ML20154N699

Monthly Operating Repts for Aug 1988 for Browns Ferry Nuclear Plant

ML20154N699
Person / Time
Site:	Browns Ferry
Issue date:	08/31/1988
From:	Campbell G, Crawford J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8809290380
Download: ML20154N699 (64)

Text

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29.0 880914 818 MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY AUGUST 1988 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted by:

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Guy G. Campb III Plant Manager

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EABLE OF CONTENTS PART I OPERATIONAL

SUMMARY

A. Significant Operational Events Summary........................... 1 B. Fuel Performance and Spent Fuel Storage Capabilities Sursary..... 2 C. Main Steam Relief Valve (MSRVs) Actuation Summary. . . . . . . . . . . . . . . . 5 D. Issuance of Special Reports Summary.............................. 6 E. Licensee Event Reports Summary................................... 7 F. Offsite Dose Calculation Manual Changes......................... 10 G. Radwaste Summary................................................ 11

1. Total volume c ' solid waste shipped off site L

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

3. Gross curie activity

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

5. Estimated quantities of spent resin in storage.

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

7. Waste type and volume of radwaste containers that a~re onsite awaiting shipment.

PART II OPERATING STATISTICS A. NRC Reports

1. Operating Data Report....................................... 20

2. Average Daily Power Leve1................................... 23

3. Unit Shutdowns and Power Reductions......................... 26

8. TVA Reports

1. Plant Operating St atis tic s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 9

2. Unit Outage and Availability Data. . . . . . . . . . . . . . . . . . . . . . . . . . . 30

3. Reactor Histogram (Reactor Power Percent)................... 33 1724n I

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TABLE OF CONTENTS ,

(Continued)

Part III MAINTENANCE

SUMMARY

A. Electrical Maintenance........................................... 34 B. Instrument Naintenance........................................... 34 C. Mechanical Maintenance........................................... 34 i D. Runnies Maintenance.............................................. 34 E. Modifications.................................................... 34 PART IV OTHER REPORTS A. Chemistry Summary ,

1. P rima ry Coo l an t Chemi s t ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 5

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

3. A i rbo rn e Re l e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 9  !

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

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

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

7. Weste Treatment System Throughputs.......................... 50 B. Testing Summary.................................................. 51 C. Reactor Vessel Fatigue Usage Evaluation.......................... 53 D. Change in Procedures............................................. 50 E. Plant Ins t ruc tion Revis ions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4 F. Change in Plant organization..................................... 55 l C. Accidents........................................................ 56 i 1

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OPERATIONAL SEMMARY l

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Pago 1 SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

AUGUST 1988 Unit 1 08/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns.

08/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

Unit 2 08/01/88 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns. Cycle 5 refueling and modifications continue.

08/31/88 2400 Unit remains on administrative hold to rossive various TVA and NRC concernr.. Cycle 5 refueling and modifications continue.

Unit 3 08/01/88 0001 ~ Unit remains on administrative hold to resolve various TVA and NRC concerns.

08/31/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns.

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P:ge 2 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

AUGUST 1988 Unit 1 Unit 1 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 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 improvements, 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 0*/37), RPS voltage monitoring modifications H022 sample line e dification (LKR 81050), and EECW < ebon to stainleau 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 transferred to unit 2 SFSP. The present available capacity of the fuel pool is 1607 locations.

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- Pcge 3 FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED)

AUGUST 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 conce rns . The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 2 modifications are CRD SDIY piping modification (IEB 80-17), environmental qualification of electrical equipsent (10CFR50.49), torus structural modifications (NUREG 0661), containment instrumentation modification (NUREG 0737), fire protection changes (Appendix R 10CFR50), MSIV leak rate reductions modifications, 4

modification of masonry walls (ISB 80-11), addition of feedwater nozzle temperature monitoring (4UREG 0619), evaluation of the vent drain and test connections (LER 82020), valve leak rate testing modifie.ations (Appendix J),

! D/G speed sensor installation (LER 81004), KPCI and RCIC testable check valve changeout, modification of PCIS logic (LER 259 85009), HPCI improvements.

I various seismic program review, and EECW carbon to stainless pipe changeout.

i 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 I

EOC-A, 352 EOC-3, 156 EOC-2, and 132 EOC-1 acetablies. The 252 EOC-6 assemblies were transferred from unit 1 SFSP. The present available capacity of the fuel pool is 1,229 locations.

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FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONTINUED) )

AUGUST 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 10CYR50), MSIV leak rete reduction modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections

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(LER 82020), valvo leak rate testing modifications (Appendix J), HPCI 1

concerns, replacement of plant process computer, seismic qualificatione of piping (IEB 79-02/14), post-accident sampling modification (NUREG 0737),

alldition of redundant drywell control air supply, RPS voltage monitoring modification H 022sample line modificatlon (LER 81050), replacement of I jet pump holddown beam assemblies (IEB 80-07), EECW carbon to stainless pipe

< cnangeout, and plant design upgrade to seismic qualification.

There art zero assnublies in the reactor vessel. The spent fue.1 storage pool presently contains 764 assemblies to finish cycle 6, 248 EOC-5, 280 IOC-4, 376 EOC-3, 97 E0C-2, and 3 Eoc-1 assemblies. The present available capacity of the fuel pool is 585 locations.

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MAIN STEAM REL15E Y&IYI W.EYs.l E8El&BI AUGUST 1988 i

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No MSRVs were challenged during the month.

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Psga ,6 ISSUANCE OF SPECIAL REPORTS, August 1988 There were no violation notices issued for the month of August 1943.

