ML19207B076

Monthly Operating Rept for Jul 1979

ML19207B076
Person / Time
Site:	Calvert Cliffs
Issue date:	08/15/1979
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19207B074	List: ML19207B073 ML19207B076
References
NUDOCS 7908230349
Download: ML19207B076 (17)

Text

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OPERATING DATA REPORT DOCKET NO. 50-312 DATE 8/15/79 COMPLETED BY S.

D. Merson TELEPHONE 301-236-5240 OPERATING STATUS

1. Unit Name: Ca1 vert Cliffs No. 1 Notes

2. Reporting Period:

'"1v-1070

3. Licensed Thermal Power (Mht).

2700

4. Nameplate Rating (Gross MWe):

418

5. Design Electrical Rating (Net MWe): 945

6. Maximum Dependable Capacity (Gross MWe): 845 810

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Level To which Restricted. lf Any (Net MWe): 700 %'e

10. Reasons For Restricions.If Any:

Blade eroblems in the hich-oressure turbine.

This Month Yr..to.Date Cumulative

11. Hours in Reporting Pcriod 744 5.087 37,092

12. Number Of Hours Reactor Was Critical 500.1 2.725.1 28,813.7

13. Reactor Reserve Shutdown Hours 10.6 133.3 1,02e.9

14. Hours Generator On.Line 361.4 2,558.2 28,103.2

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 750.240.6 6.312,686.8 67.582.891.2

17. Gross.'lectrical Energy Generated (MWHi 220,637 2,039.053 22,425.388

18. Net Electrical Energy Generated (MWH) 200.561 1.936.086 21,391,074

19. Unit Service Factor 48.b 50.J 75.8 48.6 50.3 75.8

20. Unit Availability Factor

21. Unit Capacity Factor (Using MDC Net t 33.3 47.0 71.2

22. Unit Capacity Factor iUsing DER Net) 31.4 45.0 68.2

23. Unit Forced Oe. age Rate 49.8 26.8 9.9

24. Shutdowns Scheduled Over Next 6 Months iType. Date.and Duration of Each t:

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

26. Units in Test Status lPrior to (.ommercial Operationi:

Forecast Achieved INITIAL CRITICA LITY INITIA L ELECTRICITY COMMERCIAL OPERATION e, '

(9/77)

(]z 7

7908230)

OPERATLNG DATA REPORT DOCKET NO.

50-318 DATE 3/15/79 COMPLETED BY

s. D. Merson TELEPHONE 101-234-5240 OPERATING STATUS Notes

1. Unit Name: Calvert Cliffs No. 2

2. Reporting Period: Julv, 1979 2700

3. Licensed Thermal Power (MWt):

911

4. Nameplate Rating (Gross MWe)-

845

5. Design Electrical R= ting (Net MWe):

845

.. Maximum Dependable Capacity (Gross MWe):

810

7. Maxim.m Dependable Capacity (Net MWe):

8. If Changes Occur in capacity Ratings titems Number 3 Through 7)Since Last Report. Gi e Reasons:

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

None

10. Reasons For Restrictions.If Any:

N/A This Month YrAo-Date Cumulative 744 5,087 20,447

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 670.1 4,763.9 17,750.4

13. Reactoe Reserve Shutdown Hours 73.9 121.2 340.0

14. Hours Generator On-Line 652.2 4,670.0 17,481.8

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,713,842.4 12,120,564.0 43.004.580,o

17. Gross Electrica! Energy Generated (MWHi 559.059,_,

4,037,000 14,291,081

18. Net Electrical Energy Generated (MWH) 535.152 3,862,106 13,630,135

19. Unit Service Fa: tor 87.7 91.8 85.5

20. Unit Aviilability Factor 87.7 91.8 85.5 88.8 93.7 82.3

21. Unit Capacity Factor iUsing MDC Netp

22. Unit Capacity Factor t%ing DER Net) 85.1 89.8 78.9 10.6 3.7 5.3

23. Unit Forced Outi 4e

24. Shutdowns Sch Over Next 6 MonthsiType. Date.and Duration of Each):

F11 vert Cliffs Na. 2 is scheduled for a olanned outage startine October 14 1979, and will be six weeks in duration for general insce : tion and refuelina.

