ML19344D654

Monthly Operating Repts for Mar 1980

ML19344D654
Person / Time
Site:	Calvert Cliffs
Issue date:	04/14/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19344D653	List: ML19344D652 ML19344D654
References
NUDOCS 8004250407
Download: ML19344D654 (18)

Text

_ __-_____ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

OPERATLNG DATA REPORT DOCKET NO. 50 317 DATE 4/14/80 COMPLETED BY .n."or<on TELEPHONE 'm "'- 5240 t OPERATING STATUS Notes

1. Unit Name: Calvert Cliffs Mo. 1 ,

2. Reporting Period: " arch, lo80

?,700 e

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): "Id [

5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross MWe): 345 l

7. Maximum Dependable Capacity (Net MWe): 810

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): 7 "O M'a'

10. Reasons For Restrictions.lf Any: No. 1 Plant was operatin~ with a 790 "U limitation due to the turbine blada nroble.ms until 12:01 A'! 4 /1/30. Althouch the turbine blade Aroblem has not been corrected, heater renairs and im9 roved condenser conditions '

have allowed a return to capacity (320).

This Month Yr.-to Date Cumulative

11. Hours in Reporting Period 744.0 2,184.0 42,949.0 '

12. Number Of Hours Reactor Was Critical 712.1 1,774.5 34,214.1

13. Reactor Reserve Shutdown Hours 7.6 7.6 1,068.1 l

14. Hours Generator On Line 710.2 1,733.2 33.440.2

15. Unit Reserve Shutdown flours 0.0 0.0 0.0 i

16. Gross Thermal Energy Generated (MWH) 1,7uo,808 3,502,405.2 78,839,434.0 .

I

17. Gross Electrical Energy Generated lMWH) 5 7 5 .1 L_. 1.ru t . 7M ?5,004,112

18. Net Electrical Energy Generated (MWH) 549,264 1,027.207 ,

24,676,673

19. Unit Service Factor us.5 79.6 77.9

20. Unit Availability Factor 45.5 79.6 77.9 l

21. Unit Capacity Factor tusing MDC Net) 91.1 53.1 7c.9

22. Unit Capacity Factor (Using DER Net) 87.4 55.7 e6.0

23. Unit Forced Outage Rate 4.5 1.9 8.7

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

4

25. l(Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved l INITIAL CRITICALITY l INITIAL ELECTRICITY  !

COMMERCIAL OPERATION D 800M MN g,j77)

OPERATLNG DATA REPORT DOCKET NO. 50-318

. DATE 4 /1L /F0 COMPLETED BY 9.D."ersnn TELEPHONE 101-?36-5240 t

OPERATING STATUS

1. Unit Name. calvert Cliffs "o. 2 Notes

2. Reporting Period: "areb, l'So 2,7c0 ,

3. Licensed Thermal Power (51h:):

4. Nameplate Rating (Gross SIWeI: 411

5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross SIWE): "M d23

7. Maximum Dependable Capacity INet SIWE):

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

9. Power Level To Which Restricted,if Any (Net MWe):

10. Reasons For Restrictions.lf Any:

• F This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 744 2,184 20,304

12. Number Of Hours Reactor Was Critical 744.0 1,064.9 21,909.3 i

13. Reactor Reserve Shutdown Hours 0.0 -0.0 413.1

14. Hours Generator On.Line 744.0 1,956.7 21,365.2

15. Unit Reserse Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated tMWH) 1."n6.lo?.a 5.n35.816.0 53,250.067.8 . ;

17. Gross Electrical Energy Generated (MWHi 643,786 _ ,

1,601,733 17,eue,950 l

18. Net Electrical Energy Generated (MWH) 616.100 1,617,927 16,374,o47

19. Unit Service Factor 100.0 84.6 82.0

20. Unit Availability Factor 100.0 84.6 82.0

21. Unit Capacity Factor tUsing MDC Neti 100.4 69.8 73,7

22. Unit Capacity Factor (U>ing DER Neti 98.0 37.7 75.9

23. Unit Forced Outage Rate 0.n 0.00 5.3

24. Shutdowns Sched6d 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 iPrior to Commercial Operationi: Forecast Achieved l

INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION i

(9/77)

d AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50-317 '

UNIT Calvert Cli f f s 'il  !

DATE 4/14/80 l r

COMPLETED BY S.D.Merson l TELEPHONE 301-234-5240 i

l

'! arch, 1080 l MONTH i

h DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (MWe. Net)

I 600 g7 819 2 326 gg S22 i 1

3 683 39 826 l 4 716 20 705 f

697 70 l 5 21 6

718 770 22 7 A'1 23 763 g 827 813 24 9 8b8 25 285  !

