ML19339C471
| ML19339C471 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 11/10/1980 |
| From: | Whitney G BOSTON EDISON CO. |
| To: | |
| Shared Package | |
| ML19339C468 | List: |
| References | |
| NUDOCS 8011180434 | |
| Download: ML19339C471 (6) | |
Text
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O OPERATING DATA REPORT i
DOCKET NO. 50-293 DATE 11/10/80 COMPLETED BY f.G. Whitney TELEPHONE 617-746-7900 OPERATING STATUS Pilgrim I Notes g, gg,
October. N
- 2. Reporting Penod, 1S)8.
- 3. Licensed Thermal Power (MWt):
D#0*
- 4. Namepiste Rating (Gross MWe):
655.
- 5. Design Electncal Rating (Net MWe):
690.
- 6. Maximum Dependable Capacity (Gross MWe):
670.
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Nuneber 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restricted. If Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
N/A This Month Yr to Date Cumulative 745.0 7320.0
-69216.0
- 11. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 599.1 3855.9 48836.8
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0
- 14. Hours Generator on-Line 581.0 3694.8 47247.3 l
- 15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1117080.0 6734016.0 79825128.0 388440.0 2306010.0 264/0644.0
- 17. Gross Electrical Enerly Generated (MWH)
- 18. Net Electrical Energy Generated (MWH) 373919.0 2217942.0 25424065.0
- 19. Unit Service Factor 78.0 50.5 66.J
- 20. Unit Availability Factor 78.0 50.5 68.3
- 21. Ifnit Capacity Factor (Using MDC Net) 74.9 45.2 54.8 76.6 46.3 56.1
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 22.0 6.7 10.4
- 24. Chutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each):
None
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup-
"ni r ONmtine
- 26. Units in Test Status IPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION I
I 3180
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-293 (JNIT Pilgrim 1 11/10/80 l
DM COMPLETED BY G.G. Whitney 6 U-M-M00 TELEPHONE October, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe. Net) 95.
697.
1 37 O.33-697.
697.
0.
39 3
696.
0.
20 4
0.
695.
5
,3 409.
695.
6 114.
695.
,3 685.
3 24 600.
668.
9 3
079*
0 I*
10 26 695.
696.
1g 7
12 696.
23 697.
696.
697.
g3
,9 695.
698.
y 30 697.
343.
15 31 695.
16 INSTRUCTIONS On t!us format.!ist the average daily unit power level in MWe Net for each day in the repomns month. Campute to the nearest whole rneezwart.
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DOCKET NO. 50-294 LINil SilullM)WNS AND POWER REDtlCllONS tlNI I N A M E Pfl erf ra 1 DATE.11/10/80 REPORT MONIll Oc tobe r, 1980 COMPLETED BY G.G. Whitney
'IELEPilONE 617-746-7900
=
a c
jE 3
- E3 1.icensee
L Cause & Coniedive No.
Date Q
3g R
3s&
7
^ " " " ' "
Evens g
Eo Present Recurrence b
fiE E
3 ;f, c Repius #
mO o
}
U e
6 9
80/10/01 F
.18.6 11 3
N.A.
IA NA Air bubble in Feedwater System 0
/ /
0.0 Caused liigh Radiation trip. tbnitor trip was found to be set too low.
Ibnitor was recalibrated.
10 80/10/07 F
33.3 A
1 80-69/0lT-0 SF VALVEX liigh N2 Pressure to SV caused SRV
'* '' ' * * " 0 "" 0 '
0
/ /
0.0 11 80/10/71 F
12.1 A
1 80-80/0IX-0 SF VALVEX Same scenario as LER 80-69/0IT l
I 1
3 4
F: Fmced Reason:
Method:
Exhibit G -Instrudiims S: Stheduled A-Equipment Failure (Explain) 1 Manual for Pseparation of Data B-Maintenance of Test 2-Manual Scram.
Entiy Sheels for 1.icensee C-Refueling 3 Automatic Scram.
