Text

Monthly Operating Repts for Sept 1988 for Browns Ferry Nuclear Plant Units 1,2 & 3.W/undated Ltr
	ML20205A566
Person / Time
Site:	Browns Ferry
Issue date:	09/30/1988
From:	Campbell G; TENNESSEE VALLEY AUTHORITY
To:	; NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
	NUDOCS 8810260027
	Download: ML20205A566 (70)
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43.0 88101s 014 MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY SEPTEMBER 1988 "Safety and Quality are Paramount" '

DOCKET NUMBERS 50-259, 50-260 AND 50-296 LICENSE NUMBERS OPR-33, OPR-52, AND GPR-68 l

Subinitted by:

f Guy G. Carnpbell Plant. Manager i

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8910260027 DR G80930 ' i ADOCh 0500 9 I

7 TABLE OF CONTENTS PART I OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B. Fuel Performance rnd Spent Fuel Storage Capabilities Summary..... 2 C. Main S team Relief Valve (MSRVs) Actuation Summary. . . . . . . . . . . . . . . . 5 D. I s suan c e o f S p e c i a l R e po r t s S umma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 E. Licensee Event Reports Summary................................... 8 F. Offsite Dose Calculation Manual Changes......................... 14 G. R a d w a s t e S umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15

1. Total volume of solid vaste shipped off site

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

3. Cross curie activity

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

5. Estimated quantities of spent resin in storage.

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

7. Waste type and volume of radwaste containers that are onsite avaiting shipment.

PART II OPERATING STATISTICS A. NRC Reports

1. Operating Data Report....................................... 24

2. Average Daily Power Leve1................................... 27

3. Unit Shutdowns and Power Reductions......................... 30 B. TVA Reports

1. Plant Operating Statistics.................................. 33

2. Plant Operating Statistics Fiscal Year...................... 34

3. Unit Outage and Availability Data........................... 35 4 Reactor !!istogram (Reactor Power Percent) . . . . . . . . . . . . . . . . . . . 38 1724n

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-Part III MAINTENANCE

SUMMARY

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

1. Primary Coolant Chemistry .................................. 41

2. Environmental Technical Specification Requirements.......... 45

3. Airborne Releases........................................... 46

4. Liquid Releases............................................. 51

5. Resin Usage Report.......................................... 55

6. Fuel Cladding Integrity Parameters.......................... 56

7. Waste Treatment System Throughputs.......................... 57 B. T e s t i n g S umm a ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 8 C. Reactor Vessel Fatigue Usage Evaluation.......................... 60 D. Change in Procedures............................................. 61 E. Plant Instruction Revisions...................................... 61 F. Change in Plant Organization..................................... 62 G. Accidents........................................................ 63 Addenda Revision to June 1988 e

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l OPE 3ATIl~AL S" IMAR I

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Page 1 SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

SEPTEMBER 1988 Unit 1 09/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

09/30/68 2400 ~ Unit remains on administrative hold to resolve various TVA and NRC concerns.

Unit 2 09/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

09/30/88 2400 Unit remains on administrativo hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continuo.

Unit 3 09/01/88 0001 Unit remains on administrative hold to resolve various

.' TVA and NRC concerns.

09/30/88 2400 Unit remains on administrative hold to resolvo various TVA and NRC concerns.

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a FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

SEPTEMBER 1988 Unit 1 o 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 will involve loading 8x8R (retrofit) 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 lesk rate reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections (LER 32020),

valve leak rate testing modifications (appendix J), HPCI improvements, i

modification of PCIS logic (LER 259 85009), replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), post-accident sampling modifications (NUREG 0737), RPS voltage monitoring modifications, H022sample line modification (LER 81050), and EECW carbon to scainless pipe changeout.

There are zero assemblies in the reactor vessel. The snent 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 E00-1 assemblies. The 252 EOC-6 assemblies were transferred to unit 2 SFSP. The present available capacity of the fuel pool is 1607 locations.

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Page 3 FUEL PERFORMANCE AND SPENT FUEL STORACE CAPABILITIES

SUMMARY

(CONTINUED)

SEPTEMBER 1988 Unit 2-Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. 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 80-11), environmental qualification of 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 nozzio temperature monitorin5 (NUREG 0619), ovaluation of the vent drain and test connections (LER 32020), valvo 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 stainions pipe changoout. l Thero are zero assemblies in the reactor vossol. The spent fuel storago pool presently contains 304 new assemblies, 252 unit 1 EOC-6, 764 EOC-5, 248 ,

EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblics. The 252 EOC-6 assemblics were transferred from unit 1 SFSP. The prosent available capaelty ;

of the fuel pool is 1.229 locations. ,

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FUEL PERFORMANCE AND SPENT FUEL STORACE CAPABILITIES

SUMMARY

(CONTINUED)

SEPTEMBtR 1988 Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold 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 (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV Icak rate reduction modifications, modification of rasonry walls (IEB 80-11), ovaluation of the vont drain and test connections (LER 82020), valve leak rate testing modifications (Appendix J), HPCI concerno, replacement of plant process computer, seismic qualification of piping (IEB 79-02/14), post-accident sampilns modification (NUREG 0737),

addition of redundant drywell control air supply, RpS voltage monitoring modification. If 022samplo line m dification (LER 81050), replacement of jet pump holddown beam assemblies (IEB 80-07). EECW carbon to stainions pipe changeout, and plant design upgrado to seismic qualification.

There are zero assemblies in the reactor vessel. The spent fuel storage pool presently contains 764 assemblies to finish cyclo 6, 248 EOC-5, 280 EOC-4, 376 EOC-3, 97 EOC-2, and 3 EOC-1 assemblion. The prosent available capacity of the fuel pool la 585 locations.

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MAIll STEAM RELIEF VALVE (MSRVs)

SUMMARY

SEPTEMBER 1988 tio MSRVs were challonged during the month.

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5 ISSUANCE OF SPECIAL REPORTS SEPTEMBER 1988 The following special reports are notices of violations issued for the month of September 1988.

88-16-03 1. During an inspection following the November 2, 1987 drywell fire, the following instances in which instructions and procedures were not adhered to for work activities were identified.

A. PMI 8.1 - A TACF war not used to authorize temporary connections through penetration EE for recirculation system valve controls and drywell blower controls performed under -

MRs which should have been considered long-term alterations.

B. Nuclear Quality Assurance Manual (HQAM), Part.III, Section 4.1, requires that Quality Assurance records shall have all blanks filled in or marked N/A. MRs were found with signatures and data missing.

C. PMI 6.2, Conduct of Maintenance, requires that post-maintenance testing be performed on all plant process equipment following corrective maintenance, and some preventive maintenance and trouble chooting activities that might have impaired proper functioning of the component.

No electrical checks of any nature were performed as

. post-maintenace testing following completion of the temporary electrical splices installed under MRs 793993 and 775468 and EMI 7.2.

D. Three of the six fire brigade members who entered the dryvell for fire fighting operations were not qualified for fire brigade duty in accordance with $PP-1,

2. During this inspection, it was identified that chese procedures were not followed.

A. NQAM, Part III, Section 4.1.

B. Site Director Standard Practice 3.7 This is a Severity Level IV violation and is applicab'e to all three units.

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.LSSUANCE OF SPECIAL REPORTS (Continued) 88-18-02 A Condition Adverse to Quality Report was not generated to document a condition adverse to quality that occurred during the conduct of Special Test 88-09.

This is a Severity Level IV violation and is applicable to all three units.

88-22-01 Approximately Jarsary .1987, eht Licensee's line management became aware that four toepo ari!y promo:ed shift engineers did not meet HQAM, Part 11, Sne*. ion 6,4., standards and did not adequately disposition 'Ar ' arue, IP,sddition, it was identified that four other pe;- eabsgaed shift cugineers did not have records to show ths to- ;"1 cation exAninations were successfully passed.

