ML18283A404

August 1978 Monthly Operating Report

ML18283A404
Person / Time
Site:	Browns Ferry   (DPR-033, DPR-052, DPR-068)
Issue date:	09/11/1978
From:	Dewease J Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML18283A404 (36)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RID

)

DISTRIBUTION FOR INCOMING MATERIAL 50-25'7/2 2Pg REC:

NRC ORG:

DEWEASE J G

TN VALLEY AUTH DOCDATE: 09/08/~q DATE RCVD: OV/iij' DGCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIV

SUBJECT:

LTR i ENCL i GRWARDItlG SUBJECT FACILITY"S MONTHLY OPERATING REPT FOR TtdE MONTH OF AUGUSTA l978.

."LANT NAME: BROWNS FERRY UNIT i BRGWNS FERRY UNIT 2 BRGWNS FERRY UNIT 3 REVIEWER INITIAL:

XJM DISTRIBUTER INITIAL:

DISTRIBUTION OF Tl<IS MATERIAL IS AS FOLLOWS ANNUAL> SEMI-ANNUAL 5 MONTHLY OPERATING RPTS

>~~W/ENCL AD FOR SYS 0 PROJ~4W/ENCL. RFACTGR SAFETY BR~4W/ENCL EEB~~W/ENCL 'FFLUENT TREAT SYS++W/ENCt LPDR S

ATHENS, AL~>>W/ENCL NATL LA13 GRNL++W/ENCL TERA+4W/ENCL NSIC~~W/ENCL ACRS CAT B++W/i5 ENCL NRC PDR<+W/ENCL MIPC4+W/2 LhlCL DIRECTOR DOR<.>W/ENCL ENGINEERING BR++W/ENCL PLANT SYSTEMS BR++W/ENCL CORE PERFORMANCE BR++W/ENCL DISTRIBUTION:

LTR 4i ENCL 4i ~ IZE: iPi s3P CGNTROI NBR: 782 '?02'?2 -'N-5< 4 4+%44.k%4c 6%+4 4 k M4 %% %%w+%44%% %% THE END %%%%4%%444%4 44 %4 %%+<++ TENNESSEE VALLEY+,Ll<iRQPITY Brcwns Ferry.Nccl'eK ]Ogj itnirgge '4 s Nuclear Regulatory Commission Office of Management Information and Pxogram Control Washington, DC 20555 Gentlemen: Enclosed is the August: 1978'onthly Operating Report for Browns Ferry Nuclear. Plant Units','. 2, and 3. Very truly yours, TENNESSEE VALLEY AUTHORITY'. g/ ,J.,G.. Dewease Plant Superintendent Enclosure CC: Director, Region II Nuclear Regulatory Commission ,Office of Inspection and Enforcement 230 Peachtree

Street, NW Suite 818; Atlanta; GA, 30303,.'(1. copy)

Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, DC 20555.(10'opies) 7824902o2 An Equal Opportunity Employer Ib s TENNESSEE VALLEY AUTHORITY DIVISION OP POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT August 1,."1978' August 31, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 -LICENSE LIMBERS DPR-33, DPR-52,. and DPR-68 .Submit ted by lant Superintendent TABLE OF CONTENTS Operations. Summary Operational Data ~ ~ ~ ~ ~ ~ ~ ~ 0 0 S ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 \\ ~ ~ ~ ~ ~ ~ ~ ~ ~ Maintenance. ~ ~ ~ 1 0 ~ ~ ~ ~ 0 ~ 0 3 Refueling Enformation ~ ~ ~ ~ 4 Significant Operational Events ~ ~ 0 ~ 6 Average Daily Unit Power Level ~ ~ 0 t ~ ~ o ~ ~ 15 Operating Data Reports ~ ~ 0 0 ~ ~ o ~ ~ 18 Unit Shutdowns and Power Reductions.. Plant Maintenance Summary. ~ 4 ~ ~ ~ 0 t ~ 0 ~ ~ \\ ~ ~ ~ ~ ~ ~ ~ 21 ~ ~ ~ ~ 24 0 0 erations Summar The following summary descrfbes the sf'gniffcant operational activitfes during the reportfng perfod. En support of this summary, a chronological log of significant events is included in this repozt and begins on page 6 There were 6 Reportable Occurzences reported to the NRC durfng the month of Augusta Uait 1 Significant operatfonal events for unft 1 are-tabulated by date and time beginning on page 6 The unit'scrammed four times, durfng the month of August. The unft scrammed. on August: 11 from turbine stop valve closure caused by turbine trip resulting from loss of preferred power during transfer of power,.sources. On August 12 the reactor scrammed on APRM high flux durfng startup due ta. a recirculation flow spike caused by a bzoken wire fn the scoop tube controls. The unit was manually scrammed on August. X5 and'8 when. control air problems allowed control rods to begin drifting into the core. A summary of maintenance work is shown on pages 24 through 31 Unit 2 Significant operational events for unit 2 are tabulated by date and time beginnfng on page 9 There were three scrams during the month On August 12 the reactor scrammed as a result of manual turbine trip and turbine stop valve closuze to test the recirculation pump trip (RPT) system. On August 18 the reactor was manually scrammed when control afz problems allowed control rods to begin drifting. into the core. The reactor scrammed on August 19 on APR'f high flux due to recirculation flow spiking caused by mechanical problems on 2A recirculation pump. A summary of maintenance work is shown on pages 24 through 31 0 erations Summar Continued) Unit 3 Significant operational events for unit 3 are tabulated by date and time beginning on page 12. The unit scrammed six times during the month of August. The reactor scrammed on August 3 and 17 due to turbine stop 'valve closure which resulted from a turbine trip caused by high moisture separator water level. The reactor scrammed on August 4 due to turbine stop valve closure resulting from a turbine trip due to EHC problems. On August 18 the reactor scxammed due to turbine stop valve closure resulting from turbine trip on low condenser vacuum during, testing of the low vacuum switches.. On August 22 the reactor scrammed on IBM high flux when relief valve PCV 1-4 opened and stayed open.. On. August. 24 the reactor scrammed due to turbine stop valve closux"e zesulting from turbine. trip 'on low vacuum caused by problems 'in the vacuum switches and circuitry. A summary of maintenance work is shown on pages 24 through 31. Common S stems The radwaste system performed as design'ed without significant problems. Approximately 2.3E+5 gallons of waste containing 2.38E-l curies of activity were discharged during the month. Cooling towers 1, 2, 3 and 6 were operational this month for one lift pump operation only. Towers 4 and 5 were operational this month for two lift pump operations. None of the.towexs had significant operational problems. 0 erational Data The average daily unit power level for units 1, 2, and 3 is shown on pages 15 through 17. The operating data reports for all three units are shown on pages 18 through 20. Unit shutdowns and power reductions fox all three units axe shown on pages 21 through 23. 0 erations Summar (Continued) Maintenance Major electrical, mechanica1, and instrument maintenance activities during the month are. described on pages 24 through 31. Refuelin Information Unit 1 Unit l is scheduled for its second refueling beginning on November 15, 1978, with a restart date of December 15, 1978. Resumption of operation on that date will require a change in technical specifications pertaining to the coze thermal limits. Licensing information in support of these changes was submitted in August 1978. This, refueling will load additional 8 X 8 retrofit fuel assemblies into the core, replacing presently loaded 7 X 7 fuel and will involve installing a new recircu-lation pump trip (RPT) system. There are 764 fuel assemblies in the core. The spent fuel 'torage pool. presently contains 168 spent fuel assemblies and 116 new. fuel assemblies. The present storage capacity of the spent fuel pool is 1080 assemblies. Present planning is to increase that capacity to 3471 assemblies. With present

capacity, the refueling later in 1978 uld.be. the 1ast refueling that could be discharged to the spent fuel storage pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Uni.t 2 Unit 2 is scheduled for its second refueling beginning on April 22, 1979, with a restart d'ate of July 1, 1979. Resumption of operation on that date will require a change in technical specifications pertaining'o the 'core thermal limits. Present scheduling is to submit licensing information in support of these changes before the refueling. This refueling will involve replacing some more 7 X 7 fuel assemblies with 8 X 8 retrofit assemblies. Refuelin Information (Continued) ~ Unit 2 (Cnnninned) There are 764 fuel assemblies in the core. At the end of August there were 132 discharged cycle 1 fuel assemblies in the spent fuel storage pool. There are presently 36 new 8 X 8 fuel assemblies in the spent'uel storage pool which were.not loaded into the core duiing this cycle. The present storage capacity of the spent fuel pool is 1080 assemblies. " Present planning is to increase that capacity to 3471 assem-blies. Mith present