10 815 26 245 f

1I 807 810 27 824 752 32 28 l 13 828 757 29 14 824 824 30 l

15 823 . 3, 822 16 821 INSTRUCTIONS  :

I 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. '

f (9/77)

AVERAGE DAILY UNIT POWER LEVEL i

DOCKET NO. 50-318 UNIT calvert Cliffsd2 [

DATE 4/14/80 COMPLETED BY S.D.Merson TELEPHONE 301-234-5240 MON 1H "are . 1080 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL I (MWe-Net) (MWe Net)

, 854 799

,7 814 862  !

2 I8 3 860 39 862  !

4 860 20 861 5 861 2 P62 6 85' 22 646 7 S60 856 23 8 FM 24 862 9 859 25 86) 1 10 857 26 861 L 11 838 27 862 821 0 l 12 28 826 13 29 ,

14 717 30 863 15 610 3y 862 16 602 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.

(4/77)

c .

DOCKET NO. 50-717 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME (' i l ve r t C l i f f.e. #1 DATE ^/1^/F0 REPORT MONTH t ta r c1i , 1480 COMPLETED BY " " ',,' eg_r m n ,

w.

-  ? E g

.$E 3

(

y $E Licensee [cg jg Cause & Corrective No. Date 3g ,3 g E Event p p Action to

• y: 5 j ;p, g Report a mu g' , Prevent Recurrence 6

80-02 800101 F 9.7 a 1 It !' Pilt!PXX I.eak on :/14 c i rcu la t ing wa t e r pump cooler impinging on the intaka structure high-water level trip circuitry caused loss of all circu-lating water pumps.

80-03 800325 F 24.1 a 1 RC CONROD I.oss of voltage supply to the cont.roi rods and drives.

I 2 3 4 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 & License Examination F Administrative 5 G Operational Error (Explain) Exhibit 1 - Same Source (9/77) 114):her (Explain)

DOCKET NO. 5"- M UNITSHUTDOWNS AND POWER REDUCTIONS UNIT NAME Calvert cliti ,2 DATE '/14/8" t

REPORT MONIll 't we b t o F,0 COMPLETED BY 9 0 "o " o n TELEPHONE in i '17. s '/> o

_ E E i

No. Dale 3E 3qa j E5 Licensee ,Ev, gg Cause & Corrective h 3g jg5 Event p Action to 6

$ 5 j di g Repori a mO g{ Prevent Recurrence c5 flo outages or reductions.

s i 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G Instructions A-Equiprnent Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets for Licensee C Refueling 3 Autunutic Scram. Event Report (LER) File INUREG-

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

E-Operator Training & Ucense Examination F Adnunistrative 5 G4)perational Error (Explain) Exhibit I - Sanw Source (9/77) lii)ther (Explain)

4/10/80 REFUELING INFORMATION REQUEST

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: Decem ber 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.

l S. Scheduled date(s) for submitting proposed licensing action and supporting information.

September 11, 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 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 704 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 l

l l

4/10/80 REFUELING INFORMATION REQUEST

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

2. Scheduled date for next refueling shutdown: January 1, 1980

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 licensed 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.

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

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

(a) 217 (b) 364 i Spent Fu'el 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 704 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 ,

i

SUMMARY

OF UNIT I OPERATI!!G EXPERIENCE-MARDI 1980  ;

I 3/1 At the beginning of this reportino period Unit I was operating l I

at 730 We with the reactor at 85% power, while conducting core physics measurenents to verify that the power distribution anomaly had been rectified. At 1125 reduced load to 600 We due to loss of #11 steam generator feed pump from erroneous  :

actuation of fire system deluge. At 2132 the reactor tripped due to loss of condenser vacuum when all six circulating water 3 pumps tripped due to a salt water leak sprayino on the f circulating water room high water level protective circuitry.  :

i 3/2 The reactor was brought critical at 0510 and the unit t paralleled at 0715. Load was increased to 730 ftWe at 2030.

3/6 Increased load to capacity (850 f4fe) at 2300.  ;

I 3/10 Decreased load to 835 We to repair a steam leak on 15B '

feed water heater.

3/11 Resumed full loaa operation (860 MWe) at 2200.  !

3/20 At 2130 load was reduced to 700 fS!e to investicate salt water leakage into the main condenser.  ;

3/21 After plugging one condenser tube resumed full load operation (855 MWe) at 1200.

3/22 Decreased load to 710 MWe to clean condenser water boxes at l 1830. ,

3/23 Increased load to capacity (855 MWe) at 1430. 1 3/25 At 0850 the reactor tripped due to voltage instability on the '

^

reactor trio bus caused by #12 motor generator set. At 2030 the reactor was brought critical and the unit paralleled at 2316.