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LICENSEE EVENT REPORT (s)

SEPTEMBER 1988 Descriotion of Event LEE 1-88-023 laadeauate Water Seal Design of piping Floor Penetration Could Cause Flooding of Reridual Heat Removal Service Water Pumo Rooms Durinn Desinn Basis Flood During an inspection of the residual heat removal service water pump rooms, on June 17, 1988, ground water was observed entering the pump room through a subterranean pipe penetration. Modifications to the buried piping just outside the rooms had recently been finished. The origirial fill soil had been replaced with compacted sand. The ground water entering the room was determined to be coming from efforts to further compact the ground for support of a large crane. A review of the penetration drawings revealed that a water seal at the pipe penetration had not been provided and the seal at the floor penetration was inadequate. An engineering evalustion determined that the lack of an adequate water seal was a condition that violated the requirement that the RHRSW pump rooms be water tight. This design deficiency has existed since initial construction of the plant. A water tight seal is being designed and will be installed on the floor piping penetrations of all RHRSW pump rooms.

1-88-024 EDolanned Icolation_ of Secondary C9ataint nt Due to Actuator Diaphrarm Ruotuff_pnd Subsecuent Supply,_ Damper Closure On August 28, 1988, at 0210 hours0.00243 days 0.0583 hours 3.472222e-4 weeks 7.9905e-5 months with all three units defueled, a refueling zone isolation occurred when the pressure differential between the refuel zone and atmospheric exceeded the negative pressure setpoint of one-half inch water gauge.

The large pressure differential was caused by the closure of a unit i secondary containment isolation damper in the refuel zone ventilation supply line. The damper was closed, as designed, by spring force upon loss of air pressure in the actuators Sir chamber when the actuator diaphragm ruptured.

Refuel zone ventilation as returned to service at 0230 hours0.00266 days 0.0639 hours 3.80291e-4 weeks 8.7515e-5 months .

The isolation was caused by the rupture of the diaphragm in the damper actuator. The diaphragm had been in service for over four years. The current preventative maintenance program has j set the frequancy for replacement of the diaphragms at once per 1724n i

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DfscriEtion of Event (Continued)

I&R 1-88-024 refueling outage. Unit I has been shutdown since early 1985 and (continued) the preventative maintenance on these dampers has been deferred until a time closer to unit startup. This is considered an end-of-life failure.

The preventative maintenance frequency for the secordary containment isolation dampers will be revised to once every 24 months.

1-88-026 Violation of Fire Protection Technical Scecificatione Due to Personnel Error On August 30, 1988, at 0830 hours0.00961 days 0.231 hours 0.00137 weeks 3.15815e-4 months with all three Prowns Ferry units defueled, a condition adv1rse to quality report (CAQR),

which identified a condition outside the requirements of the plant's technical specifications (TS), was delivered to the shift operations supervisor (SOS). This CAQR stated that fire doors 643, 644, 659, and 660 were blocked open without proper compensatory measures. TS 3.11.E requires a continuous fire watch be posted on nonfunctional fire barrier penetrations unless a fire detection system on either side of the penetration is operable and a roving fire watch is established. Doors 643,

,' 644, 659, and 660 were blocked open using an existing roving fire vacch without a fire detection system on either side of the doors. A decision was made following a general disqualification of all BFN fire barriers in November 1985 to establish roving l fire watch patrols throughout the plant. At the time of this I decision, the Fire Hazard Analysis was ine.dequate and no well defined fire barrier compartmentation existed. These factors contributed to the inappropriate decision and subsequent compensatory measures. The immediate corrective action was to close these doors and complete the appropriate administrative

controls. The plant's fire protection TSs have been reviewed for similar conditions in other firs protection areas and no i additional violations were found. All fire protection technical i

and engineering staff vill review the CAQR on this event. The i fire protection procedure vill be revised to correctly identify l

the TS requirements for fire barrier penetrations. A new Fire Hazards Analysis which includes defined fire compartmentation has been completed and previously e'abmitted for NRC review.

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(Continued)

LER l-88-028 Emiruncy Eqqippa:nt_c9dinz Water PInsare switcheJ_D^t ProcursIl Lq_Ergper SeispfL,yglifieation O P1aee the P1anL.in_AD Unataly2q11 Condition On February 5,1988, it was discovered that the pressure switches which automatically start the emergency equipment cooling water (EECW) strainer motor had been procured to seismic class II requirements. The EECW cystem is identified as a seismic class I system in the final safety evaluation report.

, Upon discovery of the condition, an evaluation of the required switch qualification level was begun as well as efforts to upgrade the qualification of the present switches to seismic I requirements. On August 31, 1988, a determination was made that the switches must be seismic class I and that t $ switches presently installed could not be upgraded. This condition was caused by inadequate purchasing procedural controls when the pressure switches were originally purchased, 1973.

A design specification defining the seismic requirements for category I electrical and instrumentation and control equipment is in place. This specification ensures that equipment is in compliance with IEEE standards 344-1975. A design change

, request has been initiated to replace the present pressure switches with properly qualified switches. This vill be completed before fuel load on unit 2. In addition, the design oaseline verification program will ensure that existing plant equipment meets applicable design requirements.

2-88-005 ED21rnned EnRineered Safety Feature ActyAligns Due to Inade_quait Procciarra On August 3, 1988, at 1653 hours0.0191 days 0.459 hours 0.00273 weeks 6.289665e-4 months with all three units defueled, unit 2 received spurious low reactor water level signals which completed the tuitiation logic for reactor scram, secondary containment and primary containment isolations of Residual Heat Removal (RHR), Reactor Water 71eanup (RWCU), purging and venting, and Traversing Incort Probe (TIP). The RPS scram function, RWCU, and TIP vere previously disabled and did not actuate. The sp'irious signals were initiated while releasing the clearance on pressure and level transmitters following 1724n

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Description of Event (Continued)

LER 2-88-005 raodifications which relocated the instruments. The sensing (continued) lines vn.re drained during the modification and were not backfilled prior to initially returning the valves to their normal positions. The sensing lines were backfilled and the affected systems were returned to service at 0225 hours0.0026 days 0.0625 hours 3.720238e-4 weeks 8.56125e-5 months the following day.

Several procedural inadequacies were identified which allowed the equipment clearance to be lifted following the modification with an inadequately coordinated plan of action for returning the equipment to service. The workplan procedure will be revised to ensure that a planned sequence exists for the equipment removal and return to service. The clearance procedure has been recently revised and will recuire planned sequences for removing and returning equipment to service. The conduct of maintenance procedure vill be reviewed and revised as necessary to assure that proper guidance is provided to the maintenance personnel when working without a specific procedure under the direction of operations.

2-88-006 480 Volt Shutdown Board Voltane Transient Initiates Engineered

. Egfemuard Features On August 24, 1988, at 1258 hours0.0146 days 0.349 hours 0.00208 weeks 4.78669e-4 months with all three units defueled, the 2EN low pressure coolant injection (LPCI) motoc generator (MG) set was placed in service and tied to its distribution board. Both the LPCI MG set and the 2A reactor protection system (RPS) bus were fed from the 2B 480 volt shutdown board.

The result of this action was the 2C2 RPS circuit protector tripped on undervoltage, deenergizing the 2A RPS bus. This initiated standby gas treatment, control room emergency ventilation, and a half scram on unit 2. The unit ? reactor zone ventilation and the refueling zone isolated. Also, the unit 2 residual heat removal isolation and primary containment ventilation isclation valves closed. The unit 2 remetor water cleanup and traversing incore probe systems receive; and isolation signal but were already isolated at the time of the vent. The apparent cause was an undervoltage condition created 1724n

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Descriotion of Event (Continued)

LER 2-88-006 ott the ,B 480 volt shutdown board when the LPCI MG set was (continued) placed in service. The testing required to establish the actual ciuse has not been completed. The immediate corrective action was to reset the circuit protector, reset the isolations, and return the affected systems to normal. The final determination on the root cause and recurrence control vill be included in a supplemental report.

3-88-002 EDolanned Reactor Water Cleanuo Isolation Due to Personnel Error On August 11, 1988, at 0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months with all three Browns Ferry units defueled, the temperature indicating switch (TIS) monitoring the discharge of the unit 3 reactor vater cleanup (RWCU) nonregenerative heat exchanger initiated an isolation of the RWCU aystem. This isolation function is an engineered safety feature (ESP) of the primary containment isolation system. At the time of this event, plant personnel were decontaminating the panel which houses the TIS. During an investigation ol the cause of the event, the instrument mechanics discovered that the setpoint knob, located on the front of the TIS, was turned from che original calibrated setpoint of 140*F to 52'F. This change in the setpoint has been attributed to inadvertent personnel error during the decontamination process. The TIS was recalibrated to the i original setpoint and the RWCU system was returned to service at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months . This is considered an isolated event since no other j events of a similar nature have been recorded. All i

decontamination crews have been reminded to use caution when l decontaminating any plant panels due to ponsible ESP actuatiens.

