ML18025B137

Second Monthly Operating Rept for Sept 1980

ML18025B137
Person / Time
Site:	Browns Ferry
Issue date:	10/10/1980
From:	TENNESSEE VALLEY AUTHORITY
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ML18025B135	List: ML18025B134 ML18025B137
References
NUDOCS 8010160511
Download: ML18025B137 (123)

Text

TENNESSEE VALLEY AUTHORITY BROGANS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT SEPTEMBER 1980 Submitted By: Plant Manager-">>o;6 o5//

TABLE OF CONTENTS PART I Operations Summary Plant Operations Fuel Performance

.Refueling Information.

10 Equipment Performance.

12 Change in Procedures 16 Change in Facility Design.16 Surveillance Testing 17 Containment Leak Rate Tests.18 Changes, Tests, and Experiments Requiring Authorization from the NRC Pursuant to 10 CFR 50~59 (a)~~~~~~~~~~o 18 Changes in Plant Operating Organization.

18 Reports to NRC.19 Changes, Tests, and Experiments Not Requiring Authorization from the NRC Pursuant to 10 CFR 50.59 (a)20 Primary Coolant Chemistry.

Source Tests 0~~~~~~~~~~~~~~~~~~~22 Environmental Technical Specification Requirements 23 Calculation of Usage Factor.23 PART II Important Events.24 Vis i'to 1 s~~~~~~~~~~~~~~~Safety and First Aid.27 TABLE OF CONTENTS (Continued)

PART II (Continued)

Accidental'

~~~~o~~~27 Plant Personnel Listing.Personnel Changes-Annual Personnel Changes-Hourly.Significant Operational Events Plant Instruction Revisions.

28 31 37 40 45 Reportable Occurrences 46 Primary Coolant Chemistry.

Average Daily Gross Capacity Factor.Accumulated Average Daily Gross Factor.49 51 52 Radwaste Monthly Average Discharge Activity Discharged.

Rate/Total 57 Building and Stack Monthly Release Rates 58'echnical Specification Comparison and Stack Release Rates Building 59 Reactor Power Percent.60 Nuclear Plant Operating Statistics 63 Unit Outage and Availability 64 Outage Summary.67 Electrical Maintenance Summary Electrical Maintenance Summary Charts CSSC Equipment.

Non-CSSC Equipment.

68 70 73 Mechanical Maintenance Summary 76 I

TABLE OF CONTENTS (Continued)

PART II (Continued)

Mechanical Maintenance Summary Charts CSSC Equipment Non-CSSC Equipment Instrument Maintenance Summary.77 80 82 CSSC Equipment 87 Radioactive Liquid Effluents.

88 Airborne Releases Solid Radioactive Waste 96 Effluent and Waste Disposal Monthly Report.100 Resin Usage.101 Powdered Resins%Total Usage.~~102 BFNP Filter Demineralizer Performance 103 Fuel Cladding Integrity Parameters.

106 Waste Treatment System Volume Throughputs 108 Water Treatment Chemical Use.109 Total Plant Training Summary.110 PART I 0 erations Summar September 1980 Unft 1 Unit 1 was critical for 703.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, produced 699,320 MWH (gross)with 3.07 percent station use, resulting'n a average hourly gross load of 1,003,012 Kw during the month.The average net heat rate for the month was 10,950 BTU/KWH.There are 192 full power days estimated remaining until the end of cycle 3 fuel.With a capacity factor of 85 percent the target EOC exposure would be reached on May 10, 1981.This includes 0 days of coastdown.

The capacity factor for the month was 88.4 percent.There were two scrams on the unit during the month.On September 1, the reactor scrammed when water from the offgas cooler dripped onto the stator cooling cabinet causing a short in a pressure relay tripping the turbine.The reactor scrammed on September 24, when a short circuit occurred in the sudden pressure trip caosing the 500 KV circuit breakers to open which caus'ed a general load reject.There were seven power reductions during the month.On September 3, power was reduced because of maintenance to the"C" string high pressure heaters.Power was reduced on September 7, 20, and 27, for turbine control valve tests and Sl's.On September 16, power was reduced when"A" recirculating water pump was taken out-of-service to place the unit on cooling towers.Power was reduced on September 19, when the"B" reactor feedwater pump was taken out-of-service for maintenance for excessive vibration.

On September 29, power was reduced for condensate de-mineralizer backwash and precoat due to problems on three of the condensate demineralizers.

0 erations Summar (Continued)

September 1980 Evaluation of Unit 1 cycle performance shows that the unit operated 10,620 BTU/KWH gross heat rate which is 0.88 percent higher than expected.Unit 2 Unit 2 was critical 118.78 hours9.027778e-4 days <br />0.0217 hours <br />1.289683e-4 weeks <br />2.9679e-5 months <br />, produced 113,120 NWH (gross)with 4.69 percent station use, resulting in an average hourly gross load of 952,349 kW during the month.The average net heat rate for the month was 10,850 BTU/KWH.The EOC 3 refueling outage for Unit 2 began on September 5, 1980.The capacity factor for the month was 14.3 percent.There was one scram on the unit during the month.On September 5, the reactor was manually scrammed in preparation for the beginning of the EOC-3 re-fueling outage.There was one power reduction during the month.From September 1, to'I September 5, power was reduced due to end of cycle coastdown to the EOC-3 refueling outage that began on September 5.Evaluation of the Unit 2 cycle performance shows that the unit operated 10,350 BTU/KWH gross heat rate which is 2.72 percent lower than expected.Unit 3 Unit 3 was critical for 654.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, produced 625,700 MK (gross)with 2.98 percent station use, resulting in an average hourly gross load of 956,245 kW during the month.The average net heat rate for the month was 10,820 BTU/KWH.There are 31 full power days estimated until the end of.cycle 3 fuel.With a capacity factor of 85 percent the target EOC exposure would be reached on October 31, 1980.This includes 26 days of coastdown.

The capacity factor for the month was 79.1 percent.

0 erations Summar (Continued)

September 1980 There were two scrams on the unit during the month.On September 12, the reactor was manually scrammed to begin a short maintenance outage on the"B" inboard main steam isolation valve.The reactor scrammed on September 20, when a 480 V shutdown board failed to transfer from alternate to normal feed pro-ducing a loss of RPS MG set and the isolation of a SJAE which caused a main condenser low vacuum.There were seven power reductions during the month.On September 1, power was reduced when"A" recirculation pump tripped.Power was reduced on September 7 and 27, for turbine control valve tests and SI's.From September 7 to September 12, power was reduced when the closure time was found to be too fast on MSIV 1-26 and the valve was closed until a short maintenance outage on September 12.Power was reduced on September 23, for a control rod pattern adjustment.

On September 24, power was reduced due to loss of the computer while performing preconditioning to full power.Evaluation of the Unit 3 cycle performance shows that the unit operated at 10,550 BTU/KMH gross heat rate which is 1.42 percent lower than expected.

0 erations Summar (Continued)

September 1980 Reliabilit and Availabilit The accumulated average daily gross (AADG)capacity factors, based upon midnight IÃH meter readings, for each unit is tabulated below for each month during the last calendar year.The second column compares this year'performance with last year.Unit No.1 Unit No.2 Unit No.3 1979 1980 1979 1980 1979 1980 Jan Feb Apr*17.4*7.6 (28)50.7*3.8 (29)59.2 2.9 (22)67.0 18.1 94.8 86.4 94.0 62.5 91.5 65.9*90.4 69.4 90.8 37.4 93.3 67.4 93'77.8 93.6 83.1 June 72.5 31.1*72.3 72.9 90.5 84.1 75.7 38.9 72.4 73.1 85.0 84.2'uly 78.0 44.9 75.2 73.3 85.0 7.94 Aug 79.9, 51.0 77.7 75.0*81.8 81.4 Sept Oct Nov Dec(')79.1 55.2 80.0 79.6 80.1 79.0*68.2 (25)80.6*81.5 79.5*72.7.81.1*65.5 Nc (39)*59'*58.7*Refuel Outage (Days of Month)Yearly Average (1)Unit 1 can achieve an AADG capacity factor of about 62.7%for CY'80 if it averages 85%CF (presently averaging 77.8%)for the remainder of the year, considering unit operating time (i.e.: not in refuel).Similarly, Units 2 and 3 can reach about 64.8%and 73.0%AADG capacity factors, re-spectively.

Presently these units are averaging 75.0%and 81.1%, respectively.

0 erations Summer (Continued)

September 1980 Reliabilit and Availabilit (Continued)

The largest capacity factor loss (12%)this month was on Unit 3 due to an inoperable HSIV (1-26"B" inboard valve).This valve was closed and limited to 75%power for about 5.8 days.The next largest CF loss (Unit 1~4.9%, Unit 3=2.9%)involves automatic scrams caused by equipment malfunctions.

A significant controllable CF loss involved control rod pattern limitations on unit 1 and 3 at 0.8%and 1.7%re-spectively.

These losses result from postponing rod pattern adjustment until weekends when more favorable system load requirements exist.

l, RELIABILITY AND AVAILABILITY (CONTINUED)

CAPACITY FACTOR LOSSES September 1980 Unit 1 Unit 2 Unit Losses were caused by: 80.1%88.4 79.5%14.3 58.7%79.1 l.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.23.24.25.26.27.28.29.30.31.32.33.Refueling P CION End of cycle coastdown Feed piping failure Startup testing Administrative limitations Steam tunnel temperature switches Reactor feed pump maintenance High condenser backpressure Thermal limits Recirculation pump motor bearing problems Automatic scram Drywell air leakage Reduced thermal limits Turbine vibration and balancing Heater problems Hoisture separator high level Recirculation pump starting problems Feedwater control problems EHC and turbine valve problems THI related modifications Recirculation system vibration evaluation Hain steam valve maintenance Recirculation H-G set brush changes Rod sequence exchange TIP system CMf system hydrogen sensor failure Offgas system malfunction Power cable replacement Testable check valve maintenance Load following demonstration test Demineralizer problems Low pressure air line break 5.5 2.8 1.4 1.4 0.9 0.8 0.7 0.6 0.6 0.5 0.5 0.5 0.4 0.4 0.3 0.3 0.3 0.3 0.2 1.9;0.6 1.8 I>4.9 0.2 0.6 9.5 2.5 0.2 0.5 0.6 0.1 I.0.6 0.2 0.8 2.2 1.5 0.6 0.'3 0.3 0.2 0.2 83.6 2-.1 29.3 1.8 1.0 1.3 0.3 3.9 0.8.0.1 0.2 0.2 0'0.5 0.3 0.3 0.2 0.2 0.1 2.1 0.2 2.9 12;0 0.2 RELIABILITY AND AVAILABILITY (CONTINUED)

CAPACITY FACTOR LOSSES September 1980 Unit 1 Unit 2 Unit 3 80.1%88.4 79.5%14.3 58.7%79.1 Losses were caused by: 34.Rod pattern, full core flow 35.Surveillance instruction 36.Recirculation pump trip 37.Feedwater system leak 38.Control rod adjustment 0.8 0.1 1.7 0.1 0.4 0.9 0.2 0 erations Summar (Continued)

September 1980 Common The radwaste system performed as designed.Approximately 7.58E+05 gallons of waste liquid were discharged containing approximately 1.36E+00 curies of activities.

Floor drain system through-put increased this month primarily because of decontamination activities associated with the unit two refueling outage.Radwaste shipments to Barnwell, S.C.were interrupted for approximately 8 days due to a delay in the receipt of the required state shipping permit.There were 14 shipments for an approximate total volume of 5,600 cubic feet.There were 399 (55 gallon)drums of radwaste generated during the month at an average rate of 13.3 drums per day.There were 33 boxes of trash and irradiated components generated during the month at an average rate of 1.1 boxes per day.

0 erations Summar (Continued)

September 1980 Fuel Performance Unit 1 The reactor was operated at a nominal maximum thermal power level of 99.2%of rated.Typical thermal limits for this condition include CMFLPD, 0.973;MAPRAT, 0.945 and CMFCP, 0.885.The reactor operated in control rod sequence"A" 12 days, and in sequence"B" the remainder of the month.Fuel preconditioning at the rate of 0.11 kw/ft/hr was conducted for approximately 1.4 days in sequence"A", and 3.1 days in sequence"B".Unit 2 The reactor was operated at a nominal maximum thermal power level of 90%of rated.Typical thermal limits for this condition included CMFLPD, 0.731;HAPRAT, 0.730;CMFCP, 0.810.The reactor operated in control rod sequence"B" for the entire month.Fuel preconditioning at the rate of 0.11 kw/ft/hr was conducted for approximately 0 days in sequence"B".Unit 3 The reactor was operated at a nominal maximum thermal power level of 99.2%of rated.Typical thermal limits for this condition CttFPLD, 0.850: MAPRAT, 0.827;and CMFCP, 0.965.The reactor operated in control rod sequence"A" for 14 days, and in sequence"B" the remainder of the month.Fuel preconditioning at the rate of 0.11 Kw/ft/hr was conducted for 1.5 days in sequence"A", and 3.5 days in sequence"B".

10 Operations Summary (Continued)

September 1980 Refuelin Information Unit 1 Unit 1'is scheduled for its fourth refueling beginning on or about April 15, 1981, with a scheduled restart date of July 25, 1981.This re-fueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, the final fix on, the sparger modification, power supply on LPCI modification, and torus modifications if all approvals are received.There are 764 fuel assemblies in the reactor vessel.The spent fuel storage pool presently contains 550 spent 7 x 7 fuel assemblies, five 8 x 8 fuel assemblies, and one 8 x 8 R fuel assembly.Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 1152 assemblies.

Unit 2 Unit 2 is presently in its EOC 3 refueling outage.Unit 2 is scheduled for its fourth refueling beginning on or about March 1, 1982, with a scheduled restart date of June 14, 1982.This refueling outage will involve completing relief valve modifications, torus modifications if all approvals are received,"A" low pressure turbine'inspection, and loading additional 8 x 8 R fuel assemblies into the core.There are 764 fuel assemblies in the reactor vessel.At the end of the H+'onth, there were 132 discharged cycle 1 fuel assemblies, 156 discharged cycle 2 fuel assemblies, and 352 discharged cycle 3 fuel assemblies in the spent storage pool.The present storage capacity of the spent fuel pool is 820 assemblies.

