ML19336A500

Monthly Operating Repts for Sept 1980

ML19336A500
Person / Time
Site:	Calvert Cliffs
Issue date:	10/15/1980
From:	Merson S BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML19336A499	List: ML19336A498 ML19336A500
References
NUDOCS 8010230438
Download: ML19336A500 (21)

Text

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1 OPERATING DATA REPORT DOCKET NO. 50_317 DATE 10/15/80 COMPLETED BY S.

D. Merson TELEPHONE in1_'n 4_ s 240 OPERATING STATL'S

1. Unit Name:

Calvert cifffs No. 1 Notes

2. Reporting Period:

September, 1980

3. Licensed Thermal Pow:r (MW:):

2,700 918

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

845 845

6. Maximum Dependable Capacity (Gross MWe):

810 f

7. Masimum Depenoable Capacity (Net MWe):

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

f

9. Power I.evel To Which Restricted.lf Any (Net MWe):

10. Reasons For Restrictions. lf Any:

No. 1 Plsnt is in the crocess of eradually coasting down for its refueline outage on October 17, 1980.

This Month Yr..to.Date Cumulative

11. Hours in Reporting Period 720.0 6,575.0 47,340

12. Number Of Hours Reactor Was Critical 720.0 6,011.0 38.450.6

13. Reacter Reserve Shutdown Hours 0.0 38.3 1,098.8

14. Hours Generator On Line 720.0 5,941.6 37,643.6

15. Unit Reserve Shutdown flours 0.0 0.0 o,o

16. Crcss Thermal Energy Generated iMWH) 1,858,080 14.306.192 89.643.181

17. Gross Electrical Energy Generated (MWH) 576,267 4,493,216 29.05,746 4

18. Net Electrical Energy Generated IMWH) 549,582_

4,271,270 27,92J.476

19. Unit Service Factor 100.0 90.4 79.5

20. Unit Availability Factor 100.0 90.4 79.5

21. Unit Capacity Factor iU ing MDC Net.

94.2 80.2 72.8

22. Unit Capacity FactorIUsing DER Net) 90.3 76.9 69.8

23. Unit Forced Outage Rate 0.0 3.1 8.1

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

No. 1. Plant acheduled for a planned outage starting 10/17/80 until 12/15/80 for refueline. unit cencral insrection and NT -ndiffe,rinna.

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

26. Units in Test StatusiPrior o Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 8010230 %

(9/77)

{

OPERATING DATA REPORT DOCKET NO. W118 DATE 1m/t9/9n l

COMPLETED BY e n u-son TELEPHONE int _ m '240 s

l OPERATING STATUS

1. Unit Name: Ca1 vere C1iffs No. 2 Notes

2. Reporting Period:

Seetember. 1480 7

3. Licensed Thermal Power (MWt):

2,700

4. Nameplate Rating (Gross MWe):

o11

5. Design Electrical Rating (Net MWe):

845 360

6. Maximum Dependable Capacity (Gross MWel:

825

7. Maximum Dependable Capacity (Net MWe):

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

9. Power Level To Which Restricted.lf Ar.y (Net MWe):

? Plane it dennnine en Inu Inada nn the weekend

10. Reasons For Restrictions !f Any:

period to conserve fuel until its refuelinc outage in January, 1981.

This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 720.0 6.575.0 30.645 i

12. Number Of Hours Reactor Was Critical 671.8 6,272.1 26,217.0

• 8 0.0 22.5 435.6

13. Reactor Reserve shutdown' Hours

14. Hours Generator On.Line 658.5 6,228.4 25,836.9

15. Unit Reserve Shutdown ilours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 1.530.384 15.719.733 63.963.965

17. Gross Electrical Energy Generated (MWH) 484,132 4,931,836 20,188,856 _

5,164,587 21,169,810

18. Net Electrical Energy Generated (MWH) 458,792

19. Unit Service Factor 91.5 94.7 84.2

20. Unit Availability Factor 91.5 94.7 84.2

21. Unit Capacity Factor (Using MDC Nett 77.2 90.9 79.7

)

