ML18283B212

January 1978 Monthly Operating Report

ML18283B212
Person / Time
Site:	Browns Ferry
Issue date:	02/10/1978
From:	Dewease J Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
References
Download: ML18283B212 (53)

Text

REGUI ATONY INFQRHATIDN 01STRIBUTIQ'N 'SYSTEM (RTOS)

OI STHIHU f IQN FUR UNCO!" ING HA TEHIAL SO~2 /2SO ge RECT QRGI OEwEASE g G OQCOATK~ Oa/1O/78 hRC tH VALLEY Aurl -OATE RCVO I a2/lo/78 OOC TYPE! I E1TKR l40 lAHZZEO$ HQ COPIES RECEIVEO suBJECTi LTR 1 ENCL 1

(

qQHTHl Y GPER4TINQ REPQHT FQR JANUARY l978 ~

PI ANT NAME t BRQHluS F ERR Y ~ UNI T REVIEWER INITI AL! XEF HRuwNS FERRY UNIT 2 DISTR IBUTER INITIALg HRuwN8 FERRY ~ UNIT a+*4a+*4+*4ww*iiia4 OISTRIBUTIGN QF THIS MATERIAL IS AS FOLLOWS 4*%444*+*+*A*4*40*

RQNTHLY QPKRATIhG REPORT FQR GRAY 80QK PHEPARATIUN ~

<OCSTSteuTION CCOE AOOZ)

POROUS FOH ACTION~ BRAt C~ C SCH~EHCER+ww/2 KNC IN TERNAL 1 'b FILE*~4/KNcL NRC POR+*W/ENCI

. NI e PQR 4GTIIGH ~w/P. ENCL EXtEHHALi l ATHENS ~ 4L+*>/ENCL TIC>>*w/ENCL NSIC~~p/KkCL SNL(NATL46)*+w/ENCL ACRS CAT Seww/a ENCL OISTRIBVTIQNt LTR 10 KPICL 10 CQNVRCL HBR! 780460247 slZE> 1P~$ 2P

I TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602

'~>>

FEB 10 1978 P E N ~ y <<so

~ J I

Nuclear Regulatory Commission Office of Management Information and Program Contxol Washington, D. C. 20555 Gentlemen; Enclosed is the January 1978 Monthly Operating Report for Browns Ferry Nuclear Plant Units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY

. 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, D. C. 20555 (10 copies)

A" 780460247

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT JANUARY 1, 1978 JANUARY 31,, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by Plant Superintendent

TABLE OF CONTENTS Operations Summary . ~ ~ ~ 1 Operational Data . ~ ~ ~ 2 Maintenance. ~ ~ ~ 2 Significant Operational Events . ~ ~ ~ 3 Reportable Occurrences ~ ~ ~ ~ ~ ll Average Daily Unit Power Level . ~ ~ ~ 12

, .Operating-.Data Reports . ~ ~ -.

~ ~ ~ -1 5 Unit Shutdowns and Power Reductions. ~ ~ ~ 18 Plant Maintenance Summary. ~ ~ ~ 21 Instrument Maintenance Summary . ~ 26

0 erations Summar The following summary describes the significant operational activities during the reporting period. In support of this summary, a chronologically ordered log of significant events is included in this report and begins on page 3.

There were 5 Reportable Occurences reported to the NRC during the month of January. They are listed on page 11.

Unit 1 Significant operational events for unit 1 are tabulated by date and time beginning on page 3.

Fuel loading on the unit was completed on January 2. On January 15 the 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> soak commenced to destroy the shoe cover lost in the reactor vessel. The turbine generator was synchronized to the grid on January 19.

On January 18 the unit scrammed.

A summary of maintenance and outage work is shown on pages 21 through 25.

Unit 2 Significant operational events for unit 2 are tabulated by date and time beginning on page 5.

The unit did not scram during the month of January.

A >summary of'maintenance work is shown on pages 21 through 25..