With present capacity, the 1979 refueling was the last Operations Summary (Continued)

September 1980 Refuelin Information Unit 2 (Continued) refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.However, new high density storage racks are being installed during the third refueling of Unit 2.Unit 3 Unit 3 is scheduled for its third refueling beginning on or about November 2, 1980, with a scheduled restart date of December 11, 1980.This EOC-3 refueling, involves loading additional 8 x 8 R (retrofit) assemblies into the core, and power supply on LPCI modification.

There are 764 fuel assemblies presently in the reactor vessel.There are 144 discharged cycle 2 fuel assemblies, 208 discharged cycle 1 fuel assemblies, and 164 new P 8 x 8 R assemblies in the spent fuel storage pool.The present storage capacity of the spent fuel pool is 1528 assemblies.

With present capacity, the 1980 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.

12 0 erations Summar (Continued)

September 1980 E ui ment Performance On September 16, at approximately 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, localized flooding was ex-perienced in the yard in front of the radwaste and the unit 1 and 2 diesel building.The flooding began during an attempt to place Unit 1 on cooling towers.Gate lA1 was closed and the resulting back pressure forced open a cover-plate sealing the top of the CCW conduit.Opening gate 1Al halted the flow of water into the yard area.The cover-plate on the Unit 1 conduit has been securely refastened.

While performing leak checks on 2D RHR heat exchanger, it was discovered that a check valve in the raw service water charging connection to RHR service water was stuck open.This allowed a leak test on 2D RHR heat exchanger to be interpreted as positive indication of leakage because it placed 2D RHR heat ex-changer (RHR side)in communication with RHRSW through 2B RHR heat exchanger which was known to be leaking.The check valve was repaired and a satisfactory leak check of 2D RHR heat exchanger was performed.

Unit 1 Reactor Building Equipment Drain Sump Heat Exchanger was determined to be providing inadequate cooling for the contents of the Reactor Building Equip-ment Drain Sump.This was indicated by steam rising through the sump pump support plate.Investigation thus far points to inadequate cooling water flow from RBCCW to the sump heat exchanger.

This investigation continues.

13 0 erations Summar (Continued)

September 1980 E ui ment Performance (Continued)

High vibration on 1B Reactor Feedwater Pump was noted during routine weekly vibration checks this month.Increased surveillance revealed a high axial vibration level initially.

This then shifted to high horizontal vib-ration at a frequency two times the pump run speed.As this is indicative of misalignment and the vibration levels continued to become more severe, the pump was removed from service and the coupling disassembled.

It was found that all of the oil had been thrown out of the coupling.The oil was replaced and the pump returned to service without further problems.Prior to the beginning of Unit 2 refueling outage, performance checks on both spent fuel storage pool cooling pumps for Unit 2 determined both pumps to be performing at less than 85%of their design capacities.

Both pumps were rebuilt and subsequently performed at greater than design criteria.High differential pressures were experienced on 2B reactor water clean-up filter demineralizer.

Investigation revealed that a failure of the stainless steel filter elements allowed precoat material to accumulate on the resin trap.The problem was corrected by replacement of the filter elements and associated resin trap.Resin traps on reactor water clean-up demineralizers 1A and 1B were removed I and examined to determine the cause of high differential pressure.An accumulation of rust was found on the traps.The source of the rust is still under investigation.

There was no indication of problems with filter element integrity.

New resin traps were installed and the demineralizers were successfully returned to service.

14 0 eration Summar (Continued)

September 1980 E ui ment Performance (Continued)

Problems were experienced with the condensate demineralizers on Unit 1.Failure of the filter element on vessels J and E allowed resin to accumulate on the downstream resin traps.High differential pressure across the resin traps forced replacement of the traps along with the failed filter elements.The reason for unusually short service runs on vessel 1D was investigated.

The vessel's filter elements were found to be severely fouled with iron oxide.It is believed the fouling resulted from improper precoating techniques which failed to protect the element with an over-lay of resin.The fouled elements were re-placed and the vessel was satisfactorily returned to service.Precoating records are being reviewed to determine if additional corrective action is warranted.

A visual inspection was made of the Unit 2 CCW tunnel on September 17, 1980.Algae growth covering approximately 10%of the wall surface (bottom and sides)of the tunnel was noted.The floor of the tunnel was covered with silt and mud that ranged from 1/2 inch to 2 inches in thickness.

At the intake butterfly valves, there was approximately 1.5 ft of clams accumulated in the discharge 3 from CCH pump B.At the inlet to the water boxes, there was approximately 0.5 ft 3 of clams scattered around the tunnel floor.TIP problems on Unit 3 affected the ability to establish full power rod patterns throughout the month of August.Problems with two of the five TIP machines resulted in fewer TIP sets being run than otherwise would have been run.Detector"A" was replaced on September 22, 1980, and a PORC approved PMR was completed to eliminate problems with"D" machine.At the end of the month, all five TIP machines were operational.

0 erations Summar (Continued)

September 1980 E ui ment Performance (Continued)

The plant purchased a helium leak detection instrument to check the integrity of the main condensers.

The instrument was not fully operational in time to check the Unit 2 condensers at the start of the refueling outage.A leak check on the Unit 2 condenser is planned prior to the end of the outage when condenser vacuum is re-established.

18 0 erations Summar (Continued)

September 1980 Containment Leak Rate Tests'rimary containment penetration leak rate tests were performed during the month.The results are within technical specification limits and are listed in the following table.Leaka e (scfm T e Test Unit 1 Unit 2 Unit 3 Type A (integrated containment)

Type B (Drywell/torus hatches)Personnel Air Lock (X2)Equipment hatches No Test No Test Incomplete No Test 0.0011 0.2119 Type C (Isolation valves)No Test Totals 0.0 Electrical Penetration (X107B)0.0173 0.3236 0.3420 No Test 0.2119 Chan es Test and E.eriments Re uirin Authorization From the NRC Pursuant to 10 CFR 50.59 a)There was one revision to the Unit 3 Technical Specification comprised of pages ix through xxxi-EPL 1 through 22, 156, 157, 170 and 171.Inoperable time was changed from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 10 days on standby coolant supply capability.

Chan e in Plant Or anization There was one change to the plant staff for those positions designated as key supervisory personnel positions in the Technical Specifications.

A Plant Shift Engineer, M-4, was selected as Plant Assistant Operations Supervisor, M-4.

19 0 erations Summar (Continued)

September 1980 Re orts to NRC There were 23 reportable occurrences, a revision to one of these, and 2 cancelled reportable occurrences were reported to the NRC during the month.

20 0 erations Summar (Continued)

September 1980 Chan es Tests and Ex eriments Not Re uirin Authorization from the NRC Pursuant to 10 CFR 50.95 (a S ecial Test-186"Scram Discharge Volume (SDV)Drain Valve Closure Pressure on Loss of Control Air-Unit 2" This test was performed to determine the control air pressure at which the SDV drain valves would drift shut on a loss of control air.It was originated to aid in the evaluation of the potential for flooding the SDV as a result of a decrease in control air pressure.STEAR 80-20"I and C Bus A and B Load Current Determination" Test involved measuring current to various branch circuits feeding from I and C bus A and B.Data was submitted to EN DES to be used in their eval-uation of the voltage reliability analysis performed for these buses.This was in response to NRC inquiries.

Plant modifications will be submitted in the annual report.

21 0 erations Summar (Continued)

September 1980 Primar Coolant Chemistr Unit 1 The conductivity of the reactor coolant exceeded technical specification and fuel warranty limits for a total of 30.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during the month.A rup-tured tube in Cl waterbox and transients associated with Scrams 135 and 136 were responsible for the conductivity increases.

Chloride concentrations and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.This calendar year the technical specifications and fuel warranty limits has been exceeded for 140.9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />.Unit 2 The" conductivity of the reactor coolant remained within technical speci-fication,and fuel warranty limits for the month.Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.This calendar year technical specification and fuel warranty conductivity limit has been exceeded for 71.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.Unit 3 The conductivity of the reactor coolant remained within fuel warranty limits during the month.The conductivity of the reactor coolant remained within technical specifications of 2.0 pmhos during the month.Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month.This calendar 22 0 erations Summar (Continued)

September 1980 Primar Coolant Chemistr year the fuel warranty conductivity limit has been exceeded for 27.55 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, and technical specification limit has been exceeded for a total of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Source Test None 23 0 erations Summar (Continued)

September 1980 Environmental Technical S ecification Re uirement-The raw water chlorination system was not operated during the month of September.

Reservoir water temperatures exceeded technical specification limits on two different days during the month of September.

On September 28th and 29th the temperature rise was 5.1'.The average intake water temp-erature for the month was 83.6'., The largest water temperature rise was 5.1', with an average downstream water temperature of 85.3'.Approximately 700,000 gallons of water was released from the unlined pond to the Tennessee River.The pH of the release was maintained within technical specification limits of 6.0 to 9.0.Calculation of Usa e'Factor The cumulative usage factors for the reactor vessel are as follows: Location Usa e Factor Shell at water line Feedwater nozzle Closure studs Unit 1 0.00487 0.23254 0.19566 Unit 2 0.00369 0.15822'.12899 Unit 3 0.00314 0.11570 0.09194 24 0 erations Summar (Continued)

September 1980 Im ortant Events September The Plant Manager and the Plant Operations Supervisor attended a briefing on Division Plan to Compensate Nuclear Power Employees and an Operator Staffing Presentation in Chattanooga.

The Plant Manager attended the Bi-Weekly Plant Manager Meeting in Chattanooga.

879 A Plant Outage Civil Engineer and a Plant Outage Electrical Engineer attended a meeting in Knoxville, on the Post-Accident Sampling Facility.15-19 The Plant Chemical Unit Supervisor taught a chemistry and radio-chemistry course at the Power Operation Training Center for the STA's.15-30 Two Plant Chemical Engineers attended an engineering training course at the Power Operation Training Center in Chattanooga.

The Plant Manager attended a meeting in Chattanooga on recommendations from Management Training Committee for M position profile plan.The Plant Acting Compliance Supervisor attended a meeting in Chattanooga on IE Bulletin 79-01B.19 The Plant Systems, Analyst attended a meeting in Huntsville, AL., with Chattanooga Central Office personnel and PIC Systems, Inc., to review the design of the PRIME/GE 4020 link.A meeting was held at the plant between EN DES-Knoxville, personnel, and the Plant Instrument Maintenance personnel to discuss power sources for the Feedwater Control System.The Plant Outage Director attended a meeting in Chattanooga on Instrumentation Sensing Lines.20 The Plant Acting Compliance Supervisor attended the NRC Region II, meeting in Atlanta on NUREG-0660 clarifications/TMI Action Plans.22 The Plant Manager and representatives from the plant Co-op group attended a"kick-off" for combined'Federal Campaign at the Marshall Space Flight Center in Huntsville, AL.

25 0 erations Summar (Continued)

September 1980 Im ortant Events September 22-25 The Plant Mechanical Results Unit Supervisor, the Plant Equipment Diagnostics Engineering Associate, and a Plant Mechanical Engineer attended a Vibration Training Class in Chattanooga.

23-24 The Plant Manager attended a Nuclear power Quality Meeting in Chattanooga.

24 The Plant Outage Director attended a Division Meeting in Chattanooga.

25 The Plant Manager and representatives from the Plant Co-op group attended the-United May"Kick-off" dinner in Huntsville, AL.30 The Plant Quality Assurance Supervisor attended a QA Supervisor Meeting at the Power Operation Training Center.The Plant Manager, the Plant Electrical Maintenance Supervisor, a Plant Shift Engineer, and two Plant Outage Electrical Engineers attended a meeting in Knoxville on Browns Ferry Nuclear Plant Under-voltage Modifications.

The Plant Outage Refuel Floor Coordinator attended a meeting in Chattanooga on Multi-Stud Tensioners.

Visitors September Mr.Dale Nix, Plant Engineering Staff;Mr.Frank Kelly, Reactor Engineering Staff;and Mr.C.D.Evans, EN DES-Knoxville, met with the Plant Chemical Supervisor concerning PASF and revised design criteria.Mr.Tom Hall, London Nuclear Services, was onsite to meet with the Plant Assistant Outage Director and the Plant Outage Drywell Coor-dinator, concerning chemical decontamination of CRD scram headers.Mr.Barry Smith, General Electric Customer Service Plant and AMPS, met with various plant section supervisors.

Representatives from the Hewlett-Packard Corporation met with the Plant Chemical Supervisor to demonstrate the HP 9845 for PASF.

0 erations Summar (Continued)

September 1980 Visitors September Ms.Marilyn Taylor, Director of Personnel, was on site to meet with employees regarding various employee concerns.Her visit was a result fo Chairman Freeman's visit in July when questions regarding personnel were addressed to him.Job surveys were performed at nuclear plant positions by members of Ms.Taylor's staff and representatives of the Division of Nuclear Power personnel office.The results of these surveys will be compared to job surveys to be performed at a fossil plant.4-5 Messrs.Ralph Thompson, Charlie Howell, and Frank Garrett, Chattanooga Industrial Safety and Fire Protection Engineering Staff was onsite to conduct an air flow test-Unit 1 Reactor Building.8-11 Office of Power Quality Assurance auditors were onsite to audit special processes and maintenance activities.

10-12 General Electric representatives were onsite to meet with the Plant Manager concerning HPCI and RCIC performance.

A 5-man team from Occupational Health and Safety was onsite to audit the outage operation.

12 Mr.Ron Westbrook, IS and FPE Supervisor, CHattanooga, was onsite for a Safety Inspection Audit Exit Meeting.15 Two NRC licensing personnel were onsite to administer reactor operator and senior reactor operator licensing examinations to 10 Browns Ferry operators.

15-18 Three representatives from PLC (Professional Loss Control, Inc.)were onsite to perform an audit of the fire protection system as required by technical specifications.

16 An NRC inspector was onsite to audit the inservice program.22-25 Representatives from the Division of Occupational Health and Safety conducted a safety audit of outage work.23 Mr.Marvin Lane, Executive Vice Pr'esident of Graver Water Company, met with the Plant Results Section Supervisor and others on the problems of contaminated powdered resins.23-26 Office of Power Quality Assurance auditors were onsite to perform an audit of document control and technical specifications.

