ML20069A053
| ML20069A053 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 02/04/1983 |
| From: | Angert E ROCHESTER GAS & ELECTRIC CORP. |
| To: | |
| Shared Package | |
| ML20069A039 | List: |
| References | |
| NUDOCS 8303150519 | |
| Download: ML20069A053 (5) | |
Text
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-I-OPERATING DATA REPORT DOCKET NO.
50-244 DATE February 4, 1983 COMPLETED BY M Ellen Angert O 1 (315) 524-4446 TELEPilONE OPERATING STATUS Ext. 206
- 1. Unit Name:
GINNA STATION UNIT #1 Notes The reactor power level 2.' Reporting Period:
January,D983 ms maintained at 100% until 1520 1/17 when a unit trip occurred.
- 3. Licensed Thermal Power (MWr):
The subsequent power fluctua-490
- 4. Nameplate Rating (Gross MWe):
t; ions and steps in return to 479
- 5. Design Electrical Rating (Net MWe):
full power are detailed on 490
- 6. Maximum Dependable Capacity (Gross MWe):
Page 4.
40
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Irems Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level to Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any:
This Month Yr..t o-Da te Cumulative 744 744 115,560.00
- 11. Ilours in Reporting Period 727.03 727.03 87,613.18
- 12. Number of flours Reactor Was Critical 0
0 1.631.32 *
- 13. Reactor Reserve Shutdown flours 724.25 724.25 85,704.38
- 14. Ilours Generator On.Line 0
8.5 *
- 15. Unit Reserve Shutdown llours 996,120 996,120 117,578,674
- 16. Gross Thermal Energy Generated (MWil) 324,932 324,932 38,291,729
- 17. Gross Electrical Energy Generated (MWII) 308,021 308,021 36,294,083
- 18. Net Electrical Energy Generated (MWil) 97.35%
97.35%
74.16%
- 19. Unit Service Factor 97.35%
97.35%
74.17%
- 20. Unit Availability Factor 88.09%
88.09%
68.73%
- 21. Unit Capacity Factor (Using MDC Net) 88.09%
88.09%
68.73%
- 22. Unit Capacity Factor (Using D'ER Net) 2.7%
2.7%
8.47%
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each):
Mid March - 1983 - Refueling and Maintenance
- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- Cumm21ative Total cotmencing January 1,1975
..... m v.
i n.,
E303150519 830204 PDR ADOCK 05000244 R
. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-244 UNIT
- 1, Ginna Station DATE February 4, 1983 COMPLETED BY 2(fen (jd4 Ellen Angeny TELEPHONE 1 (315) 524-4446 Ext. 206 at Ginna MONTH January, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Ne t) 1.
476 17.
454 2.
476 18, 124 3.
475 19.
453 4.
474 20.
242 5.
475 21.
356 6.
475 22.
472 7.
475 23.
473 8.
475 24.
407 9.
475 25.
238 10.
474 26.
242 11.
475 27.
240 12.
475 28.
379 13.
475 29.
472 14.
475 30.
472 15.
475 31.
471 16.
475 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.
Compute to the nearest whole megawatt.
i D(X:KET NO.
50-144 UNIT NAMis.#1,Ginna Station UNIT SHUTDOWN AND POWER REDUCTIONS DATE Febnnry 4 1983__
1 COMPLETED itY Nb Ellen An m REPORT hlONTil Jantnry, 1983 7ptypgiosg 1 (315) 524-4446 Ext. 206 m
5m
!2 I
Licensee e,
No.
Da te
{
jj
}.E Cause 8. Corrective e
E Event
{4 1 -3 Action to H
f Z_
y e @ c.
Report #
y
[v Prevent Recurrence 2
g u
O 1
1/17/83 F
19.75 A
3 83-7 m
I Instru)
Reactor trip followed by turbine trip, due to low (A) Steam Generator level, plus steam flow / feed flow misnutch.
1*
1/24/83 F
80.75 A
N/A G
(Punp XX)
"A" bhin feedwater punp - Excessive vibrations - Replaced Inpeller runner. Reactor power level at
~ 55% during the reduction period.
1 2
3 4
F: Forced Reason:
Afethod:
Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1 -hfanual for Preparation of Data ll-hfaintenance or Test 2-klanual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G-Operational Error (Explain) w 4969 t R E V.1/7 8)
II*Other (Explain)
Exhibit 1 - Same Source
- Significant power reduction a.
.~
. NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE DOCKET NO.
50-244 UNIT Ginna Station, Unit 41 DATE Febrpary 4, 1983 COMPLETED BY
- fh & M Ellen Anger (
TELEPHONE 1 (315) 524-4446 EXT. 206 MONTH JANUARY, 1983 The reactor power level was maintained at 100% until 1/17/83.
On 1/17/83 @ 1124 a unit trip occurred due to "A" Steam Generator Lo Steam Generator level and feedwater flow - steam flow mismatch.
Reactor startup began @ 0213 (1/18/83) and was brought critical @ 0246.
A reactor trip occurred @ 0353 due to Lo Lo Steam Generator level.
The reactor was again started at 0502 (1/18/83) and again brought critical at 0528.
Power increase began and Turbine Generator was on line at 0717 (1/18 /8 3 ).
Escalation of unit power followed and the unit was at 25% by 1240 (1/18 /83).
Load decrease to 35 MWe 0 1430 (1/18/83) followed due to problems with Solenoids on feedwater regulator valves.
Load increase began again at 1603 (1/18/83) and the unit power was brought to 100% by 1202 (1/19 /83).
On 1/20/83 0 0511 load reduction began due to Lo-Lo Screenhouse water level.
Load was reduced to ~ 26% by 1030 (1/20/83).
Load increase began again at 1300 (1/20/83) and the unit was returned to full power by 1330 on 1/21/83.
On 1/24/83 @ 2152 the A main feed pump tripped out manually
' to excessive vibrations after load decrease to < 50% power (1/24/8 4,
.ower level was maintained at 55% during the reduction period, while tne A main feed pump impeller runner was replaced.
The unit was returned to full power by 1425 on 1/28/83.
The unit remained at full power for the rest of the reporting period.
't Paga 5 GINNA STATIO_N Maintenance Report Summary January, 1983 During January, routine maintenance and inspections were completed.
As a result of the plant trip on'1/17/83, repairs were completed on the Steam Generator Programmed Level Setpoint Module and
-an I/P cell for the "B" Steam Generator Main Feedwater Regulating Valve.
Also completed after the trip was the replacement of faulty air solenoid valves on both Main Pe?dwater Regulating Valves.
During the week of 1/24/83, a power reduction was made to complete a maior inspection and repair on the "A" Main Feedwater Pump,'which had experienced an increase in vibration.
I