ML20244D550

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Monthly Operating Repts for Mar 1989 for Browns Ferry Nuclear Plant,Units 1,2 & 3
ML20244D550
Person / Time
Site: Browns Ferry  
Issue date: 03/31/1989
From: Campbell G, Ratliff S
TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8906190129
Download: ML20244D550 (69)
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Text

{{#Wiki_filter:. 4' [ o MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY MARCH 1989 " Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-250, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND OPR-68 i 1 I l ] Submitted by: h = 09061%$ praf 7" [sGuy G. Campbell Plant Manager ) '> k

3 y TABLE OF CONTENTS PART I. OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B Refueling Information............................................ 2 C. Main Steam Relief Valve (MSRVs) Actuation Summary................ 7 D. Issuance of Special Reports Summary...'........................... 8 E. Licensee Event Reports Summary................................... 9 F. 'Offsite Dose Calculation Manual Changes......................... 12 G. R adwas t e S umma ry................................................ 13 1. Total volume of solid waste shipped offsite 2. Nature of the waste (trashi resins, etc.) 3. Gross. curie activity 4. Dates the material was shipped and the disposal facility to which the material was shipped 5. Estimated quantities of spent resin in storage. 6. Estimated amount of spent resin that will be generated in the following month 7. Waste type and volume of radwaste ' containers-that are onsite-awaiting shipment PARI II. OPERATING STATISTICS A. NRC Reports 1. Operating Data Report....................................... 22 2. Average Daily Power Leve1................................... 25 3. Unit Shutdowns and Power Reductions......................... 28 B. TVA Reports 1. Plant Operating Statistics.................................. 31 2. Unit Outage and Availability Data........................... 32 j 3. Reactor Histogram (Reactor Power Percent)................... 35 I i l l l 1 i l' i i l

.,'d q v 1 J i 1 TABLE OF CONTENTS ] (Continued) ~j 1 ~ PART III. MAINTENANCE

SUMMARY

36 j 1 1 1 PART IV. OTHER REPORTS-1 A. Chemistry Summary 1. Primary Coolant Chemistry.................................. 38 s '2. Environmental Technical Specification Requirements.......... 41 l 3. Ai rbo rne Releases......................~...................... 4 2 4. Liquid Releases............................................. 47 5. R es in Usag e R epo rt.......................................... 51 6. Fuel Cladding Integrity Parameters.......................... 52 i 7. Waste Treatment System Throughputs....'...................~.. 53 I ) B. Testing Summary................................................. 54 C. . Reactor Vessel Fatigue Usage Evaluation......................... 56 D. Change in Procedures............................................ 57-E. Plant Instruction Revisions..................................... 57 .F.. -- Chang e in Plan t O rg anizat ion.................................... 5 8 G. Accidents....................................................... 59 l l l 1 1 I l j l l i i

s t ACRONYMS / ABBREVIATIONS ADS Automatic Depressurization System ALARA As Low As Reasonably Achievable ANSI American National Standards Institute ASER Accreditation Self Evaluation Report ASME American Society of Mechanical Engineers ASOS Assistant Shift Operations Supervi'sor ATWS Anticipated Transient Without Scram AUO Assistant Unit operator CFEL Browns Ferry Equipment List CFN Browns Ferry Nuclear Plant CFNPP Browns Ferry Nuclear Performance Plan BOD Biochemical Oxygen Demand BWR Boiling Water Reactor CAQ(R) Conditions. Adverse to Quality (Report) CAR Corrective Action Report CCB Change Control Board' CCD Configuration Control Drawing CCTS Corporate Commitment Tracking System CFR Code of Federal Regulations CML Component Master List CIP Chemistry Improvement Plan CNPP Corporate Nuclear Performance Plan CRD Control Rod Drive CREVS Control Room Emergency Ventilation System CWPS Condensate Waste Polishing System CS Core Spray CSSC Critical' Systems, Structures, and Components DAW Dry Active Waste DBA Design Basis Accident DBVP Design Basis Verification Program DCN Design Change Notice DD Drawing Discrepancy D/G(s) Diesel Generator (s) DR Discrepancy Report EA Engineering Assurance Org.; Engineering. Association ECN Engineering Change Notice ECCS Emergency Core Cooling System ECP Employee Concern Program l ECP-SR Employee Concern Program - Site Rep ECTG Employee Concern Task Group EDD Environmental Data Drawings EECW Emergency Equipment _ Cooling Water EOC End of Cycle EOI Emergency-Operating Instructions EPRI Electric Power Research Institute EQ Environmental Qualification EODP Environmental-Qualification Documentation Package l EQE Earthquake Engineering l EQP Environmental Qualification Project e.e. quemmN c' ape a>msgweeh emeencoen e m =

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'i E ACRONYMS /ACIREVIATIONS-(Continued) \\ ~ _ER Engineering' Report .l ERCW Essential Raw Cooling Water i ESF Engineered Safety Feature FCR . Field Change Request FMEA-Failure Modes and Effects Analysis FSAR-Final ~ Safety Analysis Report-. FW-Feedwater-i GE . Genera 1' Electric. H CET-Genera 1' Employee Training i GPM Gallons per: minute GOI. General Operating. Instruction'- HPCI High Pressure Coolant Injection HVAC Heating Ventilation and Air Conditioning: ) IE Inspection and' Enforcement (NRC) l 'IG Inspector General 'ICSCC Intergranular Stress Corrosion Cracking INSI In6uction Heating Stress Improvement INPO Institute of:NuclearLPower Operations IRIS Input Requirements,Information' System ISEG Independent. Safety Engineering Group j ISI Inservice Inspection ITC Immediate Temporary Change. JTG -Joint Test Group 1 'LCO Limiting ' Conditions: for Operation LDCR Loesi Design' Change Request LER-Licensee Event Report i LOCA Loss of Coolant Accident LOP Loss of Power MAI Modification Addition' Instruction MCC Motor' Control' Center MCEL Master Components Electrical List j MMI Mechanical Maintenance Instruction I MNt Megawatts thermal MOV Motor Operated Valve MR ' Maintenance Request MSIV. Main Steam Isolation Valve MWe Megawatts electrical l NCR Nonconformance Report NE Nuclear Engineering NEP Nuclear Engineering Procedure NERP Nuclear Experience' Review Program NFPA National Fire' Protection Association NMRG Nuclear Managers. Review Program 'NPS Nuclear Procedures Staff' NQA Nuclear Quality' Assurance j L NQAM Nuclear Quality Assurance Manual l NRC Nuclear Regulatory! Commission l NSS Nuclear Security Service NT Nuclear Training i NUMARC Nuclear Utility Management and Resources Countil. NUREG Nuclear Regulatory Documentary of Operating Instruction OL Operating Licensee 3 ONP Office'ef Nuclear Power i i 1

'b / ACRONYMS / ABBREVIATIONS (Continued) PASS Post-Accident Sampling System PCIS ' Primary Containment Isolation System PD Position Description-PM Preventive Maintenance. PMT Post Modification Test. PORC-Plant operations Review Committee PSI Preservice Inspection PSS Potentially Safety Significant QA. Quality' Assurance QC Quality Control QMDS Qualification Maintenance Data' Sheets RC ' Radiological Control RCIC Reactor-Core Isolati6n Cooling REP Radiological 1' Emergency Plan RETS Radiological Effluent Technical Specification' 'RHR Residual Heat Removal RHRSW-Residual Heat. Removal Service' Water RPIP Regulatory Performance Improvement Plan RPS Reactor. Protection System; Records Procedure Section y RTI Refueling Test' Instruction RTP Restart Test Program I RWCU. Reactor Water. Cleanup -SALP: Systematic Assessment of Licensee Performance SCR Significant Condition Report. l) SCRAM Safety Control Rod Activation Manually SDIV Scram Discharge Instrumentation Volume i SDSP Site-Director Standard Practice S/G(s) Steam' Generators SI Surveillance Instruction SIL-Service Information Letter d SMMI Special' Mechanical Maintenance Instruction J SOS Shift'70erations Supervisor SPDS Safety Parameter Display-System SPOC System.Preoperability Checklist SON Sequoyah Nuclear Plant SQUG Seismic Qualification. Utility Group j! SRO Senior Reactor Operator SRV Safety Relief Valve' ] STA Shift Technical Advisor SYS NOS System Numbers ~. 1 TACF Temp.orary Alteration Control Form 'TI Technical. Instruction TS Technical Specification-TSS Total Suspended Solids TVA Tennessee Valley Authority j UO Unit Operator-USA United States of America .USQD Unreviewed Safety Question Determination 'VMCP Vendor Manual Control Program WBN Watts Bar Nuclear-Plant I WP Workplan i