27 0 erations Summar (Continued)

September 1980 Safet and First Aid The regular weekly safety meetings of salary policy and trades and labor groups were held this month.Accidents There were 2 loss-of-time accidents during the month of September.

NUCLEAR PLANT PERSONNEL 28 Browns Ferry Nuclear PLANT Power Plant Superintendent~

M-8 Assistant Power Plant Superintendent M 6 TITLE End of Previous Month Changes End of Present Month Records Officer SA-2 eosIMst Mechanical En ineer SD-3 S ecification En ineer SD-3 En ineerin Aide SE-2 Safety Engineer SO 3 ngzneer ng i e Sa ety SE-Su ervisor, Mana ement Services Section M-5 Su ervisor Administrative Services hbck Unit H-4~fctttsttgtttofstetocMZ Su ervisor Document Control Unit H-~otaotctNsttgLeffttttxtnTgtrimst7BItsd Su ervisor Plt Services Unit H Secretar SB.4>tlaarttISmNcgtgtPtorILM-Editor SA-2 Clerk Typist SB 3 Clerk-Typist SB 2 zfftetsofrftsfcs88.8 Clerk SB-2 Payroll Clerk SB 5 Pa roll Clerle%8Q<

Payroll ClerleSBR SB-3 File Clerk SB.3 Supervisor Services H-4 Su ervisor Qualit Assurance Stalf M 5 Qualit Assurance En ineer SO 4 Quality Assurance Engineer SO-3 Quality Assurance Engineer SO 2 Engineering Aide (Quality Assurance)

SE 5 En ineerin Aide (Quality Assurance)

SE.4 n ineerin Aide ualit Assurance)

SE-3 lerk, SB-3 ail Clerk SB-2 Power Plant Results Supervisor M.5 Assistant Power Plant Results Supervisor M4 ower Plt Maintenance Supvr (Inst)H-5 Instrument Engineer SO 4 IfecuttttgtfrBI@tttmtcs88 Personnel Clerk SB-4 otttramstBBM S stems Anal st, SD-3 enior Instrument Mechanic-Instructor Irgtmtdge8agtsrtttt~".ItttL(saacsflsft Programming Technician SE-4 Engineering Aide SE 3 Senior Instrument Mechanic Foreman Senior Instrument Mechanic Instrument Mechanic Instrument Mechanic Ap rentice-'4th Pd.Instrument I'ftechanic Apprentice-3rd Pd.ctsrssrotttuntnhtacttmt(enectprzmfeme Pthc Nord Processor SB-4 sst.Power Plt.Maintenance Supervisor (Inst)M-4 Reactor En ineer SO 4 5U@tnBmjNI@SttgO7B Clerk SB-4 Engineering Aide (Nuclear)ZSA SE-5 TAMNQNSBrp;IftmttSGAz Supervisor, Mechanical Unit M-4 Mechanical En ineer SO 3 Engineerin Aide(Statistician)BRA SE-5 ttgfotroc'otg7rtfsfm(lamISr18ntaias)ISED Data Entry Clerk SB-2 15 44 22 10 15 16 43 27 Engineering Aide (Test Bt Studies)SE.3 TVA 7037 (PP-10.77) sheer 1 M mn,r September>>80 NUCLEAR PLANT PERSONNEL 29 Browns Ferr Nuclear PLA14T T IT t.s Mechanical En ineerin Associate SE 6 En ineerin Aide (Mechanical)

SE 4 En ineerir.Aide (Mechanical)

SE-3 En ineerin Aide (Instrument)

SE.En ineerin Coo Student (N)SE.3 Enoineerin

'Coo Student OQXZSZ (M)SE-3 Supervisor Chemical Unit if-4 Chemical En ineer SO 4 Chemical En ineer SO 3 Chemical Enoineerin Associate SE 6 Radiochelnical Laboratory Analyst SE 5 Radiochemical Laboratory Analyst SE 4 Chemical Laborator~

Anal st SE 3 Engineering Coop Student (C)SRR SE-4 En ineerinn Coo Student (C)SE.2 Radiochemical Laborato Anal st-Tr SE-3 Su ervisor Reactor Unit M-4 Power Plant Operations Supervisor M 5 Assistant Power Plant Operations Supervisor M.4 Clerk SB 3 Shift Engineer M-4 Assistant Shift Engineer M-3 Assistant Shift Engineer-SR L Unit Operator Unit Operator-RL Assistant Unit Operator Student Generating Plant Operator-th Pd.tu ent eneratxng ant perator-r Clerk SB-2 Supervisor Janitorial Services i'-3 Janitor SF 3 Janitor SF 2 Janitor SF.l End of Previous Month 16 15 55 Chonoes+1-1+17-4+27-20 Eno of PfeSenl Montn 15 15 20 17 62 Power Plant Maintenance Su ervisor E M-5 Power Plant Maintenance Supervisor M 5 Assistant Power Plant Klaintenance Supervisor (E)M 4 Assistant Power Plant Maintenance Supervisor (M)M 4 General Electrical Foreman M-4 Electrical Engineer SO 4 Electrical En.ineer SO 3 General Mechanical Foreman M-4 Mechanical Engineer SO.4 Mechanicaf En ineer SO 3&rJcttacthsgtt(:cttxftfzstutstnt)Ms'echanical Engineer SD-2 En ineerin Aide (41echanical)

SE 3 Engineering Coop Student (M)SE.Xmxnnmsmmm~unx!&SR En ineerin Aide Electrical SE-Electrician Foreman Electrician Electrician Apprentice-Pd.Electrician Apprentice-1st Pd.B Electrician Apprentice-1st Pd.A 10 46+.-2 10 10 TVA 7OS7 (PP tO 77)Sheet 2 September,(0 I'JUCLEAR PLANT PERSONNEL 30 PLANT Machinist Foreman Machinist Machinist Welder Machinist A orentice-4th Pd TITLE end or Previous Month ChangeS End or Present Month Machinist Apprentice-3rd Pd.Machinist Apprentice-2nd Pd.Hachinist A I7rentice-1st Pd.B Hachinist A rentice-1st Pd.A Boilermaker Foreman Boilermaker Boilermaker Welder Boilermaker Apprentice-Pd.Boilermaker Apprentice-Pd.Sheetmetal Worker A rentice-1st Pd.A Steamfitter Foreman Steamfitter Steamfitter Welder Steamfitter Ap rentice-5th Pd Steamfitter'Apprentice-1st Pd.A General Labor Foreman H-3 Car enter Foreman Asbestos Worker Foreman ainter Apprent3.ce

-st P.A Structural Ironworker Sheetmetal Worker Foreman Sheetmetal Worker Asbestos Worker Car enter Painter Foreman Painter Heavy Equipment Operator-Power Labor Foreman Nuclear Plant Laborer Truck Oriver I Sign Painter Total Annual Salary Policy Total ATL Operations Total ATL Maintenance 24 12 23 233 112+67-33+7-13 12 23 267 106 Total Plant 660+91-60 691 Hourly-List Titles Car enter 23 Car enter 1 Construction Laborer 71 Hortar Hixer 1 Boilermaker (10)Hach Wldr (1)Steamfitter 15 Hach 28 Bricklaver 1 Painter 13 Asbestos Worker 2 Crane 0 erator 2 Sheetmetal Worker 3 Truck Driver I 2 Total Hourly 63 20 152+12 26 TVA 7037 (PP.10.77)

Sheet 3 Month or 0 L 31 Se tember 1980 Personnel Chan es-Annual Name Title Effective Date Betty J.Grimes Billy J.Allen Kenneth E.Howard Richard L.Ingram William C.Jones, Jr.Arthur L.Littleton Jose I.Lozano Michael E.Maples Margaret L.Reach Larry D.Smith Jack W.Vinson Barbara L.Weigart Randall L.Keeton Dennis M.Castell Wayne E.Guthrie M.Neil Haraway Kenneth D.Sylvester Gary R.Cobb Janitor F01 Janitor F01 Janitor F01 Janitor FOl Janitor FOl Janitor FOl Janitor F01 Janitor F01 Janitor FOl Janitor F01 Janitor F01 Janitor F01 Janitor FOl Janitor F01 Janitor F01 Janitor F01 Janitor FOl Janitor F01 09 02 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 03 80 09 04 80 09 05 80 09 05 80 09 05 80 09 05 80 09 08 80 32 Se tember 1980 Personnel Chan es-Annual Name Title Effective Date Russell B.Huffman Willie M.Jenkins Robert L..Rice Nicholas L.Austin Thomas I.Vines Robert C.Murphy Charles Crawley James R.Hine Harlon L.Ramsey Janitor F01 Janitor F01 Janitor F01 Janitor F01 Janitor FOl Janitor F01 Janitor F01 Janitor FOl Janitor F01 09 08 80 09 08 80 09 08 80 09 09 80 09 09 80 09 10 80 09 11 80 09 15 80 09 17 80 B.Reclassifications Name Former Title New Title Effective Date Rickey E.Holtzclaw James C.Hall Danny L.Tuggle Wendell K.Holt Kenneth W.Brown Timothy D.Lane Linda G.Murphy SGPO-4th Pd SGPO-4t}1 Pd Inst Mech AP3 Elect APlA Elect APlA Inst Mech AP3 Elect APlA Asst Unit Op Asst Unit Op Inst Mech AP4 Elect AP1B Elect AP1B Inst Mech AP4 Elect AP1B 07 23 79 10 01 79 06 23 80 07 21 80 08 04 80 08 04 80 08 04 80 33 Se tember 1980 Personnel Chan es-Annual B.Reclassifications (Continued)

Name Elizabeth L.White Kenneth E.Davis Tony D.Hill Patricia F.Roland Lona C.Belue Roger D.Shireman Former Title Elect AP1A Elect AP1A Elect AP1A Inst Mech AP3 Clerk B03 Radiochem Lab Anal E04 New Title Elect AP1B Elect AP1B Elect APlB Inst Mech AP4 Effective Date 08 11 80 08 18 80 08 18 80 08 18 80 Radiochem Lab Anal E05 08 24 80 Word Processor B04 08 24 80 James A.Green Asst Shft Engr M03 James S.Watson Thomas M.Thompson Lardell Goodloe, Dan C.Barger Martha C.Barnett Nellarene P.Cobb Larry W.Cole Leonard A.Cole Michael W.Davis Helen J.Franklin William C.Freeman Elect (H)Elect (H)Elect (H)Janitor FOl Janitor F01 Janitor F01 Janitor F01 Janitor FOl Clerk B02 Janitor F01 Janitor F01 Robert E.Stone, Jr.Inst Mech AP3 Sup, Janitorial Servs M03 Inst Mech AP4 Elect Elect Elect Janitor F02 Janitor F02 Janitor F02 Janitor F02 Janitor F02 Clerk B03 Janitor F02 Janitor F02 08 31 80 09 01 80 09 01 80 09 03 80 09 04 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 34 Se tember 1980 Personnel Chan es-Annual B.Reclassifications (Continued)

Name Former Title New Title Effective Date James O.George Bobby F.Grizzard David S.Haney Robert L.Ingram Martin Johnson John W.Maynor, Jr.Morris W.Morell William L.Sandy Burl D.Stark Janitor F01 Janitor F02 Janitor F01 Janitor F02 Janitor F01 Janitor F01 Janitor F01 Janitor F01 Janitor F02 E.Jane Wilkerson Janitor FOl Thomas L.Williamson Janitor FOl Robert E.Woods Janitor FOl Garfield J.Taylor, Jr.Sr Inst Mech Inez H.Bedingfield Janitor F01 Austin L.,Burnette Shft Engr H04 Janitor F02 Janitor F03 Janitor F02 Janitor F03 Janitor F02 Janitor F02 Janitor F02 Janitor F02 Janitor F03 Janitor F02 Janitor F02 Janitor F02 Sr Inst Mech Fmn Janitor F02 Asst Pr Plt Op Sup M04 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 07 80 09 08 80 09 21 80 09 21 80 David T.Davis Herbert L.Johnson Inst Mech AP3 Qual Assurance Engr D02 Inst Mech AP4 Qual Assurance Engr D03 09 21 80 09 21 80 Donell King Richard W.Shultz Ardie R.Champion James C.Coz Janitor F01 Inst Mech AP3 Unit Op RL Unit Op RL Janitor F02 Inst Mech AP4 09 21 80 09 21 80 Asst Shft Engr M03 09 29 80 Asst Shft Engr M03 09 29 80.Willard B.Dawes, Jr.Asst Unit Op Unit Op 09 29 80 35 Se tember 1980 Personnel Chan es-Annual B.Reclassifications (Continued)

Name Former Title New Title Effective Date Johnny E.Duke Russell R.Eades Charles B.Fisher Steve R.Gray Charles G.McClain Marvin L.Meek Michael V.Hiller Asst Unit Op Asst Unit Op Asst Unit Op Asst Unit Op Unit Op RL Unit Op RL Unit Op RL Unit Op Unit Op Unit Op Unit Op 09 29 80 09 29 80 09 29 80 09 29 80 Asst Shft Engr M03 09 29 80 Asst Shft Engr H03 09 29 80 Asst Shft Engr M03 09 29 80 C.Transfers Out Name Former Title James L.Turner Radiochem Lab Anal E04 Jeannette Y.Johnson Clk B02 New Title Clk B02 Chemist-D01 Place TQ OCH&S Trng Ctr Effective Date 09 07 80 09 21 80 D.Transfers In Name George N.Veal David E.Newton Former Title Shmtl Qcr Elect New Title Shmtl Wkr Elect Place From W Creek Service Shops Effective Date 08 25 80 09 02 80 Michael N.Brown Radchm Lab Ana Tr E03 Radchm Lab Ana Trng Ctr Tr E03 09 21 80 James tJ.Burton III Chem Engr D02 Chem'Engr D03 Ctl&Test 09 21 80 B.Joan Chandler Clk B02 Data Engry Op B02 P&Svs 09 21 80 36 Personnel Chan es-Annual D.Transfers In (Continued)

Former Name Title Se tember 1980 New Title Place From Effective Date Edward J.Frederick Radchm Lab Ana Tr E03 Radchm Lab Ana Trng Ctr Tr E03 09 21 80 Aaron J.Goode Radchm Lab Ana Tr E03 Radchm Lab Ana Trng Ctr Tr E03 09 21 80 Albert M.Reynolds Radchm Lab Ana Radchm Lab Ana Trng Ctr 09 21 80 Tr E03 Tr E03 E.Return From LWOP Name Title Effective Date Brian E.Williams Engg Coop Student E03 (M)William B.Pendergrass Engg Coop Student E02 (C)Theresa M.Pickney Engg Coop Student E04 (C)09 02 80 09 08 80 09 08 80 F.Placed On LWOP Name David A.Robeson Title Engg Coop Student E02 (C)Effective Date 09 08 80 G.Terminations Name Fred Fraser Betty J.Grimes Harlon L.Ramsey Randall C.Arnold John D.Quigley Joe E.Rice Title Janitor F02 Janitor F01 Janitor F01 Elect Elect Unit Op RL Effective Date 09 02 80 09 09 80 09 10 80 09 15 80 09 15 80 09 19 80 37 Se tember 1980 Personnel Chan es-Houri Name J.R.Daniel Title Mach Robert W.Daniels Mach Jimmy D.Dean Jimmy W.Embry Billy J.Emmons William E.Griggs Harry F.Hacker Bennie D.Stults Thomas M.Thompson Harold F.Wilson Mach Stftr Stftr Mach Mach Mach Elect Stftr Jack D.Gaston Lardell Goodloe Stftr Elect Charles W.Warhurst Mach Bill C.Thornton Edwin R.Warren Morris G.Brown Earnest E.Cosby William H.Draper James P.Fields Leon Pope Stftr Mach Cons Lbr Cons Lbr Cons Lbr Cons Lbr Cons Lbr Willie T.Eggleston Stftr Effective Date 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 02 80 09 03 80 09 03 80 09 03 80 09 03 80 09 04 80 09 04 80 09 05 80 09 05 80 09 05 80 09 05 80 09 05 80 38 Se tember 1980 Personnel Chan es-Houri e Name Title Effective Date Loyd C.Canon James J.Cashion Jimmie 0.Garrett A.D.Jackson Cons Lbr Cons Lbr Cons Lbr Cons Lbr Kenneth R.Smith Esadore Meeks Albert S.Smith Mach Cr Op Mortar Mixer Thomas F.Schemeltz Cons Lbr James J.Smothermon Cons Lbr 09 05 80 09 05 80 09 08 80 09 08 80 09 08 80 09 09 80 09 15 80 09 17 80 09 30 80 B.Reclassifications Name James S.Watson Thomas M.Thompson Lardell Goodloe Former Title Elect Elect Elect New Title Elect (A)Elect (A)Elect (A)Effective Date 09 01 80 09 03 80 09 04 80 C.Transfers Out None D.Transfers En None 16 0 erations Summar (Continued)

September 1980 Chan e in Procedure There were 54 revisions to plant instructions during the month.47 instructions were changed primarily for corrections.

