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(

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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 0.00407 0.00295 0.00261 Feedwater nozzle 0.18814 0.12646 0.10293 Closure studs 0.17378 0. 11139 0.07865 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 Reactor thermal power at 95%, sequence "B" CPR limited 8/02 2200 Commenced thermal power reduction for control rod pattern adjustment, turbine C.V. tests, and SI's 2300 Reactor thermal power at 65%, holding for contxol rod pattern adjustment, turbine C.V. tests, and SI's 8/03 0230 Control rod pattern adjustment completed, holding for turbine C.V. tests and SI's 0305 Turbine C.V. tests and SI's completed, commenced power ascension 0330 Commenced PCIOMR from 75% thermal power 8/05 2100 Reactor thermal power at 99%, steady state 2200 Reduced thermal power from 99% to 98% due to thermal power 1imits 8/07 0150 Reduced'hermal power from 98% to 85% for turbine C.V.

tests and SI's 0300 Turbine C.V. tests and SI's completed, commenced power ascension 1250 Commenced PCIOMR from 95% thermal power 1930 Reactor thermal power at.99%, steady state 8/11 2114 Reduced thermal power from 99% to 70% for turbine C.V.

tests and SI's:

2220 Turbine C.V. tests and SI's completed, holding for control rod pattern adjustment 2400 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 Computer problems resolved, commenced PCIOMR from 92%

thermal power 1500 Reactor thermal power at 97%, CPR limited 8/15 0340 Reduced thermal power from 97% to 85% per request of load dispatcher (generation not needed) 0445 Load dispatcher request discontinued, commenced power ascension 0500 Commenced PCIOMR from 90% thermal power 1500 Reactor thermal .power at 98%, CPR limited

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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 Turbine C.V. tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 97%, CPR limited 8/21, 0855 Reduced thermal power from 97% to 85% when plant pre-ferred power was switched to alternate source and recirculation pump scoop tube locked 0900 Plant preferred power restored, recirculation pump scoop tube reset, commenced power ascension 0935 Reactor thermal power at 97%, CPR limited 8/25 0002 Reduced thermal power from 97% to 85% for turbine C.V. tests and SI's 0255 Turbine C.V. tests and SI's completed, commenced power ascension 0355 Reactor thermal power at 97% CPR limited 8/29 2230 Reduced thermal power from 97% to 75% due to "B" recirculation pump low oil level alarm signal 2327 Reduced thermal power from 75% to 70% due to low oil level alarm not clearing on "B" recirculation pump 8/30 0035 Commenced power ascension from 70% thermal power 0155 Commenced PCIOMR from 90% thermal power 1500 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 Reactor thermal power at 78%, sequence "A", PCIOMR in progress 2300 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 0145 Turbine C.V. tests and SI's completed, commenced power ascension 0240 Commenced PCIOMR. from 95% thermal power 1000 Reactor thermal power at 99%, steady state 8/10 2330 Reduced thermal. power from 99% to 70% for turbine C.V.

tests and SI's

"='/11 0107 Turbine C.V. tests and. SI's completed,. commenced power ascension 0200 Commenced PCIOMR from 96% thermal power 0630 Reactor thermal power at 99%, steady state 8/12 0405 Commenced reducing thermal power to shut down the unit to repair EHC leak.

0507 Reactor scram no. 83 (manual) from 35% thermal power to repair EHC leak 0850 EHC repairs completed, commenced rod withdrawal 1350 Reactor critical no. 96 (sequence " ")

1716 Rolled T/G 1739 Synchronized generator, commenced power ascension 2300 Reactor thermal power. at 50%, holding due to computer problems 8/13 0442 Computer problems resolved, commenced power ascension 0750 Commenced PCIOMR from 72% thermal power 8/14 1430 Reactor thermal power at 92%, rod limited (max. flow) 2155 Reduced thermal power from 92% to 60% for control rod pattern adjustment 2228 Control rod pattern adjustment completed, commenced po~er ascension 8/15 0100 Commenced PCIOMR from 90% thermal power 1405 Reactor thermal power at 99%, steady state 8/18 0005 Reduced thermal power from 99% to 85% for turbine C.V.

tests and SI's 0230 Turbine C.V. tests and SI's completed, commenced power ascension 0421 Commenced PCIOMR from 95% thermal power 0700 Reactor thermal power at 100% steady state

