ML18025A915

Monthly Operating Repts for May 1980

ML18025A915
Person / Time
Site:	Browns Ferry
Issue date:	06/01/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18025A912	List: ML18025A911 ML18025A915
References
NUDOCS 8006170507
Download: ML18025A915 (32)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT May 1, 1980 May 31, 1980 DOCKET NRSERS 50-259, 50-260, AND 50-296 LICENSE ~iERS J PR-33, DPR-52, AND DPR-68 Submitted By:

Plant Superintendent 8 0061 V0503

TABLE OF CONTENTS Operations Summary

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1 Refueling Information

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4 Significant Operational Events Average Daily Unit Power Level Operating Data Reports Unit Shutdowns and Power Reductions.

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6

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13

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16

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e 19 Plant Maintenance

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22 Outage Summary 28

0 erations Summar May 1980 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 fourteen reportable occurrences (plus two supplemental re-ports) reported to the NRC during the month of May.

Unit i There were three scrams on the unit during the month.

On May 6, the reactor scrammed due to turbine control valve fast closure from EHC pressure fluctuations.

The reactor scrammed on May 7, after the main and RFP turbines tripped from a false high water level signal caused by a blown fuse in the "A" feedwater inverter.

On May 27, the reactor scrammed after a generator load rejection caused by the operation of the main transformer differential relay due to personnel error.

Unit 2 There were three scrams on the unit during the month.

On May 2, the reactor was manually scrammed to repair a leak on the main steam "B" control

valve, second steam leak-off piping flange.

The"reactor was manually scrammed on May 3, to repair the EHC servo-valve to the "A" turbine control valve be-cause the servo-valve had been installed incorrectly.

On May 16, the reactor was manually scrammed to repair an EHC oil leak in the "C" control valve servo-motor.

0 erations Summar (Continued)

May 1980 Unit 3 There were two scrams on the unit during the month.

On May 15, the reactor scrammed due to a generator load rejection when a gr'ound occurred on the gen-erator field ground detector (possible personnel error).

The reactor scrammed on May 21, due to high flux on APRM "D" and MSIV "B" and "C" not fully open.

Investigation revealed that the AC pilot valve on the "C" outboard MSIV did not re-energize (defective relay) during tests on the MSL high flow switches.

0 erations Summary (Continued)

Hay 1980 Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usa e Factor Shell at water line Feedwater nozzle Closure studs Unit 1 Unit 2 0.00464 0.21997 0.00343 0.14835

0. 19099 0.12106 Unit 3 0.00295 0.10950 0.08794 Note:

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

Common S stems Approximately 9.99E+04 gallons of waste liquid were discharged containing approximately 1.67E-Ol curies of activity.

Refuelin Information May 1980.

Unit 1 Unit 1 is scheduled for its fourth refueling beginning on or about April 15, 1981, with a scheduled restart date of July 25, 1981.

This re-fueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, the final fix on the sparger modification, power supply on LPCI modification, and torus modifications if all approvals are received.

There are 764 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 550 spent 7 x 7 fuel assemblies, five 8 x 8 fuel assemblies, one 8 x 8 R fuel assemblies, and 20 new P

8 x 8 R assemblies.

Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 1152 assemblies.

Unit 2 Unit 2 is scheduled for its third refueling beginning on or about September 1,

1980, with a scheduled restart date of October 11, 1980.

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

Li'censing 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, and power supply on LPCI modification.

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.

With present capacity,

Refuelin Information (Continued)

May 1980 Unit 2 (Continued) the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Unit 3 Unit 3 is scheduled for its third refueling beginning on or about October 17, 1980, with a scheduled restart date of November 25, 1980.

This EOC-3 refueling, involves loading additional 8 x 8 R (retrofit) assemblies into the core, and power supply on LPCX modification.

There are 764 fuel assemblies presently in the reactor vessel.

There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool.