SUMMARY

OF UNIT I OPERATING EXPERIENCE-MARCH 1980 3/26 At 0127 during startup the reactor tripped at 15% power on high axial flux offset due to control rods being inserted for previous power swings. The reactor was brought critical '

at 0350 and the unit paralleled at 1104.

3/27 Resumed full load operation (850 MWe) at 1600. At 2319 load r

was decreased to 755 MWe to investigate salt water leakage

^

into the main condenser. I i

3/23 Increased load to capacity (850 MWe) at 1655 after pluaging ,

one condenser tube. At 2110 decreased load to 765 MWe to investigate salt water leakage into the main condenser. ,

r 3/29 Resumed full load operation (850 MWe) at 2130 after plugaing one condenser tube.

3/30 Load was decreased to 840 MWe at 2100 for variable Tave P

testing.

3/31 Increased load to capacity (865 MWe) at 2300. At the end of this reporting period Unit I was operating at 865 MWe with the reactor at 100% power. >

i t

P P

I

SUMMARY

OF UNIT II OPERATING EXPERIENCE-MARCH 1980 3/1 At the beginning of this reporting period Unit II was operatina at 900 MWe with the reactor at 100% power.

3/2 Decreased load to 765 MWe at 1100 due to ice forming on the .

intake traveling screens. Resumed full load operation s

(900 MWe) at 2030.

3/11 At 1000 load was reduced to 860 MWe for physics testing.

3/13 Increased load to capacity (900 MWe) at 2100.

3/14 Decreased load to 645 MWe due to control problems on #21 & 22 ,

steam generator feed pumps at 1300.

3/17 Resumed full load operation (905 MWe) at 1200.

3/22 Decreased load to 640 MWe at 0730 for maintenance on #22  :

steam generator feed pump.

3/23 Increased load to capacity (910 MWe) at 0200.

3/31 At the end of this reporting period Unit II was operating at 910 MWe with the reactor at 100% power.

F 0

b i

l l

l i

SAFETY-RELATED MAINTENANCE UNIT 1

. GROUP I&C MONTil MARCll YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-79-4443 Defective signal Greater than .1 volt Replaced the Features Actuation 11/30/79 Isolator deviation from the other Signal Isolator System / Channel "ZE" channels Pressurizer Pressure ,

Signal Isolator '

I l-E/E-1028 I

il R actor Protection IC-79-134 Defective + 18 VDC Decreased output from Replaced the + 18 VDC System / Channel "A" 12/18/79 power suppTy the 10 VDC reference power supply ~

~

Axial Power Distribution supply Calculator H

Reactor Protection 0-80-38 Dirty terminals on Greater than 22 psi Cleaned the System /#12 Steam 1/4/80 Loop Resistor , difference in Indication Resistor Generator Pressure between channel "D" and Tenninals Indication the other channels 1-PI-1023D Reactor Protection 0-80-76 Dirty terminals on Greater than 22 psi  : leaned the System /#12 Steam 1/8/80 Loop Resistor difference in Indication lesistor Generator Pressure between the four ferminals Indication channels l l-PI-1023 A, B, C l 1

SAFETY-RELATED MAINTENANCE UNIT I GROUP IaC MONTil MARCil YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Safety Injection 0-80-21 The indicating Low differential Adjusted both Systsa/#13 liigh 1/4/80 Instrument 1-PI-301Z pressure indication instruments Pressure Safety and associated across the pump Injection Pump, transmitter were out ,

Pressure Transmitter of adjustment and Indicating Instrument Reactor Protection Systea/ IC-79-129 Faulty trip test Could not read trip Replaced trip Trip Test Cable Channel 12/5/79 cable unit input voltage test cable "C"

Nuclear Instrumentation / IC-79-056 End of Life Detector instrument Replaced 16 Incore Detectors 7/23/79 , malfunction incore detectors

I .

SAFETY-RELATED MAINTEilANCE l UNIT l

GROUP I&C MONTil f1ARCil YEAR 1980 l

MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety IC-79-2167 Signal Isolators Greater than .1 volt Calibrated Isolators Features Actuation 11/30/79 2-E/E-1023 A & D were deviation between 2-E/E-1023 A & D System / Signal Isolators out of nominal channels and replaced for Steam Generator calibration. Isolator Isolator Pressure Instruments 2-E/E-1013D was 2-E/E-1013D 2-E/E-1023A defective 2-E/E-1023D 2-E/E-10130 Engineered Safety 0-79-4377 Pressure transmitter Greater than .1 volt Adjusted the Features Actuation 11/27/79 2-PT-102D was out of deviation fran the transmitter System / Pressurizer adjus tment. Also other ci.cnnels 2-PT-1020 and Pressure Signal discovered the conduit replaced the conduit Channel "ZG" at the transmitter broken Service Water 0-79-2807 Low level alarm Low level alarm was Adjusted the System /#21 Service 9/17/79 setting was out of received and an alarm setting on the Water _llead Tank Level adjustment condition did not Low Level Alarm Indication exist 2-LI-1579