25. If Shut Down At End Of Report Period Estimated Date of Startup: _ August 3, 1979

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

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION

}'

~

(0/77)

AVERAGE dally UNIT POWER LEVEL DOCKET NO.

50-317 UNIT calvert Cliffs #1 DATE 8/15/70 COMPLETED BY 1 D. Merson TELEPHONE 301-234-5240 M OP4Til. Juiv. 1070 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POhER LEVEL (MWe Net)

(Mwe. Net) l'71 I

17 2

18 607 727 3

g9 4

20 765 5

23 73 6

22 476 7

23 8

498 24 606 9

25 10 26 II 27 448 709 12 23 13 29 674 14 71 786 30 315 15 31 772 16 326

!NSTRUCTIONS On this format. list the average daily unn power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-318 UNIT Ca_1 vert Cliffs #2 8/15/79 DATF S. D. Merson COMPLETED BY 301-234-5240 TELEPHONE MONTH July, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

I 17 2

837 18 828 837 824 3

g9 736 4

20 3

R33 21 830 837 830 6

22 838 830 7

g 837

- 831 g

g 837 830 9

25 838 826 10 7

11 836 27 815 834 31 32 28 824 13 29

~

14 812 30 830 15 3g 16 827 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)

- r.

o UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-117 UNIT NAME Calvert Clitts #1 DATE 8/15/79 g

COMPLETED BY S.

D.

Herson REPORT MONTif,Ju lv. 1979 TELEPil0NE 301-234-5240 r

.!"E 3

Licensee E-r Cause & Corrective No.

Date h

3g

(

,3 g 5 Event 55 8.'8 Acti<m to

$E 5

j #3 g Report a

<N 0 V

Frevent Recurrence d

79-4 740625 F

326.9 C

4 N/A RC FilELXX Forced outage due to late return f rorn previous scheduled outage.

79-5 790721 S

24.1 B

1 N/A ZZ ZZZZZZ Conducted turbine overspeed test.

79-6 790722 F

14.9 A

3 N/A IIA ZZZZZZ Forced outage due to loss of fteld to the exciter which initiated a unit trip.

79-7 790726 F

16.7 A

3 N/A Cl!

ZZZZl.Z Forced outage due to high level in No. 11 13 feed water heater which initiated a reactor trip.

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 Autoinatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restriction 4 Other (Explain) 0161)

E-Operator Training & Ucense Examination F Admir.istrative 5

G-Operational Error (Explain)

Exhibii 1 - Same Source (9/77) llOher (Explain)

UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-118 UNIT NAME Ca l ve r t Cliffs #2 DAT1? 8 /15 / 7" COMPLETED BY s.

t>. Merson REPORT MONT11 iniv-1974 TELEPIIONE 301-234-5240 M

E e

.! E 3

j EE Licensee

$1 Cause & Corrective No.

Date

{

3g g

jg5 Event p

[9 Action to r

$2 E

jgg Report a mO Prevent Recurrence

^

g 6

i' 79-11 790728 S

14.8 B

4 N/A Cil VALVFY Scheduled outage to furmanite feed water cL-ek valve.

Reactor remained critical during this outage.

Shutdowi t

at 21:20 on 790728.

79-12 790728 F

77.0 A

1 N/A ZZ ZZZZZZ Forced outage due to condenser tube failures.

I I

2 3

4 F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain)

I-Manual for Preparation of Data B-Main'enance of Test 2-Manual Scram.

Entry Sheets for Licer.see C Refueling 3-Automatic Scram.

Event Report (i.ER) File (NilREG-D-Regulatory R:striction 4-Other (Explain) 0161)

E-Operator T.aining & Ucense Examination l

F Administrative 5

G-Operational Error (Explain)

Exhibis 1 - Same Source (9/77) llother (E xplain)

8/3/79 REFUELING INFORMATION REOUEST 1.

Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit No. 1 2.

Scheduled date for next Refueling Shutdown:

April 19, 1980 3.

Scheduled date for restart following refueling:

May 29, 1980 4

Will refueling or resumption c: operation thereafter require a technical speci-fication 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 informa tion.

