ML19208B446

Monthly Operating Rept for Aug 1979

ML19208B446
Person / Time
Site:	Calvert Cliffs
Issue date:	09/15/1979
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19208B445	List: ML19208B444 ML19208B446
References
NUDOCS 7909200314
Download: ML19208B446 (18)

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OPERATING DATA REPORT DOCKET NO. 50 117 DATE 9/15/79 COMPLETED BY S. D. Merson TELEPHONE 3nt _91c_s240 OPERATING STATUS Notes

1. Unit Name: Calvere C1iffs No. 1

2. Reporting Period:

Aucuse, 1979

3. Licensed Thermal Power (MWt): 2700

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross MWe): 845

7. Maximum Dependable Capacity (Net MWe): 810

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

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9. Power Level To Which Restricted. if Any (Net MWe): 740 MWe

10. Reasons For Restrictions.If Any: Pihde n enh I am in the hfah-cressure t u rb t ri e .

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This Month Yr.-to-Date Cumulative II. Hours in Reporting Period 744 5,831 37,836

12. Number Of Hours Reactor was Critical 720.7 3,445.8 29,534.4

13. Reactor Reserve Shutdown Hours 9.8 143.1 1,036.7

14. Hours Generator On.Line 712.0 3,270.2 28,815.2

15. Unit Reserve Shutdown flours 0.0 0,0 0,0

16. Gross Thermal Energy Generated (MWH) 1,769,457.6 8,082.144.4 69,352,348.8 .

17. Gross Electrical Energy Generated (MWHi 538,384 ,,

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2.577,437 22,963,772

18. Net Electrical Energy Generated (MWH) 511,519_, 2.447,605 21,902,593

19. Unit Service Factor 95.7 56.1 76.2

20. Unit Availability Factor 95.7 56.1 76.2

21. Unit Capacity Factor (Using MDC Neti 94.4 51.8 71.5

22. Umt Capacity FactorIUsing DER Net) 81.4 49.7 68.5

23. Unit Forced Outage Rate 4.3 97,o 9,7

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

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

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achieved

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LNITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION

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OPERATING DATA REPORT DOCKET NO. 50-318_

DATE 0/15/74 COMPLETED BY 9. n. Merson TELEPHONE 301-234-5240 OPERATING STATUS Calvert Cliffs No. 2 Notes

1. Unit Name:

2. Reporting Period: Aunust, 1979

3. Licensed Thermal Power (MWt): 2700

4. Nameplate Rating (Gross MWe): 911

5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross MWe): 845

7. Maximum Dependable Capacity (Net MWe): 810

8. If Changes Occur in Capacity Ratings (Items Number 3 Thrc~ 2h 7) Since Last Report. Give Reasons:

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

10. Reasons For Restrictions.lf Any:

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This Month Yr to-Date Cumulative

11. Hours In Reporting Period 744 5.831 21.191

12. Number Of Hours Resctor Was Critical 600.3 5.454.2 18.446.7

13. Reactor Reserve Shutdown Hours 53.7 174.9 394.3

14. Hours Generator On.Line 676.6 5,346.6 18,158.4

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 1.704.472.8 13,825,036.8 44,709.053.4 .

17. Gross Electrical Energy Generated IMWH) 544,591 _

4581,600 14,835,672

18. Net Electrical Energy Generated (MWH) 518.395 4,380,501 14,148,530

19. Unit Service Factor 00.9 91.7 85.7

20. Unit Availability Factor 90.9 91.7 85.7

21. Unit Capacity Factor (Using MDC Nett 86.0 92.7 82.4

22. Unit Capacity Factor (Using DER Net) . 88.9 79.0

23. Unit Forced Outage Rate 9.1 4.4 5.5

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

Paive-* clif 4 %. 7 ie e4pduled fn* , ninnned m'r'ae startina nereber 14 1979,

_ and will be six weeks in duration for general insoection and refueling.

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

26. Units In Test Status IPrior o Commercial Operationi: Forecast Achieved

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INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-317 Calvert Cliffs #1 WIT DATE 9/15/79 COMPLETED BY S. D. Merson TELEPHONE 301-234-5240 MONTH Aunust. 1974 DAY AVERAGE DAl PO ER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1 701 17 769 2 709 743 18 3 19 792 4

787 735 20

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5 685 21 774 686 756 6 22 7

700 807 23 g 675 808 24 9 666 807 10

• 26 721 11 548 27 517 32 28 324 I3 29 765 I4 30 793 15 745 804 16 INSTRUCTIONS On this fortnat. list the average daily unit power level in MWe. Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

(9/77) oE 212

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 UNIT Calvert Cliffs #2 DATE 9/15/79 COMPLETED BY S. D. Merson TELEPHONE 301-234-5240 MONTH Aucust, 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) (Mwe. Net)

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1 17 795

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2 18 617 3

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19 731 4 719 770 20 5 809 gg 816 6 22 794 7

809 812 23 8 782 793 24 9 759 25 172 10 741 810 26 1I 719 740 27 12 28 781 13 798 786 29 14 745 832 30 15 33 816 16 790 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)

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DOCKET NO. 50 'I I 7

• UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Calvert Cliffs No. 1 DATE 4/15/79 COMPLETED BY s.n. tierson REPORT MONTH Auaus t . l'87 9 301-234-5240 e.

