ML18025B278

Forwards Monthly Operating Repts for Dec 1980

ML18025B278
Person / Time
Site:	Browns Ferry
Issue date:	01/09/1981
From:	Abercrombie H TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML18025B279	List: ML18025B278 ML19351F621
References
NUDOCS 8101130582
Download: ML18025B278 (46)

Text

REGULATQ jNFORLlATION DISTRIBUTION TER (RIDS)

ACCESSION NBR: 8101130582 OOC ~ DATE'- 8'1/01/09 !AlOTARIZED: NO DOCKET F AC IL: 50-26n Browns Ferry lnuclear Power Stati ni Unit 2E Tennessee 05000260 o n 0-2 rnwns Ferry Nuclear Power Stations Unit 3F Tennessee 05000296 A T ~ AUTHvR AFFILIATION ABERCRUMt3IEPH Tennessee Valley Authority PEC IP ~ NAAlg. RECIPIENT AFFILIATION Office of 'sanaaement and Proaram Analysis SUB.IECT: For wards montnly oeeratina rents for Dec 1980 COOS:

TITLE: Annual, Semi-annual AOOSS COPIES OECE IVES:LTR tt mon tbl y Operation IReoor F!!CL g'ISTRISOTIOA!

ta (OL Stage)

SIZE:

NOTES:

HAEC IP IE>>T COPIES REC I I ENT Eo COPIES ID CODE/NAt'E LTTR ENCL ID CODE/NA~E LTTR ENCL ACT IUbi: IPPOL I TO, T ~ 7 7 'VARGA,ST 04 7 7 D/OIPPHUM FAC07 04'NTERNAL:

AEOD 1 1 1 1 F D

'I" IV OF LIC 1 I3,E 06 2 2 t<P A lS 2 NRC PDR 02 1 1 L BR09 1 1 OR ASSESS BR 10 1 1 HEG FILE 01 1 1 EXTERNAL: ACRS 11= 1 1 BROOKhAVEN 12 LPDP, 0 'zt 1 1 NSIC 05

)

JAN l4 )ge) e',e.

TOTAL NU~BER OF COPIES RE4lUIREO: LTTP 29 ENCL 29

ig 0 Browns Ferry Nuclear Plant P. O'. Box 2000 Decatur, Alabama 35602 JAilv'8 t98l Nucl'ear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the December 1980 Monthly Operating Report for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY H. L. Abercrombie Plant Manager Enclosure cc: Director, Region II Nuclear Regulatory Commission Office of Inspection and Enforcement 101 Marietta Street Suite 3100 Atlanta, GA 30303 '(1 copy)

Director, Office of Inspection and Enforcement

'Nuclear"Regulatory Commission Washington, DC 20555 (10 copies)

Mr. A. Rubio, Director Mr.. Bill Lavallee, NSAC Electric Power Research Institute P. '0. Box 10412 Palo Alto, CA 94304

p P

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT December 1, 1980 December 31, 1980 DOCKET NUMBERS 50-259, 50-260, AND'0-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By: /

Plant Manager

TABLE OF CONTENTS Operations Summary . ~ ~ ~ ~ ~ ~

Refueling Information Significant Operational Events ~ ~ ~ ~ ~ ~

Average Daily Unit Power 'Level,. 12 Operating Data Reports 15 Unit Shutdowns and Power Reductions. 18 Plant Maintenance 21 Outage Summary . 33

il

0 erations Summar December 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 twenty-three reportable occurrences and thirteen revisions to previous occurrences reported to .the NRC during the month of December.

Unit 1 There was one scram on the unit during the month. On December 29, the reactor was manually scrammed to accommodate rep'lacement of the stator cooling filters.

Unit 2 There was one scram on the unit during the month. On December 27, the reactor scrammed from MSIV not full open during a SI when the unit operator

,tripped channel B main steam Hi radiation while PCIS channel Al was still in trip status.

Unit 3 The unit was in its EOC-3 refueling outage the entire month.

Operations Summar~ (Continued)

December 1980 Fati ue Usa e Evaluation The cumulative usage factors f'r the reactor vessel are as follows<

Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00497 0.00381 0.00315 Feedwater nozzle 0.2'4040 '0.16081 0 '1746 Closure studs 0.1'9766 ' '

'0.13425 0;09816 Note: This accumulated monthly information satisfies technical specification section 6.6.A)17<B(~3)~ reporting requirements.

Common S stem Approximately 1.15E+06 gallons of waste 3.ibid were discharged containing approximately 1.28K+00 curies of activity.

Refuelin Information December 1980.

Unit 2 Unit 1 is scheduled for its fourth refueling beginning on or about April 10, 1981, with a scheduled restart date of August 23, 1981. This re-fueling. will involve loading additional 8 X 8 R (retrofit) fuel assembl'ies 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, and one 8 X 8 R fuel assembly. Because of'odification work to increase spent fuel pool capacity to 3471 assemblies, present available capacity is limited to 1193 locations.

Unit 2 Unit 2 finished its EOC-3 refueling outage and began cycle 4 during the month. Unit 2 is scheduled for its fourth refueling beginning on or about March '26, 1982, with a scheduled restart date of August 8, 1982.

