Text

Monthly Operating Repts for Jan 1989 for Browns Ferry Nuclear Plant
	ML20235Z147
Person / Time
Site:	Browns Ferry
Issue date:	01/31/1989
From:	Campbell G, Ratliff S; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 8903150190
	Download: ML20235Z147 (72)
	v • d • e

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S MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY i

l JANUARY 1989

" Safety and Quality are Paramount" '

DOCKET NUMBERS 50-259, 50-260 AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:

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. - [ Guy G. Campbell Plant Manager 2 g3981En3s87g89 ..

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. TABLE OF CONTENTS

, r PART I OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B. Fuel Performance and Spent Fuel Storage Capabilities Summary..... 2 C. Main Steam Relief Valve (MSRVs) Actuation Summary................ 5 D. Issuance of Special Reports Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 E. Licensee Event Reports Summary................................... 7 F. Offsite Dose Calculation Manual Changes......................... 13 G. Radwaste Summary................................................ 14

1. Total volume of solid waste shipped off site

2. Nature of the vaste (trash, 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.

PART II OPERATING STATISTICS A. NRC Reports

1. Operating Data Report....................................... 23

2. Average Daily Power Leve1................................... 26

3. Unit Shutdowns and Power Reductions......................... 29

. B. TVA Reports

1. Plant Operating Statistics.................................. 32

2. Unit Outage and Availability Data........................... 33

3. Reactor Histogram (Reactor Power Percent)................... 36 002R l

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(Continued)

Part III MAINTENANCE

SUMMARY

.............................................. 37 PART IV OTHER. REPORTS A. Chemistry Summary.

1. Primary. Coolant Chem'istry .................................. 39

2. Environmental Technical Specification Requirements.......... 42

3. Airborne Releases........................................... 43

.4. Liquid Releases............................................. 48

5. Resin Usage Report................................. ........ 52 .

6.. Fuel Cladding Integrity Parameters............................ 53 ,

7. Waste Treatment System Throughputs. . . . . . . . . . . . . . . . . . . . . . . . . . 54 B. Testing Summary...,............................................... 55 C. Reactor Vessel Fatigue Usage Evaluation.......................... 57

D. Chang e in P ro c edur e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 8 E. Plant Instruction Revisions...................................... 58 F. Change in Plant Organization..................................... 59

. G. Accidents........................................................ 60 l

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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 Supervisor ATWS Anticipated Transient Without Scram AUO Assistant Unit Operator -

BFEL Browns Ferry Equipment List BFN Browns Ferry Nuclear Plant BFNPP 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 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 l EQDP Environmental Qualification Documentation Package

EQE Earthquake Engineering l EQP Environmental Qualification Project l

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ACRONYMS / ABBREVIATIONS (Continued) , ,

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ER Engineering Report ERCW' Essential Raw Cooling Water ESF; Engineered Safety Feature FCR Field Change Request- . .

HM1EA . Failure Modes and Effects Analysis FSAR. Final Safety Analysis Report FW Feedwater GE General Electric GET General Employee Training .

GPM Gallons per minute GOI General Operating Instruction HPCI High Pressure Coolant Injection HVAC' . Heating Ventilation andcAir Conditioning IE Inspection and Enforcement (NRC)

IG Inspector General IGSCC Intergranular Stress Corrosion Cracking IHSI Induction Heating Stress. Improvement INPO Institute of Nuclear Power Operations IRIS- Input Requirements Information' System ISEG' Independent Safety Engineering Group.

ISI Inservice Inspection ITC Immediate Temporary Change

'JTG Joint Test Group LCO ., Limiting Conditions for Operation LDCR. Local Design Change Request LER Licensee Event Report LOCA' Loss of Coolant Accident LOP ~ Loss-of Power MAI Modification Addition Instruction MCC . Motor Control Center MCEL; Master Components Electrical List MMI Mechanical Maintenance Instruction MNt " Megawatts thermal

'MOV' Motor Operated Valve MR Maintenance Request .. , . . . .

MSIV Main Steam'Isolat' ion Valve MWe Megawatts electrical 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 F?S Nuclear Procedures Staff NQA Nuclear.Qu.ality-Assurance NQAM Nuclear Quality Assurance Manual

-NRC Nuclear Regulatory Commission NSS Nuclear Security. Service ;

NT .

Nuclear Training NUMARC '

Nuclear Utility Management and Resources Countil NUREG Nuclear Regulatory Documentary OI Operating Instruction OL Operating Licensee .

ONP Office of Nuclear Power

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' ACRONYMS / ABBREVIATIONS (Continued) l d , PASS' Post Accident Sampling System PCIS Primary Containment. Isolation Systee i PD ._ Position Description l PM ' Preventive Maintenance ;

PMT Post Modification Test !

PORC- Plant Operations Review Committee PSI l Preservice Inspection ,

PSS Potentially Safety Significant j

.. -QA Quality Assurance !

l QC Quality-Control '

-QMDS Qualification Maintenance Data Sheets.

RC- Radiological Control RCIC Reactor' Core Isolation Cooling REP Radiological 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 RTI Refueling Test' Instruction RTP Restart Test Program RWCU Reactor Water Cleanup SALP Systematic Assessment of Licensee Performance SCR . Significant Condition Report SCRAM Safety Control Rod Activation Mr.nually SDIV. Scram Discharge Instrumentation Volume SDSP- Site Director Standard Practice S/G(s) Steam Generators.

SI Surveillance Instruction SIL~ Service Information Letter SMMI Specia1' Mechanical Maintenance Instruction SOS. Shift Operations Supervisor SPDS Safety Parameter Display System-

'SPOC System'Preoperability? Checklist SON Sequoyah Nuclear Plant SQUG Seismic Qualification' Utility Group SRO' Senior Reactor Operator SRV Safety Relief Valve STA Shift Technical Advisor SYS NOS System Numbers TACF Temporary Alteration Control Form TI Technical Instruction 1N5 Technical Specification

. .TSS Total Suspended Solids TVA Tennessee Valley Authority UO Unit Operator USA United States of America USQD Unreviewed Safety Question Determination VMCP Vendor Manual Control Program 4

WBN Watts.Bar Nuclear Plant WP Workplan _

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OPERATIONAL SEMMARY l 4

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' Paga 1 SIGNI"TCANT OPERATIONAL EVENTS

SUMMARY

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l? JANUARY 1989 1'

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~ Unit 1

, ' 01/01/89- 0001 Unit remains on administrative hold to resolve'various l: .

TVA and NRC concerns.

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l. 01/31/89 - 2400 Unit remains on administrative hold to resolve various E TVA and:NRC concerns.

- Unit 2

.01/01/89- 0001- Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

01/31/89 2400 Unit remains on administrative hold.to resolve various-TVA and NRC concerns.. Cycle 5 refueling.and modifications continue.

Unit 3 01/01/89 0001 Unit remains on administrative hold to resolve various TVA and NRC-concerns.

01/31/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

JANUARY 1989 Unit 1

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Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with'a scheduled restart date to be determined. Major systems have been placed in layup configuration per applicable procedures. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1 modifications are environmental qualification of electrica) equipment (10CFR50.49), torus modification (NUREG 0661),

containment instrumentation modifications (NUREG 0737), fire protection thanges (Appendix R 10CFR50) (all), MSIV leak rate reduction modifications, modification of masonry-walls (IEB-80-11), devaluation of the vent drain and-

. test connections (LER 82020), valve leak rate testing modifications (Appendix J), HPCI. improvements, modification of PCIS logic (LER 259 85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14),

post-accident sampling modifications'(NUREG'0737)',~RPSafoltage monitoring modifications, H 02 2' sample line modification (LER 81050), and EECW carbon to stainless pipe changeout.

There are zero assemblies in the reactor vessel. The spent fuel storage pool-presently contains 284 new assemblies, 512 EOC-6, 267 E00-5, 245 EOC-4, 362 EOC-3, 26 EOC-2, and 168 EOC-1 assemblies. The 252 E00-6 assemblies were transferred to unit 2 SFSP. The present available capacity of the fuel pool is 1607 locations.

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FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED)

JANUARY 1989 Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date of September 20, 1989. On September 3, 1985, ;

the unit was placed on administrative hold to resolve TVA and NRC safety ;

concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 2 modifications are CRD

.SDIV piping modification (IEB 80-17), environmental qualification of 9

electrical equipment (10CFR50.49), torus structural modifications (NUREG 0661), containment instrumentation modification (HUREG 0737), fire protection, changes (Appendix R 10CFR50), MSIV. leak rate reductions modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619),. evaluation of- the v'ent drain and test

connections (LER 82020), valve leak rate testing modifications (Appendix J),

D/G speed sensor installation (LER 81004), HPCI and RCIC testable check valve, changeout, modification of PCIS logic (LER 259 85009), HPCI improvements, 2 various seismic program' review and EECW carbon to stainless-pipe changeout. 3 Core reloading began on January 3, 1989 and was completed on January 30, 1989. TVA interrupted fuel loading from January 5, 1989 until January 16, 1989, because of inadequate monitoring of core reactivity during the loading process.