capacity, the 1979: refueling would be the last refueling that could be discharged to the'pent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Unit 3 Unit 3 is scheduled for its first refueling beginning on September 8;. 1978, with a restart. date of October 31,, 1978. 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 was submitted in July, 1978 This refueling will involve repXacing some of the present-8-X 8 fuel -assemblies-with 8 X retrofit assemblies, modifying the main steam relief valves to increase simmer margin, and installing a new recirculation pump trip (RPT) system. There are 764 fuel assemblies in the core.. At the end of August there were 208 new 8 X 8 retrofit assemblies present in the spent fuel 'storage pool. The present storage capacity of the spent fuel pool is 800 assemblies due to removal of two rows c.f conventional racks to install high density racks. The present pool capacity cannot accomodate a planned full core discharge:.n September 1978 without final approval by the NRC of four high density storage racks installed on an interim basis to provide approximately 243 additional storage locations. Si n ficant 0 erational Events Date Time Event Unit 1 8/1 8/2 8/3 8/4 1240 1545 2305 Reac or thermal power at 95+p sequence "B" fzow 1imited. Comme ced, reducing thermal power for ifCPR change NCPR change completed,, commenced power ascension from 88~a thermal. power. Reactor thermal po~er at 90', holding CPR limited Reduced thermal power from 90,. to 854 due to fuse failure causi g recirculation pump tl.G. set scoop tube to lock on Loss of speed, signal Reduced; thermal power from 85~p to 75@ for turbine C,V. tests and. SZ's 8/5 8/S 8/Lo-8/11 003Q 1500 2331 Turbine. C.V. testa and SX's completed., commenced power ascension Reactor thermal power at 90',, holding CPR Limited Reactor thermal power at 89', holding CPR limited. Reactox scram~ ~no. 93 from 8gp thermal power on loss of preferred power causing main turbine trip --- - -8/12. a 0305- --- Commenced rod -withdrawal 0538 0728 Reactor critical no. 105 Reactor scram~1~no. 94 from Mp thermal power due to broken wire in controls of'A" recirculaticn pump MB set, causing high flux when flow spiked. 0905 1410. Commenced. rod, withdrawal Reactor critical no. 106 1600 Rolled T/G 8/13 0700 Synchronized generator, cc enced power ascension commenced. Pc10TE from 73'hermal power Si nificant 0 erational Events + Daae Time Event 8/14 8/15 0120 0215 0700 1326 1559 1945 2145 Reduced thermal power fram 80'o 75~ for control rod. exex cise I Control rod exercise SI comoleted, commenced power \\ ascension Commenced PCIOLR from 80;o thermal power I Rezjctor scram(l)no. 95 from 86~p thermal power on loss of 'control air. Ccmmenced rod wtthdrawaL. Reactor cxitical no. 107 Rolled, T/G 8/17 8/18 2206 0700 2200 0815 0945 1157 1431 Synchronized generator, commenced power asc nsion Commenced, PCIOtK from 84 thermal power. Sequence B'i Reactor thermal power qt 86K, holding CPR limited Reactor scram no. 96~ J (manual) from 8&p thermal power due to-loss of control air pressure ("F" air compressor ruptured. head) Commenced rod withdrawal Reactor critical no. 108 Rolled: T/G 8/19 8/21 8/25 1448 0700 0700 2307 Synchronized genexator, commenced power ascension Commenced PCIOEK from 76@ thermal power (sequence "3") Reactor thexmal power at 9', holding CPR limited Reduced thermal power.from 8'o 75K for turbine C,V. tests and. SI's 8/26 0230 Turbine C.V. tests and" SI's completed, commenced power ascension 1500 Reactor thermal power at 88~,holding CPR limited Si nificant 0 erationa1 Events Date Tice Event 8/28 1345. 1520 Reduced, thermal power from 88~p to 85+p for mainzenance to scram vaLve on control rod 34-3L Maintenance to scram valve on control rod 34-31 com-

pleted, commenced.

power ascension 8/29 0426 Reduced thermal power. from 88$ to 85+~ to scram valve on control rod. 34-1I r Maintenance to scram valve on control

pleted, commenced power ascension for maintenance rod; 34-LL com-.

