ML18283B212
| 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 OI STHIHU f IQN FUR UNCO!" ING HA TEHIAL RECT QRGI OEwEASE g G hRC tH VALLEY Aurl OOC TYPE!I E1TKR l40 lAHZZEO$HQ (suBJECTi qQHTHl Y GPER4TINQ REPQHT FQR JANUARY l978~(RTOS)SO~2/2SO ge OQCOATK~Oa/1O/78-OATE RCVO I a2/lo/78 COPIES RECEIVEO LTR 1 ENCL 1 REVIEWER INI TI AL!XEF DISTR IBUTER INITIAL g RQNTHLY QPKRATIhG REPORT FQR GRAY 80QK PHEPARATIUN
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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P.O.Box 2000 Decatur, Alabama 35602 FEB 10 1978'~>>Nuclear Regulatory Commission Office of Management Information and Program Contxol Washington, D.C.20555 P E N~y<<so~J I 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.Operational Data.~~~1~~~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 1937 A total of 602 fuel assemblies placed in the reactor with fuel loadin, activities in progress.A total of 764 fuel assemblies placed in the reactor, fuel loading activities completed.
0045 0330'Reactor vessel head torqued in place (re'actor available), Commenced pressurizing the reactor vessel for hydrostatic 0350 leak checks (High pressure, low temperature test).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)
Event gP D.ate Tire~vn e (cont)1/15 0142 0415 Relief value tests completed, commenced increasing pressure-temperature for hot hydrostatic tests.Reactor vessel at 600 ps', and 370 F and holding for leak checks.,1005 1045 Reactor vessel at 1000 psi and 483..P, holding for leak.0 checks.Reactor vessel at.1020 psi and 520 F;holding for leak-checks.1/18 1200 1300 0115 0230 Hydrostatic tests at hot standby conditions'completed, commenced decreasing reactor vessel pressure to 1000 psi.Reactor thermal power at 3%, commenced 60.hour.fuel soak.60 hour6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> fuel soak completed.
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.1/23-1/24 0915 Increased reactor thermal power to 37X.=~0700 Adjusting rods for.target patterns at 43X thermal'power.
Sipnif i c;~nt Onernt irtna1.Events (continued)
Event D:.te 1/25 Time 1500 Unit 2 (cont)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.
1/28'2300 0205 0305 Commenced-~PC10'ttR.from 62X.:thermal power.Reduced.thermal power from 78X to 70X'or turbine C.V.tests and SI's.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.
1/2 1/4 1/5 1130 Commenced PC10MR from 80X thermal power.1500 Reactor thermal power at 92X and steady state.0700 Reactor thermal power at 91X.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 f eed 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 1/29 0120 0015 Reactor thermal power at 93X and steady state.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; 1/31.0700 Reactor thermal power at 92%and steady state.2400..Reactor.thermal, power,,at 91X and,steady state.Unit 3 0000 Reactor thermal.power at 72%, sequence A,, with power ascension, in progress.1/2 1/3 0700-Commenced PC10MR from 80%thermal power.2010'eactor thermal power at 96%and steady state.0030 Reduced thermal pover from 96%to 95%due to EHC high vibration.
'i if%'rant 0 orational Events (continued)
Event Time 0108 0240~Ui~(cont)I Reduced thermal power from 95X to 70X'or turbine C.V.tests and SI's.Turbine C.V.tests and SI's completed>>
coaanenced power 0700 2300 ascension.
Commenced PC10i'K from 92X thermal po~er.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 1230 0700"B" recirculation pump in service, commenced power ascension.
Commenced PC10MR from 90X thermal power..Reactor thermal.power at 95%and steady-state.2240 0515 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).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..1/21 0700 Reactor thermal power at 93%and steady state.I.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 1/27 vibration.
r~~"2105.".'orrrmenced reducing thermal power to remove ua;it from E service for scheduled maintenance.
2332'eactor scram No..49 , manual, to accommodate outage'i)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.1/30 1339.Synchronized generator, commenced, power ascension.