There are 764 assemblies in the reactor vessel. The spent fuel storage

} pool presently contains zero new assemblies, 4 unit 1 reload 5, 604 E0C-5, 196 h EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies. The present available i

{ capacity of the fuel pool is 1,689 locations. However, when the final two

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13 x 13 racks are instal' led this will increase the available space to 2,027. ~

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~ FUEL. PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED)

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' JANUARY 1989 s

Unit 3 a

.t Unit 3'was' shut down on March 9, 1985,-and placed on administrative hold p to resolve various TVA and NRC concerns with a scheduled restart.dat'e'tofbe i

determined. Major systems have been placed in'layup configuration per applicable procedures. The sixth refueling outage involves loading 8x8R

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h (retrofit)' assemblies into the core and'ATWS modifications.- The prior-to-startup unit.3 modifications are environmental. qualification of.

. electrical equipment (10CFR50.49), containment modifications (NUREG 0737),

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fire protection changes (Appendix R 10CFR50), MSIV leak rate reduction' modifications, modification of masonry walls (IEB 80-11),' evaluation of the vent drain and test connections (LER 82020)' valve-leak rate, testing

- modifications-(Appendix J), HPCI concerns,. replacement of plant process computer, seismic qualifications of piping.(IEB 79-02/14),. post-accident

. sampling modification (NUREG 0737), addition'of redundant drywell control air supply, RPS voltage monitoring modification, H 22 0 sample line modification (LER 81050), replacement of jet. pump holddown beam assemblies.(IEB 80-07),

- EECW carbon to stainless pipe changeout, and_ plant design upgrade to seismic qualification, g There are zero assemblies in the reactor vessel. The spent fuel storage

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pool presently contains 764 assemblies to finish cycle 6, 248 EOC-5, 280 g

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i EOC-4, 376 EOC-3, 97 EOC-2, and 3 EOC-1 assemblies. The present available F capacity of-the fuel pool is 585 locations.

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l MAIN STEAM RELIEF VALVE (MSRVs)

SUMMARY

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-JANUARY:1989 L

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No MSRVs were challenged during the month.

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ISSUANCE OF SPECIAL REPORTS

! - JANUARY 1989 l.

I There were no notices of violations issued for the month of January 1989.

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LICENSEE EVENT REPORT (s)

JANUARY 1989 Description of Event ,

, LEE 2-88-012 VIOLATION OF TECHNICAL SPECIFICATIONS DUE TO PERSONNEL AND Rev. 01 MANAGEMENT ERRORS Browns Ferry units 1, 2, and 3 were defueled during this event.

On October 13, 1988, at 1230 hours0.0142 days 0.342 hours 0.00203 weeks 4.68015e-4 months , three men conducting an observation of ongoing work activities in the unit 2 drywell observed that a firewatch in the area was in a less than fully alert state. During the preparation of preliminary investigation qg of this event, information was discovered which indicates that

other incidents of firewatches in a less than fully alert state have occurred which were not reported to the plant manager's j staff. Consequently, no reports on these events were made. ,

1-88-047 PERSONNEL ERROR DURING PERFORMANCE OF PREVENTIVE MAINTENANCE CAUSES UNPLANNED ENGINEERED SAFETY FEATURE ACTUATION On December 2, 1988, at 1930 hours0.0223 days 0.536 hours 0.00319 weeks 7.34365e-4 months , with all three units defueled, the unit i reactor protection system bus B inadvertently deenergized. This caused the actuation of primary containment isolation system groups 2 and 6, isolation of the -

unit 1 reactor building ventilation and refueling zone ventilation, and initiation of standby gas treatment and control y room emergency ventilation. This event was caused by a failure to follow procedures by personnel during the performance or a preventive maintenance procedure on the unit 1 reactor protection system motor generator set. The reactor protection system motor generator set was connected to the reactor protection system bus out of the procedure sequence. A contributing factor was a meter which waarused was inaccurate even.though it was within its calibration frequency. ,

1-88-048 UNPLANNED ENGINEERED SAFETY FEATURE INITIATION AND FAILURE TO COMPLY WITH TECHNICAL SPECIFICATIONS CAUSED BY PERSONNEL ERROR Events affecting the standby gas treatment system (SGTS) that were caused either by inadvertent or deliberate incorrect actions by unknown persons occurred on December 13 and 14, 1988, with all

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three units defueled. On December 13, 1988, at 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months , the '

SGTS building was discovered unlocked with train C in operation.

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-Lgg' 1-88-048 _ . The start of SGTS train C was apparently an unplanned manual u, (Continued). initiation of an engineered safety feature. SGTS fan C was:

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- stopped,: the' operability surveillance instruction was. performed:

- and the system returned to standby readiness. On December 14, 1988, at 0935 hours0.0108 days 0.26 hours 0.00155 weeks 3.557675e-4 months ,'SGTS was started as a planned engineered:

safety feature.. Train C was declared inoperable due to low' flow

. at 1020 hours0.0118 days 0.283 hours 0.00169 weeks 3.8811e-4 months . The SGTS fan C manual inlet damper ,was found_in the closed position. The damper'was administrative 1y locked open.

and the operability surveillance instruction performed. It was

. . returned.to standby readiness at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months .

1-88-49 IRADE0UATE PROCEDURE CAUSES TWO UNPLANNED ENGINEERED SAFETY J FEATURE ACTUATIONS

. With all three. units defueled, on December.17,.1988, two

- unplanned engincered safety feature actuations. occurred during-

, the performance of the diesel generator A load acceptance.

~ surveillance instruction.- At 1721 hours0.0199 days 0.478 hours 0.00285 weeks 6.548405e-4 months the 2D residual heat

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. removal (RHR) pump started.because"of a procedural error and operated on minimum flow for 14 seconds and1 was manually

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tripped. The 2D RHR pump start should have beencinhibited. At' m .

1816 hours0.021 days 0.504 hours 0.003 weeks 6.90988e-4 months the Al and B3: residual ~ heat removal service water O. (RHRSW): pumps started.but was not' indicated intthe procedure-andL

- were allowed to operated for four. minutes. .The start of the

. RERSW pumps was a correct action but was not documented in the T surveillance instruction. - Both events vere caused by ceparate errors in the same procedure. 'Following the first event, the

- surveillance instruction was corrected"and the affected' steps-

- repeated. The surveillance instruction was_successfully.

completed. Other surveillance, instructions with.the potential.'

for initiating unplanned engineered safety: feature actuations will'be reviewed.

1-88-51' FAILURE TO MEET TECHNICAL SPECIFICATIONS BECAUSE OF PERSONNEL ERROR On December 21, 1988, at 1410 hours0.0163 days 0.392 hours 0.00233 weeks 5.36505e-4 months , the raw cooling water effluent radiation monitors on all three units were declared operable by the shift operations supervisor. At this time, the I

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Page 9 LICENSEE EVENT REPORT (s)

(Continued)

I&E 1-88-51 analyzing of grab samples as required by technical specifications when the radiation monitors are out of service was suspended. At 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months , on December 22, 1988, it was discovered that the radiation monitor sample lines did not have any flow because sampling system pumps were not operating. Grab sampling was immediately initiated at this time. The technical specification.

require samples every eight hours when the radiation monitors are out of service. Because of this condition, approximately 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months occurred between samples, therefore Technical Specification 3.2.D were violated.

1-88-52 UNPLANNED ENGINEERED SAFETY FEATURE ACTUATIONS DUE TO CIRCUIT PROTECTOR TRIP CAUSED BY DAMAGED INDICATING LIGHT SOCKET ,

Two events occurred on Browns Ferry unit 1 on December 24, 1988, and January 14, 1989, respectively, with the same cause and response. In both events the 1A1 reactor protection system circuit protector tripped deenergizing the 1A reactor protection system bus and completing the initiation logic for engineered safety features, including a channel A half scram, primary and secondary containment isolations, SGTS, and control room emergency ventilation. All three units at Browns Ferry were shutdown or defueled during these events.