This refueling outage will. involve completing relief valve modifications, torus modifications if all approvals are received, "A" low,pressure turbine inspection, and'oading additional 8 X 8 R fuel assemblies into the core.

There are 764 fuel 'assemblies in the reactor vessel. At the end of the month, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 160 locations. With present capacity, the 1979 refueling was the

Ref uelin~Information (Continued)

December 1980 Untt 2 (Conttnned) last refueling that could be discharged to 'the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool. However, 949 new high density 'storage locations have: been installed, but cannot be used until, Special Test 161 is completed.

Unit 3 Unit 3 was in,its EOC-3 r'efueling outage during the month. Unit 3 is scheduled for its fourth refueling beginning',on, or, about September 25, 1981, with a scheduled restart date. of February,7, 1982. This EOC-.4 re-fueling, involves loading additional 8 X 8 R (retrofit) assemblies into the core, relief valve modification, turbine inspection, and torus if. all approvals are received.

modi'ications There are 764 fuel assemblies presently in 'the r'cantor vessel.

There are 124 discharged cycle 3 fuel assemblies, 144 discharged cycle '

fuel assemblies, 208 discharged cycle 1 fuel assemblies, and 40 new 8 X 8 R assemblies in the spent fuel storage pool. The present available storage capacity of the, spent fuel pool is~10~12 ~1ocat~ions. With present capacity, the 1980 refueling will be the, 1@st rdfuhling 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

'2/01 0001 Reactor thermal power at 77%, PCIO~i ; in progress sequence: "A".

2300 Reactor thermal power at 96% steady state, maximum flow.

12/02'0700 Reduced thermal power from 96% to 94% due to Xenon buildup.

1406 Commenced rod withdrawal for power ascension.

1500 Reactor. thermal power at 96%, maximum flow.

12/03 2333 Reduced reactor .thermal, power from 96% to 86% for control rod'attern adjustment and maintenance to "A" reactor feedwater pump.

12/04 Control rod pattern adjustment complete, commenced 0248'425 PCIOMR 'from'86% thermal power ,sequence "A" "A" reactor feedpump in service, PCIOMR in progress.

2300 'Reactor thermal power at 99% steady state, thermal limited; 12/05 2335 Reduced thermal power from 99% to 60% for MSIV closure,and turbine control valve tests.

12/06 0250 MSIV and turbine control valve tests complete, commenced power ascension.

Commenced'CIOMR from 88% thermal power sequence "A".

0800'500 Reactor thermal power at 99%, thermal limited.

12/12 2345 Reduced thermal, power from 99% to 85% for turbine CV tests'nd SI's.

12/13 0425 Turbine: CV, tests and SI.'s completed, commenced power ascension.

0440 Commenced PCIOMR from 95% thermal power sequence "A".

1500 Reactor thermal power at 99%, maximum flow.

12/22 0305 'Commenced'educing thermal power from 99% to 70% for turbine control valve tests and SI's.

.0345 Turbine control valve tests and SI's complete, commenced power ascension from 70% thermal power.

.'I~inificant ~Oierational:Events Unit:,1 Date Time ;Event 12/22 0700 Commenced PCIOMR from 94/ thermal power -'equence-'"A".

1045 Reactor thermal power at 99/, maximum flow.

12/23 2350 Commenced reducing thermal power from 99/ to remove J MG set, "A" reactor feedpump- and~"B"'on "A"'ecirculation densate booster pump from service for maintenance.

12/24 0500 Reactor therraal power at 55/ holding for maintenance on "A" recirculation MG set, "A" reactor feedpump and "B" condensate booster pump.

0505 "B" condensate booster pump placed in .service, reduced thermal power to 50/ for maintenance on "A" reactor feedpump and "A" recirculation MG set.

0625 "A," recirculation MG set placed in service, increased thermal power to 70/ and holding for "A" reactor feed pump maintenance.

0830 Reduced reac1 or thermal power to 45/ for control rod sequence exchange from "A" to '"B".

1155 Control rod sequence exchange complete, increased there'll power to 47/ and holding for scram testing control rods,.

1430 Scram test complete, commenced power a. cension from 47/ thermal power.,

1730 Commenced PCIOMR from 57/'hermal power sequence "B".

2030 Placed "A'" reactor feedpump in service.

12/26 1500 Reactor ther'mal power at 99/, maximum flow.

12/27 0015 Reduced thermal power to 85/ for turbine contr61 valve test. and SI's.

0330 Turbine control valve tes1 and SI's complete, commenced PCIOMR - sequence 1126 thecal power "B"'eactor at 99/, maximum flow.

12/29 0822 Commenced reducing thermal power .Eor shutdown due to stator cooling fil'ter problems.

1012 Reactor scram, manual, No,. 139 from 41/ thermal power to per:Eorm maintenance on stator coollng water system.

2226 Maintenance complete on stator cooling water, system commenced rod withdrawal f'r startup.

Si nificant Operational Events Unit 1 Date Time Event 12/30 0125 Reactor Critical No. 160.

0725 'Rolled T/G.

0754 Synchronized generator, commenced power ascension.

2145 Commenced PCIOMR from 65% thermal power sequence "B".

12/31 0130 Reactor thermal, power at,82%. holding for possible feed-water heater leak.

