ML19318C359

Monthly Operating Rept for May 1980

ML19318C359
Person / Time
Site:	Calvert Cliffs
Issue date:	06/12/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19318C355	List: ML19318C354 ML19318C356 ML19318C359
References
NUDOCS 8007010392
Download: ML19318C359 (9)

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OPERATING DATA REPORT DOCKET NO. 50--318 DATE 6/12/80 COMPLETED BY c.9 Mercon TELEPHONE w m s240 OPERATING STATUS Ca1 vere C1iffg No. 2 Notes

1. Unit Name:

2. Reporting Period: May, 1980 2,700

3. Licensed Thermal Power (MWt):

911

4. Nameplate Rating (Gross M't'e):

5. Design Electrical Rating (N't MWe): P45

6. Maximum Dependable Capacity (Gross MWe): 860

7. Maximum Dependable Capacity (Net MWe): 825

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since I.ast Report. Give Reasons: i

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

10. Reasons For Restrictions. If Any:

This Month Yr..to-Date Cumulative II. Hours In Reporting Period 744 3.647 27,767

12. Number Of Hours Reactor Was Critical 714.S 3,407.8 23,352.7

13. Reactor Reserve Shutdown Hours 9.5 9.5 422.6

14. Hours Generator On.Line 723.9 3,382.0 22,990.5

15. Unit Reserve Shutdown flours 0.0 0.0 0.0

16. Gross Thermal Energy Generated iMWH) 1,o17,&7n R 7Ao.104 57.033.336 .

17. Gross Electrical Energy Generated (MWHi 616.257 .. 2.u49.454 18,955,177

18. Net Electrical Energy Generated (MWH) 604.016 2.822,489 18,079,509

19. Unit Service Factor 97.3 92.7 82.8

20. Unit Availability Factor 97.3 92.7 82.8 4 21. Unit Capacity Factor (Using MDC Net p 99.2 93.8 79.8

22. Unit Capacity Factor IUsing DER Net) 96 o 91.6 77.1

23. Unit Forced Outage Rate 2.7 1.1 6.1

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

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

24. Units la Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 8 * ?203 % . ._ .

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AVERAGE DAILY UNIT POWER LEVEL A

DOCKET NO. 50-318 UNIT hivert Cliffs #2 DATE 6/12/80 COMPLETED BY 9.D.versen TELEPHONE 301-234-5240 MONTH "'v- 1*

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 861 847

, g _

861 gg 829 2

860 39 787 3 _

4 857 20 847 859 21 844 5

858 22 846 6 --

859 3 847 7

g 857 851 24 856 25 848 9 _

10 168 26 845 ll 434 27 846-852 28 847 12 13 854 29 848 818 848 34 30 851 3g 846 15 16 847 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)

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50 3I8 DOCKET NO.

UNIT SHUTDOWNS AND POWER REDUCTIONS '

UNIT N AME ralvert cliffs #2 DATE 6/12/80 COMPLETED BY S.fl. W rs.m REPORT MONTH Mw - 1oAn TELEPHONE 301-234-5240

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[g Cause & Corrective

.$ ? 3 j .Y ~ Licensee gg j{% Action to No. Date h 3g 4 2g5 Event mO Preveni Recurrence W

3: 5 a g :g:

Report a u

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80-02 800510 F 20.1 A 1 ZZ PUMPXX Loss of excitation to all main circu-lating water pumps.

3 4 I. 2 Method: Exhibit G -Instructiims F: Forced Reason:

for Preparation of Data S: Scheduled A Equipment Failure (Explain) 1-Manual 2-Manual Scram. Entry Sheets for Ucensee B-Maintenance of Test

3. Automatic Scram. Esent Report (LFR) File (NilREG.

C-Refueling D Regulatory Restriction 4-Ot her (Explain) 0161)

E-Operator Training & Ucense Examination 5

F Administrative G Operational Error (Explain) Exhibii 1 - Same Source (9/77) Il-Ot her (Explain)

S/6/80 REFUELING INFORMATION REQUEST

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

2. Scheduled date for next refueling shutdown: January 1, 1981

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 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 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 774 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

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - MAY~1980 5/1 At the beginning of this reporting period, Unit 2 was operating at 900 !We with the Reactor at 100% power.

5/10 At 1052, the Reactor was manually tripped due to loss of excitation to all Main Circulating Water Pumps. The Reactor was brought critical at 2025.