3-88-003 Inoverability of Diesel Generators (DG) Due to Seismically Unaualified Batterv Racks Caused by an Inadeauate Procedure On August 26, 1988, at 1350 hours0.0156 days 0.375 hours 0.00223 weeks 5.13675e-4 months with all three Browns Ferry units defueled, DG 3A 3B, and 3D were declared inoperable due to seismic qualification concerns of their battery racks. The batteries and battery racks for DG 3A, 3B, 30, and 3D were installed December 1980. The front cross-braces on the battery racks for DG 3A, 3B, and 3D vere not installed as required by vendor drawings. The omission of these braces resulted from an 1724n

Page 13 Description of Event (Continued)

LER 3-88-003 inadequate workplan which did not include the detail drawings (continued) which depict the correct location of all rack components.

Workplans issued af ter June 13, 1986, are required by a new plant procedure to include all drawings and supportive documentation utilized to implement the workplan. This procedure also requires the work steps to reference any applicable drawings, procedures, or instructions required for work or inspection. The braces and supporting hardware required to ensure that the battery racks conform to the vendor design vere installed. DG 3A, 3B, and 3D vere returned to service on September 10, 1988, at 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , and September 8, 1988, at 0305 hours0.00353 days 0.0847 hours 5.042989e-4 weeks 1.160525e-4 months , respectively. This resulted in DG 3A, 3B, and 3D being inoperable for 14 days, 19 hours2.199074e-4 days 0.00528 hours 3.141534e-5 weeks 7.2295e-6 months , and 47 minutes; 15 days, 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 10 minutes; and 12 days, 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months , and 15 minutes, respectively, t

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OFFSITE DOSE CALCUf.ATION MAlJUAL Cl{ANGES SEPTEMBER 1988

!!o changes were made to the Browns Ferry of fsite dose calculation manual during the month.

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, Page i5 RADWASTE StM1ARY SEPTEMBER 1988 The radvaste system performed as designed. Approximately 1.20E+6 gallons of vaste liquid were discharged containing approximately 1.98E-02 curies of activity. I There was one spent resin shipment and three trash shipments during 3

September. All shipments were to Barnwell, South Carolina.

There were four trash shipments made by the Scientific Ecology Group, radvaste broker / processor, containing BFN waste during September. All !

shipments were to Barnwell, South Carolina.

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Solid Radioactivo Waste

SQptGmber 1988 Pogs 19 -

Dewatere'd Spent Resin Shipments ('

Volume of condensate / waste resin shipped: O Cu.M. ( 0 Cu.Ft.) {

Total curies shipped: 0 t

Volume of reactor cleanup resin shipped: 2.91 Cu.M. (103 Cu.Ft.) j i

Total curies shipped: 6.844 l t

Date Sh,iDoed DiSDosal FacilitV TVDe of Resin L 09/28!88 BarnweLL, SC RWCU Dry Active Waste '

Number of drums shipped: 78 Volumes 16.51 Cu.M. ( 585.0 Cu.Ft.)

Total curies shipped: 0.271 N..mber of boxes shipped: 23 Volumet 62.45 Cu.M. (2213.1 Cu.Ft.)

Total curies shipped: 7.245 Date Shicoed Discosal Facility Tvon~of Packaoe 09/14/88 BarnwelL, SC Drums / Boxes 09/21/88 BarnwelL, SC Boxes 09/28/88 BarnweLL, SC Boxes l Brokered shipments (SEG): 4 Volume: 20.50 Cu.M. C 726.4 Cu.Ft.)

Total curies shipped: 1.611 i Date ShiDDed DiSDosal Facility Tvoc of Packaoe_

l 09/01/88 BarnweLL, SC Boxes

! 09/15188 BarnweLL, SC Boxes 09/21188 BarnwelL, SC Boxes 09/29/88 BarnweLL, SC Boxes 1

(1) AlL shipments were by Sole Use Vehicle

Solid RadiGactive Waste (Continued)

SeptembGr 1988 P:go 17 Summary 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 585 Cu.Ft.(2' 413 Cu.Ft. 2.71E-01 600 Cu.Ft.

2 Boxes 837 Cu.Ft.(2) 279 Cu.Ft. 6.93E+00 800 Cu.Ft.(2)

Uncompacted Drums O Cu.Ft. 0 Cu.Ft. 0.00E+00 0 Cu.Ft.(2)

Boxes 1376.1Cu.Ft.(2' 102 Cu.Ft. 3.16E-01 1200 Cu.Ft.(2 Brokered 726.4Cu.Ft. O Cu.Ft. 1.61E+00 200 Cu.Ft.

Resins CWP5 0 Cu.Ft.(' 2244 Cu.Ft.C3) 0.00E+00 400 Cu.Ft.

I RWCU 103 Cu.Ft.( 180 Cu.Ft.(3) 6.84E+00 35 Cu.Ft.(

TOTALS 3645 Cu.Ft.

2' 794 Cu.Ft."3 1.80E+01 2,600 Cu.Ft.(4)

,' Total volume of waste shipped during the month: 3,645 Cu.Ft. '

Total volume of waste shipped year-to-date: 20,287 Cu.Ft.

Unused 1986 burial volume allocation at Barnwell: 62,513 Cu.Ft.

(1) Actual resin volume (2) Container burial volume (3) Estimated volume in separators (4) Does not include resins

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l 88888888888888 6

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LIQUID RADWADTE p:g, E , ',

SEPTEMDER 1988 TOTAL RIVER RELEASE FLOW RATE (GPM)- ' DATA PLOTTED FOR THE PREVIOUS'12 MONTHS TOTAL RELEASE (CZ) 40 . . 2 FLOW RATE fGAMI 30 . HI 27.81 LOW 15.37 O AVG 21.20 20 . . 1 TOTAL HI O.05 10 . LOW 0.01 AVG 0.02 o FLbMRATE OCT OV kC JAN kB kAR APR AY UN AllG fitP

_ T)MtOUGHPt1T f G At et)

FILTER THROUGHPUTS ,,,,,.

GALLONS X 10 0 HI 0.15E+07 4 ,

LOW 0.86E+0S AVG O.11E+07 3 -

FLOOR DRAIN HI 0.11E+07 LOW 0.66E+08 AVG 0.83E+0S 2 "

E LAUNDRY

< N' 4 ; 7

- m h hw d HI 0.13E+05 LOW 0.00E+00 g , h\ /

/

f///' -

AVG 0.53E+04 0 -

OCT NOV OEC JAN FEB MAR APR MAY JUN JUL AUG SEP C0ST OF OPERATION

comT087fnIunsi THOUSA 0F DOLLARS WASTE HI 0.59E+05 90 .

LOW 0.19E+05

80. m :. _

AVG 0.37E+05

70. -

FLOOR DRAIN 60 .

h, c HI 0.50E+05 LOW 0.21E+05 50 . '

AVG 0.34E+05 40 . '

sN ' LAUNDRY em. HI 0.37E+03 l.

30 .

l.

' LOW 0.00E+00 20 . '

I , -

AVG 0.70E+02

?~iOCT NOV OEC VAN lb . . ..

FED MAR APR PAY JUN JUL AUG SEP

.. . .J

'! ' WASTE COLLECTOR SY'3 TEM LAUNDRY SYSTEM FLCCR DRAIN SYSTEM i

- 8' REACTOR POWER - MWT 23

. UNITS 1, 2 AND 3

~ SEPTEMBER 1988 MWT 3500 -

anoo . .

I UNIT 1: OUTAGE 2000 -

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

500 -

menistry Section

- %****^**#44444#444444Q4544444 DAYS TecMical Services Woms Ferry htsclear Plant REACTOR WATER CONOUCTIVITY UNITS 1, 2, AND 3 SEPTE4BER 1988 UMH0/CM CONDUCTIVITY 1.75 .

