ML19269B935

Monthly Operating Rept for Dec 1978

ML19269B935
Person / Time
Site:	Calvert Cliffs
Issue date:	01/15/1979
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19269B934	List: ML19269B933 ML19269B935
References
NUDOCS 7901190054
Download: ML19269B935 (14)

Text

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OPER ATING DATA REPORT DOCKET NO. $0-317 DATE 1713/79 COMPLETED BY S. D. Morson TELEPilONE 301-23h-52ho OPERATING STATUS N te$

Calvert Cliffs No. 1

1. Unit Name:

December 1978

2. Reporting Period:

3. Licensed Thermal Power (MWt): 2700 910

4. Namepir..e Rating (Gross MWe):

Oh5

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

Ob5 810

7. Maximum Dependab!c Capacity INet MWe):

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

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

None N/A

10. Reasons For Restrictions. lf any:

This Month Yr.-to-Date Cumulative 7hh 8.760 12.004

11. Ilours In Reporting Period bb9*1 6.385,0 26.088.6

12. Number Of flours Reactor Was Critical 29h.9 355.7 891.6

13. Reactor Resene Shutdown flours 390.6 6,153.3 pg,ghg.o

14. Ilours Generator On-Line

15. Unit Resene Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWill 967.632.0 ll dQl,279.8 61.270.20h.h h

17. Gross Electrical Energy Generated (Mwili 327.7h8 h.911.192 20.186.114 310,363 h',676,123 19,hgh,988

18. Net Electrical Energy Generated (Mb H) 52.5 70.2 79.8

19. Unit Senice Factor 52+6 70.2 79,8

20. Unit Availability Factor 51*6 65.9 74.0

21. Unit Capacity Factor (Using MDC Net) 09'h 63.2 71,9

22. Unit Capacity Factor iUsing DER Net)

23. Unit Forced Outage Rate h7.5

'll.O 7,7

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

Calvert Cliffs No.1 is scheduled for a planned c>ut:we ut nrtirm April lb.1979 and will be six week's in duration for general insoection and refueling.

1/20/79

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

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICA LITY INITI A L ELECTRICITY COMMERCI AL OPER ATION 7 9 01 19 0 0$i (a/77)

OPERATING DATA REPORT DOCKET NO.

50-318 DATE 1/15/79 COMPLETED !!Y 4 1.J.erson TELEPflONE 301-22-52h0 OPER ATING STAT US N tes

1. Unit Name: Calvert Cliffs No. 2

2. Reporting Period:

Decernber. 1978 2700

3. Licensed Thermal Power (MWt):

911

4. Nameplate Rating (Gross MWe)

5. Design Electrical Rating (Net MWe):

8h5 Ob5

6. Maximu.., Dependable Capacity IGrow Mhe):

810

7. Masimum Dependable Capacity (Net MWe):

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

None

9. Power Lesel To Which Restricted,if Anv (Net MWe):

N/A

10. Reasons For Restrictions. If Any:

This Month Yr.-to-Date Cumulatise

11. Ilours in Reporting Period 7hh 8.760 14.160

12. Number Of lionrs Reactor Was Critical 73h.5 7.233.6 12[.992.6

13. Reactor Resene Shutdown !Iours 0.0 72.4 219.h

14. Ilours Generator On-Line 710.9 7 a % _7 12.811.8 0.0

' 'O.O

15. Unit Resene Shutdowa llours

_ 0.0

16. Gross Thermal Energy Generated (MbII) 1,873,968.0 16.55h.823.8 30.88h.016.6

17. Gross Electrical Energy Generated (MWilI 6 3 2,018_ __ _ _,, (h99,690 10I24h 1072

18. Net Electrical Energy Generated (MWil) 605,236 5,226.675 9'.768'.029 90.1 81.h 83.h

19. Unit Senice Factor

20. Unit Availability Factor 98.1 81.h RT_b

21. Unit Capacity Facter (Using MDC Net 100.h 73 7 7i3.4 96.3 70.6 75.3

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 1.9 7.0 6.9

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

Calvert Cliffs No. 2 is scheduled for a planned outage starting February 25,1979, and will be one week in duration to test safety related snubbers.

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

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCl \\L OPER ATION N/77)

so, AVER AGE D \\ll.Y UNII P0hER LEVEL DOCKET NO.40-317 UNIT calvert Cliffs #1 s

DATE 1/15/79 COMPLETED BY R. n. Morson TELEPil0NE 301-21h-42h0 MONTil DeccEDCL 1978 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (M We-Net )

(MWe Net) 660 I

732 37 2

827 is 3

827 i9 4

8 211 20 5

8;L1 2

6 823 22 021 7

23 8

817 24 9

787 25 so 8 312 26 1i 822 27 12 017

'S 13 233 29 14 782 30 15 78):

3 16 812 9 INSTRUCTIONS On this forrnat. list the average daily unit power level in MWe-Net for each day in the reporting month. Coinpute to the nearest whole megawatt.

