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 V 0503

TABLE OF CONTENTS Operations Summary ~ ~ ~ 1 Refueling Information ~ ~ ~ 4 Significant Operational Events ~ ~ ~ 6 Average Daily Unit Power Level . ~ ~ ~ 13 Operating Data Reports ~ ~ ~ ~ ~ ~ ~ ~ 16 Unit Shutdowns and Power Reductions. ~ ~ e 19 Plant Maintenance ~ ~ ~ 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 Unit 1 Unit 2 Unit 3 Shell at water line 0.00464 0.00343 0.00295 Feedwater nozzle 0.21997 0.14835 0.10950 Closure studs 0. 19099 0.12106 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 Reduced thermal power from 99% to 95% due to EHC high vibration 2359 Reduced thermal power from 95% to 80% for turbine C.V.

test and SI's 5/03/80 0119 Turbine C.V. tests and SI's completed, commenced power ascension 0230 Reactor thermal power at 95%, holding due to EHC high vibration 5/05/80 1016 Commenced power ascension from 95% thermal power 1402 Reactor thermal power at 99%, maximum flow (rod limited) 5/06/80 0520 Reactor scram No. 124 (2).'rom 99% thermal power on generator load rejection, No. 6 intermediate valve closed while testing No. 5 intermediate valve 5/07/80 0009 Commenced rod withdrawal 0345 Reactor critical No. 144 sequence "A" 0522 Rolled T/G 0546 Synchronized generato~ commenced power ascension 1239 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 1535 Commenced rod withdrawal 1725 Reactor critical No. 145 sequence "A" 2002 Rolled T/G 2018 Synchronized generator, commenced power ascension 5/08/80 0300 Commenced PCIOHR from 55% thermal power 0530 Reactor thermal power at 72%, holding remote "B" reactor feed pump for maintenance to flow indicator 5/09/80 0450 "B" reactor feed pump maintenance completed and pump placed in service, commenced power ascension 2300 Reactor thermal power at 77%, holding for maintenance to "C" condensate booster pump 5/11/80 0133 "C" condensate booster pump maintenance completed commenced power ascension 0215 Commenced PCIORM from 90% thermal power

Si nificant 0 erational Events Unit 1 Date Time Event 5/11/80 2300 Reactor thermal power at 98% flow limited 5/13/80 1648 Commenced reducing thermal power from 98% due to high EHC vibration 1930 Reactor thermal power at 90%, holding for high EHC vibration 5/15/80 0640 Commenced power ascension 0700 Commenced PCIOMR from 95% thermal power 1315 Reduced thermal power from 98% to 95% due to high EHC vibration 5/16/80 1445 Commenced power ascension 1500 Reactor thermal power at 99%, holding due to high EHC vibration 5/17/80 0339 Reduced thermal power from 99% to 80% for turbine C. V.

tests and SI's 0415 Turbine C. V. tests and SI's completed, commenced power ascension 1500 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 Commenced power ascension from 95% thermal power 0950 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 Reduced thermal power from 99% to 45% for control rod sequence exchange 2152 Removed "A" recirculation pump M. G. set from service for brush replacement 2209 Reactor thermal power at 45%, commenced control rod se-quence exchange from "A" to "B" 2319 "A" recirculation pump M. G. set brush replacement com-pleted and pump placed in service 2323 "B" recirculation pump M. G.. set removed from service.

for brush replacement 5/24/80 0130 Control rod sequence exchange completed holding for brush replacement on "B" recirculation pump M. G. set 0330 "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 Commenced PCIOMR from 70% thermal power 5/27/80 0845 Reactor thermal power at 98%, holding due to EHC high vibration 2001 Reactor scram No. 126 (1) 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 Commenced rod withdrawal 0445 Reactor critical No. 146 sequence f lilt 0625 Rolled T/G 0642 Synchronized generator, commenced power ascension 1900 Commenced PCIOMR from 71% thermal power 5/30/80 0030 Reactor thermal power at 97%, EHC vibration limited 5/31/80 2400 Reactor thermal power at 97%, EHC vibration limited

