ML18024B003

Monthly Operating Rept for Aug 1979

ML18024B003
Person / Time
Site:	Browns Ferry
Issue date:	09/04/1979
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024B001	List: ML18024B000 ML18024B003
References
NUDOCS 7909140381
Download: ML18024B003 (34)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT August 1, 1979 August 31, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS.DPR-33, DPR-52, AND DPR-68 Submitted By:

P ant Superintendent Y909lg OP8(

~

~

I

~

~

TABLE OF CONTENTS Operations Summary

~

~

1 Refueling Information

~ ~

~

~

2 Significant Operational Events 4

Average Daily Unit Power Level

~

~

~

~

~

~

~

~

t

~

10 Operating Data Reports

~

~

~

~

~ i

~

~

13 Unit Shutdowns and Power Reductions.

16 Plant Maintenance 19 Outage Section Monthly Report s

~

~

~

28

1

0 erations Summa The following summary describes the significant operational activities during the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

There were eight reportable occurrences reported to the NRC duxing the month of August.

Unit 1 The unit did not.scram during the month.

. Unit 2 The unit scrammed twice during the month.

On August 12 and 31, the I

reactor was manually scrammed to repair an EHC fluid leak.

Unit 3 The unit scrammed twice during the month.

On August 17, the reactor scrammed due to MSIV closure caused by personnel error during surveillance

~e testing.

The reactor was, manually scrammed on August 21 to investigate recirculation pump "B" motor upper guide bearing high temperature.

This maintenance outage extended into the scheduled refuel outage which began on August 24.

Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line Feedwater nozzle Closure studs 0.17378

0. 11139 0.07865 0.00407 0.00295 0.00261 0.18814 0.12646 0.10293 Note:

This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.

Common S stems Approximately 1 31E+05 gallons of waste liquid were discharged containing

~-- 4.40E-02 curies of activity.

Refuelin Information.

Unit i Unit 1 is scheduled for its third refueling beginning on or about November 22, 1979, with *a restart date of January 5, 1980.

This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, and LPCI modifications.

There are 764 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies, two 8 x 8 R fuel assemblies, and 252 new fuel assemblies.

Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 720 assemblies.

With present capacity, Unit 1 does not have full core discharge capability in the pool.

Unit 2 Unit 2 is scheduled for its third refueling beginning on September 1, 1980, with a scheduled restart date of October 7, 1980.

Resumption of operation on that date will require a change in technical specifications pertaining to the core thermal limits.

Licensing information in support of these changes will be submitted to the NRC before the outage.

This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.

.There are 764 fuel assemblies in the reactor vessel.

At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool.

The present storage capacity of the spent fuel pool is 1080 assemblies.

Qith present

capacity, the 1979 refueling would be the last refueling that could be di"-charged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Unit 3 Unit 3 began its second refuel outage on August 24, 1979, with a scheduled restart date of November 21, 1979.

This refueling will involve loading additional 8 x 8 R (retrofit) assemblies into the core, MSRV tailpipe routing, core spray piping modifications, feedwater sparger modifications, and LPCI modifications.

Resumption of operation following refueling will require changes in technical specifications pertaining to the core thermal limits.

Licensing information in support of these changes has been previously submitted.

There are 618 fuel assemblies presently in the reactor vessel.

There are 146 assemblies from the cycle 2 core, 208 discharged cycle 1 fuel assemblies and 144 new fuel assemblies in the spent fuel storage pool.

The present storage capacity of the spent fuel pool is 1528 assemblies.

Si nificant 0 erational Events Unit. 1 Date Time Event 8/01/79 0001 8/02 2200 2300 Reactor thermal power at 95%, sequence "B" CPR limited Commenced thermal power reduction for control rod pattern adjustment, turbine C.V. tests, and SI's Reactor thermal power at 65%, holding for contxol rod pattern adjustment, turbine C.V. tests, and SI's 8/03 8/05 0230 0305 0330 2100 2200 Control rod pattern adjustment completed, holding for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 75% thermal power Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 98% due to thermal power 1imits 8/07 0150 0300 1250 1930 Reduced'hermal power from 98% to 85% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at.99%,

steady state 8/11 2114 2220 2400 Reduced thermal power from 99% to 70% for turbine C.V.

tests and SI's:

