ML19210D660
| ML19210D660 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/15/1979 |
| From: | Merson S BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19210D655 | List: |
| References | |
| NUDOCS 7911270434 | |
| Download: ML19210D660 (19) | |
Text
.
OPERATING DATA REPORT DOCKET NO. Sr-117 DATE 11 " 5 /74 COMPLETED BY c.. n - " m an TELEPHONE 'm
-t'40 OPERATING STATUS Notes
- 1. Unit Name: c,1 vere citff In. 1
- 2. Reporting Period:
October, 1979
- 3. Licensed Thermal Power (MWt):
9.7on 418
- 4. Nameplate Rating (Gross MWe):
8'S
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): 365 810
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (items Number 3 Through 7)Since Last Report. Give Reasons:
~
740 MUE
- 9. Power Level To Which Restricted. If Anv (Net MWe):
Blade problems in the high-oressure turoine.
- 10. Reasons For Restrictions. If Any:
11 tis Month Yr..to.Date Cumulative
- 11. Hours in Reporting Period 7L5 7.?46 34,301
- 12. Number Of Hours Reactor Was Critical 7% 5 4.8"5 8 30."84 6 8.5 156.1 1,051.7
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line 7'1.1 4,701.7 10.243.7
- 15. Unit Reserve Shutdown llours 0.0 0.0 0.0
- 16. Gross Thermal Energy Generated (MWH) 1,816,24c.8 11,7 50, 7 4d.'-
73,020,952.8
- 17. Gross Electrical Energy Generated (MWH!
571,716 1,724,229 24,11c,5c4
~
565.313 1,541,665 22,996,653
- 18. Net Electrical Energy Generated (MMil) u7.1 64.5 77.0
- 19. Unit Service Factor 97.1 64.5 77.0
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Nett 40.4 54.9 72.2 86.6 57.4 6u.2
- 22. Unit Capacity FactorIUsing DER Net)
- 23. Unit Forced Outage Rate 2.4 17.6 9.4
- 24. Shutdowns Scheduled Over Next 6 Months tType. Date,and Duration of Each):
c,1 vert cliffa
o. 1 is sckeduled for.,,1,nned outaoe startin-Aoril lu. 1474 and will be six weeks in duration for general inspection and refueline.
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior o Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
~
1T98 BI C
- 9 (9/77) q W ~70 s'
OPERATING DATA REPORT DOCKET NO. Sn-3'8 DATE ' 1/15 / 7" COMPLETED BY.L n. 'eerson TELEP!!ONE
'o1
" t s240 OPERATING STATUS Calvert cliffs No. 2 Notes
- 1. Unit Name:
October, 1979
- 2. Reporting Period:
2,700
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWel:
'll 845
- 5. Design Electrical Rating (Net MWe):
8'3
- 6. Maximum Dependable Capacity (Gross MWe):
"n
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items 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..to.Date Cumulative 745 7,206 2?,656
- 11. Ifours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 281.0 6,305.6 19,248.1 c.0 193.7 ct3.1
- 13. Resetor Reserve Shutdown Hours
- 14. Hours Generator On.Line 281.0 6,190.1 lu,eet.9
- 15. Unit Reserve Shutdown flours 0.0 0.0 0.0 723,480.0 15,948,715.2 60,032,731.c
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated IMWH) 237.620 5,277,s28 15,531,900 i
- 18. Net Electrical Energy Generated (MWH) 225,114 5,040,602 14,tos,o31
- 19. Unit Service Factor 37.7 86.8 83.9 37.7 86.8 83.u
- 20. Unit Availability Factor
- 21. Unit Capacity Factor iUsing MDC Neti 37.3 85.3 80.7
- 22. Unit Capacity Factor IUsing DER Net) 35 8 81.8 77.4 1.4 6.2 6.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 MonthslType. Date.and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Dote of Startup:
Nov ener 26, 1979
- 26. Units In Test Status (Prior to Commercial Operationi:
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77) 1T98 332
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. }0117 UNIT NAME
( 41 ve rt t'l i f f c!1 DATE 11/1 W 1
COMPLETED BY % n."e r wn REPORT MONTH'ic t nbo r. 197')
TELEPHONE 301-N - W O e.
E E
.!'E
'k j E3 Licensee E*
l%
Cause & Corrective No.
Date h
3g g
jg5 Event E?
['3 a.
Action to 5
jgg Report 8r dIV Prevent Recurrence c5 74-12 741006 F
6.3 A
3 M/A Cll P;I"PXX Reactor tripped on lou steam genera-tor Icvel due to loss of power to tbc speed control circuit of No. 12 nenerator feed pumis.
