Text

Monthly Operating Repts for Oct 1988 for Browns Ferry Nuclear Plant Units 1,2 & 3
	ML20195G702
Person / Time
Site:	Browns Ferry
Issue date:	10/31/1988
From:	Campbell G, Crawford J; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM), Office of Nuclear Reactor Regulation
References
	NUDOCS 8811300008
	Download: ML20195G702 (70)
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MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY l

OCTOBER 1988 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS OPR-33, DPR-52, AND DPR-68 1

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Submitted by:

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g Guy G. Campbell Plant Manager q:{

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4 TABLE OF CONTENTS PART I OPERATIO ML SUt9MRY A.

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

1 B.

Fuel Performance and Spent Fuel St: age Capabilities Summary...... 2 C.

Main Steam Relief Valve (MSRVs) Actuation Summary................ 5 D.

I s su anc e o f S pe c i a l R e po r t s S umma ry.............................. 6 i

E.

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

7 F.

Offsite Dose Calculatiot Manual Changes.........................

13 C.

R a d w a s t e S umm a ry................................................ 14 1.

Total volume of solid waste shipped off site 2.

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

3.

Gross curie activity 4

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

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Estimated quantities of spent resin in storage.

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Estimated amount of spent resin that vill be generated in the following month.

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Waste type and volume of radwaste containers that are onsite l

awaiting shipment.

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l PART II OPERATING STATISTICS A.

NRC Reports 1.

Operating Data Report.......................................

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Ave rag e Daily Powe r Leve 1................................... 2 6 3.

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

TVA Reports 1.

1knt Operating Statistics..................................

32 2.

Unit Out age and Availability Dat a........................... 33 3.

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

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TA3LE OF CONTENTS (Continued)

Part III MAINTENANCE

SUMMARY

37 PART IV OTHER REPORTS A.

Chemistry Summary 1.

Primary Coolant Chemistry.................................. 40 2.

Environmental Technical Specification Requirements.......... 43 3.

Airborne Releases........

....................... 44 4.

, Liquid Releases..........

.......................... 49 5.

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

........................... 53 6.

Fuel Cladding Integ*.4,y Parameters..........................

54 7.

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

55 4.

T e s t i n g S umma ry.................................................. 5 6 C.

Reactor Vessel FatJ ;ue Usage Evaluation.......................... 58 D.

Cha n g e in P ro c e du re s............................................. 5 9 E.

Plant Ins t ruc tion Revision s...................................... 5 9 F.

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

61 C.

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

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i OPERATIOXAL SIMMARY

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SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

OCTOBER 1988 Unit 1 10/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

10/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Unit 2 10/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

10/31/88 2400 Unit remains on administrative hold to resolve varicus TVA and WRC concerns. Cycle $ refueling and modificationa continue.

Unit 3 10/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

10/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

OCTOBER 1988 Unit 1 Unit I was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sixth refueling vill involve loading 8x8R (retrofiv.) fuel assemblies into the core. The prior-to-startup unit 1 modifications are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661), containment instrumentation modifications (NUREG 0737), fire protection changes (Appendix R 10CFR50)

(all), MSIV leak rate reduction modifications, modificatie. e, masonry walls (IEB 80-11), evaluation of the vent drain and test connections (LER 82020),

valve leak rate testing modifications (Appendix J), HPCI improvements, modification of PCIS logic (LER 259 85009), replacement of plant process computers, seismic qualifications of riping (IEB 79-02/14), post-accident sampling modifications (NUREG 0737), RPS voltage monitoring modifications, H0 sample line m dification (LER 81050), and EECW carbon to stainless 22 pipe changeout.

There are zero assemblies in the reactor vessel. The spent fuel storage pool presently contains 284 new assemblies, 512 EOC-6, 267 EOC-5, 245 EOC-4, 362 EOC-3, 26 EOC-2, and 168 EOC-1 assemblies. The 252 EOC-6 assemblies were 1

transferred tc unit 2 SFSP. The present available capacity of the fuel pool is 1607 locations.

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s FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED)

OCTOBER 1988 Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date of April 30, 1989. On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 2 modifications are CRD SDIV piping modification (IEB 80-17), environmental qualification of i

electrical equipment (10CFR50.49), torus structural modifications (NUREG 0661), containment instrumentation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductions modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections (LER 82020), valve leak rate testing modifications (Appendix J),

D/G speed sensor installation (LER 81004), HPCI and RCIC testable check valve changeout, modification of PCIS logic (LER 259 85009), HPCI improvements, various seismic program review, and EECW carbon to stainless pipe changeout.

There are zero assemblies in the reactor vessel.

The spent fuel storage pool presently contains 304 new assemblies 252 unit 1 EOC-6, 764 EOC-5, 248 E0C-4, 352 E0C-3, 156 EOC-2, and 132 E0C-1 sssemblies. The 252 EOC-6

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assemblies were transferred from unit 1 SFSP. The present available capucity j

of the fuel pool is 1,229 locations.

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FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED)

OCTOBER 1988 Unit 3 Unit 3 was shut down on March 9, 1985, ar.d placed on administrative hold t

to resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications.

The prior-to-startup unit 3 modifications are environmental qualification of electrical equipment (10CFR50.49), containment modifications (NURIG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections

,'LER 82020), valve leak rate testing modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), post-accident sampling modification (NUREG 0737),

addition of redundant drywell control air supply, RPS voltage monitoring modification, H 0 8kmple linc :sditication (LER 81050), replacement of 22 jet pump holddown beam assemblies (IEB 80-07), EECW carbon to stainless pipe changeout, and plant design upgrade to seismic qualification.

There 2re zero assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 assemblies to finish cycle 6, 248 EOC-5, 280 EOC-4, 376 EOC-3, 97 IOC-2, and 3 EOC-1 assemblies. The present available capacity of the fuel pool is 585 locations.

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s MAIN STEAM altf IEF VALVE (MSRVs) SUIMAPY I

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No MSRVs were challenged during the month.

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ISSUANCE OF SPECIAL REPORTS J

OCTOBER 1988

.'1 The following special reports are notices of violations issued for the month

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of October 1988.

88-21-02 Failure to comply with the Nuclear Quality Assurance Manual j

(NQAM) requirements for generic review of conditions adverse to quality. Condition Adverse To Quality Reports (CAQRs)

SQN 871347, SQP 871003, SQP 871066, and SQT 871304 were classified as potentially affecting Browns Ferry and did not receive seneric review within 70 calendar days from the organization of the CAQRs.

l This is a Severity Level IV violation (Supplement II) and l

applies to all three units.

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LICENSEE EVENT REPORT (s)

OCTOBER 1988 Descriotion of Event LER-1-88-015 CONTROL ROOM OPERATOR DOSE MAY EXCEED DESIGN LIMITS AFTER LOSS OF COOLANT ACCIDENT (LOCA) BECAUSE OF DESIGN ERROR During the design baseline review program, it was determined that itnfiltered air from the control bay air supply duct bypasses the cintrol room emergency ventilation charcoal filter units and etters the control room habitability zone. Calculations pe' formed assuming 2750 cfm bypass leakage indicated the operator 30-day dose following a LOCA does not exceed the General Design Criteria 19 limits under normal meteorological conditions.

However, if a 24 miles-per-hour wind from the south occurs, exfiltration would occur from the secondary containment i

membrane. An analysis performed assuming exfiltration for two hours after LOCA determined the 30-day operator thyroid dose would exceed the General Design Criteria 19 limits.

This condition was the result of design error in the original F

design of the plent. All possible sources of inleakage into the control bay habitability zone were not accounted for in the design of the control room environmental control system.

