ML19343A946

Monthly Operating Repts for Oct 1980

ML19343A946
Person / Time
Site:	Calvert Cliffs
Issue date:	11/13/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19343A942	List: ML19343A941 ML19343A946
References
NUDOCS 8011240324
Download: ML19343A946 (17)

Text

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Q OPERATING DATA REPORT i DOCKET NO. 50--317 DATE 11/13/80.

COMPLETED BY S. D. Merson TELEPHONE m mn 4

OPERATING STATUS Calvert Cliffs No. 1 N * 5

1. Unit Name:

2. Reporting Period: October, 1980 2,700

3. Licensed Thermal Power (MWt): _

4. Nameplate Rating (Gross MWe): 918

5. Design Elcrtnol Rating (Net MWe): 845

6. Maximum Depend. ble Capacity (Gross MWe):

845

7. Maximum Dependable Capacity (Net MWe): 810

8. If Changes Occu*. m 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.lf Any:

i This Month Yr..to-Date Cumulative

11. Hours in Reporting Period 744 7,319 48,084

12. Number Of Hours Reactor Was Critical 410.1 6,421.1 38,860.7

13. Reactor Reserve Shutdown Hours 0.0 38.3 1,098.8

14. Hours Generator On.Line 409.1 6,350.7 38,052.7

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 923,611 15,229,803 90,566,792 .

17. Gross Electrical Energy Generated IMWH) 288,487 ,,, 4,781,703 29,594,233

18. Net Electrical Enerly Generated (MWH) 271,772 4.543.042 28,192,248

19. Unit Service Factor 55.0 86.8 79.1

20. Unit Availability Factor 55.0 86.8 79.1

21. Unit Capacity Factor (Using MDC Net) 45.1 76.6 72.7

., 22. Unit Capacity Factor iUsing DER Net) 43.2 73.5 69.4

23. Unit Forced Outage Rate 0.0 2.9 8.1 l

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each t: ,

l

25. If Shut Down A: End Of Report Period, Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial OperationP Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

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OPERAT'J.G DATA REPORT l DOCKET NO. 50-318

' DATE 11/13/80 l COMPLETED BY S. D. Merson TELEPHONE 101-234-5240 OPERATING STATUS

.Notes

t. Unit Name: calvert Cliffs No. 2

2. Reporting Period: October, 1980 ,

3. Licensed Thermal Power (MWt): 2.700

4. Nameplate Rating (Gross MWel: 011

5. Design Electrical Rating (Net MWe): A69

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maximum Dependable Capacity (Net MWe). 825

8. If Changes Occur in Capacity Rathgs (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions.lf Any: No. 2 Plant is drooping to low loads on the weekend oeriod to conserve fuel until its outage.

This Month Yr..to.Date Cumulative 744 7,319 31,439 i1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 737.8 7,0C9.9 26,954.8

13. Reactor Reserve Shutdown Hours 6.2 28.7 441.8

14. Hours Generator On Line 735.2 6.963.6 26,572.1 I

15. Unit Reserve Shutdown ilours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1.725.686 17.445,419 65,689,651 .

17. Gross Electrical Energy Generated iMWH) 553,654 _ , 5,718,241 21,723,404

18. Net Electrical Energy Generated (MWH) 577 01R 5.458.874 20.715.894

19. Unit Service Factor 98.8 95.1 84.5

20. Unit Availability Factor 48.8 95.1 84.5 2i Unit Capacity Factor (Using MDC Nett 85.4 90.4 80.9

22. Unit Capacity FactoriUsing DER Nett 83.8 88.3 78.0

23. IJnit Forced Outage Rate 1.2 1.3 5.5

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eschi:

No. 2 Plant scheduled for a planned outage starting Jc- ,j,1981,until March 2, 1981, for refueling, unit general inspection m u aI "odifications.