Turbine C.V. tests and SI's completed, holding for control rod pattern adjustment Control rod pattern adjustment completed, commenced PCIOMR from 70% thermal power 8/12 1945 Reactor thermal power at 92%, holding due to computer problems 8/13 0442 1500 Computer problems resolved, commenced PCIOMR from 92%

thermal power Reactor thermal power at 97%,

CPR limited 8/15 0340 0445 0500 1500 Reduced thermal power from 97% to 85% per request of load dispatcher (generation not needed)

Load dispatcher request discontinued, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal.power at 98%,

CPR limited

~

~

Si nificant 0 erational Events Unit 1 Date TDae Event 8/17 2305 Reduced thermal power from 98% to 85% for turbine C.V.

tests and SI's 8/18 0220 0700 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 97%,

CPR limited 8/21, 0855 0900 0935 Reduced thermal power from 97% to 85% when plant pre-ferred power was switched to alternate source and recirculation pump scoop tube locked Plant preferred power restored, recirculation pump scoop tube reset, commenced power ascension Reactor thermal power at 97%,

CPR limited 8/25 0002 0255 0355 Reduced thermal power from 97% to 85% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 97%

CPR limited 8/29 2230 2327 Reduced thermal power from 97% to 75% due to "B" recirculation pump low oil level alarm signal Reduced thermal power from 75% to 70% due to low oil level alarm not clearing on "B" recirculation pump 8/30 0035 0155 1500 Commenced power ascension from 70% thermal power Commenced PCIOMR from 90% thermal power Reactor thermal power at 97%

CPR limited 8/31 2400 Reactor thermal power at 97%

CPR limited e ~

Si nificant 0 erational Events Unit 2 Date Time Event 8/01/79 0001 2300 Reactor thermal power at 78%, sequence "A", PCIOMR in progress Reactor thermal power at 99%, steady state 8/03 2335 Reduced, thermal power from 99% to 90% for turbine C.V.

tests and SI's 8/04 8/10 0145 0240 1000 2330 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR. from 95% thermal power Reactor thermal power at 99%, steady state Reduced thermal. power from 99% to 70% for turbine C.V.

tests and SI's

"='/11 0107 0200 0630 Turbine C.V. tests and. SI's completed,.

commenced power ascension Commenced PCIOMR from 96% thermal power Reactor thermal power at 99%, steady state 8/12 0405 0507 0850 1350 1716 1739 2300 Commenced reducing thermal power to shut down the unit to repair EHC leak.

Reactor scram no.

83 (manual) from 35% thermal power to repair EHC leak EHC repairs completed, commenced rod withdrawal Reactor critical no.

96 (sequence

" ")

Rolled T/G Synchronized generator, commenced power ascension Reactor thermal power. at 50%, holding due to computer problems 8/13 0442 0750 Computer problems resolved, commenced power ascension Commenced PCIOMR from 72% thermal power 8/14 1430 2155 2228 Reactor thermal power at 92%, rod limited (max. flow)

Reduced thermal power from 92% to 60% for control rod pattern adjustment Control rod pattern adjustment completed, commenced po~er ascension 8/15 0100 1405 Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 8/18 0005 0230 0421 0700 Reduced thermal power from 99% to 85% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at 100% steady state

~

~

Si nificant 0 erational Events Unit 2 Date Time Event 8/21 8/23 1500 1500 Reactor thermal power at 100%, steady state Reactor thermal power at 100%, steady state 8/25 0001 0218 0700 Reduced thermal power from '100% to 85% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 100%, steady state 8/29 8/31 1500 2207 2236 2400 Reactor thermal power at 99%, steady state Commenced reducing thermal power from 99% to shutdown the unit to repair EHC oil leak Reactor scram no.

