ML19337A543

Monthly Operating Repts for Aug 1980

ML19337A543
Person / Time
Site:	Calvert Cliffs
Issue date:	09/15/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19337A542	List: ML19337A541 ML19337A543
References
NUDOCS 8009290248
Download: ML19337A543 (24)

Text

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OPERATING DATA REPORT DOCKET NO. 1.0-317 DATE 0/15/86 COMPLETED BY <_ n. varson TELEPHONE '01 714-5240 OPERATING STATUS caIvere C1iffs No. 1 O!'8

1. Unit Name:

August, 1980

2. Reporting Period:

3. Licensed Thermal Power (MWt): 2.700 1

4. Nameplate Rating (Gross MWe): 918 .

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5. Design Electrical Rating (Net MWe): 845

6. Maximum Dependable Capacity (Gross MWe): 865

7. Maximum Dependable Capacity (Net MWe): 810

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

9. Power Level To Which Restricted.If Any (Net MWe): ._ _

10. Reasons For Restrictions.If Any:

This Month Yr.-to.Date Cumulative

11. Hours in Reporting Period 744.0 5,855.0 46,620.0

12. Number Of Hours Reactor Was Critical 744.0 5,291.0 37,730.o

13. Reactor Reserve Shutdown Hours 0.0 38.3 1.098.3 j 14. Hours Generator On Line 744.0 5.221.6 36,923.6

15. Unit Reserve Shutdown llours 0.0 0.0 0.0

16. Gross Thermal Energy Generated IMWH) 1,900,363 12,448,112 87,785,101 .

17. Gross Electrical Energy Generated (MWHI 592.165__,_, 3.916.449 28,729.479

18. Net Electrical Energy Generated (MWHp 564.729 3,721,688 27,370,894

19. Unit Service Factor 100.0 89.2 79.2 l

20. Unit Availability Factor 100.0 89.2 79.2

21. Unit Capacity Factor (Using MDC Net) 93.7 78.5 72.5

22. Unit Capacity Factor IUsing DER Net) 89.8 75.2 09.5

23. Unit Forced Outage Rate 0.0 3.5 8.3

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

No. 1 Plant scheduled for a planned outage startina 10/17/80 until 12/15/80 for refuelinn, unit general insoection and DfI Modifications.

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

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8 009290 gqT> ,

L OPERATING DATA REPORT DOCKET NO. 50-718 DATE 0 /15 /80 COMPLETED BY A - n " arson TELEPHONE 201 714-5240 OPERATING STATUS Calvert Cliffs No. 2 Notes

1. Unit Name:

2. Reporting Period: August, 1980

3. Licenacd Ther cal Po act (MWel: 2 '00

4. Nameplate Rating (Gross MWe): 911

5. Design Electrical Rating (Net MWe): 845

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 Last Report. Gi+e Reasons:

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

10. Reasons For Restrictions.If Any:

This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 744.0 5.855.0 29,975.0

12. Number Of Hours Reactor Was Critical 728.5 5,000.3 25,545.2

13. Reactor Reserve Shutdown Hours 13.0 22.5 435.6

14. Hours Generator On-Line 723.9 5.560.9 25,178.4

15. Unit Resene Shutdown flour, 0.0 0.0 0.0

16. Gross Thermal Energy Generated iMWH) 1.809.208 14.189,344 62,433.576 .

17. Gross Electrical Energy Generated lMWHI 572,695 _ _ ,

4.680,455 20,685,678

18. Net Electrical Energy Generated (MWH) 545,860 4,473,044 19,730,064

19. Unit Senice Factor 97.3 95.1 84.0

20. Unit Availability Factor 07.3 95.1 84.0

21. Unit Capacity Factor (Using MDC Net) PR o 02.6 80.6

22. Unit Capacity FactorIUsing DER Net) 86.8 _

90.4 77.9

23. Unit Forced Outage Rate 2.7 1.0 5.7

24. Shutdowns Scheduled O$er Next 6 Months tType. Date,and Duration of Eacht:

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

26. Units in Test Status iPrior to Commercial Operationi: Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-317 UNIT Ca l_ve r t Cliffs #1 DATE 9/15/80 COMPLETED 8Y S. D. Merson TELEPHONE 301-234-5240 MONTH August, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe Net) l g 802 731 37 )

