ML20245E711

Monthly Operating Repts for May 1989 for Browns Ferry Units 1,2 & 3

ML20245E711
Person / Time
Site:	Browns Ferry
Issue date:	05/31/1989
From:	Campbell G, Ratliff S TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8906270408
Download: ML20245E711 (71)

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.N . TENNESSEE VALLEY AUTHORITY' Browns Ferry Nuclear-Plant Post Office Box 2000 Decatur, Alabama 35609-2000l ]

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..JUN i 61989 1

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- U.S. Nuclear Regulatory Commission ATTN: Document Control Desk .

4 Office of Nuclear Reactor Regulation Washington, D.C. 20555-

'l 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.0PERATING. REPORT - May.1989 Enclosed..is the May 1989 Monthly Operating Report to NRC for. Browns Ferry

- Nuclear Plant units 1,,2, and 3.

Very truly yours, ]

TENNESSEE VALLEY AUTHORITY b U/4 Yl '

uy G. Campbell

- Plant 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 i Regional Administration NRC Resident. Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear' Plant .,

Office of Inspection and Enforcement Route 12, Box 637 l Region II Athens, Alabama 35611 101 Marietta Street,.NW, Suite 2900 i Atlanta, Georgia 30323 Mr. Ted Marston,. Director Electric' Power Research Institute P. O. Box 10412  ;

Palo Alto, California 94304  ;

KO A U l An Equal Opportunity Employer i

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MONTHLY OPERATING. REPORT I i

i BROWNS FERRY NUCLEAR PLANT 1

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TENNESSEE VALLEY AUTHORITY MAY 1989 .

J i ," Safety and Quality are Paramount"

i DOCKET NUMBERS 50-259, 50-260, AND 50-296 '

LICENSE NUMBERS DPR-33, DPR-52. AND DPR-68 Submitted by:-

AV$

[" Guy G. Campbell Plant Manager

t TABLE OF CONTENTS (Continued)

PART III. OTHER REPORTS

l. . Chemistry Summary

1. Primary Coolant Chemistry .................................. 35

2. Environmental Technical Specification Requirements.......... 38

3. Airborne Releases........................................... 39

4. Liquid Releases............................................. 44

5. Resin Usage Report.................................. ....... 48

6. Fuel Cladding Integrity Parameters.......................... 49

7. Waste Treatment System Throughputs.......................... 50 B. Testing Summary................................................. 51 C. Reactor Vessel Fatigue Usage Evaluation......................... 53 D. Change in Procedures............................................ 54 E. Plant Instruction Revisions..................................... 54 F. Change in Plant Organization....................................

56 G.

Accidents....................................................... 57

TABLE OF CONTENTS PART I. OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B Refueling Information............................................ 2 C. Main Steam Relief Valve (MSEVs) Actuation Summary................ 7 D. Issuance of Special Reports Summary. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 E. Licensee Event Reports Summary................................... 9 F. Offsite Dose Calculation Manual Changes......................... 11 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

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....................................... 21

2. Average Daily Power Leve1................................... 24 -

3. Unit Shutdowns and Power Reductions......................... 27 B. TVA Reports

1. Plant Operating Statistics...................... ........... 30

2. Unit Outage and Availability Data........................... 31

3. Reactor Histogram (Reactor Power Percent)................... 34 j I

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ACRONYMS /ADOREVIATIONS (Continued) -

ER Engineering Report IICW 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 Gallons per. minute GOI General Operating Instruction HPCI High Pressure Coolant Injection NVAC 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 MCIL Master Components Electrical List HMI Mechanical Maintenance Instruction MNt Megawatts thermal l 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 i NPS Nuclear Procedures Staff  !

l N2A Nuclear Quality Assurance l

NQAM Nuclear Quality Assurance Manual 1 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 ,

, 1 OL Operating Licensee i ONP. Office of Nuclear Power I O

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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 BFIL 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 EQDP Environmental Qualification Documentation Package EQE Earthquake Engineering EQP Environmental Qualification Project l

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ACRONYMS / ABBREVIATIONS (Continued)

PASS Post Accident Sampling System PCIS Primary Containment Isolation System PD Position Description PM Preventive Maintenance PMT Post Modification Test PORC Plant Operations Review Committee PSI Preservice Inspection PSS Potentially Safety Significant GA 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 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 l SCRAM Safety Control Rod Activation M,snually 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 SON Sequoyah Nuclear Plant SQUG Seismic Qualification Utility Group SRO Senior Reactor Operator N 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 TVA Tennessee Valley Authority UO Unit Operator USA United States of America USQD Unreviewed Safety Question Determination VMCP Vendor Manual Control Program WBN Watts Bar Nuclear Plant WP Workplan

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OPERATIONAL SEMMARY

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l REFUELING INFORMATION MAY 1989 Unit 1  :

1. Name of facility Browns Ferry Nuclear Plant i i

2. Scheduled date for next refueling shutdown l N/A I

3. Scheduled date for restart following refueling N/A i I

4. Will refueling resumption of operation thereafter require a technical i specification change or other license amendment? i 1

BFN, cycle 7 startup has not been scheduled at this time. When required, l the cycle 7 reload licensing submittal will be made to support Technical I Specification thermal limits for the core design and specific fuel assembly types to be loaded.

1 NOTE: Item 4 information addresses only licensing changes directly l associated with the reload core design.  !

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5. Scheduled date(s) for submitting proposed licensing action and supporting  !

information N/A l

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures Cycle 7 final core design has not been developed at this time. ~

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel ,

storage pool '

(a) 0 (b) 1,864

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in the number of fuel assemblies 3,471 i

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SIGNIFICANT OPERATIONAL ZVENTS

SUMMARY

MAY 1989 4

Unit 1 05/01/89 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

05/31/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns. ,

Unit 2 05/01/89 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Modification and Operation &

Maintenance work continues to support restart in September 1989.

05/31/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerna. Modification and Operations &

Maintenance work continues to support restart in September 1989.

Unit 3 05/01/89 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

05/31/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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. i REFUELING INFORMATION MAY 1989 '

Unit 2

1. Name of facility Browns Ferry Nuclear Plant

2. Scheduled date for next refueling shutdown I l

N/A l

3. Scheduled date for restart following refueling l

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4. Will refueling resumption of operation thereafter require a technical I specification change or other license amendment?

Changes to the Technical Specification as a result of the BFN 2, cycle 6 l final core design have been submitted along with the BFN Reload Licensing I Report for unit 2, cycle 6 (TVA RLR-002) Revision 2. This report documents 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 l information j N/A

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis l 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. i 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 described 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 storage pool (a) 764 (b) 1,444

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REFUELING INFOR!% TION Unit 1 (Continued)

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licersed 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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Pags 6 REFUELING INFORMATION MAY 1989 Unit 3

1. Name of facility Browns Ferry Wuclear Plant I

2. Scheduled date for next refueling shutdown N/A

3. Scheduled date for restart following refueling l

N/A

4. Will refueling resumption of operation thereafter require a technical 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 l required (MCPR), the appropriate submittal will be made.

NOTE: Item 4 information addressec 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 fuci 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 apent fuel storage pool (a) 0 (b) 1,768

8. The present licensed spent fuel pool storage capacity and the ;ize 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 I fuel pool assuming the present licensed capacity This spent fuel storage pool will have the capacity to handle full core discharge following the cycle 13 refueling in May 2006.

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REFUELING INFORMATION 1 Unit 2  ;

(Continued)  ;

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8. The present licensed spent fuel pool storage capacity and the size of any 1 increase in licensed storage capacity that has been requested or is planned, I in the number of fuel assemblies 3,471

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9. The projected date of the last refueling that can be discharged to the spent  !

fuel pool assuming the present licensed capacity -

l 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.) l 1

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. Pags 8 ISSUANCE OF SPECIAL REPORTS J MAY 1989 The following special reports are notices of violations-issued for the month of May 1989.

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260/89-06-01 During the performance'of surveillance instructions and.

Instrument calibrations, procedures were not properly:

implemented..

.260/89-06-02 Calibration cards used to record vital instrument'information and calibration results were not controlled by plant administrative procedures as QA records.

l 259,260,296/ A design deficiency associated with nonseismically qualified- .)

89-10-02 vitrified clay pipe in three EECW discharge flow paths was.not .

identified on a Condition Adverse to Quality Report in a timely manner.

1 260/89-10-01 The requirements were not met in that during the performance of. 'j the Unit 2 core reloading on and after January 3,.1989, core spray was inoperable and the motor operated valves in the Unit 1 2 standby coolant' supply flow pe.th were. considered to be ]

$noperable due to the nonseismically qualified EECW flow paths. j i

259,260,296/ The Unit 1 Reactor Zone Exhaust' Radiation Monitor (Channel A)  ;

89-11-01 was inoperable and the required compensatory actions were not .j in place. '

296/88-11-05 The continuous conductivity monitor was ma,de inoperable'and a l reactor coolant sample was not taken and analyzed in the specified time limit.

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d MAIN STEAM RELIEF VALVE (MSRVs) SUf9tARY MAY 1989' i

No MSRVs were challenged during the month.

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-LICENSEE EVENT REPORT (s)

(Continued)'

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89-012.

EMLURE'TO MEET TECHNICAT. SPECIFICATIONS BECAUSE OF MISC 0f91UNICATION ON SPECIAL REOUIRZMENTS OF AN ELECTRICAL ]

ALIGNPEHI l On April 5,.1989, the diesel generator.480 volt auxiliary board' >

l vas aligned to 4160 volt shutdown board B in preparation for the' ,

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A diesel generator outage. The normal power supply is'the 4160 volt shutdown board A. .The engineering analysis for this 1 abnormal alignment resulted in the imposition'of special j requirements to prevent an overload of the B diesel generator in. l an accident condition. The special requirements were discussed :

with operations, systems engineering and nuclear. engineering and' a formal transmittal of the written special requirements was .i preparedi However the' written special requirements were not 1

' transmitted to the shift operators prior to the-board transfer.

When the written documentation of the special requirements was received by shift personnel, it was discovered'that the.2C RHR L pump breaker.had not been removed from service as required by the p analysis. This resulted in the 4160 volt shutdown board B being  ;

j{ declared inoperable and subsequent inability to meet the TS l requirements for RHR.

2-89-013 FAILURE TO MEET TECHNIcAT. SPECIFICAITONS BECAUSE'0F INADEOUATE I fa EROL OF FLOOD PROTECTION RADDIERS On April 9, 1989, it was discovered by a system engineer that manway covers in.RHRSW pump room A and D were not bolted down.

Since the manways provide.a flood barrier for the RHRSW pump rooms the A1, A2,.A3, D1, D2, and D3 RHRSW pumps were declared-inoperable. The manways were secured on April 15, 1989 after questions on bolting material.were resolved. A review of work documents associated with the manways revealed that.the manways were removed on February 9, 1989 in order to inspect pipe supports under the. floor. A review of plant system status from February 9, 1989, until the manways-were secured discovered that i the condition caused the TS for containment cooling to not be met. -

1 Psga 9 ,.j LICENSEE EVENT REPORT (0) -I MAY 1989 Description of Event LEE i

1-89-008 DESIGN OF PRIMARY CONTAINMENT HYDROGEN AND OXiGzn ANALYZERS DOES NOT MEET SINGLE FAILURE CRITERIA On April 20, 1989, it was determined that the design of the primary containment hydrogen and oxygen analyzers cooling water discharge ,

did not meet single failure criteria and was therefore outside the

}

design basis for the plant. For each unit the. cooling water {

discharge lines from the hydrogen and oxygen analyzers connect to a

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common Emergency Equipment Cooling Water discharge header containing a single downstream check valve. Failure of this check valve in the closed position would deprive both trains of the hydrogen analyzers for the respective unit of the cooling water necessary to perform their function. This portion of the EECW system will be modified to comply with the design basis.. .,

1-89-009 SINGLE FAILURE OF ELECTRICAL FIRE PUMP LOCK OUT DRT.AY DURING {

LOP /LOCA COULD OVERLOAD A DIESEL GENERATOR

] ]

This LER details a condition caused by a failure to adequately 4 address single failure effects during the original plant design for the fire pump logic.

2-89-009 UNPLANNED SCRAM AND MAIN STEAM LINE ISOLATION DUE TO SPURIOUS SPIKES ON MAIN STEAM LINE RADIATION MONITORS

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On April 11, 1989, unit 2 received qpurious spikes'on independent main steam line radiation monitors which resulted in completion of the initiation logic for a full scram and main steam line isolation 1 valve isolation.

2-89-011 FAILURE TO MEET TECHNICAL SPECIFICATIONS BECAUSE OF LOSS OF RHRSW -l SUMP PUMPS I On April 4, 1989, the RHRSW pump room A-1 sump pump was declared ~

inoperable because of a problem with the level switch that controlled the pump operation. The A-2 sump pump was undergoing maintenance at the time and was also inoperable. Since at least one  ;

sump pump is required to be operable to support the RHRSW pumps, the A1, A2, A3 RHRSW pumps were declared inoperable. Therefore the RHR heat exchanger did not have an operable supply of RHRSW which made the plant not meet the TS requirements for containment cooling..

Page 12 RADWASTE

SUMMARY

MAY 1989 The radwaste system performed as designed. Approximately 9.75E+05 gallons of waste liquid were discharged containing approximately 1.29E-02 curies of activity.

There was one spent resia shipment and one trcsh shipment during May. All shipments were to Barnwell, South Carolina.

There were no shipments made by a radwaste broker / processor containing any BFN waste during May. .

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OFFSITE DOSE CALCULATION MANUAL CHANGES MAY 1989 No changes were made to the BFN Offsite Dose Calculation Manual during the month.

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. Solid Radioactive Waste (Continued)

May 1989

SUMMARY

Type Cubi.c Feet Cubic F'eet Gross Activity. Estimated, of Shipped Packagad For Of Waste- Generation For

-Waste During Month' Shipment Shipped. Next' Month COMPACTED Drums 0000'0(2)

. 637.5 0.00E+00 Ci 250 Cu.Ft.

Boxes 0000.0(2) 651.0 0.00E+00 Ci. 279 Cu.Ft.

UNCOMPACTED Drums 0000.0(2) 1207.5 0.00E+00 Ci 225 Cu.Ft.

Boxes 0000.0(2) 910.6 0.00E+00 Ci 200 Cu.Ft.

BROKERED To Broker 0000.0(2) 2238.8 '0.00E+00 Ci N/A Disposal 0000.0('2) N/A 0.00E+00 Ci N/A RESIN 5 CWP5 186.0(1) 126C(3) 3.21E+00 Ci 470 Cu.Ft.

RWCU -

000.0(1) 40(3) 0.00E+00 Ci .10.Cu.Ft.

TOTALS 205.8(2) 5645.4 3.21E+00 Ci 1434 Cu.Ft.

e Total volume of waste shipped during the month: 205.8~Cu.Ft.(2)

Total volume of waste shipped. year-to-date: 5732.2 Cu.Ft.

Unused 1989 burial volume allocation at Barnwell: 77067.8 Cu.Ft.

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(1) Actual resin volume-(2) Container burial volume (3). Estimated volume in separators 1 i

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Solid Radioactive Waste May 1989 Dewatered Resin Shioments(1)

Volume of condensate / waste (CWPS) resin shipped: 5.83 Cu.M.

(205.80 Cu.Ft.)

Total activity shipped: 3.2113 Curies <

l Volume of reactor cleanup (RWCU) resin shipped: 0.00 Cu.M.

(000.00 Cu.Ft.)

Total activity shipped: 0.0000 Curies i

Date 5hicoed Disposal Facility Tvoe gf Resin 05/16/89 Barnwell, SC CWP5 Drv Active Waste ShiomentsC1)

Number of drums shipped: NONE Vo l. ume : 0.00 Cu.M. ,

(000.00 Cu.Ft.) I i Total activity shipped: 0.0000 Curies '

l Number of boxes shipped: NONE Volume: 0.00 Cu.M.

(000.00 Cu.Ft.) l Total activity shipped: 0.0000 Curies 1

Date Shipped Disoasal Facility Tvoe of Packaoe N/A

• N/A N/A Brokered Shioments Broker: QUADREX Recycling Center Volume: 0.00 Cu.M. d Address: Oak Ridge, Tennessee C000.00 Cu. Ft)

Total activity shipped: 0.0000 Curies Date Shipped Disposal Facility Tvoe of Packaoe N/A N/A N/A (1) All shipments were by Sole-Use Vehicle

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Page 20 REACTOR POWER - MWT UNITS 1, 2, AND 3 MA Y f989 MWT 3500 -

3000 -

LMIT 1: OUTAGE 2000 -

UNIT 2: OUTAGE g, , UNIT 3: OUTAGE 1000 -

500 -

0"

• • %%***^**R4%Q%5545#SC44455455R4 menistry Sectiorr 0AYS Tcchtlical Services Woms Ferry Atsclear' P1arrt

• REACTOR WATER CONDUCTIVITY UNITS 1, 2, AND 3 MA Y 1989 US/CM CONDUCTIVITY 1.75 .

UNIT 1

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~

REACTOR WATER CHLORIDE UNITS 1, 2, AND 3 NAY f989 PPB 20 '

CHLORIDE LMIT 1 is --------------------------------------------------------------

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• * + ** * * * ^ *

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menistry Section OAYS -

Tochttical Services Woms Ferry htscisar Plant

LIGUID RADWASTE -

MAY 1989 TOTAL RIVER RELEA.SE FLOW RATE (GPM) DATA PLOTTED FOR THE PREVIOUS 12 MONTHS TOTAL RELEASE (CI) 40 - - 2 p

RITE fBPM)

HI 29.91 LOW 20.72 l 30 - AVG 24.14

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4 _ LOW 0.90E+06  ;

AVG 0.13E+07 FLOOR DRAIN-3 -

HI O.12E+07 LOW O.79E+0S AVG 0.10E+07

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LAUNDRY HI 0.93E+04 LOW O.00E+00 I

g . AVG 0.19E+04  ;

JUN JUL AUG SEP OCT NOV DEC JAN FEB MAR APR MAY COST OF OPERATION oP RiS '7foLinm j THOUSANDS OF DOLLARS HI O 54E+05 j 90 - LOW 0.20E+05 '

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JUN JUL AUG SEP OCT NOV DEC JAN FES MAR APR MAY WASTE C0LLECTOR SYSTEM LAUNDRY SYSTEM FLOOR DRAIN SYSTEM

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4 OPERATING STATISTICS I

l I

, Page 22 OPERATING DATA REPORT l

DOCKET NO. 50-260.

DATE May 1989 PREPARED BY S.A.Ratliff TELEPHONE 205-729-2937 OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT TWO

2. Reporting period: MAY, 1989

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electric Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe): 1065

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason: N/A IN

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

10. Reason For Restrictions, If'Any: N/A I

THIS YEAR-TO MONTH DATE CUMULATIVE

11. Hours'In Reporting Period 744.0 3623 151278

12. Hours Reactor Was Critical 0.0 0 55860

13. Reactor Reserve Shutdown Hours 0.0 0 14200

14. Hours Generator On Line 0.0 0 54338

15. Unit Reserve Shutdown Hours 0.0 0 0 _

16. Gross Thermal Generation (MWh) 0.0 0 153245167

17. Gross Electric Generation (MWh) 0.0 0 50771798'

18. Net Electric Generation (MWh) -2416.0 -10706 49041026

19. Unit Service Factor 0.0 0.0 35.9

20. Unit Availability Factor 0.0 0.0 35.9

21. Unit Capacity Factor (MDC Net) 0.0 0.0 30.4

22. Unit Capacity Factor (DER Net) 0.0 0.0 30.4

23. Unit Forced Outage Rate 100.0 100.0 58.1

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

25. If Shut Down At End Of Reporting Period, Estimated Date Of Startup: September 20, 1989

. .. . . . .. ~, _ - . c + -

, .+- r-- -- .

Page 21 .

OPERATING DATA REPORT DOCKET NO. 50-259 DATE May 1989 PREPARED BY S.A.Ratliff TELEPHONE 205-729-2937 OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT ONE

2. Reporting period: MAY, 1989

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electric Rating (Net MWe) : 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

• 7. Maximum Dependable Capacity (Net MWe): 1065

8. If Changes occur in capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason: N/A

5. Power Level To which Restricted, If Any (Net MWe): N/A

10. Reason For Restrictions, If Any: N/A THIS YEAR-TO MONTH DATE CUMULATIVE

11. Hours In Reporting Period 744.0 3623 156391

12. Hours Reactor Was Critical 0.0 0 59521

13. Reactor Reserve Shutdown Hours 0.0 0 6997

14. Hours Generator On Line 0.0 0 58267

15. Unit Reserve Shutdown Hours 0.0 0 0 -

16. Gross Thermal Generation (MWh) 0.0 0 168066787

17. Gross Electric Generation (MWh) 0.0 0 55398130

18. Net Electric Generation (MWh) -5040.0 -24476 53474255

19. Unit Service Factor 0.0 0.0 37.3

20. Unit Availability Factor 0.0 0.0 37.3

21. Unit Capacity Factor (MDC Net) 0.0 0.0 32.1

22. Unit Capacity Factor (DER Net) 0.0 0.0 32.1

23. Unit Forced Outage Rate 100.3 100.0 57.7

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

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

,. Page 24 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 Unit One DATE 6-1-89 COMPLETED BY S. A Ratliff TELEPHONE (205)729-2937

! MONTH MAY 1989 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

. 1 ~6 17 -7 1

2 -8 18 -7 3 -8 19 -8 4 -6 20 __

-7 5 -9 21 -7 6 -5 22 -7 7 -5 23 -9 8 -6 24 -7 9 -5 25 -7 10 -5 2C -7 11 -5 27 -7 12 -6 28 -7 -

l 13 -6 29 -7 14 -6 30 -8 15 -7 31 -8 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 near:ist whole megawatt.

(9/77)

Page 23 .

OPERATING DATA REPORT DOCKET NO. 50-296 DATE May 1989 PREPARED BY S.A.Ratliff TELEPHONE 205-729-2937 OPERATING STATUS

1. Unit Name: BROWNS FERRY UNIT THREE.

2. Reporting period: MAY, 1989

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electric Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1098.4

7. Maximum Dependable Capacity (Net MWe): 1065

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

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

10. Reason For Restrictions, If Any: N/A THIS YEAR-TO MONTH DATE CUMULATIVE

11. Hours In Reporting Period 744.0 3623 133703

12. Hours Reactor Was Critical 0.0 0 45306

13. Reactor Reserve Shutdown Hours 0.0 0 5150 )

14. Hours Generator On Line 0.0 0 44195 j

15. Unit Reserve Shutdown Hours 0,0 0 0 a

16. Gross Thermal Generation (MWh) 0.0 0 131868267 I

17. Gross Electric Generation (MWh) 0.0 0 43473760

18. Net Electric Generation (MWh)~

-1415.0 -7909 41892178

19. Unit Service Factor 0.0 0.0 33.1

20. Unit Availability Factor 0.0 0.0 33.1

21. Unit Capacity Factor (MDC Net) 0.0 0.0 29.4

22. Unit Capacity Factor (DER Net) 0.0 0.0 29.4

23. Unit Forced Outage Rate 100.0 100.0 62.2

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

25. If Shut.Down At End Of Reporting Period, Estimated Date Of Startup: To be determined i

I

Pega 26

~

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Unit Three ,.

DATE 6-1-89 COMPLETED BY- S. A. Ratliff j

TELEPHONE (205)729-2937 j MONTH MAY 1989 j 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)'

1 -2 17 -2 I'

2 -2 18 -2 3 -2 19 -2 4 -1 20 -2 l 5 -2 21 -2 l

1 6 -2 22 -2 7 -2 23 -2 d 8 -1 24 -2 9 -2 25 -2 10 -2 26 -2 11 -2 27 -2 12 -2 28 -1 _l 13 -2 29 14. -2 30 -1 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)

./ ,

Pag 2 25 .

.)

)

AVERAGE DAILY UNIT POWER LEVEL j J

DOCKET NO. 50-260 Unit Two DATE 6-1-89' I

COMPLETED BY S, A. Ratliff l TELEPHONE (2051729-2937 MONTH MAY 1989 4

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVFL (MWe-Net) (MWe-Net) 1 -3 17 -3 2 -3 18 -3 3 -3 19 -3 . l 4 -2 20 -3 ,

/

5 -4 21 -3 I 6 -5 22 -2 7 -5 23 -3 8 -5 24 -3 9 -5 25 -3 1 10 -5 26 -3 l  ;

11 -4 27 -3 l 12 -4 28 -3 *)

i 13 -4 29 -3 j l

14 , , _ .

-5 30 -2 ._

l i

15 -3 31 -3 16 -3 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.

1 (9/77)

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NUCLEAR PLAN 7 OPERATING STATISVICS BROWNS FERRY NUCLEAR PLANT PERIOD HOURS: 744.00 MONTH: MAY 1989 CENERATION UNIT 1 UNIT 2 UNIT 3 PLANT

1. Average Hourly Gross Load, kW

2. Maxinun Hour Net Generation, MWh 0.00 0.00 0.00 0.00

3. Core Thermal Energy Gen, GWD(t)2 0.00 0.00 0.00 0

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

5. Gross Electrical Gen., MWH 0.00 0.00 0.00 0.00

6. Station Use, MWH 5040.00 2416.00 1415.00 8871.00

7. Net Electrical Gen., MWH -5040.00 -2416.00 1415.00 8871.00

8. Station Use, Percent

9. Accum. Core Avg. Exposure, MWD / Ton 1 0.00 0.00 0.00 0.00

10. CTEG This Month, 10(6) btu 0.00 0.00 0.00 0.00

11. SGTEG This Month, 10(6) btu NA NA NA NA 12.

FACTORS & USE

13. Hours Reactor Was Critical 0.00 0.00 0.00 0.00

14. Unit Use, Hours-Min. 0.00 0.00 0.00 0.00

15. Capacity Factor, Percent 0.00% 0.00% 0.00% 0.00%

16. Turbine Avell. Factor, Percent 0.00% 0.00% 0.00% 0.00%

17. Generator Avail. Factor, Percent 0.00% 0.00% 0.00% 0.00%

18. Turbogen. Avail. Factor, Percent 0.00% 0.00% 0.00% 0.00%

19. Reactor Avail. Factor, Percent 0.00% 0.00% 0.00% 0.00%

20. Unit Avall. Factor, Percent 0.00% 0.00% 0.00% 0.00%

21. Turbine Startups 0.03 0.00 0.00 0.00

22. Reactor Cold Startups 0.00 0.00 0.00 0.00 ,

23. ,

FFFICIENCY

24. Gross Heat Rate, Btu /kWh

25. Net Heat Rate, Bru/kWh 0.00 0.00 0.00 0.00 26.

27.

TEMP & PRESS

28. Throttle Pressure,psig 0.00 0.00 0.00

29. Throttle Temperature, F 0.00 00 0.00

30. Exhaust Pressure, InHg Abs. 0.00 0.00 0.00

31. Intake .later Teniperature, r 0.00 0.00 0.00 32.

FLOWS

33. Main Feedwater, M lb/hr 0.00 ' O.00 0.00 34 35.

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37. Full Power Capacity, EFPD (3) (4) (4) (4)

38. Accun. Cycle Full Power Days, EFPD (3) (4) (4) (4)

39. Oil Fired for Generation, Gallons 59306.00

40. Oil Heating value, btu / Gal. 139200.00

41. Diesel Generation, MWh 84.00 42.

STATION DATA Max. Hour Wet Gen. Max. Day Net Gen. Load MWh Time Date MWh Date Factor, %

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v e e T t U G D 7!f llb1, l . , '

e Pags 34 REACTOR POWER PERCENT MAY 1989 UNIT 1 PERCENT l 100-90 .

Bu -

70 -

80 ADMINISTRATIVE HDLD 50 -

40 .

3D -

20 -

10 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 15.17 18 is 20 21 22 23 24 25 26 27 28 2S 30 31 i

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 f t 1213141516171B 19 20 2122 23 24 25 26 27 28 29 30 31 l

l UNIT 3 PmCEm 100 -

J 90 -

BC -

70 -

60 -

. i ADMINISTRATIVE HOLD 50 .

)

40 -

30 -

l 20 - '

10 -

l 0 i 1 2 3 4 5 6 7 8 9 10 ii 1213141516171819 20 2122 23 24 25 26 27 2B 29 30 31 l

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9

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- ' i

) s.

i

', CHEMISTRY

SUMMARY

i 1 j MAY 1989 1 Primary Coolant Chemistry

}

l Unit 1 i ,

The conductivity of the reactor coolant remained within technical i l

specification ar.d fuel warranty limits during the month. Chloride

concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits durir.g the month. This calendar year, the technical specification and fuel warranty limits for if l ,' . conductivity and chloride have not been exceeded. 1 M  !

I Unit 2 I 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 i i

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

conductivity and chloride have not been exceeded. ,

I j Unit 3 1 1

i The conductivity of the reactor coolant remained within technical l

! 1 i 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  ;

I conductivity and chloride have not been exceeded.

I Abnormal Releases )

l l

None i l

ii

!f a

Page 36 * -

PRIMARY COOLANT CHEMISTRY MAY 1989 Parameter Unit _1 Unit 2 Unit 3

1. Gross Radioactivity

a. Crud (filter) (uci/ml)

High N/A N/A N/A low N/A N/A N/A Average N/A N/A N/A

b. Filtrat.(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. 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/ml)

High 3.70E-5 3.07E-5 1.26E-4 Low 3.50E-5 2.86E-5 1.16E-4 Average .?, . 60E-5 2.92E-5 1.23E-4

4. Iodine-131 (pC1/ml)

High <9. 31 E-7 <8.05E-7 <3.57E-7 Low <3.97E-7 <4.01E-7 <1.64E-7 -

Average N/A N/A N/A

5. Iodine-131: Iodine-133 Ratio High N, A N/A N/A Low N/A N/A N/A Average N/A N/A N/A

, Page 37 PRIMARY COOLANT CHEMISTRY (Continued) l l

Pa rameter Unit 1 Unit 2 Unit 3 l 6. Chloride (pob) l l High 2 4.1 <2 l Low <2 <2 <2 Average 2 2.2 NA

7. Sulfate (oob)

High <2 3.2 4 Low <2 <2 <2 i Average NA 2.3 2.1

8. DH @ 25'C High 7.5 6.3 7.3 Low 6.3 5.6 6.4 Average 6.7 5.9 6.7

9. Conductivity (pmho/cm@25'ql High 0.42 1.02 0.26 Low 0.19 0.83 0.088 Average 0.30 0.92 0.16 1

i <='

i Page 38 ENVIRONMENTAL REPORT MAY 1989 The ambient upstream river temperature (24-hour average) ranged from 67.2*F (May 14) to 76.9'F (May 31) with an average of 70.5'F. The downstream temperature varied between 66.9'F (May 15) to 77.0*F (May 31) with an average of 70.2*F. The largest temperature change occuring on May 24 and 25 was 0.8'F with a monthly average change of -0.l'F.

Chlorination of the plant's Emergency Equipment Cooling Water Systems was initiated on May 19, 1989. It was triggered by the appearance of juvenile clams in the water column.

The sedimentation pond is still not in service pending repairs.

The stabilization pond (Lago sp) had a maximum flow of 85,968 gallons was recorded for May 4. The averare flow was 38,899 gallons per day. The maximum BOD, and TSS were 22 (May 2) and 32 (May 31). The averages for the 800, and TSS were 20 and 25 parts per million, respectively.

1416m/p.4

)

l

.. . - 4 e ,

.~ Paga 39 l AIRBORNE RELEASES (1').

MAY 198,9

(IN I T ' fHIS MONTH' i BUMMATION OF ALL RELEASES ------- -- - - ~ ~ ~ ~ - -

.i. FISSION AND ACTIVATION GASES

1. TOTAL RELEASE C1 .< 1 18E 02'

2. AVERAGE RELEASE RATE FOR PERIOD . llCI/SEC < '4.G9E 01-~

I

% 0.00li-01

3. PERCENT OF TECH. SPEC. LIMIT (0.15 CI/SEC)

3. IODINES ,

1. TOTAL IODINE - 131 CI < 2 91E 2. AVERAGE RELEASE RATE FOR PERIOD tit:I/SEC < 1.20E-04 i

3. PERCENT.OF TECH. SPEC. LIMIT (2 19 tlCI/SEC)  % 0.00E-01 f

. PARTICllLATES ,

1. PARTICULATE WITH HALF-LIFES > OR = TO H' DAYS 'CI .

5 30E-05

2. AVERAGE RELEASE RATE FOR PERIOD t!CI/SEC

2.19E .

3. PERCENT OF TECH. SPEC. 1.1MIT(2.19 UCI/SEC)  % 1 00E-03

4. GROSS ALPHA RADI0 ACTIVITY ,

CI 2 84E-07

. TRITIUM I 1. TOTAL RELEASE CI 6.531.-03

2. AVERAGE RELEASE RATE FOR PERIOD tlCI/SEC 2.70E i

3. PERCENT OF TECH. SPEC. LIMIT (2.19 tlCI/SEC)  % 1.23E-01 l i

4. GR0tlHD LEVEL RELEASE CI 6'.53E-03'  ;

5. ELEVATED RELEASE CI* < 5.17E-04

1) REPORTING PERIOD 28 DAYS <

1

.i l

40

- - .-._.._.._._..-_____.m_i-.____

Page 40 AIRhiORNE REL. EASES (CONTINtJED)

MAY 1989 LEVATED RELEASES

. FISSION GASES UNIT THIS HUN'l H KR-85M CI < 9 93E-02 KR-85 CI < 4.92E 01 KR-87 CI < 2.65F-01 KR-88 CI < 3 07E-01 XE-133 ,_

CI < 2.31E-01.

XE-135M CI < 5.00E-01 XE-135 CI < 1.10E- 01 XE-138 CI < 1.02E 00 OTHERS(SPECIFY) '

______ ~...

.= - -

TOTAL FOR PERIOD CI < 5.17E 01

. 10 DINES I-131 .

CI < H . 99E- 06 I-133 CI < 3.2HE-05 -

I-135 CI < 2 95E-02 TOTAL FOR PERIOD CI < 2.90E-02 N*

3- sW s

. mmrrv%ena-.e __.

-e.

x . ,

Pag 2 41 .cJ

• AIRBORHE RELEASES iCONTINUED) .

MAY' .1989 I

LEVATED RELEASES UNIT THIS HONTH

. PARTICULATE ________ _________.

.< 2.3 tie-07~-

~

CI SR-89 CI- < 9 67E-08 1 SR-90'  !

C1 < 5 57E-06 CS-134 CS-137 CI < 1.2.4E-05 BA-140 ,.

CI; < 3.12E-05 LA-140 CI <.2.26E-05 i

OTHERS(SPECIFY) <

TOTAL FOR PERIOD l

CI < 7.20E-05 i

3. TRITIUM CIL <-5 1/E-04 -

q O

l l

I i

i l

I 8

- d

• 's P L ,,

4 ,-

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+.i'

' * ,f d

i m ,

-al bj ~ Cr .. i I e.

b'.. i; g ,

. w; .ju , e

e

- s o :-

e Paga 42:

AIRBORNE -. RELE ASES -( CON 1 int)LD ) '

--__------------- g MAY- 1989 -

i GROUND RELEASES 1 ._-------------

l A.. FISSION GASES tlNIT. 'THIS HONTH -

i .-------- ----------

KR-85M CI < 1.42E 01-KR-85 CI < 4 33E 01 KR-87 01 < 4.34E-01 KR-88 CI- < 4.32E-01 XE-133 __

CI- .<'3.6YE-01

'XE-135M CI- < 5.14E XE-135 CI- < 1.' 8 4 E- 01 XE-138 CI- < 1'.09E 00 0THERS(SPECIFY)

---

's TOTAL FOR PERIOD CI  :< 4.65E 01

3. 10 DINES 1

I-131 Cf. < 2 82E- 04 4

~

I-133 CI < a,92g-04 W i

1 I-135 C1 < 1 14E 00 )

i 1

TOTAL FOR PERIOD  !

l

---

C7 < 1.14E 00 ]

i m'-

. i .- _ .;

I 4

4 I

h .,

'l

~ ~ ,f' ,

'Pago 43' 1

AIRBORHE RELEASES (CONTINUED) l t

MAY 1989 ~{

- -1 j

- j 3ROUND REL. EASES.

1 UNIT THIS MONTH I

.: . PARTICLILATES -------- ... . . .... . - - l

^

<'3 88E-04 CT SR-89 SR-90 'CI < 1.32E-06 i

CS-134 CI- < 1 27E-04 CS-137 CI , - < 3.10E-04 C1 < 3 41E-04 BA-140 . , _

LA-140 'CI . < 4./3E-04 OTHERS(SPECIFY)

CD-60 -

CI 5.30E-05 .

TOTAL FOR PERIOD

---

CI: 5 30E .C ,

3 .

D. TRITIUM CI . , 1 .

t4.53F-03 3-I-

' i a >

l'; i it.

a: .

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. <  ! , j

~ .

Page 44 .

BROUNS FERRY NilCl. EAR Pl.AN'i

• M O H f H l.Y R E P O R T C A L. C llt.A T I O N S LIOUID RELEASES -

MAY 1989 RADI0 ACTIVE I.10lllD EFFl.llENTS

1. OROSS RADI0 ACTIVITY llNITS CURIES 1. 2 VE -O'/

a) TOTAL RELEASE b) AVERADE DIL.llrED CONCEHrRATION REl. EASED llc I/HL. V 74E-10

)  % V . 761:-01 c) PERCENT OF APPL.ICABLE LIMIT ( it?-7 llCI/ l.

~~

2. TRI TIllM a) TOTAL REl. EASE CURIE!! 4.01E-02 b) AVERAGE DIL.llTED CONCENTRATE 0H REl. EASED llCI /Hl. 4 . : IGE- 09 c) PERCENT OF APPL.ICABl.E L1 HIT (3E-03 UCI/Hl.)  % 1.I 21! -0 4

~.

(1)

DISSOL.VED HOBl.E GASES 3.

a) TOTAL RELEASE CllRIE li < 6 011!-04 llCI/HL < 4.iUF-11 b) AVERADE DILUTED CONCENTRATION HEL. EASED c) PERCENT OF APPLICABLE I.IHIT (2E-04 1101/66.)  % < 7 2HE- 05

4. OROSS AL.PHA RADIDACTIVI TY a) TOTAL REl. EASE 'CilRIES 2. 77h- 05 b) AVERAliE DIlllTED CONCENTRATIGH REl.FASED tlCI /HL. 2.10E-12 l

5. VOLllME OF LIQUID WASTE TO DISCHARGh CANAL. LITERS 3. 6Vli 06 I

,1

.s..

6. VOLUME OF DILUTION WATER I. I T A Ril 1.32E 10 (1) INCLUDES XE-133, XE-135, AND OTHERS 4 .t'

', s

• P:ga 45. )

BROWHS FERRY HtlCt. EAR Pl. ANT i MONTHl.Y REPORT cal.Ctll. A' LIONS LIf1tlID itEl. EASES MAY 1989

I, ISOTOPES REL.6ASED tlNTTS

- - ~ ~ - -

CI ,

1 1

CR-52

< 1 87E -03 MH-54 1 03E-Oh CO-58 < 2.23E-04 FE-59 < 5 1 M. -0 4 CO-60 __

J.35E-03 ZN-65 < 6 73F.~04 NB-95 < 2.22E-04 ZR-95 < 4.00E-04 MOTC -99M < 1.64E-04 (

< '/ . 4t;E-04 I-131 XE 133 < 4.65E-04 CS-134 1. 331: ~ 03 XE-135 . < 1,3/g.04 .

CS-137 8 17h-03 B A -140

< g.90E-04 ,{

j LA-140 < 1.77g-04 l .CE-141 < 2.81E-04 ,

SR-89 < 1.0Hh-04 SR-90 < 3 48E-05

__ : ___~___~_:-.

?

+

Paga.46 *I

- BROWNS FERRY NUCl.l~AR Pl. ANT MONTHl.Y REPORT CALCtlt.ATIONS:

i LIRU1D REl.I AliES MAY l'/89 '  ;

i OTHERS- UNITS i

..___ 1

. CI  !

.! 4 l

CO-57 1 07E-06 l 7,87E-05 CE-144 3 FE-55 - < V.56E-04 1

,1 E

I

' eme 1

e e

e

• t-=

CI

)

i

.s .

k

-\

l

• BROWNS FERRY HilCLEAR Pl. ANT Pags 47 -l i

- MONTHLY REPORf CAlt:llLATIONS )

LIDUID RELLASES )

MAY- 1989.

l W

, 1 J

9304.3 gal.i.ONS LAllNDRY DRAIN VOLUME RELEASED: GAlt.ONS V454i9.6 FLOOR DRAIN VultlHE RELEASEDi 0.0 GA1.1.ONH-WAS1E SAMPLE TAWK VOLtlME RELEASED! 0.0 HALLONS -l DISTILL. ATE TANK VOLtlHE RELEASEDt 00 HAI.I.ONS l LOCATION OTHER THAN RADWAF,1E VOI.llHE RELEA8EDt i TOTAL VOL.UME RELEASED TO THE RIVER: 974763 8 HALL (INS Ht,nriEST BATCH AC11VITY RELEASED FOR HONTHf 1. HOE-ov tit:I /Hl. A/li 320 HINilTES LONGEST RELEASE TIME FOR HUNTH:

121 HINUTES GHORTEST RELEASE TIME FOR MONTH: HINUTES-TOTAL TIME OF RELEASES FOR MONTH:

8718 AVERAGE TIME FOR BATCH Rf:1. EASES 242 M TNil1ES x.: -

NUMBER OF BATCHES RELEASED! 34 NUMBER OF ADMINIS1RATIVE LIMIT VIOLATIONHf 0 ,

' NUMBER OF TECHNICAL SPECIFICA110N VIOLATIONS! 0

/

J i

~~. . l 5 t i,

e f

I ,.

'f% ,$ g

Page 48 s e

RESIN USAGE REPORT MAY 1989 RESIN CONSUMED (CU.FT.)

% of Total Bead POWDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 43.6 0 197 0 1 0 198 Waste Demineralized 0 0 0 0 0 0 0 Waste Filter 40.1 0 176 0 6 0 182 Fuel Pool Demins 1.1 0 5 0 0 0 5 Reactor Water Cleanup Unit 1 0.7 0 3 0 0 0 3 Unit 2 1.3 0 6 0 0 0 6 Unit 3 0 0 0 0 0 0 0 Cond. Demins.

Unit 1 0 0 0 0 0 0 0 Unit 2 13.2 0 60 0 0 0 60 Unit 3 0 0 0 0 0 0 0 To,tals 100 0 447 0 7 0 454

. +

g Page 4 9 FUEL CLADDING INTEGRITY PARAMETERS MAY 1989 Unit 1 Reactor Water Iodines (pci/sec)

Date I-131 I-132 1-133 I-134 _ I-135 Unit in Outage Fission Gases at Discharae of SJAE (pci/sec)

Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85 Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (pci/sec) ,

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

Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85 Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (pci/sec) -

Date I-1 31 J-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (pci/sec)

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

~ . ,

e

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Page 51 TESTING

SUMMARY

MAY 1989 Surveillance Testing Unit 0 A total of 171 surveillance tests were completed using 46 different test

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I instructions.

Unit 1 A total of 78 surveillance tests were completed or. mit 1 using 23 different test instructions. ,

Unit 2 l A total of 163 surveillance tests were completed on unit 2 using 69 different test instructions.

Unit 3 A total of 79 surveillance tests were completed on unit 3 using 21 different test instructions.

P g3 52 ~ ,

TESTING

SUMMARY

1 (CONTINUED) l j

MAY 1989 l

Channes. Tests. and Erceriments Reauirina Authorization From the NRC Pursuant '

to 10 CFR 50.59(a)

There was one revision for units 1, 2, and 3 technical specifications.

1. Transmittal #89-10 to correct illedgable stamped dates.

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Channes. Tests. and Experiments not Reauiring Authorization from N7C Pursuant j to 10 CFR 50.59(a)

There were ten special tests completed for this month, ST 88-01

Description:

Radwaste Disposal System Representative Sample Determination,.

ST 88-21

Description:

Diesel Generator "A" Governor Calibration.

ST 88-22

Description:

Diesel Generator "B" Governor and Voltage' Regulator Calibration.

ST 88-23

Description:

Diesel Generator "C" Governor Calibration.-

ST 88-24

Description:

Diesel Generator "D" Governor Calibration.

ST 88-27

Description:

Diesel Generator "3A" Governor Calibration.

ST 88-28

Description:

Diesel Generator "3B" Governor Calibration.

ST 88-29

Description:

Diesel Generator "3C" Governor Calibration.

ST 88-30

Description:

Diesel Generator "3D" Governor. Calibration.

I ST 89-01

Description:

Control Bay Chilled Water Pump Test.

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• - Pag 3 53

o. .

REACTOR VESSEL FATIGUE USAGE EVALUATION MAY 1989 The cumu1*ative usage factors for the reactor vessel are as follows:.

Usmae Factor Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure stude 0.24204 0.17629 0.14360 1'

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Pag 2 54- .!

I CHANGES IN PROCEDURES MAY 1989 4 i

l There were 316 revisions to plant instructions during the month; 322 instructions were changed primarily for correction; and six revisions related to safe operation of the plant.  ;

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t I

PT.ATf INSTRUCTION REVISIONS l l

MAY 1989 i I

Catenorv Instructip.n Reason fir Recuest Change in response SDSP-2.1 Site Procedures Implement source document, to LER, IE Bulletin, and Instructions NQAM III, Section 1.1 and l NRC Inspection Report, reflect major. revision to I OPQA SDSP 7.4 i

SDSP-2.7 Periodic Two Superseded-by SDSP7.4 I Year Review of Site Instructions

-t SDSP-2.11 Implementation Reflect major revision to and Change of Site SDSP-7 4 for' procedure review.

Procedures and Instructions l'

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. Page 55 ,

PLANT INSTRUCTION REVISIONS (Continued)

MAY 1989 Category Instruction Reason for Reauest Change in response SDSP-2.14 Surveillance Procedure superseded by to LER, IE Bulletin, Instruction Evaluation SDSP-7.4.

NRC Inspection Report, OPQA SDSP-7.4 Procedure Plant Manager direction Review to develop a comprehensive procedure review checklist, and incorporate industry standards for procedure review.

l SDSP-2.11 Implemenattion Reflect major revision and Change of Site to SDSP-7.4 for procedure Procedure and Instructions review.

SDSP-2.14 Surveillance Procedure superseded by Instruction Evaluation SDSP-7.4.

SDSP-7.4 Procedure Plant Manager direction Review to develop a comprehensive procedure review checklist, and incorporate industry standards for procedure review.

SDSP-17.2 Post Change responsibility for Modification Test Post Modification test program, streamline review of procedures by using technical review per SDSP-7.4. -

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1 CHANGES IN PLANT ORGANIZATION- '

1 1

MAY 1989 l 1

There was one change in plant staff for those positions designated as key

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supervisory positions for the month. It was'as follows:

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1 (1). John M. Corey, Radiological Control Superintendent.

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1 Pzgs 57 "3 ,-

i ACC1 DENTS MAY 1989 I

i There was one loss-of-time accident during.the month. It was as follows:  :

(1) 5/22/89 MODS Steam Fitter, had a contusion to his back when an  ;

oscillating fan fell onto his back. is i

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