25. If Shur 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 (9/77) mT w - m e- ,i 7 m--.;- .my e--- e y-9--- r--T+w "1- 9-' 'NM'

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-317 UNIT Calvert Cliffs #1 DATE 11/13/80 COMPLETED BY S. D. Merson TELEPHONE 301-234-5240 October, 1980 MON 11f DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Nerl j 711 37 550' 2 723 gg -

3 722 39 4 728 20 J _

728 gg 6 729 22 7 711 23 g 700 24 9 678 25 10 666 26 11 654 27 12 641 28 13 626 29 14 617 30 15 615 3g 5 96 16 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reportir's month. Compute to i

the nearest whole megawatt.

(9/77)

AVERAGE DAIL'l UNIT POWER LEVEL DOCKET NO. 50-318 UNIT Calvert Cliffs #2 DATE L} H 3 /80 COMPLETED BY Ss 0. Merson TELEPHONE 301-234-5240 MONTH 0:tober, 1980 DAY AVEi1 AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe Net) l 825 37 836 2 826 gg 829 3 $21 gg 412 4 396 20 806 3 396 23 835 800 6 22 7 807 g 834 8 802 24 827 9 829 . 25 48 10 818 26 11 405 27 655-12 397 28 827 13 784 29 673 14 835 30 802 15 836 3g 756 16 777 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)

DOCKET NO. 50-117 UNIT SHUTDOWNS AhJ POWER REDUCI10NS -

UNIT NAME 0,Ivert c14frs #1 DATE 11/11/80 COMPLETED BY S- D- Merson REPORT MONTH Octcher, 1980 TELEPHONE in1_714_s9an

.!'E 3 h Ek Licensee Eg -h". Cause & Corrective No. Date h 3g ( .2 s 5 Event s7 o- Action to

$E E jig d

Report *r 65 0

[ Prevent Recurrence 80-11 801018 S 334.9 C 1 XX ZZZZZZ Refueling, unit general inspection and TMI Modifications.

. I 2 3 4 2

F: Forced Reason: Method: Exhibit G -Instructions 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 ReporI (LER) File (NUREG-

, D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination F Administrative 5 G-Operational Eirut (Explam) Exhibit I - Sanw Source (9/77) llother (Explain) t

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. sn 11 a ,

UNITNAME ca lvert CIfffs #2 DATE II/33/80 COMPLETED BY S. D. Merson REPORT MONT11 Oc t obe r - 1980 TELEPHONE 301-234-5240 S

.! E 3g .)Y$ Licensee E

% -h4 Cause & Corrective No. Date { 3g 5

5 g 5 Event sT N0 o- Action to 6

$E j di g Report

• f'3 Psevent Recurrence 6

30-11 801004 S 51.0 11 XX ZZZZZZ Fuel conservation, capacity availa-ble on demand.

30-12 801011 S 50.0 11 XX ZZZZZZ Fuel conservation, capacity availa-ble on demand.

80-13 801019 S 31.0 11 XX ZZZZZZ Fuel conservation, capacity availa-ble on demand.

80-14 801026 F 8.8 A 2 XX PUMPXX Loss of condenser vacuum when 22 condenser air removal pump failed.

1 2 3 4 F: Forced Reason: Method: Exhibit G . Instructions S: Scheduled A Equipment Failure (Explain) I Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3 Autunutic Scrain. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Exanination F Administrative 5 G-Operational Errur (Explain) Exhibit I - Same Source (9/77) 114):her (Explain)

REFUELING INFORMATION REQUEST

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

2. Scheduled date for next Refueling Shutdown: April 16,1982+

3. Scheduled date for restart following refueling: December 2,1980*

4. Will refueling or resumption of ;,eration thereaf ter require a technical specification change or other license amendment r Resumption of operation af ter 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.

, August 29, 1930 November 4,1980 (Supplemental Submittal)

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) 456*

Spent Fuel Pools are common to Units 1 and 2

8. The present licensed spent fuel pool storage capacity a nd the size of any increase in licensed storage capacity that has been requested or is olanned, in number of fuel assemblies.