1-88-53 MAIN STEAM RELIEF VALVES ACTUATING OUTSIDE TECHNICAL SPECIFICATION SETPOINT BECAUSE OF PILOT DISC STICKING On December 14, 1988, Browns Ferry was notified by Wyle Laboratories that two of the three unit 1 Target Rock main steam relief val'res tested did not pass ~ acceptance criteria. The valves had failed to actuate within 1 percent (11 psig) of their~

setpoints on initial actuation. The main steam relief valves actuated within limits on subsequent actuations. These valves were being tested so they could be loaned to ancther utility.

The remaining 10 unit 1 main steam relief valves have not been tested to date. The cause of the condition is sticking of the pilot disc in combination with inadequate clearance between the pilot rod and liner in labyrinth seal. This condition is being assessed by Boiling Water Reactor Owners Group. The valves were cleaned and setpoint properly adjusted. All unit 1 main steam relief valves will have the setpoint set as required by technical specification prior to the startup of unit 1.

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(Continued).

LEE 3

2-88-S01 SAFEGUARDS EVENT On. December 6, 1988, at 0419 hours0.00485 days 0.116 hours 6.92791e-4 weeks 1.594295e-4 months , with all three units defueled, a Nuclear Security copervisor, while conducting routine supervisory checks, discovered a Euclear Security officer

,. inattentive to his duties while. assigned to a ecmpensatory post.

on unit 2. The compensatory post had been established earlier in the year to allow access into primary containment. Upon discovery of the event,'the Nuclear Security supervisor immediately relieved the Nuclear Security officer of his duties and re-established the compensatory post. A follow-up search of the area was conducted with the assistance of other Nuclear i Security personnel. The search concluded.with negative results.

The shift operations supervisor was notified of the event. The Ruclear. Security shift supervisor'determtned/the event was-loggable in the safeguards event log. Senior security 4 management, after further review and investigation, escalated the event to a one-hcur phone call at 0730 hours0.00845 days 0.203 hours 0.00121 weeks 2.77765e-4 months in accordance with 10 CFR 73.71 Appendix G.I.c.. This phone call was made at 0812

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hours tha't same morning. This event affected unit 2 only.

.2-88-001 FUEL LOAD WITHOUT ADEOUATE NEUTRON MONITORING DUE TO INADEOUATE SAFETY REVIEW OF TECHNICAL SPECIFICATION AMENDMENTS This report is a voluntary LER which is being written to keep the NRC cognizant of an important event which occurred at Browns Ferry.

On January 3, 1989, at 1017 hours0.0118 days 0.283 hours 0.00168 weeks 3.869685e-4 months , with all three Browns Ferry units initially defueled, operators begania full' core reload of -

the unit 2 reactor. On January 5, 1989, at 1658 hours0.0192 days 0.461 hours 0.00274 weeks 6.30869e-4 months ,-with 74 assemblies. loaded, fuel loading was halted by plant management to evaluate NRC concerns with the reload procedure.

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Fuel was being loaded in accordance with a technical specification which allowed less than three counts per second on the source range monitors provided that the source range monitors t response was checked every' eight hours and the fuel was loaded in

s. spiral sequence. With the spiral sequence started at the center of the vessel, the fuel array was neutronically decoupled from the source range monitors detectors. This raised a

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Description of Event (Continued)

LEE 2-88-001 the concern that the reload procedures did not require complete (Continued) monitoring of core reactivity changes. This event occurred because of inadequate safety analyses to support technical .

specification amendments. The same technical specification is approved for other dockets. A 2-88-016 UNPLANNED MANUAL START OF AN ENGINEERED SAFETY FEATURE DUE TO PERSONNEL ERROR On December 9, 1988, at 1344 hours0.0156 days 0.373 hours 0.00222 weeks 5.11392e-4 months , with all three units defueled, the 2D RHR pump was inadvertently manually started from its local control station during the performance of the RHR logic functional test. The cause of this event was personnel

. error.--The pump was, tripped-immediately by the unit operator after operating for five seconds. The labeling of the RHR local controls will be corrected and licensed personnel vill review this event.

2-88-017 UNPLANNED INITIATION OF ENGINEERED SAFETY FEATURES DURING PERFORMANCE OF SURVEILLANCE INSTRUCTION BECAUSE OF INATTENTION TO PROCEDURAL DETAIL On December 18, 1988, at 0435 hours0.00503 days 0.121 hours 7.19246e-4 weeks 1.655175e-4 months , an unplanned initiation of the 2C core spray pump, opening of the core spray loop I inboard injection valve, and initiation of the C1 RHRSW pump occurred during performance of a surveillance instruction. During alignment of the core spray system for the surveillance instruction, an operator inadvertently placed the incorrect keylock switch in test.s Whenethe next procedural step was taken the 2C core spray pump received a start signal because the logic was not inhibited by its test switch. The pump start caused the opening logic to the injection valve to be completed opening the valve. The start of the corr. spray pump is an automatic start signal for the C1 RHRSW pump. Contributing factors to the event were: (1) The operator had been working 13.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months straight when the event occurred. (2) The procedure did not require independent verification for the test switch position.

2-88-018 REACTOR SCRAM INITIATED FROM NEUTRON MONITORING SYSTEM CAUSED BY PERSONNEL ERROR AND SPURIOUS CHANNEL TRIP On December 18, 1988, at 1815 hours0.021 days 0.504 hours 0.003 weeks 6.906075e-4 months , with all three units defueled, the unit 2 reactor received a full scram from the 0002R e'**

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Description of Event i'

(Continued).

LH 2-88-018 : neutron monitoring system. A half scram occurred on system B of (Continued) the reactor protection system, when an instrument technician accidentally grounded a jumper which was being installed under-

. the intermediate range monitor channel "E" calibration procedure. The grounded jumper cleared a fuse supplying power to the B system intermediate' range monitor detectors (B, D, F, and H),:thereby simulating hi-hi and inoperative trips. .Five seconds'after the fuse cleared a half scram was initiated on the reactor protection system A by a spurious hi-hi trip on intermediate. range monitor channel "E". This. completed the actuation logic and initiated the full scram.- Following an initial review of;the scram signals the fuse was replaced and.

the scram was reset at 1836 hours0.0213 days 0.51 hours 0.00304 weeks 6.98598e-4 months .

3-88-008~ UNPLANNED ENGINEERED SAFETY FEATURE ACTUATIONS CAUSED BY ERRATIC' VOLTAGE REGULATION DUE TO LACK OF PREVENTIVE MAINTENANCE On December 21, 1988, at 2005 hours0.0232 days 0.557 hours 0.00332 weeks 7.629025e-4 months , the unit 3 3B1 and 3B2 reactor protection system circuit. protector tripped deenergizing the 3B reactor protection system bus .and~ completing the initiation logic for engineered safety features, including a

. half-scram, primary and secondary containment isolations, SGTS, and control room emergency ventilation..

After switching to the alternate supply, the' unit operator reset the isolations and returned the systems to standby readiness by 2022 hours0.0234 days 0.562 hours 0.00334 weeks 7.69371e-4 months .

4 i

0002R t

[ - I).f J-D( [2[,4 Y#- [#<'NY #'M U N T# ("i" M N ] N '5eT#,T $ *p4 %/ #$* 2 $ $ r,3 Y I ) ["

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8 ," ? f Y 64 3]f,MW % [ri 4*

'A' # Pa gs'.13 3- .

?

0FFSITE DOSE CALCULATION MANUAL CHANGES JANUARY 1989 No. changes were made to the BFN Offsite Dose Calculation Manual during;.

the month.

6 0

! 0002R o

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P,2ga 14 r

RADWASTE

SUMMARY

JANUARY 1989 The radwaste system performed as designed.- Approximately 1.04E+06 gallons'

. of waste liquid were discharged containing~approximately 1.98E-02 curies of-activity.

There were five spent resin shipments and one trash shipment during January. A11' shipments were to Barnwell, South Carolina.

There were no trash shipments made by the Scientific Ecology Group, radwaste broker / processor, containing BFN waste during. January.

O v

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Page 15

'. Solid Radioactive Waste January 1989 Dewatered Spent Resin Shipments (

Volume of condensate / waste (CWPS) resin shipped: 29.12 Cu.M.

(1029.00 Cu.Ft.)

Total curies shipped: 69.8872 Volume of reactor cleanup (RWCU) Yesin shipped: O Cu.M.

( 0 Cu.Ft.)

Total curies shipped: 0 Date Shipoed Discosal Facility Tvoe of Resin

01/06/89 BarnweLL, SC CWP5 01/11/89 Barnwell, SC CWP5 01/17/89 BarnweLL, SC CWP5 01/20/89 BarnweLL, SC CWP5 01/25/89 BarnweLL, SC CWP5 Dry Active Waste

Number of drums shipped: 0 Volume: O Cu.M. ( 0 Cu.Ft.)

