-344 D te 7-1-80 Completed by: G. G. Bair Telephone:
(503) 556-3713 X-234 REFUELING INFORKiTION REQUEST 1.
Name of facility:
Trojan Nuclear Plant 2.
Scheduled date for next refueling shutdown:
April 1981 3.
Scheduled date for restart following refueling:
July 12, 1980 4.
Will refueling or resumption of operation thereafter require a techni-cal specification change or other license amendment?
-Yes If answer is yes, what, in general, will these be?
Hot channel factors change; rod insertion limit change; stainless-steel
~
rods in two fuel assemblies.
If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Reference 10 CFR Section 50.59)?
NA~
If no such review has taken place, when is it scheduled?
NA 5.
Scheduled date(s) for submitted proposed licensing action and supporting information:
Already submitted 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:
2 fuel assemblies received 3 stainless-steel rods each in place of fuel pins due to vessel internals baffle-plate gap water jetting.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
~
(a) 193 (b) 128 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:
651
- 9..The projected date of the last refuelit g that can be discharged to the spent fuel pool assuming'the present licensed capacity:
April 1988
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