Si nificant 0 erational Events Unit 2 Date Time Event 5/01/80 0001 Reactor thermal power at 98%, CPR limited sequence "A" 2206 Commenced reducing thermal power for shutdown due to steam leak in moisture separator room 5/02/80 0050 Reactor scram No. 98 (manual), from 35% thermal power to accommodate repairs to steam leak 0605 Steam leak fixed, commenced rod withdrawal 1315 Reactor critical No. 109 sequence "B" 2036 Rolled T/G 2102 Synchronized generator, commenced power ascension 5/03/80 0700 Reactor thermal power at 65% holding No. 1 control valve not open 1830 Commenced reducing thermal power for shutdown to correct No. 1 control valve problems 1910 Reactor scram No. 99 (manual) from 35% thermal power to accommodate control valve repairs 5/04/80 0455 No. 1 control valve fixed, commenced rod withdrawal 0624 Reactor critical No. 110 sequence "A" 0938 Rolled T/G 0957 Synchronized generator, commenced power ascension 1900 "Commenced PCIOMR from 70% thermal power 5/05/80 2330 Reactor thermal power at 97%, maximum flow 5/09/80 2225 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 Reactor thermal power at 98%, maximum flow 5/16/80 1805 Commenced decreasing thermal power for shutdown due to EHC leak (No. 3 servo valve) 1840 Reactor scram No. 100 (manual), from 35% thermal power to accommodate EHC maintenance 2135 EHC maintenance completed, commenced rod withdrawal 2330 Reactor critical No. 111 sequence "A" 5/17/80 0301 Rolled T/G 0327 Synchronized generator, commenced power ascension 5/18/80 1440 Commenced PCIOMR from 92% thermal power 5/19/80 0700 Reactor thermal power at 99%, maximum flow 1840 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 Si nificant 0 erational Events Unit 2 Date Time Event 5/20/80 0450 "C" string high pressure heaters (leak) maintenance completed, commenced power ascension 0530 Commenced PCIOMR from 95% thermal power 2055 Reactor thermal power at 99%, maximum flow 5/24/80 0015 Reduced thermal power from 99% to 80% for turbine C. V. tests and SI's 0220 Turbine C. V. tests and SI's completed 1245 Commenced PCIOMR from 95% thermal power 1500 Reactor thermal power at 99%, maximum flow 5/27/80 0736 Reduced thermal power from 99% to 90% for removal of "C" string high pressure heaters from service for maintenance (leaks) 1443 Maintenance to "C" string high pressures completed and heaters placed in service 1525 Commenced power ascension from 90% thermal power 1630 Commenced PCIOMR from 95% thermal power 1930 Reactor thermal power at 99%, maximum flow 5/31/80 2400 Reactor thermal power at 99%, maximum flow

Si nificant 0 erational Events Unit 3 Date Time Event 5/01/80 0001 Reactor thermal power at 99%, maximum flow (rod limited)

Sequence "A" 5/02/80 0700 Reactor thermal power at 99%, maximum flow (rod limited) 5/03/80 0725 Reduced thermal power from 98% to 50%, tachometer main-tenance on "B" recirculation pump 1440 "B" recirculation pump tachometer maintenance completed and pump placed in service, commenced power ascension 1600 Commenced PCIOMR from 62% thermal power 5/06/80 0030 Reactor thermal power at 99%, maximum flow (rod limited) 5/09/80 2330 Reduced thermal power from 99% to 85% for turbine C. V.