22. Unit Capacity Factor IUsing DER Net) 75.4 88.8 80.5

23. Unit Forced Outage Rate 4.0 1.4 5.7

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

7 1

No. 2 Plant scheduled for a planned' outage startina January 2, 1981 until

" arch 2, 1981, for refueling, unit general insoection and TMI modification-

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

26. Units In Test Status Prior o Commercial Operationi:

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 4

(4/77)

l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-317 I

UNIT Calvert Cliffs #1 10/15/80 DATE COMPLETED 8Y S. D. Merson 301-234-5240 TELEPHONE MONTH September DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POhER, LEVEL (MWe-Net) iMWe-Net) l 770 706-g g7 2

803 33 723 3

802 39 676 4

802 20 734 5

775 21 786 6

773 806 22 7

76 23 805 8

803 34 799 9

804 25 7YU 10 703 803 26 11 757 27 681 12 803 658 1

2g i

13 804 29 663 e

i 14 785 30 673 l

15 805 3g l

16 807 l

l LNSLCCTIONS Or 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.

l l

(9/77) l r

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AVER AGE DAILY UNIT POWER LEVEL l

DOCKET NO.

50-318 Calvert Cliffs #2 WIT DATE 10/15/80 S. D. Merson COMPLETED BY

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TELEPHONE MONTH seotember DAY AVERAGE )AILY POWER LEVEL DAY AVERAGE DAILY POhER LEVEL (MWe Net)

(MWe-Net) 766 819 g

g7 2

785 gg 774 l

3 816 19 810 819 4

20 408 5

784 23 392 730 6

22 7

400 23 821 8

772 24 820 9

787 25 A11 10 821 26 816 800 33 27 418 12 28 1A1 13 168 29 758 l

14 61 30 796 l

15 308 33 811 16 l

l l

INSTRUCTIONS On this format. fist the average daily unit power levelin MWe Net for each day in the reporting tranth. Compute to the nearest whole megawatt.

(9/77)

DOCKETNO. 50 ~I17 UNITSHUTDOWNS AND POWER REDUCTIONS Calvert Cliffs No. 1 UNIT NAME DATE 10/15780 COMPLETED BY S.

D. tierson REPORT MONTil Sentember TELEPHONE 301-234-5240 w

c

.IE 3

fY3 Licensee Ev, K

Cause & Corrective j

No.

Date k

32 F;

2s&

Event g

g{

Action to y@

F j ;y, g Report a mo Prevent Recurrence r;

6 No outages or reductions.

I 2

3 4

F: Forced Reun:

Method:

Exhibit G. Inst ructions S: Scheduled A-Equiprnent Fa; lure (Explain) 1-Manual for PreparaQn of Data B Maintenance oiTest 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3 Autunutic Scram.

Event Report tLERI File INUREG.

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

E-Operator Training & Ucense Emananation F Adnunistrative 5

G-Operat.onal Error (Explaint Exhibit I - Sanw Source 19f77) llOher iExplain)

i DOCKETNO. 50-318 UNITSHUTDOWNS AND POWER REDUCTIONS UNITNAME calvert clif f s #2 DATE 10/15/80 m u m n s. n. % son REPORT MONTH Sentember TE1.EPHONE 301-234 ',240 n.

.$ 3 3

Y Licensee Ev, Cause & Corrective No.

DJtC 5y 4

2 5

Event

r. Y c'8 Action to g3 E 5

jgg Repo, sr 40 F

Prevens Recurrence t5 80-06 800907 S

24.0 11 XX ZZZZZZ Fuel conservation, capacity available on demand.

80-07 800912 S

34.0 B

1 XX llanger Planned snubber inspection.

80-08 800914 F

27.5 11 1

XX ZZZZZZ To comply with technical specifica-tions to repair erratic level trans-mitter.