0 erations Summar (Continued)

Unit 3 Significant operational events for unit 3 are tabulated by date and time beginning on page 7, There was one scram on the unit in January. On January 27 the reactor was manually scrammed to accomodate scheduled maintenance.

The radwaste system performed as designed without significant problems. Approximately 2.01'+6 gallons of waste containing 2.97 curies of activity were discharged during the month.

0 erational Data The average daily unit power level for units 1, 2, and 3 is shown on pages 12 through 14.

The operating. data reports for all three units are shown on pages 15 through 17.

Unit shutdowns and power reductions for all three units are shown on pages 18 through 20.

Maintenance Ma)or electrical and mechanical maintenance activities during the month are described on pages 21 through 25 . Instrument maintenance is described on pages 26 through 29 .

Sli.nifir,:nit D>>uratfnnnl Events

'Event Tf nne Unit 1 0000 A total of 602 fuel assemblies placed in the reactor with fuel loadin, activities in progress.

1937 A total of 764 fuel assemblies placed in the reactor, fuel loading activities completed.

0045 'Reactor vessel head torqued in place (re'actor available),

0330 Commenced pressurizing the reactor vessel for hydrostatic leak checks (High pressure, low temperature test).

0350 Reactor vessel pressure at 100 psi. and holding for leak checks.

0445 Reactor vessel pressure at 300 psi and holding for leak checks.

0650 Reactor vessel pressure at 500 psi and holding for leak checks.

~ 0917 -Reactor.,vessel -pressure.-at,1000',psi'nd holding 'for leak

.checks.

1430 Hydrostatic leak checks completed commenced depressuriring the reactor vessel.

1740 . Reactor vessel pressure at: atmospheric pressure.

1620 Commenced rod withdrawal for heatup.

1735 Reactor critical No. 97 Sequence "A" 2106 Reactor vessel pressure at 250 psi and holding for relief valve tests (RTI 26).

SLs.nil i< iut t~n r:it i<innl Events (continued) gP Event D.ate Tire ~vn e (cont) 1/15 0142 Relief value tests completed, commenced increasing pressure-temperature for hot hydrostatic tests.

0415 Reactor vessel at 600 ps', and 370 F and holding for leak checks.

0

,1005 Reactor vessel at 1000 psi and 483.. P, holding for leak .

checks.

1045 Reactor vessel at. 1020 psi and 520 F; holding for leak-checks.

1200 Hydrostatic tests at hot standby conditions'completed, commenced decreasing reactor vessel pressure to 1000 psi.

1300 Reactor thermal power at 3%, commenced 60. hour. fuel soak.

1/18 0115 60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> fuel soak completed.

0230 Commenced power ascension.

1225 Reactor scram No. 84 from 15X'ower.

1427 Commenced rod withdrawal in rod sequence B.:

1626 Reactor critical No. 98.

1/19 0402 Synchronized generator, commenced power ascension.

0700 Reactor thermal po~er at 20X and holding for startup SI's.

1/22 0700 Increased reactor thermal power to 25X.

1/23 0915 Increased reactor thermal power to 37X.

-1/24 =~0700 Adjusting rods for .target patterns at 43X thermal 'power.

Sipnif i c;~nt Onernt irtna1. Events (continued)

Event Time Unit 2 (cont)

D:.te 1/25 1500 Commenced power ascension.

1/26 0013 Reduced power from 54..'o 40/ for turbine bypass valves calibration tests.

0340 Turbine bypass valves calibration tests completed.

Commenced power ascension.

'2300 Commenced-~PC10'ttR .from 62X.:thermal power.

1/28 0205 Reduced. thermal power from 78X to 70X'or turbine C. V.

tests and SI's.

0305 Turbine C. V. tests and SX's completed, commenced PC10>R from 70X thermal power..

1/29 2300 Reactor thermal power at 80X, with a core flow of 100X.

Holding for the remainder of the month, (rod pattern limited).

Unit 2 0000 ,Reactor thermal, power-,.atc60X,,sequenceB, and holding for electrical penetration inspection.