2 765 gg 759 3 733 gg 791 i 4 800 20 729 5 803 23 568 6 799 710 22 7 765 711 23 3 765 24 733 9 770 25 797 10 763 717 26 3g 782 775 27 g2 787 807 28 13 771 29 722 14 799 740 30 15 7'I 31 805 16 603 i

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)

AVER AGE DAILY UNIT POWER LEVEL DOCKET NO. 50-318 UNIT Calvert Cliffs #2 DATE 9/15/80 COMPLETED BY s . D. Merson TELEPHONE 301-234-5240 MONTH Aucuse. 1980 _

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 (Mwe Net) (Mwe.Ne:3 j 3

818 g7 423 2 787 1g 723 3 815 39 806 )

1 4 821 20 #99 l 5

819 745 I 21 6 814 22 804 7 821 23 428 g 810 300 24 9 822 779 25 10 802 26 823 II 810 27 806 32 491 703 28 13 556 $'

29 34 779 823 30 15 800 33 824 16 771 INSTRUC110NS 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)

DOCKET NO. 50-317 -

UNITSHUTDOWNS AND POWER REDUC 110NS UNITNAME calvert cliffs No. 1 DATE o ri s tan COMPLETED BY s . n_ w renn

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REPORT MONTH Arieers t . 1980 TELEPHONE 301-234-5240 "i -

.! E S .hIk Licensee ,E% f% Cause & Corrective No. Date [ 32 g jgy Event u7 Action to

$ 8. 5 jig Repost

• N0 [q' Prevent Recurrence d

No Outages or Reductions.

I 2 3 4

F: Forced Reason: Method: Exlubit G-Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheels for Lseensee C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-

- D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Exandnation F Adnunistrative 5 G-Operational Es ror (Explam) Exhibit I - Same Source 19/77) llother (Explain)

DOCKET NO. 50-M 8 UNITSHUTDOWNS AND POWER REDUC 110NS UNIT NAME Calvert Cliffs #2 DATE o/ts/an COMPLETED BY S. D. Merson REPORT MONTH Aueu s t . 1480 TELEPilONE 101-234-5240 "b- - ,

.! E 3 .h jgy Yk Licensee $g fg Cause & Corrective No. Date k 3 L= { Event E 12 D Action to

$8 5 jig 6

Report a N0 f Prevens Recurrence 80-04 800812 1 14.8 A 1 XX PtRIPXX Loss of No. 22 Circulating Water Pump.

80-05 800820 1 5.3 C 3 XX ZZZZZZ Reactor Tripped on Iligh Pressurizer Pressure When a Technician Inadvertent -

ly Initiated Steam Generator Isolatfori Signal.

I 2 3 4 F: Forced Rr,ason: Method:

S: Scheduled Exhibit G - Instructions A Equiprnent Failure (Explain) 1-Manual for Preparation of Data 84taintenance of Test 2-Manual Scram. Entry Sheets for Licensee C Rsfueling 3-Automatic Scram. Event ReporI (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F Adnunistrative 5 G-Operational Esror (Explain) Exhibit I Same Source (9/77) flother (Explain)

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9/10/80 i 1

l REFUELING INFORMATION REOUEST l

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

2. Scheduled date for next Refueling Shutdown: October 17, 1980

3. Scheduled date for restart following refueling: November 27, 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 witn a fresh reload batch and reshuffled l core. '

5. Scheduled date(s) for submitting proposed licensing' action and supporting information.

• l August 29, 1980

6. Important licensing considerations associated with the refueling.

i Reload fuel will he 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, l l

(a) 217 (b) 364 Spent Fuel Pools are common to Units 1 & 2 )