80-09 800920 S

65.0 11 XX ZZZZZZ Fuel conservation, c.pacity available on demand.

80-10 800927 S

50.0 11 XX ZZZZZZ Fuel conservation, capacity available on demand.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A Equiprnent Failure (Emplain) 1 Manuel for Preparation of Data B-Maintenance ci Test 2-Manual Scrarn.

Entry Sheets for b.ensee C Refueling 3-Autondic Scram.

Event Repore (LER) File (NUREG-D-Regulatory Restriction 4-Other (Explain) 0161) li-Operator Training & Ucense Exandnation F Adnunistrative 5

G-Operational Eirus (Explain)

Exhibit 1 Sanw Source (9/77)

Il4)ther (Explain)

m-10/15/eo REFUELING INFORMATION REQUEST 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: Noyember 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 with a fresh reload batch and reshuffled Core.

5.

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

August 29, 198o November 4, 1980 (Supplemental Submittal) 1 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 (L1 in the spent fuel storage pool.

(a) 217 (b) 364 1

Spent Fuel Pools are common to Units 1 & 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.

lass Licensed 1028 Currently Installed 472 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, 1985 G

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20/15/eo REFUELING INFORMATION REQUEST 1.

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

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2.

Scheduled date for next refueling shutdown:

January 1, 1981 3.

Scheduled date for restart following refueling: February 12, 1981 4

Will refueling or resumption of operation thereafter require a technical specification change or other licensed amendment 7 Resumption of operation after refueling will require changes to i

Technical Specifications. The changes will be such as to allow operation of the plant with a fresh reload batch and reshuffled core.

i 5.

Scheduled date(s) for submitting preposed licensing action and supporting information.

November 14, 1980 6.

Important licensing considerations associated with refueling.

1 Reload fuel will be similar to that reload fuel inserted in the previous cycle, j

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 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.

I 1358 Licensed 1028 Currently Installed i

472 Licensed Addition is Planned 9.

The projected date of the last refueling that can be discharged to the Spent F' al Pool assuming the present licensed capacity.

October, ISd5 e

SUMMARY

OF UNIT I OPERATING EXPERIENCE - SEPTEMBER 1980 9/1 At the beginning of this reporting period Unit I was operating at 840 MWe with the Reactor at 100% power. At 1600 load was reduced to 740 MWe to investigate saltwater leakage into the main condenser.

9/2 Increased load to capacity 830 MWe at 0150 after plugging I condenser tube.

9/5 At 0100 load was reduced to 740 MWe to investigate saltwater leakage into the main condenser. Load was increased to 840 MWe at 0800 when indications of saltwater leakage disappeared.

9/6 At 1700 load was reduced to 720 MWe to investigate saltwater leakage into the main condenser. Load was increased to 840 MWe at 2330 when indications of saltwater leakage disappeared.

9/10 At 0330 load was reduced to 725 MWe to investigate saltwater leakage into the main condener.

9/11 After plugging 2 condenser tubes resumed full load operation (840 MWe) at 2200.

9/14 At 1900 load was reduced to 735 MWe to investigate saltwater leakage into the raain condenser.

9/15 Load was increased to 840 MWe at 0145 when indications of.

saltwater leakage disappeared.

9/17 At 0300. load was reduced to 720 MWe to investigate saltwater leakage into the main condenser.

9/13

. Increased load *o capacity (845 MWe) at 0430 after plugging I condenser tube.

At 1100 load was reduced to 720 MWe to investigate saltwater leakage into the main condenser. Plugged 2 leaking condenser tubes.

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SUMMARY

OF UNIT 1 OPERATING EXPERIENCE - SEPTEMBER 1980 l

l 9/20 Load was increased to 820 MWe at 1425 for power coefficient measurements.

9/21 Resumed full load operation (840 MWe) at 2200.

