ML18024B233

Forwards Monthly Operating Repts for Dec 1979

ML18024B233
Person / Time
Site:	Browns Ferry
Issue date:	01/09/1980
From:	ABERCROMBIE H L TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF MANAGEMENT AND PROGRAM ANALYSIS (MPA)
Shared Package
ML18024B234	List: ML18024B233 ML18024B236
References
NUDOCS 8001150488
Download: ML18024B233 (32)

Text

TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT December 1, 1979-December 31, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By

fi~c P ant S erintendent TABLE OF CONTENTS Operations Summary.Refueling Information Significant Operational Events Average Daily Unit Power Level lo Operating Data Reports 13 Unit Shutdowns and Power Reductions.

16 Plant Maintenance 19 Outage Summary~1~~~~~~26

0 erations Summar The following summary describes the significant operational activities during the reporting period.Tn support of this summary, a chronological log of significant events is included in this report.There were fourteen reportable occurrences reported to the NRC during the month of December.Unit 1 There were no scrams on the unit during the month.Unit 2 There were three scrams on the unit during the month.On December 2, the reactor scrammed due to abrupt movement of the turbine control valves apparently caused by EHC pressure control problems.The turbine control valves abruptly opened, then started closing, leading to a high neutron flux scram.The reactor was manually scrammed on December 13 to investigate vibration on the 2A recirculation motor, pump, and associated piping.On December 17, the reactor was manually scrammed for implementation of modifica-tions of certain PCIS valves and the installation of acoustic monitoring instrumentation on the MSRV's.Unit 3 0 erations Summa (Continued)

Unit 3 Unit startup (BOC-3)following a refuel outage began on December 6.The unit scrammed once during the month.On December 30, the reactor was manually scrammed to install overhead cables from the cooling tower switch gear to the bus tie boards.Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows: Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line Feedwater nozzle Closure studs 0.00421 0.20264 0.17644 0.00317 0.13592 0.11572 0.00283 0.10480 0.08561 Note: This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.

Common S stems Approximately 1.13E+06 gallons of waste liquid were discharged containing 2.75E+00 curies of activity.

Refuelin Information Unit 2 Unit 1 is scheduled for its third refueling beginning on or about January 3, 1980, with a restart date of February 19, 1980.This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, LPCI modifications, installing acoustical monitors on KSRV's, and containment isolation modifications.

There are 764 fuel assemblies in the reactor vessel.The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies, two 8 x 8 R fuel assemblies, and 252 new fuel assemblies.

Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 720 assemblies.

With present capacity, Unit 1 does not have full core discharge capability in the pool.Unit 2'I Unit 2 is scheduled for its third refueling beginning on September 1, 1980, with a scheduled restart date of October 7, 1980.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 will be submitted to the NRC before the outage.This refueling involves replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.

There are 764 fuel assemblies in the reactor vessel.At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool.The present storage capacity of the spent fuel pool is 1080 assemblies.

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

Refuelin Information (Continued)

Unit 3 Unit 3 resumed power operation December 8, 1979, after its second refuel outage which began August 24, 1979.Unit 3 is scheduled for its third refueling beginning on September 6, 1980, with a scheduled restart date of October ll, 1980.This EOC-3 refueli'ng involves loading additional 8 x 8 R (retrofit) assemblies into the core.There are 764 fuel assemblies presently in the reactor vessel.There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool.The present storage capacity of the spent fuel pool is 1528 assemblies.