0502 Electrical penetration inspection completed, commenced power ascension.

1130 Commenced PC10MR from 80X thermal power.

1/2 1500 Reactor thermal power at 92X and steady state.

1/4 0700 Reactor thermal power at 91X.

1/5 0700 'eactor thermal power at 90X.

Sig'nil icont 0 ~('.rationxI Evihts (continued)

Event vnft 2 (cont) 0010 Reduced thermal power from 90% to 70% for turbine C. V. t'.sts, SZ's, and re...oval of "A". Reactor feed pump from service for maintenance.

0155 Turbine C. V. tests and SI's completed and holding at 70'hermal power for "A" reactor feed pump maintenance.

0430 "A" reactor feed pump maintenance completed and restored.

to service.

0515. Commenced power ascension with PC10MR from 70% thermal power..

l 2130 Reactor thermal power at 92% and steady state.

0700 Reactor thermal power at 91% and steady state; 0700 Reactor thermal power at 90%.

0700 Reactor thermal power at 89%.

1245 Reduced thermal power from 89% to 70% for turbine C. V.

tests and SI's.

1430 Turbine C. V. tests and SI's completed, commenced power ascension.

1830 Commenced PC10NR from 80% thermal power.

0700 Reactor thermal power at 89% and steady state.

0700 . Reactor thermal power at 88%.

0235 Reduced thermal power from 88% to 70% for Turbine C. V.

'tests 'and ".SI's.

+lgh)~$

Si<.nit'L<::<ut <li<.rat i<3n:<1 1'.v< nts (continued)

Even c n:ie- Unit 2 (cont) 1/21 0410 Turbine C. V. tests and SE's completed, commenced reducing thermal power from 70% to 40% for control rod -swap from "B" to "A" rod sequence...

'500 . Reactor thermal power at 40%, commenced, control rod'wap.

0925 Control rod swap completed, commenced power ascension in sequence'"A".

1/22 0700 'ommenced PC10MR from 67% thermal pawer.

1/26 0120 Reactor thermal power at 93X and steady state.

1/29 0015 Reduced thermal pover from 92X to 70% for turbine C. V.

tests and SI's.

0100 Turbine C. V. tests and SI's completed, commenced power ascension; 0700 Reactor thermal power at 92% and steady state.

1/31. 2400 ..Reactor .thermal, power,,at 91X and,steady state.

Unit 3 0000 Reactor thermal. power at 72%, sequence A,, with power ascension, in progress.

0700 -

Commenced PC10MR from 80% thermal power.

1/2 2010'eactor thermal power at 96% and steady state.

1/3 0030 Reduced thermal pover from 96% to 95% due to EHC high vibration.

'i if%'rant 0 orational Events (continued)

Event Time ~Ui~ (cont)

I 0108 Reduced thermal power from 95X to 70X'or turbine C. V.

tests and SI's.

0240 Turbine C. V. tests and SI's completed>> coaanenced power ascension.

0700 Commenced PC10i'K from 92X thermal po~er.

2300 Reactor 4thermal -power, at,.95X,and,steady,.state.

0054 "B" recirculation pump motor-generator. set brush replacement r

completed, reduced thermal power from '77X to 50X. to restoxe lI "B".recirculation pump to service.,

0135 "B" recirculation pump in service, commenced power ascension.

1230 Commenced PC10MR from 90X thermal power..

0700 Reactor thermal. power at 95% and steady- state.

2240 Reduced thermal power from 95X to 88X for the removal of E condensate demineralizer from service due to resin trap problems. Four other demineralizers flow limiting (High 1'P).

0515 Condensate demineralizer problems resolved, commenced power ascension.

0700 Reactor thermal power at 93X and holding, due to EHC high vibration.

2040 Reduced thermal power from 93X to 83X for the removal of "B" string high pressure heaters from service due to leaks.

'2355 '"B" string hi'gh pressure he-ters in service, commen'ced power ascension.

Sinnific.rrrt r> r rrrtionrri Evi rrts (continued)

Event Tire.e Unit 3 (cont) 1/19 0050 Commenced PC10.'iR from 88% thermal power..

