ML19323F773

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1980
ML19323F773
Person / Time
Site: Calvert Cliffs  
Issue date: 05/15/1980
From: Merson S
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19323F772 List:
References
NUDOCS 8005290454
Download: ML19323F773 (19)
v • d • e


Text

__

O OPERATING DATA REPORT DOCKET NO.

50-317 DATE 5/15/80 COMPLETED BY e n.Merson TELEPHONE 101 214-5240 OPERATING STATUS

1. Unit Name:

Calvert Cliffs No. 1 Notes

2. Reporting Period:

Anril, 1980

3. Licensed Thermal Power (MWt):

2700

4. Nameplate Rating (Gross MWe):

918

5. Design Electrical Rating (Net MWe):

845 845

6. Maximum Dependable Capacity (Gross MWe):
7. Maximum Dependable Capacity (Net MWe):

ain

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 II. Hours in Reporting Period

'li o 2.903 43,668

12. Number Of Hours Reactor Was Critical 672.4 2,446.9 34,886.5
13. Reactor Reserve Shutdown Hours 11.4 19.0 1,079.5
14. Hours Generator On.Line 645.8 2,384.0 34,086.0
15. Unit Reserve Shutdown flours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 1.644.922 5,147,417 80,484,406
17. Gross Electrical Energy Generated (MWH) 529,683 _

1,621,465 26,433,995

18. Net Electrical Energy Generated (MWH) 504,622 1,531,889 25,181,095
19. Unit Service Factor 89.8 82.1 78.1
20. Unit Availability Factor 89.8 82.1 78.1
21. Unit Capacity Factor (Using MDC Net) 86.7 65.2 71.2
22. Unit Capacity Factor IUsing DER Net) 83.1 62.5 68.2
23. Unit Forced Outage Rate 6.2 3.1 8.6
24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each t:

I niant scheduled for a olanned outage startine 10/17/80 until 12/15/80 for u n.

refueline, unit eeneral insoection and TMI Modifications.

25. If Shut Down At End Of Report Period. Estimated Date of Startup: _
24. Units in Test Status IPrior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 80 052 0 0 M

+.

.__y.

._,m.

y

,_.,,r..,-.

t j

OPERATING DATA REPORT h

DOCKET NO. 50-318 DATE 5/15/80 COMPLETED 8Y S.D. Merson TELEPHONE 1m _714_s240 OPERATING STATUS

1. Unit Name:

Calvert Cliffs No. 2 Notes

2. Reporting Period:

AnH 1_

1980

3. Licensed Thermal Power (MWt):

2.700

4. Nameplate Rating (Gross MWe):

911 845

5. Design Electrical Rating (Net MWe):
6. Maximum Dependable Capacity (Gross MWe):

860 825

7. Maximum DependAle Capacity (Net MWe):
8. If Changes Occur in Leoacity flatings (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:

1 This Month Yr.-to.Date Cumulative 719 2,903 27,023

11. Hours in Reporting Period
12. Number Of Hours Reactor Was Critical 708.4 2,673.3 22,618.2
13. Reactor Reserve Shutdown Hours 0.0 0.0 413.1
14. Hours Generator On.Line 701.4 2,658.1 22,266.6
15. Unit Reserve Shutdown flour, 0.0 0.0 0.0
16. Gross Thermal Energy Generated IMWH) 1.835.798 6,871,'>34 55,115,866
17. Gross Electrical Energy Generated (MWH) 6Mg64 2,313,697 18,318,920
18. Net Electrical Energy Generated (MWH) 595,546 2,213,473 17,470,493
19. Unit Service Factor 97.6 91.6 82.4
20. Unit Availability Factor 07.6 91.6 82.4 k
21. Unit Capacity Factor iUsing MDC Net) 100.4 92.4 79.3
22. Unit Capacity Factor iUsing DER Net) 98.0 90.2 76.5
23. Unit Forced Outage Rate 2.5 0.7 6.2
24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
25. If Shut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operationt-Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) l

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-317 Calvert Cliffs #1 WIT DATE 5/15/80 S. D. Merson COMPLETED BY TELEPHONE 301-234-5240 MONTH Anril, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I 837 17 832 2

835 gg 834 3

837 39 61 I

4 834 20 614 835 334 5

2, 6

835 22 393 1

7 767 668 23 g

800 782 24 9

836 25 445 10 835 26 639 11 834 799 27 12 820 785 1

28 1

13 836 617 29 14 815 30 15 835 31 16 834 j

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)

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 UNIT calvert Cliffs #2 DATE 5/15/80 S. D. Merson COMPLETED BY TELEPHONE 301-234-5240 MONTH April, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) g 862 275 37 2

862 gg 855 862 816 3

39 4

862 20 859 5

86?