Event Repose (LER) File iNtlRI G-D-Regulaimy Restriction 4 Other (Explain) 0161)
E-Operator Training & License Examination F-Administ rative 5
l G Operational Estor (Explain)
Eshibis 1 Same Sou ce 19f77) ll Othes (Explain)
i RN!! LUG UFORM/JION De follcwing refueling information is included in the Monthly Report as requested in a letter to Mr. G. C. Andognini dated January 18, 1973:
For your convenience, the information supplied has been enumerated so that each number corresponda to equivelant notation utilize, in the request.
1.
De name of this ' facility is 711 grim Nuclear Pever Station, Docket No.' 50-293.
2.
Scheduled date for next Refueling Shutdown:
September, 1981 3.
Scheduled date for restart following refueling:
4.
5.
Due to their similarity, requests 4, 5, & 6 are responded to collectirely-6.
De fuel, which ha_d been loaded during -J:e 19,80_ scheduled refueling outage, is of the cow iSx83, design, consisting of approx 1=ataly 64 ?8DR3282 assemblies and 120 PSDR3265 assemblies.
7.
(a) nere are 580 fuel assemblies in the core.
(b) nere are 764 fuel assemblies is the spent fuel pool.
8.-
(a) ne station is presently licensed to score 2320 spent fuel asse=blies.
ne actual spent fuel storage capacity is 1770 fuel assemblies at present.
(b) ne planned spent fuel storage capacity is 2320 fuel assemblies.
9.
With present spent fuel in storage, the spent fuel pool new has the espacit7 to accommodate an addi:1cual 1006 fuel assemblies.
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BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION '
Summary of Operations for October 1980 The reactor was in the cold shutdown mode the first five days of the month while repairs were made to "D" Relief Valve. The reactor scrammed on Oct. 1, due to high radiation at the main steam lines. This was caused by a bubble of air that was entrained in the feedwater system during condensate demineralizer operation. During this transient, "D" Relief Valve was operated and failed to close.
The unit was returned to service on Oct. 5, and power was increased to about 96%. The reactor was manually scrammed on Tuesday, Oct. 7, due to an in-advertent opening of "A" Relief Valve, which also failed to close. The cause of "A" Relief Valve opening was determined to be caused by the instrument nitrogen supply being too high in pressure.
The unit was returned to service on Wednesday, Oct. 8.
Power was increased to 100% and maintained until Sunday, Oct. 26, when the power was reduced to 50%
to backwash the main condenser. The power was returned to 100% Monday Oct. 27, and maintained until Friday Oct. 31, when the reactor was scrammed due to in-advertent opening of "A" Relief Valve again. The cause of the valve opening was again, the instrument nitrogen system, at too high a pressure. Investigation revealed that a nitrogen delivery was being received at the time, and valve operation caused the pressure increase. The system is now isolated and a relief valve is being installed to prevent recurrence of this problem.
^
2 PILCRIM NUCLEAR POWER STATION Month Qctober, 1980 IfA10R SAFETY RELATED MAINTENANCE t
'STRI COMPONENT MALFUNCTION CAUSE MAINTENANCE CORRECTIVE ACTION ASSOCIATED LER e n v n rv ru r u v erJn n r eer I
"D" Relief-Valw Failed to close Dirt Replaced Valve 80-79/03L-0 1
"A" Relief.Valvt Opened & Failed to liigh N2 Tested & Reduced Engineering Investigation underway 80-6g/0lTe0 Close Pressure N
Pressur 2
80-80/0lX-0 30 "B" RBCCW lient Reduced Flow Plugged Cleaned Tubes witi: Routine cleaning due to expected Exchanger
. Tubes Air / Water & Rod fouling with use.
30 "A" RBCCW lleat Reduced Flow Plugged Cleaned Tubes witi Routine cleaning due to expected Exchanger Tubes Air / Water & Rod -
fouling with. use.
Found Two Leaking Tubes 23 IIPCI Turbine Failure 'of Overspeed Damaged Tap-Replaced Damaged N/A Trip pit-assembly Part in overspeed trin mechanism 4
4 6
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