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• Pago 7 LICENSEE EVENT REPORT (s)

AUGUST 1988 Description of Event LEE 1-87-027 Inocerable Hand Control Valve Blocks Miah Progrure Coolant Rev. C1 Injection Torus Water Supply on September 15,1987, at 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, while performing layup maintenance on unit 1, it was discovered that a 16-inch hand control valve in the high pressute coolant injection suction line from the torus had the valve stem separated from the valve disc and could not be opened. The Associated Control Equipment. Inc., hand control valve disc and shaft are connected by a key. The key is held in place by a cover plate secured by four bolts. Three of the bolts had failed permitting the shaft and disc to separate. A betsilurgical analysis determined the cause of the bolt failure to ta tensile overload.

The bolts were replaced on the broken valve. Similar valves on all three units were inspected and valve operation verified.

No other failures were identified.

The failure of this valve is considered li isolated case based

on failure mechanisi *alve maintenance history, and inspection results of similar valves. The valves are 'cheduled to be

' inspected and tested during the next refuelitig totage on cach unit.

1-88-021 Control Power Transfer on_4KV Shutdown Board Causes Unplaunod Start of Residual Heat Removal Service Water (RHRSW) Pump On July 18, 1988, at 2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br /> with all three units defueled, there was an unplanned start of the Di RHRSW pump, an "

engineered safety featurs (EST).

The monthly operability test on the 3A diesel generator (DC) was in progress and the DG we.s running. The M1 RHRSW pump had started automatically per the DC test and had been marually stopped. The 250 VDC control power to the 3EC 4KV shutdown board was realigned per special operating instruction (301)-23 in order to meet ssecndary containment requirements to continue fuel handling operations. The 3A DC was still running. The control power transfer caused a momentary voltage drop to the RHRSW pump 81 start logic. A t!me delay stret relay and the auto start lockout relay were deenergized and therefore reinitialized, rollowing a 28-second time delay, the RHRSW 1724n d

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Descrintion of Event i (Continued) l l

l IsEE 2-88-021 pump restarted. The cause of the event was determined to be the (Continued) control power transfer with the DG running. The 31 RHRSW pump was intentionally left in operation. 30I-23 will be revised.

1-88-022 Unalanned Contaipment Isolations caused by F611ure of Loale Relay Coil on July 20, 1988, at 2135 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.123675e-4 months <br /> with all three units defueled sad work in progress over the spent fuel storage pools, Browns Ferry unit 1 received a spurious refuel cone high radiation signal which caused isolations of primso containment, refuel l sone, and main control room ventilation cystems and initiated the standby gas treatment (850T) and the control room emergency ventilation systems. As a result of the 39CT initiation, the reactor building pressure decreased causing reactor sone ventilation isolations. The other refuel sone exhaust radiation monitors were operable and indicating normal radiation levels.

Work over the spent fuel storage pools was stopped.

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The spurious high radiation signal was generated by the failure of the upscale relay coil in the unit 1. B train, refuel exhaust l radiation monitoring circuit. A definitive cause for the coil

! f ailure has not been detemined. The investigation is

! continuins into the cause of the relay coil failure and a l

supplemental report will be submitted.

l Corrective maintenance was initiated to replace the relay.

l Following repair, the radiation monitor was functionally tested i

and returned to service. All affected systems were returned to l normal by 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> on July 21, 1988. Upgrade of these relays had been previously ini' lated but is awaiting material delivery' l

for the refuel sono and reactor sono exhaust radiatioa monitors.

2-88-004 Personnel Error Initiates Enmineered Safety Feature _a_

on July 1,1988, at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br /> and again at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> witt all three units defueled, a low roactor water level signal was received by the reactor protection system (RPs). This initiated standby gas treatment and control roces emergency ventilation.

The unit 2 reactor sone ventilation isolated, the refueling sone ventilation isolated, and an isolation signal was sent to the unit 2 isolation valves on the reactor water cleanup, residual heat removal, primary containment ventilation, and traversing incore probe. The second event occurred while investigating the 1724n

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Pcge 9 Descriotion of Event (continued)

III 2-88-004 cause of the first event. Both events were caused by draining (Continoed) sensing lines on a unit 2 reactor vessel level transmitter and a rwactor pressure transmitter during performance of a modification, without an adequate clearance. This was due to a personnel error on the part of the responsible modifications engineer in filling out the clearance request and the kosistant shif t operations supervisor in establishing the clearance. The sensing lines were capped, isolations reset, and all ventilation systems returned to normal. A second clearance was issued to prevent recurrence. The individuals involved have been L

counseled.

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Pess 10 0FFSITE DOSE CALCULATION MANUAL CHANGES U

AUGUST 1988 No changes were made to the Browns Ferry offsite dose calculation manual during the month.  ;

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gs 11 RAWASTE

SUMMARY

AUGUST 1988 The radweste system performed as designed. Approximately 9.95E+05 gallons of waste 11guld were discharged containing approximstaly 1.67E-02 cueles of activity.

There w re two spent resin shipments and two trash shipments during August. All shipments were to Barnwell, South Carolina, i

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Solid dadioactive Westo .'

August 1988 Scie}2 Dewateaed Spent Resin Shipments I Volume of condensate / waste resin shipped: 7.04 Cu.M. (247 Cu.Ft.) [

Total curies shipped: 33.536 Volume of reactor cleanup resin shipped: O Cu.M. ( 0 Cu.Ft.) ,

t Total curies shipped: 0 l

Date Shioned Discosal Facility Tvoe of Resin I 08/01/88 Barnwell, SC CWP5 08/23/88 Bar nwelL , SC CWP5 i

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Dry Active Waste CI' i

Number of drums shipped: 46 Volume 9.83 Cu.M. ( 345.0 Cu.Ft.)

l Total curies shipped: 0.5496 Number of boxes shipped: 15 Volume 41.31 Cu.M. (1449.1 Cu.Ft.) '

Total curies shipped: 3.2713 f

Date Shicoed Disposal Facillig Tvoc of Packace i 08/10/88 BarnweLL, SC DrumstBoxes 08/30/88 BarnwelL, SC Boxes  !

l (1) All shipments were by Sole-Use Vehicle  ;

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Pcge 13 August 1988 Summary Type Shipped to Packaged on Gross Curie Estimated of BarnweLL Site Rwaiting Content by Generdtion for Waste During Month Shipment Type of Waste Next Month Compacted 1 Drums 285.0Cu.Ft.(2) 555 Cu.Ft. 1.16E-01 1200 Cu.Ft.(2)

Boxes 4C3 Cu.Ft.