(9/77)

n, AVERAGE D AILY UNIT POWER LEVEL DOCKET NO.

50-318 Calvert Cliffs #2 UNIT 1/1b/79 DATE COMPLETED BY S. D. Merson TELEP110NE 301-21h-52IA MONTil December, 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL 01We-Net)

( MWe-Net )

i 8h5 17 8h6 2

837 18 8h7 3

699 19 8h6 4

8h5 20 8hh 5

8h5 21 8h3 6

851 22 8h6 8h9 23 851 7

8 837 24 859 9

Ob2 25 232 to 733 26 769 11 838 27 806 12 852 28 8h2 13 8hl 29 8h8 14 8h3 30 840 15 8hh 3

850 16 8b6 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.

(9/77) a

DOCKET NO.

60 ~43 7 UNIT SHUIDOWNS AND POWER REDUCTIONS UNIT NAME Calvert CHffs No.1 DATE 1/16/79 COMPLETED BY S. D. Merson REPORT MONT11 Dece+er: 1978 TELEPIIONE 301-23h-52ho a..

c

.5 g 3

4Y~

Licensee

,E n, gn, Cause & Corrective No.

Date i

3s d

ij5 Esent 37 p'LE Action to f:

5 5gf Report :

mV 5

Prevent Recurrence

+

e v

6 78-18 121378 F

12.h G

3 N/A ZZ ZZZZZZ Forced outage oue to an operat'c error when No.11 precoat filter drain valve was opened. This resulted in the tripping of No.11 and No.12 steam generator feed pumps duc to low suction pressure. Low steam generator level caused a reactor trip.

78-19 121778 F

3hl.1 A

3 N/A HA ZZZZZZ Forced outage due to vibration on the high-pressure turbine.

I 2

3 4

F: Fo rced 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 Report (LER) File (NUREG-D Regulatory Restriction 4-Ot her ( Explain) 0161) 1 -Operator Training & License Examination F-Adnunistratise 5

G-Operational Er ror (Explain)

Exhibit 1 - Same Source (9/77)

Il-Ot her ( E xplain)

DOCKET NO.

40 11 R UNIT SifUTDOWNS AND POWER REDUCT10NS UNIT N AME r'al ve rt n14cis No. 2 DATE 1/16/79 OM l-23-5250 REPORT MONT11 Deca-bor. 1978 LEP IONE E

E

.] g 3

4 E]

Licensee

[g K

Cause & Correctise No.

Date c-

%=

4

_s d 5 Esent a?

c. ?

Action to Report =

iE 0

}U 4

j@

jdg Prevent Recurrence 6

78-21 122578 F

13.8 A

1 78-0$0 C3 PIPEXX Forced outage due to excessive reactor coolant leakage caused by a cracked weld on No. 21A Reactor coolant pump's upper seal pressure sensing line.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G -Instruetions S: Sched uled A Equipment Failure (Explain) 1 -Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C.Refuelin; 3-Automatic Scram.

Event Report (l.ER) File (NUREG-D Regulatory Restriction 4-Ot her ( E xplain )

0161) 1 -Operator Training & License Examination F-Ad minist rat ne 5

G-Operational Er ror (Explain)

Exhibit 1 - Same Source (9/77)

Il-Ot he r ( E xplain )

1/11/79 REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown April 14, 1979 3.

Scheduled date for restart following refueling May 22, 1979 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, 1979 **

6.

Important licensing considerations associated with refueling.

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

Selected fuel assemblies will be modified by installation of sleeves in the Guide Tubes.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 228*

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 which has changed since last monthly report.

1/11/79 REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown October 6, 1979 3.

Scheduled date for restart following refueling November 8, 1979 4.

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

Resun.ption of operation after refueling will require changes to Technica' 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.

July 6, 1979 6.

Important licensing considerations associated with refueling.

Reload fuel will be similar to that reload fuel inserted into the Cycle 3 of Unit 1.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

(a) 217 (b) 228*

Spent Fuel Pools are common to Units 1 and 2 8.

The present licensed spent fuel pool storage capacity 'nd the size of any increase in licensed storage capacity that has.;een 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

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - DECEMBER 1978 12/1 At the beginning of this reporting period, Unit 1 was operating at 863 MWe with the reactor at 95% power.

Reactor power being limited by the Environmental Technical Specif1.ation (ETS) 10 F limit on main condenser circulating water AT. At 0255 reduced load to 737 MWe to investigate salt water leakage into the main condenser.

12/2 Increased load to 865 MWe at 0200 after plugging one tube.

Reactor power was limited to 95% due to the ETS 10 F limit on main condenser circulating water AT.