1358 Licensed 10~3 Currently Installed 472 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,1985

• Information changed since last report.

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 42,1981

4. Will refueling or resumption of operation thereaf ter require a technical specification change or other licensed amendment?

Resumption of operation af ter refueling will require changes to Technical Specifications. The changes will be such as to allew 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 14, 1980

6. . Important licensing considerations associated with refueling.

Reload fuel will be similar to that reload fuel inserted in the previous cycle.

.I

, 7. The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.

(a) 217 (b) 456*

Spent Fuel Pool is common to Units 1 & 2.

3. 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 assemblics.

1358 Licensed 1023 Currently Installed 472 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,1985

• Information changed since last report.

+

, - n - ,ne e , , n -- ,-~< g - w

SUMMARY

OF UNIT 1 OPERATING EXPERIENCES - OCTOBER 1980 10/1 At the beginning of this reporting period Unit I was operating 740 MWe with the reactor at 89% power, limited by end of cycle coastdown. At 0155 load was reduced to 720 MWe to investigate saltwater leakage into the main condenser. Load

. was increased to 760 MWe at 1015 when indications of saltwater leakage disappeared.

10/7 Commenced power coastdown at 0835.

10/17 At 2120 commenced unit shutdown for 4th scheduled refueling outage.

10/18- The unit was taken off the line at 0106. The Reactor was shutdown at 0205.

10/19 The Reactor was placed in cold shutdown at 1020. Commenced draining the Reactor Coolant System (RCS) at 2120.

10/31 At the end of this reporting period, Unit I was shutdown for its 4thscheduled refueling outage.

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SUMM ARY OF UNIT 2 OPERATING EXPERIENCES - OCTOBER 1980 10/1 At the beginning of this reporting period Unit 2 was operating at 360 MWe with the reactor at 100% power.

10/4 At 0300 load was decreased to 420 MWe for fuel conservation.

10/6 Load was increased to capacity (865 MWe) at 0600.

10/7 At 2130 load was reduced to 700 MWe to investigate sa'twater leakage into the main condenser.

10/8 Load was increased to (365 MWe) at 0630 when indications of saltwater leakage disappeed.

10/11 At 0500 load was decreased to 415 MWe to conserve fuel.

10/13 Resumed full load operation (365 MWe) at 0700.

10/16 At 0445 load was reduced to 765 MWe to investigate saltwater leakage into the main condenser. Load was increased to 870 MWe at 2100 when indications of saltwater leakage disappeared.

l 10/19 At 0300 load was decreased to 410 MWe for fuel conservation.

10/20 Load was increased to capacity (865 MWe) at 1000.

10/25 Decreased load to 420 MWe at 0400 to conserve fuel.

10/26 At 1657 the reactor tripped due to loss of condenser vacuum when 22 condenser air removal pump failed.

10/27 The reactor was brought critical 0035 and the unit paralleled at 0147.

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4 10/28 Resumed full load operation (870 MWe) at 0100.

10/29 At 0030 load was reduced to 715 MWe to investigate saltwater I leakage into the main condenser.

10/30 Af ter plugging I condenser tube resumed full load operation (860 MWe) at 1810.

10/31 At 1330 load was reduced to 710 MWe to investigate saltwater leakage into the main condenser. At the end of this reporting period 2 was operating at 710 MWe with the reactor at 83% power, while investigating saltwater leakage into the main condenser.