0310 "C" string high pressure heaters isolated .for leak repairs.

0420 'Commenced PCIONR from 82% thermal power sequence "B".,

1501 "C" string high pressure heaters placed in, service.

2030'203 Reactor thermal'ower at 99%, maximum flow.

Commenced reducing thermal power from 99% for control rod pattern adjustment.

2400 Reactor thermal power at 58%, control rod pattern adjustment in progress.

S~inificant~O>erati,onal Events Unit 2, Date Time Event 12/01 0001 Reactor thermal power at 40% (RTI-32) xecirculation, pump ramp te. t in progres..

0135 RTX-32 complete, connnenced power ascension from 40%

thermal power.

0848 Commenced PCXOMR from 60% thermal power, - sequence "A".

12/02 2330 Reactor thermal power at 99%, maximum flow.

12/03 0040 Reduced reactor thecal power to 96% due to "B" recirculation puli speed control problems.

1500 Reduced reactor thecal power to 94% due to "B" recirculation pump maintenance (mechanical and

.electrical stops and speed indication),

2050 Maintenance complete on "B" recirculation pump, commenced PCIOMR from 94% thernlal power.

12/04 0030 Reduced reactor thecal power from 97% to 95% for isolation of Bl and B2 high pressure heaters to repai.r leaks..

12/05 0140 Bl and B2 high pressure. heaters back in service, commenced PCXOMR from 95% thermal power sequence "A".

0445 Reactor thermal power at 97%, full core flow.

12/06 1220 Commenced reducing reactor thermal power .for control rod pattern adjustment.

1500 Reactor thermal power at 55%, control rod pattern adjustment in progress.

1600 Control rod . equence exchange complete,,

ascension from 55% thermal power.

chinked'ower 12/07 1000 Commenced PCIOMR from 80% thermal power sequence '"A",

2305 React. or thermal power at 90%, holding to,run a set of TXP's.

12/08 0240 Reduced thermal power to 80% fax turbine control valve tests and SI"s.

0440 Turbine control valve tests and SX's complete commenced power ascension.

0500 Commenced PCIOMR 'f'rom 82% thermal power' sequknc4 "A",'.

1801 React. or thermal power at 99%, thermal limited.

2227 Reducing thermal power from 99% for MSXV SX's and con-trol rod pattern adjustment.

Si nificant 0 erational Events Unit 2 Date Time Event 12/09 0130 Reactor thermal power at 65%, MSIV SI's and control rod pattern adjustment in progress.

'MSIV SI's and rod adjustment complete, commenced

'300 power ascension.

.0400 Commenced PCIOMR from 67% thermal power sequence "A".

12/11 0700 Rea'ctor thermal power at 99%, thermal limited.

12/12 2345 Reducing thermal power to 85% for turbine control valve tests andSI's.

12/13 0001 Reactor thermal power at 85%, turbine control valve tests and .SI's in progress.

0229 Turbine control valve tests and SI's completed, com-menced power ascension.

0230 Commenced PCIOMR'rom 89% thermal power sequence "A".

12'/14 0700 Reactor thermal power at 99%, maximum load (electrical) .

12/17 2230 Reducing thermal power from 99% for isolation of Al and A2 high pressure heaters from service to repair leak on moisture seperator drain pump. instrument line.

2300 Reactor thermal. power at 95%, holding for maintenance on moisture seperator drain pump instrument line.

12'/18 1320 Maintenance complete, Al and A2 heaters back in service, commenced power ascension from 95% thermal power.

2300 Reactor thermal power at 99%, maximum load (electrical).

12/22 0350 Reduced reactor thermal power to 85% for control valve tests and SI's.

0515 Turbine control valve test completed, increase reactor thermal power to -91%, holding for control rod exercise SI 4.3.A.2.

0520 Control rod exercise complete, commenced power ascension from 91% thermal power.

0830 "B" recirculation pump M.G. fluid coupling oil line leaking, reducing thermal power from 95% for repairs

,to oil line.

1014 Maintenance complete .on "B" recirculation pump .M.G.

fluid coupling, oil line', commenced power ascension from 47% thermal power.

1100 Commenced PCIOMR from 94% thermal power sequence "A".

1600 Reactor. thermal power at 99%, maximum flow.

S~i nificant.~O erational Events Unit 2 Date Time Event 12/23 2047 Reduced, thermal power to 70% for maintenance on control rod,driye 38-.35', ~

2340 Ma:Lntenance complete on CRD 38-,35, commenc!ed power ascension.

12/24 1500 Reactor thi rmal power at '99%,, maximum flow.

12/27 0225 Reactor Scram, No. 111 (1)'rom 99% thermal powei when main steam line high radiation monitor was not reset,p'roperly.

1737 Commenced rod withdrawal for startup.

2125 Reactor Critical No. 122.

12/28 0035 Rolled T/G.

0103 Synchronized, generator, commenced .power ascensi'on'.,

1930 Commenced PCIOMR from 72% thermal power 'sequence ".A".

12/29 0942 Reactor thermal power at 99%,maximum 'flow.

1230 Reduced 'thermal power to 90% for control rod drive.

exercise.