9/27 At 0430 load was reduced to 700 MWe to investigate saltwater leakage into the main condenser. Load reduction continued for j,

end of cycle coastdown.

9/30 Load was increased to 740 MWe at 2230. Located and plugged I leaking condenser tube. At the end of this reporting period Unit I was operating at 740 MWe with the reactor at 90% power, l

limited by end of cycle coastdown.

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SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - SEPTEMBER 1980 9/1 At the beginning of this reporting period, Unit 2 was operating at 360 MWe with the Reactor at 100% power. At 1300 load was reduced to 785 MWe to investigate saltwater leakage into the main condenser. At 1504 Control Element Assembly (CEA) 34 dropped into the core. Reactor power was immediately reduced to less than 70% in accordance with the Technical Specifi-cations. CEA 34 was withdrawn back to its group at 1610. Full load operation (860 MWe) was resumed at 2400.

9/2 Decreased load to 750 MWe at 0545, due to approaching Axial Shape Index limits as a result of the dropped CEA.

9/3 Resumed full load operation (850 MWe) at 0001.

9/5 At 1230 load was reduced to 780 MWe to investigate saltwater leakage into the main condenser. Plugged one leaking condenser tube.

9/6 At 0100 load was decreased to 695 MWe for Fuel Conservation.

9/7 Load was further reduced to 415 MWe to conserve fuel.

9/8 Load was increased to capacity (860 MWe) at 0700.

9/9 At 0700 load was reduced to 780 MWe to investigate saltwater leakage into the main condenser. Load was increased to 855 MWe at 1900 when indications of saltwater leakage disappeared.

9/11 Started decreasing load at 2130 for planned snubber inspection outage.

9/12 The unit was taken off the line at 0105.

The Reactor was shutdown at 0120.

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SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - SEPTEMBER 1980 9/13 The Reactor was brought critical at 0753 and the unit paralleled at 1108. At 1430 load was limited to 410 MWe to conserve fuel.

9/14 At 0255 started decreasing load due to erratic level indication on 22B Safety injection Tank. The unit was taken off the line at 0639. The Reactor was shutdown at 1320.

9/15 The Reactor was brought critical at 0700 and the unit paralleled at 1007. At 1717 Control Element Assembly (CEA) 9 dropped into the core. Reactor power was immediately reduced to less than 70% in accordance with the Technical Specifications. CEA 9 was withdrawn back to its group at 1759.

9/16 Load svas increased to capacity (855 MWe) at 0230. At 2230 load I

'was reduced to 800 MWe to investigate saltwater leakage into

.' The main condenser.

9/17 Load was increased to 865 MWe at 0300 when indications of saltwater leakage disappeared.

4 9/13 At 1100 load was reduced to 780 MWe to investigate saltwater leakage into the main condenser.

9/19 Load was increased to 860 MWE at 0100 when indications of saltwater leakage disappeared.

9/20 At 0500 load was decreased to 420 MWe to conserve fuel.

9/22 Started increasing load and at 0500 load was limited to 790 MWe to investigate saltwater leakage into the main condenser. Load was increased to 350 MWe at 2200 when indications of saltwater leakag-disappeared.

9/27 At 0500 load was decreased to 410 MWe to conserve fuel.

9/28 Resumed full load operation (855 MWe) at 0700.

SUMMARY

OF UNIT 2 OPERATING EXPERIENCE - SEPTEMBER 1980 9/30 At 0045 load was reducedd to 756 MWe to investigate saltwater leakage into the main condenser. Load was increased to 860 MWe at 0900 when indications of saltwater leakage dis-appeared. At the end of this reporting period Unit 2 was oper-ating at 360 MWe with the Reactor at 100% power.