UNIT 1 1.5 I CONDUCTIVITY 1.25 -

UNIT 2 g ............................................................

, 0.75 0.5 -

0.25 -

EXPECTED RANGE COLD SHUTDOWN

* * * * * * *

4 @ & O @ # # 4 4 @ S @ @ @ Y @ $ 4 4 @ ACTION LEY Z LIMIT mesistry Sect /on OAYS COLD SHUTDOWN TecMJcol Services koms Ferry httelser Plant REACTOR WATER CHl.0 RIDE UNITS 1, 2 AND 3 SEPTEMBER 1988 PPB So...............................................................

M ORIDE UNIT 1 40 -

CM.CRIDE 3o -

UNIT 2 20 .

CHLORIDE UNIT 3 to -

EXPECTED RANGE ALL C0tO!TIONS

~~~~

%%****^**44&O4'O#A@#4#4Q4554444 m enistry Section DAYS Technical Services koners Ferry httclear Plant

OPERA"'ING S " ' A .' '1 0 1 .. vQ

. oc'

Page 24

. OPERATING DATA REPORT f

DOCKET NO. 50-259 DATE 10-01-88 COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS l Notes l

1. Unit Name Browns Ferry Unit One l l

2. Reporting Periode_ September 1986 l l

3. Licensed Thermal Power (MWt): _3293 l l 4 Nameplate Rating (Gross MWe): 1l52 l l

5. Design Elnctrical Rating (Not MWo) 1065 l [

6. Maulmum Dependable Capacity (Gross MWe) 1098.4 l l ,

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

8. If Changes occur in Capacity Ratings (items Number 3 Through 7) Since last Report, Give Reasons:

N/A

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

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

11. Hours in Reporting Period 720 _

6575 124.255

12. Number of Houes Reactor Was Critica! 0 0 59.521.38

'13. Reactor Reserve Shutdown Heurs 0 0 6.997.44

14. Hours Generator On-Line 0 0 58.267.26

15. Unit Reserve Shutdown Hours 0 0 0

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

17. Gross Electrical Energy Generated C MI) 0 0 55.398.130

18. Net Electrical Enwrgy Generated (MWH) -4994 -38961 53.642.512

19. Unit Service Factor 0 0 46.90

20. Unit Availability Factor 0 0 46.90 {

21. Unit Capacity Factor (Using MDC Net) 0 0 40.53 L

22. Unit Capacity Fector (Using DER Net) 0 0 40.53 _

23. Unit For ad Outage Rate 100 100 44.79 i

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

i I

25. If Shut Down At End Of Report Period. Estimated 04te of Startup To be determined 5

26. Units in Test Status (Prior to Corvuircial Operatiec): Forecast Achieved INiilAL CRITICAlliY INiilAL ELECTRICITY COMMERCIAL OPERAll0N (9/77) ;

1724n

Pags 25 .

OPERATING DATA REPORT ,

, 00CKEi NO. 50-260 DATE 10-01-88 COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 P

OPERATING STATUS l Notes l

l. Unit Nam Browns Ferry Unit Two l l

2. Reporting Period: September 1988 ._

l l

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

4 Nameplate Rating (Gross MWe): 1852 l l

5. Design Electrical Rating (Not MWe) 1065 l l .

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

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

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

N/A

9. Power Level To Whech Restricted, if Any (Not MWe): N/A

10. Reasons for Restrictions, if Anyt N/A [

This Month Yr-to-Cate Cumulative

11. Hours in Reporting Period 720 6575 119.142.00

12. Nurdner of Hours Reactor Was Critical 0 0 55.860.03

13. Reactor Reserve Shutdown Hours 0 0 14.200.44

14. Hours Generator On-Line 0 0 5.t . 3 38. 36

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 153.245.167

17. Gross Electrical Energy Generated (MWH) 0 0 50.771.798

18. Not Electrical Energy Generated (MWH) -2026 -18721 49.165.112 i

19. Unit Service Factor 0 0 45.60

20. Unit Availability Factor 0 0 45.60 I

21. Unit Capacity Factor (Using NDC Net) 0 0 38.74 f

22. Unit Capacity Factor (Using DER Net) 0 0 38.74

23. Unit Forced Outege Rate 100 100 44.27 I

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

i i

25. If Shut Down At End Of Report Period. Estimated Date of ',tartup To he determined

26. Units in Test Status (Prior to Carercial Operation): Forecast Achieved r

INITIAL CRITICAllTY , f INITIAL ELECTRIC 11Y ,

COMMERCI AL CPERATION L (9/77) ,

t 1724n (

)

- Page 26 I

. OPERATING DATA REPORT DOCKET NO. 50-2 %

DATE J0-01-88 ,

COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 r

OPERATING STATUS l l Notes l ,

l. Unit Nano: Browns Ferry Unit Three l l

2. Reporting Period: Sootember 1988 l l

3. Licensed Thermal Power (MWt): 3293 l l 4 Nameplate Rating (Gross MWe): 1952 l l '

5. Design Electrical Rating (Not MWe) 1065 l l

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

7. Maximwn Dependable Capacity (Not MWe) 106's l l

8. If Changes Occur in Capacity Ratings (ltems NAer 3 Through 7) Since Last Poport, Give Reasons:

N/A 9 Power Level To Which Restricted, if Any (Not MWe): N/A

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

This Month Yr-to-Cate Cwwlative ;

I

11. Hours in Reporting Period 720 6575 101.567.C0 i

12. Number of Hours Reactor Was Critical 0 0 45.306.08 f

13. Reactor Reserve Shutdan Hours __ 0 0 5.149.55 !

14. Hours Generator On-Line 0 0 44.194.76

15. Unit Paserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 131,068.267 ;

17. Gross Electrical Energy Generated (MWH) 0 0 43.473.760 t

18. Not Electrical Energy Generated (MWH) -1771 -19239 _ 42.021.909

19. Unit Service Factor 0 _

0 43.51 ,

20. Unit Availability Factor 0 0 43.51

21. Unit Capacity Factor (Using MOC Net) O C 38.84

22. Unit Capacity Factor (Using DER Net) 0 0 38.84 ,

23. Unit Forced Outage Rate 100 100 47.91

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

25. If Shut Co n At End Of Report Period, Estimated Date of Startup to be determined

26. Units in Test Status (Prior to Carercial Operation): Forecast Achieved INITIAL CRiflCALITY INITIAL ELECTRICliY COMMERCIAL OPERAll0N r

(9/71) ,

E i

1724n i

l l

Pago 27 , .

AVERAGE DAILY UIIIT POWER LEVEL ,

DOCKET NO. 50-259 Unit One DATE 10-01-88 COMPLEILJ BY J.J. Crawford TELEPl!0NE (205)729-2507 M0!!Ti{ __jlPTEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POVER LEVEL ;

(MWe-Net) (fNe-!Ie t) 1 -7 .. 17 -7 2 -7 18 -6 3 -8 19 -7 4 -14 20 -7 i

5 -7 21 -8 -

6 -8 22 -4 _

7 _

-7 23 -5 8 -7 24 -6 9 -6 25 -6 .

10 -8 26 -3 -

l 11 -8 27 -7 12 -7 28 -7 13 -7 29 -7 14 -7 30 -7 t

15 -7 31 i l

l 16 -6 i 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 i