tests and SI's 5/1O/SO 0200 Turbine C. V. tests and SI's completed, commenced PCI(MR from 85% thermal power 0700 Reactor thermal power at 99%, maximum flow 5/15/so o7oo Reduced thermal power from 99% to 70% to perform SI 4.2.A-3 (reactor low y~ter level) 0815 Reactor scram No. 82 , load reject due to generator field ground 1800 Commenced rod withdrawal 2027 Reactor critical No. 92 sequence "A" 2229 Rolled T/G 2245 Synchronized generator, commenced power ascension 5/16/80 0930 Commenced PCIOMR from 65% thermal power 5/18/80 1500 Reactor thermal power at 98%, (rod limited) 2150 Reduced thermal power from 98% to 55% for control rod pattern adjustment 5/19/80 0005 Control rod pattern adjustment completed, commenced power ascension 1800 Commenced PCIOMR from 85% thermal power 5/20/80 2300 Reactor thermal power at 99%, (rod limited) 5/21/80 1348 Reactor scram No. 83 (2) from 99% thermal power while testing of main steam line high flow switches per instruction 4.2.A.7 1944 Commenced rod withdrawal 2205 Reactor critical No. 93 sequence "A" 5/22/80 0031 Rolled T/G 0051 Synchronized generator, commenced power ascension 1630 Commenced PCIOMR from 75% thermal power

Si nificant 0 erational Events Unit 3 Date Time Event 5/23/80 2300 Reactor thermal power at 99%, (rod limited) 5/24/80 2125 Commenced reducing thermal power for control rod pattern adjustment 2235 Reactor thermal power at 55%, holding for control rod pattern adjustment 2335 Removed "A" recirculation pump M.G. set from service for brush replacement 5/25/80 0245 "A" recirculation pump M.G. set brush replacement com-

.pleted and pump placed in service 0252 Removed "B" recirculation pump M.G. set from service for brush replacement 0310 Control rod pattern adjustment completed holding for brush replacement on "B" recirculation pump M.G. set 0415 "B" recirculation pump M.G. set brush replacement and pump placed in service, commenced power ascension 0430 Reactor thermal power at 68%, holding due to "C" main steam line isolation 1315- Commenced power ascension 1830 Commenced PCIOMR from 70% thermal power 5/27/80 0030 Reactor thermal power at 99%, (rod limited) 5/30/80 2200 Reduced thermal power from 99% to 50% for control rod sequence exchange from "A" to "B"

~ 5/31/80 0815 Control rod'equence exchange completed, commenced power ascension 2400 Reactor thermal power at 84%, power ascension in progress (1) Personnel Error (2) Equipment malfunction

13 AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

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

I 1064 17 24 1063 18 999 750 19 832 4 835 20 1033 1014 607 21 1071 666 22 1076 23 974 1078 1023 24 1077 25 685 10 1070 957 26 1071 27 1071 1083 1064 28 13 1072 29 1082 1072 1027 14 30 IS 358 31 780 16 703 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 DAlLYUNIT POWER LEVEL

'I DOCKET NO.

Browns Ferry-1 DATE 5-1-80 COilIPLETED BY Don Green TELEPHONE 205-729-6846 DAY AVERAGE DAlLYPOWER LEVEL DAY AVERAGE DAlLYPOWER LEVEL (i%IWe-Net) (iHWe-Net) 17 1060 1054 18 1026 1014 19 1042 1026 1023 4 20 1037 21 1040 228 1067 22 189 988 23 713 558 799 679 25 10 790 26 879 1008 859 27 12 1042 28 1012 908 13 29 968 1052 30 1005 1031 15 31 16 1047 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.

(9 j77)

15 AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

Browns Ferry-2 DATE COMPLETED BY Don Green TELEPHOiNE MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net) 1 0 560 '7 38 18 913 503 19 1043 4 384 1038 20 954 21 1060 1043 22 1086 1047 1059 23 1043 24 1027 1027 25 1070 10 732'23 26 1058 27 ,1023 1064 1055 12 28 1066 1044 13 29 1061 1039 30 1068 1034 15 31

-16 828 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)

~, ~

16 OPERATING DATA REPORT DOCKET NO ~0-2 DATE 6-1-80 CO41IPLETED BY Green 846 TELEPHONE OPERATING STATUS Browns Ferrv Unit 1 Notes

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 p endableCa p acit y(Net MWe: )