23 858 819 859

)

6 22 7

864 23 862 g

862 24 861 9

862 25 861 10 862 26 832 gg 861 27 760 12 862 28 860 13 862 29 861 34 861 30 860 15 862 3g 16 640 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)

50-317 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME Calvert cliffs #1 DATE sits /sn COMPLETED BY <. D Merson REFORT MONT11 Anri1. 1980 TELEPHONE 301-234-5240 w.

E e

3E 3

j.E 5 Licensee h

h Cause & Corrective No.

Date k

3g

(

,;; g &

Event g?

['l a

Actitm to

$E 5

j ;ji g Repori a mV H

Prevent Recurrence d

80-04 800419 S

19.5 B

1 ZZ VALVEX To replace a hydraulic control valve for #1 main turbine intercept valve.

80-05 800421 F

15.5 A

3 ZZ CRDRVE Voltage swings on the control element drive system motor generator sets caused the trip.

80-06 800425 F

13.8 A

3 ZZ CRDRVE Trip due to undervoltage to the reacto trip breakers while trouble shooting above reason (80-05).

80-07 800429 S

11.4 B

1 ZZ VALVEX To effect repairs on main turbine intercept valves #1 and #4 80-08 800430 F

13.0 A

4 ZZ PIIMPXX Leak on #11B reactor coolant pump control bleed - off line.

Plant was already off for above outage (80-07).

1 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.

Even ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F-Administrative 5

)

G-Operational Error (Explain)

Exhibit I - Same Source (9/77)

Il4)iher (Explain) l

~

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-318 UNIT NAME Calvert Clfffs#2 DATE S/15/80 COMPLETED 3Y c-D.

Merson REPORT MONT11 Anril - 1480 TELEPHONE 101-?14-S?4n "i

e c.

.3 as

-g

}

j_g 5

p.gg Licensee E*

g ".,

Cause & Corrective g**

x 2

4

.2 5 cc Event u9

[]

a Action to

$3 5

jisy Report *

$0 Prevent Recurrence b

80-01 800416 F

17.6 A

1 ZZ VALVEX To repair a failed letdown control valve.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A-Equipment 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 Repor (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F Administrative 5

G-Operational Esror (Explain)

Exhibit I-Same Source i

19/77) lloihcr (Explain) i

5/2/80 REFUELING INFORMATION REQUtiST 1.

Name of Facility: Calvert Cliffs Nuclear Power Plant, Unit No.1 2.

Scheduled date for next Refueling Shutdown:

October 17, 1980 3.

Scheduled date for restart following refueling:

December 10, 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 infomation.

September 11, 1980 6.

Importart 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 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 774 Licensed 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 previous report.

5/2/80 REFUELING INFORMATION REQUEST 1.

Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit No. 4 2.

Scheduled date for next refueling shutdown:

January 1, 1981 3.

Scheduled date for restart following refueling: Febr ary 18, 1981 4.

Will refueling or resumption of operation thereafter require a technical specification change or other licensed amendment?

Resumption of operation after refueling will require changes to Technical Specifications. The changes will be such a; 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 infonnation.

November 20, 1980 6.

Important licensing considerations associated with refueling.

Reload fuel will be similar 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 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 required or is planned, in number of fuel assemblies.

1056 Licensed 728 Currently Installed 774 Licensed 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 has changed since previous report.

l

SUPMARY OF UtlIT 1 OPERATIllG EXPERIEllCE FOR APRIL 1980 4/1 At the beginning of this reporting period Unit I was operating at 865 INe with the reactor at 100% power.

4/7 Decreased load to 725 !Me at 1500 to investigate saltwater leakage into the main condenser.

4/8 Indications of saltwater leakage disappeared and load was increased to capacity (365 liWe) at 0900.

4/12 Reduced load to 750 tiWe at 0845 for Main Turbine Control Valve testing. Resumed full load operation (865 tale) at 1100.

4/19 The unit was taken off the line at 0510 to replace a hydraulic control valve for #1 fiain Turbine Intercept Valve.

4/20 The unit was paralleled at 0040 and began increasing load to capacity at 0700.

Load was limited to 720 fUe while repairing

  1. 12 Circulating Water Pump and investigating saltwater leakage into the main condenser.

4/21 At 1116 the main turbine tripped due to loss of power to the master trip relay. The reactor tripped on loss of load.

Voltages swings on the Control Element Drive System flotor Generator sets caused the trip. The reactor was brought critical at 2230.

4/22 The unit was paralleled at 0247. Load was limited to 775 MWe at 1130 while repairing #12 Circulatina Water Pump.

Load was further reduced to 295 MWe to investigate saltuater leakage into the main condenser.

4/24 After repairs were completed on #12 Circulating Water Punp load was increused to capacity (G65 MWe) at 2000.

