ML19296B732
| ML19296B732 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/14/1980 |
| From: | Merson S BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML19296B728 | List: |
| References | |
| NUDOCS 8002210428 | |
| Download: ML19296B732 (13) | |
Text
I OPERATING DATA REPORT DOCKET NO. 50-317 DATE 2/14/80 COMPLETED BY S. D. Merson TELEPHONE 101 ?14-5240 OPERATING STATUS Calvert Cliffs No. 1 Notes
- 1. Unit Name:
- 2. Reporting Period:
Januarv, 1980
- 3. Licensed Thermal Power (MWt):
2,700 918
- 4. Nameplate Rating (Gross MWei 845
- 5. Design Electrical Rating (Net MWe):
845
- 6. Maximum Dependable Capacity iGross MWe):
810
- 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): variaus loads
- 10. Reasons For Restrictions.lf Any: No. 1 Plant was ooerating at various forced reductions due to uneoual oower distribution of the core and turbine blade problems. The forced reduction due to unequal distribution of the core ended 1/25/80 when the Plant was eported on a planned outage for TMI Modifications, as required by NRC.
This Month Yr.-to.Date Cumulative II. Hours in Reporting Period 744.0 744.0 41,509
- 12. Number Of Hours Reactor Was Critical 600.4 600.4 33,040.0
- 13. Reactor Reserve Shutdown Hours n0 0.0 1.060.5
- 14. Hours Generator On.Line 600.0 600.0 32,302
- 15. Unit Reserve Shutdown llours
- 16. Gross Thermal Energy Generated IMWH) 929.726.4 929,726.4 76,266,715.2
- 17. Gross Electrical Energy Generated (MWH) 272,128 272,128 25,084,658 250,462 250,462 23,899,000
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor 80.7 80.7 77.8 80.7 80.7 77.8
- 20. Unit Availability Factor
- 21. Unit Capacity Factor iUsing MDC Nett 41.6 41.6 71.1 39.8 39.8 68.1
- 22. Unit Capacity FactoriUsing DER Net)
- 23. Unit Forced Outage Rate 0.0 0.0 8.9
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
- 25. If Shur Down At End Of Report Period. Estimated Date of Startup:
3/3/80
- 26. Units in Test Status (Prior :o Commercial Operationi:
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)
S002210 U Qg -
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
UNIT Calvert Cliffs #1 2/14/80 DATE COMPLETED BY
- s. D. Merson TELEPHONE 301-234-5240 MONTH January, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-NetI 356 350 g
g7 363 353 2
18 431 3
gg 354 356 4
437 20 436 357 5
21 360 6
442 22 451 361 7
g 8
m?6 24 360 332 9
526 15 10 596 26 11 925 27 11 522 23 523 13 29
~
14 525 30 15 376 31 354 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)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
50-317 UNIT NAME ca lve rt C11ffs #1 DATE 2/14/80 COMPLETED BY S-D-
Mnrson REPORT MONTil Januarv-1980 TELEPIIONE int _?14 s76n e.
.$E 3
hY Licensee Eg g
Cause & Corrective No.
Date h
5g i
25m Event p
g{
Action to yE 5
j ;?, g Report ar mV H
Prevent Recurrence 6
79-15 791108 F
600.0 11 4
RC ZZZZZz Forced Reductions to Various Loads Due to Unequal Power Distribution of the Core.
80-01 800125 S
144.0 D
1 ZZ ZZZZZZ To Perform TMI Modifications as Required by NRC.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G - Instructions S: Scheduled A Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram-Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event Report iLER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F-Administrative 5
G Operational Error (Explain)
Exhibit I - Same Sour:e (9/77)
Il-Other (Explain)
~
2/12/80 REFUELING INFORMATION REQUEST 1.
Name of Facility:
Calvert Cliffs Nuclear Power Plant, Unit No.1 2.
Scheduled date for next Refueling Shutdown:
October 15, 1980**
3.