The remaining 7 revisions related to the safe operation of the plant.Chan e in Facilit Desi n All changes in facility design will be included in the unit outage summary report.

0 erations Summar (Continued)

September 1980 Surveillance Testin Unit 1 A total of 478 surveillance tests were completed on Unit 1 per 151 different test instructions.

Unit 2 A total of 205 surveillance tests were completed on Unit 2 per 95 different test instructions.

Unit 3 A total of 328 surveillance tests were completed on Unit 3 per 115 different test instructions.

39 Se tember 1980 Personnel Chan es-Houri E.Terminations Name Title Effective Date Gary D.Nichols Charlie E.Keener Lloyd W.Guthrie Johnny Norton Harty F.Hacker Hach Cons Lbr Carpenter Mortar Mixer Hach Leslie L.Abernathy Cons Lbr 07 15 80 08 27 80 09 04 80 09 16 80 09 22 80 09 29 80 40 Date Time 9/01/80 0001 1341 1736 2025 2230 2343 Si nificant 0 erational Events Unit 1 Event Reactor thermal power.at>99%, steady state control rod sequence"A".Reactor Scram No.135 from>99%on turbine stop valves closure, due to water causing a short in pressure relay 62-C1, which caused relay KT 303 to trip turbine.Commenced rod withdrawal.

Reactor Critical No.156.Rolled T/G.Synchronized generator, commenced power ascension.

9/02/80 1500 9/03/80 0040 1939 2030 Commenced PCIOHR from 82%thermal power.Reactor thermal power at 95%, holding due to"C" string high pressure heaters isolation due to relief valve flange leak."C" string high pressure heaters maintenance completed and heaters placed in service.Resumed PICOHR from 95%thermal power.9/05/80 1500 9/07/80 0015 0230 0705 0905 Reactor thermal power at 99%, maximum flow.Reduced thermal power from 99%to 85%for turbine C.V.tests and SI's.Turbine C.V.tests and SI's completed, commenced power ascension.

Commenced PCIOHR from 95%thermal power.Reactor thermal power at>99%, steady state.9/10/80 1500 9/12/80 2100 Reactor thermal power at>99%, steady state.Reduced thermal power from>99%to 50%for control rod sequence exchange from"A" to"B".9/13/80 0205 2130 Control rod sequence exchange from"A" to"B" completed, commenced power ascension.

Commenced PCIOHR from 82%thermal power.9/14/80 2300 9/16/80"1843 1905 2030 2300 Reactor thermal power was>99%, steady state.Reduced thermal power from>99%to 90%for removal of"A" circulating water pump to allow stop log lA1 to be lifted."A" circulating water pump placed in service, (mode to cooling towers would not operate due to stuck gate), commenced power ascension.

Commenced PCIOHR from 95%thermal power.Reactor thermal power at>99%, steady state.

41 Date Tillle Si nificant 0 erational Events Unit 1 Event 9/19/80 2230 Reduced thermal power from>99%to 77%for removal of"B" reactor feedwater pump for maintenance (excessive vibration).

9/20/80 0216 0315 1220 1225 2030 Reduced thermal power from 77%to 70%for turbine C.V.tests and SI's.Turbine C.V.tests and SI's completed, commenced power ascension.

Reduced thermal power from 77%to 50%due to loss of unit preferred power, when shutdown board power supply was trans-ferred.Commenced power ascension.

Commenced PCIOIR from 80%thermal power.9/21/80 1550 9/24/80 2222 Reactor thermal power at>99%, steady'state.

Reactor Scram No.136 from>99%thermal power on load re-(1)ject trip from negative ground on main transformer sudden pressure relay circuit.9/25/80 0530 0820 1038 1107 2110 Commenced rod withdrawal.

Reactor Critical No.157, sequence"B".Rolled T/G.Synchronized generator, commenced power ascension.

Commenced PCIOIK from 67%thermal power.9/27/80 0015 0125 1500 Reduced thermal power from 99%to 85%for turbine C.V.tests and SI's.Turbine C.V.tests and SI's completed, commenced PCIOMR.Reactor thermal power at>99%, steady state.9/28/80 1500 9/29/80 0115 Reactor thermal power at>99%, steady state.Reduced thermal power from>99%to 85%for backwash and precoat condensate demineralizers.

9/30/80 2400 Reactor thermal power at 85%, holding for condensate de-mineralizer problems.

42 Si nificant 0 erational Events Unit 2 Date Time Event 9/01/80 0001 1500 Reactor thermal power at 92%, EOC-3 coastdown control rod sequence"B".Reactor thermal power at 90%, EOC-3 coastdown.

9/04/80 1500 9/05/80 2130 2247 Reactor thermal power at 89%, EOC-3 coastdown.

Commenced reducing thermal power from 89%for refuel shut-down (EOC-3).Reactor Scram No.109 (manual)from 35%thermal power to accommodate refueling outage.9/12/80 1320 1650 Received permission for fuel movement operation, holding due to communication porblems.Communications restored, commenced fuel movement operation to accommodate LPRM maintenance.

9/19/80 1000 9/30/80 2400 Commenced core fuel shuffle operations.

Refueling operation in progress.

43 Date Time Si nificant 0 erational Events Unit 3 Event 9/01/80 0001 1455 1522 2055 2200 Reactor thermal power at>99%, steady state control rod sequence"A".Reduced thermal power from>99%to 63%due to"A" recir-culation pump trip from a spurious trip.Reduced thermal power from 63%to 54%due to"A" recircu-lation pump being out-of-service."A" recirculation pump maintenance completed and pump placed in service, commenced power ascension.

Commenced PCIOMR from 75%thermal power.9/03/80 1500 9/07/80 0230 0330 0430 1500 Reactor thermal power at>99%, steady state.Reduced thermal power from 99%to 75%for turbine C.V.tests and SI's.Reduced thermal power from 75%to 67%due to MSIV-1-26 closing too fast (~1.3 seconds).Turbine C.V.tests and SI's completed, holding at 67%due to MSIV 1-26 being left in closed position, awaiting maintenance.

Increased reactor thermal power from 67%to 75%, holding due to closure of MSIV 1-26.9/10/80 1500 Reactor thermal power at 75%, holding due to MSIV 1-26 being closed.9/12/80 2245 2355 Commenced reducing thermal power from 75%for shutdown for MSIV 1-26 mainte~y~ce.

Reactor Scram No.88 (manual)from 35%thermal power to accommodate maintenance to MSIV 1-26.9/14/80 0525 1009 1706 2233 2243 Maintenance to MSIV 1-26 completed, commenced rod with-drawal.Reactor Critical No.98.Reactor was made subcritical due to a feedwater valve (3-219A)leak.Repairs to feedwater valve 3-219A completed, commenced rod withdrawal.

Reactor Critical No.99.9/15/80 0155 0233 1600 Rolled T/G.Synchronized generator, commenced power ascension.

Commenced PCIOMR from 76%thermal power.

44 Si nificant 0 erational Events Unit 3 Date Time Event 9/16/80 2330 Reactor thermal power at 92%, maximum flow, awaiting rod,pattern adjustment load drop.9/17/80 2300 Reactor thermal power at 91%, maximum flow, awaiting rod pattern adjustment load drop, 9/18/80 0700 9/20/80 1358 2230 Reactor thermal power at 90%, maximum flow.Reactor Scram No.89 from 90%thermal power, on loss (1)of preferred power when"A" 480 volt shutdown board failed to transfer back to normal causing loss of"A" RPS MG set.Commenced rod withdrawal.

9/21/80 0104 0440 0500 1500 Reactor Critical No.100.Rolled T/G.Synchronized generator, commenced power ascension.

Commenced PCIOMR from 67%thermal power.9/22/80 2240 9/23/80 2145 2255 2300 Reactor thermal power at 90%, maximum flow.Reduced thermal power from 90%to 75%for control rod pattern adjustment.

Control rod pattern adjustment'ompleted, commenced power ascension.

Commenced PCIOMR from 82%thermal power.9/24/80 0725 2130 Reactor thermal power at 93%, holding due to computer malfunction.

Computer back in service, resumed PCIOMR from 93%thermal power.9/25/80 0200 1500 9/27/80 0130 0217 0300 1200 Reactor thermal power at 99%, maximum flow.Reactor thermal power at 98%, maximum flow.Reduced thermal power from 98%to 80%for turbine C.V.Tests and SI's.Turbine C.V.tests and SI's completed, commenced power ascension.

Commenced PCIOMR from 90%thermal power.Reactor thermal power at>99%, steady state.9/30/80 2400 Reactor thermal power at>99%, steady state.Equipment Malfunction (1) 45 Plant Instruction Revisions Cate or September 1980 Instruction Reason for Re uest Change in Facility Design EHI-46 Freeze Protection Program SI 4.2.A.6 Primary Containment and Reactor Building Isolation Instrumentation Low Pressure Main Steam Line To include heat tapes at cooling tower.Junction boxes have been added for test purposes.SIHI-3 System Instrument Maintenance Index 3-Instruction Reactor Feedwater System Density compensation removed per ECN P-0130, DCR 1533, workplan 9870 for Unit 2 only.SIMI-46 System Instrument Maintenance Index 46-Instruction Feedwater Control System Pressure compensation removed per ECN P-0129, DCR 1532, workplan 9838 for Unit 2 only.Change Required to Improve the Safety of Operation EMI-44 Reactor Protection System Scram Solenoid Relays EMI-80 Maintenance of Inboard and Outboard Drywell Leak Detection Isolation Valves To implement DPH N 80 Ml, which requires an inspection of the movable contacts for a possible binding problem.Recurrence control for LER 50-259/8040.'TI-23A Refueling Test Instruction 23A, Feedwater System When controlling in"A" water level sensor element in case of 250 VDC normal supply failure.

46 Re ortable Occurrences BFRO Occurrence Date Descri tion Unit 1 50-259/8060 8/14/80 While performing SI 4.2.B-60, thermostat TS-64-73 for"B" core spray pump area cooler fan was found set above the technical specification limit.50-259/8061 8/14/80 While performing SI 4.2.B-57, a thermal overload on the breaker for 1A RHR area cooler fan was found tripped.50-259/8063 8/20/80 While performing SI 4.8.B.4.2, CAM 1-RM-90-251 for the turbine building vent was removed from service for a period exceeding one hour.50-259/8064 8/20/80 While performing SI 4.8.B.4.2, CAM 1-RM-90-249 for the turbine building roof vents was removed from service for a period exceeding one hour.50-259/8065 8/28/80 Wind direction at elevation 887 M.S.I.failed.The LCO to restore the inoperable channel to operating status within 7 days was exceeded.50-259/8066 9/02/80 Operations personnel observed an annunciation on the torus hydrogen containment atmospheric monitoring.

50-'259/8068 9/01/80 Inspection of the fire protection system by a qualified fire consultant was not per-formed within the 3 year interval as required by Technical Specification 3.11.E.2.50-259/8069 9/02/80 While performing SI 4.2.A-17, channel B of"refueling zone isolation static pressure permissive and static pressure logic systems units 1, 2, and 3" modulating damper 0-PDC 64-8 failed to close.50-259/8070 9/19/80 During a review of Unit 1 core verification video tape bundle TY 582 at core location 11-06 was found to be 90'ut of proper orientation.

47 Re ortable Occurrences BFRO Occurrence Date Descri tion Unit 2 50-260/8033 8/15/80 50-260/8034 8/15/80 During routine test TI-36A an indicated leak was found on RHR heat exchanger 2B.During a routine test TI-36A RHR heat exchanger 2C was found leaking.50-260/8035 8/30/80 Test personnel detected an increase in pressure on the shell side of RHR heat exchanger 2D while performing TI-36A, RHR heat exchanger leak test.50-260/8036 8/29/80 During normal operation while performing SI 4.7.H, the H H-76-39 hydrogen monitor for the drywell would not calibrate.