With present capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

Si nificant Operational Events Unit 1 Date Time Event 12/01/79 0001 0020 0150 0700 Reactor thermal power at 92%, core limited Reduced thermal power from 92%to 80%for turbine C.V.tests and SI's Turbine C.V.tests and SI's completed, commenced power ascension Reactor thermal power at 91%, core limited 12/03/79 1500 12/05/79 0700 12/07/79 2115 2143 2310 Reactor thermal power at 90%, core limited Reactor thermal power at 89%, core limited Reduced thermal power from 89%to 75%for turbine C.V.tests and SI's a Turbine C.V.tests and SI's completed, commenced power ascension Commenced PCIOMR from 82%thermal power 12/08/79 1500 12/10/79 0700 1500 12/12/79 1500 12/14/79 2300 12/17/79 1500 12/21/79 1500 12/30/79 0930 1620 1730 Reactor thermal power at 89%, core limited Reactor thermal power at 88%, core limited Reactor thermal power at 88%, core limited Reactor thermal power at 87%, core limited Reactor thermal power at 86%, core limited Reactor thermal power at 85%, core limited Reactor thermal power at 84%, core limited Peduced thermal power from 84%to 73%for control rod scram testing Control rod scram testing completed, commenced power ascension Reactor thermal power at 84%, core limited 12/31/79 2400 Reactor thermal power at 84%, core limited Si nificant 0 erational Events'Unit 2 Date Time Event 12/Ol/79 0001 1200 12/02/79 0555 0755 1202 1417 1439 12/03/79 0020 0755 1500 Reactor thermal power at 65%, sequence"B" with power ascension in progress Commenced FCIOM from 80%thermal power Reactor scram no.89 from 100%thermal power (suspected (1)EHC pressure regulator printed circuit board problems caused the turb control valves to open excessively and then abruptly began closing)Commenced rod withdrawal Reactor critical no.100 Rolled T/G Synchronized generatory, commenced power ascension , Reduced thermal power from 70%to 65%for control rod pattern adjustment Control.rod pattern adjustment completed, commenced power ascension Reactor thermal power at 70%, holding for"A" reactor feedpump vibration checks 12/05/79 0040 0400 Commenced power ascension from 70%thermal power Reduced thermal power from 90%to 70%for removal of"A" reactor feedoump from service for maintenance 12/08/79 0030 0220 0730 Connnenced turbine C.V.tests and SI's Completed turbine C.V.tests and ST.'s, commenced power ascension from 70%thermal power Reactor thermal power at 75%, holding for"A"'reactor feedpump maintenance 12/09/79 2200"A" reactor feedpump maintenance completed, connnenced power ascension 12/10/79 0130 2348 Commenced PCXOHR frcm 80%thermal power Reactor thermal power at 96%, holding due to excessive vibration on"A" recirculation pump 12/10/79 0700 Reduced thermal power from 96%to 94%due to excessive vibration on"A" recirculation oump 12/13/79 2000 2204 Commenced reducing thermal power to shutdown for"A" recirculation pump maintenance Reactor scram no.90 manual from 40%thermal power to acconnnodate maintenance to"A" recirculation pump 12/14/79 2005 Maintenance completed on 2A recirculation pump, holding for maintenance on FCV-1-55 valve 1