5/11 The unit was paralleled at 0226. At 0456 the unit was taken off the linedue to a blown gasket on 26A Feedwater Heater normal level control valve. After repairs were completed, the unit was paral-leled at 0929. Load was increased to capacity (880 IWe) at 2100.

5/14 Cecreased load to 740 MWe at0110 to investigate saltwater leakage into the main condenser. After indications of leakage disappeared, full load operation (890 We) was resumed at 1545.

I 5/18 Load was reduced to 770 IMe at 2105 to investigate saltwater  ;

leakage into the main condenser. l 5/19 At 1600, load was increased to capacity (885 MWe) after plugging i one condenser tube.

4 5/31 At the end of this reporting period, Unit 2 was operating at 885 !We with the Reactor at 100% power.

SAFETY-RELATED MAINTENANCE ,

UNIT TWO GROUP I&C MONTH MAY YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety IC-79-2096 Defective Bistable Readir.gs were out of Replaced the alann Features Actuation 10-9-79 alana module meter spec. during surveillance module meter.

System / Containment tests.

Pressure Transmitter 2-PT-5313C Bistable Alarm Module, Channel -

ZF Reactor Protective 0-78-2597 Loose terminal Receiving spurious Tightened the System /Thennal Margin 12-10-79 connections. trip lights and alarms, tenninal connections and Low Pressure Trip Drawer, Channel 'C' ,

Radiation Monitoring 0-78-4121 Defective component on Oscillation in the Replaced the rate System 10-15-79 the rate card A-2 in radiation monitoring card. The detector 2-RI-5316D the instrument drawer system and engineered will be replaced 2-RI-5316D. Also had safety features actuation during unit outage.

indication of a defec- system, bistable.

tive detectar.

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SAFETY-RELATED MAINTENANCE ,

UNIT TWO GROUP I&C MONTH MAY YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Radiation Monitoring IC-79-2150 Defective detectors. Oscillation of Replaced detcctors.

System Detectors . 11-17-79 instrument bistable. 2-RE-5316 A, B, C, D 2-RE-5316 A, B, C, D Reactor Protective IC-79-2175 Dirty slide links. Instrument reads high. Cleaned the slide System / Channel 'D' 12-13-79 links.

Temperature Detector Engineered Safety 0-79-4295 Defective signal The instrument channel Replaced the Features Actuation 11-21-79 Isolator. Amplifier. would not actuate a defective signal System / Channel ZD trip system properly. Isolator Amplifier.

Chemical and Volume Con-trol Actuation Sensor Module ,

1. 22 Steam Generator 0-79-4749 Dirty slide links. Reading on Channel 'C' Cleaned the slide Pressure Indication 12-20-79 Indication exceeded links.

1-PI-1023C the maximum deviation.

SAFETY-RELATED MAINTENANCE ,

UNIT TWO GROUP ISC MONTil MAY YEAR 1980 MALFUNCTI0ft SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTIO?t Engineered Safety 0-79-4297 Defective instrument Test circuit would not Replaced instrument Features Actuation 11-22-79 module. function properly. module.

System / Channel ZB Safety In.jection ,

Actuation Signal B-10 .

Test Circuit 0

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SAFETY-RELATED NAINTENANCE ,

• ' UNIT 2 GROUP Machine Shcp .

. . . g , i MONTl[ May YEAR.- i 1980 t ,, .

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LER OR MALFUNCTION j g SYSTEM OR COMPONENT MR NO. - DATE OUTAGE CAUSE RESULT CORRECTIVE ACTION 2-CV-100-F M-79-2381 Seating surface was Excessive seat .blveplugwas

• Pressurizer Spray 11/1/79 badly cut. leakage. replaced an3 lapped I

I Valve .

. ., , t,o cage. . .

• - . 7,

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f! t 1 2 i 21 Charging Purp O-80-1116 Cyclic fatigue Excessive packing Replacedpackinh.

4/10/80 leakage. F -

21 Charging PuTp O-79-4825 * ,

Cyclic fat;igue.- Excessive packing Replace:1 packing, 1/8/80 ,  ; ,; .,l, fj' 't . '.,ii . -[g Mr i ~. *1eakage. i .

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, 22 Charging PuTp O-79-4705 Cyclic fatigue Excessive packing Replaced packings 9 12/20/79 1eakage.

22 Charging PuTp O-80-1038 Cyclic fatigue Excessive packing Replaced packing, 3/31/80 ' leakage.

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