A i l i l l i OPERATIONAL SEMMARY I i l 1 l i l l l I

7 4 Pa gs.1 - ) SIGNIFICANT OPT, RATIONAL EVENTS

SUMMARY

i' MARCH 1989 Unit 1 03/C1/89 0001 Unit remains on administrative hold-to resolve various TVA and NRC concerns. I 03/31/89 2400 Unit' remains on administrative hold to resolve various' TVA and NRC concerns. Unit 2 03/01/89 '0001 Unit ren.ains on administrative. hold to resolve various TVA and NRC concerns, Core reload was completed on January 30, 1989. Modification and Operation & Maintenance work continues to support, restart in September 1989. 03/31/89 2400 Unit remains on administrative hold' to resolve various - TVA and NRC concerns.. Modification and Operations & Maintenance work continues to support restart in-September 1989. Unit 3 _ 03/01/89 0001 Unit remains on administrative hold.to resolve various TVA and NRC concerns. 03/31/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. l

Page 2 s REFUELING INFORMATION MARCH 1989 Unit 1 1. Name of facility Browns Ferry Nuclear Plant 2. Scheduled date for next refueling shutdown - N/A 3. Scheduled date for restart following refueling N/A 4. Will refueling resumption of operation thereafter require a technical specification change or other license amendment? BFN, cycle 7 startup has not been scheduled at this time. When required, the cycle 7 reload licensing submittal will be made to support Technical Specification thermal limits for the core design and specific fuel assembly types to be loaded. NOTE: Item 4 information addresses only licensing changes directly associated with the reload core design. 5. Scheduled date(s) for submitting proposed licensing action and supporting information N/A 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures Cycle 7 final core design has not been developed at this time. 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool (a) 0 (b) 1,864 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in the number of fuel assemblies I 3,471 .n.

Paga 3~ -REFUELING INFORMATION 4 Unit 1 (Continued) 4. i-9. The projected date of the last_ refueling that can be discharged to the spent fuel pool assuming the present licensed capacity Since fuel can be transferred between these two spent fuel storage pools, the two are considered together. The two spent. fuel storage pools will have the. capacity to handle one full core d2scharge from one unit following the BF2 cycle 15 refueling in September 2006. (BF1 would be in-cycle 13.) ? i i i I I_ i i j -{ 1. 1 1-j l 4 i i ~! I l i l + l l a l _._m

Pcgn.4 o s REFUELING INFORMATION MARCH 1989 Unit 2-1.. Name of facility-Browns Ferry Nuclear Plant

2. - Scheduled date for next refueling' shutdown:.

N/A 3. Scheduled date for restart following refueling l N/A. 4. Will refueling resumption of operation thereafter require a: technical f specification channe or other license amendment? I ' Changes to the Technical Specification as a result of the BFN 2, cycle 6 i final core design have been submitted along with the BFN Reload Licensing.

I Report for unit 2, cycle 6 (TVA RLR-002) Revision 2.-

This report documents ~l the Technical Specification core thermal' limits'for the specifi'c unit 2, l cycle 6 core design. NOTE: Item 4 information addresses only licensing changes directly associated with the reload core design.. i l-5. Scheduled date(s) for submitting proposed licensing action and supporting information q ? N/A 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or. performance analysis methods, significant changes in fuel design, new operating procedures l The fuel assemblies for the BFN 2, cycle 6 core are listed in TVA RLR-002. Included in this core are four new Westinghouse Quad + demonstration q l! assemblies described in WCAP-10507 dated March 1984, " Quad + Demonstration- .j i Assembly Report," Westinghouse Electric Corporation. The remaining 760 fuel assemblies are General Electric design which are described in 1 NEDE-240ll-P-A-8 dated May 1986, " General Electric Standard Application for Reactor Fuel," General Electric. This includes 212 twice-and thrice-burned assemblies which were inspected and reconstituted for cycle 6;.248 once-burned fuel assemblies from unit 1, cycle 6; and 300 new assemblies.- 7. The' number of fuel assemblies (a) in the core and (b) in the spent fuel { storage pool (a) 764 (b) 1,444 l l If u

4 Page 5-i l REFUELING INFORMATION ) Unit 2 (Continued) ) 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in the number of fuel assemblies l 3,471 1 9. The projected date of the last refueling that can be discharged to the spent l fuel pool assuming the present licensed capacity Since fuel can be transferred between these two spent fuel storage pools, 3 the two are considered together. 'The two spent fuel storage pools will have j the capacity to handle one full core discharge from one unit following the i BF2 cycle 15 refueling in September 2006. (BF1 would be in cycle 13.) 1 i f u l b i l I i l l i l l j

1 ' Pag 2 6 '1 i REFUELING.INFORMATION ] MARCH 1989-Unit 3 +- 1. Name of facility Browns Ferry Nuclear Plant 2.' Scheduled date for next refueling shutdown ' l N/A 3. Scheduled date for restart following refueling N/A j l 4. Will refueling resumption of operation thereafter require a technical I t specification change or other license amendment? d i The unit was shut down early in cycle 6. In the event that the core design -) ( is revised and a change to the Technical Specification thermal limits are. ) l required (MCPR), the appropriate' submittal will be made. I NOTE: Item 4 information addresses only licensing changes directly associated with the reload' core design. j { 5. Scheduled date(s) for submitting proposed licensing action and supporting i information N/A 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures No changes in the fuel assemblies are planned for unit 3-return to operation l from the original assemblies loaded at the beginning of cycle 6. 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool i l (a) 0 (b)-1,768 l 8. The present licensed spent fuel pool storage capacity and the'aize of any increase in licensed storage capacity that has been requested or is planned. l in the number of fuel assemblies 3,471 l h 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity This spent fuel. storage pool will have the capacity to handle. full core j discharge following the cycle 13 refueling in May 2006. l -r_n_ - ~ - - -

Pcg2 7 MAIN STEAM RELIEF VALVE (MSRVs3

SUMMARY

MARCH 1989 No MSRVs were challenged during the month. t I I i I k, i i i i 4 6 b 6 I I e I i 1 I l f i i l l i i i

Paga 8 ISSUANCE OF SPECIAL REPORTS MARCH 1989 There were no notices of violations issued for the month'of March 1989. i l l l l l 1 l i l l l l l l l e I I I i i w--- e . = -

Pege 9 i i LICENSEE EVENT REPORT (s) l I MARCH 1989 Drectiotion of Event LER I 1-89-002 DESIGN ERROR ON EMERGENCY EOUTPMENT COOLING WATER (EECW) DISCRARGE CAUSES PLANT TO BE IN AN UNANALYZED CONDITION ) On February 8, 1989, the shift operations supervisor was notified I that the buried raw cooling water (RCW) discharge piping between the reactor building and the condenser circulating water discharge conduit was not seismically qualified. Portions of the pipe consist of vitrified clay. Utility engineers identified several components required for safe shutdown of the plant that are cooled by EECW that discharges into RCW. The RCW system is not a safety related system and is not required for safe shutdown of the plant. 1-89-003 DESIGN OF SUPPRESSION POOL VACUUM RELIEF SYSTEM DOES NOT PROVIDE SINGLE FAILURE DOUBLE ISOLATION OF PRIMARY CONTAINMENT The design of the suppression pool vacuum relief system does not meet the current single failure, double isolation design criteria for primary containment isolation. An air operated butterfly valve fails in the open position on loss of its unqualified air { supply. The failed open butterfly valve would allow the pressure l relief function to be accomplished but would not provide double 4 isolation for primary containment. ) i 1-89-004 UNMONITORED RELEASE OF CONDENSATE WATER BECAUSE OF FAILURE OF INSTRUMENTATION HEAT TRACE i On February 9, 1989, between 0400 and 0800 the level in the l number 1 condensate storage tank (CST) decreased from 26.7 feet I to 10.1 feet. The unit 1 control room operator noted the rapid level decrease when recording the CST levels at 0600. Because of the freezing weather conditions and the reliability history on the CST level instrumentation and temperature monitors, the operator incorrectly concluded that the CST instrumentation had malfunctioned. An "immediate attention" maintenance request was initiated to check this instrwnentation. At 1600 hours, the unit operator noted that both condensate transfer pumps had started and the condensate head tank was indicating a low level. Investigation into this condition determined that the condensate head tank heat trace had failed. This condition could have allowed the condensate transfer pumps to pump CST water to the condensate head tank, overflowing the head tank resulting in the water being released even though visible evidence such as overflowing or standing water to support this conclusion was not found. l l