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s SAFETY-RELATED MAINTENANCE UNIT orm i

GROUP Isc MONTH sentenber YEAR 1980 1

MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Sub-Cooled Margin IC-80-0067 Defective 1-AE-12 When ground was Replaced the Monitor /1-AE-12 6/27/80 Calculator Module connected on 1-AE-12, 1-AE-12 calculator I

Indication dropped Module below expected value '

i Switdigear Roam 0-80-3365 1-IS-5438 and Doth instnrnents were Perfonned adjust-l Ambient Tmperature 9/3/80 1-TS-5439 were out giving alarms with no ments and Indicaticus of calibration alann cmdition functicnal tests 1 'IS-5438 present 1-IS-5439 4

l i

SAFETY-RELATED MAINTENANCE UNIT

'luo GROUP I&C MONTil Septaber YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Hnactor Protective IC-60-2075 Pointer on the Instrtrnent Indication Ibaligned the Systxxn/ Axial Flux Tilt 8/18/80 Indicatim Instrtrocnt was incorrect.

Pointer and Negative Limit was out of adjustment.

performed functimal Indication 2-JI-013 test on 2,II-013.

1. 22 Steau Generator IC-80-2076 Defective 2-CV-4512 lbplaced Auxiliary Fee &ater 8-20-80 Itsrote Controller Failed open 2-IIIC-4510 Valve 2-CV-4512 2-IIIC-4510 Adjusted valve Itsnote Controller positim switches.

2-IIIC-4510 Valve tested satisfactory.

2-CV-5210 0-80-3258 Buildup of paint cn Itirote valve positim cleaned paint fran

1. 21 Service 8-25-80 valvo positim switch.

indication would not the positim swit&

Water lleat Exchanger indicate when the valve and adjusted to Salt Water Outlet Valve was fully shut.

give proper position indication.

Turbine Bttilding 0-80-3124 Defective Internal Invel Switd) would not Heplaced the Condensate Pit 8/18/80 Switch. Pechanism actuate nynote alarm.

Internal Switch and Iligh Icvel Switd1 spring was also spring.

2-IS-4414 missing.

SAFETY-RELATED MAINTENANCE UNIT wo GROUP _

I&C MONTH September YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION 1

Engineered Safety IC-80-2079 Defective Signal Discovered during Replaced the Features Actuation 8/21/80 Isolator testing that the trip defective signal Systesm/ Containment 2-E/E-5313D signal would not actuate isolator Pressure, Safety at the proper setting.

2-E/E-5313D l

Injection Actuation Sicysal Isolator 2-E/E-5313D i

+

i Reactx>r Protective 0-80-3333 Out of adjustment Deviation between Perfcamed adjust-System /422 8/28/80 Channel 'D' ments and fa ctional l

Steam cenerator Indicatim md the other test i

Pressure Indication three diannels were out Channel 'D' of spec.

t 2-PI-1023D m actor Protective IC-80-2069 Trip Uhit #5 During surveillance Adjusted trip Unit SystmWSteam 7/24/80 Setpoints were out of testing it was

1. 5 Setpoints Generator Pressure adjustment discovered that the Oiannel "B" trip and pre-trip setpoints for Steam Generator pressure were our of spec. Iow 3

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SAFETY-RELATED MAINTENANCE UNIT

'IND GROUP I&C MONTil Septaber YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION Ibactor Protective 0-80-2854 Indicating Instrumnts Deviation between Calibrated Systm/ Pressurizer 7/28/80 2-PI-102C and Qianpel C & D 2-PI-102C Pressure Indicaticn 2-PI-102D were out of Indication was out of 2-PI-102D 2-PI-102C adjustment spec.

2-PI-102D Ibactor Protectiw IC-80-2067

'Itriperature Ibadings were out of Made adjust 2nents SystutVOtannel C 7/23/80 Transmitter spec. Low during and performed 21 Ilot Ing Tmperature 2-TP-ll2IIC was out surveillance test functicnal test on Transmitter of adjustnent 2 4'r-ll211C 2-TT.-11211C Ibactor Protective IC-80-2065 Plow signal Signal was out of spec.