1516 CRD exercise complete, commenced PCIOMR from~ 90%

thermal power sequence "A".

12/3O 0005 Reactor thermal power at 99%,, maximum load (electrical).

12/31 2400 Reactor thermal pow'er at 99%, maximum load (electrical).

Si nificant 0 erational Events Unit 3 Date Time Event 12/01 0001 EOC-3 refuel outage in progress.

12/04 0550 Fuel moves started.

12/22 2200 Fuel movement completed.

12/29 0600 Tensioning .reactor vessel head.

12/31 2400 Preparations for RPV hydro and startup test in progress.

(1) Personnel Error

il AVERAGE DAILY.UNIT POWER'LEVEL.

Browns Perry 1 DATE TEI EPHPyE 205-729-6846 MONTH December 1980 DAY AVERAGE DAILYPOWER'LEVEL DAY AVERAGE DAILYPOWER L'EVEL IMWe-Net) I>SIWe>>et) 909 l7 1063 I8 1012'64 l9 1056 7O 1050 1058 1050 21 22 1068 23 1052 24

'>5, 1063 1025 1057 27 1032 lOSS- 105 13 1031 19 420 I

l5 1063 3l 880 ie 1058

'INSTRUCTIONS the lleufest 9 hul>'ne>,:tivut t.

~

'>l/77 On this t'>>r>tlat.!ist lhe uveru 'e daily unit P<>wer!eiel in M'iVe Nel l'>>r each Jay in'the rel)>>rtin>. ln>>>lth. C>>It>i>ute t>)

)

1>

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 56:2 60 Bt.otms Feiry - 2 0ATE ~SL COMPLETED BY Ted Thorn TELEPHONE

>llONTH ~ec.ember DAY AVERAGE DAILYPOl>VER LEVEIL DAY AVERAGE DAILYPO)VER LEVElL.

(M'LVe.N>'t) ('M tVe.N>!t )

713 1083 1037 1044 l9 1072 1002 1073 2l 1628-876 1037 973 1061 1075 93'8 10~79 l0 I >, ~6:I 684'3 103 1080

>~

3l'007 29 3(l 1067 1070 108'7 INSTR L'CTlONS

()>a alai% I>>!>>alt, .Itt t a>: Ja'>:f J>!>'Icily ucait pa>wc;c I>'a>ll an >ilV>.'!N>.'t'.'a>rIa du~y an tla>'cp>>!tiaac a>ac>nail>. (.>>>alp>at>.'a>

llaa.'at'J!c$ l >vita>l>! >>ac!a! Jhv:>t t,

{9/7'71

14 AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

Browns Ferry 3 DATE COMPLETED BY Ted Thorn TELEPHONE 205 729 6846 ilIONTH DAY AVERACE DAILYPOWE R LEVEL DAY AVERAGE DAlLYPOWER LEVEL (MWe.Net) (MWe.Net )

-9 l8'9 20 -4 2I 6 "2

'73

)5 I 26 0'2 27 -5 28 l3 'l9 30 l5 3l

'INSTRUCTIONS On tllls tntnlnt. Ittt tile event ie Jell) nnit In>avt level in M'5'e.Net I'nt each tiny in tlte tepnt ling nnitt tlt. Ciintput<< ltt tile ne Jfcsl Iellnle nteeelvJ(l.

(0/77 )

0 i 15 OPERATING DATA REPORT DOCKET NO.

DATE COKIPLETED BY TELEPHONE J)~~n

~~i846 OPERATING STATUS

l. Unit Name: Browns Ferry Unit 1 Notes December 1 9 0

2. Reporting Period:

p d

3. Licensed Thermal Power (~IBVt):

3293 11

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net Mme):

1065

7. <>Iaxintum Dependable Capacity (Net >>I'IVe:)

1065 S. If Chang<<s Occur in Capacity Ratings (It<<ms Number 3 Through 7) Since Last Report. Give Reasons:

NA

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

10. Reasons For Restrictions, lf.Any:

This Month Yr..to-Date Cumulative

~

11. Hours In Reporting Period 56,282

12. Number Of Hours Reactor Was Critical 34,806.57 369KY7 "

13..Reactor Reserve Shutdown'Hours

14. Hours Generator On-Line 722.30 6 380.09 '3 992. 82,

15. Unit Reserve Shutdown, Hours 0

16. Gross Therinal.Energy Generated (MWH) 2,242,925 19 155 868 93,292,361

~11.111- - -, 763 290.