84 (manual) from 40% thermal power to accommodate EHC maintenance Reactor shutdown for EHC maintenance ee

Si nificant Operational Events Unit 3 Date TMe Event 8/01/79 0001 Reactor thermal power at 99% control rod sequence "A",

steady state 8/03 1745 2000 2130 Reduced thermal power from 99% to 80% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power 8/04 0230 Reactor thermal power at 98%, rod limited (max. flow) 8/10 2200 Reduced thermal power from 98% to 70% for turbine C.V.

tests and SI's 8/11 8/12 0125 1430 Turbine C.V. tests and SI's completed, commenced PCIOMR Reactor thermal 'power at 99%, steady state 8/14 1030 1445 2300 Reduced thermal power from 99% to 75% for removal of "B" reactor feedwater pump from service due to high vibration "B" reactor feedwater pump in service, commenced power ascension Reactor thermal power at 99%, steady state 8/16 1500 Reactor thermal power at 99%, steady state 8/17 0445 0910 1011 1215 1438 1713 1733 Reduced thermal power from 99% to 75% for removal of "B" reactor feedwater pump from service due to excessive vibrations

~ Reduced thermal power from 75% to 70% 'for control rod pattern adjustment Reactor scram no.

77 from 70% thermal power on Mi IV closure while performing SI Commenced rod withdrawal Reactor critical no.

87 Rolled T/G Synchronized generator, commenced power ascension 8/18 1030 2215 Commenced PCIO>K from 70% thermal power "B" reactor feedwater pump placed in service, PCIO<~K continued

~

~

Si nificant 0 erational Events Unit 3 Date Time Event 8/20 1500 Reactor thermal power at 93%, holding due to high temperature on "B" recirculation pump upper guide bearing 8/21 0100 1822 2212 Commenced reducing thermal power from 93% to 55% for removal of "B" recirculation pump from service Commenced reducing thermal power from 55% for shutdown of unit for recirculation pump maintenance Reactor scram no.

78 (manual) from 40% thermal power to accommodate recirculation pump maintenance 8/22 0001 Reactor at cold shutdown for maintenance

'e.

8/24 0700 "B" recirculation pump maintenance outage completed, commenced refueling outage for cycle 3 fuel (1) Equipment malfunction

AVERAGE DAlLYUNITPOWER LEVEL BROWS PERRY 1 COMPLETED BY mls=

MONTH

August, 1979 DAY AVERAGEDAlLYPOWER LEVEL (MWe-Net)

I 997 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

~

17 1028 994 975 4

740 974 6

1036 1021

~

1011 1003 10 56 18 19 20 21 22 23 24 25 26 27 1020 1006 1016 1007

. 1020

'007'1019 1002 1004 1005 12 13 14 15 l6 865

.1011 1022 1029 1030 28 29 30 31 1006 1006 1007 991 INSTRUCTIONS On this format, list the average daily.unit'power level in LWIWe.Viet for each day in the reporting nt>>nth. Compute to the nearest whole megawatt.

(0I77)

AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

50 260 UNIT DATE BROGANS FERRY 2 COMPLETED 8Y Ted Thorn TELEPHOiNE MOi1TH Au ust 19?9 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1006 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1070 17 2

3 10 12 13 14 15 1059 1068 1054 1070 10 7

1054 1054 1054 1054 1038 275 720 897 1037 1068 18 19 20 21 22 24 26 27 28 29 30-31 1053 1052 1063 1057 1075 1059 1074

. 1054 1064 1068 1070 1068 1075 985 INSTRUCTIONS, Oa this format,!ist the average daily unit power level in ibIIVe.Net for each day in the reporting month. Ci> npute to the nearest whole megawatt.

(<)l77 )

12

'VERAGE DAILYUNITPOWER LEVEL

" DOCKET NO.

UNIT BROWNS PERRY 3

DATE COMPLETED BY Ted Thorn TELEPHONE 205/729-6846

August, 1979 MONTH DAY AVERAGE DAILYPOWER LEVEL

. (iMWe-iVet)

I 1048 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

~

521 17 4

S 10 12 13 IS 16 1027 1039 1036 1029 1021 1001 993 971 872 980

. 1041 977 1048 1047 18 19 20 21 22'4 25 26 27 28 29 30 31 7

6 890 942 492

-10 INSTRUCTIONS On this format, list the average daily'unit power level in iWIWe.Viet for each day in the reportina >non th. Compute to the nearest whole megawatt.

(')/77 )

~ ~

13 OPERATING DATAREPORT DOCKET NO.

DATE COMPLETED EY J)~eGSeen.