12/8 Reduced load to 730 MWe at 2155 to clean main condenser circulating water boxes.

12/9 Increased load to 860 MWe at 1000.

Reactor power was limited to 95% due to the ETS 10oF limit on ma,a condenser circulating water AT.

12/13 The unit tripped at 0117 due to low steam generator water level after the feed pumps tripped on low suction pressure when 11 precoat filter drain valve was inadvertently opened. At 0552 the reactor was brought critical. The reactor was manually shutdown at 0615 when the shift supervisor recalled that Technical Specification action statements 3.7.3.1 and 3.7.5.1 were in effect (LER 78-054/

OIT describes this event). The reactor was brought critical at 1145 and the unit paralled at 1345.

SUMMARY

OF UNIT 1 OPERATING PAGE 2 EXPERIENCE - DECEMBER 1978 12/14' Resummed full load operation (857 MWe) at 1030. Reactor power was limited to 95% due to the ETS 10 F limit on main condenser circulating water AT.

19/15 At 1242 decreased load to 752 MWe to investigate salt water leakage into the main condenser.

Resumed full load operation (880 MWe) at 2400 after the leak disappeared.

Reactor power remained limited to 97% due to the ETS 10 F limit an main con-denser circulating water AT.

12/17 At 1645 began decreasing power to investigate salt water leakage into the main condenser. The unit tripped at 1856 due to main turbine high vibration.

12/18 At 0217 the reactor was brought critical.

12/20 At 1030 the reactor was shut down after attempts to rebalance the main turbine failed.

4 12/31 At the end of this reporting period the reactor was shutdown and cooled down. Repairs to correct vibration problem on main turbine high pressure turbine were in progress.

SUMMARY

OF UtlIT 2 OPERATING EXPERIENCE - DECEMBER 1978 12/1 At the beginning of this reporting period Unit 2 was performing cycle 2 escalation to power physics testing. The unit was operating at 890 MWe with reactor power limited to 98% by the Environmental Technical Specif.ication (ETS) 10 F limit on main condenser cir-culating water AT.

12/2 Decreased power to 633 MWe at 2118 for an ASME heat rate test.

12/3 Resumed full load operation (871 MWe) at 1900.

Reactor power was limited to 97% due to the ETS 10 F limit on main condenser circulating water AT.

12/9 At 2200 decreased power to 650 tUe to conduct on ASME heat rate test.

12/10 Resumed full load operation (884 PNe) at 1430 Reactor power was limited to 98% due to the ETS 10 F limit on mair condenser circulating water AT.

12/17 Completed cycle 2 escalation to power physics testing.

12/25 The unit was taken off line at 0904 to locate the source of reactor coolant system leakage in excess of Technical Specification limits.

The reactor was maintained critical. While increasing power to parallel the unit after isolating a cracked weld on 21A reactor coolant pump, the reactor tripped due to spurious high startup rate signals. The reactor was brought critical at 2000. The unit was paralleled at 2249.

SUMMARY

OF UNIT 2 OPERATING PAGE 2 EXPERIENCE - DECEMBER 1978 12/26 Full load operation (855 MWe) resumed at 0500.

Reactor power containued to be limited to 98% due to the ETS 10 F limit on main condenser circulating water AT.

12/31 At the end of the reporting period Unit 2 was operating at 887 MWe with the reactorat 100% power.

SAFEfY-RELATED MAINTDIANCE UNIT 1

GROUP ELECTRICAL & I&C MONTH DECEMBER YEAR 1978 MALFUNCTION SYTfEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE' ACTION Main Steam Isolation 0-78-3250 10/12/78 Coil shorted

1. 12 High pressure oil Rcplaced solenoid Valve #11 High pump wouldn't start valve coil.

Pressure Oil Pump Unloader 1 -V-9626 1-HS-5463 Containment 0-78-3807 11/13/78 Defective handswitch 1-MOV-5463 wouldn't open Replaced handswitch.

Normal Sump Drain Valve Control Switch

SAFEfY-RELATED MAINTENANCE UNIT 2

GROUP ELECTRICAL & I&C MONTH DECEMBER YEAR 1978 MALFUNCTION SYS"EM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE' ACTION Main Steam Isolation E-78-200 10/27/78 Solenoid valves Erratic valve perfomance Replaced solenoid Valve #21 Solenoid occasionally stuck upon closure signal valve coils with Valves 2-SV-4042 when energized higher wattage 2-SV-4043 types Steam Generator #22 0-78-3770 11/10/78 Ruptured moisture seal Ground on 125 volt Replaced position Bottom Blowdown on valve position D.C. Buss switch "ontrol Valve switch 2-CV-4013 Reactor Trip Switch 0-78-3873 11/19/78 Open winding in circuit Circuit breaker tripped Replaced under Gear Circuit Breaker breaker under voltage voltage coil TCB-21 coil