7'l-t'l 741014 F
8.0 A
1
!!/A Cil PIPEXX Unit tripped due to a stean leak on extraction steam line to No. 15 A c B feedwater heaters.
70-14 741025 F
7.6 A
2 N/A HC PilllPXX Reactor tripped due to loss of j,ower to circulatinr, water pumps.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data
~A B-Maintenance ci Test 2-Manual Scram.
Entry Sheets for Licensee o
C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG-CD D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & Ucense Examination 1,.
F-Administrative 5
tj G4perational Error (Explain)
Exhibit I - Same Source 19/77) 110ther (Explain) g
50-118 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCHT NO.
UNITNAME cal vort ciif f d2 DATE
$/'sl'"
S D "' rson COMPLETED BY REPORT MONT11 o tober. I '< 7 9 c
TELEPHONE 101-214 'i?40 e.
?
2
.$E 3
jU Licensee Ev,
{%
Cause & Corrective No.
Date h
3g i
jg5 Event y
p Action to yE 5
j ig g Report
- mU g'
H Prevent Recurrence d
79-16 741012 F
4.0 B
1 N/A Z 7.
ZZZZZ7.
Ifnit trippe:1 while performiny low vacuum trip test.
74-17 70101?
S 460.00 C
4 N/A RC FUELXX Reactor refuelinr anil unit :.e ne ra l inspection. Plant was already shut down due to unit trin as stated above.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Inst ructions A
S. Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data 4
B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee Co C Refueling 3-Automatic Scram.
Event ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination
,]y F Administrative 5
p G-Operational Error (Explain)
Exhibit 1 - Same Source (9/77) llothei(Explain)
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 117 Calvert Cliffs #1 WIT 11/15/79 DATE S.D. "erson p
301-234-5240 TELEPHONE MONTil oremba" 1"7" DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 790 g
g7 789 2
717 18 8?6 3
c,c Ig n,n 4
666 20 826 715 824 5
21
'3" 6
22 822 668 7
23 823 8
686 24 sg3 9
684 25 442 697 725 10 26 757 728 yy 27 813 788 12 28 13 29 33 D"
14 30 7"'
796 15 31 3
16 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.
(9/77)
)b90
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-318 UNIT calvert Cliffs #2 DATE 11/15/79 COMPLETED BY c. n. "aren TELEPHONE 301-?34-5240 n tober, 1979 e
MONT11 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 791 g
g7 H11 2
18 3
- 36 19 648 20 4
833 5
21 6
83" 22 840 7
3 83" 8
24 8'1 9
25 10 26
~
lI 770 27 535 12 28 13
~
29 14 30 15 31 16 INSTRUCTIONS On this normato list the average daily unit power levelin MWe Net for each day in the reporting month. Comput: to the nearest whole megawatt.
~
(9/77) iz98 636
11/12/79 REFUELING INFORMATION REQUEST 1.
Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 1 2.
Scheduled date for next Refueling Shutdown:
April 19, 1980 3.
Scheduled date for restart following refueling: May 29, 1980 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such as to allow operation of the plant with a fresh reload batch and reshuffled core.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information.
February 22, 1980 6.
Important licensing considerations associated with refueling.
Reload fuel will be similar to that relcad fuel inserted into the previous cycle.
7.
The number of fuel assemblies (a) in the cora and (b) in the spent fuel storage pool.
(a) 217 (b) 364**
Spent Fuel Pools are common to Units 1 and 2.
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.
1056 Licensed 728 Currently Installed 650 Addition is Planned.
9.
The projected date of the last refueling that can be discharged to the Spent Fuel Pool assuming the present licensed capacity.
October, 1983.
- Information changed since last month.
1398 337
11/12/79 REFUELING INFORMATION REQUEST 1.
Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 2 2.
Scheduled date for next refueling shutdown:
October 14, 1979 3.
Scheduled date for restart following refueling: November 21, 1979 d.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
A preliminary review of the design and safety analysis indicate that no changes to the Technical Specification or other amendments are required and that there will be no unreviewed safety questions as defined by 10 CFR 50.59 involved with this reload core design.
5.
Scheduled date(s) for submitting proposed licensing action and supporting infomation.
At. gust 22, 1979 (if required).
6.
Important licensing considerations associated with refueling, None, reload fuel will be identical to that reload fuel inserted in the previous cycle.
7.
The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.
(a) 217 (b) 364**
Spent Fuel Pools are common to Units 1 and 2, 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been required or is planned, in number of fuel assemblies.
1056 Licensed 728 Currently Installed 650 Addition is Planned 9.
The projected date of the last refueling that can be discharged to the Spent Fuel Pool assuming the present licensed capacity.