Si nificant 0 erational Events Unit 2 Date Tfrae Event 12/15/79 1821 1930 2347 IMntenance completed on FCV-1-55 valve, commenced rod withdrawal for startup Reactor critical no.101 Rolled T/G-could not reach rated spped, EHC problems (electronic card)12/16/79 0118 0125 0330 2300 Turbine tripped Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOHR from 78%thermal power 12/17/79 0035 0245 2122 2220 Reactor thermal power at 85%, holding for turbine C.V.tests and SI's Turbine C.V.tests and SI's completed, commenced PCIONR from 85%thermal power Commenced reducing thermal power from 90%for shutdown for modifications Reactor scram no.91 manual from 35%'hermal power to accommodate PCIS post modification 12/18/79 0910 Reactor at cold shutdown 12/22/79 2300 2345 PCIS'post modification tests completed, commenced rod withdrawal Reactor critical no.102 12/23/79 1535 Rolled T/G 1611 Synchronized generator, commenced power ascension 12/24/79 0135 12/25/79 1500 12/28/79 2325 Commenced PCIOMR from 50%thermal power Reactor thermal power at 85%, flow limited Reduced thermal power from 85%to 50%for control rod scram testing 12/29/79 0200 0500 Control rod scram testing completed, commenced power ascension Commenced PCIOHR from 65%thermal power 12/30/79 1500 12/31/79 2400 Reactor thermal power at 98%, flow limited Reactor thermal power at 98%, flow limited Si nificant 0 erational Events Unit 3 Date TMe Event 12/01/79 0001 1245 1325 1450 2045 Reactor shutdown for EOC 2, with BOC 3 fuel loaded in vessel Commenced pressurizing reactor vessel for hydrostatic test Reactor vessel pressure at 1005 PSI, holding for hydro-static test Commenced reducing reactor pressure to 570 PSI, holding for drywell leak checks Reduced reactor pressure to zero 12/06/79 0400 0645 Commenced rod withdrawal for startup Reactor critical no.88 12/08/79 1441 1615 Rolled T/G Synchronized generator, commenced power ascension as conditions allow 12/15/79 2330 Reduced thermal power from 80%to 66%for RTI's 23A, 22 and 32A 12/17/79 2000 12/18/79 1145 12/20/79 0830 2005 RTI's completed, commenced power ascension Reactor thermal power at 79%, flow limited Reduced thermal power from 79%to 60%for control rod pattern adjustment Commenced power ascension 12/21/79 0300 12/23/79 0706 0745 1100 2200 Commenced PCIOMR from 64%thermal power Reduced thermal power from 98%to 70%due to"A" and"B" string high pressure heaters isolation High pressure heaters"A" and"B" returned to service, commenced power ascension Commenced PCIONR from 88%thermal power Reactor thermal power at 97%, flow limited 12/24/79 1926 2114 2300 Reduced thermal power from 97%to 57%for control rod sequence exchange from"A" to"B" Control rod sequence exchange completed, commenced power ascension Commenced PCIOtlR from 67%thermal power Si nificant 0 erational Events Unit 3 Date Tame Event 12/26/79 0850 1145 Reduced thermal power from 92%to 86%for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced PCIONR from 86%thermal power 12/27/79 0600 1800 1930 2245 Reactor thermal power at 98%, flow limited Reduced thermal power from 98%to 80%for condensate demineralizers"A" and"3" backwash and precoat"A" and"B" condensate demineralizer placed in service, holding for"C" and"H" condensate demineralizer backwash and precoat"C" and"H" condensate demineralizer placed in service, commenced po~er ascension 12/28/79 0300 0700 1257 Commenced PCIOMR from 90%thermal power Reactor thermal power at 98%, flow limited Reduced thermal power from 98%to 85%for condensate demineralizer maintenance 12/29/79 2002 Condensate demineralizer maintenance completed, commenced power ascension 12/30/79 0700 2000 2230 Reactor thermal power at 98%, flow limited Commenced reducing thermal power for shutdown to install overhead cables from cooling tower switchgear to bus tie boards Reactor scram no.79 manual from 35%thermal power to accommodate maintenance 12/31/79 2400 Unit at cold shutdown (1)Equipment malfunction 10 AVERAGE DAILY UNIT POWER LEVEL DOCKET>NO.UNIT DATE MONTH December 197.9 DAY.AVERAGE DAlLY POWER LEVEL (MWe Net)964 DAY AVERAGE DAILY POWER LEVEL (M We.Net)915 l7 3 IO l2 I3 14 IS l6 953 953 933 934 952 938 943 929 926 926 915 920 IS 19 20 2,1 22 23'>5 26 27 2S'>9 30 3l 910 908 905 895-910 895 897 890 892 870.916 844 838 877 INSTRUCTIONS On this format.!ist the average daily unit power level in MWe.Net for each day>n the rep<>rtine

>n>>nti>.Ci>mpute tu the nearest whole megawat t.

~~AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.v UNIT DATE 1-0-80 CO~IPLETED BY TELEPHONE iE(ON TH December 1979 DAY AVERAGE DAILY POWER LEVEL (M We-Net)DAY AVERAGE DAILY POWER LEVEL (MWe-iVet) 17 3 7t 10 12 13 l4 IS 16 676 819 805 810 800 807 965 1031 1013 916-13 541 18 19 20 21 23 25 26 27 28 29 30 3I-12-10-10 136 680 865 897 887 801 1045 1062 INSTRUCTIONS On this format.list the average daily unit pi>wer levei'n l>I'tVe.Net for each day in the repi>rtinu lnontll.Ci>ltlpute to the nearest whole tnega.vat t.[9l77 s 12 AVERAGE DAlLY UNIT POWER LEVEL'DOCKET NO.50 296 T Browns Ferry 3 DATE~E!COMPLETED BY Ted Tham MONTH~'December 1979~r DAY AVERAGE DAlLY P01UER I.EVEL (!tI We-Net)I-10-10 DAY AVERAGE DAILY POWER LEVEL (hI1Ve.Net)