Calibrated the Systm/#21A 7/22/80 instrunent 2-PDY-lllC while performirrJ instrument and Peactor Coolant was out of surveillance test perforTred loop Flow Signal calibration functicnal test Instrutent 2-PDY-lllC Ibactor Protective IC-80-2068 Trip Unit #6 was out During surveillance Adjusted the SysterrVPressurizer 7/24/80 of adjustment test, discovered setpoint on the Pressure Trip pre-trip setpoint was trip unit and Unit #6 out of spec. high ampleted surveillance test satisfactorily l

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1 SAF TY-RELATED MAINTENiiNCE UNIT CNE GROUP IxacrRIC SIIOP MONTil Septenber YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 11 125 Volt DC 0-80-3364 Defectim light bulb Positive ground on #11 Iteplaced the Bus 9/4/80 in handswitch positim 125 3DC Bus Defective light Indicaticn light on bulb panel 1C24 DC Control Panel

1. 11 Diesel Generator 0-80-2753 Water in regulator No voltage control on Dried cabinet, Voltage Regulator 7/23/80 cabinet. Resulted in diesel generator sealed cmduit failure of T-2 trans-penetrations, former in the voltage replaced the T-2 regulator and failure transformer and of CF-3 cmtrol relay CF-3 relay

1. 11 Main Stean 0-80-3275 Defective Solenoid The FEIV Ilydraulic Replaced 1-SV-9626 Isolation Valm 8/26/80 Valve on Ifigh Pressure Package #2 Iligh Ilydraulic Package /

Panp Unloader Valw Pressure Punp would IIigh Pressure Panp 1-SV-9626 not start Unloader Valve 1-SV-9626

1. 14 Containment 0-80-2541 Dirty 42-11 relay in Containment Cooler Cleaned Relay Cooler Fan 7/2/80 starting circuit would not shut down 42-11 and perforned j

operational test

SAFETY-RELATED MAINTENANCE UNIT ONE GROUP EWCTRIC SilOP MONTil September YEAR 1980 i

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

1. 13 Charging Punp 0-80-2524 IIand switch was IIand switch was very Cleaned and tested Runote Iland Switch 7/2/80 dirty difficult to gerate hand switd1

1. 11 Diesel Generator 0-80-2493 Defective Alann Iboeived Diesel Replaced the alarm Alarm Panel 6/30/80 Module Generator crankcase module pressure alarm when no alarm conditica existed

1. 11 Diesel Generator 0-80-2719 Defective Relay Received Diesel Replaced Control Control Power Iblay 7/17/80 CF-1 Generator alarm Power Relay CF-1 CF-1 Indicaticn in Control Iban when no alarm ccmdition existed

. #12 Charging Pmp 0-80-2682 Breaker Spring Closing Spring Cleaned, Itbricated Motor Circuit 7/15/80 Garging Assenbly marging motor would and tested the Breaker 52-1415 was binding not shut off Spring Garging Assably

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SAFETY-RELATED MAINTENANCE UNIT TWO GROUP EIECTRIC SIDP MONTil septa ber YEAR 1980 MALFUNCTION SYSTEM OR COMPONENT MR NO. - DATE CAUSE RESULT CORRECTIVE ACTION

1. 21 125 VDC 0-80-2925 Defective Breaker Negative ground on the Replaced the Instrunent Bus 8/1/80 position Indication 125 VDC Bus defective light light socket socket

1. 21 Charging Ptunp 0-80-3227 Defective closing the Breaker would not Replaced the Breaker /52-2115 8/21/80 coil cn the 480/VAC operate defective closing Breaker 52-2115 coil