Paga-10 LICENSEE EVENT REPORT (s) (Continued) 1-89-006 LOSS OF SECONDARY CONTAINMENT INTEGRITY DUE TO PERSONNEL ERROR AND INADEOUATE COMMUNICATIONS On February 28, 1989, at 0850 hours it was discovered by a utility maintenance engineer that a unit 1 secondary containment (reactor zone) ventilation exhaust radiation monitor had been repaired on February 25, 1989, but.had not been tested following i maintenance. The radiation monitor was not declared inoperable during the following three days and the Technical Specification required compensatory measures were not maintained. The radiation monitor had failed in the safe configuration (performing its safety function) prior to repair and was, therefore, not initially declared inoperable. Units.1.and.3 were defueled during this condition and unit 2 was shutdown. 2-89-003 FAILURE TO REMOVE JUMPERS FROM REACTOR PROTECTION SYSTEM LGGIC. PLACED DURING PERFORMANCE OF A suxyriLLANCE INSTRUCTION DUE TO PERSONNEL ERROR On February 3, 1989, at 2215 hours while performing the functional test for the unit 2' Source Range Monitor Rod 1 Blocks / Scrams it was discovered that the Source Range Monitor scram. function was not operational. The subsequent investigation revealed that two jumpers installed in the reactor protection System logic daring performance of the Intermediate Range Monitor' Rod Block / Scram functional test had not been removed. The ~~ jumpers were removed at approximately 2230 hours. The root cause of the event was' personnel error. 2-89-004 TECHNICAL SPECIFICATION VIOLATION DUE TO MISSED SURVEILLANCE On February 22, 1989, at 1130 hours maintenance management Personnel discovered that the previous weekly surveill.nce, due February 14, 1989, had not been performed on the 0 and D 250 volt shutdown board batteries.' The next regularly scheduled surveillance was successfully run on February 21, 1989, at 2300 hours. The batteries were required by TS 3.9.A.4.as specified in TS 3.9.C. The interval between surveillance exceeded that required by TS. Browns Ferry was therefore in violation of TSs during the period between February 15 and February 21, 1989.

e-Pagn 11 LICENSEE EVENT REPORT (s) (Continued) J 3-89-001 FAILURE TO PROVIDE REOUIRED con 11nuGUS FIRE WATCH ON INOPERABLE { FIRE DOORS CAUSED BY PERSONNEL ERROR DUE TO INSUFFICIENT TRAINING j On February 9, 1989, a fire protection engineer discovered that' a roving fire watch had been covering two inoperable fire barriers .rather than a continuous watch as required by TS 3.11.E. A continuous fire watch was. established in the area on. February 5,1989, because of another deficiency which had been - identified on one of the fire doors. I f 1 d 1 l l 1 i j

s Paga!12-OFFEITE DOSE CALCULATION MANUAL CHANGES 4 MARCH 1989 l l No changes were made to the BFN Offsite Dose Calculation Manual during the month. l emo w I i 1 e 1 ) iw e3+* w-wa. me . ge w me +-.m,w.,m...

Pags 13- + RADWASTE

SUMMARY

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MARCH 1989 .The radwaste system performed'as designed. 'Approximately 1.23E+06 gallons of waste liquid were diacharged containing appr5ximately 2.05E-02 curies of'- activity.. There was one spent. resin shipments and one trash' shipment during March.'~All . shipments were to Barnwell,' South Carolina.- There were.no trash shipments made by the Scientific Ecology Group, radwaste broker / processor, containing BFN waste during March. ese em 4 i 1 ,i I s i i i l 1 1 c - = _ _ _ _ _ - _. _ _ _ _ _ _ _ _ - - _ _ - _ _ - - - _ - _ _ - _ _ _ _ - _ _ _ _ _. _ _ _ _ _ _ - - _ _ - _ _ _. _ _ _ _ _ _ _

Pagal14 s ' Solid-Radioactive Waste' ' March 1989-C'1) Dewstered~ Spent _ Resin Shipments Volume of condensate / waste'(CWPS) resin 1 shipped:. 2,.63.:Cu.M. (93,00 Cu.Ft.) Total curies shipped: 3.0089' Volume of reactor cleanup-(RWCU) resin. shipped': _'2.63 Cu.M. (93.00.Cu.Ft.) Total curies shipped:. 6.3980 l Date ShiDDed DisDosal Facility .T,y_gy_ L gff,, - R e s i n ' 03/10/89 BarnweLL,-SC CWPS/RWCU.(Mixed) i (1) Dry Active waste Number of. drums shipped: 60-Volume 12.74 Cu.M. (450 Cu.Ft.) Total curies shipped: 0.2407 Number of boxes shipped: 2 Volume: 5.27-Cu.M.-(186 Cu.Ft.) Total curies shipped: 0.0732 1 f. Date ShiDoed Disoosal, Facility ,T,.y p.t p_., P a c k a o e-f 03/15/89 Barnwell, SC . Drum &. Box' i Brokered shipments (SEG): 0 Volume: O Cu.M. ( 0 Cu.Ft.)' Total curies shipped: 0 ' a l \\ p_;,te ShiDDed Disoosal Facility Tvoe of Pachace i N/A N/A N/A i 1 l (1) ALL shipments were by Sole-Use Vehitte I l i l~ I 2 l . l e e, . opee v - eiwemeree p ---g w-e. gem.,,e. -

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' Pag 2 15 Solid Radioactive Waste (Continued) March 1989 i 1 Summary Type Shipped to Packaged on Gross Curie Estimated of Barnwell Site Awaiting Content by Generation for 1 Waste During Month. Shipment Type of Waste Next Month COMPACTED Drums 367.5 Cu.Ft.C2) 113 Cu.Ft. 2.40E-01 330 Cu.Ft.(2) (2) (2) Boxes 186.0 Cu.Ft. 279 Cu.Ft.. 7.32E-02 558 Cu.Ft. UNCDMPACTED Drums 82.5 Cu.Ft.(2) 900 Cu.Ft' 7.00E-04 195 Cu.Ft.(2) (2) (2) Boxes O Cu.Ft. 706 Cu.Ft. 0.00E+00 580 Cu.Ft. BROKERED 0 Cu.Ft. O Cu.Ft. 0.00E+00 0 Cu.Ft. RESINS CWP5 93 Cu Ft.(1) 293 Cu.Ft.(3) 3.01E+00 465 Cu.Ft.(1) 'I (1) (3) (1) RWCU 93 Cu.Ft. 20 Cu.Ft. 6.40E+00 5 Cu.Ft. (2) (4) TOT AL-5 841.6 Cu.Ft. 1990 Cu.Ft. ~9.72E+00 2,141 Cu.Ft., (4) (2) Total volume of waste shipped during the month: 642 Cu.Ft. Total volume of waste shipped year-to-date: 4,036 Cu.Ft. Unused 1989 burial volume atLocation at BernwelL: 78,764 Cu.Ft. J (1) Actual resin volume (2) Container burial volume (3) Estimated volume in separators (4) Does not include resins l l l i l 4 1 3 i