' 186 Cu.Ft. 3.17E+00 800 Cu.Ft.'

Uncompacted Drums 60 Cu.Ft.(2) O Cu.Ft. 4.34E-01 0 Cu.Ft.(2)

Boxes 984,1Cu.Ft.(2I 894 Cu.Ft. 1.00E-01 1600 Cu Ft.(2 Resins CWP5 247 Cu.Ft.(1) 1569 Cu.Ft.(3) 3.35E+01 450 Cu.Ft.(1)

RWC'1 0 Cu.Ft.

I' 280 Cu.Ft.(3) 0.00E+00 40 Cu.Ft.(I'

' ' 3.73E+01 3,600 Cu.Ft. '

TOTALS 2085 Cu.Ft. 1635 Co.Ft.

I Total volume of waste shipped during the month: 2,085 Cu.Ft.

Total volume of waste shipped year-to-date: 16,642 Cu.Ft.

Unused 1988 burial volume allocation at BdrnwelLt 66.156 Cu.Ft.

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

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1 LIQUID RADWADTE reg, 18 AUEUDT iCC]  ;

TOTAL RIVER RELEASE i FLOW RATE (GPM) ' DATA PLOTTED FOR TtiE PREVIOUS 12 MONTH 9 TOTAL RELEASE (C2) 40 . . 2 RATE fnown 30 - HZ 27.10 LOW 11.82 AVG 19.85 20 . . 1 TOTAL RELEASEfCI)

HZ O.05 LOW 0.01 AVG 0.03 O FLOWRATE kP OCT V EC JAN 8 > TAR APR MAY bG THRSUttHPUT f G At M FILTER THROUGHPUTS ,,,,,

GALLONS X fO' HI 0.15E+07 4 _

LOW 0.86E+0S AVG 0.11E*07 FL",JR DRAIN 3 -

H! 0.98C+06 LOW 0.49E+06 m AVG 0.77E+0S 2 ~

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LAUNDRY m

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" HI 0.13E+05 LOW 0.00E+00 g ,

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AVG 0.54E+04 0 ..

SEP OCT NOV OEC VAN FE8 WAR APR MAY JUN JUL AUG ~

COST OF OPERATION '

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H! 0.59E+05 LOW 0.19E+05 80 . m -

AVG 0.37E+05 70 .  :

FLOOR ORAIN 60 . '

HZ 0.50E+05 LOW 0.21E+05 50 . '

AVG 0.32E+05 40 . .

j LAUNDRY 30 . HI 0.37E+03 20 . '  : LOW 0.00E+00 y, f- .  ;

AVG 0.64E+02 10 .

HEP bCT NOV bEC AN FES MAR APR MAY JUN JUL AUG WASTE COLLECTOR SYSTEM

LAUNDRY SYSTEM FLOOR DRAIN SYSTEM

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REACTOR POWER - MWT P=s' 19 UNITS f, 2, AND 3 AUGUST 1988 MWT 3500 -

3000 -

WIT 1: OUTAGE 2000 -

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

500 -

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• 9****O@@O40#4##St@@&@#44&ft OAYS TecMJcol Seev1ces C<ome Ferry hesclear P]mt REACTOR WATER CONOUCTIVITY UNITS 1, 2, AND 3 AUGUST 1988 UMH0/CM CDPCUCT!YITY 1.75 ,

UNIT 1 1.5 -

C090UCTIVITY 1.25 -

UNIT 2 1 -----------------------------------------------------------

0.75 " ~

0.5 -

0.25 -

EXPECTED RANGE COLD SHUTOOWN 0

• 4 "8

• • • • • • @@@@@##D#44@@@YM&44@4CACTION L I LIMIT Oasistry Sectl e DAYS -

COLD SHuTo0wN TecMjes) Services O' oms Ferry ht/c]9ar P]mt REACTOR WATER CHLORIDE UNITS 1, 2 ANO 3 AUGUST 1988 PPB so............................................................... g ongog UNIT 1 40 CH.0R10E 3g ,

UNIT 2 g ,

CHLOA!CE l

UNIT 3 l to -

EXPECTED RANGE ALL C0to!TIONS

• 4 ~~~~

,......... .....,"* * *' * $ * * @ @ @ O 4 0 # 0 @ @ @ @ @ @ Y @ @ @ @ @ f t n.v-

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.l OPERATING  :

STATISTICS ,

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OPERATI O DATA

• REPORT Pcg3 20 000ET NO. 50-259 DATE 09-01-86 CO FLETED BY J. O. Crawford TELEPHONE (105) 729-2507 OPERATING STATUS l Notes l

1. Unit Name: Srowns Ferry Unit One l l

2. Reporting Peric4: Avoust 1980 l l

3. Llconsed Thermal Power (MWt): 3293 l l

4. Nameplate Rating (Gross MWe): 1l52 l l S. Design Electrical Rating (Not MWe) 1065 l l

6. Maxinue Dependable capacity (Gross MWe) 1098.4 l l

7. Maximum Dependable capacity (Not MWo) 1065 L l S. If Changes occur in Capacity Ratings (Itew Nup6er 3 Through 7) Since Last Report, Give Reasons:

N/A

9. Powe Level To Which Restricted, if Any (Net MWe): N/A i 10. Reasons For Restrictions, if Any: N/A This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 7a4 5855 #23.535

12. Nup6er of Hours Reactor Was Critical 0 0 59.521.38

13. Reactor Reserve Shutdown Hours 0 0 6.997.44

14. Hours Generator On-Line 0 0 _ 58.267.26

15. Unit Reserve Shutdown Hours 0 0 0

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

17. Gross Electrical Energy Generated ( M ) 0 0 55.398.1 %

18. Not Electrical Energy Generated ( M ) -4948 -33967 55.647.506

19. Unit Service Factor 0 0 47.20

20. Unit Availability Factor 0 0 47.20

21. Unit Capacity Factor (Using MDC Net) 0 0 40.00

22. Unit Capacity Factor (Using DER Net) 0 0 40.80

23. Unit Forced Outage Rate 100 100 44.40

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be deter =In d

26. Units in Test Status (Prior to Cominorcl 1 Operation): Forecast Achieved INITIAL CRITICALITY INiilAL ELECTRICITY C09ERCI AL OPERATION l

(9/77) l 1724n l

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OPERATING DATA REPORT gg DOCKET NO. 50-260 DATE 09-01-88 C0ffLETED SY J. D. Crawford TELEPHONE (205) 729-2507 OPERATING STATUS _

l Notes l

1. Unit Neues Browns Ferry Unit Two l l

2. Reporting Period: Acoust 1988 L l

3. Licensed Thermal Power (MWt): 3293 l 4 Nameplate Rating (Gross MWe): 1852 l S. Design Electrical Rating (Not MWe) 1065 ,

l

6. Manisue Dependable Capacity (Gross MWe) 1098.4 _,,, l l

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

8. If Changes occur in Capecity Ratings (Itens Munder 3 Through 7) Since Last Report, Give Reasons:

N/A

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

10. Reasons For Restrictions, if Any N/A This Month Yr-to-Oate Cumulative

11. Hours in Reporting Period 744 5855 118.422.00

12. Nwse, of Hours Reactor Was Critical 0 0 ,

53.860.03

13. Reector Reserve Shutdown Hours 0 0 14.200.44

14. h rs Generator On-Line 0 0 54.338.36

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 0 153.245.l67

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

18. Not Electrical Energy Generated (MWH) -2169 -16.695 49.l67.638

19. Unit Service Factor 0 0 45.90

20. Unit Availability Factor 0 0 45.90

21. Unit Capacity Factor (Using M)C Net) 0 0 39.00

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

0 0 39.00

23. Unit Forced Outage Rate _ _ _ 100 100 43.90

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be deter =Ined

26. Units in Test Status (Prior to Ccryorclal Operation): Forecast Achieved INITIAL CRITICAtl1Y INITIAL ELECTRICITY CO M RClAL OPERAT10N _

(9/77) 1724n i

9

-______-____-__x a __ _ _ , _ _ _ _ - - _ _ _ . _ _ _ - _ _ _ . , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

OPERATI C DATA REPORT g DOCKET NO. 50-296 DATE 09-01-80 CCpFLETED BY J. D. Crawford TELEPHONE (205) 729 2507 OPERATING STATUS l Notes l

1. Lhlt Nee Scowns Ferry Unit Three l l

2. Reporting Period: Avaust 1980 l l

3. Llconsed Thermal Power (MWt): 3293 l l 4 Napoplate Rating (Gross MWe): 1152 l S. Design Electrical Rating (Not MWe) 1065 l

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

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

8. If Changes occur in capacity Ratings (items Nweer 3 Through 7) Since Last Report, Give Reasons:

N/A i

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

10. Reasons For Restrictions, if Any N/A This Month Yr-to-Cate cumulative

11. Hours in Reporting Period 744 5855 100.847.00

12. Nweer of Hours Reactor Was Critical 0 0 45.506.08

13. Reactor Reserve Shutdown Hours 0 0 5.149.55

14. Hours Generator On-line 0 0 44.194.76

15. Unit Reserve Shutdc=n Hours 0 0 0 i

16. Gross Thermal Energy Generated (MWH) 0 0 131.868.267 ,

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

18. Not Electrical Energy Generated (Mel) -1577 -17.468 42.073.680

19. Unit Service Factor 0 0 43.00

20. Unit Avellability Factor 0 0 43.00

21. Unit Cape:Ity Factor (Using M)C Net) 0 0 39.10  ;

22. Unit Capacity Factor (Using DER Net) 0 0 39.10 3

j 23. Unit Forced Outage Rate 100 100 47.50

24. Shuthwns Sche & led Over Next 6 Months (Type, Date, and Duration of Each): o j

I

25. If Shut Deen At End Of Report Period. Estimated Date of Startup To be detemined

24. Units in Test Status (Prior to Cam ercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY 00PMRCIAL OPERATICN (9/77) l 1724n I

l l

bge23 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-259 Unit one DATE 09-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH AUGUST 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Met) (We-Net) 1 -8 17 -7 2 -7 18 -7 3 -7 19 -7 4 -7 20 -7 5 -6 ,

21 -6 6 -7 22 -7 7 -7 23 -7 -

8 -7 24 -7

. 9 -7 25 -5 10 -6 26 -4 11 -7 27 -6 12 -6 28 -7 13 -6 29 -7 14 -6 30 -7 15 -7 31 -7 16 -7 INSTRUCTIONS On this format, list the averste daily unit power level in NWe-Net for each day in the reportint month. Compute to the nearest whole metawatt.