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

With present

capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Si nificant 0 erational Events Unit 1 Date Time Event 5/01/80 0001 Reactor thermal power at 99%,

maximum flow (rod limited) sequence "A"

5/02/80 2045 2359 Reduced thermal power from 99% to 95% due to EHC high vibration Reduced thermal power from 95% to 80% for turbine C.V.

test and SI's 5/03/80 0119 0230 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 95%, holding due to EHC high vibration 5/05/80 1016 1402 5/06/80 0520 Commenced power ascension from 95% thermal power Reactor thermal power at 99%, maximum flow (rod limited)

Reactor scram No.

124

'rom 99% thermal power on (2).

generator load rejection, No.

6 intermediate valve closed while testing No.

5 intermediate valve 5/07/80 0009 0345 0522 0546 1239 1535 1725 2002 2018 Commenced rod withdrawal Reactor critical No.

144 sequence "A"

Rolled T/G Synchronized generato~

commenced power ascension Reactor scram No.

125 from 41% thermal power, turbine trip when fuse blew in "A" feedwater in-verter and "B" feedwater high level tripped turbine and the reactor scrammed Commenced rod withdrawal Reactor critical No.

145 sequence "A"

Rolled T/G Synchronized generator, commenced power ascension 5/08/80 0300 0530 Commenced PCIOHR from 55% thermal power Reactor thermal power at 72%, holding remote "B" reactor feed pump for maintenance to flow indicator 5/09/80 0450 2300 "B" reactor feed pump maintenance completed and pump placed in service, commenced power ascension Reactor thermal power at 77%, holding for maintenance to "C" condensate booster pump 5/11/80 0133 0215 "C" condensate booster pump maintenance completed commenced power ascension Commenced PCIORM from 90% thermal power

Si nificant 0 erational Events Unit 1 Date Time Event 5/11/80 2300 5/13/80 1648 1930 Reactor thermal power at 98% flow limited Commenced reducing thermal power from 98% due to high EHC vibration Reactor thermal power at 90%, holding for high EHC vibration 5/15/80 0640 0700 1315 Commenced power ascension Commenced PCIOMR from 95% thermal power Reduced thermal power from 98% to 95% due to high EHC vibration 5/16/80 1445 1500 Commenced power ascension Reactor thermal power at 99%, holding due to high EHC vibration 5/17/80 0339 0415 1500 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 Reactor thermal power at 99%, holding due to high EHC vibration 5/19/80 1426 Reduced thermal power from 99% to 95% due to high ECH vibration 5/21/80 0730 0950 Commenced power ascension from 95% thermal power Reactor thermal power at 99%, holding due to high EHC vibration 5/22/80 1500 Reactor thermal power at 99%, holding due to high EHC vibration 5/23/80 2107 2152 2209 2319 2323 Reduced thermal power from 99% to 45% for control rod sequence exchange Removed "A" recirculation pump M. G. set from service for brush replacement Reactor thermal power at 45%,

commenced control rod se-quence exchange from "A" to "B" "A" recirculation pump M. G. set brush replacement com-pleted and pump placed in service "B" recirculation pump M. G.. set removed from service.

for brush replacement 5/24/80 0130 0330 Control rod sequence exchange completed holding for brush replacement on "B" recirculation pump M. G. set "B" recirculation pump M. G. set brush replacement com-pleted and pump placed in service, commenced power as-cension

Si nificant 0 erational Events Unit 1 Date Time Event 5/25/80 1405 5/27/80 0845 2001 Commenced PCIOMR from 70% thermal power Reactor thermal power at 98%, holding due to EHC high vibration (1)

Reactor scram No.

126 from 98% thermal power on gen-erator load reject while replacing a PR block in main transformer circuitry creating a differential and load rej ection 5/28/80 0109 0445 0625 0642 1900 Commenced rod withdrawal Reactor critical No.