1-88-027 INADE0UATE PROCEDURE CAUSES UNPLANNED START OF EMERGENCY EOUIPMENT COOLING WATER PUMP on September 1, 1988, at 1723 hours0.0199 days 0.479 hours 0.00285 weeks 6.556015e-4 months with all three units defueled, during the performance of a post modification test on the 3ED 4KV shutdown board, the B1 residual heat removal service I

water (RHRSW) pump started inadvertently. This was an unplanned engineered safeguard feature (EST) actuation. This occurred during the section of the test which verified correct operation of the 3D core spray pump breaker. The cause of this event was a d

procedural inadequancy. The test required closing the 3D core l

spray pump breaker in the test position. Per plant design, this provides an auto start signal to the C3 and B1 RHRSW pumps after a 28-second time delay. The C3 pump was already running at the r

i time of the event and the B1 pump started after the time delay.

.I Tne test procedure did not identify the ESF actuation. At 1729 l

hours, the B1 RHRSW pump was stopped and the test was stopped I

until the procedure could be corrected.

Procedures governing

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preparation and review of tests will have cautions placed in them on EST actuation. All systems responded as designed, placing the plant in a conservative configuration.

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Descriotion of Event (Continued)

LER 1-88-029 FAILURE TO MEET SINGLE FAILURE CRITERIA IN EQUIPMENT AIRLOCK f

ViidILATION DAMPERS BECAUSE OF INADEOUATE DESIGN PLACES PLANT IN i

UNANALYZED CONDITION

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t During the design baseline review, it was discovered that the circuit controlling the secondary containment isolation dampers in the equipment air lock did not meet single failure criteria.

The inboard and outboard dampers are controlled by one contact that closes and opens when the exhaust fan is started and J

stopped. This condition could provide an uncontrolled release

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path from secondary containment if the inner airlock doors were i

open and the dampers failed to isolate when required because of I

l a single electrical failure.

The cot..Ition was caused by inadequate design controls durins initial design of the circuit.

4 1-88-030 ESF CAUSED BY PERSONNEL ERROR DURING INSTAffATION OF PLANT MODIFICATION l

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i On September 23, 1988, at 1003 hours0.0116 days 0.279 hours 0.00166 weeks 3.816415e-4 months , during the performance of I

a modification work plan to install permanent test jacks for i

testing the reactor and refuel zone ventilation exhaust I

radiation menitors, the following ESF actuated: Standby gas treatment and control room emergency ventilation started; and the refuel zone and primary containment ventilation system isolated. The apparent cause was bumping electrical contacts while performing the modification. Work on the modification was halted, the immediate cause of the event determined, isolations were reset, and affected systems were returned to normal.

A procedure will be written to require a review of all scheduled work for impact on safety related equipment. This will ensure that work directly affecting or potentially affecting ESFs has been evaluated and sufficient steps taken to prevent unplanned actuation of ESFs.

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s Pcge 9 Descriotion of Event (Continued)

LER 1-88-032 ELECTRICAL SEPARATION REOUIREMENTS VIOLATED DUE TO DESIGN CONTROLS On October 8, 1988, with all three units shutdown, while implementing a design change to upgrade primary containment electrical penetration, discrepancies were discovered between cable classifications and cable routings indicating possible violation of the electrical divisional separation requirements.

Since that time, a review of over 5,000 cables has identified 124 violations of the divisional separation requirements. All three units are affected.

The root cause of this condition was inadequate design control.

Divisional separation was not always adequately considered during cable routing, particularly when dealing with non-safety related cables. At the time, these cable routings were developed (1971-1974), many of the design requirements were changing and the coordination and control of the electrical design criteria by the design organization was inadequate.

These conditions impeded the comprehensive review and uniform application of the design criteria.

2-88-006-01 480 VOLT SHUTDOWN BOARD VOLTAGE TRANSIENT INITIATES ESFs On August 24, 1988, at 1258 hours0.0146 days 0.349 hours 0.00208 weeks 4.78669e-4 months , and again on September 23, 1988, at 0455 hours0.00527 days 0.126 hours 7.523148e-4 weeks 1.731275e-4 months , the 2C2 reactor protection system (RPS) circuit protector tripped deenergizing the 2A and 2B RPS buses, respectively. The result of each of these power losses was the initiation of standby gas treatment; control room emergency ventilation; refueling zone isolation; unit 2 reactor zone isolation; partial unit 2 primary containment isolation; and a unit 2 half scram. The residual heat removal (RHR) system isolated during the first event, but was already isolated at the time of the second event. The traversing incore probe and reactor water cleanup systems were removed from service and isolated at the time of both events. The 2C2 RPS circuit protector was reset, isolations reset, and affected systems returned to normal following both event hours. ESFa performed per design and placed the plant in a conservative configuration.

Root cause and recurrence control vill be provided in a supplemental report.

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e Pago 10 Descriotion of Event (Continued)

LEE 2-88-007 INADVERTENT TRANSFTR SWITCH OPERATION INITIATES ESF On September 4, 1988, at 1552 hours0.018 days 0.431 hours 0.00257 weeks 5.90536e-4 months with all three units defueled, RSP motor generator set 2A van started by the assistant shift operations supervisor (ASOS) for post maintenance testing. During this event, there was a loss of power to the 2A RPS bus. This initiated standby gas treatment, control room emergency ventilation, and a half scram on unit 2.

The refueling zone and the unit 2 reactor zone ventilation isolated. Also, the unit 2 residual heat removal and primary containment ventilation isolation valves closed. The unit 2 reactor water cleanup and traversing incore probe systems received isolation signals on loss of RPS power, but were removed from services and isolated at the time of the event.

The cause of this event was personnel error. The ASOS inadvertently operated the normal / alternate transfer switch while removing a clearance tag. This cause the loss of power to the 2A RPS bus. The unit operator reset the half scram and isolations and returned affected systems to normal.

The ASOS was counseled. During this event, all systems responded as designed, placing the plant in a conservative configuration.

The plant would have performed in a similar manner if the event had occurred during power operation.

2-88-008 UNPLANNED ESF ACTUATION DURING ELECTRICAL BOARD POWER TRANSFER DUE TO PERSONNEL ERROR i

On September 5, 1988, at 2206 hours0.0255 days 0.613 hours 0.00365 weeks 8.39383e-4 months with all t'hree units defueled, the ASOS transferred the power to the 2B 480 volt i

shutdown board back to its normal supply folleving a special test on the D diesel generator. The breaker on the D 4KV shutdown board which supplies transtormer TS2B and is the normal power source for the 2B 480 volt shutdown board, was inadvertently left in the open position. The resulting transfer f

to a deenergized transformer canned a loss of power at the 2B 480 volt shutdown board and a subsequent loss of power at the 2B i

RPS bus. This initiated standby gas treatment, control room emergency ventilation, and a half scram on unit 2.

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refueling zone and the unit 2 reactor zone ventilation isolated. Also, the residual heat removal and primary i

containment ventilation isolation valves closed. The unit 2 reactor water cleanup and traversing incore probe systems i

receive isolation signals on loss of RPS power, but were removed from service and isolated at the time of the event.

The cause l

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(Continued)

LIR 2-88-008 of this event was personnel error in that the ASOS did not verify 1

(Continued) voltage on TS2B prior to transferring the board. The corrective action was to counsel the ASOS and discuss the event with the i

Operations group. During this event, all systems responded as I

designed, placing the plant in a conservative configuration.