(9/77) 1724n

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _(

• Page 24 AVERACE DAILY UNIT POWER LEVEL DOCKET NO. 50-260 Unit Two DATE 09-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 NONTH AUGUST 1988 DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (NWe-Met) (NWe-Met) 1 -3 17 -3 2 -3 18 -3 3 -3 19 -3 4 -3 20 -3 5 -3 21 -3 6 -4 22 -3 7 -3 23 -3 8 -4 24 -3 9 -4 25 -1 10 -3 26 -1 11 -3 27 -3 12 -3 28 -3 13 -3 29 -3 14 -3 30 -2 15 -3 31 -3 16 -3 INSTRUCTIONS I On this format list the average daily unit power level in NWo-Net for each day in the reportins month. Compute to the nearest whole metawatt.

(9/77) l 1724n I

L

?:33 25 AVERAGE DAILY UNIT POWER LEVEL DOCKET No. 50-296 Unit Tnroe DATE 09-01-88 COMPLETED BY J.D. Crawford '

TELEPHONE (205)729-2507 MONTH AtlGUST 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net) (NWe-Net) 1 -2 17 -2 2 -2 18 -2 3 -3 19 -2 4 -2 20 -2 5 -2 21 -2 6 -3 22 -2 7 -2 23 -2 3 -2 24 -2 1

I 9 -3 25 -1  :

r 10 -2 26 -1 ,

11 -2 27 -2 i 12 -3 28 -2 I

13 -3 29 -2  !

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14 -2 30 -2

?

15 -2 31 -2 [

16 -2 i

INSTRUCTIONS i on this fomat, list the averste daily unit power level in NWe-Net for each day in .

the reportint month. Compute to the nearest whole metawatt. j r

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l-l#81TSHUlleOWNS AND POWER RElaUC180NS ENN-LNGT MARIE One DATE 09-01-88 -

(MIEED BY J.D. Craeaford REFURIROUNIH August .

15a 5FII0fdE (205) 729-2507

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BROWS FERRY NUCLEAR P' n. , j l

i Fer.od Hours _ 744 .. . .onth Aunust 19 L stem No. Unit No. (NIT 1 (NIT 2 (NTT 3 ptANT 1 Averaoe Hourly Cross Load. vW 0 0 0 0 2 0 1

Madmum Hour Nat _Genfration MWh ._ . 0 0 0 -

3 Core Thermal Eneror Ge9. CWD (ti2 n n o O 4

Steam Gen Thermai Eeerey Cen Jg2

$ 5 Grou cieete, cal Gen.. MWm 0

_ 0 0 0 1 1, 6 station ute. Mwh 4.948 2.169 1.$/7 8.694 '

l 7 Net Esectrical Oen . MWh =4,948 =2.169

• l.377 *S 694 dl a station we percent J 0 0 t

0 9 Accum Core Avg. E moosure. MWORon! ,

10 CTEG This Month.106 BTU

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0 0 0 0

' 1 SGTEG This Montm 106 eTil ' O O O O  !

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j 13 kourt Reactor Was entreal 0 0 0 0 14 Unit Use. Hours.M n. 0 0 0 0 l 15 _ capacity Factor. Percent 0 0 0 0

} 16 17 Mine Avait Fat. tor percent Ge.neoter Av.ia. Facter. perceat O O O O l

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• 18 Tureocen Avaa Factor pe,eent 0 0 0 0 l f 19 Reactor Ava:t_ beter Dereent 0 0 0 0 i 20 Unit A.aa. Factor. Deretat 0 0 O O

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Pego 33 REACTOR POWER PERCENT AUGUST 1988 UNIT 1 rencest 100 -

90 -

N -

70 -

80 '

ADMINISTRATIVE HOLD S0 40 -

30 30 >

10 t a '3 4 5 8 7 0 t to it it 13 14 13 18 17 1e is to at ta 23 34 23 26 37 as is 30 31 UNIT 2 PEACENT 100 -

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Pc'ge 34 MAINTENANCE

SUMMARY

f August 1988 i

Maintenance summaries unavailable for the month.

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CHEMISTRY

SUMMARY

AUGUST 1988 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical speeliication and fuel warranty limita 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 concentratior, and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. Ihis calendar year,

the technical specification and fuel warranty limits for conductivity and a

chloride have not been exceeded.

Unit 3 The conductivity of the reactor coolant remained within technical y 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 msnth. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded, f 1724n

m. 4 = o A 8 g 4 v -

Prgs.36 *

)

)

PRIMARY COOLANT CHEMISTRY AUGUST 1988 )

Parameter Unit 1 Unit 2 Unit 3

1. Gross Radioactivity a Crud (f11ter) (uci/ml)

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

b. Filtrate (uci/ml)

High W/A N/A N/A Low N/A N/A N/A ,

Average N/A N/A N/A

2. Milipore Iron (Fe. cob)

High N/A N/A W/A i

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

3. Tritiun (pel/ml)_

t High 4.61E-5 4.29E-5 1.17E-4 Low 3.95E-5 4.21E-5 9.50E-5 Average 4.218E-5 4.24E-5 1.096E-4

4. 19 dine-131 (uct/ml)

High <2.05E-6 <1.05E-6 <3.84E-7 Low <5.19E-7 <8.67E-7 <3.01E-7 As. cage <1.29E-6 <9.42E-7 <3.40E-7

5. Iodino-131tiodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 1724n l

l

.. x .. . _ . _ , . . ...- ...._

Prgo 37 PRIMARY COOLANT CHEMISTRY (Continued)

AUGUSST 1988 Parameter Unit 1 Unit 2 Unit 3

6. Ch,loride (sob)

High <10 <10 <10 l <10 Low <10 <10 j

Average <10 <10 <10 l

l 7. oH925*C i

! High 6.2 6.2 6.2 Low 6.0 5.9 5.9 Average 6.1 6.1 6.1

8. Conductivity (umho/cm025'C)

High 0.16 0.88 0.22 Low 0.10 0.70 0.12 Average 0.13 0.80 0.14 1724n

% A- .-asx_1.-x_.-t_a__-_1____ ____ _

Paga 38 -

gNVIRONMENTAL TECHNICAL SPECIFICATION REQUIREMENTS The ambient upstream river temperature (24-hour average maximum) averaged 86.2*F ranging from 82.7'F on August 31 to 89.2*F on August 18. The downstream temperature varied between 82.9*F on August 31 to 88.9'F on August 18. The maximum river temperature rise was 0.9'F on August 31.