50-260/8037 9/14/80 Fuel assemblies TZ 758 in core location 15-26 and TX 399 in core location 29-28 were found to be rotated 90'rom their correct orientation.

50-260/8038 9/11/80 With the unit in cold shutdown during a scheduled refueling outage, HPCI check valve 2-73-609 failed the local leak rate test.Unit 3 50-296/8031 8/09/80 During the performance of 1'RI 303 it was found that the EECW flow was below the minimum allowed flow on 3B RHR pump seal heat"exchanger.

50-296/8032 8/25/80 While performing RCIC steam line space high temperature SI 4.2.B-32, lead wires were accidently pulled out of the RCIC speed feedback magnetic pickup connector.

50-296/8033 8/15/80 During routine test TI-36A, a leak on RHR heat exchanger 2B was indicated.

50-296/8034

'/29/80 While investigating overload setting for RHR area cooler fans, the overload for 3A RHR pump area cooler fan was found to be set too high.When the overload was adjusted to the proper setting, the overload relay failed causing the fan to trip.50-296/8035 9/Ol/80.The"A" reactor recirculation pump tripped.The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO for one pump operation was initiated I,'Technical Specification 3.6.F.1).

48 Re ortable Occurrences BFRO Occurrence Date Descri tion Unit 3 50-296/8036 9/04/80 While running SI 4.9.A.l.a after SEMI-18 had been performed, it was found that diesel generator 3A would not trip to idle speed from a loaded condition.

50-296/8037 9/09/80 50-296/8038 9/07/80 During normal operation, while performing SI 4.7.H, H2M-76-39 would not calibrate.

While running SI 4.7.D.l.b.2 with unit at 99%steady state power, main steam isolation valve FCV 3-1-26 closed too fast.

Primar Coolant Chemistr Parameter 1.Gross Radioactivit September 1980 Unit 1 Unit 2 Unit 3 a.Crud on 0.45 millipore filter (uCi/ml)High Low Average b.Filtrate (uCi/ml)High Low Average 2.Sus ended Solids 3.98E-03 5.00E-04 1.22E-03 4.01E-01 1.13E-01 1.79E-Ol 8.68E-03 3.60E-05 1.47E-03 1.56E-01 1.60E-03 3.29E-02 5.32E-03 4.64E-04 1.12E-03 2.36E-01 6.47E-02 1.26E-01 Stained 0.45 milli ore filter (b High Low Average 3.Gross Tritium 25<10<10<10<25 10<10<10 (uCi/ml)High Low Average 1.44E-03 1.14E-03 1.27E-03 1.17E-03 9.88E-04 1.04E-03 2.18E-03 1.53E-03 1.81E-03 4.Iodine-131

~(uC i/ml High Low Average 1.02E-03 1.89E-04 6.88E-04 1.92E-03 3.43E-05 5.01E-04 7.64E-03 2.07E-05 1.75E-03 (1)Unit down 50 Primar Coolant Chemistr (Continued)

September 1980 Parameter (Continued) 5.Ratio of Unit 1 Unit 2 Unit 3 Todine-131 to iodine-133 6.Chloride (ppb)Limit 100 High Low Average 4.33E-01 1.02E-01 2.13E-01 1.72E+02 3.45E-01 4.93E+Ol 1.32E+01 3.33E-01 2.64E+00 High Low<50<50<50<50<50 Average<50<50<50 Limit 5.6 or 8.6 High Low 6.7 6.0 6.7 5.7 7.0 5.8 Average 8.Conductivit (umho/cm 8 25'eratin Limit 1.0 umho/cm Shutdown Limit 10.0 umho/cm High Low 6.4 C.)8 25'.)8 25'C.2 8(1).36 6.3 2 4(l).38 6.2 2 4(l).15 Average.72.81.53 Unit down (1) l<V IIII R<.t<<<n<~I I I~n y n I<~<~<~II~I I vs~4~L<~ww we<nv<<n<<<.,~~vv<<w GX:~J'::~%II~Ag PIII I<0 III II~.L CRAPII I*PC R 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 IO 0 0 0 I 00 rn<O H o H.CII M<<r 0: 0.-a--C H O" H--<<r 0: H 0-M 45-D=-O W-A-0 0 A.=0-H H H--ps A-0 a CA W H O H.gl-0-C"-W 0 0."~P OC CII+MW 04 PI1 CI$CO H W CII Cll CQ xa-am O CII CI1--o O=H lcl=0 O CII O 0'=0=a: H'O Pn On io ln A g 0 8 CII A H A o~\, M 0 rn 4 5 6 7 8 9 10 11 12 13 11 15 16 17 13 19 20 21 22 23 24 25 26 27 28 29 30 31 tv1ONTH OF September 19 80 13hSl:.1)111'ON NTDNI'Cll'I'lll Hl';1'1'.8 ill:hl)l'NCS

~V, I F F~~~~~(c'Coi@j+CIIAPII PAPUA tIIIIIO IA II,J,A I 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AC UHU ATE ER GE cf:19 f 80.F-AC UMV D-ER GE.C'/K9 0=55-I 2 3 4 5 6 7 8 9 10 I I 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 i V i4I L~I~L Alai~~i 1 A~(.CX 1: till IEO Ii Il,S,i, Ct<At'N pAVCll 2 3 4 5 6 7 8 9 10 11 12 13 14 I 5 16 17 19 19 20 21 22 23 24 25 26 27 28 29 30 31 n 0-=IK n 0 0 I V.OQ 2 3 4 5 6 7 8 9 IO 11 12 13 14 19 16 17 1 il 19 20 21 22 2 3 24 25 26 27 28 29 s0 31 MONTH QF September igloo BASED UPON kfIDNIGllT NW HETER READINGS tw alE I\~I Hvl IN U1 tkh14~Iw@tIIIaly (cCoQd~>s"~

Cll*PI~PAPEA ICI~IID III II, C,J 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 AC LAT'D.GE VERA c/y 191 79.5)U.-ACC LAT VERA'D.A GE c-/--19 80-68.2)-C ft'LA 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 4 I I<<a 8 f 4 dC EC C<<I~~Unit 3 AVERAGE DAILY GROSS CAPACITY FACTOR 4 C CI I~4411!~}!hj~~~>>afja il i jj>>'I}j}a'~I h!jt}<ll i!, l jhft~hfdf If I!),hj LIMITED>>FLO OD'ENEI I.l ND SI'S jl!I S AA I 4 TEST TURB!,'l It l" I h I~l jlh}at f" jfr h~W(OD~~f i~h'lf hi>>I}'i ft I, MPi,FL I'i af k L'IIif TED k,~I I ER II!'h UT I E!TO CO If<<I'ICE ERV PCI'HO DINGf,D N AIJUS ak~I}'>>h jt 4 ROL, ROD*PATTER fE I CO/>>I}lh~I IOIhfR':Dl I~l l I I 0ER ASCE I I 4 I'I'I h NS ION 4 3561 HOU*~ll h h i I SCIM k~tljl" Ill!>>l'.I h",Ij~I f!hi<<alt I~~f l WIi I~I L'IIh P NEE OW l(ROQ DED fETED OAD IMUEEI'L DRO~hh', ,, 1!!I<>I~~..if.i:~,~~MAINTENANCE TO MSIV 1 h'.'f I I!f,~~I'l SCRAM AT 2'355 HOURS 14~fk",,,'C fl.'i I i 4 I I 4 hfll I I I h~'.C j'It I 4 I-I II.Ikf Il:;II}~i i!1>>MSIV 1>26 OUT'0R , h I I IW I,I~!MAIN TEN TURBIN)CVITESflS'A i'i$J~-A~QUX WQ~j l I!vljl ND'I'a I~TC INXXNANC;i.,'i i.a~l ill.I>>ki li 4 IMU~if FLOW (ROD LIMITE D)PCIOlhfR~I If~'I 4 f NCE T FOR HAINTENAA I I AI'E'CIRCULATION PUMP 0~~I I days unit on cooling tower (helper mode)<<Indicates 4 ,h RS~~I}~f f ,-hk I Qh CC n k<<I f'=o 00 Gh (c='hf I g fhf 4J tWte fhh cn A 0}-y 0 Ch 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 ED.AVE G SO'.(SJ CUE.A ED AV iAG i~C y-l 79 (-5=7.SO A O A 2 3 4 5 6 7 8 9 10 I'I 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 MQNTH QF Se tember]g SO C' 35/7 RRDHRSTE tIONTIILY AVERAGE DISCIIAR RATE/T RL ACTIVITY DISCtlRRSED FLOH RATE}II EH~RK.G BYE~IB.H LQH~2.2 I8/2 RCT I V ITY BCT I V ITY 2.e BVG~H.B LQH~H.I 7.8 RRDHASTE SYSTEH THROUGHPUT CEALLOIIS~HG)

HRSTE 5065YSTEII RHETT HIGH~7.6 RVG~K.H LOH<2.I.8 FLOOR DRAI 8 F FLOOR DRRIh'IGH>>

2.8 BVG~I.H LOW~H.H l.8.8 a.a l8.8 T RRDHRSTE-tlat<<P~

RRTIIIG COSTC$<<E43)T HASTE 7 tiONTII R 0 III TOTRL COST T TOTAL HlEH~63.ll BVG~W.H LGH~KI.3 5!RSTE H I EI<~IK.7 BVG~2K.H LGH>>3.2 FLOOR DHRIN BIEII~39.8 BVG~IB,H LOW~G.S HUILDINE RND STRCI MONTHLY RELERSE RRTES SEPTEMBER IBHI/I SEPTEtlHER ISOH PREVIOUS II IIISTAttTAttEOUS PLOT AttCE/Stt I f'T 20L'20 BUILD lltG A ISO!4 AUILDltlS AVG=GUILDIIIG LQII 4 STACK tl!GI!4 STACK AVG=STACK LOII~!SAI.CH'l33.99 7l.00 IS!7I.CH 3HSH.S3 S20.00 2'Vtl.20 B!.GO Gl.GH 23232.00 3!l2.3fl l32.30 I SHOO AICROCURIES SEC/I!HO ADDED TO ALL OUILDltlG VALUES~~~4~4 4 4 4~4~"'4 F 4>4~4 4~~g g 4 4+1 4 4~4 4 I-4-4-1 4-4-4-4-4-r4-)-4-r4 4-4 4 4~4444!IAllll 4 Si I 4~4 4 IC I 4 i'I C IH IS 20 2S 3 el l I 4 TECHNICRL 5PECIF ICRTIGN CGHPRRI5GN HUILDINE RND STRCK RELER5E BHTE5 5EPTEI"IHER IBEIB I ttSTfitITBIIEOUS PLOT ONCET'SII II T SEPTEtlGER IBQH PI!EVIOOS I I t!I I.G lll GH~I.'I7 at.78 BVG a>>!I.SII'OM~S.I2.II 2 I.al O.'I I!I JI, a...a...a.-.a.a.a a=a~~a I-DIIYS I!>>l I~I!II I~I~L~I LI If>>L~I l I~~>>a~

rs cnemis les cn 0 teselIO Im Is~S.A I 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 10 A o 9 0 9 50 2 e 3~6.'-7 0-l-Re cto zan f~l-pP s tI'-11 a':1iP ue'Iles e co te'I binI.Ie pro~l~.ec:.V: Tu 01 Fu I IAI c t ra a te tur.in go tao an:lie te s tea ts ne equ ain'e n ang=SI 3 s ll tao eju uti>p HlP nc 11.B at'<<p U OU Dg eed t~PU CC 5 po pre-'H 0 ra r.e r-a man p3=n ca 0 r-o i.t oa n++ro n)=.f se of.se b 11 0 j ec eke 2 3 4 5 6 7 8 9 10 I I'12 13 14 15'16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 MQNTH Qg September Ig 80 C N 4 f'i i I'A I'L'il 1 2 3 4 5 6 7 8 9'10 11'12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 IO-2-;4-:Co e act e n:Rqf u esca-B a'co'ce'in re eo std:--sh era..OU e-E wn td taj 1g, el: wn.=(e sh f or-OC=-Er EH-re ma)-..uel ng oui).=.Cy APP le" Eered-C=Eu it)-LP e'pPs ce len 70 A o/0 Q 20 2 3 4 5 6 7 8 9 10 11 12 13 14 15.16 17 18'19 20 21 22 23 24 25 26 27 28 29 30 31 MONTH O SeP tember 19 80

<<A':5 A'I ONA 0>~0A m<01~55<5150 lm U,c, 5, 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 6 27 28 29 30 31<0 1.0~0 50 50 0 O H 50 50:l'2=3-Tj uel b ur ecz;pr ne rcupL CQI es s-a ori.pum em'IIm.on'j:.l.A-00"-5:1 SIV 1-.6=1 sL'.1 SU I.I.:.6':.I-RR=T'ld amm eac ue1 ng OV pr.du dM V:1 26.(ma 88.1ng+Scr GO I PN-~tO,-dit on.be.V.ua7 US ng: Jg o ed.i.n ce----.J.O-l'l-=l2 axi eac ont lunl or ol-s44p r.od m-.pa tel nL omp lte 5.-0--S rvi I 2 3 4 5 6 7 8 9 10 11-12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 MONTH OF~Sptkmmer 10 80

TVA 7382'PP.l 1 78)63'Period I lours Item No.Unit No.NUCLEAR PLANT OPERATING STATISTICS Browns Ferr Nuclear plant Month Sen tember 19 80 Average Hourly Gross Load, kW Maximum Hour Net Generation, MWh 3 Core Thermal Energy Gen., GWD(t)90.660 14.3365 80.1247 Gross Electrical Gen., MIVh Station Use.MWh Net Electrical Gen., MWh 699 320 113 120 625 700 18 21 477 302 677 843 107 818 607 023 1 438 4 1 2 4 7 Station Use.Percent 3.07 4.69 2.8 8 Accum.Core Exposure MWD/Ton 12 610 16 028 1 27 42 9 CTEG This Month, 10 6TU 10 Hours Reactor Was Critical 7,425,276 1 170 328 6 570 852 118.78 703.30 669.05 15 166 456 14 1.13 Unit Use, Hours.Min.