8/30 0700 Reactor thermal power at 88~p, holding CPR Limited Reduced, thermaL power from 88~p to 86'ue to CPR'imits 8/31 Reactor thermaL power at'6fo, holding CPR limited. ~2i nfficant 0 erational Events Date Time Event Unit 2 8/1 8/4 8/5 0000 0700 2315 Reactor thermal power at 67~, sequence "A", PCICM in progress I Reactor thermal power at 944, flow limited Reduced thermal power from 94~f2 to GPSS for turbine C.V. tests and SI's 8/6 8/7 0100 Turbine C.V. tests and. SI's completed, commenced, PCIQiR from 80'hermal power 2300 Reactor thermal po~er at 96~p, steady state 0115: Reduced., thermal'power from 96~p to 92fo due to EHC erratic pressure 1330 MC pressure problems resolved, commenced. power ascension Reactor thermal power a P@, steady state flow limited .8/9 2050 Reduced thermal po~er from 96$ to 88$'or TIP checks 8/10 0700 TIP checks completed, commenced. power ascension Reactor thermal power at 9Q steady state core flow limited 8/11 2347 Reduced, thermal power from 96~p to 8'ue to a run back on both recirculation pumps while transferring shutdown board power supply 8/n 0001 Commenced power ascension Commenced PCIO:S from 90'hermal power 2205-2323 Reduced thermal power from 96$ to 90@ for RTI-27 (manual turbine trip) kfanually tripped turbine for RTI-27 reactor scram (3)'. no. 68 10 Si nif cant Operational Events Date 'tme Event 8/13 0655 I Commenced od, withdrawal 8/15 8/16 8/18 1655 1858 0020 ~ 1400 0820 Reactor cr tical no. 81 Rolled. T/G Synchronized. generator, commenced. power ascension 1 Comaienced PCIOblR from 80'hermal power (secuence "A") Reac or thermal power at 98~~,. few l.imited Reactor scram no. (1)69 manual from 98~p thermal power due loss of control air pressure ("F" air compressor-. ruptured. head) Commenced. rcd. withdrawal 1055 Reactor. critical no. 82'olled. T/G Synchronized generator~ commenced power ascension Reduced thermal power from 92'o 75'or turbine C.V. tests and SI.'s. 8/19 0100 Turbine C.V. tests and, SZ's completed, commenced. PCIQK from 75'hermal power (sequence "A.") 1130 Reactor scram<1)no., 70 from 86'4 thermal power on high'lux,, due to 2A recirculation pump problems 8/21 8/22 8/26 3227 1415 1628 2355 1500 'ommenced, rod withdrawal Reactor critical no. 83 Rolled T/G Synchronized generator, commenced power ascension Commenced PCZOMH frcm 884 thermal power (sequence "A") Reactor thermal power at 98~o flow Limited Reduced thermaL power from 98'o 75,a for turbine C.V:.. tests and SI's 0130. Turbine C.V. tests and Sl's completed, commenced power ascension 1500 Reactor thermal power at 98X flow limited 11 S nificent Operational 1:"yen+a Bate 8/a7 1 8/30 8/3x T1me 1500 0700 24oo Event Reactor thermal power at 9Q flow limited Reactor thermal power at 9@ flow liMted Reactor thermal power at 95~p flow limiteC 12 Si nificant Ooerational Events Date Time Event Unit 3 8/1 8/3 1500'505 0842 1057 1510 .thermal power at 96'll rods fully out, state flow Limited Reactor steady Reactor thermal power at'5~p, steady.. state flow Commenced. rad withdrawal Reactor critical no. 84 Rolled T/G LimitecL ~Reactor scram 'o.. 59 from 95~p thermal power on (L) stop valve closure due to moisture separator high water level 8/4 1531 0340 Synchronized generator~ commenced power ascension Reactor scram )no 60 from 65'hermal power while (L)'erforming weekly turoine C.V. tests (Loss af hydraulic trip pressure) 0755 Commenced. rod. withdrawal Reactor critica1 no. 85 1250 Rolled, T/G h 8/5 8/7 1320 0700 Synchronized generator, commenced power ascension Commenced PCXOiB from 75~q thermal power Reactor thermaL power at 92~p steady state core flow limited. 8/10 Reactor thermal pawer at 9Lp steady state core flaw limited. 8/12 0220 Reduced, thermal power from 91'o 75$ for turbine C.V. tests and, ST.'s i Turbine C.V. tests and Sl's completed, commenced power ascension 0540 1315 Reactor therraL power at 90@ steady state flow Limited Reduced. thermal power from 90'o 7'ue to "C" reenter reedwater porno trip (low tearing oil yreeaure) 0 0 Si nificant Overational Events Event 8/13 8/15 2115 1500 Commenced ower ascension Commenced >CIQK from 8g thermal power Reactor thermal power at 9l~p, steady state core flov 8/16 8/17'700 0700 limited I Reactor thermal paver at limited. Reac or thermal power at limited 90', steady state, core low 8Q, steady state, core flow= 8/18 8/21 2237 0545 Reactor scram(1)no. 61 from 89'hermal power cn stop valve closure due to moisture separator high water level Reactor at cold. shutdown fo . general checks and maintenance. (main steam r lief'alve maintenance) i~9xintenance problems resolved, commenced rod withdrawal for startup Reactor critical no. 86 and. holding for relief valve checks Relief valve checks completed, resumed startup Rolled. T/G 8/22 Synchronized generator, commenced power ascension Reactor scram( )no. 62 from 64~p thermal power on lov condensor vacuum due to human error 0340 Commenced rod. withdrawal 0715 0923 Reactor critical no. 87 Reactor scram( )no. 63 from 57~p thermal power on IBM (1) hQh flux before generator was synchronized, 1455 Reactor in cold. shutd.own 14 Si niff.cant Ooeratio.xal Events Event I 8/23 8/2V 1635 LSLL 23I.6 Commenced rod. withdrawal Reactor'ritical no. 88 RoLLed. T/G Synchronized generator, commenced power ascension Reactor scram( )no. 64 from 53~v thermal power turbine ~ stop valve: closure (turoine tripped, on low vacuum) 1308 143O 1632 Commenced rod. withdrawaI. Reactor critical no. 89 Rolled T/G 8/25 l652 Synchronized.. generator, commenced power ascension Reactor thermal power at 65~p hoLding'due to T/G ~ vacuum problem, Admistrative hold. 8/27 L5OO Reactor thermaL'ower at 674 due to T/G vacuum problems, Administrative hold. 8/31 24OO Reactor thermaL power at 67', Administrative hold. , due to vacuum problems of T/G (1) Equipment malfunction (2) Maintenance error (3) Required, tests .. y~vE>t 15 AGE DAlLYUNITPOWER LEVE DOCKET No. Brogans Ferrv E nhTE COMPLETED BY Don Green TELEPHONE 205/729-6846 MOMH August 1978 DAY 10 14 15 AVERAGE DAILY.POWER LEVEL (MWe-Net) 953'29 903 808 886 889 902 907 922 901 137 874 465 589 DAY 1$ 19. 20 22 24'5. 26 27 2S 29 30 31 AVERAGE DAILYPOWER LEVEL (MWe-Net) 819 '65 866. 848 883 909 909 900 911 873 889 896 895 886 907 INSTRUCTIONS On this format. list the average daily unit po~cr level in MWe.>Net for each day in thc rcp>>rting >n>>nth. Compute to 'he nearest whole mi'.gawatl. (9I7 7) 16 hVERAGE DAILYUNITPOWI II LEVE DOCKET'>. b'4 'i.l COMPLETED BY TELEPHONE 50-260 4 F:.Owns Perry o-2-78 Don Green August 1978'hY hVERACE DAILYPOWER LEVEL. (MWe-Net) I 651 DhY AVERAGE DAII.YPOWER LEVEL tMWe-Net) '8 10 1 11.. 13 l5 I6 808 933 998'68 975 1016 998 992 1009 1017 977 686 1034 IS 24 26: 29 30 737 598 799 920 1027 1052 1033 1041 1008 1020 1031 1025 996 1038 ~~ ~ ~ INSTRUCTIONS On this for>nat, list the average daily unit power level in MN'e-Net for each day in the reportinr, >n>>nth. C>>>npute to the nearest whutc n>cgawatt. {OP7) t AVERAGE DhlLYUNlTPOWER LEVE y I DOCKET NO. UN)T DATE COMPLETED BY TELEPHONE 50-296 Rrowrts Ferry'IE 9-2-78 Don r.ze August 1978 DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net) 1 925. 923 DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net) 854 17 -10 3 6 9'0 12 )3 )5 16 348 378 840 932 956 933 930 934 925 836 767 840 908 19 20 24 26 27 29 30 31 -10 131 72 393 675 664 672 677 659 680 )NSTRUCTlONS On this fortnat, list thc average daily unit power level in MtVe-Nct for each day in the reporting tttonth. Ciimpotc to the ncarcst whole megawatt. ( l/77) OPERATIEIC DATAREPORT DOCKEi.'. 9-2-76 COMPLETE.) Y " E i:eeee TELEPH,'3l E ~729-6866 OPER %TING STATUS