~689 839 3 IO l2 l3 l4 IS-10 38 163 223 353 477 515 68 812 724 l9 20 21 23 24 TS 26 27 28 29 30 31 837 633 747 959 1008 983 808 974 1002 1049 871 963-12 INSTRUCTIONS On this format.!ist the average daily unir power level in Mac Nct for each day in thc reportin!t ntonth.Compute to tNe rtearcst whole megawatt;I')t77) 13 OPERATING DATA REPORT DOCKET NO.1~5-80 COMpi,ETED BY~Do Green TELEPHONE~o U29-6846 OPERATING STATUS Notes 1.Unit Name 2.Reporting Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross<II We): S.Design Electrical Rating (Net M1Ve): e e cit e'OWe: 0 8.4 1065 7.Maxuntum Dep ndabl Capa y(N ti)8.If Changes Occur in Capacity Ratings (Items Numoer 3 Through 7)Since Last Report, Give Reasons: N A 9.Povver Level To Which Restricted, If Any (Net MWe): 10.Reasons For Restrictions, lf Any: N/A This M on t h Yr.-to.Date 744 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line 744 IS.Unit Reserve Shutdown Hours 0 0'.16.Gross Thermal Energy Generated (MWH)17.Gross Electrical Energy Generated (MWH)7,700,460 Ih.Net Electrical Energy Generated (M}VH)7,495,748 19.Unit Service Factor, 100 90.4 20;Unit Availability Factor-~100 90.4 21.Unit Capacity Factor (Using ilIDC Net)80.3 22.Unit Capacity Factor (Using DER Net)23.Uiiit Forced Outage Rate 0 4.4 24.Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duratinn of Each}: Refuel January 1980 Cumulative 47',498 28,277.28 0 74 136 493 24,518,460 23,801,968 58'58.1 47.1 47.1 33.0 25.If Shut Dnwn At End Of Rcport Period.Estimated Date of Startup: '26.Uiiits in Test Status iPri<<r to Coinmercial Operation}:

Forecast Achieved INITIAL CRlTICALITY INITIAL ELECTRlCITY COi'it'll ERCIA L OPERATION io/77) a~I OPERATING STATUS OPERATING DATA REPORT DOCKET NO 5 1-260 BETE 1~5-BO C05tPLETED BY~&Green TELEPHONE~~o-6846 Notes 1.Unit Name: 2.Reportfng Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Cross MWe): 5.Design Electrical Rating (Net MWe): 6.Maximum Dependable Capacity (Gross hIIVe): 1098.4 7.Maximum De endable Ca acit Net hllVe: 1065 p p y()8.If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report, Give Reasons: N/A ,5 9.Power Level To lVhich Restricted, If Any (Net MWe): 10.Reasons For Restrictions, If Any: I I.Hours In Reporting Period 12.Number Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On.Line 15.Unit Reserve Shutdown Hours.16.Gross Thermal Energy Generated (MWH)17.Gross Electrical Energy Generated (MWH).18.Net Electrical Energy Generated (MWH)19 Unit Service Factor 20., Unit Availability Factor 21.Unit Capacity Factor (Using hlDC Net)2'2.Unit Capacity Factor (Using DER Net), 23.Unit Forced Outage Rate 24.Shutdowns Scheduled Over Next 6 Months This Month Yr:to.Date 744'760 73.1 73e1 58.3 86.7 86.7 79.8 10.3 2.7 (Type.Date.and Duration uf Each):~571.03 7,766.19 172.97 298.23 543.98~7,596.45 0 1,458,581 22,703,212 475,610 7,636,280 461.952 7,441.305 Cumulative 42 409 24,484.48-.11,774.94.

