ML20247F254

Monthly Operating Repts for Feb 1989 for Browns Ferry Nuclear Plant,Units 1,2 & 3

ML20247F254
Person / Time
Site:	Browns Ferry
Issue date:	02/28/1989
From:	Campbell G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8904030380
Download: ML20247F254 (69)

Text

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MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY FEBRUARY 1989

" Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260 AND 50-298 LICENSE NUMBERS DPR-33, DPR-52. AND DPR-68 f

Submitted by:

Guy G. Campbell 8904030380 890228 ADOCK0500g9 DR t

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' TABLE OF CONTENTS Y

PART I ' OPERATIONAL

SUMMARY

A.

Significant Operational Events Summary...........................

1 B

Refusling Information............................................

2 C.

Main Steam Relief Valve (MSRVs) Actuation Summary................

7

)

l D.

Issuanc e o f Spe cial 2epo rts Summary.............................. 8 E.

Licensee Event Reports Summary........................

.......... 9 F.

Of fsite Dose Calculation Manual Changec......................... 11 1

G.

Radwaste Summary................................................

12 1.

Total volume of solid waste shipped offsite 2.

Nature of the waste (trash, resins, etc.)

3.

Gross curie activity' 4.

Dates the material was shipped and the disposal facility to which the material was shipped.

3.

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.......................................

17 2.

Average Daily Power Leve1...................................

20 3.

Unit Shutdowns and Power Reductions.........................

23 l

B.

TVA Reports 1.

Plant Operating Statistics..................................

26 2.

Unit Outage and Availability Data........................... 27 3.

Reactor Histogram (Reactor Power Percent)...................

30

}

i TABLE OF CONTENTS,

(Continued)

Part III MAINTENANCE

SUMMARY

31 i

PART IV OTHER REPORTS 1

A.

Chemistry Summary 1.

Primary Coolant Chemistry.................................. 33 j

2.

Environmental Technical Specification Requirements,......... 36 3.

Airborne Releases.........................

4................ 37 i

4.

Liquid Releases.............................................

42 5.

Resin Usage Report.......................................... 46 6.

Fuel Cladding Integrity Parameters.......................... 47 7.

Waste Treatment System Throughputs...............

.......... 48 B.

Testing Summary..................................................

49 C.

Reactor Vessel Fatigue Usage Evaluation..........................

51 D.

Change in Procedures.....................................,

....... 52 E.

Plant Ins t ruc t i on R evi s i ons...................................... 5 2 F.

Change in Plant Organization.....................................

53 G.

Accidents........................................................

54 1

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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 Wasta DBA Design Basis' Accident l

DSVP 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 EQDP Environmental Qualification Documentation Package EQE Earthquake Engineering EQP Environmental Qualification Project

i ACRONYMS /A@BREVIATIGNS (Continued)

ER Engineering Report

, ERCW Essential Raw Cooling Water ESF Engineered Safety Feature FCR Field. Change Request FMEA Failure Modes and Effects-Analysis FSAR Final Safety Analysis Report FW Feedwater GE General Electric GET General Employee Training GPM GalJons per minute GOI General Operating Instruction HPCI High Pressure Coolant Injection HVAC Heating Ventilation and Air 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 Isolation 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 NPS Nuclear Procedures Staff NQA Nuclear Quality Assurance NQAM Nuclear Quality Assurance Manual NRC Nuclear Regulatory Commission NSS Nuclear Se urity Service NT Nuclear Trrining NUMARC Nuclear Ut'.lity Management and Resources Countil NUREG Nuclear Raiulatory Documentary OI Operating Instruction OL Operating Licensee ONP Office of Nuclear Power i

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ACRON?MS/ 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 Isolation Cooling REP Radiological Emergency Plan RETS Radiological Effluent Technical Specification RHR Residual Heat Removal RHRGW 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 Manually SDIV Scram Discharge Instrumentation Volume SDSP Site Director Standard Practice S/G(s)

Steam Generators SI Surveillance Instruction SIL Service Information Letter SMMI Special Mechanical Maintenance Instruction SOS

' Shift Operations Supervisor SPDS Safety Parameter Display System SPOC System Preoperability Checklist SQN 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 TS Technical Specification TSS Total Suspended Solids j

TVA Tennessee Valley Authority UO Unit Operator USA United States of America USQD Unrevicwed Safety Question Determination VMCP Vendor Manual Control Program WBN Watts Bar Nuclear Plant WP Workplan

i 5

OPERATIONAL SCMMARY

I Pags.1 A

SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

FEBRUARY 1989 U. nit._1 02/01/89 0001 Unit remains on administrative hold to reso,1ve various TVA and NRC concerns.

02/28/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Unit 2 02/01/89 0001 Unic remains cn administrative hold to resolve various l

TVA and NRC concerns.

Cycle 5 refueling and modifications continue.

02/28/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

IIDiLl 02/01/89 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

02/28/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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i Page 2 REFUELING INFORMATION FEBRUARY 1989 Unit 1 3

I 1.

Name of facility j

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 opersting 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 3,471 i

r, l

a Page 3 REFUELING INFORMATION Unit 1 (Continued) 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 discharge from one unit following the BF2 cycle 15 refueling in September 2006.

(BF1 would be in cycle 13.)

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Page 4 REFUELING INFORMATION FEBRUARY 1989 Unit 2 1.

Name of facility Browns Ferry Nuclear Plant 2.

Schedule.d 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?

Changes to the Technical Specification as a result of the BFN 2, cycle 6 final core design have been submitted along with the BFN Reload Licensing Report for unit 2, cycle 6 (TVA RLR-002) Revision 2.

This report documents i

the Technical Specification core thermal limits for the specific unit 2, cycle 6 core design.

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 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 assemblies described in WCAP-10507 dated March 1984, " Quad + Demonstration Assembly Report," Westinghouse Electric Corporation. The remaining 760 fuel assemblies are General Electric design which are descrioed in NEDE-24011-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 seorage pool (a) 764 (b) 1,444 l

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REFUELING INFORMATION Unit 2 l

(Continued) q 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 3,471-9.

-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 discharge from one unit following the BF2 cycle 15 refueling in September 2006.

(BF1 would be in cycle 13.)

c 1

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REFUELING INFORMATION FEBRUARY 1989 Unit 3 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?

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 required (MCPR), the appropriate submittal will be made.

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 No changes in the fuel assemblies are planned for unit 3 return to operation 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 l

(a) 0 (b) 1,768 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 3,471 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 l

discharge following the cycle 13 refueling in May 2006.

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Pags 7 MAIN STEAM RELIEF VALVE (MSRVs)

SUMMARY

FEBRUARY 1989 No MSRVs were challenged during the month.

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Page 8 ISSUANCE OF SPECIAL REPORTS FEBRUARY 1989 The following special reports are notices of violations issued for the month of February 1989.

88-32-01 (1) On October 16, 1988, the licensee failed to properly perform, and to independently verify, the tagging of equipment specified on a clearance sheet, in that "A" air start compressor for Units 1 and 2 diesel generator "C" was tagged instead of the compressor for the "B" diesel generator as specified on the clearance. This was identified through the receipt of an annunciator alarm and resulted in all eight diesel generators being technically inoperable.

(2) On October 17, 1989, Steps 7.6.111.1 thru 7.6.111.4 of 2-SI-4.2.A-10.

Reactor Building and Refueling Floor Ventilation Radiation Monitor Calibration and Functional Test, were not performed prior to performing Step 7.6.111.6.

This resulted in an inadvertent. Engineered Safeguards Features actuation.

This is a Severity Level IV Violation and is applicable to Units 1 and 2.

88-33-05 On June 20, 1986 an NRC inspector identified that a stationary electric hoist used to place fuel channels over new fuel assemblies

'had not been load tested as required by GOI-100-2, New Fuel Operations, which included required inspections of stationary electric hoists. The licensee took immediate corrective action to load test the hoist, and to correct the problems identified in the TVA audit. As a result of OSP management review, this issue meets the discretionary enforcement criteria of 10 CFR Part 2, Appendix C.,Section V.G.I.

A notice of violation will not be issued because the problems were primarily licensee identified and the corrective action has been satisfactorily completed. This item will be documented as Licensee Identified Violation (LIV) 259, 260, 296/88-33-05, Failure to Follow Procedure GOI-100-2.

No further review is necessary.

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Paga 9 LICENSEE EVENT REPORT (s)

FEBRUARY 1989 Res_criotion of Event e

LEE 1-88-032 ELECTRICAL SEPARATION REQUIREMENTS VIOLATED DUE TO INADEOUATE Rev. 01 DESIGN CONTROLS On October 8, 1986, while implementing a design change to upgrade primary containment electrical penetrations, discrepancies were discovered in electrical cable classifications and cable routings indicating possible violation of the electrical divisional separation requirements. Subsequent reviews and evaluations identified approximately 950 discrepancies in either classification or actual physical separation of cables. Of these discrepancies approximately 230 require physical modifications or further evaluation prior to unit 2 startup. All three units were affected but were shutdown at the time of discovery.

2-88-006 480 VOLT SHUTDOWN BOARD VOLTAGE TRANSIENT INITIATES ENGINEERED Rev. 02 SAFEGUARD FEATURES On August 24, 1988, and again on September 23, 1988, the 2C2 reactor protection system (RPS) circuit protector tripped, deenergizing the 2A and 2B RPS buses respectively. The result of each of these power losses was the initiation of standby gas treatment, control room emergency ventilation, refueling zone isolation, unit 2 reactor zone isolation, partial unit 2 primary containment isolation and a unit 2 half scram. The residual heat removal (RHR) system isolated during the first event, but was already isolated at the time of the second event. The traversing incore probe and reactor water cleanup systems were removed from service and isolated at the time of both events. The 2C2 RPS circuit protector was reset, isolations reset, and affected systems returned to normal following both events. Engineered safety featurcs performed as designed. The RPS and Unit Preferred Distribution System were being fed from the same unit preferred transformer.

1-89-001 DESIGN OVERSIGHT ON SEISMIC QUALIFICATION OF 4160 VOLT AND 480 VOLT BREAKERS PLACES PLANT IN UNANALYZED CONDITION I

On January 18, 1989, it was determined that seismic documentation could not be established for various positions of the 4160 volt and 480 voit safety related circuit breakers. This determination resulted in the plant being in an unanalyzed condition.

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(Continued) 1-89-001 On December 9, 1988, it was discovered that there was no (Cont.)

documentation immediately available on the seismic qualification of the 4160 volt and 480 volt safety related circuit breakers when in test, disconnect, or withdrawn position. The fully connected position had the required documentation. The condition-is applicable to General Electric 4160 volt horizontal drawout metal clad switchgear, model MC-4.76, General Electric 4160 volt vertical, lift metal clad switchgear, type M-62, General Electric 480 volt type AK circuit breakers, and ITE model K600S 480 volt circuit breakers. All three units were defueled when the condition was discovered.

2-88-050 OPERATIONS OVER SPENT FUEL POOL WITHOUT MINIMUM NUMBER OF STANDBY GAS TREA* MENT TRAINS OPERABLE December 27, 1983 with units 1, 2 and 3 defueled, it was discovered that neutron source movement was performed without the minimum required trains of stand-by gas treatment system (SBGT).

On December 14, 1988, at 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> neutron source movement, between unit 2 and 3 spent fuel pools, was performed without the minimum SBGT trains technically operable per plant technical specification (TS) 3.7.B.1.b.

During the event all three trains of SBGT were functional and running but trains B and C vere operating outside TS.

Diesel generator (DG) D had been removed from service for scheduled maintenance checks on the generator and its associated shutdown board. Diesel generator D is the normal onsite emergency power supply for SBGT train B.

In addition, Surveillance Instruction (SI) 4.2.A-12 " Standby Gas j

Treatment Blower and Heater Logic Functional" on SBGT train C had exceeded its surveillance frequency thereby technically making train C of SBGT inoperable.

2-89-002 AUTOMATIC DEPRESSURIZATION SYSTEM ACCUMULATOR PRESSURE SWITCH SUPPORTS NOT SEISMICALLY OUALIFIED On January 20, 1989, it was determined by utility plant and design engineers that the existing support design for the unit 2 Automatic Depressurization System (ADS) air accumulator pressure switches was not seismically qualified. These switches provide an alarm function on low accumulator pressure.

During a seismic event, failure of these supports could lead to failure of the drywell control air system pressure boundary. Unit 2 was shutdown with the reactor vessel head removed when this condition was discovered.

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Page 11 OFFSITE DOSE CALCULATION MANUAL CHANGES FEBRUARY 1989 No changes were made to the BFN Offrite Dose Calculation Manual during the month.

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RADWASTE

SUMMARY

FEBRUARY 1989 The radwaste system performed as designed. Approximately 8.64E+05 gallons of waste liquid were discharged containing approximately 1.71E-02 curies of activity.

There were six spent resin shipments and no trash shipment during February.

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 January.

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s Page 13 Solid Radioactive Waste February 1989 (1)

Dewatered Spent Resin Shipments Volume of condensate / waste CCWPS) resin shipped:

31.62 Cu.M.

(1116.00 Cu.Ft.)

Total curies shipped:

53.2497 Volume of reactor cleanup (RWCU) resin shipped:

O Cu.M.

(

0 Cu.Ft.)

Total curies shipped:

0 Date Shioped Disoosel Facility Tvoe of Resin 01/31/89 Barnwell, SC CWP5 02/03/89 Barnwell, SC CWP5 02/07/89 Barnwell, SC CWP5 02/15/89 Barnwell, SC CWP5 02/21/89 Barnwell, SC CWP5 02/24/89 Barnwell, SC CWP5 (1)

Dry Active Waste

. Number of drums shipped:

0 Volume:

0 Cu.M. (

0 Cu.Ft.)

Total curies shipped:

0 Number of boxes shipped:

0 Volume:

O Cu.M. (

0 Cu.Ft.)

Total curies shipped:

0 1

Date Shioped Disposal Facility Tvoe of Package N/A N/A N/A Brokered shipments (SEG):

0 Volume:

0 Cu.M.

(

0 Cu.Ft.)

Total curies shipped:

0 Date Shipped Disoosal Facility Tvoe of Packaae N/A N/A N/A (1) All shipments were by Sole-Use Vehicle l

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Page 14*

1 Solid Radioactive Waste (Continued)

February 1989 Summary Type Shipped to Packaged on Gross Curie Estimated i

of Barnwell Site Awaiting Content by Generation for Waste During Month Shipment Type of Waste Next Month Compacted Drums O

Cu.Ft.C2) 248 Cu.Ft.

0.00E+00 375 Cu.Ft.C2)

(2)

(2)

Boxes O

Cu.Ft.

279 Cu.Ft.

0.00E+00 279 Cu.Ft.

Uncompacted Drums O

Cu.Ft.(2) 203 Cu.Ft.

0.00E+00 600 Cu.Ft.(2)

(2)

(2)

Boxes O

Cu.Ft.

404 Cu.Ft.

0.00E+00 0

Cu.Ft.

Brokered 0

Cu.Ft.

O Cu.Ft.

0.00E+00 0 Cu.Ft.

Resins CWP5 1116 Cu.Ft.C1) 500 Cu.Ft.(3) 5.32E+01 500 Cu.Ft.(1)

(1)

(3)

(1)

RWCU 0

C4.Ft.

150 Cu.Ft.

0.00E+00 5 Cu.Ft.

(2)

(4)

(4)

TOTALS 1235 Cu.Ft.

730 Cu.Ft.

5.32E+01 1,254 Cu.Ft.

(2)

Total volume of waste shipped during the month:

1,235 Cu.Ft.

Total volume of waste shipped year-to-date:

3,194 Cu.Ft.

Unused 1989 burial volume allocation at Barnwell:

79,606 Cu.Ft.

(1)

Actual resin volume (2)

Container burial volume (3)

Estimated volume in separators (4)

Does not include resins 3

4 3

LIQUID RADWASTE Page u FEBRUARY 1989 TOTAL RIVER RELEASE FLOW RATE (GPM)

DATA PLOTTED FOR THE PREVIOUS 12 MONTHS TOTAL RELEASE (CI) 40 -

_ 2 FLOW AATEfGPM)

HI 27.81 LOW 20.72 30 -

AVG 23.68 3

TOTAL RFLF AEF foT)

^

v HI O.04 gg ~

LOW 0.01 AVG 0.02 O FLOWRATE 10 "2

T 2

r O D RELEASE (CI)

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a FAR APR MAY JUN JUL AUG SEP OtT AbV GEC-JAN fkB THAouGHpuT fGAL El FILTER THROUGHPUTS WASTE 6

GALLONS X 10 HI O,15E+07 4 _

LOW 0.90E+06-AVG 0.12E+07 FLOOR DRAIN 3 -

HI' O.11E+07 LOW 0.70E+06 E I..)

AVG 0.93E+06 E E,.

,N LAUNORY N

HI 0.13E+05

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LOW 0.00E+00

'pi; g;,,c h'k. ? C j h.!

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pq n MAR. APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB COST OF OPERATION o,EniTroufno5,insi-THOUSANDS OF DOLLARS 10CL WASTE HI 0.64E+05 90 -

LOW 0.20E+05 AVG 0.38E+05 80 _

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FLOOR DRAIN 0.50E+05 60 _

LOW 0.21E+05 j,,

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Paga 16 REACTOR POWER - MWT UNITS 1, 2

AND 3 FEBRUARY 1989 MWT 3500{

3000 2500 UNIT 1: OUTAGE 2000 UNIT 2: GUTME 1500 UNIT 3: OUTAGE 1000 500 0

0N S*

• • • • **@@&@@@@@@@@@@@$$$4$

Chimistry Section DAYS Technical Services Browns Ferry Nuclear Plant REACTOR WA TER CONDUCTIVITY UNITS 1, 2

AND 3 FEBRUARY 1989 UMHD/CM CONDUCTIVITY 1.75 UNIT i 1,5 c' ";TI7IT /.

1.25 1:IT g..._______y,_-

=,,____

....___c

__..q,________p,_

0.75

's CONDUCTIVITY UNIT 3 0,5 0.25 EXPECTED RANGE COLD SHUTDOWN 0

0 % ** ****

• * @ @ @ @ @ @ @ O @ @ @ Y @ @ Y @ @ 4 @ ACTION LEVEL I LIMI1 Chemistry Section DAYS COLD SHUTDOWN Technical Services Browns Ferry Nuclear Plant REACTOR WATER CHLORIDE UNITS 1, 2,

AND 3 FEBRUARY 1989 PPB 50--------------------------------------------------------------

CHLORIDE UNIT 1 40 AnM 30

"% T _

20 CHLORIDE UNIT 3 to EXPECTED RANGE

,ALL CONDITIONS

~~~~

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N Chemistry Section DAYS Technical Services Wowls Ferry hticlear Plant

1 OPERATIXG STATISTICS S

F

1 Pags 17 OPERATING DATA REPORT DOCKET NO.

50-259 DATE 3-1-89 COMPLETED BY S. A. Ratliff

)

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

1.

Unit Name:

Browns Ferry Unit One l

l 2.

Reporting Period:

Februarv 1989 l

l 3.

Licensed Thermal Power (MWt): 3293 l

l 4.

Nameplate Rating (Gross MWe):.1152 l

l 5.

Design Electrical Ratir.g (Net MWe) 1065 l

l 6.

Maximum Dependable Capacity (Gross MWe) 1098.4 l

l i

7.

Maximum Dependable Capacity (Net MWe) 1065 I

l 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 MWe):

N/A

10. Reasons For Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 672 1.416

'154.184

12. Number of Hours Reactor Was Critical 0

0-59.521.38 l

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)

O_

0 55.398.130

18. Net Electrical Energy Generated (MWH)

-4.230

-9.118 53.489.613

19. Unit Service Factor 0

0 37.8

20. Unit Availability Factor 0

0 37.8

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

32.6

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

32.6

23. Unit Forced Outage Rate 100 100 57.0

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 To be determined

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 0002R l

l l

\\...

E

-1 Page 18 OPERATING DATA REPORT DOCKET NO.

50-260 DATE 3-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (205) 729-2937 Q.PERATING STATUS l Notes l

1.

Unit Name:

Browns Ferry Unit Two l

l 2.

Reporting Period:

February 1980 l

l 3.

Licensed Thermal 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.*

l l

7.

Maximum Dependable Capacity (Net We) 1065 l

l 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 672 1.416 149.071.00

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

16. Gross Thermal Energy Generated (MWH) 0 0

153.245.167

17. Gross Electrical Energy Generated (MWH) 0 0

50.771.798

18. Net Electrical Energy Generated (MWH)

-2.383

-4.621 49.047.111

19. Unit Service Factor 0

0 36.5

20. Unit Availability Factor 0

0 36.5

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

30.9

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

30.9

23. Unit Forced Outage Rate 100 100 57.4

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

i

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

26. Units In Test Status (Prior to Comercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 0002R

f.

+

Page 19

~

OPERATING DATA REPORT DOCKET NO.

50-296 DATE 3-1-89 COMPLETED BY S. A. Ratliff TELEPHONE G.05) 729-2937 Q,PERATING STATUS l Notes l

1.

Unit Name:

Browns Ferry Unit Three l

l 2.

Reporting Period:

Februarv. 1989 l

l 3.

Licensed Thermal Power (MWt): 3293 l

l 4

Nameplate Rating (Gross MWe): 1152 l

l S.

Design Electrical Rating (Net MWe) 1065 l

l 6.

Maximum Dependable Capacity (Gross MWe) 1098.4 l

.l 7.

Maximum Dependable Capacity (Net HWe) 1065 l

l 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 MWe):

N/A

10. Reasons For Restrictions, If Any:

N/A This Month Yr-to-Da te Cumulative

11. Hours in Reporting Period 672 1.416 131.496.00

12. Number of Hours Reactor Was Critical -

0 0

45.306.08

13. Peactor Reserve Shutdown Hours 0

0 5.149.55

14. Hours Geaerator Oi-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 (MWH)

-1.578

.433 41.896.654

19. Unit Service Factor 0

J 33.6

20. Unit Availability Factor 0

0 33.6

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

29.9

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

29.9

23. Unit Forced Outage Rate 100 100 61.5

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 To be determined

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 0002R

i Page 20 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 Unit One DATE 3-1-89 COMPLETED BY S. A Ratliff TELEPHONE

_(205)729-2937 MONTH FEBRUARY 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 17

-7 2

-6 18'

-7 3

-6 19

-6 4

-6 20

-6 5

-6 21

-6 6

-6 22

-6 7

-6 23

-7 8

-6 24

-6 9

-6 25

-6 10

-6 26

-7 11

-6 27

-7 12

-7 28

-6 13

-8 29 14-

-6 30 15

-7 31 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

1 Page'21.

)

AVERAGE DAILY UNIT' POWER LEVEL i

DOCKET NO.

50-260 Unit Two DATE 3-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (205)729-2937 MONTH __ FEBRUARY 1989 DAY-AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

.(MWe-Net) 1

-4 17

-3 2

-4 18

-2 3

-4 19

-4 4

-4 20

' -3 5

-4 21

-4 6

-4 22

-3 7

-4 23

-4 8

-4 24

-4 9

-4 25

-4 10

-5 26

-4 11

-3 27

-3 12

-3 28

-4 1'

13

-4 29 l.

14

-2 30 15

-3 31 16

-2 INMRUCTIONS 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

I Page 22 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 Unit Three DATE 3-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (2051729-2937 MONTH ' FEBRUARY 1989 DAY AVERAGE DAILY POWER LEVEL DAY AI3 RAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-2 17

-2 2

-2 18 3

-2 19

-2 4

-2 20

-2 5

-2 21

-2 6

-2 22

-2 7

-3 23

-3 8

-3 24

-3 9

-3 25

-2 10

-3 26

-2 11

-3 27

-2 12

-3 28

-2 13

-2 29 j

14

-3 30 j

15

-2 31 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.

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I TvA ne2A (cM+S0 NUCLEAR PLANT OPERATING STATISTICS Page 26 Browns Ferry Nuclear Plant Period Hours 672 Month February 19 89 Item No.

Unit No.

UNIT 1 UNIT 2 UNIT 3 PLANT 1

Averaoe Hourly Gross Load, kW 0

0 0

0 2

Maximum Hour Net Generation. MWh 0

0 0

0 l

3 Ccre Thermal Energy Gen. GWD (t)2 0

0 0

0 4

Steam Gen. Thermal Energy Gen., GWD (t)2 NA NA NA NA 5

5 Gross Electrical Gen., MWh 0

0 0

0 j

3 6

Station Use, MWh 4230 2383 1578 8191 h

7 Net Electrical Gen.. MWh

-4230

-2383

-1578

-8191 5

8 Station Use, Percent 0

0 0

0 9

Accum. Core Avg. Exposure, MWD / Ton 1 0

0 0

0 6

10 CTEG Thts Month,10 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.

'O O

O 0

15 Capacity Factor, Percent 0

0 0

0 15 Turbine Avail. Factor. Percent 0

0 0

0 17 Generator Avail. Factor. Percent 0

0 0

0 e

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 staduos 0

0 0

0 23 g

24 Gross Heat Rate, Btu /kWh 0

0 0

0 5_

25 Nct Heat Rate. Btu /kWh 0

0 0

0 j$

26 U

27 j

g 28 Throttle Pressure, psig 0

0 0

0 g

29 Throttle Temperature. *F 0

0 0

0

{

30 Exhaust ' Pressure, inHg Abs.

0 0

0 0

E 31 Intake Water Temp., *F 0

0 0

0 32 33 Main Feedwater, M lb/hr 0

0 0

0 y

34 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 3822 2

40 Oil Heatina Value. Btu / Gal.

138000 41 Dismal Generation. MWh 42.0 d7 Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, %

3 43 0

0 0

o Remarks: IFor BFNP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

j 2(t) indicates Thermal Energy.

3 3 Information furnished by Reactor Analysis Group, Chattanooga 4 Administrative hold Date Submitted Date Revised a

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I Page 30 REACTOR POWER PERCENT FEBRUARY 1989 UNIT 1 PERCENT 100 90 80 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 UNIT 2 PERCENT 100-90 80 70 60 50 ADMINISTRATIVE HOLD 40 30 20 10 1 2 3 4 5 6 7 ~, 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 t

UNIT 3 PERCENT 100 90 80 70 60 50 ADMINISTRATIVE HOLD 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 l

l

r

)

MAIXTEXAXCE SEMMARY l

Page 31 MAINTENANCE MONTFLY REPORT FEBRUARY 1989 I.

INSTRUMENT MAINTENANCE A.

Placed fuel load chambers in service.

B.

Converted an Intermediate Range Monitor to a Source Range Monitor for fuel load.

II.

I&C TECHNICAL A.

Reviewed ECN/DCNs.

B.

Walkdown and validation of surveillance instructions.

C.

Maintenance Improvement Plan.

III. PREVENTIVE MAINTENANCE A.

21 component folders have been developed in the PM upgrade program in the month of February.

B.

1034 PM items were logged complete in the month of February.

IV.

MAINTENANCE SUPPORT A.

Continued the painting of floors and walls on Elevation 565 Unit 2 Turbine and Reactor Buildings.

B.

Completed the insulation of piping in the Unit 1/2 Diesel Generator Building and continuing the re-insulation of piping and components throughout the plant.

C.

Supported Operations and Restart Test with the conduct of ventilation system flow balancing tests.

V.

ELECTRICAL MAINTENANCE A.

EM continues to work MR's and PM's required for Unit 2 restart.

B.

CAQR's New - 3 Closed - 1 Submitted for closure - 2 Total open - 13 C.

Green folders New - 0 l

Closed - 0 l

Total open - 2 l

l l

1 a

l l

A Page 32 VI.

MECHANICAL MAINTENANCE Work activities performed during February A.

Performed annual and 3-year PM on 3D Diesel Gen.

B.

Assisted in flushing fire protection system and inspection of Star Deluge Valves C.

Weld preparation for ISI inspection of piping welds inside drywell.

D.

Inspection of welds on re-fuel crane C.

Swapping RHRSW sump pumps to meet operability requirements.

D.

Workplans to replace linkages on Unit 1 and Unit 3 Diesel Generator Doors (not complete, awaiting materials.)

E.

Began rebuild of Al RHRSW pump F.

Various MR's associated with supporting current Division 1 outage.

VII. MECHANICAL TECHNICAL Major work activities for the Mechanical Technical Section during the month of February 1989 involved closing numerous work activities, NRC commitments, CAQRs, ECD /DCN final closure packages, and various instructions which were approved, revised or cancelled.

VIII.

PROGRAM SUPPORT A.

Finalized Maintenance Improvement Plan B.

Critiqued MIP Training Course C.

Issued MIP action items to all organizations D.

Obtained MR data and provided graphs of performance indicators for each maintenance area E.

CAQR coordination through maintenance support group started F.

Started data input and closure of MIP items G.

Entered maintenance goals and objectives into data base in preparation of monthly report IX. ELECTRICAL TECHNICAL A.

Craft support B.

Fuse Control Program d

C.

Closed workplans D.

Numerous technical reviews E.

ITCs, ECNs, DCNs F.

Relay work G.

Numerous cognizant reviews H.

PMT for relays I.

Failure investigations J.

Measuring and Test Equipment Program K.

Circuit breaker maintenance L.

Switchyard maintenance M.

Licensing commitments N.

CAQRs

)

d l

OTHER REPORTS

e a

Page 33-CHEMISTRY

SUMMARY

FEBEUARY 1989 Primary Coolant Chemigtn Unit 1 The conductivity of the reactcr coolant remained withir 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 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 l

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.

Ahnormal Releases One abnormal release of unit 1 CST water was experienced on February 9, 1989 totaling 1.98E-04 curies. The release is documented in LER 259/89004.

l I

-_a

Page 34 PRIMARY COOLANT CHEMISTRY FEBRUARY 1989 Parameter Unit 1 Unit 2 Unit 3 l

l

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 (uCi/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. ppb)

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

3. Tritium (pCi/ml)

High 4.10E-5 3.46E-5 1.37E-4 Low 3.63E-5 3.10E-5 1.16E-4 Average 3.76E-5 3.29E-5 1.23E-4

4. Iodine-131 (uCi/ml)

High

<1.17E-6

<6.02E-7

<7.62E-7 Low

<6.89E-7

<5.00E-7

<6.09E-7 Average (8.74E-7

<5.54E-7

<7.21E-7

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

,':c:.

.Page 35 c

o e

i t

PRIMARY COOLANT CHEMISTRY (Continued)

Parameter Unit 1 Unit 2 Unit 3

6. Chloride (pob)

.High

<20

-<20

<20 Low

<10

<10

<10 Average NA NA NA

7. Sulfate (opb)

High

<20

<20

<20

. Low

<10

<10

<10 Average NA NA NA

8. DH @ 25'C High 6.2 5.9 6.0 Low 5.9 5.6 5.6 Average 6.0-5.7 5.9

9. Conductivity (pmho/;m@25'C)

High 0.13 1.02 0.28 Low 0.094 0.80 0.13 Average 0.11 0.94 0.20

-~-

t ENVIRONMENTAL REPORT FEBRUARY 1989-The ambient upstream river temperature (24-hour. average) ranged f rom 50.4*F (February 8) to 46.7'F (February 22) with an average of 48.5'F.

The downstream temperature varied between 50.4*F (February 8 and 9) to 46.5'F (February 22) with an average of 48.5'F for the month.

The largest temperature change was 0.7'F occurring on February 26.

The monthly average change was 0.1'F.

i No chlorination of plant systems took place during this. reporting period.

The sedimentation pond is still out of service. We have. received permission f rom the State of Alabama to proceed with our plans to redesign the liner system.

The stata did ask us to include a vent system into that 3 sign.

The sewage stabilization pond worked within operating parameters this month. The Biochemical Oxygen Demand (BOD) ranged from 23 ppm (February 3) to 27 ppm (February 10). The Total Suspended Solids'(TSS) i ranged f rom a high 35 ppm (February 24) to a low 10 ppm (February 10).

The 800 and TSS averages for the month were 25 and 20 ppm respectively.

1416m/p.4 1

g_L g

Paga 37 AIRBORNE RELEASES (1)

FEBRUARY 1939 l

SUMMAlION 01' Al. L RELEASEC UNIT THIS MONTH A.

FItiSION AND ACrit/ATION GASCC 1.

TOTAL RELEASE CI r, 9 22E 01 2.

At/ERAGE RELEASE RATE FOR PERIOD UCI/SEC

'; 3.81E 01 3.

PERCEN'l OF TECH. SPEC. LIMIT (0.15 C1/SEC) 0.00E-01 3s IUDINEC 1.

T01AL 10 DINE 131 CI

1.18E-04 l

2.

A t/ CR AGE RELEAGE RAIE FOR PERIOD UCI/SEC

4.07E-05 l

3.

l'ERCENT OF TECH. SPEC. L1 HIT (2.19 UCI/SEC) 0 00E-01 C.

PARTICtlLAIEC 1.

PARTICULA'IES !JITH HALF-LIFEC ; OR e TO 8 DAYS CI 3.70E-0, 2.

At/CRAGE RELEAGE RATE FOR PERIOD UCI/SEC 1.53E-06 3.

PERCENT OF TECH. SPEC. LINIT(2.19 UCI/SEC) 6.98E-05 4.

OROHG AL. Pilo R ADID AC TII/I TY CI 0.56E-07 s

D.

TRITIUM 1.

TOTAL RELEASE CI

, 2.49E-03 i

l 2.

A L)l.R A G E RELEASE RA[E FOR PERIOD UCI/SEC

( 1.03E-03 3.

PERCENT OF T li G H. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 4.

OR0!JHD LEtM(L WLI. EASE Cl

's 2.26E-03 5.

Lt.FVATEI'i REl.FASE CI

', 2 30E-04 (1)

REPtlRTING PERIOD 28 DAYO

t

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e.

Pags 38 AIRit0RNE RELEASES (CONTIHUED)

FEBRUARY 1989 GROUNO RELt'ASEC A.

IISSION GASE3 UNIT THIS MONTH NR-8%Il CI

< 9.65E-02 KR-85 CI

< 5.04E 01 KR 87 CI

< 3.65E-31 KR-08 CI

< 4.52E-01 XE-133 CI

< 3.71E-01 XE-135M CI

<, 3.29E-01 XE-135 CI c 1.38E-01 XE-138 CI i 6.04E-01.

OTHL.RG(SPECIFY)

TOTA 1. FOR PERIOD CI

's 5.28E 01 B.

100INES I-131 CI i 8.13E-05 I-133 CI

< 4.04E-04 I-130 CI

5.27E-01 TOTAL FOR PERIOD CI 5 27E-01 l

l l

j

.)

S c.

Page 39 l

AIRDORNE RELEASES (CONTINUED)

FEBRUARY 1789 l

l GROUND ret.EASEC C.

l' ART 1CULATES UNIT THIS MONTH GR-89 CI

1.34E-06 SR-90 CI

< 5.12C-07 CS 134 CI

'; 1.09E-04 C3-137 CI

< 9.63E-05 BA-140 CI

< 3.81E-04 L A - 1 10 CI

< 0.89E-05 OTHERS(SPECIFY)

C D -- (. 0 CI 3.70E-06 TOTAL FOR PERIOD CI 3 70E-06 D.

'I R I T I UM CI

, 2.26E-03

u /

Pags 40 AIRBORNE RELEASES (CONTINUED)

~

]

FEBRUARY 1989 l

ELEVATiiD RELEAfiEO I

1 A.

FISSION GASES UNIT THIS MONTH KR-OSM CI

<, 3.03E-02 KR-05 CI

< 3.75E 01 KR-87 CI

< 2 27E-01 KR -88 CI

< 3.35E-01 XE-133 CI 2.20E-01 XE-135M CI 2.44E-01 s

XE-13b CI 8.40E-02 XE-138 CI

6.64E-01 l

OTHt.RS(SPECIFY)

TOTAL.FOR PERIOD CI 3.94E 01 s

B.

10 DINES 1-101 CI

3.64E-05 I~133 CI 3.70E-05 I-125 CI

( 6.96E-03 TOTAL FOR PERIOD CI 7.03E-03 i

_.________._m_

1

~ v 2

Pags 41.-

AIRDORNE R t. L C A S E S (CONTINUED) i FEBRUARY 1989 1

i ELEVATED RELEASES j

C.

PARTICULATE UNIT THIS MONTH i

GR l:9 CI

2.16E-07 SR-90 CI

<-8.46E-08 C5"134 CI

3.07E-05 CS-137 CI

< 1.97E-05 BA-140 CI

< 1.09E-04 L A -140 CI

7.07E-05 OTHERS(SPEC.TFY)

TOTAL FOR PCRIOD CI

2 30E-04 D.

FRIrIUM CI

< 2.30E-04 l

i

Page 42' DROWNS FERRY NUCLEAR PLANT MONfHLY REPORT CALCULATIONS LIQU2D RELEASES FEBRUARY 1909 RADIOACTIVE LIQUID EFFLUENTS 1.

CROSS RADIOACTIVITY UNITS a)

TOTAL RELEASE CURIES 1.71E-02 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.57E-09 c)

PERCENT OF APPLICABLE LIMIT ( 1E -7 UCI/ML )

1.57E 00 2.

TRITIUM a)

TOTAL RELEASE CURIES 6.77E-02 b)

AVERAGE DIL.UTED CONCENTRATION RELEASED UCI/ML 6.22E-09 c)

I'ERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 2.07E-04 (1) 3.

DISSOLVED NODl.E GASES a)

TOTAL RELEASE CURIES

< 0.42E-04 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML

< 7.74E-11 c)

PERCENT OF APPLICABLE LIMIT (2E-04 UCI/ML)

< 3.87E-05 4.

GROSS AL.PHA RADI0 ACTIVITY a)

TOTAL RELEASE CURIES

<1 49E-04 b)

AVERAGE DILUTED CONCEN TRATION RELEASED UCI/HL

<1.37E-11 5.

VOLUME OF LIQUID WASTE TO DISCHARbE CANAL LITERS 3 27E 06 6.

VOLUML OF DILUTION WATER LITERS 1.09E 10 t)

INCLUDES XE-133, XE-135, AND OTHERS

u

-i Paga 43 BROWHS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIOUID RELEASES FEDRUARY

-1989 ISOTOPES RELEASED UNITS CI CR-51

<'2 05E-03 MN-54

< 2 33E-04 CD-58

< 2.06E-04 FE-59

< 4.74E-04 CO-60 2.27E-03 ZN -65 4.24E -04 ND-95

< 2.01E-04 ZR-95

< 3.58E-04 MOTC 99M

< 1.78E-04 I-131

< 2.55E-04 XE-133

< 6.95E-04 l

CS 134 1.71E-03 XE-135

< 1.47E-04 CS-137 1.26E-02 BA-140

< 1.00E-03 LA-140

< 1.67E-04 CC - 141

< 2.98E-04 SR -09

< 8.80E-05 SR-90

< 4.59E-05 i

m

w e Pags 44 BROWNG FliRRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIUUID RELEASES FEDRUARY 1909 OTHERS UNITS CI SB-125 9,07E-05 FE-55

< 8.38E-04 I

I l

l l

l

Page 45 BROWHS F3RRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES FEBRUARY 1909 LAUNDRY DRAIN VOLUME RELEASED:

0.0 OALLONS FLOOR DRAIN VOL UME REL E ASED:

926970.0 GALLONS WASTE SAMPLE FAMK VOLUME RELEMtED :

37303.3 OALLONS DISTILLATE TANK VOLUME RELEASED:

0.0 GALLONS t.UCATION OTHER IHAN RADWASTE VOLUME RELEASED:

192000.0 GALLONS TOTAL VOLUME REl,EADED TO THE RIVER:

364353.3 GALLONS HIGilEST BATCH ACTIVITY RELEASED FOR MONTH:

3.43E-09 UCI/ML A/D LONGEST RELI~ AGE TIME FOR MONTH:

315 MINUTES Sil0R LES r RELEASE FINE FOR MONTH:

20 MINUTES TOTAL TIME OF RELEASES FOR MON'lH:

7190 MINUTES AVERAGE fIME FOR DATCll RELEASES:

232 MINUTES NUMBER OF DATCHES RELEASED:

31 NUMBER OF ADMINIS TR AT IVE LIMIT VIOLATIONS:

0 NUMDCR OF TECHNICAL SPECIFICATION VIOLATIONS:

0 i

v' o

Page 46 e

RESIN USAGE REPORT FEBRAt 1989 RESIN CONSUMED (CV.FT.)

% of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 35.8 0

126 0

0 0

126 We.ste Demineralized 0

0 0

0 0

0 0

Waste Filter 47 7 0

168 0

0 0

168 Fuel Pool Demins 0

0 0

0 0

0 0

Reactor Water Cleanup Unit 1 0.9 0

3 0

0 0

3 Unit 2 4.3 0

15 0

0 0

15 Unit 3 0

0 0

0 0

0 0

Cond. Demins.

Unit 1 0

0 0

0 0

0 0

Unit 2 11.3 0

40 0

0 0

40 Unit 3 0

0 0

0 0

0 0

Totals 100 0

352 0

0 0

352

s 6

Page 47 FUEL CLADDING INTEGRITY PARAMETERS FEBRUARY 1989 Unit 1 Reactor Water Iodines (mei/sec.)

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

DJan Elp_y MW_t h ilt Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 I

l Unit in Outage l

Unit 2 Reactor Water Iodines (mci /sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Pischarme cf SJAE (mgi/sec)

DJgg Elgy MEL Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (mei/sec.)

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

E12y MW_t Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 l

Unit in Outage I

0002R

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Page 49 TESTING S,UMMARY FEBRUARY 1989 Surveillance Testing Unit 0 A total of 129 surveillance tests were completed using 43 different test instructions.

Unit 1 A total of 70 surveillance tests were completed on unit 1 using 19 different test instructions.

Unit 2 A total of 144 surveillance tests were completed on unit 2 using 53 different test instructions.

Unit 3 A total of 64 surveillance tests were completed on unit 3 using 15 different test instructions.

0002R

_ _ _ _ _ _ _ _ _ _.. _ _ = _ _ _ _ _

Page 50 s

TESTING

SUMMARY

(CONTINUED)

FEBRUARY 989 Channes. Tests. and Experiments Reauirina Authorization From the NRC Pursuant to 10 CFR 50.59(a)

There were two revisions for units 1, 2, and 3 technical specifications, Chan:2es. Tests. and Erneriments not Reauirina Authorization from NRC Pursuant to 10 CPR 50.59(a)

There were no special-tests completed for this month.

e

.o

.au.,

Page 51 REACTOR VESSEL FATIGUE USAGE EVALUATION FEBRUARY 1989 The cumulative usage factors for the reactor vessel are as follows:

l Usage Factor l

Location.

Unit 1 Unit 2 Unit 3 i

Shell at water line 0.00620 0.00492 0.00431' Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 0002R L-

...__._._._-..m..m_-.

______________m.___

as.,.

Page 52-CHANGES IN PROCEDURES FEBRUARY 1989 There were 453 revisions to plant instructions during the' month; 453 instructions' vere changed primarily for correction; and zero revisions related to-safe operation'of the plant.

PLANT INSTRUCTION REVISIONS FEBRUARY 1989 Category Instruction-Reason for Reauest There were no revisions for the month.

s.. ~ -

o.

L.

Page 53 CANGES IN PLANT ORGANIZATION FEBRUARY 1989 There were five changes in plant staff for those positions designated as key supervisory positions for the month. They were as follows:

P. T. Becknell, Manager Mechanical Maintenance, E. D. Cornelius, Manager Special Projects, Bertram C.' Morris, Manager Corrective Action Program, Daniel C. Phillips, Maintenance Superintendent, Oswald J. Zeringue, Site Director.

l

~#

Page 54*

n h

ACCIDENTS FEBRUARY 1989 There were three loss-of-cime accidents during the month.

1 0002R 1

a=

9 TENNE 95EE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35609-2000 FAR 211989

..,n s

U.S. Nuclear Regulatory Commission AITd: 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 - FEBRUARY 1989 H

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

Very truly yours, TENNESSEE VALLEY AUTHORITY 4L90 &

Guy G. Campbell Plant Manager Enclosure i

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 Rcgional Administration NRC Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Office of Inspection and Enforcement Route 12, Box 637 Region II Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 C

Mr. Ted Marston, Director C

l Electric Power Research Institute P. O. Box 10412 l

}

Palo Alto, California 94304 An Equal Opportunity Employer

_ _ _ _ _ _ _ - -