L 2-88-009 UNPLANNED ESF ACTUATIONS DUE TO LOSS OF REACTOR PROTECTION l

SYSTEM POWER CAUSED BY LACK OF PREVENTIVE MAINTENANCE ON A 480 VOLT BREAKER With all three Browns Terry unita defueled, three separate but unrelated events occurred on unit 2 which involved the unplanned initiations of a RPS half scram, partial primary containment isolations, secondary containment isolations, and actuation of the control room emergency ventilation system and standby gas treatment. The events occurred on September 9, 1988, at 1340 i

hours; October 2, 1988, at 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months ; and again on October 2 1988, at 0442 hours0.00512 days 0.123 hours 7.308201e-4 weeks 1.68181e-4 months , during switching operations when the normal supply breaker on a 480 volt board failed to close because of the dirty condition of the sliding accondary disconnects in the breaker control logic. This deenergized the 480 volt board and l

the RPS bus which it supplies. Loss of power to an RPS bus caused the EST actuations listed above.

The root cause of the breaker failures was the lack of preventive maintenance on the breaker and board compartment.

Preventive maintenance on the breakers had not bsen done during i

the last two years because the units have been shutdown for an unusually long time and the preventive maintenance frequency on these breakers is tied to the refueling outages.

All maintenance activities necessary for unit 2 restart are being identified and will be carried out prior to unit operation.

2-88-010 PERSONNEL ERROR IN PROCEDURE PREPARATION CAUS$$ ESF ACTUATION On September 15, 1988, at 0455, an unplanned ESP actuation occurred during the performance of a modification to the unit 2 primary containment isolation logic (PCIS). All three units were shutdown and defueled when this event occurred. A unit 2 PCIS group 6 isolation, unit 2 reactor zone isolation, and units 1, 2, and 3 refuel zone isolation occurred. Standby gas treatment trains A and C and control room emergency ventilation train A initiated. The wiring was returned to normal configuration and isolations and initiations reset at 0507.

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1 Descrintion of Event (Continued)

LER 2-88-010 This event was caused when a wire was lifted during the

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(Continued) performance of the work that deenergized isolation logic relays. The root cause of the isolation was personnel error in 4

j the preparation and review of the workplan. The workplan was rewritten to ensure any wire lifts or jumpering would not inadvertently deenergir.e isolation logic. The system engineer reviewed the workplan revision to ensure the procedure contained steps to prevent ESF actuations.

3-88-004 TEMPERATURE CONTROL VALVES INSTAftFD INComarCTLY DUE TO INADEQUATE DESIGN CONTROL 1

Browns Ferry units 1, 2, and 3 were defueled when this condition j

was discovered. On June 24, 1988, at 1600 hours0.0185 days 0.444 hours 0.00265 weeks 6.088e-4 months during maintenance activities, maintenance engineers discovered that air operated temperature control valves for the unit 3 shutdown i

board room air handling units will fail, on loss of control air, in such a manner that the chilled water will bypass the air handling unit. On September 9, 1988, at 1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months it was determined that this condition would not satisfy the Final Safety Analysis Report and could place the shutdown board rooms in a high temperature environment which could have adverse i-effects on the function of electrical equipment and instrumentation in the rooms. Yhe failure position of the

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temperature control valves was changed September 7, 1988, to 1

ensure flow of chilled water through the air handling units.

The cause of the event was inadequate design control in that

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there was an inadequate interface review between involved engineering disciplines. This resulted in design drawings which did not specify the failure mode of the temperaturt control a

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valves on loss t' control air. Procedures are now in place to ensure proper ap. '1 cation of design input. The chilled water flow diagram will be revised to identify the failure mode of the TCVs. This event id not pose a nuclear safety con:ern and I

posed no threat to personnel or plant safety.

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4 Pegs 13 OITSITE DOSE CALCULATION MANUAL CHANGES OCTOBER 1988 The Offsite Dose Calculation Manual was revised in October to more completely describe the calculations of gaseous release rate limits and doses, and to clarify 40CFR190 total dose calculation.

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e Pags 14 RADWASTE

SUMMARY

OCTOBER 1988 The radvaste system performed as designed. Approximately 1.09E+06 gallons of waste liquid were discharged containing approximately 1.37E-02 curies of activity.

There were no spent resin shipments and two trash shipments during October. All shipments were to Barnwell, South Carolina.

There was one trash shipment made by the Scientific Ecology Group, radvante broker / processor, containing BFN waste during October. All shipments were to Barnwell, South Carolina.

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Pego 15 Solid Radioactive Waste October 1988 Dewatered Spent Resin Shipments ( '

Volume of condensate / waste resin shipped:

O Cu.M. ( 0 Cu.Ft.)

Total curies shipped:

0 Volume of reactor cleanup resin shipped:

O Co.M. ( 0 Cu.Ft.)

Total curies shipped:

0 Date Shicoed DisDosal Facility TYDe of Resin NIR NIR NIR Dry Active Waste (13 Number of drums shipped:

48 Volumet 10.19 Cu.M. ( 360.0 Cu.Ft.)

Total curies shipped:

0.1265 Number of boxes shipped:

16 V0lume 43.57 Cu M.

(1539.4 Cu.Ft.)

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Total curies shipped:

0.6119 Date ShiDDed Discosal Facility Tvoe of Packaoe 4

i 10/12/88 Barnwell, SC Drums / Boxes 10/26/88 Darnwell, SC Boxes i

I Brokered shipments (SEG):

1 Volume:

0.12 Cu.M. (

4.3 Cu.Ft.)

Total curies shipped:

0.0010 Date Shipped Disposal Facility Tvoe of Packace 10/05/88 Barnwell, SC Boxes I

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I Pcgo 16 Solid Radioactive Waste (Continu2d)

October 1988 Summary 4

Type Shipped to Packaged on Gross Curie Estimated of BarnwelL Site Awaiting Content by Generation for waste During Month Shipment Type of Waste Next Month Compacted Drums 360 Cu.Ft.(2) 45 Cu.Ft.

1.27E-01 450 Cu.Ft.(2)

Boxes 837 Cu.Ft.(2' 279 Cu.Ft.

5.00E-01 1000 Cu.Ft.

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Uncompacted Drums O

Cu.Ft.(2)

O Cu.Ft.

0.00E+00 0 Cu.Ft.(2)

Boxes 702.4Cu.Ft.(2) 396 Cu.Ft.

1.12E-01 875 Cu.Ft.(23 Brokered 4.3Cu.Ft.

O Cu.Ft.

1.00E-03 75 Cu.Ft.

Resins CWP5 0

Cu.Ft.(1) 4264 Cu.Ft.(3) 0.00E+00 700 Cu.Ft.(1)

RWCU 0

Cu.Ft.(l' 325 Cu.Ft.(3) 0.00E+00 10 Cu.Ft.(13 TOTALS 1904 Cu Ft.

720 Cu.Ft.( )

7.40E-01 2,400 Cu.Ft.(

2' Total volume of waste shipped during the month:

1,904 Cu.Ft.

Total volume of waste shipped year-to-date:

22,191 Cu.Ft.

Unused 1988 burial volume allocation at BarnwelL:

60,609 Cu.Ft.

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Actual resin volume (2)

Container burial volume (3)

Estimated volume in separators (4)

Does not include resins

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1

LIQUID RADWASTE reso n OCTOBER 1988 TOTAL RIVER RELEASE FLOW RATE (SPM)

DATA PLOTTED FOR THE PMVIOUS 12 MONTHS TOTAL MLEASE(CI)

.S 40.

RATE fand HI R7.81 30 -

LOW 18.50 AVS R1.55 1

TOTAL 30.

pKLEAaK1211 HI 0.04 LOW 0.01 10.

AVS 0.08 o FLOWRATE kkJG kP h:T DM (CI) kC hAN ka km MI Y

M V

TleGLaaHM.itfaALA)

FILTER THROUGHPUTS WASTE d

GALLONS X 1 HI 0.18E+07 LOW 0.SSE+0S 4

AVS 0,.1M+07 FLOOR DRAIN HI 0.11E+07 3

LOW 0.SM+0S m

7 AVO 0. NE+0S P

l LAUNDRY 2

m

. N I

i-HI 0.1M+0S s,

\\

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l'K\\

I W s,

LOW 0.00E+00 N' '

K'y% 3 E

AVS 0.44E+04 lcN\\3 h

g i

g NOV OEC JAN FES MAR APR MAY JUN JUL AUS MP OCT COST OF OPERATION Affb.