Total curies shipped: 0 Number of boxes shipped: 10 Volume: 26.32 Cu.M. ( 930.0 Cu.Ft.)

Totit curies shipped: 0.5341 Date Shipped Disposal Facility Tvoe of Packaoe 01/24/89 BarnweLL, SC Boxes Brokered shipments (SEG): 0 Volume: O Cu.M. ( 0 Cu.Ft.)

Total curies shipped: 0 Date Shicoed Disposal Facility TvDe of Packaoe N/A N/A N/A ii (1) ALL shipments were by Sole-use Vehicle i

9 I . > .

8 h

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i P2ga 16 *

< Solid. Radioactive, Waste (Continued)

January 1989 Summary l

R Type Shipped to Packaged on' Gross Curie' Estimated l of BarnweLL Site Awaiting Content.by Generation for Waste During Month Shipment Type of Waste Next Month

[ Compacted

( ' Drums O Cu.Ft.(2) 105,Cu.Ft. 0.00E+00 0 Cu.Ft.(2)

Boxes 930.0Cu.Ft.( ' 93 Cu.Ft. 5.34E-01 800 Cu.Ft.(2)

Uncompacted

j. Drums- 0 Cu.Ft.(2) O Cu Ft. 0.'00E+00 0 Cu.Ft.(2)

. Boxes O Cu.Ft.(2) 404 Cu.Ft. 0.00E+00 400 Cu.Ft.(2' Brokered' O Cu.Ft. O Cu.Ft. 0.00E+00 0 Cu.Ft.

l esins

+

CWP5 930 Cu.Ft.(1) 1357 Cu.Ft.(3) 6.99E+01 700 Cu.Ft.(1) 3)

,RWCU 0 Cu.Ft.( 675 Cu.Ft. 0.00E+00 75 Cu.Ft.(I TOTALS 1959 Cu.Ft. 602 Cu.Ft.( ' 7.04E+01 1,200 Cu.Ft.

, Total volume of waste shipped during_the month: 1,959 Cu.Ft. 2)

Total volume of waste shipped year-to-date: 1,959 Cu.Ft.

Unused 1988 burial volume allocation at BarnweLL: 80,841 Cu'.Ft.

(1) Actual resin volume i' (2) Container burial volume

'C3) Estimated volume in separators (4) Does not include resins s

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. LIQUID RADWASTE

. ' JANUARY 1989

- TOTAL RIVER RELEASE FLOW RATE (GPM)- DATA' PLOTTED FOR THE PREVIOUS 12 MONTHS TOTAL RELEASE (CI)

' 40 - - 2 RATE (GPM1 HI 27.01 30 .

LOW' 17.78 20 . - 1 TOTAL RFLFAEF fCT1 HI. 0.04 LOW' 0.01 10 -

AVG. 0.02 o FLOWRATE ka kAR APR . AY N JUL US EP bT kOV - hC - AN g

FILTER.THROUGHPUTS STE GALLONS X 10 4 _ LOW 0.90E+08-AVG 0.12E+07

. FLOOR DRAIN 3 - HI 0.11E+07-LOW 0.70E+0'$

AVG 0.93E+0t3 j LAUNORY-HI O.13E+05 LOW 0.00E+00 I'

g , AVG 0.2SE+04 0 E'"

FEB- MAR APR MAY JUN JUL AUG SEP OCT NOV OEC JAN

" COST OF~ OPERATION' o,yRirrffooetin.3 THOUSA OF 00LLARS MSM HI 0.64E+05 90 - LOW 0.20E+05 80 _ AVG 0.37E+05 70 - FLOOR ORAIN 60 . HI 0.50E+05-LOW 0.21E+05 50 - AVG 0.34E+05*

40 .

LAUNORY 30 _ HI 0.37E+03 20 -

10 .

I FEB MAR APR MAY JUN JUL AUG SEP QCT NOV OEC VAN LOW 0.00E+00 AVG 0.46E+02 WASTE COLLECTOR SYSTEM LAUNDRY SYSTEM FLOOR ORAIN. SYSTEM

r- ___ .

Ppga 22

' REACTOR POWER - MWT .

UNITS 1, 2, AND 3 '

JANUARY 1989 MWT 3500 -

3000 -

2500 -

, UNIT 1: OUTAGE.

2000 -

I UNIT 2: OUTABE i g5oo . UNIT 3: OUTAGE I 1000 -

l 500 -

0 OI:mistry Section

%%%***h**&4&O%##45&&C&O45545444 DAYS

T:chnical Services . -

Browns Ferry Nuclear Plant REACTOR WATER CONDUCTIVITY UNITS 1, 2 ANO 3 JANUARY 1989 UMH0/CM CONDUCTIVITY 1.75 -

UNIT i 1.5 -

1.25 - COM)UCTIVITY UNIT 2 g ....___.-_... ........._ _......._---- --

0.75 U e -

CONDUCTIVITY UNIT 3 0.5 -

0.25 -

b \ EFECM RAME COLD SHUTDOWN o' ....

r.hemistry Section * * % * * * * **@@&O @ # # 4 4 # S & $ @ d M $ 4 $ @ 8 @ ACTION LE DAYS COLD SHUT 00NN Technical Services

-Browns Ferry Nuclear Plant REACTOR WATER CHL.0 RIDE UNITS 1, 2, AND 3 JANUARY 1989 PPB 5o.............. ___ .___ _________. ______.._____ .____________.

do -

UNIT i

CR.0 RIDE 30 -

UNIT 2 20 -

CHLORIDE UNIT 3 to -

' ~ EXPECTED RANGE

,ALL CONDITIONS Chemistry Section -

=%%%*%%h**R%&O%##4&444QQ4N545444 ~~~~

DAYS' Cchnical Services Browns Ferry Nuclear Plant

W 4

OPERATING STATISTICS i

A O @

= .

Prgs 23 I. .

t L OPERATING DATA REPORT DOCKET NO. 50-259 DATE 2-1-89 COMPLETED BY S. A. Ratliff

i TELEPHONE (205) 729-2937 OPERATING STATUS l Notes l

1. Unit Name: Browns Ferry Unit One l- l

2. Reporting Period: January 1989

'l l

3. Licensed Thermal Power (MWt): 3293 l [

4. Nuneplate Rating (Gross MWe): 1152 l l

5. Design Electrical Rating (Net MWe) 1065 l l

6. Maximum Dependable Capacity (Gross MWe)~ 1098.4 l l

7. Maximum Dependable Capacity (Not MWe) 1065 I l

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

i N/A' 9 .' Power Level To Which Restricted, If Any (Net MWe): N/A

10. Reasons For Restrictions, If Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 744 153.512

12. Number of Hours Reactor Was Critical 0 0 59.521.38

13. Reactor Reserve Shutdown Hours 0 0 6.997.44

14. Hours Generator On-Line 0 0 58.267.26

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0- 168.066.787

17. Gross. Electrical Energy Generated (MWH) 0 0 55.398.130-

18. Net Electrical Energy Generated (MWH) -4888 -4888 53.493.843

19. Unit Service Factor 0 0 38.0

20. Unit Availability Factor 0 0 38.0

21. Unit Capacity Factor (Using MDC Net) 0 0 32.7

22. Unit Capacity Factor,(Using DER Net) 0 0 32.7

23. Unit Forced Outage Rate 100 100 56.8 l 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):

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

}.

. INITIAL CRITICALITY

! INITIAL ELECTRICITY j COMMERCIAL OPERATION s (9/77) t . -

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Pzgs 24 .

OPERATING DATA REPORT .

DOCKET NO. 50-260 )

2-1-89 DATE.

COMPLETED BY S. A. Ratliff

)

j TELEPHONE' (205) 729-2937 i

OPERATING STATUS I l Notes l

1. Unit Name: Browns Ferrv Unit Two l l l

2. Reporting Period: Januarv 1989 l l ]

3. flicensed Thermal Power (HWt): 3293 l l

4. Nameplate Rating (Gross HWe): 1152 l l

5. Design Electrical Rating (Net HWe) 106E l l

6. . Maximum Dependable Capacity (Gross MWe) 1098.4 l l

7. Maximum Dependable Capacity (Net MWe) 1065 - 1 I

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 (Not HWe): .N/A .