October, 1983
- Infomation has changed since last month.
iW8 438
SUMMARY
OF UNIT 1 OPERATING EXPERIENCE - OCTOBER 1979 10/1 At the beginnino of this reportino period, Unit I was operating at 845 MWe with the Reactor at 100% power. At 2250 reduced load to 735 M'le to investigate salt water leakage into the main condenser.
Located and plugged one leaking tube.
10/2 Increased load to capacity (845 MWe) at 0930. Reduced load to 685 MWe at 1800 to investigate salt water leakage into the main condenser. Three leaking condenser tubes were pluoged.
10/6 At 1208 the Reactor tripped on low steam generator level due to loss of power to the speed control circuit of #12 Steam Generator Feed Pump. The Reactor was broucht critical at 1525 and the unit paralleled at 1824. Load was limited to 675 MWe at 2145 to investigate salt water leakage into the main condenser. Two leaking condenscr tubes were plugaed.
10/8 Started increasing power and at 0800 load was limited to 715 MWe to investicate salt water leakage into the Main condenser.
10/11 After plugging one condenser tube, started increasing load and at 1200 load was limited to G35 MWe due to the approach to core power distribution limits.
10/12 Increased load to capacity (845 We) at 0200.
~
10/14 Began reducing load at 0700 to repair a steam leak on the Extraction Steam Line to #15 A & B Feedwater Heaters. The unit was taken off the line at 1149. At 1950 the unit was paralleled.
10/15 Increased load to capacity (845 MWe) at 1900.
10/16 At 0500 load was reduced to 745 We to investigate salt water leakage into the main condenser.
i198 339
SUMMARY
OF UNIT 1 OPEPATING EXPERIENCE - OCTOBER 1979 10/17 Resumed full load operation (845 MWe) at 1500, after plugging one condenser tube.
10/25 The Reactor was manually tripped at 1103 due to loss of excitation to all Unit 1 'iain Circulating Water Pumes. At 1615, the Reacter was brought critical and the unit was paralleled at 1843. Started increasing load and at 2300 load was limited to 735 MWe to investigate salt water leakage into the main condenser.
10/27 Began increasing power after pluagirg one condenser tube and at 2100 load was limited to 825 MWe due to the approach to core power distribution limi ts.
10/30 Load was increased to 835 MWe at 0000.
10/31 At the end of this reporting period, Unit 1 was operating at 835 MWe with the Reactor at 97% power, power being limited by core power distribution limits.
1398 340 G
0
SUMMARY
OF UNIT 2 OPERATING EXPERIENCE - OCTOBER 1979 10/1 At the beginning of the reporting period Unit 2 was operating at 865 M4e with the Reactor at 100% power. At 2250 load was reduced to 735 Mle to investigate salt water leakace into the main condenser.
10/2 Resumed full load ooeration (865 MWe) at 0245, after pluggina one condenser tube.
10/4 At 0228 Control Element Assecely (CEA) #1 drcpped into the Core.
Reactor oower was immediately reduced to less than 70% in accordance with the Technical Specifications. CEA #1 was withdrawn back to its group at 0328. Began increasing power and at 2130 load was limited to 785 MWe due to the approach to core power distribution limits.
10/5 Increased load to capacity (875 Wie) at 0230.
0 10/10 Reduced load to 825 MWe due to the ETS 12 F limit on main condenser circulating water 6 T.
10/12 At 1701 the turbine tripped while conducting turbine low vacuum trip test. The Reactor tripped on loss of load. Comenced refuelina outage at this time.
10/13 The Unit was in cold shutdown at 1121.
10/19
'The Reactor Vessel Head was removed at 0230.
10/26 Refueling Operations were commenced at 0304.
10/31 At the end of this recorting period Unit 2 was shutdown for its second scheduled refuelina outage.