THOUSA 0F DOLLARS g

HI

0. SM+0S LOW 0.1M+0S SO.

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[k hM Nk NQY DEC JAN FES MAR APR MAY JUN JUL AUG SEP OCT N'-

WASTE COLLECTOR SYSTEM

' LAUNDP.Y SYSTEM b b FLOOR oRAIN SYSTEM

Pass 22 REACTOR POWER - NWT UNITS 1, 2 AND 3 OCTOBER 1988

\\

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2000 sete UNIT 1: OUTAGE UNIT 2: OUTAGE 3000 UNIT 3: OUTAGE 1000 see

- - - - 4h4####h444t&#4#$4&&4&

Onnistry not: tin D61S

!\\neMical Servicee 9%nne forty M] ear P]mt AEACTOR WATER CONOUCTIVITY WITS 1, 2, AND 3 OCTOBER 1988 UMH0/CM C0600CT!YITY UNIT 1 g,73 1.5 CONDUCT!Y1TY UNIT 2 3.3s g.......--............---.......--...........--.------- -----

l e.75 UNIT 3 i

s.5 EXPECTED MANGC e.as COLD SHUTDOWN P. s g**%9***A*#4@%@4%#D444&&f44444@4YACTION LEVEL I LIMIT mes/stry.sectfm DAYS COLD sHUTooWN TecMical.snevices n'oene ferry M Jear' P]m t l

REACTOR WATER CH!.0 RIDE WITS 1, 2, ANO 3 OCTMER 1988 PPSm..-............-.---....--..-..-..-.........----...-....---.--.

x 0nroc LNIT 1 40 CHLORICE UNIT 2 gg Of.CaIDE UNIT 3 A

EXPECTED RANGE le

, ALL COPCITIONS

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it***A**ge@cce#c44ft&#fff4&&4+

mesistry,sectim DAYS TecMical Jlnevices Owens ferry Mirar Plot

0

'a e

e OPERATIONAL STATISTICS l

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Pcgo 23 OPERATING DATA REPORT DUCKET No.

50-259 OATE I l-01-M CnpFLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERAflisG STATUS l Notes l

l.

Unit Neus:

Srowns Ferry Unit One l

l 2.

Reporting Period:

October 1900 l

l 3.

Licensed Thertel Power (part): )??)

l l

4.

Neumplate Rating (Gross Pedo): 1152 l

S.

Ossign Electrical Rating (Not m e) 1065 l

6.

Moulnwe r, nedle Capacity (Gross We) 1000.4 l

7.

Realeen Dependable Capacity (Not m e) 1065 l

l 8.

If Changes Occur in Capacity htings (items Nweer 3 Through 7) $1nce Latt Report, Give Reasons:

N/A g.

Poser Level To Which Restricted, if Any (Not me):

N/A

10. Reasons For Restrictions, if Any N/A s

This Month Yr-to-Cate Cw'ulative

11. Iburs in Reporting Period 745 7320 125.000

12. Nweer of Hours Reactor Was Critical 0

_,0 59.521.34

13. Reactor Reserve Shutdown Hours 0

0 6.997.44

14. Hours Generator On-Line 0

0

_ j4.267.26

15. Unit Reserve Shutdann Hours 0

0 0

16. Gross Thermal (norgy Generated (NH) 0 0

160.066.787

17. Gross Electrical Energy Generated (1441) 0 0

55.390.130

10. Not Electrical Energy Generated (pt#f)

,,-48S5

-45416 53.637.6S7

19. Unit Service Factor 0

0 46.61

20. Unit Availability Factor 0

0 46.61

21. Unit cepecity Factor (Using POC Net) 0 0

40.29,,

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

40.29

23. Unit Forted Outage Rate 100 100 45.l?

24. Shutdowns ScMied Over Ibst 6 months (Type, Date, and Duration of Each):

25. If Shut Dawn At End Of Report Peric f. Estimated Date of Startup To be determined

'6. Units in Test Status (Prior to Comercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICl1Y CDP 9(RCI AL OPERATION (9/77) liten 1

Pcg2 24 OPERAfil4 DATA REPORT i

000(ET NO.

M-260 DATE

. I l-O L es CoprLETED BY J. D. Crawfor t TIttPHONE (205) 729-2507 OPERAilies STATV5 l Notes l

1.

Unit Name:

Browns Ferry Unit Two l

l 2.

Reporting Period October 1900 l

3.

Llunsed Thermal Nor (lett): 3293 l

4 Nameplate Ratly (Gross lede): 1852 l

l i

S.

Deslan Electrical Rating (Not lede)_1065 l

l 6.

b imus Dependable Capecity (Gross MWe) 1090.4 l

l 7.

blown 0; _.Mle Capacity (Not Pede) 1065 l

l S.

If Changes occur in Capacity Ratings (ltens Nueer 3 Through 7) $ lace Last Rogert, Give Asesons:

N/A i

9.

Pcner Level To Which Restricted, if Any (Not MWe):

N/A

{

10. Reasons For Restrictions, if Any:

N/A i

i This Month Yr-to-Cate Cuwlative

11. Howrs in Reporting Period 745 7320 119.887.Ch)

12. Nueer of Hours Reactor Was Critical 0

0 55.860.03

13. Anector Reserve shutdo n Hours 0

0 14.200.44

14. Hours Generator On-lins 0

0 54.334.34

15. Unit Reserve Shutdown Hours 0

0 0

14. Gross Thermal teergy Generated (MWH) 0 0

15h245.167

17. Gross Electrical Energy Generated (1444) 0 0

M.771.798

18. Net El u trical Energy Generated (leWH)

-2005

-20006 49.165.027

19. Unit Service Factor 0

0 45.32

20. Unit Avelledllity Factor 0

0, _

45.32

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

34. M

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

30.M

{

23. Unit Forced Outage Rate 100 100 44.70 r

24. Shutdowns ScheA led Over b t 6 Pbnths (Type, Dete, and Duration of tech):

25. If Shut Down At End of bport Period. Es+! mated Date of Startup 1o te_ determined i

26. Units in Test Statua (Prior to Co, rsial Operation):

Forecast Achieved INITIAL CRITICAL.lTY l

iumAt ettCThiCm t

Cimact AL OPERATION i

(9/77) 172 0 l

[

l

Pcgo 25 5

OPERATING DATA REPORT 000rir so, _30 296 DATE 11-01-48 Cov'Ltit0 BY J. D. Crawford TELEPHONE (205) 729-2507 ortRAf teso STATjg l Notes l

1.

Unit Nam Brosas Ferry Unit Three l

l 2.

Reporting Period October 1900 l

l 3.

Licensed Thermal Power (mrt): 3?93 l

l 4.

Nameplate Rating (Gross m ): 1152 ll l

S.

Design Electrical Rating (Not mis)_1065 6.

Raulmus P, Mle Capacity (Gross fede). 1000.4 2.

Asalmum Dependable Capacity (Not fede) 1065 8.

If Changes Occur in Capacity Ratings (Items Nueer 3 Through 7) Since Last Report, Give Roa.ons:

N/A 9.