The sedimentation pond remained out of service for the entire month. An engineering design report for repairing the pond was submitted to the Alabama Department of Environmental Management for approval on August 29.

The sewage lagoon discharge was resumed on August 8. The effluent flow averaged 8.160 gallons per day with average BOD 5 and TSS concentrations of 14 mg/l and 43 mg/1, respectfully.

The plant did not experience any compliance problems during the month.

1724n 1 . .. . _ _ (

P:go 39 AIRBORNE REl. EASES (1)

AULIUS T 1988 SUMMAT.(OH OF AL.L. REl. EASES UNIT THIS MONTH A. FISS(OH AND AC rit/A r f 0H GASES

1. 10TAl. RFLEASE CI < 1.41E 02 2, At!ERAOF RELCASE RAIE FOR PERIOD UCI/SEC , 5.85C 01

3. PERCF'NT Dl' IECH. SPEC. LIMIT (0.10 c.I/SEC) 7. 0.00E-01 D, IUl11NES

1. TOTAL IODINE - 131 CI  : 4.40E-04

2. At/ERAGE REl.FASE RATE F0F PERIOD UCI/SEC < 1 82E-01

3. PERCENT Of TFCH. SPEC. L1 HIT (2.19 UC]/SEC)  % 0.00E-01 i

C, PnRT[ cut. ARES .

1. PARTICULATES W)IH HALF-LIFES > OR  :

TO 8 DAYS CI 2.23E-04

2. A L/ C R A TIE RELEASE RALE FOR PERIOD UCI/SEC 9.23E 05

3. PFRCENT OF TECH. SPEC. LIllIT(2.19 UCI/SEC)  % 4.21E-03 4, tlROSS AtPHA RAD 10ACrIt/ITY CI 1 32C-05 D. I R I 1 1 *J M

1. TOTAL RELF ASE CI 2.74E-02

2. At/EH ADE RElqHE RAIE FOR PERIOD UCI/SEC 1.1.sE-02

3. PFRCENT OF TECH. SPEC. l.IMIT(2 19 UCI/SEC) 7. 5.16E-01 4, O R 00H l1 l.F.t> L L R E L E A S E CI 2.74E-00 l .

5. ElEt/ATED REl. EASE CI '; 4.67E-04

(!) REPORIING PERIuli 20 DAYS t -

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Pega.40 AIRBORNE RELEASES (CONTINUED)

• AUGilST 1900 El. Et/ ATED REl.E A!!ES A. FI8SIOff GASES UNIT THIS NONTH X R- 8!iM CI < 7.56E-02 KR-85 CI < i.23C 01 KR-H/ CI < 1.93E-01 KR-08 CI i 2.78E-01 XE-133 CI <: 1 4SE-01

.<E-135H CI ', 4.63E-01 XE-135 CI < 9.78E-02 XE-133 CI < 1.0VE 00 GTHERS(SPECIFY)

TOTol FOR PERIOD CI < 4.47E 01 I. 10DINFC I*131 CI < 3.81E-06 I-133 CI < 7.17C-05 I-13S CI < 1.01E-01 T O I A I.. FOR PERIOD CI  ; 1 01E-01

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P go 41

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AIRD0ftNE RELEASES (CONTINUED)

AlJ Gij S T 1980 EL.EVATED RELEAGES C. P Alfl I CLIL A T E S UNIT THIS MONT!1 SR-89 CI s 4 10E-07 SR-90 CI ,

< 1.61E-07 CS-134 CI < 4.4YE-06 CS-137 CI < 5.88E- 06 BA-140 CI < 1 07E-05 L A -140 CI < 8 41E-06 OTHERS(SPECIFY)

TO T Al. FOR PERIOD CI '

- 3.01E-05

~

D. IRIt'IUM CI < 4 67E-04

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Pcge.42 .- '

AIRNORNF; REl.E ASES (CONTINUED)

• AUGUST 1908 OROUND REl.EAfiES A. FISSION DASES UNIT THIS MONTH KR-85M CI < 2.36E-01 KR -85 CI < 9.16E 01 NR-87 CI < 7.2'.E-01 NR-88 CI - G.50E-01 XE-133 CI  : 6 23E-01 XE-135M CI < 6.75E-01 XE-135 CI < 1.90E-01 XE-130 CI < 1 06E 00 O T H F.R G ( S P E C I F Y )

T 0 T Ai. FOR a CI < 9.68E 01 B. [0DlHES I-131 CI < 4.36E-04 I-133 CI < 3.09E-03 I-135 CI < 7.72E 00 TOTAL. FOR PERIOD CI < 7.73E 00

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l Pcg3 43 l . AIRBORHE REl. EASES (CONTINtlED)

AUGUST 1988 GR0llHD "ELEAtiES C. P ARTICitL A1ES UNIT THIS MONTH SR-HY CI < 2.31E-04 SR-90 CI 8.54E-05 CS-134 CI < 4 03E-04 CS -137 CI < 4.90E-04 P. A 2 10 CI t 7.97E-04

.L A -14 0 CI < 5.3SE-04 l

OTHLRS(SPF CIFY)