0700 Reactor thermal power at I 93% and steady state.

1/21 . 0110 . Reduced thermal, power from 93% to. 70%,.for, turbine C. V tests and SI's.

,0350 Turbine C. V; tests:,and SI'.s,completed'. commenced power F

ascension.

0452 Commenced PC10HR from 88X thermal power-1500 Reactor thermal power at 93X and steady- state.

1/25 1500 Reduced thermal power from 93% to 90X'ue to EHC high r vibration.

~ ~

1/27 "2105." . 'orrrmenced reducing thermal power to remove ua;it from E

2332'eactor scram No.. 49

'i) service for scheduled maintenance.

, manual, to accommodate outage maintenance work.

1/29 0610 Outage work completed.

0615 Commenced rod withdrawal for startup.

0742 Reactor Critical No. 58 (Sequence B"}.

1305 . Rolled T/G.

1339 . Synchronized generator, commenced, power ascension.

1/30 0730 Commenced PC10MR from 60% thermal power.

-2330 "tReduced ~thermal~power from 76% to 65X for control rod pattern ad) ustment.

-10<<

S fpn t.l [cont <>>i~rat ion:il Evi'nts (continued)

Event Pate P$ +le Unf,t 3 (cont) 1/31 0210 Control rod pattern established, commenced power ascension from 65X thermal power.

1/31 2400 Reactor thermal power at .75K with power, ascension in progress.

(4) Manual scram.

Re ortable Occurrences BE'RO Occurrence Date Unit 1 259/7727'2-28-77 During S;I. testing, an interlock switch mal-functioned which would allow the'efueling bridge to travel over the rector while in the startup mode.

259/781 12-26-77 During refueling a smoke alarm-which would not cle~z was received for auxiliary instru"

~S ment room 1.

259/782 1/ll/78 During normal operation of units 2 and 3 with unit 1 shutdown, continuous monitoring of the =-

stock gases temporarily was lost.

259/783 >/13/78 During plant shutdown, while- performing sur-veillance instruction (SI4.2.B-21) core spray pump discharge pressure switch PS-75-44 exceeded

.the technical specification. setpoint.

Unit Z 260/7716 12-18"77 During power operation following a hot restart, the HPCI flow controller was observed to be in the manual control mode and at a reduced flow'etting when the reactor conditions required the HPCI to be operable with the flow controller in the Automatic mode and set to maintain an injection flow rate of 5000 GPM as required by technical specifications.

-u-

~

AVERAGE DAlLYUNlT POWER LEVEL DOCKET NO.

Brogans Ferry l DATE 2-6-78 COMPLETED BY TELEPHONE 205/729-6846 MONTH Janua 1978 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net)

-9 -11 IS -'14 19 190'02 20 21 204 351

'411

-10 536

-10 549 10 688

'12 731 13 838

-12 850 14 30 31 824 15

-12 INSTRUCTIONS On this format, list the average dailv unit power level in MWe.Net for each dav ia the reporting month. Compute to the nearest whole megawatt.

(9/77)

~0 R. DAlLYUNlT POWER LEVEL DOCKET NO.

Browns Ferry II DATE COMPLETED BY TELEPHONE 205/729-'6846 MONTH Janua 1978 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net)

I 792 934'7 960. '18 ~

930 973 19 909 955 20 946 957 518

'950 659 21'6 70."- 785 869 782

96. 942 10 950 1012 973 979 .

.12 945 978 13 94 g 29 973 14 930 30 982 946. 31 965 937 INSTRUCTIONS Qn this format,!ist the average daily unit power level in MWe.Net for each day in the reporting Inonth. Compute tt~

the nearest whole me awa'.t.

(9/77)

~0

'

R DAILYUNIT POWER LEVEL Browns Ferry III DATE 2-6-78 COMPLETED BY Don Green TELEPHONE 205/729/6846 MONTH January 19 78 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (MWe-Net }

1020

.980 .966 1023 974 1014 932 1014 21 960 1015 967 975 1040 1002 894 1039 961

.26 971 10 1013 883.