1. Unit Name'rowns Pe E

2. Reporting Period: A 1 78

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

f. Design Electrical Rating (Net hllVe):

6. Maximum Dependable Capacity (Gross hIWe)i 1098 Notes 7.Maxim m p

p y( )

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

9,<ower Level To Which Restricted, IfAny (Net hOVe): 10 Reasons For Restrictions, IfAny: ~ '1. 12. 13. 14. ..15. 16e 17,'8. 19. 20. 21. 1a. 23. 24. 126. 57 4,880,130 4,732,285 ihis Month Yr:to-Date Hours In Reporting Period Number Ot Hours Reactor.Was Critical 5393.41 Reactor Reserve Shutdown Hours Hours Generator On.Line 711.9 '5212. 98 Unit Reserve Shutdown.Hours 0 0 Gross Thermal Ener y Generated (MWH) 1 998.274 1'4,834,056 Gross Electrical Energy Generated (hlWH) Net Electrical Energy Generated (MWH) Unit Service Factor 89.4 Unit Availability Factor 95.7 89.4 Unit C'opacity Factor (Using MDC Net)

77. 8 76.2 76.2 Unit Forced Outa e Rate 4.3 3.6 Shutdowns Scheduled Over Next 6 hlonths (Type, Date, and duration of Each):

Refuel Outage October 1978 Cumuh tive ~ 35,809-18,373. 29 4173. 37. 171859'. 0 47,2')7,285 15,220,632 49.9 39.9 39.9 42.1 25.. IfShut Down At End Of Report Period. Estimated Date ofStartup: 26.-Units ln Test Status {Prior to Commercial Operation): Forecast Achieved INITIAL C R IT I CALITY ,)NITIALELECTRlCITY COhlh1ERCIAL OPERATION (>f7>) 19 OPERATliiG DATAREPORT DOCKET NO. DATE COMPLETED BY 1. 2e 3. 4; 5. 7. ~ S.'PERATING STATUS Notes Unit Name Bzowns Fez II Reporting period. Au us t 1978 3293 I.icensed Thermal Power (MWt). Namephte Rating (Gross MWe): Design Electrical Rating (Net 44IWe): Maximum Dependable Capacity (Gross hlWe): 1098 Maximum Dependable Capacity (4Vet hlWe): 1065 1f Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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

10. Reasons For Restrictions. IfAny:

This Month: 'r:toDate Cutnula tive

11. Hours ln Reporting Period 12.'umber Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

19. 70 188.47

14. Hours Generator On-Line 7154 3 3,205.3

15. Unit Reserve Shutdown Hour's 16, Gross Thermal Energy Generated(MWH) 2 155 279 8 593 250 i7: Gener Elecrricnl Ener,y Genernred.(yiWD}