TELEPHONE OPERATING STATUS Unit Name BROWNS FERRY 1

3. Licensed Thermal Power (jPIWt)t

4. Nameplate Rating (Gross MWe):

'152

5. Design. Electrical Rating (Net ijIWe):

5

6. Maximum Dependable Capacity (Gross MWe):

1098.4

7. Maximum Dependable Capacity (Net jMWe):

1065 Notes

8. IfChanges 0'ccur in Capacity Ratings (Items Number 3 Through,7) Since Last Report, Give Reasons:

9. Power Level To Which Restjicted, IfAny (Net jPIWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to.Date 5,831

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

~ 744

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

17. Gross Electrical Energy Generated (MPH)

. 18. jXet Electrical Energy Generated (MPH)

20. Unit AvailabilityFacie

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duratio

. Refuel Outage November, 1979 744 5 232.09 175.08 8

4 09 199 5,107,630 4 971 311 88.0 88.0

80. 1 80.1 4.3 n of Each):

T

~

Cumuhtive 44'569

~. 25 463.68 "24820 0

66 281 871 21,925,630 21,2779531 55.7 55.7 44.8 35.2 I

~

~

I

25. IfShut Down At End Of Report Period, Estimated Date of Startup:

'6. Units In Test Status IPrior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhfilfERCIAL OPERATIOj'I (o/77)

14 OPERATING STATUS OPERATING DATAREPORT

'i, DOCKET NO.

DATE 4 79 COiiIPLETED BY TELEPHONE ~~846 BR OWN S FERRY 2

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross i%(We):

5. Design Electrical Rating (Net ilIWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

Notes

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

-~- 9. Power Level To Which Restricted, IfAny (Net iiIWe):

10. Reasons For Restrictions, IfAny:

This Month Yr:to-Date Cumulative I

~'

5 831 5 052.65 82.77 4

4 48 28 84.

~

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical '33

~ 88

13. Reactor Reserve Shutdown Hours 10.12

14. Hours Generator On-Line.

15. Unit Reserve Shutdown Hours 0

0

- ""'r""i

19. Unit Service Factor 98.1

20. Unit AvailabilityFact<

21. Unit Capacity Factor (Using MDC iNet)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 1.9 1.5

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

39 '480 21 770.94 11 559;48 21'05.40 0

27 628 18-723 692 53.2

'53.2 44.5 3.4

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

26. Units In Test Status(Prior to Commercial Operation):

INITIAL CRITICALITY INITIALELECTRICITY COM!iIERCIALOPERATION Forecast Achieved (A/77)

15 OPERATING STATUS

l. Unit Name

. 2. Reporting period:

Au ust-1979

3. Licensed Thermal Power (MWt):

4. Namephte Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

OPERATING DATAREPORT Notes l.

DOCKET NO.

5296 DATE ~Z9 COMPLETED BY TELEPHONE 2Q5l~j846

7. Maximum Dependable Capacity (Net MWe):

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

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

10. Reasons For Restrictions, lfAny:

~r This Month Yr:to-Date Cumuhtive 5 831 744 497.75 15 724 989 5 231 290

11. Hours In Reporting Period

'12. Number Of Hours Reactor Was Critical 5 224.60

13. Reactor Reserve Shutdown Hours 61.25 421.40

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH) 1 506 382

17. Gross Electrical Energy Generated (MWH)

. 18. Net Electrical Energy Generated (MWH)

~

~

6 5 091 972 473 146

20. Unit Availability Factttr

~ 66.5 "21. Unit Capacity Factor (Using MDC Net) 59 ~ 7

22. Unit Capacity Factor (Using DER Net) 59 ~ 7

23. Unit Forced Outage Rate 11.5

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

21'35 18 15.80 1526.81 17 904.03' 51 876 371 16 998 790 81.6 81.6 70.6 70.6 9.2

~ tr I

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

'6. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COiblibIERCIALOPERATION (o(77)

VNlTSllUTDOWNS AND POWER REDUCTlONS REPORT h(ONTO DOCKET NO.

BROWNS PERRY 1 COhlPLETED BY No.

Date r<

C

~A CI tp I

p o

a5cc

~ V)

Ltccnscc Event Report e

~n 0C Q

C ~

PJ Cause &Correitive Action to Prevent Re<.urrcn<.e 89 790802 F

Derated for turbine control valve tests and SI<s, and control rod pattern ad)ustment 90 790811 B

II

<I II 91 790829 A

Derated due to "B" recirc.

pump low oil level alarm signal F: Forced S: Scheduled

(')/77)

Reason:

A.Equipment Failure (Explain) 8-Maintenance or Test C-Refueling D-Regulatory Restriction E.Operator Training & Liccnsc Examination F-Administrative G.Operational Error (Explain)

Il.Other (Explain) 3 Method:

l -hlanual 2-Manual Scram.