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No. Date

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.!E 3 .h Ek Licensee Eg f4 Cause & Corrective k 5@ 4 2s5 Event s7 c Action to H g3 E 5 jgg Report 8 50

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79-8 790810 F 8.3 A 3 N/A ZZ ZZZZZZ Forced outage due to the loss of No.

15 circulating water pump which resulted in a loss of vacuum trip.

79-9 790812 F 7.3 11 3 N/A ZZ ZZZZZZ Forced outage due to low steam genera-tor level which initiated a reactor trip.

79-10 790827 F 16.4 A 1 79-046 PC PIPEXX Forced outage due to a leak in the chemical volume control system.

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 oi Test 2-Manual Scram. Entry Sheets for Licensee C Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination

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-d G-Operational Es ror (Explain) Exhibit I - Same Source (9/77) t" llother (Explain) ix'-

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- ' O UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-313 PQ UNIT NAME Calvert Cliffs No. 2

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DATE 4/15/74 630 ggpgg7 ggg73, g,,gyt, 1979 Ni.EED n S .D . W mn TELEPHONE 101-234-5240

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- jg 3 jYh Licensee Ev, gg Cause & Corrective No. Date k

e 5g i 2 ~5 Event g gg' Action to g5 5 g gy, Report a mV g Prevent Recurrence d

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79-12 790728 F 67.4 A 1 N/A ZZ ZZZZZZ Forced outage due to condenser tube failures.

79-13 790818 F O.0 A 4 Forced reduction due to condenser tube leaks.

i 1 2 3 4 F: Forced Reason: Method:

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

'2 E-Operator Training & Ucense Examination

-< F-Administra ise 5 tr G Operational Es ror (Explam) Exhibit I Sanw Source

9/77) llother iExplain)

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9/10/79 REFUELING INFORMATION REQUEST

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 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 infonnation.

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 dore 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 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 olb 2\b

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9/10/79 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 tech-nical specification change or other license amendment?

A preliminary review of the design and safety analysis indicate that no changes to the Technical Spedification 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 submitting 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 of 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 projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

October, 1983 U]5 2\

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - AUGUST 1979 8/1 At the beginning of this recorting period, load was being decreased on Unit I to E35 We to clean condenser water boxes. Began increasing load and at 1930 reduced load to 745 We to investigate saltwater leakage into the main condenser.

8/2 Load was increased to capacity (815 We) at 0405.

8/5 Reduced load to 655 We at 1030 to investigate saltwater leakage into the main condenser.

8/6 Resumed full load operation (815 We) at 1800. Reduced load to 655 We at 2241 to investigate saltwater leakaoe into the main condenser.

8/7 At 0430 started increasing load and at 1525 reduced load to 685 We to investigate saltwater leakage into the main condenser. Began increasing load at 1852.

8/8 Load reduced to 685 We at 0430 to investigate saltwater leakage into the main condenser.

8/9 At 2000 started increasing load.

8/10 Reduced load to 655 We at 1025 to investigate saltwater leakage into the main condenser. The reactor tripoed on loss of vacuum due to loss of 15 circulating water pumo at 1040. The reactor was brought critical at 1531 and the unit paralleled at 1825. Load was limited to 615 We at 2300 to investigate saltwater leakage into the main condenser.

8/11 At 2140 started reducing power to repair an EHC leak on

1. 2 turbine intercept valve. At 2325 the reactor tripped due to low steam generator level.

8/12 The reactor was brouaht critical at Od'^ and +he unit paralleled at 0717. ~ Resumed full los. .. (815 We) at 1900. Load was reduced to 725 We due to the ETS 120F limit on main condenser circulating water A T.

8/13 Decreased load to 535 We at 1500 to investigate saltwater leakage into the main condenser.

8/14 Started increasing load at 1345 and at 2230 comenced reducing power to 605 We to clean main condenser water boxes. Resumed full load coeration (825 We) at 1200.

8/17 At 0345 decreased load to 745 We to investigate saltwater leakage into the main condenser. Full load ooeration (835 We) was resumed at 1600.

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8/18 Load was reduced to 745 Mde at 0345 to investigate saltwater leakage into the main condenser.

8/19 Increased load to capacity (845 M4e) at 0700, 8/20 At 0415 load was reduced to 755 We to investigate saltwater leakage into the main condenser.