Pc=ar Level To Which Restricted, if Any (Not MWe):

N/A

10. Reasons for Restrictices, if Any:

N/A This Pbnth t e-to-Cate C a lative

11. Hours in Reporting Period 745 7320 102. 312.0p

12. Nueer of Hours Reactor Was Celtical 0 _

0 45.306.0W

13. Anector Reserve Shutdown Hours 0

0 5.149.55

14. Hours Generator On-Line 0

0-44.194.76

15. Unit Reserve Shutdown M rs 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

131.064.247

17. Gross Electe 9al Energy Generated (MWH) 0 0

43.473.760

18. Not Electrical Energy Generated (mdH)

-1696

-20915 42.020.213

13. Unit Service Factor 0

0 43.19

20. Unit Avellability Factor 0

0 43.19

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

34.M

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

38.%

13. Unit Forced Outage Rate 100 100 44.37

24. Shutdowns ScMied Over host 6 Manths (Type, Date, and Duration of Each):

25. If Shut Do.n At tad of Report Period, Estimated Date of Startup _ To be deterwir t

26. Units in Test Status (Prior to Ccreercle' Operation):

Forecast Achieved INITIAL OtlTICALITY INITIAL ttECTRIClfY CD9(ACI AL QTRATION

~

l (9/77) 17 ten M

Q /,.,

Pcg2 26 5

AVERAGE DAILY UNIT POWER LEVEL

\\!

DOCKET NO.

50-259 I.

Unit One DATE 11-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MOHTr1 OCTOBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL l

(MWe-Net)

(MWe-Net) l 1

-5 17

-6 l

2

-6 18

-6 3

-7 19

-6 4

-7 20

-7 5

-6 21

-6 6

-6 22

-7 7

-7 23

-7 8

-5 24

-7 l

)

9

-7 25

-6 1

1 10

-2 26

-7 11

-5 27

-6 12

-7 28

-7 13

-7 29

-7 I

l 14

-7 30

-7 15

-6 31

-7 16

-6 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) 1724n

D Pags 27 ir AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 Unit Two DATE 11-01-88 COMPLETED BY J.D. Crawford TELEPHONE (2051729-2507-MONTH OCTOBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-3 17

-2 i

2

-3 18

-3 3

-3 19

-3 4

-3 20

~3 5

-3 21

-3 6

-3 22

-3 7

-3 23

-3 8

-4 24

-2 9

-3 25

-3 i

10

-3 26

-3 11

-3 27

-2 i

12

-m3 28

-2 13

-3 29

-2 l

14

-3 30

-2 l

15

-3,

31

-3 16

-i INSTRUCTIONS l

l On this format, list the average daily unit power it. vel in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 1724n i

I L

Pcg3 28 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 Unit Three DATE 11-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH OCTOBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i

(MWe-Net)

I 1

-2 17

-2 2

-3 18

-2 3

-3 19

-2 4

20

-2 5

-2 21

-2 6

-3 22

-2 7

-2 23

-2 8

-3 24

-2 9

-2 25

-2 10

-2 26

-2 11

-2 27

-2 12

-2 28

-2 13

-3 29

-2 14

-3 30

-2 15

-3 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) 1724n

s.

UNITSIIU1 DOWNS AND POWER REDUC 110NS DOCKET NO. 50-259 UNIT NAME One DATE 11-01-88 COMPLETED BY

.I. D. Crawford REPr4RT MONilg October TELEPHONE (205) 729-2507

=

=u c

3 s, =a

=

ai Licensee E-r j%

Cause & Ciureceive 23 g

Date g

3g g

,3 g 5 Even 53 o.]

A oiin to

$2 5

j5g Repente ifi0

]O Prevent Recurrence d

315 10-01-88 F

745 F

4 Administrative hold to resolve various TVA and NRC concerns.

s

's l

^

I 2

3 4

m F: F ws:cd Reasim:

Method:

Exhibit G-Instructions S: Ssheduleil A-Equipment Failure (Expain) l-Manual fin Preparasi m of Data a

841aintenanceof Test 2-Manual Scram.

Entry Sheets for Licensee to C-Refueling 3-Automatic Stram.

Evens Repowi(LER) File (NUREG-D-Regulasiw) Resirictium 4-Other ( Englain) 0161)

E Operator Temining & Litense Examinasiim F-AJnumstrative 5

Goperatiemal Erria Explain)

Eshibis t -Same Source l'8/77) lleiher (Explain)

L

b

~

50-260 DOCKET NO.

UNIT SilU1 DOWNS AND POWER REDUCTIONS UNIT NAME Two DATE 11-01-88 REPORT MONiil October COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 o

E c

33 3

j E~

Licensee

,E-r,,

{*?

Cause & Currective Date 3

4 5

E Evens g7

=

e Acti.m to j E 5

3 ;f, =

Repixt e mO 5O Psevent Recurrence u

e 6

l 1

l 305 10-01-88 F

745 F

4 Administrative hold to resolve l

various TVA and NRC concerns.

l

.~

l N

N J

A I

2 3

4 m

F: Forced Reasaui:

Metimd:

Exhibit C. Instructitmis S: Stheduled A-Equipnwns Failure (Explain) 1-Manual for Preparati m of Data B-Maintenance ci Test 2-Manual Scram.

En ry Sheets for IJcensee w

C-Refueling 3-Autunutic Strani.

Event Report Ill!R) File INUREG-D-Regulasi. ) Restriction 4-Other IExglaini 0161)

EOperaior Tsaining& litense Exanunanon F-Adannistratise Goperati. mal Essin IExplain)

Eshibit I. Same Source r8/77)

Il4)ther IExplaini

l DOCKETNO. 50-296 UNIT SIIU1 DOWNS AND POWER REI)UCTIONS UNaT NAME Three DATE 11-01-88 COMPLETED BY

.I.

D.

Crawford REPORT MONIH October TELEPHONE (205) 729-2507 l

=

C re

' sa :

53 f c ~4 Licensee 5-e, j",,

Cause & Corrective N...

Date

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g jgE Evens

=?

93 Action to

$2 5

5 g5 =i Report e

'N O E'

Prescas Recurrence a

u 6

157 10-01-88 F

745 F

4 Administrative hold to resolve various TVA and NRC concerns.

s.

N l

I i

l

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1 l

I 2

3 4

m F: Finced Reason:

Metimd:

Exhibit G-Insernctions S: Sttwduleil A-Equipnen Failure (Explain) 1-Manual for Preparati.m of Data 8-Maintenance ci Test 2-Manual Scram.

Entry Sheets for Licensee w

C-Refuelin:

3-Antomatic Stram.

Event Repin:(LER)FileINUREG-D-Regulatory Restrictiim 4-Other t Exglain) 0161)

E-Operator Training & Latense Examination F-Adnunist rat a se 5

G4)perati. mal Erein IExplain)

I his 1 - Same Source cr/77)

II4)iher IExplaini t

e

U TVA 73aWOP&4 82 NUCLEAR PLANT OPERATING STATISTICS Browns Ferry Nuclear Plant s

Period Hours 745 Month October 19 88 Item I

No.

Unit No.

UNIT 1 UNIT 2 UNIT 3 PLANT 1

Averace Hourly Gross t.oad, kW 0

0 0

0 2

Maximum Hour Net Generation. MWh 0

0 0

0 1

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

0 0

0 l

4 Steam Gen. Thermal Energy Gen., GWD (t)2 0

0 0

_0 l

j 5

Gross Electrical Gen., MWh 0

0 0

0 t

6 Station Use, MWh 4,855 2.085 1,696 8,636 7

Net Electrical Gen.. MWh

- 4, 8 5 5__

-2.085

-1,696

-8,636 h

8 Station Use, Percent 0

0 0

0 9

Accum. Core Avg. Exposure, MWD / Ton!

0 0

10 CTEG This Month,100 BTU 0

0 0

0

, 11 SGTEG This Month, IO6 BTU 0

0 0

0 12 13 Hours Reactor Was Critical 0

0 0

0 14 Unit Use. Hours. Min.