3-Automatic Scram.

4.Other (Explain)

Exhibit G - Instructions for Prepi<ratfon of'Data Lntry Shccts for Licensee Event Report (LER)File (NURFG-016I l S

~

Exhibit I

~ Sa<nc Source

I i

~

UNITSl>>UTDOWNS AND POWER REDUCTIONS REPORT MONT>>>>

AUGUST DOCKET NO.

UNITNAME DATE COh>>PLETED it@,

Don Green No.

Dale r>

~A sV J

m Sec 0~ M Liccnsce Event Rcport4'~

0

<O Cause A, Corrective Aclion lo Prevent Recurrence

'L 96 790810 B

Derated for t'urbine con'trol valve test and SI's.

97 790812 98 790814 99 790831 12.53 B

H 1.40 B

Maintenance to EHC '(Oil Leak)

Derated for Control Rod Ad)ustment Maintenance to EHC (Oil Leak)

F: Forced S: Scheduled

('I/77)

Reason:

A-Equipment Failure (Explain)

B.Maintenance or Test C.Refueling D Rct,uiatory Restriction E.Operator Training 8c Liccnsc Examination F.Administrative G.Operational Error (Explain) ll Other (Explai>>)

Melhod:

I Manual 2-Manual Scram.

3.Automatic Scram.

4 Other (Explain)

Exhibit 'G - lnslruclio>>s for Preparation of Data Entry Sheets I'or Liccttsee Event Report (LER) File (NUREG-OI6 I I S

Exhibit I - Sante Source

UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPIIONE BROWNS FERRY 3 NII.

Date I I IArI Q

C

~- n

~ C/)

Liccnscc Evc nl Report tr c~

o ~

CI Q

0 Cause A Corre).tive Action lo Prevent Rccurrcnce 105 790810 B

Derated for turbine control valve tests and SI's.

106 107 790814 790817 7.37 A

"B" reactor feed pump high vibration HSIV closure during performance of an SI..

108 109 790821 790824 F

56.80 S

185.0 "B" recirculation pump maintenance

~

Forced S: ScheduleMARY 8/6 SYSTEM Rx. Bldg.

Control Bay Fans COMPONENT All fans Rx.

Bldg. Control Bay NATURE OF MAINTENANCE MSIL 30 EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION None RESULTS OF MALFUNCTION Performed MSIL 30 on fans ACTION TAKEN TO PRECLUDE RECURRENCE Checked fan speeds all were ok 8/7 8/25 CRD Scram discharg valve on modul 50-19 1 "A" pump reduction gear Valve leaking through TCV and RCM lines plugged None None Valve seat not healing I

lines plugged Valve leaking High temp.

on reduction gear Ad)usted steam Cleaned out lines 8/28 1 "A" discharge filter Dirty filters None Filters dirty Dirty filters Changed out dirty filters

~

~

~

~

~

g I

P

~

~

~

I

~,

~

~

~

~

~

~

CSSC E UIPMENT BRO!%S FERRY NUCLEAR PLANT UNIT 3

MECHANICAL MAINTENANCE SUGARY For the Month of August 1979 Page 1 of 2 DATE SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 8/1 8/5 8/5 Drywell Air Comp.

High Pressure Fire Protection High Pressure Fire Protection 3

iAu comp, Valve "771" Valve 735 System will hold pressur Valve stuck Valve stuck None None None Broken reeds Valves were not lubricated I

Valves were not lubricated Mould not hold pressure Valve hard to open and shut Valve hard to open and shut Replaced reeds and installed new head gaskets Greased with plug valve lubricant Greased with p g

valve lubricant 8/5 High Pressure Fire Protection Valve "791" Valve stuck None Valves were not lubricated when installed Valve hard to open and close Greased with plug valve lubricant 8/5 High Pressure Fire Protection Valve 751 Valve stuck None Valves were not lubricated when installed Valve hard to open and close Greased with plug valve lubricant 8/5 8/7 4

High Pressure Fire Protection HPCI Valve 761 Valve 73-34 Valve stuck Handwheel br ken off None None Valves were not lubricated when installed Handwheel off Valve hard to open and close No way to turn valve on or off Greased with plug valve lubrica Replaced handwheel with new one.