F

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SAFETY-RELATED MAINTENANCE UNIT n ,, ,

GROUP r&c MONTH netow,r YEAR 1980 MALFUNCTION

SYSTEM OR COMPONENT -

MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Reactor Prc,tective 1C-80-9h Dirty Selector Switch The Channel 'D' 4 T Cleaned the Selector System / Channel 'D' 9-18-80 and Instrument Slide Power Signal was erratic Switch and' Slide Links Links Reactor' Protective '

0-80-4115 Defective Matrix Relay Reactor Trip Preakers

• Replaced the Matrix System / ChannelA' 9-22-80 AB-1 1 & 5 would not open Relay AB-1 and per-Matrix Relay AB-1 when a Trip Signal was formed functional generated test i

1. 12 Steam Generator Pres- 0-80-h074 Loop Resistor leads and 1-PI-1023D was indicating Cleaned the Resistor sure Indication 1-PI-1023 ) 9-18-80 instrume w slide links greater than 22 psi higher Leads and Instrument were dirty than the other channels Slide Links

1. 12 Emergency Diesel 0-80-4158 Defective Ferrule and Oil leak at the Tubing Replaced the Ferrule Generator 9-24-80 Compression Nut Connection for Pressure and Compression Hut Switch 0-PS-4788 4

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SAFETY-RELATED MAINTENANCE ,

UNIT Two GROUP roc MONTH n a nw,,,. YEAR 1080

, MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Reactor Protective System / IC-80-2078 Defective Matrix Relay Reactor Trip Breakers Replaced Matrix Matrix Relay AB-1 8-20-80 AB-1 opened with no indication Rehy AB-1 of trip signal from relay.

Engineered Safety Feature 5 0-80-2859 Defective Bistable Voltage Oscillations on Replaced the Bistables Actuation System / Channel , 7-29-80 Modules for Safety In- SIAS and CIS Signals for SIAS and CIS Char nel ZE jection Actuation Signal ZE and Containment Isolation Signal on Channel ZE Engineered Safety Feature 1 0-80-2908 Defective Volt Meter Greater than .1 Volt Devi- Replaced the Volt Actuation System /#21 7-31-80 ation between channels Meter Steam Generator Pressure Signal Channel ZE

1. 22 Low Pressure Safety 0-79-4306 Defective Pressure Switch Received Erroneous Low Replaced the Pressure Injection Pump Pressure 8-6-80 2-PS-302Y Suction Pressure Alarm Switch Switch 2-PS-302Y 2-PS-302Y Refueling Water Tank Leve L 0-80-2578 Defective Signal Isolator Level Indication was er- Replaced the failed Indication Signal Iso- T-T-80 ratic Signal Isolator lator 2-LY-b1h2 Steam Generator Pressure 0-80-2239 Dirty Instrument Icop High Deviation between Cleaned the Loop Indication Resistor Terminal Con- Pressure Indications on Resistor Terminal 2-PI-1023A nections on Pressure Redundant Channels Connections Instrument 2-PI-1023A 4

~ . . . _ _ - _ - - - . - . . . - . .- . - - .-- . . - - - - . - . .

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SAFETY-RELATED MAINTENANCE UNIT  %

GROUP I&c MONTH october YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 23 Charging Pump Low 0-80-2(80 Internals of Instrument Received Erroneous Signals. Replaced the Instru-Suction Pressure Instru- 7-24-80 2-PC-22hZ vere worn out from 3,he Pressure Instru- ment Internals. '

ment ment i

)

2-PC-224Z

1. 11 Control Room Air

• IC-80-2047 Defective Temperature . Temperature Controller Replaced the Tempera-.

Conditioning Unit Tempera- 9-30-80 Controller was not repeatable during ture Controller ture Controller 0-TC-53h] calibration 0-TC-5341 0-TC-5341 Engir.eered Safety Feature s 0-80-h176 High Bistable Module for Greater than 0.1 Volt Replaced the Defective  !