0 0

15 Capacity Factor, Porcent 0

0_

0 0

j 16 Turbine Avail. Factor, Percent 0

0 0

0 g, _LZ_

Generator Avail. Factor. Percent 0

0 0

0 g

18 Turbonen Avail, Factor. Percent 0

0 0

0 19 Reactor Avail._Eactor. Percent 0

0 0

20 Unit Avail Factor. Percent 0

0 0

0 21 Turbine startuos 0

0 0

0 22 neactor Coid startuos 0

0 0

0 n

g 24 Gross Heat Rate, Blu/kWh 0

0 0

0 25 Net Heat Rate, stuAWh 0

0 0

0 3

26 C

27 g

28 Throttle Pressure, psig 0

0 0

0 d

29 Throttle Temperature, 'F 0

0 0

0 4

30 Exhaust Pressure, inHg Abs.

0 0

g 31 intake Water Temo., *F 0

0 0

0 H

32 33 Main Feedwater, M Ib/hr y

34 i

l 35 i

36 37 Full Power Capacity, E F PD (3)

(4)

~

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

(4)

(4) j 39 Oil Fired for Generation, Gallons 11,466 2

40 Oil Heatina value. ntu/Gai 139,000 41 Delet Generation. MWh 147 1?

Man. Hour Net Gen.

Max. Day Net Gen.

Load MWh Time Date M Wh Date Factor. %

a 43 0

0 0

Remarks: IFor OF NP this value is MWD /STU and for SONP and WBNP this value is MWD /MTU.

l 2(t) indicates Thermal Energy.

3 3 Information furnished by Reactor Analysis Group, Chattanooga 4 Administrative hold Date Submitted Date Revised P' ant Superintendent

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Page 36 REACTOR POWER PERCENT OCTOBER 1988 UNIT 1 PEACENT 100 90 80 70 60 :

ADMINISTRATIVE HOLD 50 40 30 20 10 0

1 2 3 4 5 6 7 8 9 to 11 12 13 14 15 16 17 15 19 20 21 22 23 24 25 26 27 28 29 30 31 UNIT 2 PERCENT 100-90 80 70 60 50 ADMINISTRATIVE HOLO 40 30 20 10 0 1 2 3 4 5 6 7 8 9 to 111213141516171819 20 2122 23 24 25 26 27 28 29 30 31 UNIT 3 PERCENT 100 90 80 70 60 50 ;

ADMINISTRATIVE HOLD 40 30 20 10 1 2 3 4 5 6 7 8 9 to 111213141516171819 20 2122 23 24 25 26 27 28 29 30 31 e

,-e h

4 9

MAIXTEXAXCE

SUMMARY

(

I i

I l

l l

l e

M Pegs 37 e c MAINTENANCE MONTHLY REPORT OCTOBER 1988 I.

MAINTENANCE SUPPORT SECTION A.

Completed lead shielding removal on Unit 2.

B.

Worked SPOC items.

C.

Worked plant pickup and cleanup.

D.

Performed scheduled PMs and MRs work on doors.

E.

Remond insulation on RHR, HPCI, and RCIC in support of ISI ins pec tions.

F.

Completed sandblasting and painted B and C RHRSW pump rooms.

G.

Remond asbestos insulation in support of Chem. Lab remodeling effort.

II.

I & C TECHNICAL A.

Wrote procedures to meet SPOC.

B.

Reviewed impact sheets for design changes.

s a

f t)

Pags 38 III.

ELECTRICAL TECHNICAL SECTION

.l A.

Fuse Control Program B.

Closed numerous workplans C.

Numerous technical revie'es D.

EQ valve program E.

EQ Program F.

ITC's, ECN's, DCN's G.

Relay work H.

Numerous cognizant reviews I.

PMT for relays J.

Failure Investigations K.

Measuring and Test Equipment Program L.

Equipment Program H.

Circuit breaker maintenance N.

Switchyard maintenance IV.

I & C MAINTENANCE A.

Working to place off line Radiation Monitors back in service after Modification Group did the Mod on W2064 and other work plans.

B.

Worked scheduled SI's and PM's also supported refuel load sche dule.

C.

Investigated and initiated action to correct the daficiencies identified in the NRC Inspection Report 88-11 page 21 Item F-1, 2 & 3.

Pags 39 g'

V.

MECHANICAL MAINTENANCE A.

Supported work on systems that were SPOC'd during October.

B.

We did not do any other significant items.

VI.

ELECTRICAL MAINTENANCE A.

Worked b?OC items including MRs, PMs, and sis.

B.

Closed 588 MRs and at present have 56 in "H" status and 150 in "C" s tatus.

C.

12 open CAQRS and closed 3 i

D.

As of 11-04-88 Electrical Maintenance had 107 employees.

1 VII.

MECHANICAL TECHNICAL SECTION A.

Major work activities for the Mechanical Technical Section during the month of October 1988, involwd closing numerous work activities, NRC coamitments, CAQRS, ECN/DCN final closure packages, various instructions which were approved, revised, or cancelled.

l l

l 1

i l

t

9 4

0 0

e OTHER REPORTS I

e

Pcge 40 5

~

CHEMISTRY

SUMMARY

OCTOBER 1988 Primary Coolant Chemistry Unit 1 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 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.

UA1.L2 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 l

chloride have not been exceeded.

1724n t

P gs 41 PRIMARY COOLANT CHEMISTRY OCTOBER 1988 Parameter Unit 1 Unit 2 Unit 3 1.

Cross Radioactivity a.

Crud (filter) (uci/ml)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A b.

Filtrate (pci/ml)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 2.

M111 pore 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 (pel/ml)

High 4.13E-5 5.29E-5 1.093-4 Low 3.08E-5 4.54E-5 1.04E-5 Average 3.56E-5 4.77E-5 1.05E-4 4.

Iodine-131 (pel/ml)

High

<1.08E-6

<1.16E-6

<5.84E-7 Low

<5.56E-7

<3.778-7

<3.01E-7 Average

<8.31E-7

<8.45E-7

<4.15E-7 i

5.

Todine-131tiodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Averago N/A N/A N/A 1724n 1

i f

e

-. ~. - -. - - - - --.._--.

Pcg2 42 PRIMARY COOLANT CHEMISTRY (Continued)

OCTOBER 1988 Parameter Unit 1 Unit 2 Unit 3 6.

Chloride (oobl High <10

<10

<15

<10 Low <10

<10

<10 Average

<10

<10 7.

DH025*C High 6.2 6.2 6.1 Low 5.7 5.8 5.8 Average 6.0 6.0 5.9 8.

Conductivity (vmho/cm025'C)

High 0.24 0.93 0.30 Low 0.081 0.52 0.24 Average 0.10 0.77 0.26 1724n l

l

L Pags 43 ENVIRONMENTAL TECHNICAL SPECIFICATION REOUIREMENTS OCTOBER 1988 The ambient upstream river temperature (24-hour average) ranged from 75.5'T (October 1) to 60.4'F (October 31) with an average of 66.6'F.

The 24-hour average downstream temperature varied between 74.9'F (October 1) and 60.6*F (October 31) with a monthly average of 66.9'F.

The largest temperature change occurred on October 6 (1.5') while the monthly average was 0.6*F.

Chlorination of the Emergency Equipment Cooling Water System continued though the month.

It should be noted that a few larval clams were found in the water column. The raw cooling water system feeding the high pressure fire protection system is being made ready for the November chlorination of that system.

The sedimentation pond, removed from service November 2, 1987, is still waiting for permanent repairs.

The oevage lagoon operated within permit parameters during the month. The total suspended solids ranged from 60 ppm (October 2) to 38 ppm (October 31) and the biological oxygen demand had a high reading of 30 ppm (October 11) and a low reading of 13 ppm (October 24).

