ML19318C356

Monthly Operating Rept for May 1980

ML19318C356
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 8007010390
Download: ML19318C356 (8)

Text

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OPERATLNG DATA REPORT DOCKET NO. 50-317 DATE 6/12/80 COMPLETED BY tn % mn TELEPHONE 301-236-5240 OPERATING STATUS Notes

1. Unit Name: Calvere C1iffs No. 1

2. Reporting Period:

May, 1980

3. Licensed Thermal Power (MW ):

2,700 918

4. Nameplate Rating (Gross MWel:

845

5. Design Electrical Rating (Net MWe):

845

6. Maximum Dependable Capacity IGross MWe):

810

7. Maximum Dependable Capacity (Net MWe):

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):

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulative 744 3,647 44,412 II. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 636.1 3.083.0 35,522.6

13. Reactor Reserve Shutdown Hours 19.3 38.3 1,098.8

14. Hours Gecerator On Line 629.6 3.013.6 34,715.6

15. Unit Reserve Shutdown ilours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1,648,361 6,795,778 82,132,767

17. Gross Electrical Energy Generated (MWH) 526,927 2,148,392 26,960,922

18. Net Electrical Energy Generated (MWH) 502,342 2,034,231 25,683,437

19. Unit Service Factor 84.6 82.6 78.2

20. Unit Availability Factor 84.6 82.6 78.2

21. Unit Capacity Factor iUsing MDC Net) 83.4 68.9 71.4 79.9 66.0 68.4

22. Unit Capacity Factor tusing DER Net)

23. Unit Forced Outage Rate 15.4 6.0 8.8

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

oytare startine 10/17/80 until 12/15/80 No. 1 Plant scheduled for a olanned for refueling, unit general inspectn sa and TMI Modifications.

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

i

26. Units In Test Status (Prior to Commercial Operationi:

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 80070.Lu3%

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-31/

Calvert Cliffs #1 UNIT O

DATE COMPLETED BY C D "arnon TELEPHONE 301-234-5240 MONTH

",v.

10A0 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(Mwe. Net) 788 g

,7 2

13 831 3'

39 825 4

24 20 617 5

723 21 114 6

767 22 808 7

772 23 822 785 824 8

9 820 I91 25 10 830 819 26 789 021 11 27 12 822 823 28 798 823 13 29 830 823 14 30 15 827 820 3g 16 821 l

l l

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.

(9/771 1

~

50-3I7 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME calvert CIitfs #1 DATE 6/12/80 COMPLETED 3Y S.D.Merson REPORT MONT11 Mw ioso TELEPHONE 301-234-5240 l

% a5 5

c r,

No.

D.ite f_5

? 56 li'""5**

h*I Cause & Corrective

?i.3 g

g 3 oc Event i,13 Action to 3v v

QO

I! 5l Report er Prevent Recurrence

..j 6

L 80-08 800410 F

91.2 A

4 LER 80-24/3L CB PUMPXX Leak or,i #11B Reactor coolant pump control bleed-off line.

Plant was I

already off for outage (80-07).

i 80-09 800520 F

23.2 A

1 LER 80-27/1T llTETCII I.eak in the after-cooler on #12 instrument air compressor.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equiprnent Failure (Explain) 1-Manual for Preparation of Data j

8-Maintenance of Test 2-Manual Sesam.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File INUREG-D-Regulatory Restriction 4-Continuation 0161) i E-Operator Training & License Examination 5-1.oad reduction F Adnunistrative 9-Other S

G-Operational Error (Explain)

Exhibit I - Same Source j

(9/77)

Ifother (Explain) i

6/6/80

-REFUELING INFORMATION REQUEST 1.

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

Scheduled date for next Refueling Shutdown:

~0ctober 17, 1980 3.

Scheduled date for restart following refueling:

December 10, 1980 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendr.ient?

Resumption of operation after refueling will require changes to i

Technical Specifications. The changes will be such as to allow 1

operation of the plant with a fresh reload batch and reshuffled i

core.

4 5.

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 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, 1993

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - MAY 1980 5/1 At the beginning of this reporting period, Unit I was shutdown for repair of the Reactor Coolant System leak from 11B Reactor Coolant Pump control bleed off line.

5/3 Commenced Reactor Coolant System fill at 0250. At 1830, heatup of the Reactor Coolant System was begun.

5/4 The Reactor was brought critical at 1635 and the unit paralleled at 1910.

5/5 At 1020, load was limited to 765 MWe to investigate saltwater leakage into the main condenser.

5/8 After plugging 1 condenser tube load was increased to capacity (850 MWe) at 0030. At 1900 load was decreased to 805 MWe to investigate saltwater leakage into the main condenser.

5/9 Resumed full load operation (870 MWe) at 0945 after plugging one condenser tube.

5/11 Load was reduced to 710 FWe at 1445 to investigate saltwater leakage into the main condenser.

5/12 One condenser tube was plugged and load was increased to capacity (865 FWe) at 0300.

5/13 At 0900 decreased load to 78C FWe to investigate saltwater leakage into the main condenser.

. 5/17 At 1035 load was reduced to 750 MWe for Main Turbine Control Valve Testing.

Resumed full load operation (660 MWe) at 1435.

5/20 ' The unit was macually tripped at 1803 when the service water system became airboui:4. The cause was a leak in the after-cooler on No.12 Instrument Air Compressor.

5/21 The Reactor was brought critical at 1320 and the unit paralleled at 1714.

5/22 At 0500 full load operation (860 M'.le) was resumed.

5/25 Load was decreased to 760 MWe at 1500 to investigate saltwater leakage into the main condenser. At 2230, after indications of leakage disappeared, load was increased to 860 MWe.

5/31 At the end of this reporting period, Unit I was operating at B60 MWe with the Reactor at 100% power.

~~m l

SAFETY-RELATED MAINTENANCE UNIT ONE GROU?

I&C MONTH MAY YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-80-870 Defective isolation Test light would not Replaced the Features Actuation 3-17-80 nodule in sensor reset.

isolation module.

System / Channel 'AL' channel ZE.

Containment Recirculation Signal Reactor Protective System IC-80-045 Defective power supply Channel 'A' Wide Range Replaced the power Channel 'A' Wide Range 3-25-80 and pre-amplifier.

Nuclear Instrument supply and the Nuclear Indication would not calibrate.

preamp? ' fi er.

Reactor Protective IC-80-038 Defective Signal Containment Pressure Replaced the System / Channel 'D' 2-26-80 Isolator Instrument out of defective signal Containment Pressure 1-E/E-5313D tolerance.

isolator 1-E/E-53130 i

Engineered Safety 0-80-808 Dirty terminals 1-SU-6529 and 1-5U-6531 Cleaned the Features Actuation 3-11-80 on relay XK45 in the would not function.

terminals on the System /1-SU-6529 BR Relay Cabinet.

Relay XK45.

1-SU-6531-

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- b LER OR MALFUNCTION l

SYSTEM OR COMPONENT MR NO. - DATE OlffAGE CAUSE RESULT CORRECTIVE ACTION 1-ERV-402 M-80-3026 Pilot and niain valve Seat leakage.

Pilot valve disc whs replaced and' Pressurizer Relief 2/12/80 seating surfaces were l

Valve cut.

lapped in.

Main.

d,,isq was lapped in.

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-'l 1-ERV-404 O-79-4412 Pilot and main valve Excessive seat Pilot and maid v, alw Pressurizer Relief 2/12/80 seating surfaces were

leakage, discs were rsplaced

i Valve cut.

and lapped in.

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