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Si nificant 0 erational Events Unit 2 Date Time Event 8/21 1500 Reactor thermal power at 100%, steady state 8/23 1500 Reactor thermal power at 100%, steady state 8/25 0001 Reduced thermal power from '100% to 85% for turbine C.V. tests and SI's 0218 Turbine C.V. tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 100%, steady state 8/29 1500 Reactor thermal power at 99%, steady state 8/31 2207 Commenced reducing thermal power from 99% to shutdown the unit to repair EHC oil leak 2236 Reactor scram no. 84 (manual) from 40% thermal power to accommodate EHC maintenance 2400 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 Reduced thermal power from 99% to 80% for turbine C.V.

tests and SI's 2000 Turbine C.V. tests and SI's completed, commenced power ascension 2130 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 0125 Turbine C.V. tests and SI's completed, commenced PCIOMR 8/12 1430 Reactor thermal 'power at 99%, steady state 8/14 1030 Reduced thermal power from 99% to 75% for removal of "B" reactor feedwater pump from service due to high vibration 1445 "B" reactor feedwater pump in service, commenced power ascension 2300 Reactor thermal power at 99%, steady state 8/16 1500 Reactor thermal power at 99%, steady state 8/17 0445 Reduced thermal power from 99% to 75% for removal of "B" reactor feedwater pump from service due to excessive vibrations 0910 ~

Reduced thermal power from 75% to 70% 'for control rod pattern adjustment 1011 Reactor scram no. 77 from 70% thermal power on Mi IV closure while performing SI 1215 Commenced rod withdrawal 1438 Reactor critical no. 87 1713 Rolled T/G 1733 Synchronized generator, commenced power ascension 8/18 1030 Commenced PCIO>K from 70% thermal power 2215 "B" reactor feedwater pump placed in service, PCIO<~K continued

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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 Commenced reducing thermal power from 93% to 55% for removal of "B" recirculation pump from service 1822 Commenced reducing thermal power from 55% for shutdown of unit for recirculation pump maintenance 2212 Reactor scram no. 78 (manual) from 40% thermal power to accommodate recirculation pump maintenance 8/22 0001 Reactor at cold shutdown for maintenance 8/24 0700 "B" recirculation pump maintenance outage completed,

'e. commenced refueling outage for cycle 3 fuel (1) Equipment malfunction

AVERAGE DAlLYUNIT POWER LEVEL BROWS PERRY 1 COMPLETED BY mls=

MONTH August, 1979 DAY AVERAGE DAlLYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) ~

I 997 17 1028 994 18 1020 975 19 1006 4 740 20 1016 974 21 1007 6

1036 22 . 1020 1021 23 '007'1019

' 1011

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24 1003 25 1002 10 26 1004 56 27 1005 12 865 28 1006 13 .1011 29 1006 14 1022 30 1007 15 1029 31 991 l6 1030 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 DAILYUNIT POWER LEVEL DOCKET NO. 50 260 UNIT BROGANS FERRY 2 DATE COMPLETED 8Y Ted Thorn TELEPHOiNE MOi 1TH Au ust 19?9 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) 1006 17 1070 1059 18 1053 2

3 1068 19 1052 1054 20 1063 1070 21 1057 10 7 22 1075 1054 1059 1054 24 1074 1054 . 1054 10 1054 26 1064 1038 27 1068 275 1070 12 28 720 29 1068 13 897 30- 1075 14 15 1037 31 985 1068 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 )

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'VERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNIT BROWNS PERRY 3 DATE COMPLETED BY Ted Thorn TELEPHONE 205/729-6846 MONTH August, 1979 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL

. (iMWe-iVet) (MWe-Net) ~

I 1048 17 521 18 7 6 1027 19 890 4 1039 20 942 S

1036 21 492 1029 -10 22'4 1021 1001 993 25 10 971 26 872 27 980 12 28 13

. 1041 29 977 30 IS 1048 31 16 1047 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 )

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13 OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED EY J)~eGSeen.

TELEPHONE OPERATING STATUS BROWN S FERRY 1 Notes Uni t Name

3. Licensed Thermal Power (j PIWt)t

4. Nameplate Rating (Gross MWe):

'152 5

5. Design. Electrical Rating (Net ijIWe):

6. Maximum Dependable Capacity (Gross MWe): 1098.4 Maximum Dependable Capacity (Net jMWe):

1065 7.