10.' Reasons For Restrictions, If Any: N/A F

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 744 148.399.00 12.. Number of Hours Reactor Was Critical- 0 0 55.860.03

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 0 167 Gross Thermal Energy Generated (MWH) 0 0 153.245.167 172 Gross Electrical Energy Generated (HWH)

~

0 0 50.771.798

18. Net Electrical Energy Generated (MWH) -2238 -2238 49.049.494

19. Unit Service Factor , , 0 0 36.6

20. Unit Availability Factor 0 0 36.6

21. Unit Capacity Factor (Using MDC Net) 0 0 31.0

22. Unit Capacity Factor (Using DER Net) 0 0 31.0

23. Unit Forced Outage Rate 100 100 57.1

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

25. .If Shut Down At End Of Report Period Estimated Date of Startup Seotember 20. 1989

26. Units In Test Status (Prior to Connercial Operation): Forecast Achieved i

, INITIAL CRITICALITY INITIAL ELECTRICITY I

COMMERCIAL OPERATION (9/77) 0002R -

g. . . . .. . , , . ~ . . . . . . . .

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. 'P:gs 25 k

' OPERATING DATA REPORT DOCKET.NO. 50-296 ;

DATE 2-1-89 ]

S. A. Ratliff ;

COM'PLETED BY TELEPHONE (205) 729-2937 i

OPERATING STATUS- I

. l Notes l

1. Unit Name: Browns Ferry Unit Three l l-

2. Reporting Period: Januarv 1989 l l-

3. Licensed Thermal Power (MWt): 3293 l F1

4. Nameplate Rating (Gross MWe): 1152 l l<

5. Design Electrical Rating (Net MWe) 1065 l l'

' 6.~ Maximum Dependable Capacity (Gross MWe) 1098.4 l l

7. Maximum Dependable Capacity (Net MWe) 1065 l !

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

N/A -~

m

9. Power Level'To Which-Restricted, If Any (Net' MWa): 5- . N/A

10. Reasons For Restrictions, If Any: N/A '=.

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 744 130.824.00

12. Number of Hours Reactor Was Critical 0 0 45.306.08

13. Reactor Reserve Shutdown Hours 0 0 5.149.55

14. Hours Generator On-Line 0 0 44.194.76

15. Unit Reserve Shutdown Hours 0 0 0

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 (HWH) -1855 -1855 41.898.232

19. Unit Service Factor ._ ... ___ 0- , 0 33.8

20. Unit Availability Factor 0 0 33.8 .-.

21. Unit Capacity Factor (Using MDC Net) 0 0 30.1 -.

22. Unit Capacity Factor (Using DER Net) 0 0 30.1

23. Unit Forced 00tage Rate 100 100 61.3

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined

26. Units In To.L Status (Prior to Commercial Operation): Forecast Actieved INITIAL CRITICALITY l INITIAL ELECTRICITY !

COMMERCIAL OPERATION (9/77)

* ~

0002R l

l-

__Ak m . w s-m -e ~ n _ -x--r.. m e-,m ,-=-m. -m-m v n.m e,mes... ~ cn,.v:. m n- n n e-~. -

k Pzgs 26 .

AVERAGE DAILY UNIT POWER LEVEL .

l l- DOCKET NO. 50-259 L _ Unit One i

DATE 2-1-89 COMPLETED BY S. A Ratliff i-TELEPHONE (205)729-2937' l

MONTH JANUARY 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERA'l DAILY POWER LEVEL-(MWe-Net) (MWe-Net) 1 .17 -7 2 18 -7 3 -6 19 -7 4 -6 20 -7 4

5 -7' 21 -7 6 '7 22 -6 s

7_ -7 23 -6 8 -5 24 -7 _

~

9 -7 25 -7

,10 -5 26 -6 11 -6 . 27 -6

-12 -7 28 -6 13 -12 29 -7 14- -5 30 -5 15 -5 31 -6 16- -7 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) 0002R

)

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, .Pags 27 p , ;

l .: ,

AVERAGE DAILY UNIT POWER LEVEL V.

1 DOCKET NO. 50-260 )

Unit Two DATE: '

2-1-89 ;

COMPLETED'BY S. A. Ratliff TELEPHONE (2051729-2937 i MONTH JANUARY 1989 -

i DAY AVERAGE DAILY POWER LEVEL DAY. AVERAGE-DAILY POWER LEVEL

,(MWe-Net) (MWe-Net) j 1 -3 17 -3

.k 2 -3 18 -3 -

3 -3 19 -2 4 -4 20 -2 ~

t 5- -3 21 -2 -

6 -3 22 -2 '

7 -3 23' -2 8 -3 24 -2 '-

9 -4 '25 -3 i 10 -3 26 -3 l 11 -3 27 -4 -

12 -2 28 -1 13 -2 29 -6 14- -3 30 -3 I 15 -2 ,31 -4 i

-;! 16 -2 -

1 p

.i i' , INSTRUCTIONS '

I L 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.

4 (9/77) j- 0002R i . . .

1 cwa w: _- e - :..,-mr ~ ; :.r --_v- - v~:nn. -ew , u n,ws --nn- ci.: .vv.-- .~ v---, m - -mr e,. m m. , m ., ,s . ,. a

[- Pag 3.28 ,; j f.

- AVERAGE. DAILY UNIT POWER LEVEL , _ .

DOCKET NO. 50-296 s Unit Three DATE 2-1-89 COMPLETED BY S. A. Ratliff f TELEPHONE '(205)72912937

-MONTH JANUARY 1989-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY--POWER LEVEL (MWe-Net) (MWe-Net) 1 -2 17 -2

. 2- -2 18 -2 3 -3 19 -2 4 -4 20 -3 75 -5 21 -3 6' -2 22 7 23 -2 8 -1 24 -2

,,9 -3 25 - 2'

~10 -2 26 -2 11 -3 . 27 -3 12 -3 28 -2 13 -2 29 -3 14 -3 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) 0002R-

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TvA na A (DNP+8u Page 32 NUCLEAR PLANT OPERATING STAT.lSTICS ,

Browns Ferry Nuclear Plant 6

Period Hours 744 Month January 1989 It6m No, Unit No. UNIT l' UNIT 2 UNIT 3 PLANT 1 Averaae Hourly Gross Load, kW 0 0 0 0- I 2 Maximum Hour Net Generation, MWh 0 0 0 0 3 Core Thermal Enerav Gen. GWD (t)2 0 0' 0 0 4 Steam Gen. Thermal Energy Gen., GWD (t)2 NA NA NA NA j 5 Gross Electrical Gen., MWh 0 0 0 0

6 Station Use, MWh 4888 2238 1855 8981 -

e l 7 8

Net Electrical Gen., MWh Station Use, Percent

-4888 0

-2238 0

-1855 0

-8981 0

q i

9 Accum. Core Avy. Exposure, MWD / Ton 1 0 0 0 0 !

10 CTEG Th's Month 106 BTU 0 0 0 0 11 SGTEG This Month,106 BTU NA NA NA NA 12 ,

13 Hours Reactor Was Critical 0 0 0 0 14 Unit Use, Hours. Min. "0 0 0 0 )

15 Capacity Factor, Percent 0 0 0 0 I y 16 Turbine Avail. Factor, Percent 0 0 0 0 4 J7 Generator Avail. Factor. Percent 0 0 0 0 j 0 18 Turboaen. Avail. Factor. Percent 0 0 0 0 )

$ 19 Reactor Avail. Factor. Percent 0 0 0 0 0 20 Unit Avail. Factor. Percent 0 0 0 0 21 Turbine Startuos 0 0 0 0 22 Reactor Cold Startues 0 0 0 0 23 g 24 Gross Heat Rate, Btu /kWh 0 0 0 0

,$ 25 Net Heat Rate, Btu /kWh 0 0 0 0 5 26 U 27 g 28 Throttle Pressure, psig 0 0 0 0

& 29 Throttle Temperature, F 0 0 0 0 30 Exhaust Pressure, inHg Abs. 0 0 0 0

{ l g 31 Intake Water Temp., "F 0 0 0 0 I H 32 33 Main Feedwater, M lb/hr 0 0 0 0 j 34 c 35 36 37 ' Full Power Capacity, EFPD (3) (4) (4) (4) 38 Accum. Cycle Full Power Days, EFPD (3) (4) (4) (4) j 39 Oil Fired for Generation, Gallons 3627 2 40 Oil Heatina Value. Btu / Gal. 139000 41 D' ' Generation. MWh 4.2 d7 Max. Hour Net Gen. Max. Day Net Gen. Load MWh Time Date MWh Date Factor, %

3 43 0 0 0

$ Remarks: A For BFNP this value is MWD /STU and for SQNP and WBNP this value is MWD /MTU.-

~

E 2(t) indicates Thermal Enert)y.