1. 21 Instrunent Air 0-80-3310 circuit Breaker

'Ihe Instrunent Air Lubricated the Crvrpressor Breaker /

8/26/80 52-2118 not operating Canpressor would not Circuit Breaker 52-2118 properly start and cleaned the control circuit limit switches 521 125 VDC 0-80-2799 Water in Junction Box Ground on #21 DC Bus Drained the water Instrunent Bus 7/25/80.

on U-25000-12 frm the junction transformer box

1. 21 125 VDC 0-80-2745 Ground in alarm module Ground on 121 125 VDC Replaced the alarm Instrunent Bus 7/22/80 for #11 Diesel Instrument Bas module Generator local Annunciator Panel

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SAFETY-RELATED MAINTENANCE UNIT I

e GROUP Machine Shop PMD g l1986 7

MONTH September YEAR 8 LER OR MALFUNCTION SYSTEM OR COMPONENT

.MR NO. - DATE OUTAGE CAUSE RESULT CORHECTIVE ACTION Number 12 Charging 0-80-2936 Cyclic fatigue Excessive packing Ryplaced packing.

Pump 8/11/80 leakage.

-Number.12 Charging 0-8d-3032 Cyclic' fatigue' Excessive packing Rfp)facedpacking.

Pump 8/14/80 leakage.

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Replacedpacj[!on Number 12 Charging M-80-188 Defective lube Excessive packing ng Pump 8/25/80 ring.~

Icakage on one and lube ring plunger only.

intermediate plunger only.

I-CV-1588-Service 0-80-2128 Defective fa'1ve Excessive seat Rdplaced valve water inlet to 12 6/30/80 seat. p,'..,,.

4 leakage.

seat.,,

Diesel Generator Number 11 Chargihg M-80-184 Cyclic fatigue Excessi'e pump Replacejvalves.

v Pump 8/11/80

^

suction and dis-charge valve u.

leakage.

Number 12 Charging M-80-187 Cyclic fatigue Excessive pump Replaced valves.

Pump 8/25/80 suction and dis-charge valve

leakage, Number 12 Charging 0-80-2968 Cyclic fatigue Pump desurger1 Replaced desurger Pump 8/11/80 would not hold bladder.

a nitrogen charge.

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SAFETY-RELATED MAINTENANCE a

UNIT I

6 CROUP Machine Shop PMD g ;

y MONTH September YEAR

• 1980 LER OR MALFUtiCTION I

SYSTEM OR COMPONENT MR NO. - DATE OUTAGE CAUSE RESULT CORRECI'IVE ACTION Number 12 Salt M-80-124 Water in thrust Excessive temper-Replaced thrust Water Pump 7/24/80 bearing.

ature on bearing.

bilaring and over-hauled complete py'mfat same time

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Number llB Reacter M-79-557 Cyclic fatigue of Excessive seal R,eplaced sea Coolant Pump 5/3/80 Mechanical shaft leakage

(

seal.-

'3, g Number 13 Charging 0-80-2671 Defective Lube Excessive packing Replaced packing Pump 7/17/80 ring.

leakage.

and defective lube ring.

Cpciic'fatihue' Excsssive padking Repladed packing.

Number 13 Charging M-80-149 Pump 6/25/80 leakage.

Number 13 Charging 0-80-2139 Cyclic fatigue Excessive packing Replaced / packing.

Pump 6/18/80 leakage.

Number 13 Charging 0-80-2580 Cyclic fatigue Excessive packing Replaced packing.

Pump 7/14/80 leakage.

Number 13 Charging 0-80-2710 Cyclic fatigue Excessive packing Replaced packing.

Pump 8/26/80 leakage.

4 Nwnber 13 Charging 0-80-3316 Cyclic fatigue Excessive packing Replaced packing.

Pump 9/9/80 leakage.

Number 12 Charging 0-80-1876 Cyclic fatigue Excessive packing Replaced packing.

7/21/80 leakage.

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Number 12 Charging 0-80-2930 Cyclic fatigue Excessive packing Replaced ~p,acking.

8/4/80 leakag'e.

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