146 sequence Rolled T/G Synchronized generator, commenced Commenced PCIOMR from 71% thermal flilt power ascension power 5/30/80 0030 5/31/80 2400 Reactor thermal power at 97%,

EHC vibration limited Reactor thermal power at 97%,

EHC vibration limited

Date Time Si nificant 0 erational Events Unit 2 Event 5/01/80 0001 2206 Reactor thermal power at 98%,

CPR limited sequence "A"

Commenced reducing thermal power for shutdown due to steam leak in moisture separator room 5/02/80 0050 0605 1315 2036 2102 Reactor scram No.

98 (manual),

from 35% thermal power to accommodate repairs to steam leak Steam leak fixed, commenced rod withdrawal Reactor critical No.

109 sequence "B"

Rolled T/G Synchronized generator, commenced power ascension 5/03/80 0700 1830 1910 Reactor thermal power at 65% holding No.

1 control valve not open Commenced reducing thermal power for shutdown to correct No.

1 control valve problems Reactor scram No.

99 (manual) from 35% thermal power to accommodate control valve repairs 5/04/80 0455 0624 0938 0957 1900 No.

1 control valve fixed, commenced rod withdrawal Reactor critical No.

110 sequence "A"

Rolled T/G Synchronized generator, commenced power ascension "Commenced PCIOMR from 70% thermal power 5/05/80 2330 5/09/80 2225 Reactor thermal power at 97%,

maximum flow Reduced thermal power from 97% to 60% for control rod pattern adjustment 5/10/80 0330 Control rod pattern adjustment completed commenced PCIOMR from 60% thermal power 5/12/80 0320 5/16/80 1805 1840 2135 2330 Reactor thermal power at 98%, maximum flow Commenced decreasing thermal power for shutdown due to EHC leak (No.

3 servo valve)

Reactor scram No.

100 (manual),

from 35% thermal power to accommodate EHC maintenance EHC maintenance completed, commenced rod withdrawal Reactor critical No.

111 sequence "A"

5/17/80 0301 0327 5/18/80 1440 5/19/80 0700 1840 Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 92% thermal power Reactor thermal power at 99%,

maximum flow Reduced thermal power from 99% to 90% for removal of "C" string high pressure heaters from service, due to FCV 6-84 flange leak

10 Date Time Si nificant 0 erational Events Unit 2 Event 5/20/80 0450 0530 2055 "C" string high pressure heaters (leak) maintenance completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at 99%,

maximum flow 5/24/80 0015 0220 1245 1500 Reduced thermal power from 99% to 80% for turbine C. V. tests and SI's Turbine C. V. tests and SI's completed Commenced PCIOMR from 95% thermal power Reactor thermal power at 99%,

maximum flow 5/27/80 0736 1443 1525 1630 1930 Reduced thermal power from 99% to 90% for removal of "C" string high pressure heaters from service for maintenance (leaks)

Maintenance to "C" string high pressures completed and heaters placed in service Commenced power ascension from 90% thermal power Commenced PCIOMR from 95% thermal power Reactor thermal power at 99%,

maximum flow 5/31/80 2400 Reactor thermal power at 99%, maximum flow

Date Time Si nificant 0 erational Events Unit 3 Event 5/01/80 0001 Reactor thermal power at 99%,

maximum flow (rod limited)

Sequence "A"

5/02/80 0700 5/03/80 0725 1440 1600 Reactor thermal power at 99%, maximum flow (rod limited)

Reduced thermal power from 98% to 50%, tachometer main-tenance on "B" recirculation pump "B" recirculation pump tachometer maintenance completed and pump placed in service, commenced power ascension Commenced PCIOMR from 62% thermal power 5/06/80 0030 5/09/80 2330 Reactor thermal power at 99%,

maximum flow (rod limited)

Reduced thermal power from 99% to 85% for turbine C. V.

tests and SI's 5/1O/SO 0200 0700 Turbine C. V. tests and SI's completed, commenced PCI(MR from 85% thermal power Reactor thermal power at 99%,

maximum flow 5/15/so o7oo 0815 1800 2027 2229 2245 Reduced thermal power from 99% to 70% to perform SI 4.2.A-3 (reactor low y~ter level)

Reactor scram No.