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rag 20 LIQUID'RADWASTE ~ MARCH 1989 TOTAL RIVER RELEASE FLOW RATE (SPM) DATA PLOTTED FOR THE PREVIOUS 12 MONTHS.. TOTAL RELEASE (CZ) 40. _2 FLOW RATE fa,td) HI' 27.81 LOW 20.72 30 - AVS 23.72 1 TOTAL C mELEASE fCT) ^ SO ' _ HI 0.04 LOW .0.0$ -AVS

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o FLOWRATE b6 P bT kV hC JAN ( Y ' ~ " " " ' FILTER-THROUGHPUTS 8 WASTE SALLONS X 10 gg 4 LOW 0.90E+0S AVS 0.12E+07 FLOOR DRAIN I HI 0.11E+07 LOW 0.79E+0S AVS 0.95E+0S 'I ~ LAUNDRY E-fjfj 7/f AVS 0.22E+04 HI 0.13d+05 LOW 0.'00E+00 m 1 0 1 1 1 APR-MAY JUN JUL AUS SEP OCT NOV OEC JAN FES MAR COST OF OPERATION o,,,,r1o 7,oo5 um., THOUSA OF OOLLARS TE HI 0.84E+05 90 - LOW 0.20E+05 SO AVS 0.30E+05 70 FLOOR DRA,IN 0 HI 0.50E+95 l N,),, LOW 0.22E+05 e [ 50 - p, j7l AVS 0.35E+05 4g " j? ' j j'.7;j j' '{

~ ' ; ;7,;

j LAUNDRY 30. j . { ', j j ; ({ j.: fj 7

j, j HI O.37E+03 j

j

j.l j j

'f j j j j 3 j'.: J. j j. j LOW 0.00E+00 j : l: j-j : j AVS 0.46E+02 10 - s I ' - ! !- I' -! ! ! !1 i l' i i. ! 1 i l

  • Ii :

o APR MAY JUN JUL AUS BEP OCT NOV DEC JAN FES MAR WASTE COLLECTOR SYSTEM L UNORY SYSTEM FLOOR DRAIN SYSTEM

Page 21 REACTOR POWER - MWT UNITS 1, 2, AND 3 MARCH 1989 MWT 3500-3000

  1. 5 UNIT 1: OUTAGE 2000 UNIT 2: OUTAGE

,3,, UNIT 3: OUTAGE 1000 500 0**%%***h**24&O%C&45&&#404554%%%4 Chealstry Section DAYS Technical Services Woms Ferry httelear Plant REACTOR WA TER ' CONDUCTIVITY UNITS 1, 2, AND 3 MARCH 1989 US/CM CONDUCTIVITY 1.75 MTi 1.5 CONDUCTIVITY 1.25 UNIT 2 ________________...... A ___.___.... 3 0.75 CONDUCTIVITY UNIT 3 0.5 EXPECTED RANGE 0.25 M COLD SHUTDOWN 0 0 * * * * * * ^ * * # C & O J # # 0 $ @ & C & @ 4 $ & D & @ 4 @ ACTION LEVEL I LIMIT Cnemistry Section DAYS COLD SHuToown Technical Services Broms Ferry httclear Plant REACTOR WA TER CHl.ORIDE UNITS 1, 2 AND 3 MARCH 1989 PPB SD CHLORIDE UNIT 1 40 CHLORIDE 30 UNIT 2 20 CHL:: RIDE UNIT 3 0 T EXPECTED RANGE " LL CONDITIONS i A 0

      • ^**&%&O%454&#444444@4&&44

\\'