Pago 28 AVERAGE DAILY UNIT PO',!ER LEVEL DOCKET NO. 50-260 Unit Two DATE 10-01-88 COMPLETED BY J.D. Crawford TELEP110NE (2051729-2507 MONTil SEPTEMBER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (tNe-Ne t) 1 -3 17 -3 2 -3 .18 -3 3 -3 19 -2 4 -5 20 -1 5 .__._ -2 21 -2 6 -2 22 -1 7 -3 23 -1 8 -2 24 -3 9 -L 25 -3 10 -7 26 -3 11 -3 27 -4 12 -3 28 -3 13 -7 29 -3 14 -3 30 -3 15 +1 31 16 -3 INSTRUCTIONS On this format, list the average daily uni': Power level in MWe-Net for each day in the reportinr, month. Compute to the nearest whole megawatt.

17?An (9/77)

~

.Pege 29 . '

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-296 Unit Three DATE 10-01-88 COMPLETED BY J.D. Crawford TELEPl!ONE L2.Q5}729-2507 MONT!! SEP1EMPER 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL L (MWe-Net) (MWe-Net) a 1 -3 17 -3 r 2 -2 18 -2 3 -3 19 -2 4 -5 20 -3 5 -2 21 -2 6 -3 22 -2

.7 , -2 23 -3 8 -3 24 -3 9 -2 25 -3 10 -0 26 -3 11 -2 27 -2 12 -2 . . _ _ 28 -3 13 -2 29 .-3 14 -3 30 -3 15 -2 31 .,

16 -2 INSTRUCTIONS on this format, list the average daily unit p wer level in MWe-Net for each day in f the reporting month. Compute to the nearest whole megavatt.

(9/77) '

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tva neta ion 44u NUCLEAR PLANT OPERATING STATISTICS * '

Browns Ferrv Nucl-ar Plant Period Hours 720 Month N00.tenher gg 88 item No. Unit No. I'NTT 1 PNTT ? UNTT 1 PI M ,

1 Averace Hourly Gross Load kW 0 _

0 0 0 2 Mauimum Mour Net Genarst6on MWh 0 0 0 0 3 Core the<mai 9ercy GenJWO (tl2 0 0 0 0 4 Steam Gen. Thermal Energy Gen., GWO (t)2 _

[ 5 _ Gross Electrical Gen., MWh O O O O

6 Station Use, MWh 4994 .1026 1771 874l 7 Net Electrical Gen., MWh -49064 -2026 -1771 -6791 f

0 8 Station Use, Percent O O O O 9 Accum. Core Avg. E sposure. MWO/Tond 0 0 0 0 10 CTEG This Month,100 BTU O O O O 11 SGTEG This Month,106RTU U 0 0 0 12 13 Hours Reactor was Critical O O O O 14 Unit Use, Hoars Min. O O O O

_l_5 Capacity Factor, Pe'eent 0 0 0 0 j

16 . Turtpne Av ail, Cactor, Percent 0 0 0 0 ,

o !? Gemerator Avail. Factor. Percent 0 0 0 0 g 18 Turoocen Ava? Factor. A*rcent 0 0 0 0

l ') Deletor Avbl F3 Cor_ Dercent 0 0 (i O 4

6 20 Unit Avaet. 7 sctor. Deretat 0 0 0 _ 0 21 Tureene Startuos 0 0 0 0 22 Aegetor Cold Startuos 0 0 0 L

1 y 24 Gross Heat Rate,8tu,kWh O n g g g 25 Net Heat Rate,8tu>kWh 0 g g g 1 26 C 97 g 28 Throttle Prenure. os.4 O O O O g 09 Throttle Temperajure. r o q n o d 10 iw haust Preuure, inh 4 Aos. 0 0 2 0 0 g 31 intaw n Water 'emo., 3 ' 0 0 0 0

> 17

_ _3 3 Main Feeowater, M lb/hr 34 3S 36 37 Fuis Power capacity, UPO ( 1) (4) ( c. ) (4)

M Accum. Cycie Fud Power Days, EFDO (4) (4) (4) j 39 Oil roed f or Generatest dailons 44Ihg 3 40 Oil Hem,aa value.dlyg3Qt i 184(10 M D eu1 Geeeuticin. MWM' 445,2

!?

Ma n. Hour Net Gen. Vas. Day Net Gen._

VWN T.me Cate t

i MWn t,oao f'

I 1 ! Da te Factor. %

a 43 0 I l i 0 I o _

d H ema r k s ? O or 8F NP tms value is MWO/5T U and for 5GNP and W ONP this value is MWO/M TU.

l 2(t) indicates Tbermal Energy.

3 1 Intornation furntshed hv Ke.ic t o r .in.il v 419 broup, l'h.t t t atma g a 4

4 Admitii s t r.s t ive Hold Oate Submitteo _- Cate Aevised f ,[_ M_ o M

w "V 7 etant $ Aerintencent(

. tva numtm+en NUCLEAR PLANT OPERATING STATISTICS

Browns Ferry h.ue l e ti r Page 34 Plan t period Hours M84 Yea rl y Fiscal Year gg88 Item No.

Unit No. I'n i t 1 I?n i t 2 Urit 1 Plant 1 Ayerace Hour!v Gross Load. kW O O O O 2 Vanirrium Nour Net Generat on ..VWh O O O O

~

3 Core Therrnal (netcy Gen. GWO {t}2 d O O O 4 $leam Gen. Thermal Energy Gen., GWO (t)*'

j S Gross Electrical Gen. MWh _

O O O O 1 6 $tation Use MWh 4 $5 50 ?R90, il867 104198 l

7 Net Electrical Gen., MWh -4 $30 -2890I -11867 -

- 10/,298 c 8 Station Uw. Percent O O O O 9 Accum. Core Avg. E xposure, MWD / Ton A O O 0 'O

~

10 CTEG This Month.104 BTU O O O O 11 SGTEG This Month,106sTu 1?

13 Hours Reactor Wat Critecal O O O O l 14 _ Unit Use, Hours. Min. O O O O 15 ppacity Factor, Percent O O O il j 16 Turtpne Avail. Factor, Percent O O 16,n ;,5

} t7 Generator Avail. Fsctor. Dercent O tr 1 e i_, *3,3 g 15 Turboaen, Aat f actor. Percent 0 0 16,6 8,3 l

_1 t1P*ctSr Avail Facter. D8"cent O O l4,h ; ,5 4

20 Unit Av u. Factor oarcent O O O O j 21 Turbine Starun U O O l}

_. 22 Reactor Cold Startues O O O O

?3

> 24 Grou Heat Rate. Stu/kwh O r

O O u g 25 N_et Heat Rate, StujkWn il O O fl 3 26 5 ??

{Q1 Throttle Pressure eseg O O O U g 79 Thre ttle Temperature. 'F 0 0 0 n j 10 E = haust Dressure, inHg Abt. O O O O

~

j ll intJk e Water 'emo. 'T O O O O -

1? l

'J 3 . Main f eedwater. M st/hr O O O o 34

M 36 37 Full Pnwer C_Jpacity, E F PO f 1) ( 4.) (4) 1 J 's t 4 )

38 ' Accum Cycle Fui Pnwer 0254. EFPO (3) (*1 (;) 'O(4) y 19 Oil Fieco for G rneration. Gallons ) 9 4 7.+ /

Ai 40 Oil Heatino Vatue. 8tuiGat l I"h ' 2 i

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J .* ( g Cate _ _F actor. %

i

i 1

43 0 o I

l 1 O I O ./

$ Rematk%: A f nr Of NP that value is MWO/STU ano for SCNF Jod WONP this vaiue in M AO,M TV.

-j Ut) indicates inef re as Eneeny.

_ 1 !nt im it t on t u rn isheti nv Re.wtor .\ n a i s s . s troup, Cha t t.inana 4 Mm a nis t rat ive hold g

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OJte Submitted 04te Revited

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Page 38 REACTOR POWER PERCENT SEPTEMBER 1988 UNIT 1 FERCENT 100 -
90 -
80 -
1 70 -
50 -
a:t V::'~ m :* = n . .
, 40 -
30 -
20 -
SC -
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 13 16 11 19 19 20 21 22 23 24 25 26 27 25 23 30 UNIT 2 PESCENT 10Cr 90 -
80 -
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1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 19 19 20 21 22 23 24 25 26 27 20 29 30 UNIT 3 PEACENT 100 -
90 -
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70 -
60 -
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30 ,
20 -
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s O' .t 1 2 3 4 'i ti 7 tl 9 10 11 12 13 14 15 10 11 1B 19 LJ 21 22 23 24 2S 26 2 7 28 2'J 30 r
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MAIXTE' ~AXCE SUMMA 3 p
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MAINTENANCE I MONTHLY REPORT
, SEPTEMBER 1988 Page 1 of 2
1. MAINTENANCE ELANNING E TECHNICAL A. Valve Group Closed nine workplans and DCNs Revised numercus procedures Performed numerous system and workplan reviews Performed fourteen valve analyses Performed technical ieview on three electrical instructions Urote post maintenance tests for various relays and for the reactor mode switch -