~704 840 2 784,640 1S. Net Electrical Energy Generated (hIWH) 96.1 t 2 691 661 . 19. Unit Service Factor 55.0

20. Untt Availability Factor 96.1 55.0

21. Unit Capacity Factor (Using MDC Net) 86.0

~ D>. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outa e Rate 1.3

24. Shutdowns Scheduled Over Next 6 hlonths (Type. Date. and duration of Each):

30,720 13,877.76 0 ~ 13, e 0-34 766,387 ll 381,590 11,034,465 43.1 33.7 33.7

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

26. Units In Test Status lprior to Commercial Operation):

Forecast Achieved INlTIALCRITICALITY gNITIAL ELECTRICITY COhlhlERCIALOPERATION 20 OPERATING STATUS Browns Perry XZI OPZRATliiiGDATAREPORT Notes DOCKET NO ~8-246 DATE COMPLETED BY TELEPHONE ~7D 72+-6846 2 Reportinn Period. Au ust 1978

3. Licensed Thermal Power {4INt)t

4. Namephtc Rating (Gross Mme):

5. Design Electrical Rating (Net MWejt 1065

6. Maximum Dependable Capacity (Gross MWe):

T. Maximum Dependable Capacity (Net iiIWe):

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

'. Power Level To Which Restricted, lfAny (Nct MWe)t

10. Reasons For Restrictions. lfAny:

This Month YrAo-Date Cumuh'tive

11. Hours ln Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Ilours -.-

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated {MWH)

19. Unit Service Factor

'0. Unit AvaihbilityFactor 21.. Unit Capacity Factor I Using MDC Net)

22. Unit Capacity Factor IUsing DER iNet)

23. Unit Forced Outa e Rate

. 24. Shutdowns Schedukd Over Next 6 4iionths Refuel Outage September 1978 744" 612.65 100.15 586.45 .-0 1 567 322 484 770 465 199 5312.25 449.75 5,224.34 14 998 050 4 906 740 4 757 259 78.8 89.6 76.

76. 6 9.8 58.7 21.2

{Type. Date. and Duration of Each): T ~ I 13,175 12,007.92 1038.16 11,723.65 33 639 744 10,940,610 10 608 165 89.0 89.0 75.6 75.6 9.9 r

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

. 26. Units In Test Status iPrior to Commercial Operation): Forecast Achieved INITIALCRITlCALITY QNITIAL ELECTR ICITY COII~IERCIALOPERATIOi i ~ ~ II ~

I

'I UNITSHUTDOWNS ANDPOWER REDUCTIONS REPORT MONTH August 5n-259 UNITNAMF Browns Ferry I DATE COMPLETED BY TEI.EPl{QNF 2 35-7? 3-684t> >> ~ Datl I C Lra "~'> IA CJ Yg t C4 ~ ee g ec ~ vj Licenscc Event Rcport f E~ cn G Cause h. Currectivc Action lu Prcvcnt Rccurrcncc 46 47 48 I 49 780811 ~ 780812 780815. 780818 P 893 A 8.67 A F 6.55 A F 795 A 2 i I ~ I ~ I ~ I ~ ~ Loss of unit preferred power due to operatg~rar.. "A" recirc. pump M.A. set harl a broken wire in'its controls.. Loss of control air pressure Loss of control air pressure when "F" air compresser ruptured its head. F: Fornd S: Scheduled I (o/77) Reason: A-Equipmcnt Failure (Explain) B.Maintcnancc oi Test C-Refueling D-ltegulatory Restriction 1'. Operat>>r Training h Liccnsc Examination F.Adu>inistrative ' ()l>erali>n>al 1:III>r(L'xplain) 11.0tl>er (I:xt>lain) I ~ ~ I 'I Mcthr>d: I-Manual 2.Manual Scram. 3.Autu<natic Scram, 4.Other (Explain) 4 Exhibit G - Instructions for Preparation of Data Entry Sheets fur Licensee Event Report (LER)File (NUREC. 0161) 5 Exl>ibit I ~ Same Source UNlTSHUTDOWNS ANDPOWER REDUCTlONS N DOCKET NO. 5n-260 UNlTNAME Brogans Ferr ZI DAT'- II Date n A rs UI ~ tl OJ t4 ~ c 5M U ~ W O Li<<cnscc. Event 'eport4F Ew Vl P cn G Cause &Corrcctivc Acltun lo Prevent Recuncnce 57 58 59 60 780812 780818 780819 780826 S 19.53 P 3,87 5.25 3 ~ I Recirculation pump (RTI-27) trip (RPT) Test Loss of control 'air pressure srhen "P" air compresser ruptured its head. High flux due to "A" recirc. pump problems. ,Oersted for turb. control valve tests. I',III F: Forced S: Scheduled I 1 ~ I I Reasini: A.Equipment Failure (Explain) O.htaintcnancc or Test C.Refueling D.R 'guhtory Restriction E Operator Training & Uccnsc Examination F-Adnministralivc C.Operational Error (Explain) ll Other (Explain) I I 3 I Method: l Manual 2-Manual Scram. 3.Automatic Scram. 4.Other (Explain) Exhibit G - instructions for Preparation of Data Entry Sheets for l.icensee Event Report (LER) File (NUREG-OI 6I ) 5 Exhibit l - Satne Source i II t I UN{TSHUTDOWNS ANDPOWER REDUCTlONS REPORT MONTN I DOCKETNO. UNlTNAME DATE. COMPLETED BY TELEPl{ONE 5n-2nc n on .reen 205 72 -6RI6 Date rEg CC EO ~ jp ~ C/I Lfccnscc. Event Rcport 0 Ew ~l Vl ot CJ Co~ 0~ u CI p o CJ Cause Sc Corrective Action.tii Prevent Recurrence 57 58 60 780803 780804 '780812 780817