12 Capacit Factor.Percent 697:13 88.4 118:47 14.3 654:20 79.1 1 470:2 60".6 13 16 17 Turbine Avail.Factor, Percent Generator Avail.Factor.Percent Turbocen.Avail.Factor.Percent Reactor Avail.Factor, Percent Unit Avail.F ctor, Percent 99.5 100 99.5 100 98.5 19.0 19.0 19.0 16.5 16.5 100 100 100 100 4.0 72.8 72.2 18 Turbine Startups 0 19 20 Peactor Cold Startups 0 0 0 Cl lJ 21 Gross Heat Rate, Btu/kWh 22 Net Heat Rate, Btu/kWh 23 24 25 10,620 10,950 10 350 10 500 10,850 10 820 10 550 10 890 26 Throttle Pressure, psig 950 913 38 27 Throttle Temperature, F 539 534 28 Exhaust Pressure, InH Abs.3.12 3.33 29 30 31 32 33 34 Intake Water Temp., F Reactor Feedwater, M Ib/hr Makeup, Percent 82.9 12.4 87.0 11.8 83.8 11.7 12e 36 37 Full Pr.Days to End of Cycle (E)(3)38 Oil Fired for Generation, Gallons 39 Oil Heatin Value.Btu/Gal.192 31 2 137 60 40 Diesel Generation, MWh 29.4 Max.Hour I'let Gen.MWh Time Date 43 2,972 0600 9-5-80 Pemarks Load Factor,%Max.Day Net Gen.MWh Date 72, 284 9-4-80 65.1 1~Inf orma tion unavailable.

2.Unit 2 refuel outage (EOC-3)began at 2247 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.549835e-4 months <br /> on 9-5-80.Based on 5%capacity tactor.D t 5 bmitted Date Revised Plant Superintendent TVA 4'C Irn-3 1st UNIT OUTAGE AND AVAILABILITY licensed Aeactor Power 3293 MIVRh)Generator Rata)g 1152 MW(e)Design Gross Electrical Rating 1098 4 MW Brouns Parr Unit No.Nuclear Plant l MonthiYear Septcnber 1980 Period Hours Total sids radn~58 24 00)S)S rdbn 06 07 T)dne Vn)l Available Nol V)ed Time NOt Ava))able Reactor H)$Mdn Tw bine~lr)s M n Nds M)n~0)55 Vn)I I srs Min 03 r 55 Time O)dt Vail T)me In I id)Mdn 23 43 lbs M)n 13 41 OUTAGE CAUSE Turbine trl due to sto METHOD OF SHUTTING DOsvN REACTOR Scrub UN I T STATUS DURING OUTAGE liat Standby CORRECTIVE ACTION TAKEN TO PAEVENT REPETITION 5 IO 12 13 15 18 P.t 25~r)27 S~"4 00 22 22 J 8~0 24 100 22 t22 L22)3~41~01 37 0~138 05 130 22l 22~tt 07~l,d*d on natn transforner sudden ressure rota Scran Oot Standby 29 30 31 1'tat 1~08 57 gC 0)79 13 11 44 03 I 55 1 1 03>C OC t, UNIT OUTAGE ANO AVAILABILITY Licensed Reactor Power 3293 MW(lh)Generator Rating~252 MW(e)time Vml Avaelbre 1 nrar~Cen.llOl Vied Tw bine nay I lis 4'I n I lis l.bn lbs rvbn~lus.Msn Design Gross Oectricat Rating~~84 Mw Vml lbl Mm~S4S ItlIn l 4S Msn Time eeet AVasrabre Aeactor Urut No Vnil Time Ovt Time In lb s Min llis Mm Nuclear Plant OUTAGE CAUSE METIIOO OF SIIUTTING DOWN REACTOR UNIT STATUS DURING OUTAGE CORALCTIVE AC1ION TAI<EN 10 PREVENT ACPLT ITION Month/Year Se cenbee 1980 Period Hours 720 I 2 24 I 00 24 00~24 00 22 I 47~24 00 22 lC7 06 54 06 i 54 24 00 24 00 0LLL3&1~24'00 24L 00 I 12 13 15 22 I 25 2Ci 27 I I I I I 29 drs L" Intel 118 47 18 47~24 582 I 54 82 54~-'is i UNIT OUTAGE ANO AVAILABILITY Licensed Rcatlnr Power 3293 hIW(th)Gcncialnr Rating 1152 I.IW(c)Design Gioss Electrical Rating 1090~4 MSV Srovns Petr Nuclear Plant U is N.~hlonih/Year Se tenbec 19SO Period Hours 720 Toter trst Mn 24 i00 Gcn, t ris c.lsn 24 00 Nol Vscii Cist htsn Tinsc Unit AvaiNbte Tsss bine~trit lain Time Not Available Reactor leS Min~its r Min Vnil~His M so Vnsl Time In Time Ovl lrsr htin tlii Min OUTAGE CAUSE METHOD OF SHUT TING DOWN REACTOR UNIT STATUS DURING OUTAGE CORRECTIVE ACTION TAKEN TO PREVENT REPETITION c c sJ IO II 12 13~4 l5)fi l7 18 lg 0?I?7~7?l?6 27 24 IOO 13~08 2it I00 jk I28 2'K I 24~00 I 21.IQL+4 I 0 1'9i 00 24 00 c I 0~05 00 c 00 l05 24 00 08 I32~23 55 13 5S 02 33 05 00 Maintenance to MSIY 1-26 and feedvater valve 3-219A lass of nAn RPS MG Sct Manual Stean llot Stan b Ilot Standb 29 30 2~4 3l Trit.tt 676 31 t c 24 00 I 654 20 22 11 I 43 9 67 OUTAGE

SUMMARY

September 1980 The unit two reactor shutdown sequence was conducted in an orderly process on September 5, 1980, for refueling activities and routine maintenance to plant equipment.

The refuel activities involve disassembly of Unit 2 reactor for refueling operation with reactor startup scheduled for October 26, 1980.The routine maintenance involves inspection and repairs to major components and safety systems within the plant.The initial containment entry was conducted at 1:05 P.H.on September 6, 1980.The planned duration for the Unit 2 cylce 3 refuel outage is 49 days.The pre-planned schedule shows that turbine inspection and maintenance work sequence as the critical work path, a fix'st at Browns Ferry Nuclear Plant.In order to prevent the outage duration from exceeding the 49 day schedule, non-curcial modifications are being minimized, however, major modifications intended to meet safety requirements are being performed.

68 ELECTRICAL MAINTENANCE

SUMMARY

September 1980 Unit 1 There were no major maintenance on CSSC or non-CSSC equipment during the month.Unit 1 tripped when a ground in the wiring to the sudden~pressure relay caused a transformer trip.The ground was cleared and the unit returned to service.A summary of non-CSSC and CSSC maintenance activities is given in the following electrical maintenance summary.Unit 2 Major activities include major maintenance inspections to PCB's 5244 and 5248, inspection of 2A 500 kV transfoxmer, and inspection and repair of leaks on 2B and 2C main transformers.

At the close of the month, work is 90%complete on PCB 5248 and 25%complete on PCB 5244.The inspection of 2A main transformer is complete and final testing in progress.Work continues on 2B main transformer.

The 2B condenser circulating water pump motor failed on September 2.After testing, the motor was sent to the service shop for repairs.The motor is due back in early October.Routine refueling outage activities are in progress.A summary of other non-CSSC and CSSC maintenance activities are given in the following elec-trical maintenance summary.Unit 3 A scram occurred on Unit 3 when returning 480 volt shutdown board 3A to service following changing the tap setting on transformer TS3A.The tap setting was also changed on transformer TS3B and TS3E.There was no 69 ELECTRICAL MAINTENANCE

SUMMARY

(Continued)

September 1980 Unit 3 (Continued) major maintenance on CSSC and non-CSSC equipment.

A summary of other non-CSSC and CSSC maintenance act'ivities is given in the following elec-trical maintenance summary.Common NONE DROWNS PEit1;YiilUCLHtll PLAIT UHIT 1 ELECTRICAL HAINTENANCE SRBfhRY 1'or the Honth of 0,".te 9/2/8 System Neutron Honitor in Component RBH Bypass Switch Nature of Haintenance RBH Bypass Switch on panel 9-5 needs repair-ing E ect on Sa c Operation of The Reactor NONE Cause of Halfunction RBH Switch Bad Results of Halfunction Switch would not go in bypass Action Taken To Preclude Recurrence Replaced RBH switch.Checked switch for proper operation.

Switch functioned okay.TR8 179518 9/23/80 RNR ECV-74-71 RHR valve 1.-74-71 won'run Unit in limiting condition for operation (TS.3.5.8.7)

Hotor burned up Valve inoperable.

Performed EHI 71.Replaced old motor.Performed EHI 18.Valve now functioning properly.TR8 165755 LER No.BPRO 50-259/8072 o URU!'UR"URRT UUCUElS PXRUT UUXT 2 IQ,XNTENANCE SUtkfARY For the Honth of September]9 80 D.".te System Component Nature of Haintenance E ectonSae Operation of The Reactor Cause of Halfunction Results of~Rfal f tmc tion Action Taken To Preclude Recurrence 9/21/80 RBCCH 2B RBCCH Pump 2B RBCCH pump motor trips out.Sparks reported com-ing from the motor.NONE tutor failed.i Loss of 2B RBCCH pump motor.Hotor repaired at'ervice shop, then returned to service.TlU/178647, 160689 9/22/80 RHR FCV-74-24 Valve will not cycle.NONE Hire loose in alve would not cycle motor starter>overload assembly Tightened loose wire on overload assembly in motor starter.Valve operated okay.TRt 1'78632

~~I~~~~~~~~~~~~I~~~~~~I ol I~~I I~ol~~~~~~~~~~I I I~~~~~~~~~~I l I<<I'l o~~~~ol~~~o~~~~~~~~~I I~~~~~~~~~~'/l~~~~~I~~I~l'~~~o~~~~~I~o~I~~o~I o~~~~~~~~~~~I I o~~~

NON-CSSC E UIPMENT URONNS PERRY NUCLEAR PLRNT UNIT ELECTRICAL MAINTENANCE

SUMMARY

Pot tbe Noetb oP SePtelnber IP SO DaLe 9/13@0 RWCU System Com onent 2A RMCU demin.Nature of Maintenance 2A RWCU demin.F valve will not open during precoat step.Cause of Malfunction or Maintenance Action Step switch not working properly.Corrective Action Adjusted step switch.Checked okay.TR8 169260 9/17/80 Reactor water cleanup.2B reactor water clean-up.pump motor 2B RMCU pump'motor locked up Motor bad.Replaced with rebuilt motor.Checked okay, Tlg 180452 9/19/80 Main steam FCV-1-59 Valve will not operate.Motor burned up and torque switch bad.Replaced motor an'd torque switch.Performed EMI 18.Checked okay,-TR8 160644 9/21/80 FCV-69-8 RMCU demin, bypass valve will only, open and close.Broken limit switches in valve FCV-2-69-8.

Replaced broken limit switches.Performed EMI 16 and 18.Checked okay.T1UI 169299 UROIINS PERRY NUCLEAR PLAN'1'NLT NON-CSSC E UZPlmNT ELK'CTRXCAL ifAXHTENANCH SUiQlARY pot tha Hooth of RapteaIbet 19 80 l)a te 9/25/80 RWCU System Com onent 3A RMCU demin.stepping switch Nature of Haintenance 3A RMCU demin.stepping switch needs to be cleaned and checked.Cause of Halfunction or Haintenance hction Switch.contacts dirty.-" Corrective Action 1 Inspeated switches and cleaned contacts.Checked okay.Tip 179.318 76 MECHANICAL MAINTENANCE SALARY September 1980 Unit 1 On September 19, 1980, the 1B RFP was experiencing high vibration problems.The RFP coupling was inspected and was found to be low in lub-ricant.The RFP coupling was disassembled, cleaned, and filled with new lubricant.

This corrected the vibration problem.The mechanical controls on all RFP turbines were inspected for proper lubrication and cleanliness.

Unit 2 Twenty-three of the CRD scram pilot solonoid valves were rebuilt during the month.A number of valves throughout the turbine and reactor building were worked on for packing leaks, broken diaphragms and o-rings.Some of the small hand control valves were replaced due to steam cuts around bonnet gasket surfaces.The 2A RCW booster pump discharge check valve was replaced because the old discharge check valve was stuck in the open position and beyond repair.The 2B reactor water cleanup demineralizer resin trap was replaced on'September 6, 1980.2A RCW pump isolation valves were dis-assemble, cleaned and reassembled.

The RCIC turbine and pump were inspected during the last week of September and all outage work was completed September 30, 1980.The Unit 2 HPCI work is behind schedule due to delayed shipment of the new pedestal.The disassembly work has begun on the removal of the temporarily repaired pedestal performed earlier this year due to water hammer damage.The RHR and recirculation system valves graffoil packing was adjusted during the month.

77 MECHANICAL MAINTENANCE

SUMMARY

(Continued)

September 1980 Unit'3 Unit 3 ran essentially all month with only minor repair work with the exception of repair work to 3B MSIV.The MSIV had closed too fast during a routine surveillance instruction test.The unit was removed from service September 13, 1980, for inspection and repair to the MSIV.The valve operator was found to be approximately three quarts low of oil.Oil was added to the operator and the valve functioned properly.No sign of oil was evident on the floor or around the valve at the initial inspection.

3B CRD filter required replacing on September 25, 1980.The Unit 3 RCIC had to have three quarts of oil added on'September 8, 1980.The outboard packing on 3A fuel pool cooling pump required tightening on September 22, 1980.Common Scheduled maintenance of all service air compressors were performed September 24, 1980.No significant problems were found.The raw cooling water.lines to the CRD pump bearing were cleaned during the first part of the month.The 1B RHRSW pump vibration reading was above the acceptable limits on September 25, 1980, and the pump was pulled and disassembled during'the last few days in September.

CSSC E UXP:kk;I!T 2'I IKCIU.NXCAL HAXNTENAN"F.

SUIQ4<RY DATE 9/22/80 SYSTP~I RCTC CC~!PONENT Turbine exhaus rupture disk NATUIIK OP E'i1.Vi TENAi ICE Ruptured disk EFFECT ON SEVE OE'EBATXO:I OF TIIE-RI~CTOR none CAUSE OP I!.'iLPUNCTXON old disk ruptured RESULTS OF I'ALFUNCTXON Ruptured disk ACZXON TAI'EN'19 PRECLUDE RECURRENCF.