B. E. O. Frogram Awarded contract to Wyle Labs for performing EO program upgrade. Wyle arrived on-site 9/26/88.
C. Thermal Overloads Completed tield testing for fuel load on systems 69. 24, 74 and 219.
issued response on LER 26-8809, Failure of Normal Feeder Breaker for 480V RMOV Board 28.
Closed nine thermal overload workplans on various systems.
D. Circuit Breaker Rebuilds Eighty 4160V breakers and thirty 480/250V breakers were shipped to General Electric for rebuild. Five 4160V and nineteen 480/250V have been returned.
4160V 480/250V Total number to be rebuilt 298 471 Total number rebuilt 14 39 E. Instrument t< Control Major activities involved preparation of instructions and supporting Scaling and Setpoint Documents to sur.nort the plant restart test and SI schedule. A total of sixty-eight procedures were sent to word processing.
11. MECHANICAL. ELECTRICAL AND INSTRUMENT MAINTENANCE Major af fort for the conth was directed toward completion of MRs. FMs and sis in support of the schedule for Unit 2 Fuel Load.
Mechanical completed the annual and three year inspection of the 1A diesel Generator. Also completed action required to allow closure of CAOR BFP 871012, 1A D/G Feel Oil Transfer Pump Loss of Frime.
Conducted walkdown reviews of several upgraded procedures.
4
Page 40 -
Page 2 of 2 ,
II. MECHAfJICAL ELECTRICAL AND INSTRUMENT MAINTENANCE (continued)
Support Nodifications, System Engineering and Post Modification Test personnel with the post modification testing of several ECN/DCtJs.
Electrical comraeted five wortplans on thermal overloads, also workplans for 41 and #3 battery charger capacitor changeout, and reactor flood level switch replacement.
III. MAINTENANCE SUFPORT Continued the repair effort in the RHRSW rooms to sandblast and recoat l piping, valves, supports, floors and walls; re-install heat tracing; and reinsulate piping and valves.
l Completed an extensive clean-up, paint effort in various areas of the l control, service and office buildings.
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Page 41 CHEMISTRY
SUMMARY
SEPTEMBER 1988 Primary Coolant Chemistry Unit 1 The conductivity of the coactor 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 chlorido have not boon exceeded.
Unit 2 The conductivity of the reactor coolant remained within technical specification and fuct warranty limits during the month. Chloride concentration and pH af the reactor coolant remained within technical specification and fuel warranty limtes during the month. This calendar year, tho technical specification and fuel warranty limits for conductivity and chlorido have not been exceeded.
Unit 3 The conductivity of the reactor coolant remained withire technical specification and fuol warranty limits during the month. Chlorido concentration and pH of the reactor coolant remained within technical specification and fuol warranty limits during tho month. This calendar year, the technical specification and fuel warranty limits for conductivity and chlorido havo not boon execeded.
1724n
.g.
Page 42
CHEMISTRY
SUMMARY
(Continued)
ODCM Chanagi There were no ODCM changes in the month of September 1988.
1724n
Page 43 1 -
1)* PRIMARY COOLANT CHEMISTRY SEPTEMBER 1988' Parameter Unit 1 Unit 2 Unit 3 l'. Gross Radioactivity
a. Crud (filter) (uci/ml)
High N/A N/A N/A '[
Low N/A N/A N/A Average N/A N/A N/A
b. F8.1trate (pci/ml)
High N/A N/A N/A Low N/A N/A~ N/A Average N/A N/A N/A
2. Hillpore Tron (Fe. ppb)
High N/A .N/A !!/A Low N/A N/A N/A Average N/A N/A fl/A
3. Tritium (pel/ml)
High 4.00E-5 4.498-5 1.08E-4 Low 3.44E-5 4.28E-5 1.02E-5 Average 3.70E-5 4.40E-5 1.05E-4
4. Iodine-131 (uct/ml)
High <1.01E-6 <1.61E-6 <3.14E-7 Low <8.10E-7 <5.998-7 <2.70E-7 Average <9.09E-7 <1.90E-1 <2.97E-7
5. Iodine-131:fodine-133 Rati?
High N/A N/A N/A Low N/A N/A N/A Averago N/A N/A N/A 1724n
b
.' - - I l
. Page 44 ,- -
PRIMARY COOLANT CHEMISTRY'(Continued) -
SEPTEMBER 1988'
. Parameter' Unit 1 Unit 2' Unit 3 3
6. Chloride (pob)
High <10 <10 <10 -
Low <10 <10 <10
,,g Average <10 <10 <10 ,
t, 7. pH925*C ,
l High 6 '. 2 6.1 6.2 Low 5.9 - 5.7 5.8 Averare 6.1 6.0 6.0
8. Conductivity (umho/cm025*C)
High 0.19 0.84 0.25 Low 0.12 0.73 0.11 Average 0.15 0.79 0.17 l'
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, , Pags 45 ENVIRONMENTAL TECHNICAL SPECIFICATION REQUIREMENTS SEPTEMBER 1988 The ambient upstream river temperature (24-hour average) ranged from 81*F (September 1) to 26.3*F (September 29) with an average of 78.4*F. The downstream temperaturo varied between 81.3*F (September 1) and 76.1*F (September 29) with an averago of 78.6'F. The la"gost temperature char.go occurring on September 29 was 1.1* with a monthly average of 0.1.
Chlorir.ation of the Emergency Equipment Cooling Water System continued though the month. The Raw Cooling Water System (Firo Protection) was not required to be chlorinated.
The sedimentation pond is still out of service pending more permanent repairs.
Disruption of nvrmal water flow to plant sanitary systems resulted in an overloading of the mechanical lifting stations which in turn resulted in a dischargo of sewago into the yard drainago system on September 27. Although disruption of the system had a duration of two plus days, an estimated total sewago loss of 10,000 gallons occurred during a two-hour period. Fumps were used to move sowago to holding tanks and thus stop the dischargo after that.
The sewago lagoon operated within permit paramotors during the month. A monthly high of 64 and 19, with a monthly average of 62 and 15, was obtained on tho total suspended solids and D0D3, respectively.
1724n -
. Peg 2 46 . '
A RBORNE REl. EASES (1) ,
SEPTEMBER 1980 SUMMATION OF ALL RFLFASFS UNIT THIS MONTH A. FISSJON AND ACTIVATION DASES
1. f0TAL RF_l. EASE CI < 1.69E 02
2. AL)ERAGE REl. EASE RATE FOR PERIOD UCI/SEC < 5.59E 01
3. PERCENT OF TECH. SPEC. l.IrlIT(0.15 CI/SEC) % 0.00E-01 B. IUDINES
1. 10TAL IODINE - 131 CI < 1.81E-03
2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC < 5.99E-04
3. PERCENT OT TECH. SPEC. LIMIT (2.19 UCI/SEC) % 0 00E-01 C. PARTICULATES -
1. PARTICULATE'S WITH HAl.F-LIFES > OR = TO 8 DAYS CI < 1.28E-02
2. At/ERAGE REl. EASE RATE FOR PERIOD llCI/SEC < 4.24C-03
3. PERCENT OF TECH. SPEC. LIMI T (2 19 LICI/SF C) % 0.00E-01
4. GROHS Al. Pila RA9IOACTIVITY CI 5 39E-06 D. IRIIIUM
1. TO T Al. RELEASF CI 1.18E-01