Ig. iNet Electrical Energy G<<neratcd,(MWH) 723 052 6 061 849 29 863 817

19. Unit Service Factor 97.1 72. 6 60.4

20. Unit Availability Factor 60.4 49.8

22. Unit Capacity Factor. (Using DER Niet) 91. 3 49.8

23. Unit Forced Outage Rate 2.9 7.5 29.3

4. Shutdowns Scheduled Over Nest 6 ><>Ionths(Typ<<, Date, and Duration of Each):

Refuel A ril 1981

25. If Sliut I)own At Fnd Of Report Period. Estimated Date of Startup:

6. Units In Test Status IPri<>r to Conimercial Op<<rationl: F<>rc<<ast Achieved INITIAL CRITICALITY INITIALELECTRICITY CORI<>IERCIAL OPERATION (o/77)

aa 16 OPERATIabpG DATA REPORT DOCl<ET iVO. 50 260 CO41IPLETED DY Dt)n.~m~

TELLPHONE 205=Z2.'M846 OPERATING STATUS Notes

i. Unit Nanre: ~Bnds08~xx!s=~ijJ~

2. Reporting Period: Decembe>r 1~8)

3. Licensed Thermal Power PI>Vt): 3293

4. Namcphtc Rating (Gross 41IWc): 115.'2 S.,Design Electrical Rating (Net i I '): 1 0i65 1098.4

6. iiaximam Dependable Cepaeiry [Grass

7. biaxiraam Dependabie Cepaeiry lNer biWe):

SSSaei:

.~!55~

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

NA

19. Power Level To Which Restricted, lf Any (Net II'We):

.JO. Reasons For Restrictions, If Any:

This Month Yr.-toi-Date Cumulative J I. Hours ln Reporting Period 744 8,784 51,193

.J'7. Number Of Hours Reactor Was Criti:al

13. Reactor Reserve Shutdown Hours 19.0 6 B.,5n4

~~74'~-

12,453.48

14. Hours Generator Ott-Linen 721.37 6~076.65 ~29 74i0. g,'6

15. Unit Reserve Shutdown',llours 0 0 0

16. Cruse Thermal Ener y Gencratcd (MWH) 2., FP), 2Y(~,, 3,7, $ 15643 83, 57i0, 6,43, 17.'ross Electrical, Energy Generated (sl I IVH) 738 400 720,719

, , 5 787 120 ~2t~LJ29

18. Net Electrical'Energy Generated (MWH) 5~6j'~8838 26 950 307,

19. Unit Service Factor 97 ~ 0 69. ! 58.1

20. bnit Availability Factor

%~7. 0 69. 2 58.1 Zl. Unit Capacity. Factor (Using x~lDC Nctl 91.0 60.1 49.4

22. Ut)it Capacity Factor (Using DEIR Net)

&1~.0. 60. 1 49.4

23. Unit Forced Outage Rate 3~

4. Sltutilowns Scheduled Over I'blcxt 6 lrlonths (Type. L)ateand Duration of Each):

$. If Sliut I)@wit At End Of Report I'eriod. Estimated l)ate of Starjtup.

3tp. Units ln Test Status t Prior tii Cumiiierciil Operation): Forecast Achieved IisITIALCRITICALII'Y INITIALELECTR, !CITY CObb(ilERCIA L OIPERATIION (it/77)

17 OPERATING DATA REPORT DOCKET NO.

DATE CO!>IPLETED BY TELEPHONE

~~

1-4-81 2Q5='~%46 OPERATING STATUS

1. Unit Name:

2. Reporting Period: December 1980 3..Licensed Ther>nai Power (MWt):

4. Name late Rating (Gross Mac): 1152

5. Design Electrical Rating (Net 1>I'lVe):

6. >>Iaxi>num Dcpendablc Capacity (Gross MWe):

7. l il i u mD e I)cndable C a p acit y(Net MIVc:

a )inl )

1065

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

NA

.. 9. Poiver Level To Which Restricted, If Any (Nct MWe):

.10. Reasons For Restrictions, If Any This Month Yr..to-Date Cumulative I l. Hours In Reportin Period

~

744 33 648

..12. >Number Of Hours Reactor Was Critical 0 7, 064 25,971.55

13. Reactor Reserve Shutdown Hours 152.58 1,810.89

14. Hours Generator On. Linc 9 25,390

15. Unit Reserve Shutdown llours 0 0

16. Gross Thermal Energy Gcneratcd (MIVIC) 21,257,162 74 365 028

17. Gross Electrical Energy Generated (MPH) 0 7,136,450 24,539,030

18. Net Electrical Energy Generated (l>IWH) 6,936,660 23,824,323

19. Unit Service Factor 0 79.1 75.5

20. Unit Availability, Facti>r 75.5

22. Unit Ca>>acity Factor IUsing DER Niet) 0

23. Unit Fi>reed Oiltage R:ite 0 11.7 9.8

24. Sliutd>>ivns Scheduled Over iNert 6 i>I>>nths(Type. Date. and Duration of Each):

25. If Shut Di>ivn At End Of Rcport Peri>>d. Estimated Date uf Startup:

'6. Units ln Test Status lprii>r I>> C>>n>mcrcial ()pcrati>>n): F>>recast Achie'veil INITIALCRITICALITY I> >ITIALELECTRICITY CO,'>It>I ERCIA L OPERATION (t)/77)

4 0 0

UNIT SIIUTDOWNS AND PO'IVER REDUCTIONS lllk"" f11 .:jft~

COMPLETED EY DATE ~~1

~~m REPORT MONT!I december A C Lice))see Cause A, Corrcit)vc o O Event Action Ii)

EJ Rcport- i T/) Q Prevent Rceurrcn<<e 158 801205 B Derated for turbine control valve and MSIV tests and SI's 159 801222 B Derated for turbine. control valve tests and SI's 160 801233 Maintenance to "A" reactor feedpump "A" recirculation MG set and "B" condensate booster pump 161 801229 F 21.70 A Maintenance to stator cooling system (Replace filters) 162 801231 Derated for control rod pattern adjustment F: Fi)r;ed Rcasi)ll: hlcthod:

S: Schcduleil Exhibit G - Instructions A Equipment Failure (Explain) I .hla nual for Preparation i)f Data B.hIaintenance or Test 2 h(anual Scram.