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8. The present licensec spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been reouested i or is planned, in number of fuel assemblies. I 1056 Licensed 728 Currently Installed 1 774 Licensed Addition is P' anned

9. The projected date of the last refueling that can be discharged to

, the Spent Fuel Pool assuming the present licensed capacity, October, 1983

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9/10/80 REFUELING INFORMATION REQUEST

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

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

3. Scheduled da e for restart following refueling: February 12: 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 baten and reshuffled core, i l

5. Scheduled date(s) for submitting proposed licensing action and l l supporting infomation.

November 14, 1980

6. Important licensing considerations associated with refueling.

Reload fuel will be similar to that reload fuel inserted in the

l. previous cycle.

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7. The number of fuel assemblies (a) in the core and (b) in the Spent Fuel Storage Pool.

(a) 217 (b) 364 Spent Fuel Pool are comon to Units 1 & 2 1

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has beer.

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 l

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SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - AUGUST 1980 8/1 At the beginning of this reporting period, Unit I was I

operating at 845 MWe with the reactor at 100% power.

8/2 Reduced load to 735 MWe to investigate saltwater leakage into the main condenser at 0145. After indications of saltwater leakage disappeared, load was increased to 830 MWe at 1230.

8/3 Decreased load to 710 MWe at 1530 to investigate saltwater leakage into the main conde,'ser. At 2130 after plugging two condenser tubes, load was increased to capacity (835MWe).

8/7 At 0025 load was reduced to 740 MWe to investigate salt-water leakage into the main condenser. At 1050 after indications of saltwater leakage disappeared, load was increased to 815 MWe, limited by high baywater temperature.

8/8 Load was reduced to 730 MWe at 0300 to investigate salt-water leakage into the main condenser. At 1345, after l plugging one condenser tube, load was increased to 835 MWe. l l

8/9 Decreased load to 765 MWe due to mechanical problems with  !

1. 11 Condensate Pump. At 1430 load was increased to capacity l

(835MWe). At 1745 load was reduced to 740 MWe to investigate i saltwcter leakage into the main condenser.

8/10 At 1130, after plugging one condenser tube, full load operation (835 MWe) was resumed.

8/11 Reduced load to 720 MWe at 2100 to investigate saltwater leakage into the main condenser.

.4d

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - AUGUST 1980 8/12 At 0415, after indicationsof saltwater leakage disappeared, load was increased to 830 MWe.

8/13 Reduced load to 715 MWe at 0320 to investigate saltwater leakage into the main condenser. After indicationsof salt-water leakage disappeared full load operation was rasumed (830 MWe) at 1055.

8/15 Decreased load to 740 MWe at 1110 to investigate saltwater leakage into the main condenser.

8/17 After plugging six condenser tubes began increasing power.

At 2300 started reducing load to 707 MWe to investigate saltwater leakage into the main condenser.

8/18 At 0800, increased load to capacity (830 MWe) after indications of saltwater leakage disappeared. At 0950 load was reduced to 820 MWe while conducting reactivity coefficient measurements.

8/19 Resumed full load operation (835 MWe) at 2000.

8/20 At 0100 reduced load to 735 MWe to investigate saltwater leakage into the main condenser.

8/21 Load was further reduced to 630 MWe due to the inability to monitor incore detectors because of computer problems.

Plugged two leaking condenser tubes.

8/22 Resumed full load operation (840 MWe) at 2330.

8/23 %duced load to 690 MWe at 0700 to do maintenance work on the intake traveling screens.

8/24 Started increasing load and at 0400 reduced load to 675 MWe to investigate saltwater leakage into the main condenser.

After plugging three condenser tubes, load was increased to capacity (835 MWe) at 2100.

SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - AUGUST 1980 8/26 At 0100 load was decreased to 710 MWe to investigate saltwater leakage into the main condenser. After indications of salt-water leakage disappeared, load was increased to capacity (840MWe)at1640. Decreased load to 740 MWe at 2100 to investigate saltwater leakage into the main condenser.