2. AVER AGE RELE Atic R A l F. FOR PERI 0li UCI/SEC 3.91E-02
3. PERCEN~l DF TECH. SPEC. LIMIT (2.1Y UCI/SEC) % 1.78E 00
4. O R u ll N D 1. E V f. L R El. F A S E CI 1 15E-01
5. ELEVATED RELEASE CI 3.23E-03 (1) RF!'O R r i tlli l'ERIOD 3G DAYS
\
l' . AIRBORNE RELEASES (CONTINUED) Paga 47
, l
~*
SEPTEMBER 1988 El.EVATED RELEASES l
A. FISSION DASES UNIT THIS 110NT H KR-85M CI < 9.92E-02 KR-85 CI < 4.50E 01 Kit-87 CI < 2.77E-01 KR-88 CI < 3.18E-01 XE .133 CI < 2.73E-01 XE-13GM CI < 2.57E-01 XE-135 CI < 9 73E-02 XE-139 CI < 4.56E-01 OTHERG(SPECIFY)
TOTAL FOR PFRIOD CI : 4.68E 01 B. IODINES.
I-131 CI ; 4.52E-06 I-133 CI < 6.60E-05 I-130 CI < 1 11E-01 TOTAL. FOR PERIOD CI < 1 12E-01 L.
AIRD0RNE RELEASES ( CO N T IllU E D ) .Paga 43 ,
SEPTEMBER 1988 ELEVATED RELEASES
_______~_________
C. PARTICULATES UNIT THIS HONTH GR-89 CI < 4 39E-07 SR-90 CI < 1.75E-07 CS-134 CI < 6 09E-06 CS-137 CI < 5.60E-06 BA-140 CI < 1.41E-05 LA-140 CI < 8.46E-06 OTHliRC(SPECIFY)
TOTAL FOR PERIOD CI < 3.49E-05 D, 'TRII'IUM CI 3.23E-03 I
AIRDORHE RE8. EASES ( (;0 H1 I N U E D ) #E*
S E P T E t' R E R 1980 GROUND RELEASES ,
A. FISSIDH GASES UNIT THIS HONTH KR-05M CI < 2.50E-01 KR-05 ,
CI < 1.13E 02 KR-87 CI < 6.27E-01 KR-89 CI < 8 6?E-01 XE-133 CI < 1 04E 00 XE-133N CI < 1 17E 00 XE-13b CI < 2.67E-01 XE-133 CI < 4.49E 00 OTHERS(SPECIFY)
TOTAL FOR PERIOD CI < 1.22E 02 B. IODIMES.
l l I-131 CI < 1 81E-03 I-133 CI < 3.48E-03 I-135 CI < 5.51E 00 T0 rol. FOR PERIOD CI < 5.52E 00 4
Pags 5d r .
AIRBORHE RELEASES (CONTtHUED) .
SEPTEMBER 1980 GROUND RELEASES -
C. PARTICULATES UNIT THIS MONTH SR-HY CI < 2.91E-04 SR-90 CI < 1.09E-04 CS-134 CI < 1.68E-03 CS-137 CI < 2.59E-03 BA-140 CI < 5.61E-03 LA-140 CI < 2.51E-03 OTHERS(SPECIFY)
TOTAL. FOR PERIOD CI < 1 08E-02 D. TRIr[UN CI 1.15E-01 l
. l t
.. . 1 BROWNS FERRY NUCLEAR Pt. ANT Pags 51 f* MONTilLY REPORT CALCULATION!i LIQUID RELEASES SEPTEMBER .1980
)
l RADI0 ACTIVE L30UID EFFLUENTS H 1, GROSS RoDI0 ACTIVITY UNIT 5' a) TOTAL RELEASE CURIES 1.98E-02 b) AVERAGE DILU TED CollCENTRATION RELEASED UCI/NL 1.30E c) PERCENT OF APPLICABLE LIMIT ( 1E-7 UCI/ML ) % 1.30E 00
2. TRITIUM a) TOTAL RELEASE CURIES 1 5?E-01 b) AVERACE DILUTED CutlCENTRATION RELEASED UCI/ML 1.03E-03 c) PERCENT OF APPLICADLE LIMIT (3E-03 UCI/ML) % 3.43E-04 i (1)
3. DISSOLVED fl0BLE GASES

~~--------~~

a) TOTAL RELEASE CURIES < 9.47E-04 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML < 6 23E-11 c) PERCENT OF APPLICABLE LIMIT (2E-04 UCI/ML) % < 3 11E-05 ;
4. OROSS Al.PlfA RADIuACTIV!TY a) I TOTAL RELEASE CURlES <3.04E-04 ,
b) AVERAGE All.llTED CONCENTRAI!ON RELEASED UCI/ML <2.00E-11
!! . VOLUNF OF LIQUID WASTE TO DICCHARGE CANAL LITERS 4.UbE 06
[
k
6. VOLUME OF DILUTION WATER LITERS 1.52E 10 ,
l (1) INCLUDEC XE-133, XE-135, AND OTHFRS
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r BROWHS FERRY NUCLEAR PLANT P.ag2 52 ,
MONTHLY REPORT CALCULATIONS '
LIQUID RELEASES
. SEPTEhDER 1988 ,
6 ISOTOPES RELEASED UNITS o CI CR-51 < 2.56E-03 Mil-54 2,00E-05 CD-SG < 3.03E-04 FE-59 < 6 20E-04 CD-60 2.98E-03 ZN-65 1.93E-04 NB-95 < 2.77E-04 2C-95 < 4.72E 04 N0rC-99H < 2 23E-04 I-131 < 3 3:E-04 l
XE-133 < 7.62E-04 CS-134 2 89E-03
XE-135' < 1.85E-04 CS-137 1.34E-02 BA-140 < 1 22E-03 LA-140 < 2.22E-04 CE-141 < 3.84E-04 SR-09 < 1 34E-04 SR-90 < 6.00E-05 1
e
i s' ,
BROWNG FERRY HUCLEV: PLANT Pags 53 t10NTHLY REPORT CALCULATIONG LIQUID RELE AST.~S SEPTEMBER 1930 OTHERS UNITS CI SB-125 3.01E-04 FE-55 .: t,10t-03 0
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)
BROWHS FERRY ilVCLEAR Flot4T Pago 54 0 HONTHLY REPORT CALCULATIONS ,
LIOUID HELEASES DEPTEt1BER 1900 LAUNDRY DRAIN VOLUME RELEASED: 3270.4 G All.ONS FLOOR DR(IH VOLUME RELEASED: 1122321.4 GALLONS IJAS TE sal 1Pt E TANK VOLUH2 REl. EASED: 70670.2 GALLONS DISTILLATE TANV VOLUME RELEASED: 00 GALLONS LOCATION OTHER IMAN RADUASIE VOLUME RELEASED: 0.0 GALLONS 70TAL. VOLUME RELEASED TO THE RIVERT- 1201290.0 GALLONS HICHEST BATCH ACTIVITY REl. EASED FOR MONTil: 5.20E-09 UCI/ML A/D LONGEST RELEASE TIME FOR MDNrH: 205 MINUTES SHORTEST RELEASE TIME FOR MONT!!: 156 MINUTEG TOTAL TIME OF RFLEASES FOR MONTH: 10046 MIflUTES AVERACE TleiE FOR BATCH RELEASES: 245 NINUTES HUMRER OF DATCHES RELEASED: 41 tiUtiBER OF ADMINISTRATIVE LIMIl VIOLATIONS: 0 NtlMDER OF TECHNICAL. SPECIFICATI0fl VIOLATIONS: 0 b
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Paga 55 s
RESIN USAGE REPORT SEPTEMBER 1988 RESIN CONSUMED (CU.FT.)
% of Total lle.s_4 POWDEX ECODEX ECOSORB F2IILQ_Q Iq1.gL hadvaste Floor Drain Filter 51.9 0 157 0 3 101 261 Waste Demineralizer 0 0 0 0 0 0 0 Waste Filter 29.4 0 130 0 0 18 148 Fuel Pool Demins 0.8 0 4 0 0 0 4 Heactor Water cleanuq tenit 1 0 0 0 0 0 0 0 Unit 2 0 0 0 0 0 0 0 Unit 3 0 0 0 0 0 0 0 Cond. Deming Unit 1 0 0 0 0 0 0 0 Unit 2 17.9 0 90 0 0 0 90 Unit 3 0 0 0 0 0 0 0 Totals 100 0 381 0 3 119 503 h
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FUEL CLADDING INTEGRITY PARAMETERS ,
i+ SEPTEMBER 1988 Unit 1 Reactor Water Iodines (uci/sec.)
Date 'I-131 T-132 I-133 I-134 I-135 Unit in Outage It '
Fission Gasos at Discharge of SJAE (uci/sec) i Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 l
Unit'in Outage Unit 1 Reactor Water Iodines (uci/sec.)
Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Cases at Discharge of FIAE (uci/sec) i Date Flow MWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage t
e
Unit 3 ,
i Reactor Wator Iodinos (uci/sec.)
l Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission cases at Discharge of SJAE (uci/sec)
Date Flow HWt Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Ko-133 1
j Unit in Outago i i t
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WASTE TREATHENT SYSTEM THROUGHPUTS SEPTEMBER 1988 FLOOR FLOOR FLOOR l m 3.7s4 DRAIN DRAIN DRAIN , 3,7 g ,
> an. > -
G C 1.12E+C6 COLLECTOR FILTER SAMPLE GAu 1.12E+06 TAfiK TANK i (2) CIET: 261.00 !
GAL: 1.12E+C6 G* 8
' 4 _. __. _:CCE+M 6A!; 0.00E+C0
...Y- __I LAUNDRY GPO 2.77E*02 QRAIN GAu a.30Ed3 CANAL I ->
g 3,s 3, TANK 'em 4.0cE+04
~ ~ '
1.G B 06 GA!; 1.20E*C6 ECYCLED WATER SP(t 1.22E+04 l 4 l GAL: 3.67E+05 d
. .Y Y 1r ._-_ _ ._ .. _ . _ _ . _ . _ _ . _ . _
WASTE '
WASTE
. WASTE WASTE G a 2.36E+03 ,
COLLECTOR M > SAMPLE
FILTER >'DEMINERALIZER 8* 78 " 4 TAMK 1 TANK l
r m art: 14a.m , ,_ ,
L m m: _ ,0.c0
,. l gat: 1.43E+G6
.- .. . , y I E m curi ecoot 130.00.m EsIn s rnen xIxrue sa.00 .CuFT ECTMR G CR PCGX: 157.00 .QET MSIN & FIBER MIXTtJC 101.00 .CUFT ECD:74iit 0.00 3.00 3 M *04