Y d

l 1724n

Pcge 44 AIRBORNE RELEASES (1')

j OCTOBER 1980 n

~

SUMMATION OF ALL RELEASES UNIT THIS MONTH A.

FISSION AND ACTIVATION OASES 1.

TOTAL RELEASE CI

< 1 39E 02 2.

AVERAGC RELEASE RATE FOR PERIOD UCI/SEC

< 5.75E 01 3.

PERCENT OF TECH. SPEC. LIMIT (0.15 CI/SEC) 0 00E-01 8.

IODINES 1.

TOTAL IODINE - 131 CI

< 4.82E-04 2.

AVERAOC RELEASE Rort FOR PERIOD UCI/SEC

< 1.99E-04 3.

PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 j

C.

PARTICULATES 1.

PARTICULATES WITH HALF-LIFES > OR = TO 8 DAYS CI 3.40E-05 i

2.

AVERAGE RELEASE RAfC FOR PERIOD UCI/SEC 1.41E-05 3.

PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 6.44E-04 4.

GROSG ALPHA RADIDACTIVITY CI 1.07E-05 D.

TRITIUM l

1.

TOTAL RELEASE CI 9.20E-03 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 3.04E-03 3.

PERCENT OF TECH. SPEC. LIMIT (2 19 UCI/SEC)

X 1 75E-01 i

i 4.

GROUND LEVEL RELEASE CI 9.20E-03 l

5.

CLEVATED RELEASE CI

< 3 04E-04 i

(1)

REPORTING FERIOD 20 DAYS

Pega 45 AIRBORNE RELEASES..(, CONTINUED)

+

OCTOBER 1988 ELEVATED RELEASES A.

FISSION GASES UNIT THIS MONTH KR-85M CI

< 1 01E-01 KR-85 CI

< 3.70E 01 KR-87 CI

< 2.60E-01 KR-88 CI

< 3.72E-01 XE-133 CI

< 2 47E-01 XE-135M CI

< 2.99E-01 XE-135 CI

< 1.d7E-01 XE-138 CI

< 6.10E-01 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 3.90E 01 B.

IODINES I-131 CI

< 6 30E-05 I-133 CI

< 1.23E-04 I-135 CI

< 4.51E-02 TOTAL FOR PERIOD CI

< 4.53E-02

I' AIRBORNE RELEASES (CONTINUED)

OCTOBER 1988 ELEVATED RELEASES C.

PARTICULATES UNIT THIS MONTH SR-89 CI

< 3.66E-07 SR-90 CI

< 1.46E-07 CS-134 CI

< 9.13E-05 CS-137 CI

< 7.74E-05 BA-140 CI

< 8.76E-05 LA-140 CI

< 1.63E-04 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 4.20E-04 D.

TRITIUM CI

< 3 84E-04

i Pqgo 47 AIRBORNE RELEASES (CONTINUED) i OCTOBER 1988 l

OROUNO RELEASES A.

FISSION GASES UNIT THIS MONTH KR-85M CI

< 1.81E-01 KR-05 CI

< 9.33E 01 KR-87 CI

< 6.23E-01 d

KR-88 CI

< 7.85E-01 t

l XE-133 CI

< 7.91E-01 t

XE-135M CI

< 1 70E 00 XE-135 CI

< 2 32E-01 XE-138 CI

< 2.51E 00 OTHERS(SPECIFY)

TOTAL FOR PERIOD t

i CI

< 1 00E 02 i

i i

B.

IODINES I-131 CI

< 4 19E-04 i

i 1-133 CI

< 2 39E-03 1

I I-135 CI

< 3 71E 00 4

t a

TOTAL FOR PERIOD f

I l

CI

< 3.71E 00 l

i i

l l

1 i

k f

I i

1-I

[

l 4

i f

6 e

Pcgn 48 AIRBORNE RELEASES'4 CONTINUED)

_------___-~~~~...

OCTOBER 1988 GROUND RELEASES C..

PARTICULATES UNIT THIS MONTH

--~~~-----

SR-89 CI

< 1.62E-04 SR-90 CI

< 5 95E-05 CS-334 CI

< 4.90E-04 CS-137 CI 3.40E-05 BA-140 CI

< 7.45E-04 LA-140 CI

< 6 59E-04 OTHERS(SPECIFY)

TOIAL FOR PERIOD CI 3.40E 05 D.

TRITIUM CI 9.28E-03 I

4 J

P0g3 49 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULAYIONS LIOUID RELEASES OCTOBER 1900 RADIDACTIVE LIOUID EFFLUENTS 1.

GROSS RADI0 ACTIVITY UNITS a)

TOTAL RELEASE LURIES 1.37E-02 b)

AVERAGE DILUTt.'D CONCENTRATION RELEASED UCI/ML 1.00E-09 l

c)

PERCENT Or APPLICADLE LIMIT ( 1E-7 UCI/HL )

1.00E 00 l

l 2.

TRITIUM a)

TOTAL RELEASE CURIES 8.64E-02 b)

AVENAGE DTLUTED CONCENTRATION RELEASED UCI/ML 6.34E-09 c)

PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 2.11E-04 1

1 (1) 3.

DISSOLVED NOBLE GASES

(

a)

TOTAL RELEASE CURIES

< 0 62E-04 l

b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML

< 6.32E-11 1

c)

PERCENT OF Af'PLICABLE LIMIT (2E-04 UCI/ML)

< 3.16E-05 4.

GROSS ALPHA RADIUACTIVITY l

a)

TOTAL RELEASE CURIES

<2.20E-04 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML

<1.62E-11 5.

VOLUME Or L;DUID WASTE TO DISCHARGE CANAL LITERS 4 12E 06 A.

VOLUME OF DtLUTION WATER LITERS 1 36E 10 (1)

INCLUDES XE-133, XE-135e AND OTHERS

e Pags 50 BROWNS FERRY HUCLEAR PLnHT MONTHLY REPORT CALCULATIONS LIQUID RELEASES OCTOBER 1988 ISOTOPES RELEASED UNITS CI CR-51

< 2.13E-03 MN-54

< 2.46E-04 CO-58

< 2.20E-04 FE-59

< 4 73E-04 CD-60 1.57E-01 ZN-65 3 19C-04 NB-95

< 2.10E-04 2R-95

< 3 74E-04 NOTC-99N

< 1.??C-04 I-131

< 0.77E-04 XE-133

< 7.05E-04 i

CS-134 1.95E-03 XE-135

< 1.57E-04 CS-137 l

9.74C-03 f

DA-140

< 1.06E-03 l

l LA-140

< 2.25E-04 CE-141

< 3,;oc_o4 l

SF:-09

< 1.21E-04 SR-90

< 5.4iE-05 1

1 Q

Prg2 51 BROWNS FERRY NUCLEAR PLANT MONillLY REPORT CALCULAfIONS LIQUID RFLEASES OCTOBER 190fl OTHERS UNITS C1 SB-125 0.64E-05 HF-181 0.45E-06 FE-55

< 9.93E-04 I

i u

T 1

Pcge 52 BROWNS FERRY NUCLEAR PLANT x

MOMI'llt.Y RFPORT CALCUL A TIONS LIQUID RELEASES OCTOBER 1900 l

l LAUNDRY DRAIN VOLUME RELEASED:

00 GALLONS FLOUR DRAIN VOLUME REl. EASED:

1088602.0 GALLONS WASTE SAMPLE T ANK VOLUME RE LE ASED:

0.0 GALLONS DIS T I Lt. A TE T ANK V OL'.'ME REl.EASEDI 0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME RELEASLol 00 0ALLONS TOTAL VOLUllE REl. EASED TO THL RIVER:

1088602 0 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR MONTH!