C. Re fueling linlry Sheets I'or Licensee 3-Auto)natic Scratn. Event Report (LL'R) Fili (NURI'.G.

D Reyilatory Restriction 4 Other (Explain) OI 6I )

I'..Operator Trainint; &. Liccnsc Exan)ination F-Ailn)inistra tive G Operational Lrri>r (Explain)

('t/77) Fxhibit.l - Sainc Source I I.Other (Explai>>)

I~ I el I ~ ~ ~

I ~

I

~ ~ ~

I s I I II ~

I ~ I

~ ~

I ~ ~

~ ~ ~

~ ~ 8 ~ I I ~

UNIT SIIVTDOWNS AND POWER REDUCTIONS DOCKET 80> :3 6 UNIT NAME SaumMr~~ 3 DATE COMPLETED BY J3o~ mao=

REPORT hlONTII ~eetrdser TELEPI ION E ~66 I

C A C>

Llccllscc O 6> Cause A Corrective I)JIc F.vent Action to I/> Report =

C + Picv>.nt Rct.urrcn<<

153 801201 744 C EOC-3 Refuel Outage Cont.

I F: I orced Reason: Method: Exhibit G ~ Instructions S: Schedoie(l A E>luipment Failure (Explain) I Marlual for PrepafJllon of Oat J II hlaintcnance or Test 2.hlanual Scram. Entry Sheets lor Licensee C.Refueling 3.Autontatic Scratn. Event Rcport (I.I R) File INUI(I'.G.

D.Regulatory Restriction 4.Other (Explaini OI6l l I Operat>>r Training 4 License Exami>ration F.Administrative G Op rational Lrror (I:xpl>nnl Exlnbit I ~

Sa>nc Source I I Other (Explain l

0 Ik e

BROliNS FERlB NUCLEAR PLAVRT UNIT ~rrron ELECTRICAL HAINTENANCE SORRY lor the Honth of December . 1980 E ect on Sa e Action Taken Date Sys terr. Component Nature of Operation of Cause of Results 'of To Preclude Haintenance The Reactor Halfunction Half unc tion Recurrence 2/1/80 Diesel 'O'iesel Scheduled ., None, the A bad coil on The bad coil caused Replaced bad coil.

Generator Generator redundant diesel generato signal unit slow operation of on SUDR relay, start test was operable. duration relay, the SUDR relay completed EHI 3. SUD 811 3 allowing an arc to relay operated proper remain across relay contacts 1-2 thus not allowing DG fast start circuit to reset.

ly I

j I

,'R i

fj194429 t

12/3/80 Diesel 'O'iesel Output bkr. NONE A shorted diode A shorted diode in Replaced shorted diod.

Generator Generator 1812 opened in over-speed over-speed trip Reran survei)lance during sur- trip alarm alarm circuit est, diesel'enerate v'eillance circuit. tripped breaker operated properly~

testing (SI 1812. TR 1I189406 BFRO 4.9.A.l.a.) 50-259-8088 I

12/ll/80 CO2 Fire Refrigerant Compressor None. C02 fire Filter giyer Capacity to cool l

Replaced filter Protection compressor on lines freezing protection became saturated CO was slightly ryer and checked System Card'ox unit system remained causing lines to reduced. xpansion valve, located at in service freeze. drooling unit opera~

units 1 6 2 I3roperly. TR !ll7~

diesel gene '- I rators l I

12/14/8( Diesel 'D'iesel Audio alarm NONE DG alarm panel Audio Alarm inop- Replaced bad relay, Generator Generator relay was relay mechani- erable alarm operates found to be cally hanging )eopeely TR919.7031 hanging up Up during sur-veillance testing (SI 4.9.A.l.d)

UPOiiNU PUiUil lWCLLVII PLIIViT UIIZT 1.

ELECTRICAL HAINTENANCE SlMfMY E ecton 'ae 'ction Taken Unte Sj'stem I Component Nature of Operation of 'ause of Results of To Preclude I

,Haintenance The Reactor Halfunction lHalfunction Recurrence I

12/2/80 Reactor 1A, RPS HG HG set was ¹ne. Equipmen Relay contact Burned relays, Replaced w'iring Protection set removed from responded in arm retainer >l.. wiring and trans- and trans'former,.

System service due safe direction rings were former. changed relays to to smoke and gave 4 made of flamma- non-flammable.'type,.

coming from scram. Hinor ble, materials. retainer rings-.

HG set control fire was local- mrr t$ 1 OnrlC7 rl1ni1n1~

LLL Ã JV7LV I ) LL7CVJ hnv ized and rnn-tained within the equipment enclosure; 12/4/80 Radwaste FSV 77-15B Not receiving NONE Closed limit Received no closed 'A'dju'sted limit switch

'System  : a closed'n- switch was indicating light indicating lights dicat J.ng out'f adjust inl cvntrol rooim ~ Operate propeLlyL licht in the meAt. TR fI189278 '

'ontrol room.