Actuation System /Contain- 9-26-80 Channel ZF was defective Deviation between Channel Bistable

ment Isolation Signal ZF and other channels Channel ZF Engineered Safety Feature s IC-80-2098 Defective Signal Isolator Received Intermitt.ent Replaced the Signal Actuation System / Steam .9-26-80 2-E/E-1023C Block Trip Signal while Isolator Generator Isolation trying to test Trip 2-E/E-10230 i

Block Signal Channel ZF Function 1 Engineered Safety Feature ; IC-80-2100 Broken pin on Isolation Containment Isolation Repaired the Connector Actuation System /Contain- 9-26-80 Module 'B' Cabinet- Signal Channel ZF Trip Pin ment Isolation Signal ~

mounted Connector without Bistable Trip Channel ZF Indication l

4 a

1

SAFETY-RELATED MAINTENANCE UNIT  %

GROUP p sung MONTil on t nw e r. YEAR 3 can MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 11 Emergency Diesel 0-80-h12h Defective Relay CF-4 Relay dropped out for no Replaced the Relay Generator 9-24-80 apparent reason CF-4

1. 11 Emergency Diesel

• 0-80-1672 Voltmeter zero adjust- Voltmeter on panel 1C18 Recalibrated the Generator Voltmeter on 7-25-80 ment was lov was indicating ~~100 Volts Voltmeter on Panel Panel lover than actual Voltage 1C18 1C18 t

i I

SAFETY-RELATED MAINTENANCE UNIT Two l

GROUP e m,,m MONTH october YEAR 1980 i MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 21 125VDC Bus 0-80-401h Relay 2K12X was vet and Positive ground on #21 Dried the water out 9-16-80 corroded 125VDC Bus of the relay box and replaced the relay 2K12X W

Reactor Protective System ' 0-80-3982 Closing Coil solenoid The Reactor Trip Breaker Lubricated the movine Trip Breaker TCB-21 9-12-80 Slug was sticking TCB-21 would not close parts and breaker operated satisfactory

1. 14 Battery Charger in 0-80-3089 Bad connection on Current #14 Battery Charger uns Replaced the Current 125VDC power train 8-18-80 Control Module not sharing the Bus Ind Control Module

'I

SAFETY-RELATED NAINTENNiCZ i

' one UNIT CROUP Machine Shop i.

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HONTl! October

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t YEAR' 1950 LER OR MALFUNCTION l SYSTEM OR COMPONENT MR NO. - DATE OUTACE CAUSE RESULT CORRECTIVE ACTION 1-CV-517 Auxiliary IC-79-067 Washed out cage Excessive leakage R9placed gasket Spray Line Control 5/17/79 gasket. during local. leak and lapped valke Valve ,

rate test. septp. l,

~i 13 Charglng Pump 0-8b-4313 ' ESce's'sive'1icakage Varying amperkge Rkpfapedvalves 10/6/80 P'ast suction and ' readings on pump .

discharge valves motor ' {; ,

12 Charging Pump 0-80-1290 -

Cyclic Fatigue Excessive packing ReplacediPa,bkfhg -

leakage 4/19/80 12 Charging Pump 0-80-665 Cyclic Fatigue Excessive packing Replaced packing 2/28/80,. , ,

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, , . ,y ., . *.

, Leakage. n . .: :j.u ;* and giungers 12 Charging Pumq 0-80-849 Cyclic Fatigue Excessive packing' Replaced packing 3/13/80 leakage -

1

• 11 Chargi,g Pu.,p 0-80-1123 , Cyclic Fatigue Excessive packing Replaced packing . l 4/5/80 leakage and plungers  ;

11 Charging Pump 0-80-1700 / Cyclic Fatigue Excessive packing Replaced packing 5/14/80 leakage 13 Charging Pump 0-80-829 Cyclic Fatigue Excessive packing Replaced packing 3/12/80 leakage and plungers 13 Charging Pump M-80-149 Cyclic Fatigue Excessive packing Replaced packing 6/23/80 leakage and one plunger v

13 Charging Pump 0-80-4405 Cyclic Fatigue Excessive packing Replaced packing 10/12/80 leakage 13 Charging Pump O-80-4328 '

Cyclic Fatigue Excessive packing Replaced packing 10/7/80 leakage

,s

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