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

N A

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

IO. Reasons For Restrictions. If Any:

This Month Yr:to-Date Cumuhtive

'

11. Hours In Reporting Period 744 647 51 145

12. Number Of Hours Reactor Was Critical 708.08 1531.68 29808.96

13. Reactor Reserve Shutdown Hours 35.92 283.85 4973.

14. Hours Generator On-Line 701.23 1428.60 29,041.33

~

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2,075,263 3,816,795 77,953,288

17. Gross Electrical Energy Generated (MWH) 680 430 2 253 390 25 771 850

18. Net Electrical Energy Generated (MWH) 663,602 1,213,207 25,015,175

19. Unit Service Factor 94.3. 39. 2 56.8

20. Unit Avaihbility Factor 94.3 39. 2 56. 8.

21. Unit Capacity Factor (Using 44IDC Net) 83. 8 31. 2 45.9

22. Unit Capacity Factor (Using DER Net) 83. 8 31. 2 45.9

23. Unit Forced Outage Rate 5.7 18.8 32.4

24. Shutdowns Scheduled Over Next 6 41fonths (Type, Date, and Duration of 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 INITIALCRITICALITY INITIAL ELECTRICITY

~ I COMMERCIAL OPERATION

~ 3 j ~ ~ ,q ~ ,

>~ M

' a i' i." (9/77)

17 OPERATING DATA REPORT 50-260 DOCKET NO.

DATE COtlfPLETED BY

~E}

2'~~

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

2. Reporting Period:

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross tlfWe):

5. Design Electrical Rating (Net MWe):

6. tlfaximum Dependable Capacity (Gross tbfWe): 1098. 4 7..faxm'um De p e n dable Ca p acit y(Net idWe:) 1065

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 tlfWe):

,"10. Reasons For Restrictions. If Any r

This Month Yr.-to-Date Cumulative

-.11. Hours In Reporting Period 744 3 647 46'0 6

12. Number Of Hours Reactor Was Critical

- 715.52 3 146.60 27 631.08 Reactor Reserve Shutdown Hours 28.48 ~ 12,275.34 13.

14. Hours Geherator On. Line

15. Unit Re~rve Shutdown flours 0 0 0 2 120 551 8 781g400 74 936 400

16. Gross Thermal Energy Generated (MWH) ty. Gross Eteetrieal Energy Generated (ittyH) ~y>> g>O 2 936 690 24 886 758 24 189 526

18. Net Electrical Energy Genersated (MWH)

19. Unit Service Factor 94. 1 84. 1 8.0 Unit'vailability Factor 94. 1 84. 1 58.0 .

'59 20.

21. Unit Capacity Factor (Using tlfDC Net) 87. 6 73.6 49.3

22. Unit Capacity Factor (Using DER Net) 87.6 73.6 49.3

23. Unit Forced Outage Rate 59 35.0

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:

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COtlfM ERCIA L OPER ATION

18 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 6-1-80 COi'IPLETED BY TELEPHONE

~~~e

~~2- 846 OPERATliVG STATUS

l. Unit Name: Browns Ferr - Unit 3 Notes

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 7.,faxmi um De p endableCa p acit y (Net iiOVe:)

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

N/A

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

10. Reasons For Restrictions, If Any:

This Month Yr.-to Date Cumulative

11. Hours In Reporting Period 744 3 647 28 511

12. Number Of Hours Reactor Was Critical 723.52 3214.95 22122.50

13. Reactor Reserve Shutdown Hours 20.48 20.48 1678.79

14. Hours Generator On-Line 718.45 3186.38 21624.'19

15. Unit Reserve Shutdown IIours 0 0 0'3

16. Gross Thermal Energy Generated (MWH) 2 139 84 9 947 427 055 293

17. Gross Electrical Energy Generated (MWH) 718 180 3 356 390 20 758 970

18. Net Electrical Energy Generated (MPH) 700 399. 3,272,840 20,160,613

19. Unit Service Factor

20. Unit Availability Factor 6.6 87.4 75.8

21. Unit Capacity Factor (Using i9ifDC Net) 88.4 84.3 '6.4 2"". Unit Capacity Factor (Using DER Net) 84.3 66.4

23. Unit Forced Outage Rate 3.4 12.6 9.6

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

Refuel Outa e October 1980

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

26. Units ln Test Status (Prior,to Commercial Operation): Forecast Achieved IN ITI A L CRITICALIT Y INITIALELECTRICITY COMM ERCIA L OPER ATIOi I (9/77)

UNIT SIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-259 UNIl NAhIE Browns Ferr 1 DATE 5-1-80 COhIPLETED BY TELEPI lONE 205-729-6846 4J Licenscc Cause k. Corrective No. Date 0 D m ~lY Eve>>l Q Actlotl to Report 4 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

4 F: Forced ':

Reason: hIethod: Exhibit G - Instructions Scheduled A-Equipment Failure (Explain) I -hlanual for Preparation of Data B.hlaintenance or Test 2-h(anual Scram. Entry Sheets I'or l.iccnsec C-Refueling 3-Aulotnatic Scram. Evc>>t Rcport (I.ER) File (NURFG-D.Regulatory Restriction 4.Other (Explain) OI 6I )

E.Operator Training 8; Liccnsc Exa>>tination F-Administrative 5 G-Operational Error (Explain)'I Exl)ibit I - Sr>>>>c Source

"~ '-

(9/77) ~

t Other (Explain)

DOCKET NO. 50-260 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAhl E Browns Ferr 2 DATE o Cree REPORT hiON Ill ~Ha COhIPLETED BY TELEPI!ONE 205-729-6846 I 4J~

Liccnscc CO41 C Cause & Corrective CP O Date IA r$

CP Event Rcport ¹ v) G iu Q

0 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 Reason: Method: Exhibit G - Instructions S: Scheduled A.Equipment Failure (Explain) I -hlanual for Preparation of Data B-hlaintenance or Test 2.hlanual Scram. Entry Sheets fur l.iccnsee C-Refueling 3-Automatic Scram. Event Report (I.L'R) File (NUREG-D.Regulatory Restriction 4.0llter (Explain) OI6I)

E.Operator Training& Liccnsc Exanlination

,

F-Administrative

~

G-Opcfattunal Error (Explain) Exhibit I - Sante Source (9/77) - i ~

I I-Other (Explain)

'i ~

DOCKET NO. 50-296 UNIT SIIUTDOWNS AND POWER REDUCTIONS Browns Ferr 3 UNIT NAhlE DATE 5-1-80 COhlPLETED IIY TELEPIIONE 205-729-6846 (P

r( AJ Cl Lice nscc ((( O Cause &. Corrective N((. Date IX

( Event IA 'n Q Q A>>lion to J

~ (/I Report ~ cn'Cr O 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 Reason: hlethod: Exhibit G - Instructions I-hlanual for Preparation of Data

':

Scheduled A-Equipment Failure (Explain)

B-hlaintenance or Test 2-hlanual Scram. Entry Shc>>ts for l.icensee C-Refueling 3-Autonlatic Scraln. Event Report (I.l(R) Fil>> (NUREG-D Regulatory Restriction 4.Other (Explain) OI 6 I )

E.Operator Training &. Ucensc Examination F.Adnlinist ra tive G-Operational Error (Explain)' Exhibit I - Sa(n>> Source