SUtiMARY OF UilIT 1 OPERATIflG EXPERIEllCE FOR APRIL 1980 4/25 The reactor tripped at 1316 on undervoltage to the reactor trip breakers while troubleshooting the voltage problems on the Control Element Drive System ftotor Generator sets.

4/26 At 0012 the reactor was brought critical and the unit paralleled at 0301. Load was increased to capacity (860 MWe) at 2200.

4/28 At 1620 Main Turbine Intercept valves #1 and #4 went shut and would not reopen. Load was reduced to 700 ffWe at 1730.

4/29 At 2334 the unit was taken off the line to effect repairs to Main Turbine Intercept Valves #1 and #4. The reactor was shutdown at 2343.

4/30 At 0905 commenced cooldown of the Reactor Coolant System due to the discovery of an unisolable leak from the controlled bleed-off line on #118 Reactor Coolant Pump. At the end of this reportino period Unit 1 was shutdown for repair of the Reactor Coolant System leak from #11B Reactor Coolant Pump control bleed-off line.

l

Sutt1ARY OF OPERATING EXPERIENCE FOR UtlIT 2 FOR APRIL 1980 4/1 At the beginning of this reporting period Unit 2 was operating at 910 tNe with the reactor at 1007, power.

4/6 Decreased load to 770 iWe at 0610 for ttain Turbine Control Valve testing. At 1600 full load operating (900 IUe) was resumed.

4/16 The unit was taken off the line at 1930 to repair a failed letdown control valve. The reactor was shutdown at 2054.

4/17 The reactor was brought critical at 0730 and the unit paralleled at 1307. The extraction steam valve for #26A feedwater heater was stuck shut limiting load to 865 fUe.

4/18 Increased load to capacity (900 iMe) at 0500.

4/19 Decreased load to 735 f4!e due to a computer outage. Resumed full load operation (900 ffle) at 2230.

4/26 At 0700 load was reduced to 810 FMe to work on the condenser Amertap system.

Increased load to capacity (900 tWe) at 1700.

4/27 At 0700 decreased load to 765 IMe to complete work on the condenser Amertap system. At 1000 load was further reduced to 680 fWe for maintenance on #22 f1SR Reheat Stop Valve. At 1100 repairs were completed and load was increased to capacity (900 ! ale).

4/30 At the end of this reporting period Unit 2 was operating at 900 iWe with the reactor at 100". power.

l 1

i

SAFETY-RELATED MAINTENANCE UNIT I

GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Refueling Water Tank /

0-79-615 12/4/79 Defective signal Oscillations in level Replaced signal Level Instrument isolator indications isolator 1-LY-4142 i

Reactor Protective 0-79-2109 2/26/80 Defective temperature Channel 'B' hot leg Replaced the System / Channel 'B' detector 1-TE-122HB temperature indication temperature Hot Leg Tenperature failed detector Detector 1-TE-122HB Reactor Pratective 0-79-4364 2/26/80 Defective temperature Spurious alarms Replaced the System / Channel 'A' detector 1-TE-112CA temperature Cold Leg Temperature detector 1-TE-112CA Detector 1-TE-112CA Engineered Safety 0-80-394 2/9/80 Defective relay K54 The refueling water Replaced relay

]

Features Actuation in cabinet IC68 tank mini-flow return K54 System / Cabinet IC68 valve would not shut when a recirculation actuation signal is received i'

.........................m,..

..uo....o=n..in..o.nonun.oinia:n.ai=

nw" n..:m SAFETY-RELATED MAINTENANCE UNIT I

GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Injection Tank 1C-80-021 1/31/80 Defective microswitch 1-CVC-641 would not Replaced micro-Fill Valva 1-CV-641 indicate "open",

switch Reactor Protective 0-80-181 1/21/80 Defective + 15 VDC liigh voltage meter Replaced the + 15 System / Channel ' A' Wide power suppTy pegged high VDC power supply Range Nuclear Indica-tion 1-NI-001 Reactor Protective IC-79-2165 11/28/79 Dirty drawer rollers Intermittent ground Cleaned the drawer System connections on RPS rollers channels Component Cooling 0-80-294 2/1/80 Defective relay in Received alann when Replaced defective Heat Exchanger Outlet alann circuit an alann condition relay Temperature Alann did not exist circuit 1-TIA-3824

..~..,.....