    • +%

~~~~ h h###$, DAYS yj ALL VALUES LESS THAN DETECTABLE Woma Ferry httelaar Plant ] _=_=__-_-_-_v_=-

o 9 e ~ OPERATING E STATISTICS S

4 Page 22 OPERATING DATA REPORT DOCKET NO. 50-259 j DATE 4-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (205) 729-2937 i OPERATING STATUS l Notes l 1. Unit Name: Browns Ferry Unit One l l j 2. Reporting Period: MARCH 1989 l l l 3. Licensed Thermal Power (Wt): 3293 l l t 4. Nameplate Rating (Gross We): 1152 l l { 5. Design Electrical Rating (Net We) 1065 l l j 6. Maximum Dependable Capacity (Gross We) 1098.4 l l l 7 Maximum Dependable Capacity (Net We) 1065 l I f 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A I \\ 9. Power Level To Which Restricted, If Any (Net We): N/A

10. Reasons For Restrictions, If Any:

N/A i t This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 2.1f0 154.928 j
12. Number of' Hours Reactor Was Critical 0

0 59.521.38 j

13. Reactor Reserve Shutdown Hours 0

0 6.997.44 1

14. Hours Generator On-Line 0

0 58.267.26 j

15. Unit Reserve Shutdown' Hours 0

0 0

16. Gross Thermal. Energy Generated (WH) 0 0

168.066.787

17. Gross Electrical Energy Generated (MWH) 0 0

55.398.130

18. Net Electrical Energy Generated (MWH)

-5.109 -14.227 53.484.504

19. Unit Service Factor 0

0 37.6

20. Unit Availability Factor 0

0 37.6

21. Unit Capacity Factor (Using MDC Net) 0 0

32.4 i

22. Unit Capacity Factor (Using DER Net) 0 0

32.4 2

23. Unit Forced Outage Rate 100 100 57.2

}

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

4 i 1'

25. If Shut Down At End Of Report Period Estimated Date of Startup To be determined
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 1 INITIAL ELECTRICITY I COMMERCIAL OPERATION (9/77) ? ? 4 _ __ r_ __1__ _ _ _ -~

Pega 23 OPERATING DATA REPORT DOCKET NO. 50-260 DATE 4-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (2051 729-2937 OPERATING STATUS l Notes l 1. Unit Name: Browns Ferrv Unit Two l l 2. Reporting Period: March 1989 l l 3. Licensed Therinal Power (Wt): 3293 l l 4. Nameplate Rating (Gross We): 1152 l l 5. Design Electrical Rating (Net We) 1065 l l 6. Maximum Dependable Capacity (Gross We) 1098.4 l l 7. Maximum Dependable Capacity (Net We) 1065 l 1 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: N/A 9. Power Level To Which Restricted If Any (Net We): N/A

10. Reasons For Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 2.160 149.815.00 l
12. Number o_f_ Hours Reactor Was Critical 0

0 55.860.03 i

13. Reactor Reserve Shutdown Hours 0

0 14.200.44

14. Hours Generator On-Line 0

0 54.338.36

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (WH) 0 0

153.245.167

17. Gross Electrical Energy Generated (WH) 0 0

50.771.798

18. Net Electrical Energy Generated (WH)

-2.005 -6.626 49.045.106

19. Unit Service Factor 0

0 36.3

20. Unit Availability Factor 0

0 36.3

21. Unit Capacity Factor (Using MDC Net) 0 0

30.7

22. Unit Capacity Factor (Using DER Net) 0 0

30.7

23. Unit Forced Outage Rate 100 100 57.6
24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Ecchi:
25. If Shut Down At End Of Report Period, Estimated Date of Startup Seotember 20. 1989
26. Units. In Test Status (Prior to Comercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY l COMMERCIAL OPERATION (9/77) i

=. _ _ - - - _. _ '1 e Pegs 24 OPERATING DATA REPORT DOCKET NO. 50-296 DATE 4-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (2051 729-2937 OPERATING STATUS' l Notes l 1. Unit Name: Browns Ferrv Unit Three l l- ' 2. Reporting Period: March. 1929 l. l t 3. Licensed ' Thermal Power (Wt): 3293 l-l l 4. Nameplate Rating (Gross We): 1152= l. l l 5. Design Electrical Rating (Net We)-1065 l- .'l l[ 6. Maximum Dependable Capacity (Gross MWe) 1098.4 l l. 7. Maximum Dependable Capacity'(Not MWe) 1065 l I I

8. 'If Changes Occur in Capacity Ratings (Items Number 3 Through 7) $1nce Last Report, Give Reasons:

h/A t f-9. Power Level To Which Restricted,' If Any (het We): N/A {

10. Reasoir 'r Restrictions If Any:

N/A Thir Month Yr-to-Date-Cumulative I

11. Hours in Reporting Period 744 2.160 132.240.00 j
12. Number +f-Hours Reactor Was Critical 0

0 45.306.08 j

13. Reactor Reserve Shutdown Hours 0

0 5.149.55 1

14. Hours Generator On-Line 0

0 44.104.76 j

15. Unit Reserve Shutdown Hours 0

0 0 1

16. Gross Thermal Energy Generated (MWH) 0 0

131.868.267

17. Gross Electrical Energy Generated (MWH) 0 0

43.473.760

18. Net Electrical Energy Generated (MWH)

-1.590 -5.023 41.895.064

19. Unit Service Factor 0

0 33.4 3

20. Unit Availability Factor 0

0 33.4 j

21. Unit Capacity Factor (Using MDC Net) 0 0

29.7 l

22. Unit Capacity Factor (Using DER Net) 0 0

29.7 }

23. Unit Forced Outage Rate 100 100 61.7 j
24. Shutdowns Scheduled Over Next 6 Months (Type Date, and Duration of Each):

I r i

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined
26. Units In Test Status (Prior to Commercial Operation):

Forecast' Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9177) 3m. .-m

Pags,25 - 5" AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO. 50-259~ Unit 'One -DATE 4-1 * . COMPLETED BY S. A Ratliff-TELEPHONE' -(2051729-2937 MONTH MARCH 1989 DAY AVERAGE DAILY POWER LEVEL DAY' ' AVERAGE DAILY POWER LEVEL-(MWe-Net)- '(MWe-Net). 1 -8 17 -7 2 -7 18 -8 1 3. -4 19 -7 4 -6 20. -7 5 -5 21 -7 6 -5 22 -8 7 -7 23, 8 -6 24 -9 9 -7 25 -8 10 -8 26 -5 11 -8 27 -8 12 -7 28- -8 13 -7 29 -8 14 -7 30 -8' 15 -5 31~ -8 '16 -9 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in l the reporting month. Compute to the nearest whole megawatt. l (9/77)

-.%9p,m. e v.i , es .o .e -.. m Pegs 26 AVERAGE DAILY UNIT. POWER LEVEL $h? DOCKET NO. 50-260 s 4~a - -z

  • 2 -

Unit Two ww J. s,... w' .~n,.,- ' W u DATE 4-1-89 4 .,.m,,&y.,. mugwgircq s' C y b y v,3 z_ , <.jnWWF.a(Qh'MMrr.. COMPLETED BY S. A. Ratli g c

n. 3 ;

.n as n -' re ;..tg ~ ' T"A '7"'4 TELEPHONE. (2051729-2937 i ?r % y %, g C f g,! $ w!T R ~< m: nv n.: ' S:t.(f$

  • ,1

%(k%&i fgdWQ? Abs;,?WW c s i ..a;;/;,9 agMw;c+gg@g@ f,4

.?

.w,. m.,, '):,62 gds,yg MONTH MARCH 1989 uwMjnca 4niMg:w!:; p '+- g, my.g.y .y DAY AVERAGE DAILY POWER d N T " DAY ~ AVERAGE DAILY POWER LEVEL ^ (MWe-Net) 'M @ w w.M % Q 4FI ~Y "'(MWe-Net) l v y a:. n.. ey.17 -2 _4 -m - .m g,,.w%..cMy,cp? y,&w e je . A.,Go. iwho ~

    • r:,k'wm : 18

-3 2 ~4 W ~ x. A b%*.$5;.. %% kin,:e x t e v:.M,,r. 19 -2 3 -3 i - w: ' q$TQy*~ip".f'? 4 -3 4+-t 20 -3 -yr.

w 5

-5 21 -2 ,-w,% 4.f- ..i. s_~,< 22 -2 6 -4 , vcngy, ap4 _,wy;,s am e x nn e y _g ,g3 n : p r s ~~ g,= 9 9 9 ~~ l 8 -4

  • 'WJQ+sf*dLt ",;#msh 24

-2 l.

q. yh ;c;-

a n y.,- A y I N ' my . a w.p~.w L 9 -3 .WH 25 -3 10 -2 26 -2 11 -3 27 -2 12 -2 28 -2 mmmy = 64 *e 29 '2 l 13 -2 ~ n n.v.mw4

  • ' ~ ~ '
  • 14

-2 30 -2

c -