23,664"31 66,155,000 21,950'b 21,3315469 55.8 55.8 47.2 47.2 36.8 5'25.If Shut Down At End Of Report Period, Estimated Date of Startup: 26.Units In Test Status (Prior tn Commercial Operation):

e INITIAL CRl'I'ICALITY INlTlA L ELECTRIC lTY COMht ERC I A L OPER ATlON Forecast Achieved (o/77) 15 OPERATING STATUS, OPERATING DATA REPORT Notes DOCKET NO SQ-296 DATE E-5 ED COMPLETED BY~~MD TELEPHONE~~-6846 1.Unit Name'.Reporting Period: 3.Licensed Thermal Power (MWt): 4.Nameplate Rating (Gross hIWe): S.Design Electrical Rating (Net MIVe): 6.ihlaximum Dependable Capacity (Gross MWe): CI IWe 7.Maxtmum Dependable Capa ty (Net h).8.If Changes Occur in Capacity Ratings (Items Nxmber 3 Through 7)Since Last Report, Give Reasons: 9.Power Level To Which Restricted, lf Any (Net>IWe): 10.Reasons For Restrictions, lf Any: This Month Yr..to.Date Cumulative 11.Hours ln Reporting Period 12.iNumber Of Hours Reactor Was Critical 13.Reactor Reserve Shutdown Hours 14.Hours Generator On-Line IS.Unit Reserve Shutdown Hours'6.Gross Thermal Energy Generated (MWH)1.7.Gross Electrical Energy Generated (MWH)18.Net Electrical Energy Generated (MPH)19.Unit Service Factor 20.Unit Availability Factor 21.Unit Capacity Factor (Using MDC Net)22.Unit Capacity Factor (Using DFR Net)23.Unit Forced Outage Rate 24.Situ(downs Scheduled Over Next 6 hlonths (T 591.75 131.50 534.25 5 816.35 552.9 5,708.30 1 231 495 403,790 390,613 16 956 484 5 635,080 5,482,585 71.8 4 65.2 8.8 49.3..--58.8 4.6 8.0 ipe.Date.and Duration of Each): 18 907.55 1,658.31.18438.28 53.107 866 17 402,580 16,887,773 74.2 74.2 63.8 9.0 S.If Shut Down At End Of Report Period.Estirrared Date of Startup: 6.Units ln Test Status (Prior to Commercial Op;mtion):

Forecast Achieved liVITIA L CRITICALITY INITIAL ELECTRICITY COhth(ERCIAL OPERATIC'E

.-UNIT SIIUTDOWNS AND POWER REDUCTIONS REPORT h(ONTII DOCKET NO.UNIT NAME DATE COhlPLETED IIV TELEPilONE rowns erry 1 o t:re en 205 29-68t'r6 Nii.nate~II fl I t4 cc Cl CA O Lieenscc Event Report 0'Cl 0 C E~Q Cause k.Corrective Action to Prevent Recurrence I F: Forced S: Scheduled (st/77)Reason: A.l'.quipmcot Failure (Explain)0-hiaiotcoaoce or Test C-lfefueling D Regulatory Restriction E"Operator Training k Liccnsc Examination I'.A J toinist rat ive C.Operational Error (Fxplain)ll Other (I:xplaht)

'(ethod: I hlaoual 2.hlanual Scram.3-Automatic Scram.4 Other (Explain)Exhibit C-Instructions for Preparation ot Data L'otry Sheets (or Licensee Eveot Report (LER>Flic (80REC-OI6I)Exlubtl I~Saroi Soon.e

--UNIT SIIUTDOWNS A4D POIVER REDUCTIONS REPORT hlOHTII DOCKET NO.50-260~UNIT NAME Browns Ferr 2 COhIPLETED IIY I<o l)ale C<r<Cl Q~r<C<~CJ c u~CA g Licensee Event Report¹<C<0 0'n cn G Cause 8'c Corrective Acttort to Prcvcnt Recurrence 109 791202 8.73 A.3 Suspected EliC pressure regulator printed circuit board problems, caused control valve closure and turbine trip.110 791213 53.44 Maintenance to"A" recirc pump and.FCV-1-5.'ll 791217 137.85 Pcs t modifications to the primary containment isolation system.112 791228 B Derated for control rod scram testin F: Forced S: Scl<eduletl

(<I/77)Reason: A-Equipment Failure (Explain)I}.hlaintenance or Test C Rcfuclittg D.Regulatory Restriction E Operator Training lc License Examination I'dllltntslrall"e G Op<'tattuttal Error (Fxplain}I I Otlt<'r (L<xplattt}

Method: I.hlanual 2rManual Scram.3-Aulomalic Scram.4.0tlter (Lxplain}Exltibit G-Instructions for Pret)aratiott of Data Entry Sheets I'or l.icensec Event Report (I.ER)Fii<s(NOREG-OI 6 I}Exhibit I~Sante Source