,'g' CONDENSATE
[
gg STORAGE G BEAD ESIN TANK e
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.' TESTING
SUMMARY
SEPTEMBER 1988 Surveillance Testinx i
Unit 0-A total of 159 surveillanco test.s were completed using 27 different test
.Instruetions.
Unit 1 A total of 61 surveillance tests were completed on unit i usin8 17 different test instructions.
Unit 2 l A total of 91 surveillance tests were completed on unit 2 using 38 different I
test instructions.
-Unit 3 A total of 79 surveillance tests were completed on unit 3-using 25 different test instructions. 3 f
I p
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.y.
,.e, Page 59 TESTING
SUMMARY
(CONTINUED)
SEPTEMBER 1988 ChaDnes. Tests, and Experiments Reauiring Authorization _From the NRC Pursuant 12.10 CFR 5.Q.59(al There were two revisions for units 1, 2, and 3 technical specifications.
Change,s. Tests, and ExogIlments not Recuirinn Authorization from NRC Pursuant t_o 10 CER_50. 59(a)
There were two special testa completed for this month.
ST 87-26
Description:
Gather flow data for various control bay ventilation system lineups through the control room emergency ventilation system units A and B.
? ST 87-31
Description:
Control Bay Emergency Pressurization and Leak Rate Test to verify that the design differential pressure :an be established and maintained by the CB-liVAC (31) Emergency Pressurization System (CREVS) under postulated vorst-case conditions.
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HEACTOP VESSEL FATICUE USAGE EVALUATION SEPTEMBER 1988 The cumulativo usage factors for the reactor vossol are ao fol;ows:
Usar.o Factoe Location Unit _1 Unit 2 n it 3 Shell at water line 0.00620 0.00442 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 4
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CHANGES _Hi PROCEDURES SEPTEMBER 1988 There were 494 revisions to plant instructions during the month; 492 lustructions were changed primarily for correction, and two revisions related to cafe operation of the plant.
PLANT INSTRUCTION REVISIOfLS SEPTEMBER 1988 Cater.ory Instruction Reason for_Reapesi Change in response 2-SI-4.2.B-36( A) !!igh New instruction to provide to LER, IE Bulletin, Pressure Coolar.t Injection for calibration of instrument.
NRC Inspection Report, Turbine Steam Line High OPQA riov, Instrument Channel Calibration, 2PD-73-1A Change in response 2-SI-4.2.B-36(B) liigt: New instruction to provide to LER, IE Bulletin, Pressure Coolant Injection for calibration of instrument.
NRC Inspection Report, Turbine Steam Line High 0FQA riov, Instru.~ent Channel Calibration, 2PD-73-1B 1724n t
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Page 62*
a CHANGES IN PLANT ORGANIZATION j
SEPTEMBER 1988 There were 26 changes in plant staff for those positions designated as key supervisory positions. They were as follows:
Guy G. Campbell, Plant Manager David T. Nye, Head, Grorp, Project Control and Pinancial Services (Capital Projects)
Masoud Bajestani, Supervisor, Section, Technical Support, Systems Engineering Timothy E. Abncy, Supervisor, Section, Technical Support / System Engg/B-0-P System John C. Crowell, Manager, Instrument Maintenance Walter T. Christopher, Manager, Electrical Maintenance Section Merritt W. Haney, Coordinator, Support Projects Unit Perry T. Becknell, Manager, Special Projectu Section Ronald E. Burns, Manager, Maintenance Planning and Technical Section Charles E. Anderson, Coordinator, Maintenance Superintendent, Support Projects Gene A. Hartsfield, Jr., Stiervisor, Mainter nce Superintendent / Preventive Maintenance Randy D. Garner, Coordinator, Mechanical Proj Hechanical Maintenance Section Edwin D. Corne11us, Manager, Mechanical Mainte. ce Section Thomas E. Scott, Supervisor, Unit. Instrument Pm.nning Unit, Maintenance John M. Killen, Jr., Coordinator, Electrical Project, Electrical Maintenance Section Charles G. Wages, Coordinator, Support Projects, Maintenance John E. Whitt, Coordinator, Support Projects, Maintenance John R. Nebrig, Supervisor, Unit, Mechanical Planning, Maintenance Robert L. McLemore, Coordinator, Support Projects, Maintenance Edwin L. Logan, Manager, Maintenance Support Section Alton W. McCaleb, Coordinator, Instrument Project, Instrument Maintraance Section Jerry C. Pettitt, Manager, Work Control Outage Gary T. McChristian, Supervisor, Section, Work Control / Outage William C. Thomison, Supervisor, Section, Plant Manager, Technical Support, Ter.hnical Support Program John /.. Wilson, Supervisor, Section, Technical Supt 't. 7"% atry, Chemistr.
Technical Support Nichols M. Moon, Stpervisor, Section, Technical Suppot., ,emistry, padchem Lab 1714n a
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AG_Q1DEllTS SEPTEMBER 1988 These vere three loss of-time accidents during the month.
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_ISSUA!!CE OF SPECIAL REPORTS JUtlE 1988 There were no violation notices issued for the month of June 1988.
Reported violation 88-10-04 was deleted.
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Revision 1724n
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ADJ3NDA i
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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35642 i
i U.S. Nuclear Regulatory Convaission l ATTN Document Control Desk Office of Nuclear Reactor Regulation Washington, D.C. 20555 Attention Office of Management Information and Program Control
[. Docket Nos. 50-259 j In the Matter of the ) $
Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (B/N) - MONTHLY OPERATING REPORT - SEPTEMBER 19PS I'
Enclosed is the September 1988 Monchly Operating Report to NRC for Browns Ferry Nuclear Plant units 1, 2, and 3.
. Very truly yours, TENNESSEE VALLEY AUTHORITY cuy C. Campbell Plant Manager Enclosure cc: INPO Hecords Center Mr. C. C. Zech, 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 U.S. Nuclear Regulutory Convaission Browns Ferry Resident Inspector Region II Browns Ferry Nuclear Plant Attn Dr. J. Nelson Grace, Route 12 Box 637 Regional Administrator Athens, Alabama 35611 101 Marietta Street, NW, Suite 2900 Atlante, Georgia 30323 Mr. Ted Marston, Director Electric Power Researct Institute P. O. Box 10412 Palo Alto, California 94304 4 f$l \
' s An Equal Opportunity Employer l .

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