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:

T ~

This Month Yr.-to.Date Cumuhtive

11. Hours In Reporting Period 5,831 44'569

12. Number Of Hours Reactor Was Critical

~ 744 5 232.09 ~

. 25 463.68

13. Reactor Reserve Shutdown Hours 175.08

14. Hours Generator On-Line 744 8 4 "24820

15. Unit Reserve Shutdown Hours 0 09 199 66 281 871

17. Gross Electrical Energy Generated (MPH) 5,107,630 21,925,630

. 18. jXet Electrical Energy Generated (MPH) 4 971 311 21,2779531 88.0 55.7

20. Unit Availability Facie 88.0 55.7 I

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21. Unit Capacity Factor (Using MDC Net) 80. 1 I

22. Unit Capacity Factor (Using DER Net) 80.1 44.8

23. Unit Forced Outage Rate 4.3 35.2

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

. Refuel Outage November, 1979

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 DATA REPORT 'i, DOCKET NO.

DATE 4 79 COiiIPLETED BY TELEPHONE ~~846 OPERATING STATUS Notes 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):

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

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

10. Reasons For Restrictions, If Any:

This Month Yr:to-Date Cumulative I'

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39 '480

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12.

Hours In Reporting Period Number Of Hours Reactor Was Critical '33 10.12

~ 88 5 831 5 052.65 82.77 21 770.94 11 559;48

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line. 4 . 4 21'05.40 Unit Reserve Shutdown Hours 0 0 0 15.

27 628

- ""'r""i 98.1 48 28 18-723 692 53.2

19. Unit Service Factor

20. Unit Availability Fact< 84. '53.2

21. Unit Capacity Factor (Using MDC iNet) 44.5

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 1.9 1.5 3 .4

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

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

26. Units In Test Status(Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COM!iIERCIALOPERATION (A/77)

15 OPERATING DATA REPORT l.

DOCKET NO. 5296 DATE COMPLETED BY

~Z9 TELEPHONE 2Q5l ~j846 OPERATING STATUS Notes

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):

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, If Any (Net MWe):

10. Reasons For Restrictions, lf Any:

~ r This Month Yr:to-Date Cumuhtive

11. Hours In Reporting Period 744 5 831 21'35

'12. Number Of Hours Reactor Was Critical 497.75 5 224.60 18 15.80

13. Reactor Reserve Shutdown Hours 61.25 . 421.40 1526.81 17 904.03'

15. Unit Reserve Shutdown Hours 0

16. Gross Thermal Energy Generated (MWH) . 1 506 382 15 724 989 51 876 371

17. Gross Electrical Energy Generated (MWH) 5 231 290 16 998 790

. 18. Net Electrical Energy Generated (MWH) ~

473 1466

~ 5 091 972 ~ tr I

81.6

20. Unit Availability Factttr ~

66.5 81.6 .

"21. Unit Capacity Factor (Using MDC Net) 59 ~ 7 70.6

22. Unit Capacity Factor (Using DER Net) 59 ~ 7 70.6

23. Unit Forced Outage Rate 11.5 9.2

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

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 COiblibIERCIAL OPERATION (o(77)

DOCKET NO.

VNlTSllUTDOWNS AND POWER REDUCTlONS BROWNS PERRY 1 COhlPLETED BY REPORT h(ONTO I

r< p o Ltccnscc

~n C Cause & Correitive C 0 No. Date ~ A a5cc Event Q Action to CI tp Report e C ~ Prevent Re<.urrcn<.e

~ V) PJ Derated for turbine control valve 89 . 790802 tests and SI<s, and control rod F

pattern ad)ustment II <I II 90 790811 B 91 790829 A Derated due to "B" recirc. pump low oil level alarm signal 3

F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A.Equipment Failure (Explain) l -hlanual for Prepi<ratfon of'Data 8-Maintenance or Test 2-Manual Scram. Lntry Shccts for Licensee C-Refueling 3-Automatic Scram. Event Report (LER)File (NURFG-D-Regulatory Restriction 4.Other (Explain) 016I l E.Operator Training & Liccnsc Examination F-Administrative S G.Operational Error (Explain) ~ Exhibit I ~

Sa<nc Source

(')/77) Il.Other (Explain)

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UNIT Sl>>UTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIT NAME DATE COh>>PLETED it@, Don Green REPORT MONT>>>> AUGUST No. Dale r>

~

V A

s m Sec

~0 M J

Event Rcport 4'~

Liccnsce

<O 0 Cause A, Corrective Aclion lo Prevent Recurrence

'L 96 790810 B Derated for t'urbine con'trol valve test and SI's.