82

, load reject due to generator field ground Commenced rod withdrawal Reactor critical No.

92 sequence "A"

Rolled T/G Synchronized generator, commenced power ascension 5/16/80 0930 5/18/80 1500 2150 Commenced PCIOMR from 65% thermal power Reactor thermal power at 98%, (rod limited)

Reduced thermal power from 98% to 55% for control rod pattern adjustment 5/19/80 0005 1800 Control rod pattern adjustment completed, commenced power ascension Commenced PCIOMR from 85% thermal power 5/20/80 2300 5/21/80 1348 1944 2205 Reactor thermal power at 99%,

(rod limited)

Reactor scram No.

83 from 99% thermal power while (2) testing of main steam line high flow switches per instruction 4.2.A.7 Commenced rod withdrawal Reactor critical No.

93 sequence "A"

5/22/80 0031 0051 1630 Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 75% thermal power

Si nificant 0 erational Events Unit 3 Date Time Event 5/23/80 2300 5/24/80 2125 2235 2335 Reactor thermal power at 99%,

(rod limited)

Commenced reducing thermal power for control rod pattern adjustment Reactor thermal power at 55%, holding for control rod pattern adjustment Removed "A" recirculation pump M.G. set from service for brush replacement 5/25/80 0245 0252 0310 0415 0430 1315-1830 "A" recirculation pump M.G. set brush replacement com-

.pleted and pump placed in service Removed "B" recirculation pump M.G. set from service for brush replacement Control rod pattern adjustment completed holding for brush replacement on "B" recirculation pump M.G. set "B" recirculation pump M.G. set brush replacement and pump placed in service, commenced power ascension Reactor thermal power at 68%, holding due to "C" main steam line isolation Commenced power ascension Commenced PCIOMR from 70% thermal power 5/27/80 0030 5/30/80 2200 Reactor thermal power at 99%,

(rod limited)

Reduced thermal power from 99% to 50% for control rod sequence exchange from "A" to "B"

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5/31/80 0815 2400 Control rod'equence exchange completed, commenced power ascension Reactor thermal power at 84%, power ascension in progress (1)

(2)

Personnel Error Equipment malfunction

13 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

UNIT DATE 5-1-80 COMPLETED BY TELEPHONE 205-729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL (il(We-Net)

I 1064 DAY AVERAGE DAILYPOWER LEVEL (MWe iVet) 24 17 4

10 13 14 IS 16 1063 750 835 1014 1071 1076 1078 1077 1070 1071 1083 1072 1072 358 703 18 19 20 21 22 23 24 25 26 27 28 29 30 31 999 832 1033 607 666 974 1023 685 957 1071 1064 1082 1027 780 INSTRUCTIONS Qn this format, list the average daily unit power level in ilDVe.i/et for each day in the reporting month. Compute to the nearest whole megawatt.

(')(77)

14 AVERAGE DAlLYUNITPOWER LEVEL

'I DOCKET NO.

DATE COilIPLETED BY Browns Ferry-1 5-1-80 Don Green TELEPHONE 205-729-6846 DAY AVERAGE DAlLYPOWER LEVEL (i%IWe-Net)

DAY AVERAGE DAlLYPOWER LEVEL (iHWe-Net) 17 1060 4

10 12 13 15 16 1054 1014 1026 1037 228 189 713 799 790 1008 1042 1012 968 1005 1047 18 19 20 21 22 23 25 26 27 28 29 30 31 1026 1042 1023 1040 1067 988 558 679 879 859 908 1052 1031 INSTRUCTIONS On this format, list the average daily unit power level in illWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9j77)

15 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

DATE Browns Ferry-2 COMPLETED BY Don Green TELEPHOiNE MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1 0

DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 560

'7 4

10 12 13 15

-16 38 503 384 954 1043 1047 1043 1027 732'23 1064 1066 1061 1068 828 18 19 20 21 22 23 24 25 26 27 28 29 30 31 913 1043 1038 1060 1086 1059 1027 1070 1058

,1023 1055 1044 1039 1034 INSTRUCTIONS On this format, list the average daily unit power level in MIVe.Net for each day in the reporting n\\onth. Compute to the nearest whole megawatt.