$ 3 Information furnished by Reactor Analysis Group. Chattanooga

4 Administrative hold Date Submitted Date Revised

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a Pags .36 -

REACTOR POWER PERCENT JANUARY 1989 UNIT 1 PERCENT 100 -

90 -

80 -

70 -

80 :

ADMINISTRATIVE H0u0 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 100 -

90 -

80 -

70 -

60 -

50

', ADMINISTRATIVE HOLD 40 -

30 -

20 -

10 -

0 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 3 PERCENT 100 -

90 -

80 -

?0 -

60 -

50

ADMINISTRATIVE HOLD 40 -

I') -

20 -

10 -

0 1 2 3 4 5 6 7 8 4 10111213141516171819202122232425262728293031-

i b y e

9

. s MAINTENANCE SEMMARY

>s*ma,n

&W &

G G=

,' = .

- Page 37 7

t MAINTENANCE MONTHLY REPORT JANUARY 1988 ,

I. MAINTENANCE SUPPORT SECTION 4

A. Started plant recovery (painting program). Working Unit 1 & 2 Diesel Generator Building and Elevations 565 and 593 in Unit 2.

i i B. Continued weld preparations of Unit 2 drywell piping for Post

,' IHSI/ISI UT inspection.

I

! C. Completed re-insulation of piping on Unit 3 Shutdown Board Room Chillers.

D. Replaced insulation on HVAC piping and ductwork in SBGT Building.

i

E. Devoted a significant amount of manpower to building clean-up.

II. INSTRUMENT MAINTENANCE A. FLC installation / monitoring / removal B. SRM D/IRM F temp. a3teration to provide SRM.

C. 0ff line process rad monitors sis / associated MRs D. Sys. 3, Sys 6, Sys 24 PMs/ associated MRs III. , I & C TECHNICAL A. Fuel loading chambers B. Reviewed ECN/DCRs C. Assembled material for NRC audit D. Upgraded System 18 IV. ELECTRICAL TECHNICAL A. Fuse Control Program B. Closed one workplans C. Numerous technical reviews D. EQ valve program E. EQ program F. ITC's, ECN's, DCN's G. Relay work H. Numerous cognizant reviews I

I. PMT for relays J. Failure investigations

K. Measuring and Test Equipment Program L. Licensing Commitments 3

M. Circuit breaker maintenance N. Switchyard maintenance O. SPOC Support

< P. CAQRs j Q. Licensing commitments s

h

)

" # #* N Y# *

D' '

__ . _1 Y_ _ _ U EEI2 ____ ((f[_ __ [I __ )) I

0138M .

Page 38..

V. MECHANICAL MAINTENANCE

A. Changed out 18" EECW check valves 67-622 and 67-502

, B. Cut out and revelded 21 of 24 condenser water box manways ,

C. Repair CCW traveling screens

. D. Maintained U-1 & U-3 layup i

VI. ELECTRICAL MAINTENANCE EM report for month of January:

1. CAQRs/PRDs - Closed 4 ;

- New 2 '

- Total open 12

2. Worked MRs and PMs items to support fuel load and restart

3. Concentrated on performance / deferral of late PM items.

4. Requested artension requests for 4 CAQRs.

VII. MECHANICAL TECHNICAL SECTION Major work activities for the Mechanical Technical Section during the month of January 1988, involved closing numerous work activities, NRC commitments, CAQRs, ECN/DCN final closure packages, and various instructions which were approved, revised or cancelled.

VIII. v PRB~ralivE MAINTENANCE A. 19 Component folders have been developed in the PM upgrade program in the month of January.

B. 1126 Preventive Maintenance (PM) items were logged complete in the month of January.

IX. SPECIAL PROJECTS A. Turbine Crew performed PMs on U-1, U-2 & U-3.

B. RFP & RFPT and U-1, U-2 & U-3 main turbines.

C. Completed fuel load U-2.

X. PROGRAM SUPPORT A. Submitted the Maintenance Inspection Plan to Maintenance Superintendent for review and approval.

B. Finalizing the Maintenance Improvement Program document for review and approval.

1 I

t i

_Mi' '1 l OO_._._ E

'''i*Ul

. ili_2

W 6

4 4

1 OTHER -

REPORTS .

4 @*

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~

P2g2 397

?l s

, i ' L. ,

tt-3 CHEMISTRY

SUMMARY

sJ JANUARY 1989' Li Primary Coolant chemistry Unit 1-

~

The conductivity of the reactor coolant. remained within technica11 r

specification and fuel warranty limits during the month.- Chloride-

.-- concentration and pH of the reactor coolant remained,within technical'

j. specification and fuel warranty limits during the' month. This calendar year,

a. 0 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,-

i- .

i 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 a[ 1 j . specification and fuel warranty limits during the month. This calendar year,

[4p the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

T .

j: 0002R a

r ..

._m,.m._,. m.m.m._om,m,,.,.._...<,...,.,.. .m . ....,..yy_.m._.s .

_m u. e , , y. .c_._.___.c,m,. mz n.s. .~ .. . , .. .... , -

Page 40 PRIMARY COOLANT CHEMISTRY JANUARY 1989 Parameter Unit 1 Unit 2 Unit 3 i i

1. Gross Radioactivity

a. Crud (filter) (pei/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. Millipore Iron (Fe. cob)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A

3. Tritium (pci/mli High 3.96E-5 4.32E-5 1.23E-4 Low 3.19E-5 3.64E-5 1.14E-4 Average 3.66E-5 4.01E-5 1.'9E-4

4. Iodine-131 (pci/ml)

- High (1.01E-6 <5.63E-7 <8.20E-7 Low <6.33E-7 <4.56E-7 <6.83E-7 Average <7.34E-7 <4.90E-7 <7.57E-7

5. Iodine-131rIodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 0002R

g ..

h .* -

Paga 41 7

. PRIMARY' COOLANT CHEMISTRY.

R' f (Continued)

Jg JANUARY 1989

.. 1 1

I Parameter Unit 1 Unit 2 Unit 3 if' ~6. . Chloride (nob)

i . -

a.

4~ High,<10 <10 <10 <10 Low '<10 <10 ' <10 <10 j Average <10 <10 <10 -

e, ,

,s

3. 7. Sulfate (oob) a

?~ High <10. <10 <10 Low <10 (10 <10

j. Average <10 (10 <10

8. DH925'C High. 6.1 6.1 6.2' Low .5.8 5.6 5.7 Average' 6.0 5.8 6.0

,t.

9. Conductivity (umho/cm825'C)

High 0.38 0.99 0.41 3- Low 0.12 0.79 0.13.

Average 0.20 0.91 0.21 1

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1 5

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j 0002R l; ;

u . - ,.u a - , . . r u . .

,r.,,_ r. - - n u ..x . . .g. .- ,,. . . mn r s n .~r m-r > r- rr.:r_~.vt rc_~_c_13.~: = rmv~ w m en m

Paga 42

ENVIRONMENTAL TECHNICAL SPECIFICATION REQUIREMENTS JANUARY 1989 The ambient upstream river temperature (24-hour average) ranged from 50.4'F (January 8) to'46.7'F (January 22) with an average of 48.5'F. The downstream temperature varied between 50.4*F (January 8 and 9) to 46.5'F f

(January 22) with an average of 48.5'F. The largest temperature change was

', 0.7'F occuring on January 26. The monthly average change was 0.1*F.*

i j No chlorination took place during the month of January.

I .The sedimentation pond is still out of service. BFN did, however receive approval from the State of Alabama ~to' proceed with the necessary repairs in order to return.the pond to normal function..

A noncompliance was noted on January 17 in Discharge Serial Number (DSN 107). The TSS value of the sample was 116 ppm while the maximum permitted -

value is only 100 ppm. Subsequent sampling did not reveal a reoccurring problem. The maximum possible time of the noncompliance of DSN 107 was 3 days. Increased surveillance will hopefully prevent recurrance.

The sedimentation pond had a maximum flow of 140,000 gallons per day (gpd) with an average flow for the month of 70,610 gpd. The high rates are

' attributed to the winter drawoown in anticipation of a spring algal bloom.

The total suspended' solids remained fairly constant with a high of 27 ppm (January 10) and an average of 25 ppm. The Biochemical Oxygen Demand (BOD) for the month ranged from a high of 35 ppm (January 24) to a low of 9 ppm

! (January 10). The average BOD for January was 20 ppm.