10. 43 9.67

87. 93 A

A A Hoisture seperator high pater level EllC stabilizing pressure accumulator Depressurization. C>> Reactor Feed pump trip. Hoisture seperator high water level (unit remained down.for relief valve maintenance.) 61 780822 I 62. 780822 63 780824 6.80 A 37.89 .A 4.83 A I ~ Low condenser vacuum due to a faulty test switch. IRH high flux dqe to relief valve-l-4, hanging open. Condenser low vacuum (corroded strips in a )unction box prevented pressure signals from reaching the EflC system). 1 F: Furred S: Scheduled l (9/77) Reasiin: I A-Equipment Failure (Explain) B-Maintenance or Test C. Refueling tI D.Regulatory Rcslrh:llull 1:..Operator Trainingh Uccnsc Exant{nat{on F.Adi)tiiiistrat iv'e C Otter Jllollal Liror {Lxplaln) Il.Other (Explain) 3 Method: 1-Manual 2-Manual Scram. 3-Automatic Scram. 4.Other {Explain) Exhibit C - {nstruetions for Preparation of Datp Entry Sheets lor Licensee Event Report {LER)File {NUREG-OI 6 I ) Exhibit I ~ Satt)>> Source I 9 CSSC E UIPHENT BROWNS FI'.RRY NUCLEhR PLMIT UNIT~~gg MECHhNICAL MAINTENANCE SUHIARY ~l9~ SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 8/8 8/16 I CO Storaa. an3 Fire Protection "A" RHR Ser-vice Water PumI I C02 odorizer Holes in., filter Broken C02 odorizer bottle None None Operation CO2 line pressur caused rupture None None Replaced filter '9 Replaced odorizer 8/18 RHR Ser-v'ice'Water D-3 RHR Servio Water Pump Packing leak t None Loose packing None Ad)usted packing 8/23 RIOR Ser-C-3 RHR Ser<< vice Water vice. Water 7ump Pump not oper ating at suf-ficient capa-city None Worn parts None Dismantled, inspeci replaced worn parti and rebuilt pump 9I CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 1 MEQfANICAL MAINTENANCE

SUMMARY

2ll DATE SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 8/1 8/4 8/13 8/14 Control Rod Drive Control Rod Drive Control Rod Drive Control Rod Drive "B" Pump A" Pu 22-51 Module "B" Pump Mud in cooler Low oil level Insert solen-oids not work in Oil leak at union on oil um dischar None None None None Operation Operation Unknown Valve stem loose None None None None Removed head and cleaned coolers ar re laced heads Added oil Replaced in~

valve on C~-5]

with new one Tightened valve stem 8/14 CRD 8/15 CRD 1A Discharge um SCRAM Pilot air header Dirty filter Dirty filter None None Operation Operation None None Changed filter Changed filter'lements 8/16 CRD Scram,outlet.

valve 34-31 Leaking gone Operation None Ad)usted stem on valve 8/25 CRD Fuel-Pool Demin.

Scram'utlet valves 38-11, 34-11, 22-15, 30-47 34-39 "B" Fuel Pool Cooling Pump Porn seals Bearings lock ed and end bracket brokei None Operation Unknown None Replaced seals Rebuilt pump 8/11 Diesel Generator Starting Air No.

2 Air Compressor Safety valve leaking and clogged with rust None Operation None Replaced safety valves and cleane~

CSSC E UIPMENT BROUNS PERRY NUCLEAR PIANT UNIT~

MECHANICAL MAINTENANCE

SUMMARY

DATE SYSTEM 8/3 HPCI 8/3 RCIC COiAPONENT Oil Reservoir Turbine Bear-in s Water in oil

None, Low oil level None EFFECT ON SAFE DENATURE OP OPERATION OP MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION Unknown Operation RESULTS OF MALFUNCTION None None ACTION TAKEN lO PRECLUDE RECURRENCE Drained and cleanei reservoir.

Replace oil Added oil 8/7 Monorails Hoist, el ator, over head crane.

doors and stairs Access door to Rx. Bldg.

U2 and equipment room door Door seals broken and door not closing None Operation.