Installed lock washers

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 3

~QQHICAL MAIJTENAQCE SUlkfARY For the Month of August 1979 Page 2 of 2 8/8 8/10 SYSTEM Drywell Air Compressor Diesel Generator COMPONENT 3 "B" comp, No. 2'air compressor NATURE OF lS.INTENANCE Leaking oil r

Leaking aroun high press.

head EFFECT ON SAFE OPERATION OF THE REACTOR None None CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION Oil leaking from Oil leak bottom of jugs I'eak around head Loss of pressure ACTION TAKEN TO PRECLUDE RECURRENCE Tightened both jugs Repaired leak a id high press.

head

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT Common MECllANICALMAINTENANCE

SUMMARY

.t For the Month of August 19 79 SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAPE OPERATION OP THE REACTOR CAUSE OP MALFUNCTION RESULTS OF HALF UNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 8/1 High Press Pire Protection Isolation

valves, demin.

and raw water valve curb boxes Install rails for protec-tion of these t'one Protection of Need rails installed high press. fire for protection

'rotection Install rails for protection from trucks backing over high press fire system.

8/6 EECW EECW "Strainer A"

Clean, inspect ad)uqt drum make repairs None Inspection of.

.'Strainer A" No trouble found Hade inspection ad)usted drum ~

lubricated.

Al~.

inspections good 8/12 High Press No.

5 Fire Fire plug Protection Plug leaking water None Steam shear pin Valve not closing, sheared off.

letting water leak Valve not seatin Replaced shear pin and seated valve 8/ll High Press Pire pump Fire strainer Protection blowdown valve Handwheel broken off, blowdown valve None Handwheel broken Broken handwheel Replaced with a new off valve would not close handwheel and valve 8/18 EECW C "3" pump strainer Packing leak at strainer on C "3" pump None Packing was out of ad)ustment Leak at strainer Packing was replaced

CSSC E UIPMENT BRCRHB FERRY NUCLEAR PLRRY UHLY 1

ELECTRICAL MAINTENANCE SUlMARY For the Month of August 19 79 Date

'System Component Nature of.

Maintenance ect on a e Operation of The Reactor.

Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 7/31/79 Not I prev.

reporte Pire protectio X5-39-106FC smoke 'detec-tor Pailed smoke

'detector t

N/A.

Failed sensor Would not respond to smoke Replaced detector, performed SI 4.11.C.

1

&.5.

Checked OK.

TR 139932 8/5/79 Pire protectio Smoke detec-tor in unit 1 auxiliary instrument room (XS 120)

Pailed detec-tor N/A Failed detector and annunciator card.

Replaced detector and card, performed SI 4.11.C.l

&.5.

Checked OK.

TR 141937.

LER No.

BFRO 50-259/7915, 8/13/79 480V shut down

'oards Normal feed to 480V shutdown

board, transformer TS 1B cool-ing fan Transformer cooling f'an failure N/A Control trans-former WG burned out Cooling fan inoper-able Replaced cooling fan transformer(WG)'hecked OK.

TR 125452 8/24/79 250V DC Unit 1 control Failed SE distribu-room panel relay tion 9-9, SE relay N/A~

olding coil urned up Switch would not "

transfer Replaced coil.

Checked 'OK.

TR 134245

CSSC E UIItKNT BR0%lB PE!IRX NUCLEAR PLANT UNIT 2.'LECTRICAL MAINTENANCE SDMARY For the Month of August 19 79 Date

'System Component Nature of Maintenance ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude RA currence 7/27/79 Distribu-tion panels Panel 9-42 indicating light for FCV 64-21 reactor build ing to torus vacuum break-er Relay 16AK40 failed,t'alve inoperable Relay coil burne up I

Blowing fuses rend-ering valve inoper-able Replaced fuse and re-lay coil.

Checked OK.

TR 134865 LER No.