SAFETY-RELATED MAINTENANCE

1. 4' UNIT II GROUP I&C MONTH MARCH YEAR 1980 i MALFUNCTION I SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION S:rvice Water 0-79-3907 Level Transmitter The Head Tank make-up Replaced the Level System /#21 Service 10/19/79 2-LT-1579 was valve would not operate Transmitter Water Head Tank Level defective: output on a low level in the 2-LT-1579 Transmitter non-repeatable tank ~

2-LT-1579 S rvice Water 0-79-4077 The Alarm setpoint was Received low level alarm Adjusted the alarm System /f21 Service 11/12/79 Out of adjustment and alarm condition did setpoint

. Water Head Tank Level not exist Indication 2-LI-1579 4

R: actor Protection Systei/ 0-79-2690 Defective card A-5 in Nuclear power signal Replaced card A-5 Linear Power Drawer 9/6/79 Instrument drawer. ,

would drift and cleaned the Channel "D" Also dirty drawer drawer rails.

rails.

Engineered Safety 0-79-4478 Loose input terminal Greater than .1 volt Tightened the Features Actuation 12/3/79 connections for deviation between terminal connections System / Channel "2G"; #22 2-E/E-1023D channels Steam Generator Pressure Instrament Signal Isolator 2-E/E-10230

. a --- - - _-. -_ _ . ____ - - - _ _ _ , - _ . . _ . - - _ . - - . _ _ - - - _ _ _ _ - - . _ . _ . - - _ . - - . _ . _- _. -. .. -_, .

SAFETY-RELATED MAINTENANCE UNIT II ac GROUP I&C MONTH HARCH YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-79-4296 Defective logic Both logic modules Replaced Features Actuation 11/22/79 modules failed to trip when its both logic System / Safety Injection test button was depressed modules Actuation Signal Logic Module B-5 and Contain-ment Isolation Signal Logic Module B-5 on Channel "2B" T-Engineered Safety IC-79-2098 Defective signal Signal oscillations Replaced the Features Actuation Isolators 2-E/E-5316C from sensor modules signal isolators System / Channel "ZF", 10/9/79 and 2-E/E-5316D Containment Radiation 2-E/E-5316C and Signal Sensor 11odule 2-E/E-5316D Signal Isolator 2-E/E-5316C and 2-E/E-53160 ,

i i

I I

e -, _. -.. -

N O

I 0 T 8 C 9 &

1 A s E l 7 R V ei4 A I ho0 E T t c4 Y C - 8 E ddV4 R eiS0 R co 4 an2 -

O l e V C pl rS eoo-Rsf2 d

l u

P oe O wt emo H

S H T C

R L

U mve al r I E A S ea I '

M E tVy R S b n

not iiul T P H atho I U T N Masr N O N O l t U R O I 2otn G M T 2soo C #i nc E N C U N F A L N A E M O T

N d I i A o M n E e D S l E U o T A s A C L e E v R i

- t Y cs T el E fi F

A DC eo S

E T

A D

1

. 3 O 29 N 7 9/

R 76 M /

02 T

N E

N O n P /i8 M e 4 O mvs0 C all4 eai R tVo&

O S C n 7 M nod 4 E iii0

. T ato4

. S Man-

_ Y l eV

- S 2olS 2so-

_ #IS2 A

N 0 O I

8 9 T 1 C A

E m R V a A I c

E T dr Y C ee E E cw C R ao l

t R ll O pl Al f C eo E Rf T

l f

l A

M .

e L m A o C c I

l e

t b A l l

l l C T d C R L a

n. U E A h n M  !

f S

E R

rn oe op do T P !

l rk I U T 1 ec N O N O nu U R O I nt G M T I s C

E N !I C U f F A L N A

- E t f r e T e N w I

A o

l M l D

E S f o

E U T A m A C a L C E

R n

- e Y k T o E r F B A

S 9

E 7 T 9

_ A 1 D ,

- 0 01

. 2

_ O 0r N 4e

- b R 9o M 7t c

0O G

l T e

_ N E n n

N o O s

_ P r

- M e

_ O P C )

R 2 O (

M ok E wc T To S L Y t S i r ni UA

.