---VNIT SIIVTDOIVNS AND POlVER REDVCTIONS REPORT hIO")TII DOCKET NO.50 296 UNIT NAh!E DATE COhIPLETED BY Mn~tJ:a Ni I, Dull.'b I I Vl u V c u~-n tl AA Lice<<scc Event Rcport~Cause Ec Corrective Aetio<<tu Prcvcnt Rccurrcncc 109 110 791201.791220 791924 S 184.25 H Refueling Derated for control rod pattern adjustment.

Derated for control rod sequence exchange.112 791230 P 25.50 Ground in auxiliary power supply cables from cooling towers,to bus tie boards.Installation of over-head cables in progress.F: Forced S: Scheduled (It/77)Reasun: A.Equipmenl Failure (Explain)Il.hl;tintcnance or fest C-Rct'<<eliot, D.l<cttulatory Reslrictiun E-Ot>eratur Trainint', k Liccnsc Examination F-A Jlntrlist lative G Opclatil>>lal Lrrur (Explain)I I Other ((explain) 3 hlethod: I'hla<<ual 2-hlanual Sera<<i'.3 Auto<<latic Scram.4.Other (Explain)Exhibit G-Instructions for Preparatiun

<<I'Data Entry Sheets I'or l.ice<<see Event Report (LLR)Flh'WOREG-016I), Exhibit I-Salnc Source

CSSC E UIPMENT BROWNS FERRY NUCLEAR PIANT UNIT 1 MECIKHICAL MAINTENANCE SU%MARY ZR-DATE SYSTEM COi fPOHENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF Tl1E REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 12/9 HPCI FCV 73-16 Bad pinion gear With NPCI inop-able it could force unit shutdown Operation NPCI inoperable Replaced pinion gear in valve limitorque 12/13 Rx.Bldg.Uent.Computer Room Exhaust damper Damper closed None I Unknown Hone Opened damper and hooked linkage bac u 12/13 Fuel Pool Cooling"lA" FPC pump discharge check valve Disc pins broken None Operation None Replaced with r.ew valve 12/22 Fuel Pool Cooling"lA" FPC pump Internal part worn None Operation None Replaced all internal parts CSSC E UIPMENT BROWNS FERRY NUCLEAR FIANT UNIT 2 MECHANICAL MAINTENANCE SUl&fARY For the Month of DATE SYS TEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE

'QlE REACTOR CAUSE OF'ALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURREkacE 12/17 CRD"B" CRD discharge filter Dirty filter None Operation None Changed filter 12/17 Main Steam FCV-1-55 Pressure seal leak None OPeration None Disassembled, cleaned and installed new pressure seal rin~12/20 Radwaste FCV 2-77-2A Bad solenoid None Operation None Installed new solenoid valve BROWNS FERRY NUCLEAR PLANT UNIT 3?KQQQlICAL MAINTENANCE