BFRO 50-269/,

7918 8/9/79 Radiation monitor-ing LPRM detector cable con-

~

nector Broken connec-tor N/A, Broken wire to LPRM common plug terminal Reterminated wire.

Checked OK.

TR 139255 8/22/79 250V DC reactor motor operated valve boards 250V DC reac-tor MOV board 2C - spare breaker (panel 10B2)

Check breaker N/A Failed molded case breaker (found in per-formance of EMI 7)

Breaker inoperable

. Installed new breaker, Checked OK.

TR 133712

CSSC E UIPHENT FROUDE FERRY UUCLEM FLEET UHYY 9

ELECTRICAL MAINTENANCE St&MAR~

Date

'System Component Nature of Maintenance ect on a e Operation of The Reactor

'ause of Malfunction Results of Malfunction Action Takeg To Preclude Recurrence 8/22/79 I

~

Reactor heat re-moval service water C-1 RHR SM pump motor SHB switch Replace

'switch.t'/A

~

Contacts burned and pitted Unable to start pum Replaced SMB switch.

from unit 3 control Checked OK, room TR 96885 0

8/22/79 Reactor feedwater Reactor low water level relay SA-K25B Check relay N/A Relay coil burned up Failed relay J

Replaced relay.

Tested OK.

TR 116011

CSSC E UIPMENT BROWS.FERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE

SUMMARY

SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE Unit l 8/27 Neutron Monitoring LPRM 24-09 24-57 32-09 48-4l Repairt'one Reference diode degradation Slight drift in reference voltage caused alarms None 8/28 Control Rod Drive TCV-85-62A Calibrate None Valve out of ad)ustment..

Oil flow was too high, causing low tempera-ture None

" Unit 2

8/28 l 8/29 Radiation Monitoring Primary Contain-ment Main steam line "C" LI-64-54B Calibrate Calibrate None None Instrument drift Mechanical zero shift Indicated high level Did not agree with control room indica-tion None None 8/30 Radiation Monitoring RM-90-249 Repair None Broken resistor Low particulate indi-

cation None

28 OUTAGE SECTION MONTHLY REPORT August 1979 Outage modification efforts prior to Unit 3, cycle 2 refueling outage were concentrated on security modifications, hypochlorite plant installation, LPCI board and battery room installation, high density storage rack and transfer slot canal expansion joint installation, DPP warehouse feeder modifications and prefabrication efforts for Unit 3 refueling outage.

Considerable effort was directed toward refueling activities the last couple of weeks prior to the outage.

Support craft were fabricating temporary buildings, tool boxes, and work facilities.

The recirculation pump, motor 3B upper guide bearing was wiped, causing a

forced shutdown of Unit 3 on August 21.

Investigation of the problem revealed 9 of l2 of the studs holding the upper guide bearing were-broken and the 3

others stretched.

The oil level, lower guide bearing, thrust bearing and annunciation were all normal Presently, Technical Support in Chattanooga is examining the studs.

The Unit 3, cycle 2 refueling outage start date was not officially declared until August 24, but actual vessel disassembly activities started soon after shutdown on August 21, 1979.

Progress was slower than usual as the overhead crane was utilized to receive and process Unit 1 fuel on a priority basis.

As of the end of August, the outage valve testing was over 90 percent complete, with approximately a 67 percent pass rate and a 33 percent failure rate.

Included in this failure rate were five main steam isolation valves.

The electrical boards were slightly over three percent

complete, and the major motor testing was about 95 percent complete with two pump motors discovered bad.

29 OUTAGE SECTION MONTHLY REPORT (Continued)

August 1979 Outage modification work started included:

main steam relief valve tailpipe routing; core spray piping changeout; ASEA transformer installation; heater manway installation; number 4-and 5 heater platform installation; LPCI conduit and cable installation; and reactor feedpump turbine logic installation.

All of the feedwater heaters, except C high pressure and the condenser water box tubes, were vacuum leak checked and found satisfactory.

A con-denser inspection, CCW inlet tunnel and CCW pump pit have been conducted with satisfactory results reported.

The low pressure B section of the turbine was disassembled and preparation made to perform NDE inspections of the spindle blades and dovetail pins.

The reactor feedpump 3A has been pulled for inspection of the impeller and shaft.

The control valve 3B as well as reactor feedpump turbine have been disassembled in order to make inspections and repairs as necessary.