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.Manual scram.(4)
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=-259/783 stock gases temporarily was lost.>/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.260/7716 12-18"77 Unit Z 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 DAlLY UNlT POWER LEVEL DOCKET NO.Brogans Ferry l DATE 2-6-78 COMPLETED BY TELEPHONE 205/729-6846 MONTH Janua 1978 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)-9 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)-11 IS 19 20 21-'14 190'02 204 351 10'12 13 14 15-10-10-12-12 30 31'411 536 549 688 731 838 850 824 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.DAlLY UNlT POWER LEVEL DOCKET NO.Browns Ferry II DATE COMPLETED BY TELEPHONE 205/729-'6846 MONTH Janua 1978 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)I 792 DAY AVERAGE DAILY POWER LEVEL (MWe-Net)934'7 10.12 13 14 960.973 955 957'950 70."-869 96.950 973 945 94 g 930 946.937'18 19 20 21'6 29 30 31~930 909 946 518 659 785 782 942 1012 979.978 973 982 965 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 DAILY UNIT POWER LEVEL Browns Ferry III DATE 2-6-78 COMPLETED BY Don Green TELEPHONE 205/729/6846 MONTH January 19 78 DAY AVERAGE DAILY POWER LEVEL (MWe-Net).980 1023 1014 DAY AVERAGE DAILY POWER LEVEL (MWe-Net}1020.966 974 932 10" 12'3 14 1014 1015 975 1002 1039 1013 9&9 939 914 993 21.26 30 31 960 967 1040 894 961 971 883.12'184 699 728 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 Notes i 1.Unit Name Drowns Per 2.Reporting Period:~>ri<<1978 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross A(We): 1152 5;Design Electrical Rating (Net MWe}: 6.Maximum Dependable Capacity (Gross iPIWe}: 1098 1065 T.Maxunum Dependable Capacity (Net MWe): 8.If Changes 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, If Any:%xis Month~Yr:to-Date 744 445.56 0 307.97 506,179 162, 230 152,617 41.4 19~3 4.8 11.Hours In Reporting Period 744 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdov,n Hours 14.Hours Generator On-Line 15.Unit Reserve Shutdown llours'LI6.'ross'7Thermal'Energy:GE'.n'crated (MWH)17.Gross Electrical Energy Generated (hf)VH)18.Net Electrical Energy Generated (MWH)19.Unit Service Factor 41.4 20.Unit Availability Factor?1.Unit Capacity Factor (Using MDC Net)19.3 K.Unit Capacity Factor (Using DER Net)23.Unit Forced Outage Rate 4.8 24.Shutdowns Scheduled Ov:r iVext 6 Months (Type.Date.and Duration of Each): Cumuhtive 30 722 13,425.44 4046.8 12,95.1 0 32, 879,408 10,980,250 10,640,964'2.2 32.5 49.7 25.If Shut Down At End Of Report Perind.Estimated Date of Startup: 26.Units In Test Status (Prinr,to Commercial Operation):
Forecast Achieved INITIA L CRITlCA LITY INITIAL ELECTRICITY COiVlib(ERCIA L OPERATlON
OPERATING DATA REPORT DOCKET NO.DATE COMPLETED BY Don Green TELEPHONE~~~84" OPERATING STATUS 1.Umt Name: Browns Fer IX , 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): V.Maximum Dependable.Caoacity (Net MWe): 1098 1065 Notes e 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): 10.Reasons For Restrictions.
If Any: I A C This Month~Ifr:to-Date Cumulative 744 744 0 744 2,112,504 691,800 673 067 100 100 84.9.84.9 0 11.Hours In Reporting Period 12.Number Of Hours Reactor Was Critical'44 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line 15.Unit Reserve Shutdown llours 0"'16.'Gross'thermal"'Eheig'y Generate'd:(MWH),*17.Gross Electrical Energy C:enerated (MWH)t 18.Net Electrical Energy Generated (MWH)19.Unit Service Factor 20.Unit Availability Factor 100 21.Unit Capacity Factor (Using MDC Net)W,.Unit Capacity Factor I Using DER Net)23.Unit'orced Outage Rate 0'24.Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): Refuelin Outa e March 1978 25,633 11 312.23 11,199).77 10,777.36 28,285,641 9,288,750 9 015 871'2.0 42.0 33 0 33.0 55.2 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 INITIAL CRITICA LITY INITIAL ELECTRICITY COMMERCIAL OPERATION (~I77)
~0 OPERATING DATA REPORT DOCKET NO.DATE COMPLETED BY Don r rein 8577~i 846 OPERATING STATUS Notes e 1.Unit Name Browne Fer III 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross MWe}: 1152 5.Design Electrical Rating (Net MWe): 6.Maximum Dependable Capacity (Gross MWe): e able a a it let hIWe: 7.MaxtmumDep nd C p c y{i}8.If Changes 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, lf Any.Thh Month Yr:to-Date, , Cumulative.