Y w' h t hk N? W f 15 -2 31 -2 1 16 -2 l 1 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. ~,: n,., uw Mw. J..-A: (9/77) .r.as , t *., A g, L.6

,s,a' 4 ) g' s

..N* ,y ulpino, g, ; 4..mN e,.y ,.gg . benawawe. mens *,IlogerpJM.ns'ygv*y wm ape,a p >, ~w,,+yp#w r,vtpdQygt w.m ;w p,,,,,,,, .e r c_,.. ,, ~3,qu a s,p., ..s. y y g - W 9' l'i,,..s cm cq e g%;g..Qf..y*g;,.A. ]y.pAv;.; 4.s34, c. w.f,.:.,., die 3 fy n.r... a.+pfges;p.eem+ m>msw;.3, 'n,arp % _ uc ,:; y. .s .}a,,. M &., e;\\7".:n.w7;p..y.,4,, M; g w y.a v,k M;, A m m u.v,,: &mu,

__ Ty e,gsfn

'w r l

P:ga 27 . AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Unit Three DATE 4-1 " COMPLETED BY-S. A. Ratliff TELEPHONE' (2051729-2937' MONTH MARCH 1989 DAY AVERAGE DAILY POWER LEVEL DAY - AVERAGE DAILY POWER LEVEL -(MWe-Net) (MWe-Net) 1 -2 17 -2 1 2 -2 18 -2 3. -2 19 -3 4 -2 20- -2 5 -3 21 -2' j 6 -2 22 -2 7 -3 23 -2 8 -2 24 ' 9 -2 25 ' 10 ~ -2 26 ' -1 11 -2 27 12 -2 28- -2 13 -2 29 14 -2 30' -2 15 -2 31 -2' 16 -2 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day 'in the reporting month. Compute to the nearest whole megawatt. -(9/77)

] . j i)lll1 i

]

~ l mg e,oo c . 7. f 3 i 2 .A f 9 l I R t 9 l a 2 t R 7 .N 9 9 e ( e 5 8 . ) v ele 2 - A 5 l s . s a si e nt nF rt e 1 0 on oa e) u' 0 n . 2 sr i D i.R o c t 5 O 4 S ( ee c g e e rc u I1E S o Iv-c rL e r n n o c e oo ts mf( m' O.EEYE. t ni I r Ii s a r e, t c N MT8N ,u - ae ro S r t t r AA D O ep o c dC 4 r E H C,y K T T P

R lR

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  • g haa ut b 7,u E

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  • t t

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l'l1I! 4' 1 yn$ ne ' ~ &3 7 i 9 G~ 2 H .E = 9 R n 2 U - 0' 9 7 e' N - 3 ) v'. 6 1 ( e e~ .2 A 5 l s . el s 1 0 on a si~ e o ninF c - 0 w 2 sr oae) i c u 5 T a c ( ee iDiR o t rc cfL E S e e u v c n orL' e i n uo r o ts m m t nf( O EEYE c e t c r eor t a . N MTBN Iis io' S r ..t t u dC ae t r A A D O unc lR ep-E H 'Co K T T P. iR oN

Gahe r

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4' S i rT ss iuno iimr da Av SN O

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minu ur meh r e uif ge 4

is ga e e pd p t i ,g* F a E. M R R O A. O O e - 1 RABCDEFG1 ~* 2 4 8 / te 5 ~ a 1 D ./ l ~ 9 ilc 0 du' ed c e sp. g' l lIl1lIl - .nh it FS o. 5 ) 0

i 7

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Page 31 rva nara toup.6.au NUCLEAR PLANT OPERATING STATISTICS Browns Ferry Nuclear Plant Per od Hours 744 Month umh 19 14 Item l, No. Unit No. UNIT 1 UNIT 2 UNIT 3 PLANT 1 Average Hourly Gross Load, kw 0 0 0 0 2 Madmum Hour Net Generation. MWh 0 0 0 0 3 Core Thermal Eneroy Gen, GWD (t)2 0 0 0 0 4 Steam Gen. Therrnal Energy Gen., GWD (t)2 NA NA NA NA l 5 5 Gross Electrical Gen., MWh 0 0 0 o j j 6 Station Use, MWh 5,109 2.005 1.590 8.704 l E 7 Net Electrical Gen., MWh -5.109 -2.005 -1.590 -R.704 l. 8 Station Use, Percent 0 0 n n ( 9 Accum. Core Avg. Exposure, MWD /Toni 0 0 __ _ R_ _,,,_ _fL ) 10 CTEG This Month.106 BTU 0 0 n n- '11 SGTEG This Month.106 BTU NA NA NA NA I? 13 Hours Reactor Was Critical 0 0-n n 14 Unit Use, Hours-Min. 0 0 n n 15 Capacity Factor, Percent 0 0 0 0 y 16 Turbme Avail. Factor Percent 0 0 0 n 17 Generator Avait. Factor. Percent 0 0 n n 4 C 18 Turbooen Avail Factor Percent 0 0 o n 19 Peactor Avail. Factor. Percent 0 n n n 2 20 Unit Avail. Factor. Percent 0 0 n n 21 Turbine Startues 0 0 n n 22 Reactor Cold Startuos 0 0 0 0 23 ~~ g 24 Gross Heat Rate, Btu /kWh 0 0 0 0 j 25 Net Heat Rate, Btu /kWh 0 0 0 n E 26 C ?7 g 28 Throttle Pressure. psig 0 0 0 n E 29 Throttle Temperature, 'F 0 0 0 n d, 30 Exhaust Pressure, inHg Abs. 0 0 0 n j E 31 intake Water Temo.. *F 0 0 0 n 32 33 Main Feedwater, M lb/hr 0 0 n n i 34 35 l 36 l 37 Full Power Capacity EFPO (3) (4) (4) (A) j 38 Accum. Cycle Full Power Days. EFPo '(3) (4) (4) (A) f 39 Oil Fired for Generation, Gallons 8,507 7 40 Oit Heatma Value. Btu / Gat 11R 5n0 41 Diesel Geneestion. MWh 134.4 49 Max, Hour Net Gen. I Max. Day Net Gen-Load MWh Time Date i MWh { Oate Factor. % 2 43 0 1 0 1 0 / i Remarks: A For BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU. j 2(t) indicates Thermal Eneroy. 3 3 Information furnished by Renctnr Anm1ve4e Group. Chattanooga l 4 Administrative hold Date Submitted Date Revised Pleng gegrinte9iSQnt

q]1

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N N 8' uE J 4. C N T O N I T E CVN AEO RI E P I T V v I OTE T T s, C P 3 'I E NE R ER R K h cr 4 O A T a 6 C M 7 s r r M P SDO X. a u e o E Y. H .SG G / TWN h d I I A t o n NA RT o. ire UT UU I X F G R NNO TWT TO C UD A T H F. S R m. a ~ un i tn E o S c U t d n A l la C o P E h r Y a G e IT e A v L lc T i t I o U s_ B N a O r A t L s I i A = V N A e D n ^ y O X N r a All W e e E F n G o Timi I e!i e I i !i I 8* i Ii i I 8 X S A s N W n T w it U o n n X O r U E et B T imu s!; i 8 tj-i I' i 8 I8 e e I t!' ? o NI T s W U C 0 0 n t i 0 0 0 (1 i lM r n u 1 s 6 4 4 W 2 2 4 7 r n e a e 0 0 0 M 0 0 0 lb ic r I s la a 's 1 e ia 6 4 6 n m v 2 2 4 A 1 t o a 0 - 0 0 0 0 N M 6 0 e n r n e 8 h G l '4 1 s 4 4 T W 2 2 4 7 W e m 0 0 M m 0 0 0

M w

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  • t!i 8

w 1 le o 1 ic th m ) P r e m t 6 i 7 r g c n o n le n ee a a t M 3 t it c E m s o t e R s T l 8 8 i 8 ?l m 6 8 i 8 I'

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Page 35 REACTOR. POWER PERCENT MARCH 1989' UNIT 1 PERCENT 10D 90 BD 70 60 : ADMINISTRATIVE HOLD. 50 40 30 20 10 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 UNIT 2 PERCENT $00 90 80 70 60 ADMINISTRATIVE HOLD 50 40 30 20 10 0 1 2 3 4 5 6 7 8 9 10111213141516171B 19 20 2122 23 24 25 26 27 28 29 30 31 UNIT 3 PERCENT 100 90 80 70 60 50 ADMINISTRATIVE HOLD 40 I 30 20 10 1 2 3 4 5 6 7 8 9 10111213141516171B 19 20 2122 23 24 25 26 27 2B 29 30 31

v 3i e 4 'l ) 1 -j i i MAINTEXAXCE SEMMARY I l 1 i I

Paga 36 6 MAINTENANCE MONTHLY OPERATING REPORT MARCH 1989 The Maintenance Request backlog has continued to increase, Preventive Maintenance was not being performed at'an acceptable' level and, even though Preventive Maintenance performance was not. acceptable, thb manhours dedicated to preventive types of maintenance was near the 50% goal. System engineers are reviewing the Maintenance Request backlog to ensure all work is correctly categorized. This will allow Maintenance to focus N on the correct activities to not only support unit 2 restart but also have an acceptable backlog of work at the time of restart. Preventive Maintenance is being evaluated by the Maintenance-Planning and-Technical Group to determine those items not required for. restart which should be deferred. Also, they are evaluating which items that would be more efficiently performed by the Operations Department.,.These evaluations are scheduled to be complete by May 6, 1989. The Maintenance Planning and Technical Group efforts for the month of March were primarily devoted to closure of action items associated with the April INPO evaluation, failure investigations and revisions to plant instructions. I The Electrical, Instrument, and Mechanical Maintenance groups supported divisional outage schedules and performed walkdowns and validations of Surveillance Instructions. Maintenance Support continued its' efforts on improvement of plant-material condition and began walkdowns of SPOC systems to identify repairs. 1 that might be needed. l Program Support continued to improve the NRC Maintenance Inspection Plan, tracked and closed Maintenance Improvement Program Action Items, and coordinated with Nuclear Maintenance to obtain resources to close Operational Readiness Review Items'and Maintenance Assist Review Team Items. l l 1 l l r A