8/27 After indications of saltwater leakage disappeared, load was increased to 835 MWe at 0930.

8/29 Reduced load to 720 MWe to investigate saltwater leakage into the main condenser at 0115. Resumed full load operation (835 MWe) at 1100after indications of saltwater leakage disappeared. At 1400 load was reduced to 740 MWe to investigate saltwater leakage into the main condenser.

8/30 After plugging one condenser tube, full load operation (840 MWe) was resumed at 1730.

8/31 At the end of this reporting period, Unit I was operating at 840 MWe with the reactor at 100% power.

i 1

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - AUGUST 1980 8/1 At the beginning of this reporting period, Unit 2 was operating at 855 MWe with the reactor at 100% power.

8/2 At 0515 load was reduced to 790 MWe to investigate saltwater leakage into the main condenser.

8/3 After plugging one condenser tube, full load operation (860 MWe) was resumed at 0400.

8/5 Decreased lead to 830 MWe at 1200 to investigate saltwater leakage into the main condenser. After indicaticr.3 of salt-water leakage disappeared, increased load to capacity (860 MWe) at 1700.

8/6 Load was reduced to 810 MWe at 0045 to investigate saltwater leakage into the main condenser. Resumed full load operation (855 MWe) at 0715 after indications of saltwater leakage disappeared.

8/8 Reduced load to 825 MWe at 0700 to investigate saltwater leakage into the main condenser. At 1700, after plugging one condenser tube, load was increased to capacity (850 MWe).

8/10 At 1355 reduced load to 760 MWe to investigate saltwater leakage into the main condenser. Resumed full load operation (860MWe)at'.000afterpluggingonecondensertube.

8/11 Reduced load to 780 MWe at 0225 to investigata saltwat u leakage into the main condenser. At 0635 full load operation (860) was resumed after indications of saltwater leakage disappeared.

8/12 At 0120 load was reduced to 815 MWe to investigate saltwater leakage into the main condenser. At 1500 the main turbine was manually tripped due to the loss of #22 Main Circulating

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SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - AUGUST 1980 '

Water Pump when its excitation cabine: was sprayed with water.

The Reactor tripped on loss of load.

8/13 The reactor was brought critical at 0400 and the unit paralleled at 0550. Load was increased to capacity (850 MWe) at 1125. l At 2300 load was reduced to 770 HWe to investigate saltwater l

leakage into the main condenser.

8/14 Resumed full load operation (850 MWe) at 0900 after indications of saltwater leakage disappeared. Decreased load to 790 MWe at 1935 to investigate saltwater leakage into the main condenser.

8/15 Increased load to capacity (850 MWe) at 0800 after plugging one leaking condenser tube. At 2200 load was reduced to 800 MWe to repair #23 Main Circulating Water Pump.

8/16 Began increasing load and at 0445 load was reduced to 800 MWe to investigate saltwater leakage into the main condenser.

8/17 Load was further reduced to 420 MWe at 0500 for fuel conservation.

Plugged two leaking condenser tubes.

8/18 Resumed full load operation (860 MWe) at 2200.

8/19 Reduced load to 795 MWe at 1800 to investigate saltwater j l

leakage into the main condenser.

8/20 At 0900, the Reactor tripped on high pressurizer pressure when a technician inadvertently initiated a Steam Generator Isolation Signal while perfonning the monthly ESFAS test.

The reactor was brought critical at 1130 and the unit paralleled at 1419. Load was limited to 770 MWe at 2100 to investigate saltwater leakage into the main condenser.

8/22 At 0800, full load operation (850 MWe) was resumed after plugging one condenser tube.

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - AUGUST 1980 8/23 Reduced load to 420 MWe at 0600 for fuel conservation.

8/25 At 0801, load was increased to capacity (855 MWe).