8/21 Full load operation (835 Mde) was resumed at 1000. Reduced load to 735 MJe at 2300 to investigate saltwater leakage into the main condenser.

8/22 Increased load to capacity (835 We) at 1800.

8/26 A load reduction was necessitated at 0430 to 735 We to inves-tigate saltwater leakage into the main condenser.

8/27 Started reducing power at 1500 to repair a chemical volume control system leak. The unit was taken off the line at 1830 and the reactor shutdown.

8/28 The reactor was brought critical and the unit paralleled at 1055. Started increasing load and at 1600 load was limited to 755 We to investigate saltwater leakage into the main condenser.

8/29 Full load operation (835 MJe) was resumed at 1700.

8/30 Load was reduced to 815 We due to in-core power distribution problems .

8/31 At the end of this reporting period Unit I was onerating at 815 We. Reactor power was limited to 97". due to in-core power distribution problems.

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SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - AUGUST 1979 8/1 At the beginning of this reporting period, Unit 2 was shutdown to cleanup secondary chemistry due to a major condenser tube ruoture.

8/2 The reactor was brought critical at 2304.

8/3 The reactor was shutdown at 0810 to comply with Technical Specifications on containment radiation samoling. The reactor was brought critical at 0910 and the unit caral-leled at 1054. At 1220 the reactor tripped on loss of load. The reactor was brought critical at 1615 and the unit paralleled at 1815. The reactor trioped at 1900 due to loss of EHC oressure in the main turbine valve control system. At 2045 the reactor was brought critical.

The unit was paralleled et 2135.

8/5 Load was increased to capacity (845 P4e) at 0100.

8/8 At 1100 load was reduced to 765 Pde to investigate salt-water leakage into the main condenser. Full load ooera-tion (845 M4e) was resumed at 2040.

8/9 Load was reduced to 760 Wie at 1100 to investigate salt-water leakage into the main condenser.

8/12 At 0500 load was decreased to 705 MWe due to the ETS 12 F limit on main condenser circulating water A T.

8/13 Resumed full load operaton (845 MWe) at 1930.

8/14 At 2100 load was reduced to 765 MWe to investigate salt-water leakage into the main condenser. Increased load to capacity (845 MWe) at 2300.

8/16 Decreased load to 755 Mde at 1500 to investicate saltwater leakaae into the main condenser. Started to increase load at 1830.

8/17 Reduced load at 0300 to 735 *de to investigate saltwater leakage into the main condenser. Full load operation (845 Mde) was resumed at 0900.

8/18 Decreased load to 635 M4e at 0530 for maintenance on 22 Heater Drain Pump.

8/19 Increased load to capacity (845 MWe). Reduced load at 1400 to 735 MWe to investiaate saltwater leakage into main condenser.

8/20 Resumed full load operation (865 MWe) at 1730.

8/21 At 1800 reduced load to 765 MWe to investigate saltwater leakage into the main condenser.

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8/22 Started increasing load and at 2000 reduced load to 740 M4e to investigate saltwater leakage into the main condenser.

8/23 Increased load to capacity (865 M4e) at 0640.

8/24 Reduced load at 2030 to 735 M4e to investigate saltwater leakage into the main condenser.

8/25 Resumed full load operation (845 M4e) at 1700.

8/26 Load was decreased to 765 M4e at 0150 for main turbine governor valve testing. Load was returned to capacity (865 P4e) at 0900.

8/27 At 0130 load was decreased to 765 P4e to investigate saltwater leakage into the main condenser.

8/28 Began increasing load and at 2230 reduced load to 810 94e to investigate saltwater leakage into the main condenser.

8/29 Increased load to capacity (855 M4e) at 1700.

8/31 At 2150 reduced load to 745 M4e to investigate saltwater leakage into the main condenser. At the end of this reporting period, Unit 2 was operating at 745 M4e. Reactor power was limited to 93% while investigating for saltwater leakage into the main condenser.

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SAFErY-RELATED MAINTENANCE

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mn I GROUP ELECTRIC SHOP MONTH AUGUST YEAR 1979 MALFUNCTION SYM EM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 11 Pefueling Water 0-79-1690 6/7/79 Close limit switches out The valves stay open 4 to Adjusted the close Tank Outlet Motor of adjustment 6 turns when electrically limit switch Operated Valves shut

1. 11 Switchgear Air 0-79-2014 7/5/79 Condenser fan motor de- Condenser fan breaker Replaced fan motor Conditioner fective kept tripping Reactor Trip Switchgear/ 0-79-2067 7/8/79 Wire on trip pushbutton Breaker would not close Reconnected wire Breaker TCB-9 was disconnected

1. 13 Inverter / Vital 0-79-2211 7/20/79 Defective fuse holder low output voltage alarm Re-soldered fuse-AC Power solder connection with output voltage at holder normal value