(')(77)

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16 OPERATING STATUS OPERATING DATAREPORT DOCKET NO

~0-2 DATE 6-1-80 CO41IPLETED BY Green TELEPHONE 846 Notes Browns Ferrv Unit 1

2. Reporting Period:

3. Licensed Thermal Power (41IWt):

4. Nameplate Rating (Gross 49IWe):

5. Design Electrical Rating (Net 4%We):

6. Maximum Dependable Capacity (Gross 41OVe):

7. Ifavimum De endableCa acit Net MWe:

p p

y(

)

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

N A

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

IO. Reasons For Restrictions. IfAny:

This Month Yr:to-Date Cumuhtive

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

~

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvaihbilityFactor

21. Unit Capacity Factor (Using 44IDC Net)

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 41fonths 744 647 51 145 708.08 35.92 701.23 0

1531.68 283.85 1428.60 0

29808.96 4973.

29,041.33 0

2,075,263 3,816,795 77,953,288 25 771 850 663,602 94.3.

94.3

83. 8

83. 8 5.7 1,213,207

39. 2

39. 2

31. 2

31. 2 18.8 25,015,175 56.8

56. 8.

45.9 45.9 32.4 (Type, Date, and Duration of Each):

680 430 2 253 390

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

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

Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY COMMERCIALOPERATION

~I

~ 3 j ~

~,q

~,

> ~ M a i ' i." (9/77)

17 OPERATING DATAREPORT DOCKET NO.

50-260 DATE ~E}

COtlfPLETED BY 2'~~

TELEPHONE ~~8-6846 OPERATING STATUS Notes Browns Ferr finest 2

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross tlfWe):

1152

5. Design Electrical Rating (Net MWe):

6. tlfaximum Dependable Capacity (Gross tbfWe):

'um De e dable Ca acit Net idWe:

1098. 4 1065 7..faxm p n p

y(

)

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

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

,"10. Reasons For Restrictions. IfAny r

This Month Yr.-to-Date Cumulative 744 3 647

- 715.52 28.48

-.11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 3 146.60

13. Reactor Reserve Shutdown Hours

14. Hours Geherator On.Line

15. Unit Re~rve Shutdown flours 0

0

16. Gross Thermal Energy Generated (MWH) 2 120 551 8 781g400 ty. Gross Eteetrieal Energy Generated (ittyH)

~y>> g>O 2 936 690

18. Net Electrical Energy Genersated (MWH)

19. Unit Service Factor

94. 1

84. 1

20. Unit'vailabilityFactor

94. 1

84. 1

21. Unit Capacity Factor (Using tlfDC Net)

87. 6 73.6

22. Unit Capacity Factor (Using DER Net) 87.6 73.6

23. Unit Forced Outage Rate 59 '59

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

46'0 6

27 631.08

~

12,275.34 0

74 936 400 24 886 758 24 189 526 8.0 58.0 49.3 49.3 35.0

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

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

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COtlfMERCIAL OPER ATION

18 OPERATING DATAREPORT OPERATliVG STATUS DOCKET NO.

50-296 DATE 6-1-80 COi'IPLETED BY ~~~e TELEPHONE ~~2-846 Notes

l. Unit Name:

Browns Ferr

- Unit 3

2. Reporting Period: ~

3. Licensed Thermal Power (ilOVt):

4. Nameplate Rating (Gross iaaf tVe);

1152

5. Design Electrical Rating (Net MWe):

6. hfaximum Dependable Capacity (Gross AIWe):