Scheduled date for restart following refueling: December 3, 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.
September 4, 1980**
6.
Important licensing considerations associated with the refueling.
Reload fuel will be similar to that reload fuel inserted into 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 comon 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.
- Infonnation has changed since last report.
JANUARY 1980
SUMMARY
OF UNIT 1 OPERATING EXPERIENCE 1/1 At the beginning of this reporting period, Unit I was operating at 385 MWe with the Reactor at 50% power, continuing further testing and analysis of the power distribution anomaly.
1/3 Increased load to 465 MWe (60% power) for further testing and analysis of the power distribution anomaly at 0001.
1/8 Load was increased to 560 MWe (70% power) for further testing and analysis of the power distribution anomaly at 0100.
1/15 After completing testing at 70% power, load was reduced to 385 MWe at 0510.
1/25 The Unit was taken off the line at 2357 for installation of NRC required plant modifications. (NUREG 0578) 1/26 The Reactor wae shutdown at 0025.
1/27 The Reactor,
placed in cold shutdown at 2012.
1/30 Completed draining the Reactor Coolant System at 1900.
1/31 At the end of this reporting period, Unit I was shutdown for installation of NRC required plant modifications.
SAFETY-RELATED MAINTENANCE UNIT I
GROUP
'E' Shop MONTH January YEAR 80 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION DIESEL GENERATOR BREAKER 0-79-4488 Defective Auxiliary Shutdown Sequencer Replaced Defective 152-1103 12-3-79 Switch "MJ" in Breaker Initiated on Unit One Switch With New One Circuit Logic Cabinet 'A' e
e.
6
SAFETY-RELATED MAINTENANCE i
UNIT I
GROUP IAC MONTH Januarv YEAR 80 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION COMP NENT COOLING 0-79-2974 Out of Adjustment, and The Hand Controller Did Made Zero Adjustment SYSTEM /1-CV-5206 10-8-79 Air Leak On Actuator Not Control the Valve and Repaired the Air Properly Leak On the Actuator e
1 D
9 e
O t
g r
t OPERATING DATA REPORT DOCKET NO. 50-318 DATE 2/14/80 COMPLETED BY s. D. Merson TELEPHONE 1ru_9,6 5240 OPERATING STATUS Calvert Cliffs No. 2 Notes
- 1. Unit Name:
- 2. Reporting Period:
January, 1980
- 3. Licensed Thermal Power (MWt):
2,700 911
- 4. Nameplate Rating (Gross MWe):
845
- 5. Design Electrical Rating (Net MWe):
860
- 6. Maximum Dependable Capacity (Gross MWe):
825
- 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:
9 Plant was reported out of service on a planned outage from 1/12/80 until 1/21/80 to perform TMI Modification as required by mm r.
This Month Yr.-to-Date Cumulative 744.0 744.0 24,864.0
- 11. Hours in Reporting Period 524.9 524.9 20,46 9.8
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours 0.0 0.0 413.1
- 14. Hours Generator On.Line 516.7 516.7 20,125.2
- 15. Unit Reserve Shutdown flours
- 16. Gross Thermal Energy Generated (MWH) 1,357,176.0 1,357,176.0 49,601,407.8 454,186 454,186 16,459,409
- 17. Gross Electrical Energy Generated (MWHI
- 18. Net Electrical Energy Generated (MWH) 433,092 433 #92 15,690,112
- 19. Ur.it Service Factor 69.5 69.5 80.9
- 20. Unit Availability Factor 69.5 69.5 80.9 70.6 70.6 76.)
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor tUsing DER Net) 68.9 68.9 74.7
- 23. Unit Forced Outage Rate 0.0 0.0 6.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial OperationI:
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (0/77)
.... i..