February 22, 1980 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) 300 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 projecteo date of the last refueling that can be discharged to the spent fuel pool assuming the present 1icensed capacity.

October, 1983 l

8/3/79 REFUELING INFORMATION REQUEST 1.

Name of Facility:

Calvert Cliffs Nuclear Power Plant, Unit 2 2.

Scheduled date for next Refueling Shutdown:

October 14, 1979 3.

Scheduled date for restart following refueling: November 21, 1979 4.

Will refueling or resumption of operation thereafter require a technical speci-fication change or other license amendment?

A preliminary review of the design and safety analysis indicate that no changes to the Technical Specification or other amendments are required and that there will be no unreviewed safety questions as defined by 10 CFR 50.59 involved with this reload core design.**

5.

Scheduled date(s) for subm n cing proposed licensing action and supporting information.

August 22, 1979 (if required) **

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) 300 Spent Fuel Pools are comon to Units 1 and 2.

8.

The present licensed spent fuel pool storage capacity and the size cf 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 pi 7jected date of the last refueling that can be discharged to the spent fuel puol assuming the present licensed capacity.

October, 1983 Information has changed since last monthly report.

k

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE July 1979 7/1 At the beginning of this reporting period, Unit I was shutdown for its scheduled third refueling outage.

7/8 Commenced reactor coolant system heatuo at 0650.

7/10 The reactor was brought critical at 1717 and commenced low oower physics testing.

7/14 The Unit was paralleled at 1455 and began increasing load to 50%

power physics test plateau.

7/16 At 2230 began increasing load to capacity.

7/19 Escalated power to 96% whereupon received numerous in-core detec-tor alanns. Power was reduced to 94% to clear the alarms.

7/20 Began reducing load at 2300 to work on 11 feedwater regulating valve and conduct turbine overspeed test.

7/21 The Unit was taken off the line at 0825.

7/22 At 0857 the Unit was paralleled. The turbine trioped due to loss of field to the exciter at 0930. The Unit was again caralleled at 2332.

7/23 Increased load to 705 Sie whE nupon began decreasing load to 550 MWe due to condenser a T and repair of 12 heater drain tank level control valve.

7/26 Began increasing power to full load operation and at 0938 the reactor tripped on high level in 11B feedwater heater. The reactor was brought critical at 1725 and the Unit paralleled at 2020. At 2251 the reactor tricoed on high level in 12 mois-ture separator reheater drain tank.

7/27 The reactor was brought critical at 0139 and the Unit paralleled at 0255. Began increasing load and at 1425 started decreasing power due to 12 feedwater pump vibration problems. At 2210 began increasing load.

7/28 Reduced load to 750 MWe to investigate saltwater leakage into the main condenser.

7/29 Reduced load at 0520 to 500 MWe tc alean condenser water boxes.

Resumed full load operation (825 MWe) at 2000.

,f n At the end of the reporting period load was being reduced to 700 We to clean condenser water boxes.

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE July 1979 7/1 At the beginning of this reporting period, Unit 2 was vperating at 880 MWe with the reactor at 100% power.

7/4 At 0145 Control Element Assembly (CEA) 2 dropped into the core.

Reactor power was inuediately reduced to less than 70% in ac-cordance with the Technical Specifications. CEA 2 was withdrawn back to its group at 0307. Full load operation (880 MWe) resumed at 1115.

7/13 Reduced load at 2300 to 800 MWe to work on the Amertap System.

Resumed full load operation (880 MWe) at 0700.

7/20 Load was decreased to 720 MWe to clean condenser water boxes.

Full load operation (820 MWe) was resumed at 0900.

7/27 At 2210, started decreasing load to furmanite feedwater check valve.

7/28 The Unit was taken off the line at 0410. The reactor was shut-down at 2120 due to a major condenser tube rupture.

7/29 At 1450 the reactor was in cold shutdown.

7/31 At the end of this reoorting period, Unit 2 was shutdown to clean up secondary chemistry.