I Aa717n p ~ vl/ttv Dv4lrrnvrr l L XII ilLJ

~ vr fl, Deli v I 1l,n R IV unllrn pnni I inn' NnND

~ i \r r r rr Limit. srritr hes Ihdirat inlr inh ts 1 nn Adjusted limit

'ontainment indicating out,of adjust- panel 9-3 did not switches, indicati~

System lights not ment. opera't'e properly. lights and switch~

operating operate properly.

trLvtrr v v'vA L 1 ~Jr ~ TR /$ 203251 12/21/8 HPCI FCV 73-6 ~

Not receiving NONE Open limit ~

Open indicating Tighte'ned open opera-a'alve inul- S'PLLcll GPVLLLLvL J.l.gill. invPeLcltiYe ~ avm ] irlriP sirwiPct cating .light arm was loose. now operates propert for .open TR 8203247 posit'ion o' panel 9-3.

12/22/80 1IPCI Closed ing light for indicat- NONE'ad resistor Closed light =fgr indicating FCV 73-65 Re'placed icating light resister, in-oper-.

ru Vr I J lD 7'2 Vlr Vll I rlVtrrhvL Vll trnllr 1L 07 J7 4rrri rlvonnv 1y TP'i anel was inop- a tive.I 203245

BROliNS EENTSY NUCLEAR PLANT UNIT ELECTRICAL MAINTENANCE SRQhRY

~'

Por the Honth of December 1989 E ect on a e I Action Taken Date Sys tert. Component Nature of Operation of Cause of Results,'of To Preclude Haintenance The Reactor - Halfunction ~ifalfunction Recurrence I

I I

12/29/80 Associated Indicating Handswitch for NONE Blown fuse in Handswitch indicat-C Replaced fuse, indi-Electrical on 'ights normal-alter- indicating ing lights were cating lights operate System panel 9-8 nate feed to light circuit. inoperative. pzaj eely. TR 8201 480V.shutdown board 1B has no indicating lights

BROtPifS FERRY NUCLE)'J< PLANT UNIT 2 .~

ELECTRICAL MAINTENANCE SlkQfhRY For the Honth of December 19 80 ect on 'a e Action Taken Date System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction -R"currence 12/6/80 EEClf FCV 67-49 Open indicat- NONE Bad pushbutton Local control open Replaced bad trans-ing light on light transfor- indicating light former, open indicat-local conirol m&Lv~ inonel aiive ing light transformer

~wi t ch innn- is operable. TR II erative 197013 I

12/7/ 80 Neuiron Neuiron 2A ttl thVUUJ 3 1 G'll NONE, Syst em Durintt EMI 4C Neutron 2A battery Replaced broken Monitorin Battery maintenance continued to found neutron was inoperative. battery per SEMI 27.

System EMI 4C operate pro- 2A battery TR I/193740t 1/8795t

't perly. post broken. J7O7n 1 4 IVA>

Core FCV 75-39 Both open and NONE Bad terminal Indicating lights Replaced bad terminal Spray closed indica block on limit fail to operaie block. TR vl89321 Cooling zing lights traino ~vevnv1u rLVt% I, ag ~

System are en-with

'valve .closed.

12/28/8 Fire TA J9 110 Neat- detected t;fnND Shnr t- ed re] av ,'ondensation acted Removed condensati D'vnt.ant L ~

a n or power due to conden- as a conductor from relay and dr failure sation in zone .across the relay detector box, annunc alarm detector box. coniacis of the ator 1 r d. Ttt ll heat det et tor (TA 202843 39-110) thus giving a false alarm 1

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BRO'iXIR PERRX iXUCLE/Z PLAiNT UIILT 3.

CSSC E UIPllENT HAINTENANCE SQQfARY 'LECTRICAL For the Honth of December 19 80 E ect on Sa e Act ion Taken I Nature of Operation of Cause of Results of To Preclude Date System Component ,'talfunction- Recurrence Haintenance The Reactor Halfunction properly at local panel TRlll89572 Relay 5AK13C Relay 5AK13C HONE Relay contacts Relay 5AK13C some- Aligned relay con-I.2/24/80 CRD i contacted'perated located at sometimes A. ~

4ELI JAIL \AUC 4V

~ 4 4maa9 4 J.ill% 0svn4na L i J.ill) contacts 1g o

~~1 0J J.a P44444 J, arciRlcl caulsinE/ contact mis- causinn relay properly.

relay 5AK15 alignment. 5AK15 and 5AK15C. TR II203130 and'AK15C to chatter.

to chatter.,

BROWHS FERRY NUCLEAR PLANT UNIT ALL INSTRUMENT MAINTENANCE SEQUNY CSSC E VIPMENT FOR, THE MONTH OF December 1980 NATURE EFFECT ON SAFE CAUSE ACTION TAKEN BATE SYSTEM C(&PONENT OF OPERATION OF OF RESULTS OF TO PRECLUDE l MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

)NIT L2-ll Radiation TA-90-144 Calibrate None Setpoint drift Indicated abnormal None Monitoring temperature L2-17 Containmen H M-76-39 Replace None End of sensor Low sensor output New system-to 2