97 790812 12.53 B Maintenance to EHC '(Oil Leak) 98 790814 H Derated for Control Rod Ad)ustment 99 790831 1.40 B Maintenance to EHC (Oil Leak)

F: Forced Reason: Melhod: Exhibit 'G - lnslruclio>>s S: Scheduled A-Equipment Failure (Explain) I Manual for Preparation of Data B.Maintenance or Test 2-Manual Scram. Entry Sheets I'or Liccttsee C.Refueling 3.Automatic Scram. Event Report (LER) File (NUREG-D Rct,uiatory Restriction 4 Other (Explain) OI6 I I E.Operator Training 8c Liccnsc Examination F.Administrative S G.Operational Error (Explain) Exhibit I - Sante Source

('I/77) ll Other (Explai>>)

DOCKET NO.

UNIT SIIUTDOWNS AND POWER REDUCTIONS BROWNS FERRY 3 UNIT NAME DATE COMPLETED BY TELEPI IONE NII. Date I I IA

~- nC Liccnscc Evc nl c~

o ~CI Cause A Corre).tive Action lo rI Q Q

Report tr 0 Prevent Rccurrcnce

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105 790810 . B Derated for turbine control valve tests and SI's.

106 790814 A "B" reactor feed pump high vibration 107 790817 7.37 HSIV closure during performance of an SI..

108 790821 F 56.80 "B" recirculation pump maintenance 109 790824 S 185.0

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4 Forced Reason: Method: Exhibit G ~ Instructions S: ScheduleMARY CSSC E UIPMENT EFFECT ON SAFE ACTION TAKEN OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE SYSTEM COMPONENT NATURE OF THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE MAINTENANCE 8/6 Rx. Bldg. All fans Rx. MSIL 30 None None Performed MSIL 30 Checked fan speeds Control Bldg. Control on fans all were ok Bay Fans Bay 8/7 Scram discharg Valve leaking None Valve seat not Valve leaking Ad)usted steam valve on modul through healing I

50-19 8/25 CRD 1 "A" pump TCV and RCM None lines plugged High temp. on Cleaned out lines reduction gear lines plugged reduction gear 8/28 1 "A" discharge Dirty filters None Filters dirty Dirty filters Changed out dirty filter filters

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BRO!%S FERRY NUCLEAR PLANT UNIT 3 CSSC E UIPMENT MECHANICAL MAINTENANCE SUGARY For the Month of August 1979 Page 1 of 2 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8/1 Drywell 3 iAu comp, System will None Broken reeds Mould not hold Replaced reeds and Air hold pressur pressure installed new head Comp. gaskets 8/5 High Valve "771" Valve stuck None Valves were not Valve hard to open Greased with plug Pressure lubricated I

and shut valve lubricant Fire Protection 8/5 High Valve 735 Valve stuck None Valves were not Valve hard to open Greased with p g Pressure lubricated and shut valve lubricant Fire Protection 8/5 High Valve "791" Valve stuck None Valves were not Valve hard to open Greased with plug Pressure lubricated when and close valve lubricant Fire installed Protection 8/5 High Valve 751 Valve stuck None Valves were not Valve hard to open Greased with plug Pressure lubricated when and close valve lubricant Fire installed Protection 8/5 High Valve 761 Valve stuck None Valves were not Valve hard to open . Greased with plug Pressure lubricated when and close valve lubrica Fire installed Protection 8/7 HPCI Valve 73-34 Handwheel br None Handwheel off No way to turn Replaced handwheel 4

ken off valve on or off with new one.

Installed lock washers

BROWNS FERRY NUCLEAR PLANT UNIT 3 CSSC E UIPMENT ~QQHICAL MAIJTENAQCE SUlkfARY For the Month of August 1979 Page 2 of 2 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE l S.INTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 8/8 Drywell 3 "B" comp, Leaking r

oil None Oil leaking from Oil leak Tightened both jugs Air bottom of jugs Compressor I'eak 8/10 Diesel No. 2'air Leaking aroun None around head Loss of pressure Repaired leak a id Generator compressor high press. high press. head head

BROWNS FERRY NUCLEAR PLANT UNIT Common MECllANICAL MAINTENANCE

SUMMARY

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

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

Need rails installed fire for protection

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

"Strainer Clean, inspect Inspection of.