h i Pag 3 37 This page intentionally left blank. c9 e I e a h aus eum l 4 l I j i i i i ) ' 1 i )

R Y 1 i a O b OTHER REPORTS 3 a l I l l 1 1 i 1 L i 1 i

Pags 38 CHEMISTRY

SUMMARY

MARCH 1989 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained'within technical. specification and fuel warranty limits duri,ng the month. Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. 'This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.. Unit 2 The conductivity of the reactor coolant remained within technical -specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant' remained within technical specification and fuel warranty limits during the month. ' This calendar year, the technical specification and fuel warranty limits for. conductivity and chloride have not been exceeded. Unit 3 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded. Abnormal Releases None 4 4 ) 4

o Pega 39._ PRIMARY COOLANT CHEMISTRY MARCH 1989 Parameter Unit 1 Unit 2 Unit 3-

1. Gross Radioactivity a.

Crud (filter) (uci/ml)- High N/A N/A N/A Low. - N/A -N/A N/A Average N/A N/A' N/A -b. Filtrate (pCi/ml) High-N/A N/A N/A Low N/A- 'N/A N/A Average N/A N/A N/A

2. M1111oore Iron (Fe.DDb)-

High N/A N/A N/A Low N/A N/A .N/A Average N/A N/A N/A'

3. Tritium (vC1/ml)

High 3.57E-5 2.90E-5 1.28E-4 Low 3.26E-5 2.69E-5 1.07E-4 Average 3.41E-5 2.79E-5 1.19E-4

4. Iodine-131 (yci/ml)

High <1.14E-6 <8.49E-7 <7.94E-7 Low <9.87E-7 <6.74E-7 <2.72E Average N/A N/A N/A

5. Iodine-131: Iodine-133 Ratio High N/A' N/A N/A Low N/A N/A N/A~

Average N/A N/A N/A q 1 i

l n Pega'40 PRIMARY COOLANT CHEMISTRY (Continued)- Parameter Unit 1 Unit 2 Unit 3

6. Chloride foobl High.

<20 <20 <20 Low <5 '<5 <5' Average. NA NA NA L 7.. Sulfate (Dobl High: . <10 <10 - <10 Low <5 <5 <5 Average NA NA NA

8. DH 9 25'C High 6.2' 5.9-6.1 l

Low 59 5.6 5.7 Average' 6.0 5.7 5.9

9. Conductivity (pmho/cm825'C) -

High 0.28 1.02 0.51 Low-0.092'. 0.88 0.29 Average 0.12 0.95 0.41 i l l j l \\ l 1 i l l l l L)

Pegs 41. i'" =- l l l ENVIRONMENTAL REPORT j MARCH 1989 l The ambient upstream river temperature {24-hour average) ranged from l The' 8 i 46.3'F (March 1) to 60.0'F (March-29) with an average of 53.7'F. downstream temperature varied between 46.8'F (March 1) to 60.5'F (March 29) { i with an average of 53.8'F. The largest temperature change occuring 'on March 6 was 1.8'F with a monthly average change of 0.3*F. The water temperature has been. steadily increasing and therefore l Aquatic Research has been contacted for the detection of juvenile clams. Surveys completed indicate gravid adults with larvae in the trochlore stage. No juveniles were detected in the water column. We are presently j moving toward beginning another chlorination cycle for the Emergency l EquipmentCoolingWater. 1 i The sedimentation pond is still not in service pending repairs. The stabilization pond (Lagoon) flow was sampled only once dur.ing the l month. A noted elevation in the Biochemical Oxygen Demand (B005) prompted personnel to shut the flow of f on March 13. The flow maximum was 148,000 GPO on March 3 and 7, with an average of 84,247 GPD. The Total Suspended Particulate and the B005 are respectively 21 and 35 ppm with the l RODS exceeding the daily average of 30 ppm. l

l a Peg 2 42 j 1 -l AIRDORNE RELEASES (1) MARCH 1989 rj SUMMATION OF ALL RELEASES UNIT THIS MONTH-a A. FISSION AND ACTIVATION SASES 1. 'f07AL. RELEASE CI- .< 1.04E 02 ) i 2, AVERADE RCLEAtlE RATE FOR PERIOD UCI/SEC. < 3.45E 01 3. PERCENT OF TECH. SPEC. LIMIT (O'.15 CI/SEC) 0.00E-01 B. IODINES j 1 1. 10T0L 10 DINE - 131 CI < 1.26E-04 i 2. AVERAGE RELEASE MATE FOR PERIOD UCI/SEC' < 4.17E-05 3. PERCENT OF TLCH. SPEC. L1 HIT (2.19 UCI/SEC) 0 00E-01 C. P ARTIcuT.?iTES 1 5 j 1. PARTICULATE WITH HALF-LIFES > OR'= TO 8 DAYS 'CI <.6 96E-04 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC < 2.30E-04 l 3. PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 4. GROSS ALPHA RADI0 ACTIVITY CI 6.37E-07 D. TRITIUM 1. TOTAL RELEASE CI 1 24E-03 j l 2. AVERADE RELEASE RAIE FOR PER;9D UCI/SEC 4.10E-04 I 3. PE RCE N'l DF TECH. SPEC. LIMIT (2.19 UCI/SEC) -1'87E-02 4. GROUNO LEVEL REl..EACE CI < ?.37E-03 ELEVATED RELEASE CI 1.24E-03 Lj l' . REPORTING PERIOD 35 DAYS 1 '(1) 1 1 _ A

P:g2 43 AIRBORNE RELEASES (CONTINUED) MARCH 1989 ELEVATED RELEASES A. FIBGION GASES-UNIT THIS MONTH KR-85M CI < 1 67E-01 KR-05 CI < 4.93E 01 KR-87 CI < 4.46E-01 KR-GD CI < 5.01E-01 XE-133 CI < 3 80E-01 XE-13$M CI < 2.94E-01 XE-135 CI < 1.89E-01 XE-138 CI <, 8.29E-Oi OTHERS(SPECIFY) i TOTAL FOR PERIOD CI < 5.21E 01 ) B. IODINES 1 I-131 CI < 8.26E-06 l I-133 CI < 6.64E-05 l 1 I-135 CI < 6.29E-02 I TOTAL FOR PERIOD CI < 6 29E-02 l i l I l i i l

1 l d P2gs 44-AIRDORNE RELEASES (CONTINUED) MARCH 1989 . ELEVATED RELEASES C. PARTICULATE UNIT: THIS MONTH SR-89 CI. < 2.59E-07 SR-90 CI < 1.06E-07 CS--134 CI <'?.09E-06 CS-137 CI < 1.76E-05 B A -14 0 CI <'2 85E LA-140 CI < 3.29E-05 OTHERS(SPECIFY) TOTAL FOR PERIOD CI < 8.84E-05 D. TRITIUM CI 1.24E-03 4 i i i 1 -l l; L,.. -m.,, _. _.a., i

Peg 2.45 s AIRDORNE RILEASES (CONTINUED) MARCH '1909 GROUND RELI::ASES A A. FICGION GASES ' UNIT THIS MONTH KR-GSM CI < 1.25E KR-05 C'I < 4.04E 01 KR-87 CI <'3 09E-01 KR-88 CI- < 4.93E-01 l l XE -133 CI < 4.73E-01 1 XE-135M CI < 7.48E-01 XE-135 CI < 1.51E-01 X E .t c 0 CI < 1.40E 00 0THERS(SPECIFY) l TOTAL FOR PERIOD CI < 5.21E 01 __...-----~~----- B. 10 DINES I-131 CI < 1.10E-04 I-133 CI < 5.30E-04 I-135 CI < 0.00E-01 l TOTAL FOR PERIOD -CI < 8.01E-01 l i l \\ { i l

( Page 46 AIRDORNC REl. EASES (CONTINUED) MARCH .1789 GROUND RCl. EASES 4 C. PARTICULATE UNIT THIS MONTH SR-89 CI < 2 61E-06 SR-90 CI < 9 86E-07 CS -134 CI < 8.14E CS-137 CI < 7.58E-05 BA-140 CI < 3 39E-04 LA-140 CI < 1 00E-04 ~ OTHERS(SPECIFY) TOTAL FOR PERIOD CI < 6 0BE-04 D. TRITIUM CI < 7.37E-03 l r .._,...m__..-,