"

12 12'3 9&9 '184 939 30 699 14 914 728 31 993 INSTRUCTIONS

. On this format, list the average daily unit power level in MWe.Net for eachday its the reporting tn>>nth. Cr>mpute to

,the nearest whole mega~vat t.

(9/77'l

OPERATING DATA REPORT DOCKET NO.

'DATE COMPLETED SY Do+ Gree+

TELEPHONE 2~05 729- EA6 OPERATING STATUS Drowns Per Notes i

1. Unit Name

2. Reporting Period: ~>ri<<1978

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross A(We):

5; Design Electrical Rating (Net MWe}:

6. Maximum Dependable Capacity (Gross iPIWe}: 1098 T. Maxunum Dependable Capacity (Net MWe): 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 MWe):

10. Reasons For Restrictions, IfAny:

%xis Month ~Yr:to-Date Cumuhtive

11. Hours In Reporting Period 744 744 30 722

12. Number Of Hours Reactor Was Critical 445.56 13,425.44

13. Reactor Reserve Shutdov,n Hours 0 4046.8

14. Hours Generator On-Line 307. 97 12,95 .1

15. Unit Reserve Shutdown llours 0

'LI6.'ross'7Thermal'Energy:GE'.n'crated (MWH) 506,179 32, 879,408

17. Gross Electrical Energy Generated (hf)VH) 162, 230 10,980,250

18. Net Electrical Energy Generated (MWH) 152,617 10,640,964'2.2

19. Unit Service Factor 41. 4 41.4

20. Unit Availability Factor

?1. Unit Capacity Factor (Using MDC Net)

19. 3 K. Unit Capacity Factor (Using DER Net) 19 ~ 3 32.5

23. Unit Forced Outage Rate 4.8 4.8 49.7

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

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

26. Units In Test Status (Prinr,to Commercial Operation): Forecast Achieved INITIAL CRITlCALITY INITIALELECTRICITY COiVlib(ERCIAL OPERATlON

OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY Don Green TELEPHONE ~~~84" OPERATING STATUS Browns Fer IX Notes e

1. Umt Name:

, 2. Reporting Period: Janua

3. Licensed Thermal Po~er (LvIWt):

4. Nameplate Rating (Gross MWe): 15 ~

S. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): 1098 V. Maximum Dependable.Caoacity (Net MWe):

1065

8. 1f Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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

10. Reasons For Restrictions. IfAny:

C This Month ~Ifr:to-Date Cumulative

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical '44 744 744 0

25,633 11 312.23 11,199).77

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 744 10,777.36 0

15. Unit Reserve Shutdown llours

"'16.'Gross'thermal"'Eheig'y Generate'd:(MWH), ' ' t

• 2,112,504 691,800 28,285,641 9,288,750

17. Gross Electrical Energy C:enerated (MWH)

18. Net Electrical Energy Generated (MWH) 673 067 9 015 871'2.0

19. Unit Service Factor 100

20. Unit Availability Factor 100 100 42.0

21. Unit Capacity Factor (Using MDC Net) 84.9. 33 0 W,. Unit Capacity Factor I Using DER Net)

84. 9 33.0

23. Unit'orced Outage Rate 0 0 55.2

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

Refuelin Outa e March 1978

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

,26.,Units ln Test Status (Pri)r to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION

(~I77)

~0 OPERATING DATA REPORT DOCKET NO.

DATE COMPLETED BY Don r rein 8577~i 846 OPERATING STATUS

1. Unit Name Browne Fer III Notes e

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe}:

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. MaxtmumDep e nd able C a p a c ity{ilet hIWe:

}

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

9. Power Level To Which Restricted; IfAny {Net MWe):

10. Reasons For Restrictions, lfAny.

Thh Month Yr:to-Date, , Cumulative.