8/27 Load was decreased to 790 MWe at 1130 to investigate salt-water leakage into the main condenser. After indications of saltwater leakage disappeared load was increased to capacity (865 MWe) at 1800.

8/28 At 0100 reduced load to 820 MWe to investigate saltwater leakage into the main condenser. Resumed full load operation (860 MWe) at 2300 when indications of saltwater leakage disappeared. 1 8/29 Load was decreased to 770 MWe at 0115 to investigate salt- ,

1 water leakage into the main condenser. Increased load to capacity (860 MWe) at 2100 when indications of saltwater l

l leakage disappeared. '

8/31 At the end of this reporting period, Unit 2 was operating at 860 MWe with the reactor at 100% power.

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SAFETY-RELATED MAltlTEtlANCE UtlIT one GROUP 'E' SHOP MONTil AUGUST YEAR 1980 MALFUNCTI0ft SYSTEM OR COMPO!!ENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

!!Igh pressure Tiafety 1-79-1729 Defective limit switch Damaged valve operator Rebuilt the valve Injection Systen/1-m V- t. 21-79 and prevented the valve operator, replaced .

616 from shutting properly and adjusted limit switches, prefomed functional tests W

SAFETY-RELATED MAlflTErlANCE U! LIT Two GROUP I&C MONTH AUGUST YEAR 1980 MALFUNCTION SYSTEM OR COMPONLn. MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Service Water 0-80-100h Position switch for open Remote Tndication for Ad. justed The Positio-1 Systern/ Turbine Eldg. 3-27-80 Indication was out of 2-CV-1639 vould not Switch Supply Valve adjustment Indicate open when the 2-CV-1639 valve was full open Service Water 0-80-30h0 Position Switch for Remote indication for Adjasted the positio 2 System /2-CV-1590 8-12-80 open Indication was out 2-cV-1590 would not switch of adjustment indicate full open  ;

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SAFETY-RELATED MAltlTEtlANCE UtlIT Two GROUP I&C

. MONTH AUGUST YEAR 1o80 MALFUNCTION SYSTEM OR COMP 0tlENT MR N0. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 21 Service Water /IIend 0-80-1601 Transmitter 2-LT-157o Received Low Level Alam Perfomed calibration Tank Level Indication 5-9 80 was out of calibration beford make up would and functional test 2-LT-1579 start

1. 21 Service Water 0-80-1884 2-TI-1576 was out of Remote and Local Temper- Performed calibration lleat exchange outlet 5-28-80 calibration atures did not agree and functional test tercperature 2-TI-1576

SAFETY-RELATED MAINTEllAtlCE

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Ut11T TWO GROUP T&C M0flTil AUGUST YEAR 1980 t1ALFUNCTI0t1 l SYSTEM OR COMPONENT Pa NO. - DATE CAUSE RESULT CORRECTIVE ACTION Vital Switchgear 0-80-3029 2-TS-Sh38 was out of Temperature Indication Calibration 2-TS-Sh38 Room Temperature 8-11-80 calibration was higher than the and Perfomed Indication 2-TS-Sh38 Actual Room Temnerature functional test

'#22 Switchgear Air 10-80-2033 2-TC-Sh27A was out of The Air Conditioning Calibration 2-TC-Sh27 Conditioner / Temperature 3-31 80 calibration compressor would not A and perfomed Controller shut down at the c6rrect functional test 2-TC-Sh27A temperatures

SAFETY-RELATED MAINTENANCE UNIT Two GROUP I&C MONTil AUGUST YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 21&22 Service water 0-80-1040 Pressure Transmitters Local and remote pressure Ad.1usted zero and -

Heat exchanger Salt h-1-80 2-PP-5203 indications did not performed functional Water inlet pressure 2-PT-520h were out of agree test on 2-PT-5203 Transmitter calibration 2-PP-520h 2-PT-5203 .