1. 11 Control Room Air 0-79-1708 6/9/79 Defective compressor A/C unit would not run Replaced A/C com-Conditioner motor pressor motor

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SAFETY-RELATED MAINTENANCE

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WM I GROUP IRC MONTH AUGUST YEAR 1979 MALMINCTION SYSFD1 OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Pressurizer Relief 0-79-1306 5/21/79 Loose field lead connec- Erroneous temperature Tightened loose Valve Outlet Tempera- tion on temperature reading connection on ture 1-TE-108 element temperature element

1. 11A Safety Injection 0-79-1645 6/12/79 Limit switch on valve Incorrect valve position Adjusted limit Tank Vent 1-SI-613-CV was out of adjustment indication switch Reactor Coolant System / 0-79-1297 5/2/79 Defective temperature Temperature indication Replaced temperature 12A Loop Cold Leg element failed iiigh element Temperature 1-TE-125 Steam Generator Outlet 0-79-1311 5/16/79 Defective temperature Erroneous indication Rrplaced temperature Temperature 1-TE-4008 element element

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SAFETY-RELATED MAINTENANCE UNIT I GROUP Igc MONTH AtlGilST YEAR 1979 MALFUNCTION SYSFD4 OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Pressurizer Level 0-79-2055 7/11/79 Defective oscillator in Erroneous level indica- Replaced defective Indication LT-103 transmitter tion oscillator Nuclear Instrumentation 0-79-1955 7/11/79 Dirty signal connector Increase in counts for Cicaned signal Channel "A" Wide Range on drawer no apparent reason connector on drawer

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Nucleir Instrumentation 0-78-1292 7/2/79 Defective atidio Channels A, B. & C Replaced audio Wide Ranss/ Audible amplifier Inoperable Amplifier Count P, ate Ir:strument

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Engineered Safety 0-79-1947 6/28/79 Defective logic module #11 liigh pressure -1

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Replaced defective Features Actuation safety injection p0mre logic module system /A2 Logic Module did not start on SEAS signal

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Reactor Protection 0-79-2076 7/9/79 Defective matrix relay Associated' trip circuit Replaced defective System / Matrix Relay breakers would not trip matrix relay -

AC-3 while performing surveil-

. .; lance test procedure s,

tJ- i Steam Flow Indicaticn '

0-79-208 5/28/79 Defective transmitter Steam flow pegged low Replaced defectise I'J on 1-FR-1011/1111 on recorder transmitter 1-FT-1011 N

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SAFEPY-RELATED MAINTENANCE UNIT II GROUP MACHINE SHOP MONTH AUGUST YEAR 1979 MALMINCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRE0"PIVE ACTION Number 22 Main Steam 0-79-2339 8/2/79 Air in pump Pump had no discharge Vented pamp Isolation Valve pressure Hydraulic Package.

Number 2 High Pressure l Pump

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SAFETY-RELATED MAINTENANCE UNIT II GROUP ELECTRIC SHOP MONTH AUGUST

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YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 21 Diesel Generator / E-79-45 6/25/79 Field flash circuit Over heated and Replaced resistors Exciter Cabinet energized after damaged resistors and connecting wire 2C61C diesel shutdown in excitar cabinet

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Switchgear Air M-79-3129 7/31/79 #21 Condenser fan The breaker for +he Replaced #21 fan motor Conditioner / Con- motor was grounded condenser fans tripped denser Fan Motor when the A/C unit was started

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SAFETY-RELATED MAINTENANCE _

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UNIT II GROUP IAC

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MONTH AUGUST YEAR 1979 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION.

Engineered Safety 0-79-1602 5/25/79 B-8 Safety Injection SIAS B-8 would not acto- Replaced faulty Features Actuation Sys- actuation signal module ate on containment pres- module tem / Containment Pressure was faulty sure from any of the sensor channels Service Water System / 0-79-1782 6/13/79 Valve position microswitch Valve was open but the Adjusted the valve Turbine Bldg. Isolation was out of adjustment close position indication position microswitch Valve 2-CV-1600 would not go out Engineered Safety 0-79-1649 6/5/79 Defective bistable Spurious trips Replaced bistable Features Actuation System /CVCS Ch. ZE Safety Injection Tank 0-79-1164 4/9/79. Broken glass on indication Incorrect level indica- Replaced broken glass Level Indication /2-LIA- instrument in Control tion 331 Room Reactor Protection IC-79-2039 4/11/79 Faulty relay in G-2 module Reset demand light on Replaced G-2 module System / Channel "A" channel "A" would not y Variable Over Power Trip come on

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Engineered Safety Fea- 1C-79-2068 7/17/79 Faulty voltmeter Power supply voltmeter Replaced voltmeter tures Actuation System / pegged low

', Channel "ZD" SVDC Power  %

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