1098-4 um De endableCa acit Net iiOVe:

7.,faxmi p

p y (

)

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

N/A

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

10. Reasons For Restrictions, IfAny:

This Month Yr.-to Date 3 647 744

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown IIours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MPH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using i9ifDC Net) 2"". Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over iVext 6 Months (

Refuel Outa e October 1980 3214.95 20.48 3186.38 723.52 20.48 718.45 0

0 2 139 84 9 947 427 3 356 390 718 180 700 399.

3,272,840 87.4 6.6 84.3 88.4 84.3 12.6 3.4 Type, Date,and Duration of Each):

Cumulative 28 511 22122.50 1678.79 21624.'19 0'3 055 293 20 758 970 20,160,613 75.8

'6.4 66.4 9.6

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

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

Forecast Achieved INITIAL CRITICALIT Y INITIALELECTRICITY COMMERCIAL OPER ATIOiI (9/77)

UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNIl NAhIE DATE COhIPLETED BY TELEPIlONE 50-259 Browns Ferr 1

5-1-80 205-729-6846 No.

Date m ~lY Licenscc Eve>>l Report 4 4J 0

D Q

Cause k. Corrective Actlotl to Prevent Rccurrcnce 122 800506 24.44 B

Generator load rejection (No.

6 intermediate valve closed while testin No.

5 intermediate valve.

123 800507 7.65 A

Turbine trip due to a blown fuse in "A" feedwater inverter and "B" feedwater hi h level si nal.

124 800523 Derated for control rod sequence exchan e.

125 800527 10.68 Generator load rejection while re-placing a PK block in ma$ n trans-former creating a differhntial and load re ection

( ersonnel error I

F: Forced Scheduled

"~ '- (9/77)

~

t Reason:

A-Equipment Failure (Explain)

B.hlaintenance or Test C-Refueling D.Regulatory Restriction E.Operator Training 8; Liccnsc Exa>>tination F-Administrative G-Operational Error (Explain)'I Other (Explain) hIethod:

I -hlanual 2-h(anual Scram.

3-Aulotnatic Scram.

4.Other (Explain) 4 Exhibit G - Instructions for Preparation of Data Entry Sheets I'or l.iccnsec Evc>>t Rcport (I.ER) File (NURFG-OI 6I )

5 Exl)ibit I - Sr>>>>c Source

UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT hiON Ill~Ha DOCKET NO.

UNITNAhlE DATE COhIPLETED BY TELEPI!ONE 50-260 Browns Ferr 2

o Cree 205-729-6846 Date I

IA r$

CP Liccnscc Event Rcport ¹ CO CP 41 v) G 4J~

OC Qiu 0

Cause & Corrective Aclion to Prevent Rccurrcnce 136 800502 F

20.21 A

To accommodate repairs to steam leak in steam tunnel.

137 800503 F

14.78 A

To accommodate repairs to No.

1 control valve.

138 800509 Derated for control rod pattern ad ustment.

139 800516 8.78 A

To accommodate repairs to EHC leak No.

3 servo valve I

F: Forced S: Scheduled (9/77) - i

'i

~

Reason:

A.Equipment Failure (Explain)

B-hlaintenance or Test C-Refueling D.Regulatory Restriction E.Operator Training& Liccnsc Exanlination

, F-Administrative

~

G-Opcfattunal Error (Explain)

~

II-Other (Explain)

Method:

I -hlanual 2.hlanual Scram.

3-Automatic Scram.

4.0llter (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets fur l.iccnsee Event Report (I.L'R) File (NUREG-OI6I)

Exhibit I - Sante Source

UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNITNAhlE DATE COhlPLETED IIY TELEPIIONE 50-296 Browns Ferr 3

5-1-80 205-729-6846 N((.