11. Hours In Reporting Period 744 744 8088.

12. Number Of Hours Reactor Was Critical 711.83 711.83 7407.50

13. Reactor Reserve Shutdown Hours 1.'45 589.'86

14. Houis Generator On-Line 705.88 705.88 7205.19

15. Unit Reserve Shutdown flours 0 0 0 2'4 0

17. Gross Electrical Energy Generated (MWH} 687 910 6 721 780

18. Net Electrical Energy Generated (MWH) 669 715 6 520 621'9.1 19, Unit Service Factor 94.9 94.9

20. Unit Availability Factor 8Q

21. Unit Capacity Factor (Using MDC Net) 84.5 84.5 75.

~A, Unit Capacity Factor (Using DER Net}

23. Unit Forced Outage Rate* Jl 24, Shutdowns Scheduled Over Next 6 Months (Type, Date. and Duration of Each):

84.5 7'5.7 M. If Shut Down At End Of Report Period. Estimated Date of Startup:

.26. Units In Test, Status (pri >r to Commercial.Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRlCITY COMMERCIAL OPERATION

{9/77)

~0 DOCKET NO. 50-259 UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NAME Brows Ferr

-78 I

DATE COMPLETED BY on .reen REPORT MONTll TEL EPIIONE Lice nscc E~ gill Cause &, Corrective Nu. Event gj Action tu Report 4F wQ E~

O Prevent Rccurrcnce 27 7,80101 192. 75 28 780109 227.67 B 29 780118 15.61 A APRM HALFUNCTION 3

F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A.Equipn>ent Failure (Explain) I.Manual for Preparation of Data B Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Autumatic Scram, Event Repurt (LER) File INUREG-D.Regulatory Restriction 4 ther (Explain) OI6 I )

E Operator Training & License Examination F.Administrative 5 G.Operational Error (Explain} Exhtbtt I - Satne Source

(')/77) ll-Other (Explain)

~0 50-260 DOCKET NO.

UNIT SllUTDOWNS AND POWER REDUCTIONS UNIT NAME Hrowhs Fear II DATE C

rl p Liccnscc E~ V~ Cause & Corrective 0 u C-O No. l)ate I Event Q Action to EQ

~U~.c

~

V G CA Report 0 cn O Prevent Recuncnce CJ 0

l 3 F: Forced Reason: Method: Exhibit G - instructions S: Scheduled A-l'.quipmcnt Failure (Explain) l-Manual for Preparation of Dati B Maintenance oi Test 2-Manual Scram. Entry Sheets for Licensee C-Ret'ueling 3-Automatic Scram. Event Report (LER) File (NUREG-D.Regulatory Restriction 4%ther (Explain) 016l )

E-Operator Training & Liccnsc Examination F-Administrative 5 I

G-Operational Errur (Explain) Exhibit I - Sante Source

(')/77) I l-Other (Expl'ain)

~0 DOCKETNO.

" 2 ."

50-2oi UNITSIIUTDOWNS AND PO)PER REDUCIlONS Brot"nn I:r.rrv III D g E 2-6-7.rt r, ~

COMPLETED AY o REPORT MONHI TELEPIIONE 2"5 729 ""4" Llccnsce Cause & Corrective No. Date m Event 'ction lo SCAN Repurt ¹ Prevent Recurrence

~ %

47, 780127 S 38.12 B I 3 F: Forced Reason: Method: Exhibit G ~ Instructioirs S: Scheduled A-Equipmcnt Failure (Explain) I-Manual for Preparation of Data 8-Maintenance ni Test 2.Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Rcport (LER) File (NUREG-D.Regulatory Restriction 4%ther (Explain) OI6I )

E.Operator Training & License Examlnatlun F-Administrative 5 GZperallonal Enur (Explain) Exllibit I - Saltlc Source

('I/77) Hither (Explain)

~0 BROWNS FERRY NUCLEAR PlANT UNIT 2 CSSC E UIPMENT 5KQIANICAL MAINTENANCE SUHMARY For the Month of ""aW 19 7S.

EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE, MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE H PCI Valve 73-5 Repacked None Packing Blown S team blowing Repacked valve

BR01fHS FERRY NUCLEAR P?ANT UNIT 3 CSSC E UIPHENT MECHANICAL MAINTENANCE

SUMMARY

For the Honth of January ].978.

EFFECT ON SAFE ACTION T'diEN WTE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE .OF RESULTS 'OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE CRD Accumulator Unstuck Accumu None Stuck Accumulator Blowing pressure Tightened nut on 58-43 lator gage o-ring 8 Hain Steam Valve 1-176A Repacked valve None Packing Leak at 1 Leak packing>g Installed new packing wO)

7 CSSC FOUIPMEHT y teIE Cori= .Spray Component FCV 75-,57 Nature of Maintenance

.Adjust limit JJf(U

.

(liV l i Qct Gn Operation of The Reactor Hone

~ iiws ate

+i E ~

FLECTRICAL tlAIHTEHAHCE SUNfARY

.Cause of Malfunction 19.

Results of Yalfunction Limit switch out Limit switch not i'L To

% ~

R.--:"rence Adjusted limit switch on Ta An r eclat." e switch in- clos d of adjustment in making up in closed in closed position on position closed position position FCV 75-57. TR 79075 Ri."- "tor; Feedwa tez'. tez .isn' None Uoltage control Inverter isn' Replaced voltage Fejdwater Inverted,. producing 12CV I

cazd bad. producing 120V A.C. control card;TR 68096 A.

/.9 l'ive Smoke Detecto smoke C.'eplace Hone Increased detecto Detector alarming Replaced detector Protection XS-39-15D '. detector. sensitivity dpe with no cause with new model XS-.39-..15D to natural aging /iFT-200. TR 68778 25UV DC.. Chil. 8lO.pain Cell: housing Cell misalignment Cell 810 was replaced Installed new'~ in m;iln bat- bat'teries cr'a'eked " Hone caused cell hous- with a new cell main battery ban~on teries tboard'nver ing to crack when retai~4ug braces U-l. TR 88302 ~

were Kightened

~ ~

0

/14 Main steam MSIV 'A'- limit sQitch. Hone.. 1.imit .sw'itch~ Limit switch caused Adjust limit switch ou out of adjust-. MSIU 'A'utboard 5AK3A relay to drop on HSIV 'A', outboard ment out of adjustment out TR 97373 I/19 Diesel D/G Exhaust flow. Plow switches .bad Exhaust Fan f llaw 'switche Generator Pan 'AB' J'eplace switches one

~,.None on 'A' 'B'D/G to start

'A'ailed Replace on both 'A'.&

exhaust fans Exhqggt..fan .motor f'ans.. 'B'xhaust contr'ols TR" 9760)

/ '.(

1/23 control HS-89-48 Returq spring None Returh spring Hand switch would'not Reglaceif get'up~rin, Drive'od on hand.swit'ch brok'en . return automatically on-."qj-85'-'48.'

broken.; ". 'N""9711) '~

..-:r=.. - . ~

r4~

~

' 1

CSSC EOUIP:fENT ELZCTRZC~L HAINTENANCF, SENARY 19 78

i. <on Tai eil System Component Nature of Operation of . Cause of Results of T~ r eclu'-'e Haintenance The Reactor Y>alfurction . ~<!alfunction R . -..:"ren-e I(PC I HPCI hotwell Motor burned up None Motor burned up Breaker trips after Replhced pump motor pump on pump ~

on hotwell pump each r'eset TR 97668

~y HP~'I LCV 73-8 Solenoid coil . None Coil burned .up Level ann. in turbine Replaced solenoid coi exh; drain pot.

~%

burned up TR 85522

~ i I

~ i

~ ~ ~

I

'

• g% qf

I ~~i "+ ~

I ~ ~

. ~ ~ I g4~

r'( '

L:~ '+ ~ .