SAFETY-RELATED MAINTENANCE UNIT I

GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR H0. - DATE CAUSE RESULT CORRECTIVE ACTION Reactor Protective 0-80-975 3/24/80 Dirty loop resistor Deviation between Cleaned the loop System /#12 Steam lugs pressure indications resistor lugs Generator Pressure was out of specification Indication Channel ' A' 1-PI-1023A 1

i

SAFETY-RELATED MAINTENANCE UNIT II GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-80-218 1/28/80 Defective trip light Trip light would not Replaced the Features Actuation on the bistable nodule stay on bistable module System /#21 Steam Generator Isolation Signal Bistable, Channel 'ZD' Reactor Protection 0-79-4764 12/71/79 Defective 250 ohm Temperature reading Replaced the System / Channel 'B' resistor in the was erratic resistor Cold Leg Temperature instrument loop Nuclear Instrumentation /

0-79-4806 12/30/79 Test cable contact Power indication on Cleaned the test Channel 'D' Linear points dirty DVH was reading.3 cable contact Drawer to.4% high points

  1. 21B Safety Injection 0-79-4464 1/15/80 Limit switches were The remote indication Aligned the limit Tank Fill Valve misaligned would indicate inter-switches 2-CV-611 mediate when the valve was shut

\\

SAFETY-RELATED MAINTENANCE g

UNIT II GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Pressurizer Pressure 0-79-4819 1/2/79 Loose connection at Indication deviation Tightened the Indication Channel indicating instru-with the other channels connectors

'C'/2-PI-102C nent was out of specification Reactor Regulating

,IC-79-2174 1/21/80 Temperature detector Hot leg tenperature Replaced the System / Channel 'X' 2-TE-111X failed indication on channel temperature Hot Leg Temperature

'X'

& 'Y' failed high detector 2-TE-111X Indication Reactor Protection 0-80-192 1/18/80 Defective relay Drop out and hold Replaced the relay System / Channel 'B' lights would illuninate Matrix Relay BC-Z at the same time i

Safety Injection System /

IC-80-2007 1/13/80 Bad solder joint Would not control in Re-soldered the Low Pressure Safety automatic connection Injection Punp Flow i

Control Instrument 2-FY-306 1

l

\\

i

SAFETY-RELATED MAINTENANCE UNIT 11 GROUP I&C MONTH APRIL YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Containment Sump 0-79-4500 1/13/80 Defective signal Erroneous indication Replaced the Level Indication isolator signal isolator 2-LT-4145 s

5 0

t e

I E

q

,4

.,-.c..

SAFETY-RELATED MAINTEN#fCE UNIT II

]

s CROUP MACifItE SIDo gg y

MONT![

AFRIL yggn, 1980,*

LER OR

!.'ALFUNCTION I

SYSTEM OR COMPONENT MR NO. - DATE OUTAGE CAUSE RESULT CORRECPIVE ACTION

  1. 23 Charging Itap O-80-511 2/20/80 Cyclic Fatigue Excessive packing fif.placed packith,_

leakagg e

J' i

,'i.t ;

t h

o

  1. 21 Charging Ptmp O-80-54*/

2/21/80

' Cyclic Fatigue Excessive packing ITeplaced packmg leakage t

8 i V

  1. 23 Charging Ptmp O-80-396 2/12/80 Cyclic Fatigua Excessive packing Heplaced packing leakage

'r

.ja

.'3,',*

i. ),'.

"r 7 e 4

+4 * ;;., g.':t' ' r fl h,..,(

e g-

  1. 22 Charging Ptup O-79-30/4 10/13/79 Cyclic' Fatigue Excessive, packing Replaced packing leakage,

s

  1. 22 Charging Ptup O-79-2668 9/4/79 Cyclic Fatigue Excessive packing Replaced packing
  • leakage 8

Salt Water Control M-79-2225 11/16/79 Corrosion-Erosion Exc.essive seat Replaced valve leakage with rubber lined Valve 5210 valve.

  1. 22 Boric Acid O-79-4541 2/7/79 Bad ptmp bearings Ptnp motor consist-Replaced ptmp Ptnp antly tripped bearing and all i

other defective parts I

  1. 21B Reactor Coolant M-78-2498 12/27/78.

' Suspect mechanical Excessiye leakage Replaced' seal failure of seating Ptmp surface

.g......

SAFETY-RELATED MAINTENANCE UNIT II I

CROUP MTCIIITE SliOP MONTil APflIL YEAR'1

/

i l

LER OR MALFUNCTION i

2 SYSTEM OR COffPONENT MR NO. - DATE OUTAGE CAUSE RESULT CORRECTIVE ACTION

  1. 21 Charging Pmp O-79-2668 8/24/ 79 Cyclic Fatigue Excessive packing Itpplacedpacking leakage

)

.; J V

k.}

.e

  • ea, T) ';

^ '

t q) t r

e,

.s-t4 F.

g.-

1 a

p s,.

~

i

(-...

  • 6 f

.. \\'.t '?, ' ].p's.'"Q't., (. h. e i,f't.*.2'd 'h!' t. '.!,

M,.:

.a.t** [

1

  • g-r.,
l)
r I

's I

f j

4' t

f 5

l G

9 8

-.

Retrieved from "https://kanterella.com/w/index.php?title=ML19323F773&oldid=4769059"