None Replaced seals and ed$ ueeed 8/7 SLC 8/8 CRD "2B" Pump Discharge pump IIAII Intake valve leakin Dirty filter None None'peration Operation None

.None Lapped valve Changed filter 8/9 RCIC 8/12 Rx. Clean-up Filter Demin.

Condenser vacuum um...

Motor, generato oil pump 2A-2 Packing leak None Seal leaking None Bad Seal Ir =- ~

'oose packing None None Replaced seal Tightened packing gland on valve 8 12 Rx. Clean-up g4.1Wer Demin.

Moto~generato oil pump 2A-3 Packing leak None Loose packing None Tightened pa ng gland on valve 8/14 CRD 8/18 CRD

'2A pump Backup scram solenoid Dirty suction filter Coupling leak ing on air line None None Operation Loose union None None Changed suction filter Tightened union f/25 Rx. Water Cleanup "28" heat exchanger Flange leak-ing None Loose flange None Furmanite leak

I CSSC E UIPMENT HKUNNb

l. I.lined Hul'u.An rt.usa Ucsj.r.

MEQIAHICALMAINTENANCE SUIQIARY For the Month of.

XSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF.

MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN

'O PRECLUDE RECURRENCE 8/3 1

Hain I

Steam FCV-1-38 Low oil level None Operation None Added oil 8/8 H CI Oil sump e

Water in oil None Unknown None Drained oil, cleai oil sump and repl oil 8/11 Reactor Cleanup Filter Demin.

Motor genera-tor. "A" and IIBil Low oil level None Operation'one Added oil 8/19 HPCI Exhaust line Mater leak None Ruptured Diaphragm None Changed ruptured diaphragm 8/19 Radwaste Building Drainage "A" sump pump Not opera-tional Nona Pump not ad)uste correctly None Ad)usted impeller 8/22 Liquid Radwaste FCV 28 Low oil level None Operation None Added oil

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'or the Month o I

EROUNS FERRY NUCL)AR PLANT UNIT III ELECTRlCAL MAINTENANCE

SUMMARY

.'AUGUST lg 78 D"te Sys A.~

Component Nature of Maintenance ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Take To Preclude Recurrence 8/8/78 I

I IControl bay ~ir

,cond

.Emergency chillers

~

~

Chillers won't gone run I

Low freon pressure due to

'leaks Chiller won't run Repaired leaks ant recharged with fry TR 92696 8/21/78 HPCI Outboard steam valve FCV 73-3 Ground on FCY 73-3 None Motor grounded and.broken

.torque switch FCP 73-3 had 150V ground Repaired gr at torque switch TR 114201 8/21/78 Contro'1 bay air condition Control" bay chiller.

Low oil in chiller None Leaks on chiller ow oil level Repaired leaks ant added oil to propt level TR 114611 8/24/78 Control rod

--drive HS85-48 Spring return broken None Return spring

)roken in hand switch

.S, wouldn' perate properly Replaced return sI HS works ok TR ll~

8/24/78 RHRSW 4160 breaker for C3 pump motor Breaker won',

change Hone.

Spring charging drive motor burned out reaker won't charge Replaced dr~ moj checked ok ~114.'

"SSC EQUIP.fEHT ERONNS FERRY NUCLEAR PLANT UNITS I. 2.

3 INSTRUMENT HAINTENANCE SU&fARY I

FOR THE MOllTll OP August, 1977 Daa.e

.nit 1

~

C yste omponen i

Nature of

,Maintenance Effect on Safe Operation of the reactor:.

e

~

~

Cause of

...Malfunction. I.

Results 'of

.:.Malfunction..

Action Ta to preclu recurrenc 8/20 8/23 8/29 Unit 2 7/17 7/23 7/2S 7/29 8/1 8/13

.- 8/14

'eutron fc~itnring LPRM Page Rod Display

.L.C.

.C.I.C.

LI-63-1B FI-71-1A ad Monitor-RI-90-9B ng ad Monitor-ng

'eutron fonitoring RI-90-3A APRM Page IS Rod Displag

~eedwater PI-3-61 ad Monitor-RI-90-22A ng Replace Replace Replace Calibrate

. Calibrate Replace Replace Replace Replace Calibrate

- None None None None

'one None Pione None None None

~ iI Faulty Diode

~

IPiulty Relay Faulty Relay i

~

~

Instrument Drift:

i 2jro Shift

~

~

Paulty Sensor

~

I

~

~

Faulty Relay

~

~

Faulty Resistor 6

Capacitor

~

~

Faulty Display Unit

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~

~

~

~

~

~

i.0ose Connection

~

~

LPRM Do "Rod 0 Hi Rad scale I

rtravel" Alarm larm Indicat evel ndicat ystem ensor Iigh R ing Improper ng Flow with ut of Service ndicating diat!ion li Rad larm O'RH ll lo Pos ispla ndica ith R i

~..g a

tion 22 and 26 I,Cs, i j

ion did.not agre dundant Instru-None None None None Hone Mone

.io None one lone