1.05E-09 UCI/ML A/D LONGEST RELEAtit TIME FOR MONTH:

305 MINUTES SHORTEST RELEASE TIME FOR MONTH!

145 MINUTES TOTAL TIME UF RFLEASES FOR MONTH:

G998 NINUTES AVERAGE TIME FOR BATCH RELEASES 237 MINUTES NUMBER OF BATCHES REl. EASED:

38 NUMBER OT ADMINISThATIVE LIMIT VIOLATIONS!

O NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS:

O c

\\

e l

Pcas 53

+

s e

RESIN USACE kEPORT OCTOBER 1988

,' i RF'.IN CONSUMED (CU.IT.)

% of Total 3.t.ad POWDEX ECODEX ECOSORB EPIFLOC I.otal i

padvaste Floor Drain Filter 41.1 0

120 0

0 57 117 Waste Domineralizer 0

0 0

Waste Filter 32.0 0

136 0

2 0

138 Fuel Pool Domins 3.7 0

16 0

0 0

16 Riantor water Clean m Unit 1 0.5 0

2 0

0 0

2 Unit 2 1.9 0

a 0

0 0

8 Unit 3 0

0 0

Cond. Demins l

Unit 1 0

0 0

Unit 2 20.8 0

90 0

0 0

90

{

Unit 3 0

0 0

Totals 100 0

372 0

2 57 431

^

}

i i

1724n t

l j

Pass 54 e

FUEL CLADDING INTEGRITY PARAMETERS OCTOBER 1988 Unit 1 Reactor Water Iodines (uci/sec.)

Date I-131 I-132_

I-133 I-134 I-135 Unit in Outage Fission Gases at Discharme of SJAE (uci/see)

DLt.1 21gy tEt Xe-138

), r-8 7.

Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (uci/sec.)

Date I-131 1-132 I-133 I-134 M *.L Unit in Outage Fission Giggs at Discharme of SJAE (uci/see)

Ralt fley t!!dt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.)

Date I-131 I-132_

I-133 I-134 I-135 Unit in Outage Fission Gases at Discherme of SJAE (uci/see)

DAlt 11gy tEt Xe-131 Kr-87 Kr-88 Kr-65m Xe-135 Xe-133 Unit in Outage 1724n

1 WASTE TREATMENT SYSTEM THROUGHPUTS OCTOBER 1988 FLOOR FLODR FLOOR DRAIN DRAIN DRAIN

, 3,3,,

3,3,,

sa: 1.o9E+

COLLECTOR FILTER SAMPLE sa: 1.osE+os TANK TANK ca on: m.co sN 1.o9E m erd: o.osE

1I II LAUNDRY sa: e.coE W EPD: o.osE+os DRAIN CANAL _

TANK spit 3.51E+6i m 3.snm

,,,,, 3 sa: 1.osE+os ECYtifD MTER WD:

7. M +o3 sR: 2.CE+o5 N

ifIfif l

WASTE WASTE WASTE WASTE ern: o.osE+oo COLLECTOR SAMPLE FILTER DEMINERALIZER TANK TAtM j

til an: 13s.co G an:

o.co sE: 1.eE+o6 (1) an ronDe us.co.an EsIN s nem MIxme o.co. a n u nso m:

2.co CONDENSATE y,

3,,,

e OR PoWDC 12o.co.an RESIN s HEER NIXMe 57.oo.an ECmDm:

e.oo E

1. m m STORAGE G EAD fE3IN TANK

9 Pege 56 0

L.

4 g'

TESTING SUPMARY g

OCTOBER 1988 Surveillance Testina Unit 0 A total of 141 surveillance tests were completed using 43 different test instructions.

Unit 1 A total of 84 surveillance tests were completed on unit i using 25 different test instructions.

Unit 2 A total of 116 surveillance tests were completed on unit 2 using 55 different test instructions.

Unit 3 A total of 85 surveillance tests were completed on unit 3 using 21 different test instructions.

1724n

__________________________________--_______O

Pago S7

's o

TESTING

SUMMARY

(CONTINUED)

OCTOBER 1988 1

channes. Tests. and Erneriments Reauirinz Authorization From the NRC Pursuant to 10 CPI 50.59(a)

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

Channes. Tests. and Erneriments not Reauirina Authorization from NRC Pursuant to 10 CFR 50.59fa)

There were two special tests completed for this month.

ST 87-25

Description:

To gather data and evaluate the flows and pressures to the RHR heat exchangers.

ST 87-31

Description:

Control Bay Emergency Pressurization and Leak Rate Test to l

Verify that the design differential pressure can be l

established and maintained by the CB-HVAC (31) Emergency Pressurization System (CREYS) under postulated worst-case

{

i conditions.

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o Pege 58 0

,5 REACTOR VESSEL FATIGUE USAGE EVALUATION OCTOBER 1988 The cumulati're usage factors for the reactor vessel are as follows:

Usame Factor Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29182 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 l

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9

o Pega 59 CHANGES IN PROCEDURES OCTOBER 1988 There were 531 revisions to plant instructions during the mouth; 523 instructions were changed primarily for correction; and 8 revisions related to safe operation of the plant.

l PLANT INSTRUCTION REVISJpH1 l

OCTOBER 1988 CateRory Instruction Reason for Recuest Change in response Instruction SI 4.11.A.1.g To incorporate SDSP 2.14 to LER IE Bulletin, Building Hydraulic review.

NRC Inspection Report, Performance Verification OPQA Audits, etc.

I SI 4.5.C.1(1) ;3RSW and To incorporate NRC comments EECW System Valve and close Licensing commitment Operability Test SLT 861087005.

1-SI-4.5.C.1(2) EECW Pump To incorporate NRC comments Operation Surveillance and close Licensing commitment Instruction SLT 861087005.

2-SI-4.5.C.1(2) EECW Pump To incorporate NRC comments Operation Surveillance and close Licensing commitment Instruction SLT 861087005.

3-SI-4 b.C.1(2) EECW Pump To incorporate NRC comments and Operation Surveillance and close Licensing commitment Instruction SLT 861087005.

1-SI-4.5 C.1(3) RHRSW Pump To incorporate NRC comments and Header Operability Flov and close Licensing commitment rest SLT 861087005.

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't Pogs 60 e,

5 PflMT 'NSIEUCTION REVISIONS OCTOBER 1988 Catemory Ins t ruct ion Reason for Reauest Change in Response to 2-SI-4.5.C.1(3) RHRSW Pump To incorporate NRC comments LER, IE Bulletin, NRC and Header Operability Flow and c1cse Licensing commitment Inspection Report, OPQA Test SLT 861087005.

Audit, etc.

0-SI-4.5.C.1(4) EEri System To incorporate NRC comments Annual Flow Rate Test and close Licensing commitment SLT 861087005.

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O '

Pego 61 o

-(,

a CHANGE.1 IN PLANT ORGANIZATION d'

OCTOBER 1988 There was one change in plant staff for those positions designated as key supervisory positions, Barry W. Hargis, Supervisor, Maintenance Planning and Technical.

I J

l h

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0 Pego 62 c,

. c:.

ACCIDENTS OCTOBER 1988 There was one loss-of-time accident during the month.

l l

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l l

TENNE 2SE LEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 2J602 NOV 21 poo U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C.

20555 Attention: Office of Management Information and Program Control In the Matter of the

)

Docket Nos. 50-259 Tennesoco Valley Authority

)

50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - OCTOBER 1988 Enclosed in the October 1988 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY Guy G. Campbell Plant Manager j

Enclosure cc: INPO Records Center Mr. S. D. Richardson, 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 Mr. Ted Marston, Director Electric Power Research Institute P. O. Box 10412 Palo Alto, California 94304

. ;l11l4{

- _ f' i\\

An Eaual Opportunity Ernptoyer.

s

ML20195G702

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