8088.7407.50 711.83 711.83 589.'86 1.'45 705.88 7205.19 0 0 2'4 0 687 910 6 721 780 669 715 6 520 621'9.1 94.9 8Q 84.5 75.7'5.7 84.5 11.Hours In Reporting Period 744 744 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Houis Generator On-Line 705.88 15.Unit Reserve Shutdown flours 0 17.Gross Electrical Energy Generated (MWH}18.Net Electrical Energy Generated (MWH)19, Unit Service Factor 94.9 20.Unit Availability Factor 21.Unit Capacity Factor (Using MDC Net)84.5~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): 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 INITIAL CRITICA LITY INITIAL ELECTRlCITY COMMERCIAL OPERATION{9/77)
~0 UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT MONTll DOCKET NO.UNIT NAME DATE COMPLETED BY TEL EPIIONE 50-259 Brows Ferr I--78 on.reen Nu.Lice nscc Event Report 4F E~wQ gj gill E~O Cause&, Corrective Action tu Prevent Rccurrcnce 27 28 29 7,80101 780109 780118 192.75 227.67 B 15.61 A APRM HALFUNCTION F: Forced S: Scheduled (')/77)Reason: A.Equipn>ent Failure (Explain)B Maintenance or Test C-Refueling D.Regulatory Restriction E Operator Training&License Examination F.Administrative G.Operational Error (Explain}ll-Other (Explain)3 Method: I.Manual 2-Manual Scram.3-Autumatic Scram, 4 ther (Explain)5 Exhibit G-Instructions for Preparation of Data Entry Sheets for Licensee Event Repurt (LER)File INUREG-OI6 I)Exhtbtt I-Satne Source
~0 UNIT SllUTDOWNS AND POWER REDUCTIONS 50-260 DOCKET NO.UNIT NAME Hrowhs Fear II DATE No.l)ate rl~I V p U~.c~CA 0 Liccnscc Event Report 0 E~cn G C V~0 C-u Q O EQ O CJ Cause&Corrective Action to Prevent Recuncnce l F: Forced S: Scheduled (')/77)Reason: A-l'.quipmcnt Failure (Explain)B Maintenance oi Test C-Ret'ueling D.Regulatory Restriction E-Operator Training&Liccnsc Examination F-Administrative G-Operational Errur (Explain)I l-Other (Expl'ain) 3 Method: l-Manual 2-Manual Scram.3-Automatic Scram.4%ther (Explain)5 I Exhibit G-instructions for Preparation of Dati Entry Sheets for Licensee Event Report (LER)File (NUREG-016l)Exhibit I-Sante Source
~0 UNIT SIIUTDOWNS AND PO)PER REDUCIlONS REPORT MONHI 50-2oi DOCKETNO." 2." Brot"nn I:r.rrv III D g E 2-6-7.rt COMPLETED AY o r,~TELEPIIONE 2"5 729""4" No.Date m SCAN Llccnsce Event Repurt¹Cause&Corrective
'ction lo Prevent Recurrence
~%47, 780127 S 38.12 B I F: Forced S: Scheduled ('I/77)Reason: A-Equipmcnt Failure (Explain)8-Maintenance ni Test C-Refueling D.Regulatory Restriction E.Operator Training&License Examlnatlun F-Administrative GZperallonal Enur (Explain)Hither (Explain)3 Method: I-Manual 2.Manual Scram.3-Automatic Scram.4%ther (Explain)Exhibit G~Instructioirs for Preparation of Data Entry Sheets for Licensee Event Rcport (LER)File (NUREG-OI6I)5 Exllibit I-Saltlc Source
~0 CSSC E UIPMENT BROWNS FERRY NUCLEAR PlANT UNIT 2 5KQIANICAL MAINTENANCE SUHMARY For the Month of""aW 19 7S.SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE, RECURRENCE H PCI Valve 73-5 Repacked None Packing Blown S team blowing Repacked valve CSSC E UIPHENT BR01fHS FERRY NUCLEAR P?ANT UNIT 3 MECHANICAL MAINTENANCE
SUMMARY
For the Honth of January].978.WTE SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE.OF MALFUNCTION RESULTS'OF MALFUNCTION ACTION T'diEN TO PRECLUDE RECURRENCE CRD Accumulator 58-43 Unstuck Accumu lator None Stuck Accumulator Blowing pressure gage Tightened nut on o-ring 8 Hain Steam Valve 1-176A Repacked valve None Packing Leak Leak at packing>g 1 Installed new packing wO)
CSSC FOUIPMEHT JJf(U (liV l i~iiws+i.FLECTRICAL tlAIHTEHAHCE SUNfARY E~19.y teIE Component Nature of Maintenance Qct Gn ate Operation of The Reactor.Cause of Malfunction Results of Yalfunction i'L%~on Ta An To r eclat." e R.--:"rence 7 Cori=.Spray FCV 75-,57.Adjust limit Hone switch in-clos d position Limit switch out of adjustment in closed position Limit switch not making up in closed position Adjusted limit switch in closed position on FCV 75-57.TR 79075/.9/14 Ri."-"tor;Fejdwater l'ive Protection 25UV DC..m;iln bat-teries Main steam Feedwa tez'.Inverted,.