Replaced disk with new one TR 103732 CSSC EOUXPH 2!T HECHAKXCAL KXINTENANCE SUGARY 3 BATE SYSTBf CGiaiPONEN T iB.'L'URE OF KXXNTENAN CE EFFECT ON SAFE OPERATXO:i'F 1dE REACTOR CAUSE OF Y~LFUNCTION RESULTS OF NALFUNCTXGN ACTION TAl:i;N'10 PRECLUDE RECURRENCE 9/17/80 Fuel pool coolin 3A FPC pump Outboard pack-None in Packing leak Packing leak Adjusted packing TR 178817 1 I.'02-CSSC~EUIPl KHT lKCHANICAI, MLU"HA11CE SLMQRY For the ltoeth of September tp 80 Date S stem Com nnent Nature of?faintenance Cause of 14alfu>>ction or llaintenance Action Corrective Action 9/12/80 Radwaste FSV-77-19 Bad solenoid valve Bad solenoid valve Replaced solenoid valve TR 182079 9/19/80 Reacotr Feed-um 1B RFP High vibration Lube oil dried out in cou lin Cleaned coupling and put new oil TR 103114 t0:4-CSSC~F.

UIPl KHT>?EC?>AHICgZ.

HAP?T"HAHCE SEQfAPY For the?fonth of September 19 80 Date S stem Com onent Nature of?fai.n tenance Cause of Malfunction or llaintenance Action Corrective Action 9/80 RCW 2A RCM pump isolation valves Isolation valve 2-24-516 A,B,&C ,2-24-520 A,B,&C would not close Isolation valve out of adjustment S Removed, cleaned, and a'djusted, and reinstalled TR 119083, 119085, 119086.9/28/80 Hain Steam PCV 1-167 Valve binding Valve binding Cleaned, lubricated, and adjusted valve TR 166667 9/24/80 9/25/80 Heater drains and vents LCV-6-73B Heater drains LCV-6-73A and vents Bad o-rings and diaphragm Bad o-rings and diaphragm Bad o-rings and diaphragm Bad o-rings and diaphragm Replaced o-rings, diaphragm.

Adjusted packing and lubricated ste TR 166658 Replaced o-rings, diaphragm.

Adjusted packing and lubricated sten TR 166659 9/25/80 Heater drains and vents 9/25/80 Heater drains and vents 9/10/80 Feedwater LCV-6-62A LCV-6-62B HCV-3-211A Bad o-rings and diaphragm Bad o-rings and diaphragm Bad seat in valve Bad o-rings and diaphragm Bad o-rings and diaphragm Bad seal in valve Replaced o-rings, diaphragm.

Adjusted packing and lubricated ste TR 166661 Replaced o-rings, diaphragm.

Adjusted packing and lubricated stem TR 166662 Replaced valve TR 180437 9/9/80 Heater drains and vents HCV-6-418A Bad seat in valve Valve seat worn Replaced valve TR 180438 82 INSTRUMENT MAINTENANCE SALARY September 1980 Unit 1 There were no major instrument maintenance or modification activities on Unit 1 this month.Unit 2 Extensive time and effort has been expended this month on refueling outage related routine calibration, maintenance and modification activities.

Major areas include: Installed the Hays-Republic oxygen and hydrogen analyzer system, including writing of new surveillance instructions, maintenance procedures, and initial calibrations.

Implemented DCR 1937 by work plan 6617.This modification replaces six mercoid pressure switches in the condensate system.Implemented DCR 1892 by work plant 9818.This modification prevents feed-water control loops from reading downscale upon meter failure.Replaced twelve LPRM detector assemblies due to end of life criteria.An additional LPRM assembly had to be replaced due to being irreparably damaged during preliminary LPRM activities.

All thirteen assemblies are of the GE NA-200 breeder types.Representatives from the General Electric Company in conjunction with Instrument Maintenance personnel conducted extensive testing on the EHC system to resolve the tubing vibration and servo valvea'ilure problems.Realignment and modifications include: increase the dampening on the fluid pressure sensors, changed the valve movement operating point to the second slope of the Diode Function Generator and attached the sensing line to the wall at four foot intervals.

83 INSTRIRKNT MAINTENANCE

SUMMARY

(Continued)

September 1980 Unit 3 N There were no major instrumentation maintenance or modification activities on Unit 3 this month.Common DCR's were initiated this month concerning the following modifications:

-1.Replacement of FE-66-111 in the off-gas system, due to the flow element not being reliable and spare parts not available.

2.Enclose and air condition the off-gas hydrogen analyzer area.This modification will imporve the environment of the electronics and therefore improve the reliability of the system.3.Incorporate additional HPCI and RCIC testing parameters'into the Real-time evaluation, monitoring and analysis system.4.Replacement of the freestanding E-Field mounted on the face of pilars at the intake pumping station with a microwave transmitter and receiver system.5.Extending the E-Field in sectors 4 and 5 along the wingwalls of the intake to the waterline.

6.Installation of additional standby batteries in the PERIM-ALERT and Wells Fargo system to sustain operation for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following a power failure.This modification is due to NRC specification WA-00450B.

INSTR12KNT MAINTENANCE SUKfARY (Continued)

September 1980 Com uter S stem System availability for the units 1 and 2, and unit 3 process computer was 98.47%and 99.86%respectively.

Downtime was due to analog scanner problems which was resolved by replacing 25 leaking diodes.System availability for the PRIME computer was 100%with only routine mainte-nance being performed.

System availabiltiy for the RRRMS PDP 1134 computer was 99.93%.Downtime was due to high temperature in the computer room (1/2 hour).The Instrument Maintenance section in conjunction with the Controls&Test Section has installed two NOVA 1200 computers in the secondary alarm station to monitor the RUSCO MAC S40.This system will allow report generating and up-to-'date cross reference of all coded data form the cardkey system.Securit S stems RUSCO Card Access S stem-On September 2, we experienced another system malfunction due to power transfer.As of this date, we still have not received the recommendations from Chattanooga or Knoxville for an uninterruptable power supply to help stabilize our power source.CCTV-Browns Ferry now has 18 CCTV cameras in operation.

These cameras and associated monitors are requiring daily maintenance for adjustment and re-location for security and fuel pool activities.

Intrusion Detection Hells Far o-Performed routine maintenance and repair on MP2 modules, AS24 boards, and Cu-3 boards.Failure rates on these components are much higher than expected.

85 INSTRUMENT MAINTENANCE St&MARY The following instrument Maintenance Summary tabulates man-hours expended on instrument maintenance, calibration, loop checks, and work plans for various plant systems.Svs tern Main Steam Unit Total 3 M-H 30 2.3.5.6.12.18.23.24.25.26.27.28.31.32.33.34.35.37.39.40.43.44.46.47.53.56.58.63.65.66'7.68.69.70.71.73.74.75.Condensa te Ho 0 Reactor Feedwater Extraction Steam Heater Drain and Vent Auziliarv Boiler Fuel Oil RHR Service Water Raw Coolin Water Raw Service Water High-Pressure Fire Protection Condenser Circulatin Water Water Treatment Air Condition Coolin and Heatin Control Air Service Air Vacuum Primin Generator H dro en Coolin Gland Seal Water COo Station Draina e Sam lin and Water Oualitv Buildin Heatin Feedwater Control Turbo enerator Control Demineralizer Backwash Air Temo rature Monitorin Biothermal Research Standbv Li uid Control Prima~Con tainmen t Standbv Gas Treatm nt Off-Gas Eeer enc E nionen~ttoolin

!Pater Reactor Water Recirculation Reactor Water Cleanup Reactor Buildin Closed Coolin Hater Reactor Core Isolation Coolin Hi~h-Pressure Coolin In ection Residual Heat Removal Core Sorav Isolation Coolin 39 40 21 21 10 51 157 35 43 32 515 320 51 36 10 45 181 102 55 237 12 304 147 49 72 74 51 10 45 71 28 12 28 10 62 94 207 173 10 134 468 32 340 187 55 125 34 32 86 INSTRUMENT MAINTENANCE S'CHARY (Continued)

S stem Unit Total M-H 76.77.78.80.82.84.85.90.92.Containment Inertin Radvaste Fuel Pool Coolin and Demineralizin Prima Containment Coolin Standb Diesel Generator Containment Air Dilution Control Rod Drive H draulic Radiation Monitorin Neutron Monitorin 308 1 0 550 228 1086 96.99.Travelin In-Core Probe TIP Recirculation Floe Control Reactor Protection RPIS EHC 26 330 245 24 50 335 259 SI IMI Comouter 4020 Prime RRK 1S 129 313 743 151 1075 504 781 2599 427 1211 313 Pere herials Card Ke intrusion Detection Closed Circuit T.V.Portal Monitors Standards Coolin Towers 321 203 304 256 16 331 49 319 49 319 321 203 304 256 98 654 331 General Instrument Pork Instrument Repair Recorder Maintenance 443 179 32 223 139 761 32 223 General Employee Trainin ADDrentice Trainin H P.Trainin B'.JR Instrumentation)

Trainin"C" Zone Dressout Radiochem 1ab H P Lab TR's Received/Completed Dual Rate Foremen Outa e Sup ort Hand and Foot Monitors X Rav 65 262 100 255 45 45 96 86 17 177 308 12 211 260 33 27 62 25 47 61 204 8 127 260 125 111 20 307 774 39 438 520 255 299/269 93 47 17 I.D.Camera Overtime Seismic Monitors'2 292 239 30 5003 42 441 5975 30 CSSC E UIPlfENT BROWS l FERkY'UCLEAR PLANT UNIT 1,2,3 INSTRUI'IENT MAINTENANCE SUI MARY I FOR THE HONTII OF September 19 80 DATE SYSTEH Unit 1 COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 9-2 Containment Inerting H A-76-37 2 Replace None Faulty Heter Alarm would not reset None 9-24 Unit 2 P rimary Containment Reactor Building Closed Cool-ing Hater PDT-64-138 TI-70-56 Calibrate Replace None None Zero'Shif t Did Not Indicate with Redundant Broken Indicator Did Not Indicate None None 9-23 lligh Press-ure Fire Protection PS-26-78J Calibrate None Instrument Drif t Setpoint Incorrect None Unie 3 9-25 Emergency Equipment Cooling Mater RllR Service Hater FI-67-9A-12A PT-23-11 FH-23-42 FH-23-48 Calibrate Calibrate Calibrate Calibrate None None None None Zero Shif t Zero Shift Zero Shift Zero Shift Indicated Low Flow Indicated Low Pressur Indicated Low Flow Indicated Low Flow None None None None 88 Radioactive Li uid Effluents September 1980 1.Gross Radioactivit a)Total Release (1)b)Average Diluted Concentration Released c)Maximum Concentration Released d)Percent of Applicable Limit (20 Ci/quarter)

Units Curies uCi/ml uCi/ml 1.36E+00 3.16E-08 1.91E-07 6.80E+00 2.Tritium a)Total Release b)Average Diluted Concentration Released c)Percent of Applicable Limit (3E-03 uCi/ml)3.Dissolved Noble Gases (2)Curies uCi/ml 1.93E+00 4.49E-08 1.50E-03 a)Total Release b)Average c)Percent of Applicable Limit (6E-06 uCi/ml)Curies uCi/ml<3.07E-02<7.12E-10<1.19E-02 4.Gross Al ha Radioactivit a)Total Release b)Average Diluted Concentration Released 5.Volume of Li uid Waste to Dischar e Canal 6.Volume of Dilution Water 7.Isoto es Released Curies uCi/ml Liters Liters Ci 3.96E-05 9.19E-13 2.87E+06 4.33E+10 Ba/La-140 Co-58<5.15E-04<1.85E-03 (1)Based on pre-release analyses which are not decay corrected (2)includes Xe-133, Xe-135, and others (3)Released on basis of MPC 89 Radioactive Li uid Effluents (Continued)

September 1980 Isoto es Released (Continued)

Units Co-60 Cr-51 Cs-134 Cs-137 Fe-59 I-131 Mn-54 Mo-Tc-99m Na-24 Nb-95 Sr-89 Sr-90 Zn-65 Zr-95<1.31E-02<1.56E-02<2.64E-02<3,20E-02<8.01E-04<6.94E-03<2.58E-03<8.39E-04 2.71E-02<1.17E-03 2.98E-03 4.07E-04<1.51E-02<1.25E-03 Others F-18 Cs-136 Cu-64 I-133 7.94E-04<9.02E-04<9.62E-03<2.04E-03 90 Radioactive Liquid Effluents (Continued)

Others (Continued)

September 1980 Uni ts Mn-56 Sb-122 Sb-124 Xe-133 Xe-135 I-135 Br-82 As-76 Ag-110m Sb-125 As-74 Ci<1.47E-04<3.53E-03<7.03E-04<1.51E-02<1.17E-02<6.82E-03<1.07E-03<3.78E-03<2.02E-03<7.39E-04<7.39E-04 NOTE: Symbol<indicates sums of nuclide activity influenced by values representing threshold limit of analytical sensitivity.

Thus, re-ported values are conservatively higher than actual release.