Date r(

IX(J (P

A J

~ (/I Licenscc Event Report ~

((( 'n IA cn'Cr Cl OQ Q

O Cause &. Corrective A>>lion to Prevent Rccurrcnce 123 800503 Derated for maintenance on "B" recirculation pump.

124 800515 14.50 G

Apparent generator field ground-(personnel error).

125 800518 H

Derated for control rod pattern adjustment.

126

, 800521 11.05 B

Reactor scrammed while performing reactor low water level SI.

127 800524 Derated for control rod pattern adjustment.

128 800530 S

Derated for control rod sequence exchange.,

F: Forced Scheduled

(()/77).

Reason:

A-Equipment Failure (Explain)

B-hlaintenance or Test C-Refueling D Regulatory Restriction E.Operator Training &. Ucensc Examination F.Adnlinist ra tive G-Operational Error (Explain)'

II Other (Explain) hlethod:

I-hlanual 2-hlanual Scram.

3-Autonlatic Scraln.

4.Other (Explain)

Exhibit G - Instructions for Preparation of Data Entry Shc>>ts for l.icensee Event Report (I.l(R) Fil>> (NUREG-OI 6 I )

Exhibit I - Sa(n>> Source

CSSC 1:. UIPMFNT BR011NS,FERRY NUCLEAR PIANT UNIT 2

11ECHANICAL MAINTENANCE SUM 1ARY For the Month of May

] 9 80 DATE SYSl~rii COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 5/15/8 HPCI Instrument line FE 73-33 Instrument lin sags and clamp missing None Clamps missing Inoperable instrument line Replaced and tightened clamps TR 103607

CSSC E UIPHENT WINS FERRY NUCLEAR PLANT UNIT ffECflANICALMAINTENANCE SUMfARY For the Month of Ma/

19 80 DATE SYS'1i;if.

COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF ffAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 5/15/8 FPC 3A pump Packing leak None Packing leak Packing leak Tightened packing TR 182948

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 5KQIANICAL MAINTENANCE

SUMMARY

For the Month of DATE SYS'is'.i1 COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 5/20/8 HPCI Steam supply drain trap Steam blowing None Gasket leak Bonnet gasket 'leak Replaced bonnet gasket TR 103606 5/6/80 HPCI PCV 73-43 Bonnet leak None Bonnet leak Bonnet leak Tightened bonnet bolts TR 165401

CSSC E UIEHENT BROli'HS FERRY NUCLEAR PLANT UNIT 1

ELECTRICAL HAINTENANCE SIMfARY 19 80 D"te 4/30/80 System RHRSW Component 1-B RHRSW Hotor Nature of Haintenance Balance motor after taking initial vibra-tion readings check vibratio after balancin E

ecton 'ae Operation of The Reactor Cause of Halfunction Hotor out of balance.

Results of Halfunction Rendered 1-B RHRSW pump inoperable.

Action Taken To Preclude Rocurrence RE-install D3 RHRSW motor.

Checked ok.

TR8 146733 I5/03/80 Core Spray HCV-75-8 Fuses blowing causing loss of indicating lights.

NONE HCV-75-3 wire shorted to side of switch box.

Lose light indica-

. tions on panel 9-3.

Repaired short in switch box.

Indi-cating lights check ok.

TRP 166327 5/06/80 Radiatio monitoring FCV-1-90-257 FCV-1-90-257 NONE will open but will not make up limit switcl Limit switches burned out FCV-1-90-257 not operating properly.

Replaced bad limit u switched.

Checked ok.

TRf/ 136942 LER No. 259/8040

HROHHR PERRY HUCLEAR PLRHT CHIT ELECTRICAL MAINTENANCE SIMfARY Eor the Month of 19 80 D"te 4/30/80 System RHRSW Component D-3 RHRSW motor Nature of Maintenance Pull D-3 RHRSW motor for re-pair E

ecton

'a e

Operation of The Reactor NONE Cause of Malfunction otor out of balance.