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-318 UNIT Calvert Cliffs #1 2/14/80 DATE COMPLETED BY S. D. Merson 301-234-5240 TELEPHONE MONTH Ja nua ry, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 863
,7 2
864 18 3
863 39 863 4
20 5
R62 21 138 6
861 799 22 860 845 7
3 860 856 8
24 861 858 9
25 10 863 26 859 840 860 3g 27 12
~
28 859 13 29 0
I4 30 15 31 852 16 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77)
DOCKETNO. 50-318 UNIT SHUTDOWNS AND POWER REDUC 110NS UNITNAME 'a lvert cliffs #2 DATE 2/14/80 UU REPORT MONT11 Januarv. 1980 TELEPHONE 301-234-5240 e.
E E
.$ E 3
jY3 Licensee Ev, je.
Cause & Corrective No.
Date k
3g
,3 g 5 Event gg Q
Actitm to F
f E
j gg g Report a mu Prevent Recurrence g
d 80-01 800112 S
227.5 D
1 ZZ ZZZZZZ To Perform THI Modification as Required by NRC.
I 2
3 4
F: Forced Reason:
Method:
Exhibit G. Instructions S: Scheduled A-Equipment Failure (Explaia)
I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.
Entry Sheets for Licensee C-Refueling 3-Automatic Scram.
Event ReporI (LER) File (NUREG.
D-Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F Administrative 5
G-Operational Error (Explain)
Exhibit I - Same Source (9/77) llother (Explain)
2/12/80 REFUELING INFORMATION REQUEST 1.
Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No. 2 2.
Scheduled date for next refueling shutdown:
January 1,1981**
3.
Scheduled date for restart following refueling: February 18, 1981**
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.
November 20, 1980**
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 report.
JANUARY 1980
SUMMARY
OF UNIT 2 OPERATING EXPERIENCE 1/1 At the beginning of this reporting period, Unit 2 was operating at 895 MWe with the Reactor at 100% power.
1/12 The Unit was taken off the line at 0130 and the Reactor shutdown at 0230 for installation of NRC required plant modifications (NUREG - 0578). The Reactor was placed in cold shutdown at 1700.
1/20 Started heatup of the Reactor Coolant System at 0958. At 2030, Reactor Coolant System heatup was completed.
1/21 The Reactor was brought critical at 0535 and the Unit paralleled at 1245.
1/22 Increased load to capacity (895 MWe) at 0700. At 2145, reduced load to 835 MWe to investigate saltwater leakage into the main condenser.
1/23 After plugging one leaking condenser tube, full load operation (895 MWe) was resumed at 0500.
1/31 At the end of this reporting period, Unit 2 was operating at 895 MWe with the Reactor at 100% power.
SAFETY-RELATED MAINTENANCE UNIT II GROUP 18C MONTH January YEAR 80 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION
- 21A. Safety Injection 0-79-4368 Indicating Instrument Indication Reading Low Performed Functional Tank, Wide Range Pres-11-26-79 Was Out of Adjustment Test and Adjusted the sure Indicator PI-321 Indicating Instrument Safety Injection System IC-79-2151 Dampening of Transmit-Output of the Transmitter Cacked Out Dampening Flow Transmitter 11-26-79 ter Would Not Change With a Screw and Readjusted 2-FT-306 Change in the Shutdown Cooling Flow Reactor Coolant System /
IC-79-2087 Defective Padding Results of the Calibra-Replaced the Padding Resistance Temperature 10-22-79 Resistors tion Test Performed On Resistors Detectors The RTD's Were Out of Tolerance Reactor Protection 0-78-3964 Defective Resistance Primary Temperature Replaced System /2-TE-122HC 9-18-79 Temperature Detector Indication Was High RTD 2-TE-122HC Engineered Safety 0-79-4267 Defective Signal Voltage Readings From The Replaced Signal Features Actuation 11-11-79 Isolator Signal Isolator Were Not Isolator 2-E/E-102C System / Channel
'ZF',
Within Specifications Pressurizer Pressure Module 'PP' 2-E/E-102C 9
1 e
r i