Page 47 BROWHS FERRY NUCLEAR PLANT ^ MONTHLY REPORT CALCULATIONS LIQUID RELEASES MARCH 1989 RADI0 ACTIVE LIQUID. EFFLUENTS 1. GROSS RADIDACT[VITY UNITS s) TOTAL RELEASE CURIES 2.05E-02 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1 17E-09 c) PERCENT OF APPLICABLE LIMIT ( 1E-7 UCI/ML ). 1.17E 00 2. TRITIUM s) TOTAL RELEASE CURIES 6.08E-02 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 3.91E-09 c) PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 1.30E-04 (1) 3. DISSOLVED NOBLE GASES a) TOTAL RFLEASE CURIES C 1.03E-03 b) AVERAGE DILUTED CONCENTRATE 0H RELEASED UCI/ML < 5.07C-11 c) PERCENT OF APPLICABLE LIMIT (2E-04 UCI/ML) < 2 93E-05 4. GROSS ALPHA RADI0 ACTIVITY a) TOTAL RELEASE CURIES <2.12E-04 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML <1.21E-11 1 5. VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERG 4 65E 06 l I 5. VOLUME OF DILUTION WATER LITERS 1.76E 10 (1) INCLUDES XE-133, XE-135, AND OTHERS

i Page 48 BROWNS FERRY HUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASEC MARCH 1989 l 1 ISOTOPES RELEASED . UNITS CI CR-51 < 2.58E-03 MN-54 < 3.33E-04 CO-50 < 3.06E-04 FE-59 < 6.76E-04 CD-60 5.50E-03 ZN-65 1.81E-04 NB-95 < 2.88E-04 2R-95 < 5.25E-04 N0rC-99M < 2.31E-04 I - 131 ~ < 3.45E-04 XF-133 < 8.47E-04 CS-134 2.10E-03 l XE-135 ! 1.85E-04 l CS-137 1.27E-02 l BA-140 < 1.26E-03 LA-140 < 2.34E-04 CE-141 < 3.98E-04 CR-89 < 1.28E-04 SR-90 < 4.69E-05

^ Pagi 49 DROWNS FERRY NUCLEAR PLAN'T MONTHLY' REPORT CALCULATIONS LIQUID RELEASES MARCH 1989 4 OTHERS UNITS ~ 4 CI-SB-125 1.34E-05 FE-55 < 1.20E-03 Y t .i i l l l l )

^**hr PagaiS0; ' BROWNS FERRY, NUCLEAR' PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES . MARCH .1989 r LAUNDRY DRAIN VOLUME RELEASED: 5658.0 GALLONS FLOOR DRAIN VOLUME RELEASED:. -992524.1-l GALLONS WASTE SAMPLE-TANK VOLUME RELEASED - 229380 5 GALLONS. DISTILLATE TANK VOLUME-RELEASED: 0.0 GALLONS LOCATION OTHER THAN.RADWASTE VOLUME RELEASED: 00 GALLONS TOTAL VOLUME RELEASED TO THE RIVE'R: 1227562.6-GALLCNS-HIGHEST BATCH' ACTIVITY RELEASED FOR MONTH:' 8.72E-09 UCI/ML A/D-LONGEST RELEASE' TIME FOR' MONTH:. 1157 MINUTES-SHORTEST RELEASE TIME FOR MONTH: .195. MINUTES TOTAL TIME 0F RELEASES FOR MONTH: 11614 MINUTES . AVERAGE TIME FOR BATCH RELEASES: .283 MINUTES: NUMBER OF' BATCHES RELEASED: 41 NUMBER OF ADMINISTRATIVE LIMIT VIOLATIONS: 0-NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS: 0 t

Peg 2 51 e i l l RESIN USAGE REPORT MARCH 1989 RESIN CONSUMED (CU.FT.) l % of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 35.3 0 153 0 0 0 153 Waste Demineralized 0 0 0 0 0 0 0 Waste Filter 39.5 0 171 0 0 0 171 l Fuel Pool Demins 0 0 0 0 0 0 0 Reactor Water Cleanuo 1 Unit 1 0.7 0 3 0 0 0 3 Unit 2 1.4 0 6 0 0 0 6 Unit 3 0 0 0 0 0 0 0 Cond. Demins. Unit 1 0 0 0 0 0 0 0 Unit 2 23.1 0 100 0 0 0 100 Unit 3 0 0 0 0 0 0 0 Totals 100 0 433 0 0 0 433

  • "8 Pags 52 FUEL CLADDING INTEGRITY, PARAMETERS MARCH 1989 Unit 1 Reactor Water Iodines (vci/sec)-

Date I-131 1-132 I-133 I-134 .1-135-Unit in Outage Fission Gases at Discharae of SJAE (uci/sec) -l Date Flow MWt Xe-138 ' Kr-87 Kr Kr-85 Xe-135 Xe-133 - Unit in Outage Unit 2 Reactor Water Iodines (yci/sec) Date I-1 31 1-132 I-133 'I-134 I-135 Unit in Outage Fission Gases at Discharae of SJAE (vci/sec) Date Flow MWt Xe-138 ' Kr-87 Kr-88 Kr-85 Xe-135' Xe-133 Unit in Outage Unit 3 j Reactor Water Iodines (vci/sec) i Date I-1 31 1-132 I-133 1-134 I-135 j =i Unit in Outage-i Fission Gases 'at 'Discharoe of SJAE (vci/sec) Date Flow MWt-Xe-138 Kr-87 Kr-88 Kr-85 Xe-135 Xe-133 l Unit in Outage L r ___?_ -._r__

0 O 2 3 03 5 0 M + E E 1, e 9 8 4 2 1 7 2 5 , 0

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T Y

.W N F t I C S M )3 E ( T H l 0 50 D 0 + 4 5 NC R E R R N 3 E 0 0 E s 3 + + 9 E E M A O I 1 T 8 0 T M L 6 2 O A 9 L R T 1 5 A I F F D E F u lA C R ml 6 A a 6 6 T ( 0 60 0 E m R E+ T E 0 i 1 A E 7 4 N T 1 T S o S 1 A E L A T L I W l Wl W C F y A c G E ) M0 1 0 ( + + E E M. 00 0 O R O P t; D A G G R N T O I C K O A E N L R L A T U R F D L O p E O T K C T C N y S E A O A L T W L O C 1 l l I'

-1 .e '1 ,+ e ~i Pags 54. y 1 I -l TESTING

SUMMARY

MARCH 1989 ~ k Surveillance Testina -{ l )) Unit 0 A total of 164 surveillance tests were completed using 44 different test instructions. -Unit 1 A total'of 82 surveillance tests were completed on unit i using 22'different test instructions. Unit 2 .A' total of'132 surveillance tests were completed on unit 2 using 64 different-test instructions. Unit 3 ~ A' total-of 71 surveillance tests were completed on. unit 3 using-18 different test. instructions. I ] ..\\ . il i i l i i J .i

e-Page 55 ..i l TESTING

SUMMARY

'i (CONTINUED)- MARCH 1989 n =nnes. Tests. and Eneriments Heat:irinn Authorization From the NRC Pursuant to 10 CFR 50.59(a) f There were two revisions for units 1, 2, and'3-technical specifications. &=nnes. Tests. and Eneriments not Reauirinn Authorization from'NRC Pursuant to 10 CFR 50.59(a) j There were no special tests completed for this month. l l l l l J s l l l l i 1. l Z _*i?_N b_-_7_**:__^ "r_*l__~_r'__-._ Tr ~_T _'*r-n~= --v ---m-.. ._-w m --m, im. --__._m_ _,m._m_____

e... ** s Pege 56 REACTOD VESSEL FATIGUE USAGE EVALUA'QQJ MARCH 1989 The cumulative usage factors for the reactor vessel are as follows: Usaae Factor. ~ Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629' O.14360 ) i I h !~ 1 t -) M___________._.___._________ _.]

Paga 57 1 l s. CHANGES IN PROCEDURES MARCH 1989 1 >There were 352 revisions to plant instructions during the month; 352' instructions.were changed.primarily for correction;=and zero revisions related to safe operation of the plant. 4 i 'l L.. PT. ANT INSTRUCTION REVISIONS MARCH 1989. Category Instruction Reason for Reauest There were no revisions for the month. 1 i I 1 i i J

ed *+ f Pags 58 i I g - i CHANGES.IN PLANT ORGANIZATION MARCH 1989 l. L I There were two changes in plant staff for those positions designated as key' i supervisory positions for the month..The changes were:' q I l-(1) John R. Nebrig, named to Manager of Maintenance Planning.& Technical i .(2) ' Daniel C. Phillips, resigned as Maintenance Superintendent i 1 i .j l i

l..-

n Paga 59 p., [ 4 ACCIDENTS MARCH 1989-There were four loss-of-time accidents during the month. They.were as follows: (1) 3/6/89' AUO, Operations, strained back while loading bags ~in trash-compactor. (2) 3/7/89 Materials Clerk, Materials, broke leg, standing between fork lift and load of unistrut. Cut banding on'unistrut, unistrut fell on'her and broke her leg. (3) 3/9/89 Tool clerk, Materials, strained back. While standing at tool counter, he turned around to get some tools and felt a sharp pain in his back. (4) 3/20/89 Carpenter helper, MODS,' strained neck and shoulder while movir4 scaffold material on a willie wagon through personnel air lock door. l l-l 4 -____ - _. _ - _ _ _ _ _ _ - _ _ _ _ _}}

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