+ ~

~ ~

~ ~

e

~0 CSSC FOUIBENT HLECTRlCAL 1fAIHTENA!'CE SU'"GORY I:or the llonth of 19~8

'z ect on ale A "ion To~en System Component Nature of Opera tion of Cause of Results of T) ".rec-u~e Maintenance The Reactor <<fal function l".alfunction

' Tighten set Set screws loose Limit switch isn'

/28 R11R . HCV 74.:4g None Tightened set screw screws on 'limi on limit switch giving an open and adjusted.limit switch. indication. swiicl>. TR 79577 r

. (28 1fain steam HSIV 1-'26 Cl'ose limit . Hon'e Limit switch bad Green light stays Replaced limit switcl

)

switch sticldn & limit switch op after red light syitch and '.adjusted out of ad)ustmen comes. on. li'v.it arm.

TR' 67268-69696

~ 4 I" '

Pr'imary . FCP '64 28D'. & Red light: Hone,. Bad limit switch Red light wouldn' Replaced limit switcl Containmen failed.to come cpme on. TR 79589-67003- 00-on - . -.:. 97758

, )

) ~ rr'\ ~ ~

I t4 Vt I

I

~ r ~

r>r 7

~ ~

' '

~ ~

J 0

~ ~

~ I

~

' )

~ ~

~ s

~0

~ ~ ~ ~

~ ~

~ ~

~ ~

) ~: ~ ~ I

~ I ~

~ ~ I ~ ~ ~ ~ ~

I ~ ~ ~ ~ I ~ ~ I

~

) ~ ~ ~

~ I ~ ~

~ ~

~ ~ ~ II ~ ~ II ~ ~

~ I 0 ~ ~ ~ ~ I ~ ~ ~ ~

~ ~

~ ~

~ ~

L' ~ ~

~ ~

~ 0

~ ~ ~ ~ ~ ~

~ I ~

~ ~

$ f ~ ~ ~ ~ ~ I I ~ II ~ ~ ~ ~

~ ~ ~ II ~ ~ ~

~ ~

'

~ ~ I ~ II ~ ~

~ ~ ~

i~ I . ~ e

~ II ~ \

RROlB<E FERRY NUCLEAR PLANT UNTT INSTRUf fFNT MAINTENANCE SUf fHARY FOR TllE MONTH OF ry , 1978 CSSC Equipment Effect. on Safe Action Taken Nature of Operation of " Cause of Results of to preclude te System Component Maintenance the reactor 'Malfunction Halfunction recurrence 3 . CRD P dI-85-17 Calibration None Instrument Drift False Indication None tw 6 Contain- 0 R-76 2 Maintenance None Low Amplifier Gain Slow Response 'eplaced ment Component

'ilution Primary PdI-64-137:& Calibration None Instrument Drift Readings Disagree'-:. None Contain- 138 tnent Primary PR-64-.50 Maintenance None Bad Amplifier Board Low Pressure Ind. Replaced Contain-ment Component Core PdA-75-28 .Calibration None Instrument Drift alse Alarm Replaced Spray Switch

-'12 PdA-85-10 Calibration None Instrument Drift alse Alarm None

-18 RCIC TS-71-41A Maintenance None Bsd Relay ould not test Replaced Component

.-28 CRD PCV-85-66,67 Calibration None Valve Stroke Ad)ustment mproper Control keestablished

.-28 Feedwater LI-3-206 Stroke

. Calibration None Instrument Drift evel Indication one

,=28 Contain- 0 M-76-42 Replacement None Faulty Sensors Incorrect Oxygen ment 2 onsidering .

0 M-76-43 Indication ew Monitonin]

Inerting 2 System

~-

~ ~

~

~ ~

~ ~

I ~ ~ ~ ~ ~

~ \ ~ ~ I

~ ~

~ ~ ~ ~ 'l ~

o o

Ill

~ I O

~ ~

~ ~ ~ I

~ ~ ~

It o ~

~ I ~ I ~ II o I

~ ~

~ ~ ~ ~

~ 'I ~ ~

' I lo

~ ~ I ~ I'

~

~ I ~ Il ~ It I~

0~