Inerting life replace GE syste JNIT l.2-2 Radiation FI-90-165 Calibrate None Instrument drift Annunciator would None Monitoring not clear L2-ll Residual FI-74-56 Repair None Faulty amplifier Indicated 'flow with None Heat pump off Removal L2-22 Residual TI-74-1368 Repair None PCB corroded Room temperature None Heat indicated downscale

-Removal

BROWNS FERRY NUCLEAR PLANT UNIT CSSC E UIPMENT MECHANICAL MAINTENANCE SUlfffARY For the Month of December ] 9 80 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE HAINTENANCE THE REACTOR MALFUNCTION ffALFUNCTION RECURRENCE

!/1/80 RCIC Steam line drai Valve bonnet None eeking valve Leaking valve Replaced bonnet gasket pot isolation 1'eak a on valves valves TR 166790 RCIC Valve 71-201A Valve seat None (elva leaking Valve leaking Replaced bonnet gasket steam leak on valve Tn 16Fi7A7

!/15 CRD CRD Modules Replaced dia- None reventive None Changed. out repair kit<<

22-31, 26-31 phragms and faintenance and diaphragms 26-39, 18-39 valve internal TR 198949 J. a sn J7a in Jar aJ 14-43, 18-43 22-43, 26-43 30-43$ 22-39 scram iiot val es CRD Modules R eplaced dia- None reventive Changed out repair kit.

30-35, 26-35 p hragms and faintenance and diaphragms 22-35-18-35 14-35, i.0-39 valve internal TR 198949'.

06 47 10~7 14-47, 18-47 22-47, 26-47 scram ilot val es 1 Ieara

<<Ic<< Fuel Pool Valve 78-, 66 Va ve None alee eesll kind Betad. ShaVinga COamalaa RGPalrzaa Packlnag glen(

Cooling ccaceccll ell'ined os when operated on valve TR 202996 2/10 FCV-85-llA and Bad seat None ad seat Flow in excess of Replaced-seat with new FCV-85-11B minimum requirement One I,' ~ rr TR, 158658 fa 1586159

BROMNS FERRY NUCLEAR PIANT UNIT 2 MECHANICAL MAINTENANCE SU1%fARY CSSC E UIP1fENT Por the Month of 19~

EFFECT ON SAPE ACTION TAKEN SYSTEM COMPONENT NATURE OP OPERATION OP CAUSE OP RESULTS OF TO PRECLUDE 1fAINTENANCE THE REACTOR 1fALFUNCTION HALFUNCTION RECURRENCE RCIC 2-71-570 Steam Leak None Packing leak Unknown Tightened nuts on packing gland on valve TR 198933 HPCI Tes't connection Steam blowing None eak on test Unknown Replaced the'/2" pipe on FCV 73-3 through 73-584 connection plug to stop leak

& 73-585 TR 217527

BROWNS FERRY NUCLEAR PLANT UNIT 1 MECHANICAL MAINTENANCE

SUMMARY

I For the Month of December 19 80 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE

!/23/80 High Press HCV-0-26-994 6 Hater leaking i; None 2" water line Hater leakage Replaced section ~f ure Fire HCV-0-26-1400 ruptured 2" PVC pipe Protection Tr 203410 p.

33 OUTAGE

SUMMARY

December 1980 Refuel floor activities progressed well through the month of December with completion of fuel shuffle at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on December 22. Core verification work was completed at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on December 24, and vessel reassembly work started shortly thereafter. Vessel reassembly efforts in preparation for the RPV hydro were complete at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on December 30. At this time emphasis shifted to the drywell valve work remaining in preparation. for hydro. All outage preparations for RPV hydro were complete by the end of this reporting period.

Major modification work which was underway during this reporting period includes:

1. LPCI modification (L1845) completed installation and testing I

of Loop Motor-Generator sets. Loop II terminations and testing are scheduled during the next reporting period.

2. Install raw cooli'ng water pump and strainers (P0214) strainers and pump have, been placed and minor piping and electrical wbrk remains.

3. Replace GE H20 Analyzer Conduit and Cable.,(L2079) piping work was approximately 60% complete and electrical approximately 90% complete.

Other areas of outage involvement include:

1. Limited turbine floor work because turbine disassembly was deferred until the next outage. The principal effort has been with reactor water feed pumps, oil pumps, and associated refurbishment.

2. Eddy current inspections of selected heat exchanger tubes and subsequent repairs as required has been completed.

3. Main steam relief valve removal for off-site testing and repairs. These valves have been reinstalled in preparation for RPV hydro testing.

4. Main steam isolation valve testing revealed seven (of eight total) valves required repairs. The repairs were performed l and the valves are being returned for functional testing. *is

~

yg

~

34 0

OUTAGE

SUMMARY

(Continued)

December 1980 Schedule Remarks The refuel floor activities, which are critical path, have been on schedule when assessecl p'her the revised 46 day~ outage schedule. Currently the expected return to shervice date for Unit 3 Xs Sanctuary 9, 1981. Pactors which may affect this date are H O.,

2 2 modificator.on work, scram discharge header UT devices (P0367) and CCW inlet tunnel )oint repairs.