CD 60 CI 2 23E-04 TorAl. FOR PERIOD

.. .. ._ _.. - - - - - - - - - CI ,2.23E-04 l

l D. TRtrIUM CI 2.71E-02

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Pcg3 44 .~

BR0lJ14S F ERRY NUCLE AR PL ANT -

HUNTHLY REPORT CALCllt.ATIONS LIQUID RELE ASE S AUGUST 1988 R A DI D AC11VI: LIQUID EF Fl.Ul!N IS

1. GROSS RADIDACTIVITY UNITS a) TOTAL RELEASE CURIES 1.67E-02 b) AUFRAOC DIl.tl RED CONT:ENTRA TI0il RELEASED U C I /NI. 1.32E-09 e) PERCClli DF APPt.ICADLL LJMIl ( 1L 7 UC1/ML )  % 1.32E 00

2. FRI r' M a) T01AL REl. EASE CURIES 1.14E-01 b) AVERAGE DIt.tllED CONCENTRATION RELEASED UCI/ML 8.99E- 09 e) PERCENI 0F APPL.ICADLE LIMIT (3E-03 UC1/ML)  % 3 00E-04 (1)

3. DI!iS01.t/ED NOBLE OASES a) TOTAL REIEASE CURIES < 7.25E.~04 b) AVERAOC DILUTED CONCENTRATION RELEASED UCI/ML < 5.73E-11 c) PERCENT O F A P Pl.1 C A Tt L E' t. I M I T (2E-04 UCI/MI.)  % < 2.86E-05

1. ORUSS AL.PflA RADI0 ACTIVITY J) (O'IAL RELEASE CURIES <1.94E-04 b) AVCRADE DII.UIED CONCENTRATION RELEASED UCI/ML <1.54E-11

5. VOLUME OF L 10V ill lJAU1E 10 DISCHARGE CANAL LI1ERS 3.77E 06

6. VOLUMC Of DIL U TION 461 ER LITERS 1.27E 10 (1) I N C L.U D L' S XF-133: XE-13br AND OTHERS 3

.,' ,4 ,

Pcg3 45 BROWNS FERRY NilCLEAR Pl. ANT NONTHLY REPORT CALCul.ATIONS LIOUID RELEASES AUGttST 1988 ISOTOPES RELCASED UNITS CI CR-U1 < 2.11 E- 0 3 MN-54 < 2.8HE-04 Cti-53 < 2 . 3.3 E - 0 4 FE-59 < 5.24E-04 CO-60 2.16E-03 Z N -- 6 b 2.46E-04 N8-95 < 2.27E-04 ZR-VS < 4 00E-04 N0fC ?VM < 1.80E-04 I-131 < 2 72E-04

, E 1 :13 < 5.74E 04 CS-134 2.74E-03 X E - t .3 5 < 1.49E-04 CS 137 1.13E-02 DA 140 < 1 0;iE-0 3 LA-140 < 2 11F-04 CE-141 < 3.16E-04 SR-OY < 9 4S1-05 SR 70 < 3 0SE-05 l

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__ _ _ __ ____.________1_________. J

Pcg: 46 -

BROWNS FERRY NijC1. EAR PLANT lt0N illt.Y REPOR T Col.ClJt. ATIONS L IQlJID RI.~t.E AfiE S AUGUST 1988 OTHERS UNITS CI FE-55 < 9.11E-04 SB -123 2.38E-04 0

Pcg: 47 BROWNS FERRY NtlCLEAR Pl. ANT MONTHLY REPORT C ALCLfl. A I ION S LIQUID REL.EA!1ES AUGLIS T 1980 LAUN11RY DRAIN VOLUME RELEASED: 0.0 Gall.ONS FLOOR liR A) H VOLUME REl.E ASED: 887021.5 UALLDNS W ASTE fi AMPl.E FANK VOLUME RELEASED: 107710,1 GALLONS DISIII.l.ATF TANK VOLUME REl.E ASE D : 0.0 UAl.LONS LOCATION OTilER l'H AN R AD4 ASTti V0l.tlME RELEAtlED : 0.0 Oh!.LONS T O T Al. VOLUHF RELEASFU ~10 THE RIVER: 994731."6 GALLONS H 1 CllE !! T DAT(:M AurIVIlY RELEA!!ED FOR ?!OilT H : 3 . fid E -0 9 UCI/ML A/D LOHOEST RELEAHL TIME FOR MONTH: 351 HINU1ES SHORTEff r REl.F A!!E IIMC FOR MOH1 H : 117 MINilTES TO I A!. TIME OF RELEASES FOR MONTH: 8355 MINUTES AVtRAOC FIMC FOR D A T C ll R E L E A ti E S : 239 N(HUTES NUMl!ER OF BATCHES REl.EAUCli! 35 N U M B C. it OF ADMINICITRATIVE LIMIr VIOt.ATIONS: o NUML:E R OF IFCHNICAL SPECIF)CA110N V101.A110NS: 0 i

I l

__ - - - - - _ _ _ . _ _ _ _ ._ _ _ (

. ~. ' .

• P;gi 48 RESIN USAGE REPORT AUGUST 1988 RESIN CONSUMED (CU.FT.)