6 l

l I i N

1

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'P ga 63 a

AIRBORNE RELEASES (1)

JAtlUARY 190'1 SUMMATION OF ALL RELEASES UNIT THIS MONTH A. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE CI < 1.05E 02

2. AVERAGC RELEASE RATE FOR PERIOD UCI/SEC '

4.3R C1

3. PERCENT OF TFCH. SPEC. LIMIT (0.15 CI/SEC) % 0.00E-01 B. IODINES

1. 'I U 'l A l . IDDINE 131 CI '

/ M. OS

2. AVERAGE RELEASE RATE FUR PERIOD UCI/SEC < 3.1CE-05

~

3. PERCENT OF TECH. CI'E C . LIPIT(2.17 UCI/SEC) % 0.00E .:1 C. PARr!CULorES

1. PARTICULATE WITH HALF-LIFES i DR = r0 0 DAYS C1 5.$2E-04

2. AVERAGE RELFASE Role FOR PERIO! UCI/GEC 2.2CF-04

3. I'ERCFNT OF I F C H .^ S P E C '. LIMIT (2.19 UCI/SEC) "

, 0.00E-01

4. GROSS ALPHA RAD [0 ACTIVITY CI 9.57E-07 D. TRITIUM

1. TOTAL RELEASE CI 1 0?E-02

2. AVERAGE RELEAGE RorE FOR PERIOD UCI/SEC 4.43E-03.

3. PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) % 2.02E-01 4 .- GROUND LEVEL RELEASE CI 1.05F-0?

5. ELEVATED RELEASE CI 2.16E-04 (1) REPORTING PERT 00 20 DAYS

Page 44 .

AIRBORNE RELEASES (CONTINUED) -

JANUARY 1989 ELEVATED RELEAtlEG A. FISSION GASES UNIT THIS n0NTil KR-8bM CI '

3.47E-02 ,

1 I

KR -85 CI '

3 48E C1 '

KR-87 CI I 2.??E-0.1 KR-88 CI < 3 11E-01 XE 133 CI ; 1 50E-01 XE-135M C1 2 . 3 5 t. - 01 XE .135 CI 9.30E-02 XE -130 C1 6.3 Mi ">1 DTHERS(SPECIFY)

TOTAL FOR Pl.RIOD CI '

3.66E 01 P. IUDINEC I-131 CI 4.57E-C6 I-133 CI ; 2.3r.E-05 I-130 CI '

4.60E-02 T 0 l' A L FOR PERIOD CI s 4.6CE-02

9 9 J

g -.

P:ga 45 AIRBORNE RELEASES (CONTINUED)

JANUARY 1 *P 8 9 ELEVAIED RELEASES C. PARTICULATE UNIT THIS MONTH SR-89 CI r; 1.99E-07 i

SR-90 CI < 7.7BE-03 CS-134 CI ' 4.74E-06 CS 137 CI < 5.65E-06 BA-140 CI < 1.04E-05

'. A - 14 0 CI - l'. 1 5 E - 0 5 DTHERS(SPECIFY) ,

4 TOTAL FOR PERIOD

._ - - - _.- - -._ - _.- - - - CI 3.2CE-05 D. I R I f II.lM CI 2.16E-04 4 ep a-

{ _ - - . . . . - _----- . .. , , .. .-. ,-

P:ga 46 .

AIRBORNE RFLEASES (CONTINUED) 4-

JANUARY 1909

-GRUUNO REl,EASEG JA, FISSION GASES UNIT THIS MONTH-

. . . . . . . . ~ . . . . . . . _ _ . _ _ _ . . . _ _ _ . _ . . _ , _

K R-- 8 S M CI ( 2 60E--01 KR-85 CI < 6.33E 01 K R - 8'I -

CI C 6.30E 01 KR-88 CI < 6.66E-01' XE-133 CI < 6.58E X C - 1 3 5ti CI s 5.13E C' XE-135 CI '

, 1 , 8 0 E -<'.)1 XE 138 CI 1 76E OC O T H Fil:S ( S P E C I F Y ) .

TOTAL. FOR PERIOD CI '

, 6.79E 01' B. 10DINEC I-131 C1 7.22E-03 1-133 CI . 4.00E 04 I-135 CI < 5.66E-01 TOTAL FOR PERIOD CI t 5.66E-01 1

I

. . . ,c. . . . . ._,,.m.,.m,.. . , . . . . . _ . . . . . _, , . , , . , . _ _ . .

. _ __, _o

e 1 '

Pcg2 47

-... , AIRBORNE RELEASES-'(CONTINUED)

~'

JANUARY 1789 i

GROUND RELEASES

, C.. PARTICULATE UNIT THIS MONTH

, SR-89 CI ( 1.39E-06 t;

r SR-90 CI <, 5.32E-07 CS-134 'CI i 1.'30E-04 J

)

CS-137 CI < 9.29E-05 i

.BA-140 CI < 2 07E-04 LA 140 CI < 3 .' 01 ~. . 0 5 OT-HERS(SPECIFY)

T 0 rot. FOR Pt.kIOD CI : 5.20E-04 D. TRITIUN CI 1. 0 5 E - O 'J

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Pqgs 481-

'RDWNS FERRY NUCLEAR PLANT- '4 ,' -

6JNrilLY REPORT-CALCULATIONS.

LIQUID RELEASES' JANUARY 1789 o.

RADIOACTIVE LIQUID E.FFLUENTS

1. GROSS RAD 10 ACTIVITY UNITS a) 10TAL. RELEASE' CURIES 1.98E-02'.

b)' AVERADE DILUTED CONCENTRATION RELEASED UCI/ML' 1'.49E-09' e . .

c)' PERCENT OF APPLICABLE LIMIT'( 1E-7 LICI/ML . )

% 1 .'4 9 E '0 0 .

g G ,

6 - s

.2.- IRITIUM.

a) ' TOTAL RELEASE CURIES 9.76E-02 t..

b) AVERAGE 11II.,U. RED CONCEN TRA TION RELEASED UCI/HL 7.36EH09-

.c) PERCENT.'0F APPLICABLE LIMIT (3E-03 UCI/ML) '% 2 45E -

(1)

~ 3 .1 DISSOLVED NOBLE GASES

t. _...................:.....--

a) 10TAL RELEASE. CURIES < 1.07E-03 b) AVERAGE'. DILUTED CONCENTRATION RELEASED UCI/ML < 8.08E-11

i. c) PERCENT OF'APPLICAfsl.E LIMIT (2E-04'UCI/ML) % t:4'.04E-05 1

j. - 4. GROSS ALPHA RADI0 ACTIVITY l 's) ' TOTAL RELEASE CURIES 1.94E-05

h. b) AVERAGE DILUTFD CONCENTRATION RELEASED UCI/ML 1.46E-12 p

l' i-

' 5.

VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 3.96E 06 l :_.....__..........__..__....._...___

r b

{ ;. '6 . V O L.tlM E O F-. D I L U T I O N

W A T f R LITERS 1.-33E 10 L . . . . . _ . . . . . . . . . _ . _ _ . .

3s

i. .

(

,1): INCLUDES XE-133r XE-13b, AND OTHERS L

L . - . .

.c. ,

Paga 49 BROWNS. FERRY HUCLEAR PLANT

, MONTHLY REPORT CALCULATIONS LIQUID RELEASES JANUARY 1989 ISOTOPES RELEASED UNITS CI CR-51 < 2.50E-03 MN-DA 2.11E-05 CO-58 < 2.91E-04 FE-59 < 6.40E-04 CD-60 4.10E-03 ZN-65 4.61E-04 NB-95 r; 2.76E-0A ZR-9S < 4.64E-04 MorC-99M -

< 2.18E-04 I-131 < 3.29E-04

. XE-133 < 8.90E-04 CS-134 2 21E-03 XE-135 < 1.82E-04 CS-137 1.29E-02 DA-140 < 1.20E-03 LA-140 < 2 14E-04 CE-141 < 3.71E-04 SR-89 < 1 06E-04 SR-90 < 5.54E-05 i

_ -- - - - - - - ._-~.-__-__a

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-- BROWNS' FERRY.: NUCLEAR' PLANT. .

W

, MONTHLY. REPORT CALCULATIONS- 's

-LIGUID RELEASES'.

EJAN.UARY!.: 1989:.

.n i ;, .'

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h ;.'

OTHERSi 1 UNITS-.

CI p.- ,

L _

SBi125; -6 04E '

.. . FE-S5- : <- 1.01E-03..-

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$4, '

-, BROWNS. FERRY. NUCLEAR PLANT-j

't<' i MONTHLY REPORT' CALCULATIONS-h' . LIQUID. RELEASES' k' '

JANUARY 1989

},

f I

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N

[:ji :L'AUNORY DRAIN VOLUME' RELEASED . O'.0 GALLONS LTp . FLOUR. DRAIN:VOLUMETRELEASED: .. .971982.9 -GALLONS.

1<< WASTE SANPLE FANK VOLUME RELEASED: 72942.'2. GALLONS-

! " .. DISTILLATE. TANK' VOLUME RELEASED: '0 0 GALLONS I'

LOCATION! 0 rHER THAN RADWAS TE VOLUME RELEASED:

.0.0 GALLONS' N7 ..

j. . TOTAL VOLUNE RELEASED 10 THE RIVER: 1044925.2 .. ' GALLONS 1 . ._ ..

.HIGHESTgBAFCH ACTIVITY' RELEASED FOR HUNTH: 2.07E-09 UCI/ML A/D' Q-f'q- " L O N G E.ST RELEASE- TIME: FOR MONTH:

SHORTESr: RELEASE ~ TIME'FOR MONTH:

335 MINUTES 130 MINUTES-l ., T01AL TIME-0F-RELEASES.FOR MONTH: .8759- MINUTES

', AVERADE TIME'FOR LBAICH RELEASES: ~237 MINUTES

).

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: 1 ff" " NUMBER' 0F BATCHES REL EASED: 37 L *;

.NUMBERLOF' ADMINISTRATIVE LIMIT VIOLATIONS: 0 ij :- . NUMBER'0F21ECHNICAL SPECIFICATION VIOLATIONS: 0

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< j Paga 52 -

l RESIN USAGE REPORT JANUARY 1989 RESIN CONSUMED (CU.FT.)' i

% of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total i

Radwaste .j Floor Drain Filter 23.5 0 114 0 0 0 114

, . Waste Demineralized 25.8 125 0 0 0 0 125 Waste Filter 39.2 0- 190 0 0 0 190 j:

Fuel Pool Demins 1.6 0 8 0 0 0. 8 q Reactor Water Cleanuo Unit 1 0.4 "O 2 0 "O O 2 Unit 2 5.0 0 24 0 0 0 24 Unit 3 0.4 0 2 0 0 0 2:

Cond. Demins.

Unit 1 0 0 0 0 0 0 0 Unit 2 4.1- 'O -- 2 0 'O O O 20 Unit'3. 0 0 0 0 0 0 .0 Totals 100 125 360 0 0 0 485

, i.

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L' !% 'Yv & !* 'T i* =t W M f'"'s ^"-

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Paga 53

~ '

f FUEL CLADDING INTEGRITY PARAMETERS j i ;

JANUARY 1989 1 ij

' Unit 1 Reactor Water Iodines (pci/sec.)

Date I-131 I-132 I-133 I-134 I-135-1 Unit.in Outage J

Fission Gases at Discharme of SJAE (pci/sec)

Date Flow MWt Ke-138 Kr-87 Kr-88 Kr-85m Ke-135 Xe-133 i Unit in Outage

i. Unit 2 Reactor Water Iodines (pci/sec.)

i Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Cases at Discharte of SJAE (pci/sec)

Date Flow MWt Ke-138 Kr Kr-88 Kr-85m- Xe-135 Ke-133 Unit in Outage _

Unit 3 Reactor Water Iodines (pel/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (pci/sec)

Date Flow MWt Ke-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage 4

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. 6 TESTING

SUMMARY

JANUARYs1989

. Surveillance Testina Unit 0 A total of 133 surveillance tests were completed using 40 different-test in'structions.

Unit i

1. A total of 71 surveillance tests were completed on unit 1 using 20 different test j? - instructions.

i'

- Unit 2-A total'of 257 surveillance tests were completed on unit 2 using 82 different test instructions.

Unit 3 .

A total of 116 surveillance tests were completed on unit 3 using 21 different test instructions.

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lb'- ' 1 *.._f_.__** AN 'J' .?.L _.M?.'_'. '*_'-f_f"2.___ ' *' ' *_ 'J. MCI " _*mH ? _ Y,_T_*1.' I_ 'f_7 ?'2_*_._ C.'_ E I_

D _S.'_ Ql _f5I.'EN.* I '_'r ^ d Tf_3_'

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e Paga 56-

TESTING

SUMMARY

(CONTINUED)

JANUARY-1989 Channes. Tests. and Erneriments Reauirina Authorization From the NRC Pursuant -

1 to 10 CFR 50.59(a)

There were:three revisions for units 1, 2, and 3 technical. specifications.

.)

i

)

Channes. Tests. and Experiments not Reauirina Authorization from NRC Pursuant to 10 CFR 50.59(a)

There were no special tests completed for this month.

4 h

0002R 1 3 4- D' t*_/*_e "' 4 @

4 .i_ i u _ a f L = a a F /* 1 't d. 2.N .'k / C #. - 1. L. 26 & wm2_' E ?.. *%f -.%.4 SS E f JP.Jh% _ trA . law _M_%J f'mh :lO'_ L1 ' _J _' _: Jai

dh.f_L _* Lh .

. :Paga 57 u s-

.g, J

I REACTOR VESSEL FATIGUE USAGE EVALUATION

'$ JANUARY 1989 a.i 4

The cumulative usage factors for the reactor vessel are-as follows:

,2 h'

Usaae Factor Location Unit 1 ~ Unit 2 Unit'3

-l

'9 Shell at water line 0.00620 0.00492 0.00431 j Feedwater nozzle 0.29782 0.21319 'O.16139 Closure studs 0.24204 0.17629 0.14360

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L Pags 58-

V e N'

CHANGES IN PROCEDURES-JANUARY 1989

?

_There-vere 362 revisions.to plant instructions during the month; 359

! instructions were changed primarily for' correction;.and three revisions related to safe operation of the plant.

- PLANT INSTRUCTION REVISIONS DECEMBER 1988 Catenory Instruction Reason for Reauest Change in response SDSP-13.1 Welding and To incorporate NRC to LER, IE Bulletin, Applications commitment NCO 860326174 NRC Inspection Report, into procedure.

OPQA Audits, etc.-

2-SI-4.2.A.10 Reactor To cancel instruction Building and Refueling and replace with Floor Ventilation 2-SI-4.2.A.9(A),

Radiation Monitor 2-SI-4.2.A.9(B),

Calibration and Functional 2-SI-4.2.A.10(A), and

. Test 2-SI-4.2.A.10(B).

i 0-SI-4.7.E.4.B Control To incorporate ITC-02 Room Emergency Ventilation which implemented the System - Iodine Removal intent of NRC inspection Efficiency report 88-05 by replacing l C00 requirements with

, added ASTM 03803-79 test conditions. Also, added urgent justification to t' . example purchase request

{ form.

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-* Pcgs 59 1

.- i L.. .

- - J L.-

1 i

l CHANGES IN PLANT ORGANIZATION -

~1

)

JANUART 1989 1 1

There were no changes in plant staff for those positions' designated as key-supervisory positions for the month.

9 4

e 0002R en an e * *M . +% NJ M 1 0 % ao ?b / *i'i

_.1 *%*' 5 ._ n ' . _ 1 I _ ' _7_'_1. ?! U f _'l _'. _'1Il_' #' ""*^3 * ' ' ' * '# * "

e Paga 60 .

e

= .

l ACCIDENTS JANUARY 1989 There was one loss-of-time accidents during the month.

t e

0002R 4 *g - a m e g g w g a. W Tr p -t y v 3 m47 y Ony mag *p- isfeq- es p+ g put r- gut a %4 m,-m ,.g4 7, , , ej.

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&+'

' TENNESSEE VALLEY. AUTHORITY l Browns Ferry Nuclear Plant Post Office Box 2000' <

Decatur, Alabama- 35609-2000'

. MAR . 021989 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk-Office of Nuclear Reactor Regulation

' Washington, D.C. 20555 Attention: Office of Management Information and Program Control In the Matter of the ) Docket'Nos. 50-259 Tennessee Valley Authority ) 50-260' 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - JANUARY 1989

' Enclosed is the January 1989 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY

$ t MM $

. hGuyG. Campbell.

JPlant Manager Enclosure cc: INPO Records Center Mr. B. D. Liaw, Director Institute of Nuclear Power Operations TVA Projects Division Suite 1500 One White Flint, North 1100 Circle 75 Parkway 11555 Rockville Pike Atlanta, Georgia 30389 Rockville, Maryland 20852 Regional Administration NRC Resident Inspector U.S. Nuclear Regulatory Commission' Browns Ferry Nuclear Plant

.0ffice of Inspection and Enforcement Route 12, Box 637 Region II Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Ted Marston, Director Electric Power Research Institute P.'O. Box 10412 r Palo Alto, California 94304 pjh2E' I

\

An Equal Opportunity Employer

.

ML20235Z147

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