2-PP-520h

1. 21 Salt Unter 0-80-1093 The position switch for 2-CV-51h9 Remote pocition Cleaned and adjusted Hender Emergency h-3-80 the closed position indication did not the close position discharge valve indication was out of indicate when the valve switch for 2-CV-5149 2-CV-5149 adjustment was shut

SAFETY-RELATED MAINTENAtlCE UNIT TWO GROUP I&C

, MONTil AUGUST YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 22 ttain Steam 0-80-2837 Defective Sump level Incorrect Sump Level Replaced Isolation valve 7-28-80 Instrument Indication

' 2-LT-0670

!!vdraulic Pa^ age /

Level Indicator 2-LT-96TO .

Reactor Protective 0-78-396h Defective Resistance Temperature Indication Replaced System / Temperature 9-18-70 Temperature Detector oscillating 2-TE-122-IIC Detector 2-TE-122-IIC 2-TE-122-IIC

_ - - - - - - - - - - _ - - - - - - - --- __-----u _- ---

SAFETY-RELATED MAltlTENANCE UtlIT TWO GROUP I&C M04Til AUGUST YEAR 1980 MALFUNCTI0ft SYSTEtt OR COMP 0tlENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTI0ft Reactor coolant' system 0-80-1845 Dirty loop Resistor Excessive Deviation Cleaned the Loop control Panel / Channel 5-28-80 Lugs and slide links on between channel 'A' and Resistor and slide

'C' Pressurizer 2-PI-102C 'C' Indications links Pressure Indication 2-PI-102C .

Condensate and feed- 0-80-1736 Pressure Indication Excessive Deviation Performed calibration water control Panel / 5-27-80 Instruments 2-PI-1023A between channel A,B,C check and functional Steam Generator 2-PI-1023B Indications check on 2-PI-1023A Pressure Indication 2 PI-1023C 2-PI-1023B 2-PT-1023C

SAFETY-RELATED MAltlTEllatlCE UNIT ONE GROUP I&C MONTil AUGUST YEAR 1980

' MALFUNCTION SYSTEli OR COMP 0? LENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Salt water system / 0-80-2964 Broken flexure wire in Pressure indication was Replaced flexure pressure Transmitter 8-7-80 the Transmitter failed low vire in transmitter 1-PT-5203 1 "T-5203 1-PT-5203 Reactor Protective IC-80-72 Defective trip test Intermittant loss of Replaced the trip system / channel 'C' trip T-lh-80 cable signal when test cable test cable test cable was plugged in.

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SAFETY-RELATED MAltlTENANCE U.' LIT ONE GROUP I&C

. MONTil J.UGUST YEAR 1o80 MALFUNCTI0tl SYSTEM OR COMP 0flENT MR NO. - DATE CAUSE RESUL F CORRECTIVE ACTION Refueling water tank 0-80-1500 Defective 2h VDC Power Refueling water tank Replaced the 2h VDC level indication signal 5-2-80 Supply for signal narroy range level Power Isolator Power Cupply Isolator Instrument indication was pegged low 1-LY b1h2 1-T.Y b1h2 Wide Range 0-80-lhT9 Defective Bistable Board Iligh start up rste functioGeplaced the bistable Ex-core Iluclear h-30-80 A-9 not getting trip or Pre- Board A-9 Instrument / Channel 'B' trip signal start up rate

SAFETY-RELATED MAINTENANCE UNIT ONE GROUP IE

, MONTH AucusT YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Engineered Safety 0-80-208T Defective Channel B Containment Isolation Replaced the Features Actuation 8-15-80 Isolation Module in Signal Channel B Actuation defective Isolation System / Channel ZD containment Isolation during surveillance afodule Sensor Cabinet signal path. Testing of Channel A

1. 12 Containment 0-80-1589 Slight zero shift on Discharge pressure'vas Recalibrated the

. Spray Pump Discharge 5-7-80 1-PT k147 (Lov) not Indicating correctly pressure Transmitter pressure Transmitter during surveillance test. 1-PT kih7 1-PT-hih7

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_ . _ . _ _ _ . _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ ___