Text

Monthly Operating Repts for Apr 1989 for Browns Ferry Nuclear Plant Units 1,2 & 3
	ML20244A947
Person / Time
Site:	Browns Ferry
Issue date:	04/30/1989
From:	Campbell G, Ratliff S; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 8906120207
	Download: ML20244A947 (69)
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TENNESSEE-VALLEY AUTHORITY

-Browns Ferry Nuclear Plant L

Post Office Box 2000-9 Decatur,fAlabama ' 35609-2000' L'

- MAY 3 0 1989-l p

'U.S. Nuclear Regulatory Commission r

ATTN: ' Document Control Desk Office of Nuclear = Reactor Regulation-

' Washington, D.C.. 20555

-Attention:. 0ffice 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 - April 1989

' Enclosed is the April 1989 Monthly Operating Report to NRC for Browns Ferry'

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

-Very truly yours,

' TENNESSEE VALLEY AUTHORITY WA

[GuyG. Campbell p

Plant Manager Enclosure ec: INPO-Records Center Mr. B. D. Liaw, Director Institute of Nuclear Power Operations TVA Projects Division Suite 1500

-One White Flint, North 1100 Circle 75. Parkway 11555 Rockville Pike Atlanta, Georgia 30389 Rockville, Maryland 20852 Regional Administration NRC Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant Office of Inspection and Enforcement Route 12, Box 637 Region II.

Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 1

Mr. Ted Marston, Director Electric Power Research Institute P..O. Box 10412 Palo Alto, California 94304 8906i20207 890430

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PDR ADOCK 05000259 4

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R PDC

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An Equal Opportunity Employer

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MONTHLY OPERATING. REPORT BROWNS FERRY-NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY APRIL 1989

" Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND.DPR-68 Submitted by:

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/~ Guy G. Campbell Plant Manager

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p TABLE OF CONTENTS ~

PART I.:

OPERATIONAL'SUEMARY A.

'SignificantLOperational Events Summary........................'....1 B.

Refueling Information............................................

2 C.

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

7 D.:

Issuance ' of Special-Reports - Suar.ary........~............ '.......... 8 :

.E.

Licensee Event Reports Summary................................... 9-F.-

Offsite. Dose Calculation Manual Changes......................... 13 G..

'Radwaste Summary................................................ 14

.1..

Total volume of solid waste shipped offsite U

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

'3.-

Gross curie activity

14.. Dates the material was shipped and the'dispo.ial 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

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awaiting shipment PART II.

0PERATING STATISTICS A.

'NRC Reports Operating Data Report....................................... 23

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'2.

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

-3.

Unit Shutdowns and Power Reductions......................... 29 B.

-TVA' Reports

-1.

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

32 2.

Unit Outage and Availability Data........................... 33 3.

Reactor Histogram (Reactor Power Percent)................... 36 y,

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PART III. OTHER REPORTS A.

Chemistry Summary 1.

Primary Coolant Cher.is try.................................. 3 8 2.

Environmental Technical Specification Requirements.......... 41 3.

Airborne Releases........................................... 42 4.

Liquid Releases............................................. 47 5.

Resin Usage Report.............

5...........................

51 6.

Fuel Cladding Integrity Parameters..........................

52 7.

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

53 B.

Testing Summary................................................. 54 i

C.

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

56 D.

Change in Procedures............................................ 57 E.

Plant Instruction Revisions.....................................

57 F.

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

58 G.

Accidents....................................................... 59 I

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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 q

ASOS Assistant Shift Operations Supervisor-

ATWS.

Anticipated Transient-Without Scram i

AUO Assistant. Unit Operator CFEL?

Browns. Ferry Equipment-List CFM Browns Ferry. Nuclear ~ Plant-CFMPP Browns'Farry Nuclear Performance Plan BOD.

Biochemical. Oxygen Demand

.BWR

Boiling. Water Reactor CAQ(R)L Conditions Adverse to Quality (Report)

' CAR Corrective. Action' Report ECCB

-Change Control. Board CCD Configuration Control Drawing.

-CCTS.

Corporate Commitment-Tracking System CFR.

Code of Federal Regulations

.CML

. Component Master List 4 CIP

Chemistry Improvement Plan CNPP.

Corporate l 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 FQ-Environment 1' Qualification EQDP Environmental Qualification Documentation Package EQE-Earthquake Engineering EQP Environmental Qualification Project

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ACRONYMS /AMREVIATIONSL(Continued) 4 y

-ER:

y engineering; Report J

'ERCWi'

' Essential Raw Cooling Water;

]

~ ESF.

Engineered. Safety Feature.

s FCR'

' Field Change Request:

FMEA Failure Modes,and Effects; Analysis FSAR Final' Safety Analysis Report.

U FW Teodwater, GE General Electric GET-General: Employee. Training -

4 GPM-

-Gallons per minute.

c'

.GOI General Operating' Instruction

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HPCI.

'High. Pressure Coolant Injection

.HVAC:

Heating Ventilation and Air. Conditioning-IE

. Inspection,and' Enforcement'(NRC)

SIG Inspector GeneralE IGSCCt Intergranular Stress-Corrosion Cracking' 1,

IHSIL Induction Heating' Stress? Improvement:

F

<INPO.

Institute of. Nuclear: Power Operations L

IRIS Input Requirements Information' System-

'ISEGl Independent Safety' Engineering 1 Group.

'p

ISI, Inservice Inspection-

'ITC.

Immediate. Temporary-Change >

'JTG.

Joint TestLGroup LCOL' LLimiting Conditions for-Operation' LDCRs Local 4 Design Change Request-

.LER.

Licensee Event Report LOCA LossJof Coolant Accident LOP Loss of Power.

HMAI Modification Addition Instruction.

1MCC.

Motor Control Center MCEL' Master Components. Electrical List MMI Mechanical Maintenance Instruction MNt Megawatts thermal 1

MOV

. Motor. Operated Valve MR Maintenance Request MSIV:

Main Steam Isolation Valve MWe-Megawatts electrical

'NCR Nonconformance. Report NEL 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 Security Service-NT:

Nuclear Training NUMARC Nuclear Utility Management and Resources Countil

'NUREG Nuclear Regulatory Documentary

-OL Operating Instruction OI Operating Licensee ONP Office of Nuclear Power J

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' ACRONYMS / ABBREVIATIONS (Continued)

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PASS Post Accident Sampling System i

PCIS-

' Primary Containment. Isolation' System PD_

- Position Description p

'PM' PreventiveLMaintenance

-PMT Post Modification Test?

-PORC:

Plant Operations Rcview Committee-

>PSIl Preservice-Inspection-iPSS; Potentially Safety Significant QA-LQuality Assurance-.

1 QC.

Quality; Control;

-QMDS Qualification Maintenance' Data Sheets iRC

. Radiological Control?

RCIC

- Reactor. core Isolation Cooling.

?

' REP:

RadiologicaljEmergency Plan;

'RETS

Radiological! Effluent. Technical Specification-RHR.-

' Residual;. Heat Removal 3,

.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.

F 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

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 l

SCMMARY I

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- SIGNIFICANT OPERATIONAL EVENTS'

SUMMARY

' APRIL 1989-Unit 1.

04/01/89.

- 0001 Unit remains on administrative hold to resolve various' j

TVA and NRC concerns.

04/30/89 2400-Unit remains on administrative hold to resolve various.

TVA and NRC concerns.

Unit'2 04/01/89 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.

- 04/30/89

- 2400 Unit remains on administrative hold to resolve various.

TVA and NRC concerns. Modification and Operations &

Maintenance work continues to support restart in September 1989.

Unit 3 04/01/89-0001 Unit' remains on administrative hold to-resolve various TVA and NRC concerns.

04/30/89 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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'Pzg2 2 REFUELING-INFORMATION APRIL 1989 I

Unit 1

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Name of facility Browns Ferry Nuclear Plant 2.

Scheduled date for next refueling shutdown N/A

.3.

' Scheduled date for restart following refueling l-N/A4 4.

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

BFN, cyc1c'7'startup has not'been scheduled at this time. When required, the cycle 7 reload licensing submittal will be made to support Technical Specification thermal limits for the core design and specific. fuel assembly types to be loaded.

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

5.

Scheduled date(s) for submitting proposed licensing action and supporting information

~N/A 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel' design, new operating.

procedures Cycle 7 final core design has not been developed at this time.

i 7.

The number of fuel assemblies (a) in the core and (b) in the spent-fuel 4

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 i

planned, in the number of fuel assemblies 3,471 h

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REFUELING INFORMATION; Unit 1 (Continued)'

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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 Since. fuel can be transferred between these two spent _ fuel'atorage' 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 b'e in.

cycle 13.)

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gn Pr.gs 4 REFUELIE0'INFORMATION APRIL 1989 Unit 2 1.

Name of facility Browns Ferry Nuclear Plant 2.

Scheduled date for next refueling shutdown N/A 3.

Scheduled.date for restart following refueling 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

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

Thir report documents 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.

1 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-240ll-P-A-8 dated May 1986, " General Electric Standard Application for Reactor Fuel," General Electric. This includes 212 twice-and thrice-burned assemblies which were inspected and reconstituted for cycle 6; 248 4

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 i

storage pool i

i (a) 764 (b) 1,444

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REFUELING INFORMATION Unit 2 (Continued)

'8.

The present licensed spent fuel pool storage capacity.and the size of any increase in licensed storage' capacity that has been requested or is planned,

~in the number of fuel assemblies I

3,'471 9.

The projected date'of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity 4

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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REFUELING INFORMATION

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APRIL 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 (a) 0 (b) 1,768 6.

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 discharge following the cycle 13 refueling in May 2006.

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N' MAIN STEAM RELIEF VALVE (MSRVs)

SUMMARY

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..;. - No MSRVs were challenged during the month.

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ISSUANCE OF SPECIAL REPORTS APRIL 1989 The following special reports are notices of violations issued for the month of April 1989.

260/89-08-01 _Punctional Test of Unit 2 Intermediate Range Monitor Rod Blocks / Scrams, were not followed resulting in the failure to remove jumpers that had been installed earlier during the performance of the surveillance instruction.

l This is a Severity Level IV Violation and is applicable to Unit 2.

259, 260 A weekly surveillance of the 250 volt DC power system batteries 89-08-02 conditions was not perfermed on time.

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

259, 260, Failure to properly establish an administrative procedure for 296/88-36-01 the control of equipment, in that OSIL 43 was being used to govern system status. control. As an OSIL, the procedure had not received PORC approval or other independent review.

This is a Severity Level IV Violation and is applicable to Units 1,2, and 3.

259,260, Failure to follow procedure SDSP-3.15 in that electrical 296/88-36-02 lineups on equipment clearances and system alignment checklists were being independently verified by individuals who had not received the required electrical training for performance of independent verification of electrical lineups.

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

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LICENSEE EVENT REPORT (s)

APRIL 1989 Description of Event LEE 1-88-038 FAILURE TO IDENTIFY AND MAINTAIN MINIMUM SET OF ELECTRICAL REV. 01 CALCULATIONS BY DESIGN RESULTS IN CONDITIONS THAT COULD DEGRADE PLANT PERFORMANCE On October 17, 1988, a review of open condition adverse to quality reports (CAQRs) was initiated using a more conservative reporting philosophy. This review was designed to ensure that all conditions as defined by 10 CFR 50.72 and 50.73 have been properly reported.

This review discovered the following condition that affected all three units. This condition was discovered with all three units shutdown and defueled.

1-89-005 PLANT TECHNICAL SPECIFICATIONS SURVEILLANCE RE0!TIREMENT EXCEEDED DUE TO A MISINTERPRETATION BY SUPERVISION RESPONSIBLE FOR PATROLLING FIREWATCHES On March 14, 1989, quality assurance personnel discovered that firewatch patrols had exceeded the hourly intervals set by the action statement for TS section 3.11.a.1.b.

This section states that "...a patrolling fire watch will be established to ensure that each protected zone or area with inoperable detectors is checked at intervals no greater than once each hour." This requirement was interpreted to mean that rounds of inspection areas were sufficient as long as the rounds were completed once per clock hour. This interpretation was incorrect and was the cause of the late firewatch.

Immediately upon notification of this condition, actions were taken by plant management to provide roving firewatch rounds at intervals of 45 minutes. Firewatch routes were reviewed to ensure the rounds could be completed within the time allotted.

1-89-007 UNPLANNED START OF DIESEL GENERATOR A BECAUSE OF UNCLEAR POST MAINTENANCE. TEST INSTRUCTION On March 5, 1989, a diesel generator common to units 1 and 2 was inadvertently started.

A post maintenance test (PMT was being performed on DG A following maintenance on the logic wiring. Following testing of annunciator prestart logic, alignments were being performed on the DG per the operating instruction. When the DG start logic was energized the DG unexpectedly started. This start occurred because the start failure relay in the DG start logic had not been reset after earlier logic testing. The root cause was that the (PMT) instruction was not clearly written, resulting in the sequence of actions for the PMT not being followed as intended. The DG was immediately stopped and the shift operations supervisor was notified. The DG alignments were stopped pending investigation into the event. The DG PMT was performed in the proper sequence. The PMTs for the other DGs have been revised to clarify the sequence of actions to be taken.

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, LICENSEE EVENT REPORT (s)

(Continued) 1-89-010 FAILURE TO PERFORM PRsvEnrivs MAINTENANCE ON A REACTOR' PROTECTION SYSTEM MOTOR GENERATOR SET CAUSES ENGINEERED SAFETY FEATURE

.ACTUATIONS_

On March 23, 1989, the unit I reactor protection system bus Ib was deenergized when the 1B1 and 1B2 circuit protectors tripped.

As a result, the following engineered safety features were actuated:. standby gas treatment, control' room emergency ventilation, refueling zone isolation, and primary containment isolations, and a half scram.

The output voltage of the IB rps motor generator (MG) was found to be slowly oscillating between 120 and 125 volts (circuit protector overvoltage trip is 124.5 +- 0.8 volts). This oscillation was caused by a dirty voltage adjustment potentiometer.

2-89-005 UNPLANNED SCRAM DURING LOGIC FUNCTIONAL TESTING CAUSED BY MISPLACED JUMPER On March 16, 1989, unit 2 received a full scram signal during the performance of.a rod block / scram functional test.

The scram signal occurred because a utility instrument technician momentarily paralleled logic circuits powered from non-synchronous power supplies while placing a jumper in the RPS logic. The instrument technician inadvertently contacted the adjacent terminal point while trying to place the second end of the jumper. This cleared-fuses in RPS channels A3 and B3 simulating trips of those channels thereby completing the scram logic.

l This event was initiated by a personnel error which was caused by

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human factors (ergonomic) inadequacies.

2-89-006 UNPLANNED ENGINEERED SAFETY FEATURE ACTUATIONS DUE TO LOSS OF REACTOR PROTECTION SYSTEM MOTOR / GENERATOR OUTPUT CAUSED BY PERSONNEL STANDING ON BREAKER CABINET On March 31,1989 unit 2 RPS bus 2B was deenergized, resulting in the following engineered safety feature actuations:

standby gas treatment, control room emergency ventilation, refuel zone isolation, primary containment isolations and a half scram.

This event was initiated by personnel errors.

2-89-007 CABLE DETERIORATION CAUSES INOPERABILITY OF NEUTRON MONITORING SYSTEM On March 17, 1989, viring in the unit 2 neutron monitoring system IRM and SRM was found to be brittle and cracked. The shift operations supervisor declared the affected channel of neutron l

monitoring inoperable. The other channel of neutron monitoring was inspected and found to contain wiring in the same condition.

The reactor mode switch was locked in shutdown to comply with TS.

All work in the reactor cavity was stopped.

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2-89 008' ELECTRICAL FAULT ON TRANSFORMER CAUSES ENGINEERED SAFETY FEATURE ACTUATIONS On March 9,[1989, an.ESFfactuationLoccurred due to'an electrical:

-fault-on the-unit station service. transformer 28.

The fault led ~

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to the loss of shutdown bus l2 (the' alternate: feed'wasLtagged out

for maintenance). ;As a result, 4kV. shutdown boards'C and;DS sensed the undervoltage condition and automatically: started

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. diesel generators C and.D.

Emergencyfequipment cooling water:

pumps Clland.D3 also. auto started per design due to:the. diesel; generator: starts.

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'2 89 010 UNPLtlENED ENGINEERED SAFETY FEATURE ACTUATIONS CAUSED BY A

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0 SPURIOUS RADIATION MONITOR SPIKE L

On March 23, 1989, a' unit 2 radiation monitor'on the. refuel zone ventilation; exhaust (2-RM-90-140), experienced'a downscale.. spike immediately.followed by an upscale spike.g The upscale. spike.

resulted in a Primary Containment Isolation System group 6 isolation,-refuel zone isolation ~, Standby Gas Treatment and:

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Control! Room' Emergency; Ventilation initiation.

3-89-002-MISSED COMPENSATORY SAMPLING WHILE CONDUCTIVITY MONITOR WAS OUT OF SERVICE l

On' March 7, 1989, it was. discovered the. compensatory reactor coolant' water sampling had not been performed with a continuous

conductivity monitor inoperable as required by TS.

On February 12,:1989 while performing surveillance. instruction 3-SI-4.6.b.1.a-c, Reactor coolant' Chemistry,-it was discovered ~

. that local. conductivity monitor 3-CIT-43--011 was-out of calibration. On March.6, 1989 the instrument mechanics removed the continuous conductivity monitor,from service for repair.

It-was not returned to service.until.21^ hours later on March 7, 1989. TS 4.6.b.1.c requires sampling every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> when the conductivity monitor is inoperable.

The cause of the event was attributed to procedural deficiencies and personnel error. SDSP 7.9 will be revised to require an-impact evaluation for any maintenance on TS equipment.

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. LICENSEE EVENT REPORT (s)

(Continued)

? 003:

LUNPLAMNED ENGINEERED SAFETY FEATURE ACTUATIONS CAUSED BY VOLTAGE 3

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' R RUENT ON ELECTRICAL DISTRIBUTION SYSTEM

.On March'7, 1989 unit 3 received isolations of PCIS (secondary

. containment),'a RPS. channel A half scram and' actuation of SGTS

.and CREV when the RPS circuit protectors.on.the power supply to' the 3A.RPS bus RPS momentarily tripped. The half scram and PCIS isolation signals were reset. Secondary containment ventilation,.

SBGT, CREV, RWCU, and other effected components were not~ reset-immediately pending an evaluation.. All systems were returned to normal on' March 8, 1989. Electrical maintenance then began the-performance of the preventive maintenance on the RPS MG set.

When the PM was completed, the-RPS MG' set was returned to service.

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.V OFFSITE DOSE CALCULATION MANUAL CHANGES

' APRIL 1989 C

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' No changes were made to the BFN Offsite Dose Calculation Manual during

.the month.'

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'RADWASTE

SUMMARY

APRIL 1989 d

The'radwaste' system performed as designed. Approximately:1.29E+06 gallons

- of waste' liquid were discharged containing approximately'1.45E-02 curies of p

activity.

l There were two spent resin shipments and one' trash shipment during' April. ~All shipments were.to Barnwell, South Carolina.

. There were no' trash-shipments made by the Scientific Ecology Group, (SEG),

radwaste broker / processor, containing BFN waste during April..

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Paga 15 2.

Solid Radioactive Waste April 1989 Dewatered Spent Resin Shipments (1)

Volume of condensate / waste (CWPS) resin shipped:

10.53 Cu.M.

(372.00 Cu.Ft.)

Total. curies shipped:

'9.3580 Volume of reactor cleanup (RWCU) resin shipped:

0.00 Cu.M.

(00.00 Cu.Ft.)

Total curies shipped:

0.0000 Date Shipped Disposal Facility Type gi Resin 04/07/89 BarnweLL, SC CWP5 04/25/89 Barnwell, SC CWP5 Dry Active Waste (1)

Number of drums shipped:

0 Volume:

0.00 Cu.M. (O Cu.Ft.)

Total curies shipped:

0 Number of boxes shipped: 11 Volume:

30.6 Cu.M. (1079 Cu.Ft.)

Total curies shipped:

0.2268 Date Shipped Disposal Facility Type of Packaoe 04/20/89 BarnwelL, SC Boxes Brokered shipments (SEG):

0 Volume:

O Cu.M. (O Cu.Ft.)

Total curies shipped:

0 Date Shipped Disposal Facility Type of Packaoe N/A N/A N/A (1) AlL shipments were by Sole-Use Vehicle

C e

_______m.

'_m__

e

~_

Pags:16-d a

1 y

't,

.A

.O ' ' -

. Solid Radioactive. Waste CContinued) j April 1989 Summary

. Type.

Shipped to.

. Packaged;on Gross Curie Estimated o f-Barnwell:

Site Awaiting

' Content.by GenerationEfor..

LWaste.

During Month-Shipment Type of Waste'

-Next Month COMPnCTED Drums; 0.

Cu.Ft. (2) 390 Cu.Ft.

0.00E-01 225 Cu.Ft. :(2)

Boxes 279.0 Cu.Ft. (2) 279 Cu.Ft.

9.40E-02 279 Cu.Ft. (23-

1 :

.UNCOMPACTED.

Drums' O

Cu.Ft. (2) 1020 Cu.Ft.

'O.00E-01 225 Cu.Ft. -(2)

' Boxes 800L.2 Cu.Ft.-(2) 808 Cu.Ft.

1.33E O1 i S 5 C'u. F t. (21 k

BROKERED 0

Cu Ft.

'O Cu.Ft.

0.00E+00 O'Cu.Ft.

RESIN' S CWP5 279 Cu.Ft. (1) 793-Cu.Ft. (3) 9.36E+00-465'Cu.Ft. (1)'

RWCU' O

Cu.Ft.. (1) 30 Cu.Ft..C3) 0.00E+00; S L Cu '. F t.. C 1 ) ~

,TO ALS 1491 Cu.Ft. (2)

.2497-Cu.Ft. (4) 9.58E+00 914"Cu.Ft. (4)-

Total volume of-waste shipped during the month:

1,491 Cu.Ft. (2)

~

' Total volume of waste shipped year-to-date:

5,527 Cu.Ft.

Unused 1989 burial. volume allocation at BarnwelL:

73,237 Cu.Ft.

(1)

Actual resin volume

.(2 )

Container burial volume (3)

Estimated volume in sc'Jarators (4)

Does not include resins i

u 1

1

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cy LIQUIDLRADWASTE

J. ;

APRIL 4

-1989

?

TOTAL. RIVER-. RELEASE P

'~.

PLOW RATE (SP80 DATA PLOTTED POR TIE PREVIOUS 12 MONTHS-TOTAL furt saar (CZ) 40

.'E.

' PLOW mit, fantal

HI 39.91

. LOW-30.73 30.

Avg-

-34,37-g

.' TOTAL '

MPL.FABF ff*T1

- 30.

MI

. O ' 04 '-

LOW 0.01:

AVS -

0.05 O FLONRATE Y.

S P kT. kV C

N

(

T6mout1HpuT faALal FILTER THROUGHPUTS S

A8TE' SALLONS X 10 HI.'O.18E+07-4 LOW 0.SOE+0S-AVS 0.13E+07 FLOOR DRAIN

'I-

HI 0.18E+07'

. LOW 0.79E+0S' x

-AVS 0.SSE+0S cf g'y sm' m;s, vx '

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/

f Mk g

y y

g MAY JUN JUL AUS-SEP OCT NOV OEC JAN FEB MAR--APR-COST OF OPERATION

"*' fu n - _

op ir f

g, WASTE HI 'O.84E+0S 90 -

wss s-LOW 0.30E+0S 80.

b'i

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AVS 0.3SE+0S-

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FLOOR DRAIN'.

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LOW 0.22E+0S

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kb h' f < -

'40 u

W LAUNDRY HI 0.37E+03 l'

30 W.

xi LOW 0.00E+00 30.

AVS 0.4SE+02 MAY JUN JUL AUS SEP OCT NOV OEC JAN FES MAR APR WASTE COLLECTOR SYSTEM LAUNDRY SYSTEM W

FLOOR DRAIN SYSTEM P

Paga 22 '

REACTOR POWER - MWT UNITS 1, 2, AND 3.

APRIL 1989 MWT.

aseo sooo

~

LMIT 1: OUTAGE lMIT 2: OUTAGE aooo LMIT 3: OUTAGE 1000 Soo o*%%%>*****R444%454##44&Q4444494

' m asistry Secti m DAYS TecMical Srvicer hane Ferry Ahwier Plu.t REACTOR WATER CONDUCTIVITY UNITS 1, 2 AND 3 APRIL 1989 us/cM CONDUCTIVITY 1.75 WIT 1 CONDUCTIVITY 1.25 WIT 2 g........................-__................___......____....

o.75 y

- C0feuCTIVITY 3

WIT 3 o

ADM MIT COLD SHUTDONN

~~~~

- - - - ^**&######4##44&O4944494 mesistry Sectim DAYS TecMical Srvicae Mnne Fery Atmler P1mt REACTOR WATER CHLORIDE UNITS 1,

2. AND 3 APRIL 1989 PPB ao m

WIT i is CH.0 RIDE to UNIT 2 4

CHLORIDE UNIT 3 5

ADMIN l

LIMIT 3

0

* * * * * * ^ * * # # # 4 4 4 # 4 # # 4 4 4 0 4 & # 4 5 9 4 ~~~~

l Genistry Sectim DAYS TecMical Servicae hane Ferry Ateler P1mt l

j 4

,g e

OPERATIXG STATISTICS I

='

4 Pega 23 a_

OPERATING DATA REPORT' DOCKET NO.

.50-259

'DATE

'5-1-89 COMPLETED BY S. A. Ratliff

^

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

1.

. Unit Name:

Browns Ferrv Unit One l

l 2.

Reporting Period:

APRIL 1989 l

l 3.

Licensed Thermal Power (MWt): 3293 l

l 4.

Nameplate Rating (Gross MWe):,1152 l

l 5.

Design Electrical Rating (Net MW3) 1065 l

l

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

l 7.

Maximum Dependable Capacity (Net MWe) 1065 l

8.

If Changes Occur in Capacity Ratings (Items Number 3 Through 7) $1nce 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 Per'od 719 2.879 155.647

12. Number of Hours Reactor Was Critical 0

0 59.521.38

13. Reactor Reserve Shutdown Hours 0

0 6.997.44

14. Hours Generator On-Line 0

0 L8.267.26

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

168.066.787

17. Gross Electrical Energy Generated (MWH) 0 0

55.398.130

18. Net Electrical Energy Generated (MWH)

-5.209

-19.436 53.479.295

19. Unit Service Factor 0

0 37.4 2D. Unit Availability Factor 0

0 37.4

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

32.3

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

32.3

23. Unit Forced Outage Rate 100 100 57.4

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

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)

- lIl g ;

' Pag 2[24 f

. OPERATING DATA REPORT.

+

. DOCKET NO. j 0-260 DATE J-1-89 R

COMPLETED BY ' 1, A. Ratliff TELEPHONE f!05) 729-2937

--OPERATING STATUS l Notes l

1; Unit Name:

Browns Ferry Unit Two l

l'

2. - Reporting Period:

APRIL 1989 l

l.

3..' Licensed Thermal Power (Wt): 3293 l

l 4

Nameplate Rating (Gross NWe): 1152 l

l-c 5.

Design Electrical Rating (Net MWe) 1065 l

l~

6., Maximum Dependable Capacity (Gross We) 1098.4 l

.l

- 7.

Maximum Dependable Capacity (Net MWe) 1065 1

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

N/A 9.

Power Level To Which Restricte', If Any (Net We):

N/A d

10. Reasons For Restrictions If Any:

N/A

-This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 719 2.879 150.534.00

12. Number of Hours Reactor Was Critical 0

0 55.860.03

13. Reactor Reserve Shutdown Hours 0'

O 14.200.44 0+

14. Hours Generator On-Line 0

0-54.338.36

15. Unit Reserve Shutdown Hours 0

0 0

= 16. Gross Thennal Energy Generated (WH) 0 0

153.245.167

17. Gross Electrical Energy Generated (MWH) 0 0

50.771.798-

18. Net Electrical Energy Generated (MWH)

-1.664

-8.290

'49.043.442

19. Unit Service Factor 0

0 36.1

20. Unit Availability Factor 0

0 36.1

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

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

30.6 l;

23.' Unit' Forced Outage Rate 100 100 57.9

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

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

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77) 1

+

l

-J_--_____-_________---_-

i

(

Pzga 25 OPERATING DATA REPORT DOCKET NO.

50-296 DATE 5-1-89 COMPLETED BY S. A. Ratliff TELEPHONE (205) 729-2937 OPERATING STATUS l Notes l

1.

Unit Name:

Browns Ferry Unit Three l

l 2.

Reporting Period:

APRIL. 1989 l

l 3.

Licensed Thermal Power (MWt): 3293 l

l 4.

Nameplate Rating (Gross MWe): 1152 l

l 5.

Design Electrical Rating (Net MWe) 1065 l

l 6.

Maximum Dependable Capecity (Gross MWe) 1098.4 l

l 7.

Maximum Dependable Capacity (Net MWe) 1065 1

1 8.

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

N/A 9.

Power Level To Which Restricted, If Any (Net MWe):

N/A

10. Reasons For Restrictions, If Any: _

N/A This Month Yr-to-Date Cumulative

11. Hours in' Reporting Period 719 2.879 132.959.00

12. Number of Hours Reactor Was Critical 0

0 45.306.08

13. Reactor Reserve Shutdown Hours 0

0 5.149.55

14. Hours Generator On-Line 0

0 44.194J76

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. Het Electrical Energy Generated (MWH)

-1.471

-6.494 41.893.593

19. Unit Service Factor 0

0 33.2

20. Unit Availability Factor 0

0 33.2

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

29.6

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

29.6

23. Unit Forced Outage Rate 100 100 62.0

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 l

COMMERCIAL OPERATION l

l (9/77) l l

m________.

[h y%*

, v-Paga 26' 7

AVERA,GE DAILY UNIT POWER LEVEL W~s ~^<

f

~ DOCKET NO.

50-259 Unit One DATE 5-1-89 COMPLETED BY 4 S. A Ratliff

..p TELEPHONE (2051729-2937 MONTH -APRIL 1989 lr DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1-17

-8 0',

2

-7 18

-7 3.

-7 19

-7

'4

-8 20

-7 5

-7' 21

-7

'-6'

-8 22

-7 7-

-7 23

-6 8"

-8 24

-7 9

-8

'25

-7

' 10 -

-7 26

-7 11-

-7 27

-7 12

-8 28

-7 13

-7 29

-7 14

-7 30

-8 15

-8' 31 16

-6 l

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) k= z.

y-.,

~;

[,s

' ?:

Is i

,' r '

t y.j

-Pega 27 O

AVERAGE DAILY UNIT POWER LEVEL DOCKET'NO..

'50-260

'M Unit-Two DATE-5-1-8'9 COMPLETED BY:

S. A. Ratliff--

TELEPHONE

'(2051729-2937-

, MONTH AERJL 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

. MWe-Net).

(

1

-2 17

-2

? 21

'2 18'

=-2~

e 3

-3 19~

' -3

.' 4 -

-2' 20

-2 5

-2

. 21 -

-2 6

-2 22

-3

'7'

-2 '

23.

-2 0

8

-2 24'

-2 9

-2

- 25

-2 10'

-3 26-

-2 11 27

-2 12

-3 28

-2

.13

-2 29

-3 14

-2 30

-2 15

-3 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.

(9/77)

-w__1_u_----.--.. _ _ _.. _ _ _ _ _ -.

' e ';

P5ga.-28L I.

AVERAGE DAILY UNIT _ POWER LEVEL!

nc DOCKET NO.?

50-296 Unit Three DATE.

5-1-89 COMPLETED BY

'S. A. Ratliff.

' TELEPHONE

~(205}729-2937-

{.

MONTH APRIL 1989 VC '

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

(MWe-Net).

J1.

-2

.17

-2 2

-2 18

-2

-.3 -

-2 19

-2 4

-2

.20

'2-

.5:

-2~

21

-2 6

-2 22

-2 7"

-2 23

-2'

'8-

-2 24

-2 9

-2 25

-2 10

-2 26

-2 11

-2 27

-2 '

12

-2 28

-2' 13

-2 29

-2 14

-2 30

-2 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.

(9/77)

A

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' NUCLEAR PLANT OPERATING STATISTICS.

r t

i nrnwn= verrv-Knir1.=v Pla nt.

719 Month April 19 L Period Hours ltem i

No.

Unit No.

j 1

Average Hourly Gross Load. kW 0

0 0

0 2

Maximum Hour Net Generation. MWh 0

0 0-0 3

Core Thermal Enerov Gen. GWD (t)2 0

0 0

0 4

Steam Gen: Thermal Energy Gen., GWD (t)2 NA NA NA NA 8

5 Gross Electrical Gen.. MWh 0

0 0

0 j

6 Station use, MWh 5,209 1,664 1,471 8.344 E

7 Net Electrical Gen., MWh

-5,209

-1,664

-1.471

-8.344 8

Station Use, Percent 0

0 0

0 1

0 0

0 0-9 Accum. Core Avg. Exposure. MWD / Ton

-10 CTEG This Month,106 BTU 0

0 0-0 11 SGTEG This Month,106 BTU NA NA NA NA 12 13 Hours Reactor Was Critical 0

0 0

0-14 Unit Use, Hours. Min.

0 0

15 Capacity Factor, Percent 0

0 0

0 t

3 16 Turbme Avail. Factor. Percent 0

0 0

0

.h 17 Generator Avail. Factor. Percent 0

0 0

0 e

18 Turbooen. Avail. Factor. Percent 0

0 0

0-19 Reacter Avait. factor. Percent 0

0 0

0 C

' 20 Unit Avail. Factor. Percegit 0

0 0

0 21 Turbine Stortuos 0

0 0

0 22

~ Reactor Cold Startuos 0

0 0-0

?3 g

24 Gross Heat Rate, Btu /kWh 0

0 0

0 5

25 Net Heat Rate, Btu /kWh 0

0 0

0 h

26 U

27 5

28 Throttle Pressure, psig 0

0 0

0

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0 0

0 c.

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0 0

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0 0

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0 0

0 y

34 35 36 37 Full Power Capacity, EFPD (3)

(4)

(4) 38 Accum. Cycle Full Power Days. EFPD (3)

(4)

-(4) l N

39 Oil Fired for Generation. Gallons 4.407 5

40 Oil Heatena Vatue. Btu / Gal.

139.000 50.4 41 Diesel Generation. MWh d?

Max. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date MWh Date Factor, %

s 43 0

0 0

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

5 2(t) indicates Thermal Energy.

3

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Page 36 REACTOR POWER PERCENT P

APRIL 1989

. UNIT 1-PERCENT 100 90 80 70 60 :

ADMINISTRATIVE HOLD 50

'4C 30

- 20 10 1.2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 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 101112131415161718192021222324252627282930 UNIT 3 l

PERCENT l

100 90 l

80 70

- 60 50 ADMINISTRATIVE HOLD 40 30

[

20 10 0

,J 1 2 3 4 5 6 7 8 9 10111213141516171B 19 20 2122 23 24 25 26 27 2B 29 30 i

l 1

4..

'.(.

s -

Pzgs'37

.s:

I

~4 This page intentionally left blank.

s

-9

4 1

4 OTHER REPORTS l

1 i

i

f V:rl

_P2g2 38 CHEMISTRY

SUMMARY

APRIL 1989

- Primary Coolant Chemistry Unit'1 The conductivity of.the reactor coolant' remained within technical-i:

specification and fuel warranty limits during the month.

Chloride; n

concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

Unit 2 The conductivity of the reactor coolant remained within technical' specification and fuel warranty limits during the month.

Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

Unit 3 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.

This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

Abnormal Releases None

_=_

_ _ _ _ _ _ - - _ _ = _ - -

i.

h Pegs 39' g

i PRIMARY COOLANT CHEMISTRY APRIL 1989 s

i Pa rameter Unit 1 Unit 2 Unit 3

.'l.

Gross Radioactivity l:

a.

Crud (filter) (pC1/ml)

High N/A N/A N/A low N/A N/A N/A Average N/A N/A N/A b.

Filtrate (pCi/ml)

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

2. Millipore Iron (Fe. ppb)

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

3. Tritium'(u i/ml) c High 3.73E-5,

3.05E-5 1.28E-4 Low 3.54E-5 2.70E-5 1.07E-4 Average 3.62E-5 2.91E-5 1.21E-4

4. Iodine-131 (pC1/ml)

High

<1.06E-6

<9.85E-7

<4.05E-7 Low

<5.39E-7

<5.17E-7

<l.84E-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

p.

- ' '7 9

..t LPega<40 g,,

s PRIMARY' COOLANT CHEMISTRY' (Continued)

Parameter Unit 1 Unit 2 Unit'3

6. Chloride (opb)

High

<10

<10 Low

'<2

<2

<2 Average NA-NA' NA

7. Sulfate (pob)

High

<10

<10 Low

<2-

<2

<2 Average NA NA NA

8. DH @ 25'C High 7.3 6.0 7.0 Low 5.9 5.7 5.7 Average 6.2 5.8' 6.0

9. Conductivity (pmho/cm@25'C)

High 0.18 0.93 0.57 Low 0.093 0.78 0.22 Average 0.12 0.87 0.42

, d.r

. ~..

7 7

.Piga'41/

r

.+-

ENVIRONMENTAL REPORT

' APRIL-1989 The ambient upstream river temperature (24-hour average') ranged from 55.7'F (April 11).to 70.2*F ( April 28, 29 and 30) with an average of

61. 9 ' F. The downstream temperature varied between 55.7.*F ( April 11) to 70.7'F. ( April 28, 29 and 30) with an average ofl61.8'F. The largest-temperature change occuring'on April 23 was 1.9'F. with a monthly average change of 0.2F.

No chlorination of plant systems have begun although surveillance has started for asiatic clam juveniles.

The sedimentation pond is still not in service pending repairs..

The stabilization pond (Lagoon) flow was re-established on April 10. A maximum flow of 49,248 gallons was recorded for both April 27 and 28. The average flow was 30,538 gallons per day. The maximum 800, and TSS were 22 and 19 respectively occurring on April 18. The averages for the BOD,.and TSS were.16 and 14 parts per million, respectively.

e

___-_-__..-___m

.____-_____.-____-___.--__-______m.

w.

l;

.,1 y. '- _

p s

2 P 33 42.-

AIRSORNE RELEASES (1).

E APRIL-1989 +

A

-u

,. n..

.. s v.

y.jp.y;y.:..=- [rL, "'S *gy p..~ L-4,g n.: g. 4 5 ;;~%

' SUMMATION OF.ALL RELEASES

~.

UNIT

'IHIS' MONTH

~

. ?=

'A.-' FISSION.AND ACTIVATION BASES-

~

4 e

~x

+ +,

1.

TOTAL. RELEASE CI-

< 9.98E 01' 2..

AVERAGE RELEASE' RATE FOR PERIOD UCI/SEC

< 3.30E 01 3.

PERCENT OF TECH. SPEC. LIMIT (0 15 CI/SEC)

X 0.00E-01 B. : 10 DIMES ~

}

,,'W 1 '.

TOTAL IODINE - 131

(

CI

< 4 04E-05 4

2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC

< 1.34E-05 t

3.

PERCENT'0F-TECH. SPEC. LIMIT (2 19 UCI/SEC)

X.

0.00E ' ':

{ '-

5:;,,

..., L_, _

~

C.

PARTICULATE

~

.m 1.

PARTICULATE 6:ITH HALF-LIFES > OR = TD 8 DAYS C1 1 01E-04 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.34E-05.

r 3.

PERCENTOFTECH, SPEC.LIMITk2.19UCI/SEC)

I t.53E-03 4.

GROSS ALPHA RADI0 ACTIVITY CI 9.15E-07 D.~

TRITIUM 1.

TOTAL RELEASE CI 2.35E-02 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 7.77E-03 3.

PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC)

Z 3 55E-01 4.

GROUND LEVEL RELEASE CI 2.35E-02 5.

ELEVATED RELEASE CI

< 3 19E-04

~

(1)

REPORTING PERIOD 35 DAYS

~

o.

.o n.

y;gy'43; '

i-p

'AIRb"RNE RELEACES-l(CONTINUED) 4w APRIL 1989 m:-

2 ELEVATED.' RELEASES 5-f1

-FISSION-SASES.

UNIT THIS MONTH A.-

"KR-85M-CI:

< 6 62F.-02 y

~KR-85 CI

< 5.10E 01..

KR-87 CI

< 5.00E-03;

.KR-68 CI

< 6.28E-01 XE-133 CI

< 3.09F.-01 XE-135M.

CI

.< 4.34E-01

+

XE-135-CI

< 1.09E-01

'XE-138 CI

< 7.40E OTHERS(SPECIFY)

=;

TOTAL FOR PERIOD CI

< 5.3HE 01

.B.:

10 DINES

~

I-131 CI

< 3.32E-06:

I-133 CI

< 3.78E-05 I-135-CI

< 9.5*/E-02 TOTAL FOR PERIOD CI

< 9.5HE-02 j

!L Pdga 44'

/r 4

+1 GIRB RNE RELEASES:(CONTINUED)'

' NE-M......__.........

p L

~

.., APRIL:

,.1989,

r.

_+

=..- y ELEVATED RELEASES s.

Ci.

PARTICULATE UNIT

.THIS MONTH.

58R-89 CI

<'2.64E-07 SR-90 CI

<L1 08E-07.

CS-134-CI

< 4.13E CS-137 CI

< 4 33E-06 34-140' CI

<!1 30E-05.

LA-140 CI

<:5 74E-06 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 2.78E-05 D.-

TRITIUM CI

< 3.19E-04

+

am G G e

y

=

Pcg145 *

~

OICBOT;NE~ RELEASES'(CONTINUED)

~

APRIL 1989 I>

. r - : p ~y,59& n.

m

1

.p., ;3::

u

,. r :+,,

.w

,3

'~

GROUND RELEASES l.

-0.

FISSION GASES UNIT ~

THIS HONTH hy d.,,

.CI

< 1.48E-01

' KR-8,5N O

4 KR-85~

CI

< 4.22E 01 KR-87 CI

< 2 38E-01 KR-88 CI

< 4.43E-01 XE-133 CI

< 2.70E-01 XE-135N.

CI

- < 8 53E-01 XE-135 CI

< 9.34E-02 XE-138-CI

< 1.79E 00 OTHERS(SPEbiFY)

~

1

,. TOTAL FOR PERIOD CI

< 4.61E 01

.B.

10 DINES I-131 CI

< 3.71E-05 I-133 CI

< 5.12E-04 I-135 CI

< 1.23E 00 TOTAL FOR PERIOD CI

< 1.23E 00' q

'*W a

4 Y-

\\ ;e..

u,

- v. ;

Pcs) 46

(;IRBORNE RELEASE 8L(CONTINUED) l APRIL' 1989'

.i l

.,: -t

GROUND RELEASES, L

C.

. PARTICULATE UNIT.

THIS - NONTil SR-89 CI.

<L3.1411-06 SR-90 CI.

' < - 1.18 E-0 6' -

CS-134 CI~

<.3.42E CS-137 CI.

< 3.83E-05':

BA-140-CI

< 1.03E-04 LA-140 CI

< 4.94E-05 OTHER8(SPECIFY)

LCO-60 CI 3.01E-04 TOTAL FOR PERIOD T

CI 1.01E-04' D.? ~

TRITIUM CI 2 35E,

h

=no

______..____._i.._______ _. _ _. _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _. _. _ _ _ _ _. _ _ _ _ _ _ _

=

Pega 47.*

BROWNS FERRY NtlCL. EAR PLANT MONTHLY REPORT CALCULATIONS

-LIRUID RELEASES-

+-

APRIL 1989 RADI0 ACTIVE LIRUID EFFLUENTS 1.

GROSS RADI0 ACTIVITY UNITS a)

TOTAL RELEASE CURIES 1.4bE-02 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 8.43E-10 c)

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

8.43E-01 2.

TRITIUM a)

TOTAL RELEASE CURIES 8.3HE-02

~b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/HL 4.83E-09 c)

PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML)

1. 63E- 0 4 e

(1) 3.

DISSOLVED NOBLE GASES a)

TOTAL RELEASE CURIES

< 9.76E-04 b)

AVERAGE DILtlTED CONCENTRATION RELEASED UCI/ML

< 5.69E-11 c)

PERCENT OF APPLICABLE LIMIT (2E-04 UC1/ML)

< 2.84E-05 4.

GROSS AL.PHA RADI0 ACTIVITY a)

TOTAL RELEASE CURIES 2.32E-04 b)

AVERAGE DILUTED CONCENTRATION REL. EASED UCI/HL 1.35E-11 5.

VOL.UME OF LIQUID WASTE TO DISCHARGE CANAL L.ITERS 4.89E 06 6.

VOLUME OF DILUTION WATER LITERS

- 1. 72E.10 -

J (1)

INCLUDES XE-133, XE-135, AND OTHERS

f::

5.;.

-l 1

PCS2 48 1

~ BROWNS FERRY NUCLEAR PLANT.

l r p'

. PtDNTHLY REPORT: CALCULATIONS i

LIQUID. RELEASES. -

L'<

APRIL 1989.

q

-' *1..

,~

~

ISOTOPES-RELEASED UNITS

,. CI

)

CR-51

< 2.42E,

- MN-54

< 2.73E-04 CO-58

< 2. M E--0 4 FE-59

< 5.64E-04' CD-60' 1.65E-03

' ZN-65

< '8.19E-04' NB < 2.49E ZR-95:

< 4 3bE-04 MOTC-99M

< 2.14E-04 I-131

< 3 24E-04 g,

~ XE-133

' < '7 99E-04 CS-134 1 89E-03.

XE-135

< 1.78E-04 CS-137 1 09E-02 BA-140

< 1 14E -03 LA-140

< 2.36E CE-141

< 3 71E-04

. SR-89

< 1.43E-04

- SR-90

< 4.42E-05 es

,=q

_._m

-m--

s--x.-----

y-7-

O

. P:33 49 *.

' BROWNS FERRY NUCLEAR PLANT.

'W MONTHLY REPORT-CALCULATIONS-LIQUID.~ RELEASES,*

APRIL.

1989

' I.

L,

.a,-

',,* j s.i

, - +.

^

OTHERS.

UNITS CI; 4

CO-57

.4 53E L

'FE-55

.< 1.27E-03

(

e.

9 t

b NT e

S4 9

e

,.q

4. T l ' ';

P:ga 50 BROWNS FERRY NtlCLEAR~ PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES APRIL.

'1989 j

\\

.. ;_ a; ;;...a L.

L LAUNDRY DRAIN VOLilME' RELEASED:

0.0 GALLONS

. FLOOR. DRAIN VOLUME RELEASED:

1223478.6 GALLONS WASTE SAMPIE TANK VOLUME RELEASED:

48692.5 GAL.LON S DISTILLATr4 TANK VOLUME RELEASED:

0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLilME. RELEASED:

'O.0 GALLONS

. TOTAL VJLUME RELEASED TO THE RIVER:

1292171.1 GALLONS HIGHEST 9ATCH ACTIVITY: RELEASED FOR MONTH:

1.79E-09 UCI/HL A/D LONGEST RELEASE TIME FOR MONTH:

332 HrKUTES.

SHORTEST PELEASE TIME FOR MONTH:

167 M1HUTES TOTAL TIMI 0F RELEASES FOR MONTH:

11337 MINlllES A'8ERAGE *,IME FOR BATCH RELEASES:

264 MINUTES 26 W

NUMBER OF BATCHES RELEASED:

43 NUMBER OF ADMINISTRATIVE LIMIT VIOLATIGHS:

0 NU,MBER OF TECHNICAL SPECIFICATION VIOLATIONS:

0 9

I*

e a e

Il,

. g i

H 7.

11

'.J pigs.SiL *,

C v.,

g,q

c @

.fl RESIN USAGE' REPORT APRIL 1989 RESIN CONSUMED (CU.FT.)

1

% of Total Bead 'POWDEX ECODEX ECOSORB' EPIFLOC -Total-Radwaste-LFloor Drain Filter

'35.3-0 147--

0 0

'O 147

' Waste. Demineralized-0 0

0

.0 0

0 0

Waste Filter 41.1 0 ~.

171 0

0 0

171

' Fuel Pool-Demins.-

1.2'

.0-5 0

0 0

5-Reactor Water Cleanup J

Unit'1:

0 0

0

. Unit.2-

'O 0.

0 0

0.

0 0

Unit'3' O.'1 0

3

-0

~0 0-

3 y

Cond. Demins.-

' Unit'l-0 0.

0 0

0

-Unit 2 21.7 0

90 0

0 0

90

-Unit 3L O'

0 0

0 0-

. Tota l s -

100-0 416 0-0 0

416.

e

..k.

a

_ - _ _ = - -

r,_-____

i. o Page'52 e

FUEL CLADDING INTEGRITY PARAMETERS

)

APRIL 1989 I

Unit 1 Reactor Water Iodines (pci/sec)

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

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

Unit 2 Reactor Water Iodines (yci/sec)

Date-I-1 31 1-132 1-133 1-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (vci/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-131 1-132 I-133 1-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (vci/sec)

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

0 3

4 0,

0 M

+,

+

E,

E E

0 9

7 0,

2 8

0 2 6 6

, 0+

I g

t C t

E P

P 2

G G

6

,, 2 1

,. U A

Y S

R N K

E

~

D I

E N

L K N A T

A P N U R S

T N

M A A D A

A T E

L W

R N S

L K S

O I

P N T

O A M A U

L R A T P

F D f

H S

I G

UOR R

H E

T 9 Z

0 8

I 0

f M 9 E

L 0

I E 1 T

A T

S R S

A E

T Y

W N F

l I

C S

M

)

3 E

(

6 T L 0

D 0

0

+

4 5

N I R

E 0

0 E R R N 7

E 4

2

+ +

2 E

E O

I 1

7 2

M P T

T A

L 7

3 O A t

1 5

L R T

A I

F U F D E

F A

U lC 6

DP A

R

)

G 6

2 T

(

6 0

0 R

0

+

E E

R 2

T E

7 1

T A

E 7

3 W

T 1

T S

D S

1 L

A E

A T:

L I

F U

W C

W Y

F U

A C

C 6

E

)

O 0

(

1 M

0+

E E

N.

0 l

0 0

0 R

U R6 A

O R N T O

I C KN L R L A O A E T

R f

O F D L I

E T K O

f C

T C N I

S E A f

A I

L T W

L O

C l

ll l

l

QVT'~ ~

p ;,. ? e '.

9.'

lf. '.j', _

,,t_

- 6:n Pega 54

. a :-

TESTING SUfftARY.

4

. APRIL 1989 I

Surveillance Testina

- Unit 0 A tocal of 162 surveillance tests were completed using 34 different test.

instructions.

.iUnit 1

A total of 68. surveillance tests were completed on unit 1.using 17 different test instructions.

Unit 2

' A total of-163. surveillance tests were completed on unit 2 using 78 different test' instructions.-

Unit-3 l'A total of'69' surveillance tests were completed on unit 3 using.17 different test instructions.

=_u=__._______:.

n l;

e.

Pagt 55 s

TESTING

SUMMARY

(CONTINUED)

APRIL 1989 channes. Tests.'and Eroeriments Tecuiring Authorization From the NRC Pursuant

'to 10 CFR 50.59(a)

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

They were:

1.

Amendment'#163, Transmittal #89-06 to correct'EPL errors issued'4-18-89.

~

2.- Transmittal #89-09 to correct pages issued out'of sequence.

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

There was one-special tests completed for this month.

ST 89-02

Description:

Inspection of fuel bundles LY4673 and LY4610.

k

_l._A_--.-

hkn.,h

.?M, '

e.

uit i ' s-3 Paga 56 ji-:%,.

.p :,:;,

1.,* c l

REACTOR VESSEL FATIGUE USAGE EVALUATION L

.o

~

APRIL 1989 The cumulative usage factors for the reactor, vessel are as follows:

'Usane Factor-

n

" Location' Unit 1 Unit 2 Unit'3

~

s Shell at water'line 0.00620 0.00492-

-0.00431-3

-Feedwater nozzle-0.29782

' O.21319-

'0.1'6139

. Closure-studs'

.'O.24204 0.17629"

O.14360 R

.s 1

i 4

4

.s e9 e+<..

~

3 pl Pags 57 b:

CV g.

D'.

p'l CHANGES IN PROCEDURES-APRIL 1989 There were 349. revisions to plant instructions'during the month;'346-

' instructions were changed primarily for correction; and three revisions b

-related to safe operation of the plant.

i-I' l

PLANT INSTRUCTION REVISIONS 1

APRIL 1989 l

Category Instruction Reason for Reauest Change in rerponse EPI-0-090-VLV001 Identify QMDS requirements to LER, IE Bulletin, Electrical Preventive and correct typo.

NRC Inspection Report, Instruction Maintenance OPQA for Hills-McCanna Ramcon Motor Operated Valve 1/3 GOI-100-3 Refueling Identify requirements of Operations INPO SER 86-040 and IE notice 87-013 SDSP-6.9 Cleanliness of Incorporate source document Fluid Systems implementation 88-1175.

Added compressed air system criteria for Resolution of NRC Bulletin 88-014.

-x_-__-_______-

je

[_1;p

' Pag 2 58 1

)

l:.

CHANGES IN PLANT ORGANIZATION-APRIL 1989

- There were three changes in plant staff for those positions designated as key su'pervisory positions for the month. The changes.were:-

(1)

Gene A. Hartsfield, Manager of Maintenance Planning & Technical,

~

transferred out.

(2)

Kenneth S. McVay, named Manager of Industrial Safety.

(3)

Allen W. Sorrell, named Maintenance Superintendent.

d i__.__.m_,. _ _ _., _ _ _ _ _ _. _

. _ _ = _ _ _ _ _ _

7,..

"4 s - ; :.

N Pegs 59.

- . 1*D w

, s.-

fj,

\\

ACCIDENTS i

e APRIL 1989 p

i.

. There were two loss-of-time accidents during.the month.. They were.as.-

~

' follows:

'(1),4/3/89 MODS Electrician, strained his chest while climbing..

P (2) 4/4/89

'DNE Computer Graphics Technician, slipped and tore Ligament in his knee.-

T:

.\\

r I

(

4 d

'i

ML20244A947

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