8/6 EECW EECW A" ad)uqt drum make repairs None

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

~

Al~ .

inspections good 8/12 High Press No. 5 Fire Plug leaking None Steam shear pin Valve not closing, Replaced shear pin Fire plug water sheared off. letting water leak and seated valve Protection Valve not seatin 8/ll High Press Pire pump Handwheel None Handwheel broken Broken handwheel Replaced with a new Fire strainer broken off, off valve would not close handwheel and valve Protection blowdown valve blowdown valve 8/18 EECW C "3" pump Packing leak None Packing was out Leak at strainer Packing was strainer at strainer on of ad)ustment replaced C "3" pump

BRCRHB FERRY NUCLEAR PLRRY UHLY 1 CSSC E UIPMENT ELECTRICAL MAINTENANCE SUl MARY For the Month of August 19 79 ect on a e Action Taken Date 'System Component Nature of. Operation of Cause of Results of To Preclude Maintenance The Reactor. Malfunction Malfunction Recurrence 7/31/79 Pire X5-39-106FC Pailed smoke N/A. Failed sensor Would not respond Replaced detector, Not I protectio smoke 'detec- 'detector to smoke performed SI 4.11.C.

prev. tor t 1 & .5. Checked OK.

reporte TR 139932 8/5/79 Pire Smoke detec- Pailed detec- N/A Failed detector Replaced detector protectio tor in unit 1 tor and annunciator and card, performed auxiliary card. SI 4.11.C.l & .5.

instrument Checked OK. TR room (XS 141937. LER No.

120) BFRO 50-259/7915, 8/13/79 480V shut Normal feed . Transformer N/A Control trans- Cooling fan inoper- Replaced cooling down to 480V cooling f'an former WG . able fan failure transformer(WG)'hecked

'oards shutdown burned out OK. TR board, 125452 transformer TS 1B cool-ing fan 8/24/79 250V DC Unit 1 control Failed SE N/A~ olding coil Switch would not " Replaced coil.

distribu- room panel relay urned up transfer Checked 'OK.

tion 9-9, SE relay TR 134245

BR0%lB PE!IRX NUCLEAR PLANT UNIT MAINTENANCE SDMARY 2.'LECTRICAL CSSC E UIItKNT For the Month of August 19 79 ect on a e Action Taken Nature of Operation of Cause of Results of To Preclude Date 'System Component Maintenance The Reactor . Malfunction Malfunction RA currence 7/27/79 Distribu- Panel 9-42 tion panels indicating light for t'alve Relay 16AK40 failed, inoperable Relay up I

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

OK. TR 134865 Checked re-FCV 64-21 LER No. BFRO 50-269/,

reactor build 7918 ing to torus .

vacuum break-er 8/9/79 Radiation LPRM detector Broken connec- N/A, Broken wire to Reterminated wire.

monitor- cable con- ~ tor LPRM common plug Checked OK.

ing nector terminal TR 139255 8/22/79 250V DC 250V DC reac- Check breaker N/A Failed molded Breaker inoperable . Installed new breaker, reactor tor MOV board case breaker Checked OK. TR motor 2C - spare (found in per- 133712 operated breaker formance of EMI valve (panel 10B2) 7) boards

FROUDE FERRY UUCLEM FLEET UHYY 9 CSSC E UIPHENT ELECTRICAL MAINTENANCE St&MAR~

ect on a e Action Takeg Date 'System Component Nature of Operation of 'ause of Results of To Preclude The Reactor . Malfunction Malfunction Recurrence t'/A Maintenance 8/22/79 Reactor C-1 RHR SM Replace ~

Contacts burned Unable to start pum Replaced SMB switch.

I ~

heat re- pump motor 'switch. and pitted from unit 3 control Checked OK, moval SHB switch room TR 96885 service water 0 8/22/79 Reactor Reactor low Check relay N/A Relay coil Failed relay Replaced relay.

water level J

feedwater burned up Tested OK.

relay SA-K25B TR 116011

BROWS .FERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE

SUMMARY

CSSC E UIPMENT NATURE EFFECT ON SAFE CAUSE ACTION TAKEN SYSTEM COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Unit l 8/27 Neutron Monitoring LPRM 24-09 24-57 32-09 t'one Repair Reference diode degradation Slight drift in reference voltage caused alarms None 48-4l 8/28 Control TCV-85-62A Calibrate None Valve out of Oil flow was too high, None Rod Drive ad)ustment.. causing low tempera-ture Unit 2

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

None Monitoring cation

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.