SUMMARY

For the Month of December 19 79 SYS 621 COMPONENT NATURE OF HAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 12/1 Control Bay Vent"3A" Control Bay Chiller Nater Regu-lating Valve Bad Valve None Operation None Rebuilt valve 12/12 Auxiliary Boiler HCV 3-12-708 Bad packing glanQ leak None Operation None 12/19 Rx.fiater Cleanup FCV 69-60B Packing leak None Operation None Repacked valve CSSC E UIPENT BRO',FANS PERRY NUCLEAR PLANT UNIT 1 ELECTRICAL MAINTENANCE SENARY~For the Month of December 19 79 Date System Component Nature of Maintenance E ect on a e-Operation of The Reactor.Cause of Malfunction Results of Malfunction Action Taken To Preclude.Recurrence 12/9/79 HPCI FCV'73-16 HPCI turbine steam supply valve motor HPCI auxilia~oil pump will not start from control room HPCI inoperable at the time of failure Failed limit switch Auxiliary oil pump will not start Replaced limit switch.Auxiliary oil pump now starts as required.TR 146244 12/10/7 HPCI FCV-1-73-16 HPCI turbine steam supply valve motor Failed limit switch HPCI-inoperable at the time of failure Failed limit switch on FCV 73-16 t Valve inoperable Replaced torque switch, ran EMI 18.Checked OK.TR 161333 12/12/79 250V battery board 1A 250V bat-tery board HPCI gland seal conden-ser blower motor ground-'ed None Motor grounded Motor failed to operate Replaced motor.Checked OK.TR 149686 12/31/79 Common unit 90-51 neutron monitoring Motor that drives pumps is locked up, blowing fudes None Bad motor Cam inoperable Replaced bad motor, started unit.Checke OK.TR 161539 CSSC E UIPMENT PROSER PERRY NUCLEAR PLP3lT URYT 2.ELECTRICAL MAINTENANCE SALARY For the Month of December 19 79 Date System Component Nature of Maintenance ect on a e Operation of The Reactor.'ause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 12/14/79 I Hain steam FCV'2-1-55 steam line drain valve motor Green light Not applicable and open limit switch not working right Limit switch drive frozen False indication Replaced limit switch drive and gear key per EMI 16 and 18.Checked OK.TR 134713 12/20/79 Ventila-tion 8-3 drywell air blower motor Breaker trips out when try-ing to start None Motor grounde'd Motor failed to operate Replaced motor.Checked OK.TR 122352 EROUMR PERRX NUCLEAR PLY~VX tRlXX 3 ELECTRICAL MAINTENANCE Sl&QSRY Fore Month of December 19 79 Date System Component Nature of Maintenance ect on a e Operation of The Reactor.Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 12/4/79 Diesel generator D/G.3C failed to accept load on emergency load acceptance test Hi voltage supply None U-3C diesel generator frequency gen-erator was supplying too high voltage to SSPl and SSP2 Too high voltage Adjusted air gap.on frequency generator pickup to reduce supplied voltage to correct valve.Checked OK.TR 96702 BFRO 50 296/7923 12/5/79 Core spray FCV 75-50 (core spray II test valve)motor Motor failed to operate None SBM switch controls HIY were not ma!'ing Up Valve would not operate.Replaced SBM switch, functional.

Cheeked OK.TR 146429.

CSSC E UIPOKNT BROGANS 1ERRY NUCLEAR PLQ<T UNIT INSTRU?fENT MAINTENANCE SUGARY~FOR TI?E MONTH OF December 19 79 Init 1 2-10.2-31 SYSTHf Neutron Monitoring CO~fPOHENT FI-67-9A AERf-A NATURE OF?fAINTENANCE Calibr,ate Calibrate EFFECT ON SAFE OPERATION OF THE REACTOR None None CAUSE OF?fALFUNCTION Instrum nt Drift Instrument Drift RESULTS OF?fALFUNCTION Flow Indicator Pegged Upscs,le Rod Block came in with lg LPRM's in-stead of 13 ACTION TAKEN TO PRECLUDE RECURRENCE None None Init, 2?0?K Init 3 2-13 Standby Die el Generator 3D Air Com-pressor.Pres-sure Switches Calibrate None Setpoint Drift Air Compressor shut off 3 PSI low None 2-26 Standby Diesel Generator 3A Diesel Replace Generator Fue1 Pressure Gage None Leaking Gage Diesel Fuel in gage None 2-26 Radwa ste Lls 77 ll)B Clean None Static on Meter Face Static Charge Caused Indicator to Stick Hone 26 OUTAGE

SUMMARY

December 1979 The Unit 3, cycle 2 refuel outage was completed on Saturday, December 8, 1979, marking the completion of a 107 day modification, maintenance, and refuel outage.Unit 2 was shutdown on December 17 for modifications to the primary con-tainment isolation system and installation of an accoustic monitoring system for the main steam relief valves.During this outage, approximately 80 percent of the repair items on the Unit 2 short outage list were completed as well as the PCES and accou tic monitoring mods.Unit 2 was returned to service on December 23.Unit 3 was shutdown on December 30 for a modification to install an alternate power supply from the cooling tower transformers to the Unit 3 shutdown bus tie board.This modification should be completed and the unit returned to service by the middle of January.Preparations have been underway for the upcoming Unit 1, cycle 3 refueling outage and should be completed by January l.Unit 1 is scheduled for a 48 day refueling outage to begin January 3, 1980.