"Y

SAFETY-RELATL3 MAINTENANCE UNIT I

caoup MACilINE Sii0P MONTH JULY YEAR 1979 MALFUNCTION SYS"EN OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 12 Salt Water Pump M-78-407 9/28/76 Excessive shaft sleeve Excessive Packing gland Installed new wear leakage stainless steel shaft sleeve 1-AFW-3988 Auxiliary 0-78-4008 5/11/T9 Valve was held open by Valve would not close Reshaped strainer Feed Water Trip Valve strainer.

completely and reinstalled 1-RV-325 #12 Charging M-79-156 2/9/79 Pitted valve disc Valve leaking past seat Replaced valve Pump Discharge Relief disc Valve

1. 11 Steam Generatur M-79-260 5/3/79 Initial clamp installa-Steam seperator was Replaced clamp on tion was impropr loose on its mounting seperator i

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3 M

SAFEPY-RELATED MAINTENANCE UNIT I

GROUP MACilINE SHOP MONTH JULY YEA" 1979 MALMJNCTION SYfiPEM OR COMNNENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 1-CV-5156 #11 Service 0-79-883

(,j7/79 Solenoid sticking and Valve did not close Replaced solenoid Water lleat Exchanger mechanical binding completely and reshimed actua-Emergency Salt Water tor mounting plate Discharge Valve

1. 11 Main Steam 0-79-1505 5/17779 Cyclic fatigue llole in bladder Replaced bladder Isolation Valve

1. 2 liigh Pressure Pump Surge Supressor a

)

SAFETY-RELATED MAINTENANCE UNIT I

GROUP IAC MONTH JULY YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - MTE CAUSE RESULT CORRECTIVE ACTION Reactor Protection 0-79-372 2/16/79 Defective temperature AT Power potentiometer Replaced temperaturc System / Channel "C" detectors setting out of specified detectors AT Power Potentiometer range.

Engineered Safety 0-79-1049 4/2/79 Defective signal CRS module would not Replaces signal Features Actuation /

isolator trip when given an isolator Containment Radiation alarm condition Signal e

SAFETY-RELATED MAINTFNANCE UNIT l

GROUP "E" Sil0P MONTil JULY YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Breaker 52-1121/#13 E-79-62 4/27/79 Defective amptector Erratic trips of breaker Replaced defective Contair, ment Filter amptector

1. 13 Inverter 0-79-1330 4/30/79 Defective silicon Inverter would not Replaced silicon controlled rectifier start controlled rectifier Reactor Trip E-79-74 5/22/79 Defective under voltage Would not trip TCB-8 Replaced under Swi tchgear/TCB-8 relay on undervoltage voltage relay i

1 Q

4 0

SAFETY-RELATED MAINTENANCE UNIT II GROUP MACHINE SHOP MONTH JULY YEAR 1979 MALMINCTION SYSPEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 23 Salt Water Pump 0-78-1391 j,figj79 Water in guide bearing liigh guide bearing Remove pump and temperature replaced bearing

1. 21 Salt Water Pi'mp 0-78-3246 12/29/78 Corrosion Valve leaking past seat Removed check valve Discharge Check and rebuilt corrod-Valve ed area using belzona

.)

C

SAFETY-RELATED MAINTENANCE UNIT II GROUP ISC MONTH JULY YEAR 1979 MALFUNCTION SYUNH OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-79-1507 5/16/79 Isolation module was Reactor bus under-voltage Installed new Features Actuation defective trip from channel ZG isolation ~ module System / Turbine Trin Actuation Relay Reactor Protective 0-79-1215 4/16/79 Broken plastic plug Could not plug in test Installed new System / Channel "C" cable trip unit Containment Pressure Trip Unit #TU-9 Reactor Protective IC-79-2014 2/22/79 Defective flow trans-Flow signal oscill6tions Replaced flow System / Channel "D" mitter transmitter RPS Flow a

?

2 Reactor Protective IC-79-2012 2/22/79 Defective flow trans-Flow signal oscillations Replaced flow System / Channel "B" mitter transmitter RPS Total Flow i

SAFEfY-RELATED MAINTENAtlCE UNIT II GROUP "E" SHOP M0rmi JULY YEAR 1979 MALFUNCTION SYf7PEM OR COMP 0flENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 21 Emergency Diesel 0-79-1014 3/27/79 Damaged wiring harness Could not load generator Replaced potentia-Generator and motor operated while regulator was in meter and wiring potentiometer auto harness.

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