% of Total M E0WDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 61.8 0 136 0 0 146 282 Weste Domineralizer 0 0 0 0 0 0 0 Weste Fi).ter 34.7 0 104 0 3 51 158 Fuel Pool Domins 0.9 0 4 0 0 0 4 Reactor Water Cleanup Unit 1 0 0 0 0 0 0 0 Unit 2 0 0 0 0 0 0 0 Unit 3 0.4 0 2 0 0 0- 2 Cond. Domins Unit 1 ~ 0 0 0 0 0 0 0 Unit 2 2.2 0 10 0 0 0 10 Unit 3 0 0 0 0 0 0 0 Totals 100 0 256 0 3 197 456 l

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Pcgs 49 FUEL CLADDING INTEGRITY PARAMETERS AUGUST 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 (uel/sec)

Date Flow MWt Ko-138 Kr-87 Kr-88 Kr-85m Ko-135 Xe-133 Unit in Outage Unit 2 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/sec) ggtg Elog MWt Xe-138 Kr-87 Kr-88. Kr-85m Xe-135 Xe-133 Unit in Outage pnit 3 Reactor Water Iodines (uci/sec.)

D, ate I-131 I-132_ I-133 I-134 I-135 Unit in Outage Fission Gases at Discharme of SJAE (uci/sec) pate Flow HW1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage 1724n

\

WASTE TREATMENT SYSTEM Tifl00GWUTS AUGUST 1988 l

FLOOR FLOOR FLOOR

DRAIN DRAIN DRAIN

, 3, a 2. m +04 _

~

gat 9.78E d COLLECTOR FILTER SAMPLE GAC 8.87E+05 TANK TANK (2) CUFT: 282.00 GAU 9.78E+05 M 2.92E+03 jf If I

' LAUNDRY GAL- 9.06E+04 GP[t 0.00E+00 DRAIN ,,g ,,,,g ,,0 CANAL

, 3,,, . TANK GP:t 3.21EE Gae 1.14+06 W 9.95E+05 E CYCLED WATER GP[t 7.62E+03 gat 2.36E+05 Jk ifU i f WASTE .

WASTE WASTE WASTE GP[t 3.47E+03 COLLECTOR SAMPLE  ::

FILTER Gau 1.08E+05 DEMINERALIZER TANK TANK (1) CIFT: 158.00 D) QFT: 0.09

.m GAU t.47E+06

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(t) Curt PDCOL 104.00 QFT ESIN G FIBER MIXTWE- 51.00 .CUFT ECOSORt 3.00

[GP[t 3.63E+04 0 QFT N 136.00 .QET RESM G FIBER MIXTURE: 146.00 QFT ECOSDREt 0.00 '

STORAGE (3) BEA3 ESIN TANK

1. 8 4

e' -

Page 51 l

TESTING

SUMMARY

AUGUST 1988 surveillance Testinz

Unit 0 A total of 186 surveillance tests were completed using 51 different test instructions.

• Unit 1 A total of 63 surveillance tests were completed on unit i using 24 different test instructions.

Unit 2 A total of 114 surveillance tests were completed on unit 2 using 39 different test instructions.

Unit 3 A total af 77 surveillance tests were completed on unit 3 using 23 different test instructions.

1724n

~

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. Ppgs'$g TESTING

SUMMARY

(CONTINUED)

AUGUST 1988 Channes. Tests and Experiments Requiring Authorization From the KRC Pursuant to 10 CFR 50.59(a)

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

Changes. Tests and Experiments not Requirint Authorization from NRC Pursuant to 10 CFR 50.59(a)

There were two special tests completed for this month. .

ST 87-28

Description:

Hayes-Republic H,03Analyzer Hostile Environment ST 88-15

Description:

Ventilation System Flow Measurement 2 i

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Pago 53 d

REACTOR VESSEL FATIGUE USAGE EVALUATION AUGUST 1988 The cumulative usage factors for the reactor vessel are as follows:

' Usame Factor Location Unit 1 Unit 2 Unit 3

> Shell at wator line 0.00620 0.00492 0.00431 6

Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360

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CHANGES IN PROctDURES l

l AUGUST 1988  ;

I i

There were 515 revisions to plant instructions during the month; 515 instructions were changed primarily for correction, and zero revisions related to safe operation of the plant.

PLANT INSTRUCTION REVISIONS l AUGUST 1988 There were no revisions for the month.

I 4

l 1724n e

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l'cya 55 CHANGES IN PLANT ORGANIZATION AUGUST 1988 4

There were six changes in plant staff for those positions designated as key supervisory positions. They were as follnvs: Levyn W. Ivey, Nuclear Engineer, Site Licensing; Jinny D. Johnson, Work Control / Outage Shif t Msnar.er; Jerry S.

Olson, Assistant Plant Manager; John L. Sparks, Supervisor NSSS; Robert McKeon, Manager, Plant Manager's Staff; and W. Gary Harland, Manager Work Control / Outage.

i 1724n i

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.. .' l P:ga 56 ,- ,

ACCIDENTS AUGUST 1988 t

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

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f I:

TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant Post Office Box 2000 Decatur, Alabama 35602 513'i9IOne U.S. Nuclear Regulatory Commission ATTN: Document Control Denk office of LNelear Reactor Regulation Washington, D.C. 20555 Attention: Office of Management Information and Program Control In the Matter of the ) Docket Nos. 50-259 Tennessee Valley Authority ) 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) - MONTHLY OPERATING REPORT - AUGUST 1988 Enclosed is the August 1988 Monthly Operating Report to NRC for Browns Ferry Nuclear Plant unita 1, 2, and 3.

Very truly yours.

TENNESSEE VALLEY AUTHORITY Guy C. Campbell III Plant Manager I

Enclosure cct INPO Records Center Mr. G. G. Zech, Director 3 Institute of Nuclear Power Operations TVA Projects Division Suite 1500 One White Flint, North l 1100 circle 75 Parkway 11555 Rockville Pike Atlanta, Georgia 30389 Rockville, Maryland 20852 U.S. Nuclear Regulatory Commission 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 Atlanta Georgia 30323 Mr. Ted Marston, Director Electric Power Research Institute P. O. Box 10412 #

l Palo Alto, California 94304 /

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I s i)

An Equal Opportunity Employer