Smoke Detecto XS-39-15D'.Chil.8lO.pain bat'teries MSIV'A'-ou tboard'nver tez.isn'producing 12CV A.C.'eplace smoke detector.XS-.39-..15D Cell: housing cr'a'eked" limit sQitch.out of adjust-.ment None I Hone Hone Hone..Uoltage control cazd bad.-Increased detecto sensitivity dpe to natural aging Cell misalignment caused cell hous-ing to crack when retai~4ug braces were Kightened 0 1.imit.sw'itch~MSIU'A'utboard out of adjustment Inverter isn'producing 120V A.C.Detector alarming with no cause Cell 810 was replaced with a new cell Limit switch caused 5AK3A relay to drop out Replaced voltage control card;TR 68096 Replaced detector with new model/iFT-200.TR 68778 Installed new'~in main battery ban~on U-l.TR 88302~~~Adjust limit switch on HSIV'A', outboard TR 97373 I/19 Diesel Generator D/G Exhaust Pan'AB'J'eplace flow.switches one exhaust fans~,.None Plow switches.bad on'AB'D/G Exhqggt..fan.motor contr'ols Exhaust Fan'A'ailed to start Replace f llaw'switche on both'A'.&'B'xhaust f'ans..TR" 9760)/'.(1/23 control'od Drive HS-89-48 Returq spring on hand.swit'ch broken.;".None Returh spring brok'en.Hand switch would'not return automatically Reglaceif get'up~rin, on-."qj-85'-'48.'
'N""9711)'~r4~..-:r=..-.~1~'
CSSC EOUIP:fENT ELZCTRZC~L HAINTENANCF, SENARY 19 78 System I(PC I HP~'I Component HPCI hotwell pump~y LCV 73-8~%Nature of Haintenance Motor burned up on pump~Solenoid coil burned up Operation of The Reactor None.None.Cause of Y>alfurction
.Motor burned up on hotwell pump Coil burned.up Results of~<!alfunction Breaker trips after each r'eset Level ann.in turbine exh;drain pot.i.<on Tai eil T~r eclu'-'e R.-..:"ren-e Replhced pump motor TR 97668 Replaced solenoid coi TR 85522~i I~i~~~I'*g%qf~~~~e.I~+~~~i"+~I~~~g4~I r'('L:~'+~.
~0 CSSC FOUIBENT HLECTRlCAL 1fAIHTENA!'CE SU'"GORY I:or the llonth of 19~8 System/28 R11R'.Component HCV 74.-:4g Nature of Maintenance Tighten set screws on'limi switch.'z ect on ale Opera tion of The Reactor None Cause of<<fal function Set screws loose on limit switch Results of l".alfunction Limit switch isn'giving an open indication.
A"ion To~en T)".rec-u~e Tightened set screw and adjusted.limit swiicl>.TR 79577.(28 1fain steam)r HSIV 1-'26 Cl'ose limit.switch sticldn Hon'e Limit switch bad&limit switch out of ad)ustmen Green light stays op after red light comes.on.Replaced limit switcl syitch and'.adjusted li'v.it arm.TR'67268-69696 Pr'imary.Containmen
~4 FCP'64 28D'.&I" Red light: failed.to come on-.-.:.Hone,.Bad limit switch Red light wouldn'cpme on.'Replaced limit switcl TR 79589-67003-00-97758 ,))~rr'\~~I t4 Vt I I~r~~~r>r 7~~J~I~~)~'~~0
~s~0
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CSSC Equipment RROlB<E FERRY NUCLEAR PLANT UNTT INSTRUf fFNT MAINTENANCE SUf fHARY FOR TllE MONTH OF ry , 1978 te System Component Nature of Maintenance Effect.on Safe Operation of the reactor Cause of"'Malfunction Results of Halfunction Action Taken to preclude recurrence 3.CRD 6 Contain-ment'ilution P dI-85-17 0 R-76-41-2 Calibration Maintenance None None Instrument Drift Low Amplifier Gain False Indication Slow Response None'eplaced Component tw Primary Contain-tnent PdI-64-137:&
138 Calibration None Instrument Drift Readings Disagree'-:.
None Primary Contain-ment PR-64-.50 Maintenance None Bad Amplifier Board Low Pressure Ind.Replaced Component Core Spray PdA-75-28.Calibration None Instrument Drift alse Alarm Replaced Switch-'12-18 RCIC.-28 CRD ,=28 Contain-ment Inerting.-28.Feedwater PdA-85-10 TS-71-41A Calibration Maintenance LI-3-206 0 M-76-42 2 0 M-76-43 2 Calibration Replacement PCV-85-66,67 Calibration None None None None None Instrument Drift Bsd Relay alse Alarm ould not test Instrument Drift evel Indication Faulty Sensors Incorrect Oxygen Indication Valve Stroke Ad)ustment mproper Control None Replaced Component keestablished Stroke one onsidering
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