Results of Malfunction Rendered D-3 RHRSW pump inoperable.

Action Taken To Preclude Recurrence Sent D-3 RHRSW motor to service shop for repair.

After repair re-installed motor.

Checked ok.

TR8 146733, 166926 5/12/80 RCIC EGM Box RCIC operation indicated loss of speed control Unit placed in limiting condi-tion for opera-tion.

R9 Diode shorted in EGM box.

Loss of speed control.

Replaced EGM box.

Checked ok per EMI 37.

TR8 156718 LER 296/8014.

5/25/80 Main Steam Relay 16-AK16 Repair relay 16-AK16 panel 9-43.

NONE ontacts arcing nd coil heating po Caused relay 16-AK16 Replaced relay.

to malfunction.

Checked ok.

TR8 143573

CSSC E UIPMENT UROtRIE FERRY NUCLEAR PLANT UNIT I 2

& 3 INSTRAKNT MAINTENANCE SUI &1ARY FOR THE MONTH OF May 19 8O Unit 1 5-9 SYSTEM Corespray COMPONENT FT-75-49 NATURE OF MAINTENANCE Calibrate EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION Instrument Drift RESULTS OF MALFUNCTION Indicated Flow with System Off ACTION.;.TAKEN TO PRECLUDE RECURRENCE None Unit 2 5-8 5 13 RCIC Primary Con tainment FT-71-lA PT-64-138 PDI-64-137 PDI-64-138 Pds-64-137A B

Calibrate Calibrate None None Loss of-Mater Leg Instrument Drift Indicated Flow with System Off Disagreement Between Indicators None None Unit 3 5-.12 Radiation Monitor RM-90-249 Repair None Faulty Ratemeter Card Failed to Calibrate None 5-15 Feedwater LIS-3-56A 6 B

Repair None Faulty Switches Failed Surveillance Test None 20 5-28 Standby Liquid Con-trol Radwaste LI-53-1B FT-77-16 Maintenance Replace None None Partial Clog of Sensing Line Faulty Transmit te Indication did not Agree with Measure

'Probe Transmitter Zero Shift with Pressure None None

28 OUTAGE SlBKARY May 1980 The major emphasis during this reporting period has been on completion of reactor building overhead crane repair, completion of the Unit 3 condenser pull out area radwaste storage zone and work required to effect completion of the security modifications in order to meet the June 30,

1980, NRC commitment dead-line.

The final overhead crane wheel bearing inspections are now in progress and should be complete in sufficient time to allow fuel receipt around the middle of June.

All work associated with the Unit 3 condenser pull out area radwaste storage zone has been completed, with the exception of painting of floor grating and sump coating.

Both of these activities are in progress and will be completed the early part of June.

Work on the security modifications is continuing with door multiplexers now being placed in service.

The commitment work associated with security should finish on or near June 30.

Several other non-outage modifications are in varying stages of completion.

Included in these modifications are installation of safety rails on the condensate storage tanks; installation of guard rails on top of the reactor building elevators; installation of cages around the ladders on the microwave towers; modifications to the RHRSW check valves; installation of H2 and 02 panels and piping for the new Hayes Republic analyzers; installation of snubbers and check valves on plant air compressors; construction of an ambulance storage building; sewage treatment facility modifications; east portal modifications; hypochlorite modifications; condensate storage tank modifications and construction of an outage fabrication shops

29 OUTAGE

SUMMARY

(Continued)

May 1980 Work is progressing on schedule on NRC Bulletin 79-14 (hanger inspections) with an estimated 60 percent overall completion.

Anchor repairs associated with NRC Bulletin 79-02 stands at 26 percent complete with 1000 of the iden-tified 3916 anchor repairs being completed.

Research associated with NRC Bulletin 80-08 (fluted head penetration inspection) is essentially complete with a memorandum being prepared stating results of this inspection.