91 Airborne Releases (1)Summation of All Releases September 1980 Unit This Month A.Fission and Activation Gases 1.Total Release 2.Average release rate for period 3.Percent of Technical Specification limit Ci uCi/sec.<1.43E+04<4.73E+03 9.46E+00 B.Iodines 1.Total Iodine-131 2.Average release rate for period 3.Percent of Technical Specification limit Ci uCi/sec.7.50E-03 2.48E-03 6.21E-01 C.Par ticulates 1.Particulates with half-lives

-8 days 2.Average release rate for period 3.Percent of Technical Specification limit 4.Gross Alpha radioactivity uCi/sec.Ci<3.29E-03<1.09E-03 2.7E-01<1.43E-09 D.Tritium 1.Total release 2.Average release rate for period 3.Percent of Technical Specification limit 4.Ground Level Release 5.Elevated Release Ci uCi/sec.Ci 7.07E+00 2.34E+00 1.87E+00 6.74E+00 3.31E-01 (1)Reporting period-35 days 92 Elevated Releases Airborne Releases (Continued)

September 1980 A.Fission Gases 1.Krypton-85 2.Krypton-85m 3.Krypton-87 4.Krypton-88 5.Xenon-133 6.Xenon-135 7.Xenon-135m 8.Xenon-138 Unit Ci Ci Ci Ci This Ifonth 7.73E+00 2.05E+03<8.19E+02<3.18E+03 6.28E+03<1.88E+02<8.17E+01<4.60E+02 Others (specify)9.Argon-41 Unidentified Total for Period Ci Ci Ci<3.13E001 NA<1.31E+04 B.Iodines l.Iodine-131 2.Iodine-133 3.Iodine-135 Total for Period Ci 5.18E-03<4.45E-03<3.99E-03<1.36E-02 93 Airborne Releases (Continued)

September 1980 Elevated Releases C.Particulates l.Strontium-89 2.Strontium-90 3.Cesium-134 4.Cesium-137 5.Barium-140 6.Zirconium-95 7.Niobium-95 8.Cobalt-58 9.Ifanganese-54 10.Zinc-65 11.Tron-59 12.Cobalt-60 Other (speci f y)N/A 13.Lanthanum-140 D.Tritium Total for Period Unit Ci Ci Ci Ci Ci Ci Ci This Month 4.61E-06 3.82E-07<1.03E-05<1.01E-05<6.55E-05<2.19E-05<9.79E-06<1.02E-05<8.85E-06 3.78E-05<2.25E-05 1.73E-05<6.70E-05<2.86E-04 3.31E-01 94 Airborne Releases (Continued)

September 1980 Ground Level Releases A.Fission Gases Unit This Month 1.Krypton-85 2.Krypton-85m 3.Krypton-87 4.Krypton-88 5.Xenon-133 6.Xenon-135 7.Xenon-135m 8.Xenon-138 Others (specify)9.Argon-41 Unidentified Ci Ci<3.69E-03<2.78E+01<6.80E+Ol<9.11E+01<1.22E+02<1.85E+02<1.86E+02<4.89E+02<4.14E+01 Total for Period<1.21E+03 B.Iodines l.Iodine-131 2.Iodine-133 3.Iodine-135 Total for Period Ci Ci 2.32E-03<1.79E-03<9.94E-03<1.41E-02 95 Airborne Releases (Continued)

September 1980 Ground Level Releases C.Particulates Unit This Month 1.Strontium-89 2.S trontium-90 3.Cesium-134 4.Cesium-137 5.Barium-140 6.Zirconium-95 7.Niobium-95 8.Cobalt-58 9.Manganese-54 10.Zinc-65 11.Iron-59 12.Cobalt-60 Others (specify)N/A 13.Lanthanum-140 D.Tritium Total for Period Ci Ci Ci Ci 1.93E-06 1.79E-06<1.35E-04 1.30E-04<4.87E-04<2.69E-04<1.21E-04<1.18E-04<1.20E-04<4.98E-04 2.88E-04 4.32E-04<3.94E-04<3.00E-03 6.74E+00 96 Solid Radioactive Waste (1)September 1980 Low Level Shi, ments Approximate Volume of Sludge Shipped 42.1 Cu.M.(1486 Cu.Ft.)Total Curies Shipped Principal isotopes 9/08/80 9/10/80 9/12/80 9/16/80 9/18/80 9/21/80 9/23/80 9/30/80 195.2 MAP, MCP (Dewatered Resins)Dis osal Facilit Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Hi h Level Shi ments Approximate Volume of Sludge Shipped 17.7 Cu.M.(624 Cu.Ft.)Total Curies Shipped Principal isotopes 282.6 MAP, MCP (Dewatered Resins)Dis osal Facilit 9/09/80 9/15/80 9/19/80 9/24/80 Barnwell, SC Barnwell, SC Barnwell, SC Barnwell, SC Footnotes on next page.

97 Solid Radioactive Waste (Continued)

September 1980 Slud e Inventor Condensate and Waste Phase Separator Sludge on Hand Cleanup Phase Separator Sludge on Hand 34.0 CU.M.(1199 CU.Ft.)5.7 Cu.M.(200 Cu.Ft.)Drummed Shi ments (2)Total Number of Drums Total Curies Shipped Principal Isotopes Date Shi ed 233 18.2 CR5 1~CS 1 37~ZN65 j C060~MN54~SR90 Dis osal Facilit 9/17/80 9/19/80 Barnwell, SC Barnwell, SC 98 Solid Radioactive Waste (Continued)

September 1980 Boxed Shi ments (2)Total Number of Boxes Total Curies Shipped Principal Isotopes 9/11/80 9/17/80 22 0.1 CR51,CS137,ZN65,C060,i$

54,SR90 Dis osal Facilit Barnwell, SC Barnwell, SC (1)All shipments by Sole-use truck.(2)Combination box/drum shipments on these dates.

99 Solid Radioactive Waste (Continued)

September 1980~scmaac Drums Boxes Resin Shipped to Barnwell 1747.5 ft 2292 ft 2110 6149.5 ft Stored Onsite 1650 ft 3100 ft 4750 ft Allotted~sac e 6149.5 ft 6149.5 ft 100 Effluent and Waste Dis osal Monthl Re ort September 1980 Su lemental Information 1.Batch Releases-Li uid Units a)Number of batch release b)Total time period for batch releases c)Maximum time period for a batch release d)Average time period for batch release e)Minimum time period for a batch release Each 32 Minutes 10883 Minutes 783 Minutes 340.1 Minutes 180 2.Batch Releases-Gaseous None 3.Abnormal Releases-Liquid None 4.Abnormal Releases-Gaseous None 101 Resin Usage for September 1980 Resin-Cu.Ft.Powdered Volume Bead Resins Radwaste Floor Drain Filter Waste Demineralizer Waste Filter (1)Fuel Pool Demineralizers 516.0 192.0 16.0 130.0 516.0 192.0 16.0 Reactor Water Cleanu Unit 1 Unit 2 Unit 3 120.0 56.0 12.0 120.0 56.0 12.0 Condensate Demineralizers U it 1 Unit 2 Uni 827.0 198.0 376.0 827.0 198.0 376.0 Totals 2313.0 130.0 2313.0 (1)Total Resin Volume includes 16.0 cu.ft.of Overlay Haterial.(2)Total Resin Volume includes 63.0 cu.ft.of Overlay Haterial.(3)Total Resin Volume includes 20.0 cu.ft.of Overlay Haterial.(4)Total Resin Volume includes 17.0 cu.ft.of Overlay Haterial.

102-Powdered Resins%Total Usa e September 1980 Radwaste Usa e Total Floor Drain Filter Waste Filter Reactor Water Cleanu 516.0/2313.0 22.3 192.0/2313.0 8.3 Unit 1 Unit 2 Unit 3 120.0/2313.0 56.0/2313.0 12.0/2313.0 5.2 2.4 0.5 Condensate Demineralizers U it 1 U.it 2"'.it 3 (4)827.0/2313.0 35.8 198.0/2313.0 8.6 376.0/2313.0 16.3 Fuel Pool Demineralizers (1)ALL UNITS 16.0/2313.0 0.7 (1)Total Resin Volume includes 16.0 cu.ft.of Overlay Material.(2)Total Resin Volume includes 63.0 cu.-.ft.of Overlay Material.(3)Total Resin Volume includes 20.0 cu.ft.of Overlay Material.(4)Total Resin Volume includes 17.0 cu.ft.of Overlay Material.

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...VE55CL litt GTItttD-BY It!Tll IILD PRC(URT 0-LM R.OW 106 Fuel Claddin Inte rit Parameters Unit 1 September 1980 Reactor Water Iodines (uCi/sec.)

Date I-131 I-132 I-133 I-134 I-135 9-04-80 9-22-80 2.97E+00 1.68E+01 l.92E+01 3.15E+02 6.86E+00 1.08E+02 3.77E+02 1.82E+02 3.71E+Ol 1.24E+01 Fission Gases at Dischar e of SJAE (uCi/sec.)

Date 9-02-80 Xe-138 1.33E+03 Kr-87 Kr-88 Kr-85m 4.43E+02 2.87E+02 1.47E+02 Xe-135 1.21E+03 Xe-133 3.10E+03 Off-gas flow rate 13 scfm 0>Ãt 9-23-80 4.72K+04 1.76E+04 8.87E+03 6.44E+03 2.62E+04 1.45E+04 Off-gas flow rate 50 scfm 3265 11Wt Unit 2 Reactor Water Iodines uCi/sec.)Date 9-04-80 9-22-80 I-131 I-132 I-133 3.36E+00 1.74E+01 6.40E+00 (Unit Outage)I-134 2.25E+01 I-135 1.04E+01 Fission Gases at Dischar e of SJAE uCi/sec.)Date 9-02-80 Xe-138 Kr-87 9.52E+03 1.42E+03 Kr-88 Kr-85m 8.16E+02 6.06E+02 Xe-135 Xe-133 2.08E+03 6.97E+02 Off-gas flow rate 120 scfm 2985 Mit 9-23-80 (Unit Outage)Off-gas flow rate 0 scfm 0 M<t 107 Fuel Claddin Inte rit parameters (Continued)

September 1980 Unit 3 Reactor Water Iodines (uCi/sec.)

Date 9-04-80 9-22-80 I-131 3.28E+01 6.67E+00 I-132 2.26E+02 l.22E+01 I-133 5.49E+01 7.04E+00 I-134 1.79E+02 2.94E+Ol I-135 9.23E+01 9.64E+00 Fission Gases at Dischar e of SJAE (uCi/sec.)

Date Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 9-02-80 3.27E+03 3.29E+02 1.62E+02<4.86E+00.

4.62E+02 3.03E+02 Off-gas flow rate 42 scfm 2497 HWt 9-23-80 5.48E+03 6.83E+02 3.48E+02 2.09E+02 8.04E+02 2.24E+02 Off-gas flow rate 80 scfm 3018 MWt j w r WASTE TREATMENT SYSTEM VOLUME THROUGHPUTS (1).1980 Year (2)September Month 9.47E+04 d[2.84E+06]FLOOR DRAIN COLLECTOR TANK FLOOR DRAIN FILTER 3 756 FLOOR DRAIN'RPLE TANK 1.40E+04 gpd[4.19E+05]TO CANAL--2.53E+04 d gpd[7.58E+05][2.42E+06][2.84E+06]LAUNDRY DRAIN TANK 7~27 E+0[2.18E+05]~pd[0'2.00E+06 EVAPORATOR DISTILLATE TANK 0'pd 0 gpf WASTE COLLECTOR TANK WASTE FILTER (4)308[6.42E+06]WASTE DEMINERALIZE 130 ft (9-17-80)WASTE SAMPLE TANK 4,03E+03 gpd[1.21K+05]~2.14K+05 pd 2.10E+05 gpd[6.42E+06][6.30K+06][0]CONDENSATE STORAGE TANK (1))Represents 30 days 3 Values accurate to two (2)(p)240 Ft3 of powdered resins 116 Ft of powdered resins gpd evetage gallons pet day signifjcant figures[]total gallons 516 Ft of mixed resin/filter media 192'Ft of mixed resin/filter media 3

'P 109 WATER TREADKNT CHEMICAL USE Browns Ferr Nuclear Plant Month September Year 198,0 CHEMICALS REQUIRED DESCRIPTION AMOUNT Grade, concentration

%, Pounds, Gallons, Cuft, etc.Anh drous etc.This Month/Year To Date BOILER WATER MAKEUP TREATifENT Aluminum Sulfate Anthracite (filter media)Coagulant aid, Polyelectrolyte (Wisprofloc 20)Sodium hydroxide Sulfuric acid, demineralizer Coagulant-liquid polymer (Magnifloc 575-C)2700 lbs 8700 lbs 11.9 tons 65.8 tons 8.2 tons 65.9 tons 1000 lbs BOILER WATER SECONDARY TREATMENT Ammonium hydroxide Hydrazine, hydrate Powdex, PAO (Wet)Powdex, PCH (Wet)Resins, bead type (stator cooling)Celite, Supergel HSC Epicor PD-1 anion (Dry)Epicor PD-3 cation (Dry)Epicor AC-31 Mixed Bed (Gravex-Mixed Bed)1 gal 1 gal 20,790 lbs 51,650 lbs 19 Cu Ft 1,200 lbs 192 Cu Ft 216 CU Ft 196 Cu Ft 13 gal 12 gal 111,870 lbs 272,650 lbs 28 CU Ft 19,900 lbs 4,056 Cu Ft 5,496 Cu Ft 2,112 Cu Ft Epifloc-Waste Filter Graver Ecocote-condensate Graver Ecodex-Fuel Pool&Waste Filter 1,044 Cu Ft 1,088 Cu Ft 3,788 Cu Ft MISCELLANEOUS WATER TREATMENT (Includes sample and bearing cooling water systems, ash pond treatment, and other water systems, i.e., radwaste systems and fuel pool cleanup systems at nuclear plants requiring treatment.)

Sodium Nitrite (RBCCW and and Off Gas chiller)450 lbs SEWAGE TREATMENT Sodium Hypochlorite Soda Ash 620 gal 1,575 gal 5,500 lbs Se tember Nonth 1980 Year Total Pla>>nt Training Summary 0 4J (>>>>>>0 pl 0 cI (>>(>>(>>>>>>0 (t>(>>U 0 0 Cg 0~~'u (4 X C4 6 I>SecLion OI>eraLor Traini>>g II.P.Ra(Iiological)Iygiene Trai>>ing (8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)II.P.Retraining (3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />)Chemical Laboratory

'ualification Training Fire Training N.E.Training I.H.Training U (>>4J 0 I>>>W'0 0 Cl I>>>>>0 U t>>(J>4J (>>(>(lI (>>Cl llea 1 th~Vh sic>>I:.lee t ri ca 1 II;I i>>tenance.Plcch;>ni c;>1 ll>>l I.l>LC>>>>l>>ce 14 10 OI>el>>>Liolls II>>:I I I Ly>1ssllr>>lllc('0 22 IIes>>l ts h(lm>>s Lr tv I>>>>Lr C(>>>t r(>I.s I'ub I ic.S>>JII cL'y I o(J('."L(>rc'.:

I'>>>(J('>>>>y'I-I ('I>>l I>I>>('10....2.>>24 33 I>l.h>>I'00 131 Total 69 245 7 47 24

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