(()/77) . I I Other (Explain)

BR011NS,FERRY NUCLEAR PIANT UNIT 2 CSSC 1:. UIPMFNT 11ECHANICAL MAINTENANCE SUM 1ARY For the Month of May ] 9 80 EFFECT ON SAFE ACTION TAKEN DATE SYSl~rii COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5/15/8 HPCI Instrument line Instrument lin None Clamps missing Inoperable instrument Replaced and tightened FE 73-33 sags and clamp line clamps missing TR 103607

WINS FERRY NUCLEAR PLANT UNIT CSSC E UIPHENT f fECflANICAL MAINTENANCE SUMfARY For the Month of . Ma/ 19 80 EFFECT ON SAFE ACTION TAKEN DATE SYS'1i;if. COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE ffAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE 5/15/8 FPC 3A pump Packing leak None Packing leak Packing leak Tightened packing TR 182948

'

BROWNS FERRY NUCLEAR PLANT UNIT CSSC E UIPMENT 5KQIANICAL MAINTENANCE

SUMMARY

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

BROli'HS FERRY NUCLEAR PLANT UNIT 1 CSSC E UIEHENT ELECTRICAL HAINTENANCE SIMfARY 19 80 E ecton 'ae Action Taken D"te System Component Nature of Operation of Cause of Results of To Preclude Haintenance The Reactor Halfunction Halfunction Rocurrence 4/30/80 RHRSW 1-B RHRSW Balance motor Hotor out of Rendered 1-B RHRSW RE-install D3 RHRSW Hotor after taking balance. pump inoperable. motor. Checked ok.

initial vibra- TR8 146733 tion readings check vibratio after balancin I5/03/80 Core HCV-75-8 Fuses blowing NONE HCV-75-3 wire Lose light indica- Repaired short in Spray causing loss shorted to side . tions on panel 9-3. switch box. Indi-of indicating of switch box. cating lights check lights. ok. TRP 166327 5/06/80 Radiatio FCV-1-90-257 FCV-1-90-257 NONE Limit switches FCV-1-90-257 not Replaced bad limit u monitoring will open but burned out operating properly. switched. Checked will not make ok. TRf/ 136942 up limit switcl LER No. 259/8040

HROHHR PERRY HUCLEAR PLRHT CHIT ELECTRICAL MAINTENANCE SIMfARY Eor the Month of 19 80 E ecton 'a e Action Taken D"te System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 4/30/80 RHRSW D-3 RHRSW Pull D-3 RHRSW NONE otor out of Rendered D-3 RHRSW Sent D-3 RHRSW motor motor motor for re- balance. pump inoperable. to service shop for pair repair. After repair re-installed motor.

Checked ok.

TR8 146733, 166926 5/12/80 RCIC EGM Box RCIC operation Unit placed in R9 Diode shorted Loss of speed Replaced EGM box.

indicated loss limiting condi- in EGM box. control. Checked ok per EMI of speed tion for opera- 37. TR8 156718 control tion. LER 296/8014.

5/25/80 Main Relay 16-AK16 Repair relay NONE ontacts arcing Caused relay 16-AK16 Replaced relay.

Steam 16-AK16 panel nd coil heating to malfunction. Checked ok.

9-43. po TR8 143573

UROtRIE FERRY NUCLEAR PLANT UNIT I 2 & 3 INSTRAKNT MAINTENANCE SUI &1ARY CSSC E UIPMENT FOR THE MONTH OF May 19 8O NATURE EFFECT ON SAFE CAUSE ACTION.;. TAKEN SYSTEM COMPONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE Unit 1 5-9 Corespray FT-75-49 Calibrate None Instrument Drift Indicated Flow with None System Off Unit 2 5-8 RCIC FT-71-lA Calibrate None Loss of- Mater Leg Indicated Flow with None System Off 5 13 Primary Con PT-64-138 Calibrate None Instrument Drift Disagreement Between None tainment PDI-64-137 Indicators PDI-64-138 Pds-64-137A &

B Unit 3 5-.12 Radiation RM-90-249 Repair None Faulty Ratemeter Failed to Calibrate None Monitor Card 5-15 Feedwater LIS-3-56A 6 B Repair None Faulty Switches Failed Surveillance None Test 20 Standby LI-53-1B Maintenance None Partial Clog of Indication did not None Liquid Con- Sensing Line Agree with Measure trol 'Probe 5-28 Radwaste FT-77-16 Replace None Faulty Transmit te Transmitter Zero None Shift with Pressure

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.