9
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SAFETY-RELATED MAINTENANCE UNIT I
GROUP I&C SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineerin9 Safety IC-79-103 8/1/79 Defective signal Block would not actuate Replaced the Features Actuation isolator isolator System / Steam Generator Isolation Signal Block
- 12 Steam Generator 0-79-2716 9/7/79 Dirty loop resistor Greater than 22 pound Cleaned the loop Pressure Indication terminals deviation between resistor terminals 1-PI-1023C channel 'C' and the other three channels Engineering Safety LC-79-075 9/10/79 Defective voltmeter Meter sticks and will Replaced voltmeter Features Actuation on module not respond System /#12 Steam i
Generator Isolation Signal Block Bistable l
Channel ZG
- 11 Emergency Core 0-79-2G96 9/5/79 Broken flapper arm on Fan running and salt Replaced flapper Cooling System / Room 1-TC-5404 temperature water valves open arm Air Temperature controller j
Cooler / Temperature Controls 1-TC-5404
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SAFETY-RELATED MAINTENANCE UNIT II GROUP IAC SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Reactor Protective IC-79-2079 8/15/79 Broken spring on push-Lights on trip module Replaced trip System / Steam Generator button reset assembly would not illuminate module Pressure Trip Module when a pretrip or trin Channel 'A' occurred Safety Injection Tank /
0-79-1737 7/31/79 Defective micro-switch, Valve position indica-Replaced the Bleed Off To Reactor for position indication tion would not indicate defective micro-Coolant Drain Tank the actual valve posi-switch Valve /2-CV-661 tion Refueling Water Tank /
IC-78-188 7/25/79 Defective voltage Narrow range level in-Replaced voltage Level Indication to current convertor dication would not in-to current con-2-LI-4142 and power supply dicate properly verter and power supply Safety Injection Tank 0-79-1847 7/30/79 Positioning arm for Intermediate position Adjusted the
' >4 Loop 12A Check Valve the open-close posi-indication when the positioning arm
'I)
Leakage Isolation tion indication was handswitch was in. shut C33 Valve 2-CV-638 out of adjustment position t~
b 4
SAFETY-RELATED MAINTENANCC UNIT II GROUP I&C SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Inj.ction Tank 0-79-1403 7/31/79 Positioner torque Valve was full open Reconnected posi-Check Valve Leakage motor spring was with only a 20% open tioner torque Drain Valve 2-CV-618 disconnected and signal motor spring and defective air supply replaced the air regulator supply regulator i
Demineralized Water 0-79-2300 7/28/79 Linkage from valve Valve would not control Adjusted linkage To Charging Pump positioner was out of properly and reconnected Suction Valve 2-CV-210X adjustment and output output from con-from controller to the troller to solenoid solenoid had broken loose I
Reactor Protective 0-79-2531 8/22/79 Defective rod drop Rod drop bistable in Replaced defective l
System Rod Drop Circuit assembly circuit card tripped condition for circuit card Channel 'A' no apparent reason i
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SAFETY-RELATED MAINTENANCE UNIT I
GROUP ELECTRIC SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION High Pressure Safety E-79-172 9/24/79 Movable contact for Motor operator was Adjusted the Injection Loop 11A valve operator motor single phasing when movable contact Isolation Valve 1-MOV-was misaligned valve was opening 617 t
Containment Spray Pump E-79-167 9/17/79 Motor winding was Caused an insulation Replaced motor Motor #12 rubbing against a break down and resulted with new one stationary part of the in the motor burning up motor Main Steam Isolation 0-79-3020 10/8/79 The pump unloader Control fuse in pump Replaced solenoid Valve Hydraulic Package valve, solenoid coil breaker Slew preventing valve coil and
- 12/#12 High Pressure had burned up the pump from starting control fuse Pump i
Service Water Cooling 0-79-2930 9/24/79 Defective auxiliary Pump would not start Replaced defective System /#13 Service switch in motor when it received a switch Water Pump breaker safety injection actua-
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tion signal
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SAFETY-RELATED MAINTENANCE UNIT I
GROUP ELECTRIC SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION
- 11 Main Steam Isola-0-79-2782 9/11/79 Defective solenoid Motor breaker control Replaced solenoid tion Valve Hydraulic valve coil in the fuses kept blowing coil Package /#12 High pump unloader valve preventing motor from Pressure Pump starting
- 11 Emergency Diesel 0-79-2266 7/24/79 Transformer T-54 When diesel generator Replaced the Ganerator primary side was was started smoke came transformer T-54 grounded from control cabinet I
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SAFETY-RELATED MAINTENANCE UNIT II GROUP ELECTRIC SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM CR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION
- 21 Charging Pump 0-79-2799 9/13/79 Loose fuse holder Pump motor breaker Adjusted the fuse Breaker would not trip remotely, clip for a tight connection
- 23 Containment 0-79-2722 9/7/79 Closing coil was The disconnect would not Replaced the de-Iodine Removal Unit /
burned up close from remote switch fective coil
- 24 Bus Disconnect 34 O
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SAFETY-RELATED MAINTENANCE UNIT II GROUP MACHINE SHOP MONTH October YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION
- 22 Servic~e Water 0-79-2667 9/5/79 Mechanical binding Valve would not open Shimmed between Heat Exhanger Saltwater fully actuator and valve Inlet Valve 2-CV-5152 to allow smooth operation of valve
- 21 Charging Pump 0-79-2568 8/24/79 Cyclic fatigue Excessive packing Replaced packing, leakage plungers, and associated seals
- 21 Main Steam 0-79-1680 8/1/79 2-SV-4044 was
- 21 main steam isolation Replaced 2-SV-4044 Isolation Valve sticki g took too long to close with new solenoid during partial stroke valve test O
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