Text

Monthly Operating Repts for Feb 1988
	ML20148E735
Person / Time
Site:	Browns Ferry
Issue date:	02/29/1988
From:	Crawford J, Jacqwan Walker; TENNESSEE VALLEY AUTHORITY
To:	;
References
	NUDOCS 8803250302
	Download: ML20148E735 (80)
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MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY FEBRUARY 1988 "Safety and Quality are Paramount" DDCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS OPR-33, DPR-52, AND DPR-68 Su itted by h

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AD Plant Manager DCD

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TABLE OF CONTENTS PART I OPERATIONAL SUMHARY A.

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

1 B.

Fuel Performance and Spent Fuel Storage Capabilities Summary..... 2 C.

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

5 D.

I s suanc e o f S p e c i al Repo r t s S umma ry.............................. 6 E.

Licensee Events Summary..........................................

7 F.

Offsite Dose Calculation Manual Changes.........................

12 G.

R a dw a s t e S umm a ry................................................ 13 1.

Total volume of solid waste shipped off site 2.

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

3.

Gross curie activity 4.

Dates the material was shipped and the disposal facility j

to which the material was shipped.

5.

Estimated quantities of spent resin in storage.

6.

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

7.

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

PART II OPERATING STATISTICS 7

A.

NRC Reports 1.

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

17 2.

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

20 3.

Unit Shutdowns and Power Reductions.........................

23 i

B.

TVA Reports i

1.

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

26 2.

Unit Outage and Availability Data...........................

27 3.

Reactor Histogram (Reactor Power Percent)................... 30 i

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TABLE OF CONTENTS (Continued)

Part III MAINTENANCE SUPHARY A.

Electrical Maintenance........................................... 31 B.

Instrument Maintenance........................................... 34 C.

Mechanical Maintenance........................................... 36 D.

Mod 1ficatt.ons.................................................... 39 PART IV TVA GADS EVENTS REP 0RT............................................

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PART V OTHER REPORTS A.

Chemistry Sumunary 1.

P r ima ry C o o l an t Ch emi s t ry.................................. 4 6 2.

Environmental Technical Specification Requirements.......... 49 3.

Airborne Releases........................................... 50 4.

Liquid Releases............................................. 55 5.

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

59 6.

Fuel Cladding Int egrity Parmet ers............................ 60 7.

Wast e Treatment Syst em Throughputs.......................... 61 1

B.

Testing Summary.................................................. 62 C.

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

64 D.

Change in Procedures............................................. 65 E.

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

65 F.

Change in Facility Design (ECNs)................................. 66 G.

Change in Plant Organization..................................... 69 H.

Accidents........................................................ 70 Addenda - Revision to January 1988 Report

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OPERATIOXAL SEMMARY f

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-Page 1 4'

SIGNIFICANT OPERATIONAL EVENTS SUff!ARY.

FEBRUARY 1988 Unit I r

-t 02/01/88 0001 Unit remains on administrative hold to resolve various i

TVA and NRC concerns, and end of cycle-6 refueling and modifications continues.

02/29/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.

Unit 2 02/01/88 0001 Unit remains on administrative hold to resolve various l

TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

i 02/29/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

Unit 3 02/01/88

.0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.

02/29/88 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.

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e Pcgo 2 FUEL PERFORMANCE AND SPENT WEL STORAGE CAPABILITIES

SUMMARY

FEBRUARY 1988 Unit 1 Unit I was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit alt;o began its sixth refueling on June 1,1985, with a

=ch-duled restart date to be determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10CTR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modificationa, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J), HPCI concerns, modification of PCIS logic (LER 259 85009),

replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), RPS modifications (IE Notice 78-45), H 0 8 ample line modification (LER 81050), radiation 22 monitors modification (LER 80033), EECW carbon to stainless pipe change out, r

and all NRC commitment items except Anticipated Transients Withcut Scram (ATWS) modifications which is scheduled for next outage.

i There are 0 assemblies in the reactor vessel. The spent fuel storage pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 ascemblies. The present available i

I capacity of the fuel pool is 1355 locations.

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Paga 3 WEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES SUM 4ARY (CONT.)

TEBRUARY 1988 Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 80-17), environmental qualification of electrical equipment (10CFR50.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial),

MSIV modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J)

(partial), D/G speed sensor installation (LER 81004), HPCI and RCIC testable check valve change out, modificatior. of PCIS logic (LER 259 85009), HPCI concerns, seismic program review, and EECW carbon to stainless pipe change out.

There are 0 assemblies in the reactor vessel. At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 EOC-3, 156 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 1481 locations. All HDRs have been installed in the pool with the exception of two.

c Pcge 4 FUEL PERFORMANCE AND SPENP IVEL STORAGE CAPABILITIES

SUMMARY

(CONT.)

FEBRUARY 1988 Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and ERC concerns with a scheduled restart date to be determined. The sixth re fueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications. The prior-to-stArtup unit 3 items are environmental qualifica-tion of electrical equipment (IDCFR50.49), containment modifications (NUREG 0737), electrica2 changea (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of taasonry Valls (IES 80-11), evaluation of the vent drain and test connections, ODTC,(LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), addition of redundant drywell control alt supply, RPS modification (IE Notice 78-45),

H0 sample line m dificatten (LIR 81050), radiation monitor modification 22 (LER 80033), replacement or jet pump holddovn beam assemblies (IEB 80-07),

change out of switches an SBQT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.

There are 0 assemblies dn the reactor vessel. There are 764 assemblies to finish EOC-6, 248 E00-5, 280 E00 4, 124 E0C-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent ftel storage pool.

The present available capacity of the fuel pool is 585 loca tions. All high density racks (HDR) have been installed in the pool v4th the exception of six.

Page 5 MSRVs (MAIN STEAM RELIEF VALVE)

SUMMARY

FEBRUARY 1988 No MSRVs were challenged during the month.

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Pago 6 I

ISSUANCE OF SPECIAL REPORTS The following special report was submitted to the NRC in February 1988.

87-46-03 During a Nuclear Regulatory Commission (NRC) inspection conducted on December 1-31, 1987, a violation of NRC requirements was identified. The violation involved failure to properly test the Standby Gas Treatment System following the fire in the Unit 2 drywell on November 2, 1987.

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LICENSEE EVENT REPORT (S)

Page 7 FEBRUARY 1988 The following licensee event reports (LERs) were reported to the Nuclear Regulatory Commission in February 1988.

Description of Event LIE 1-85-026 Cable Trav Loadina Rev. 3 On July 1, 1985, field inspections and subsequent structural evaluations determined various cable tray sections and their supports not seismically qualified in accordance with the plant's original design criteria.

In addition, a number of cable tray sections were determined to have excessive fire retardant ec2 ting applied, raising a concern on cable ampacity. The essential cable trays and their supports in unit 2 and in other areas essential to operation of unit 2, were subjected to an evaluation by United Engineers and Constructors (UE&C). This evaluation specified modifications to ensure structural integrity of the cable tray supports. These modifications will be completed prior to unit 2 startup.

A design standard has been written to derate cable based upon excessive depth.

Cables determined to be unsatisfactory will be replaced.

1-88-001 Unolanned Reactor Water Cleanuo Isolation due to Loose Connection On January 17, 1988, at 0810 hours0.00938 days 0.225 hours 0.00134 weeks 3.08205e-4 months , with the unit defueled, the temperature switch monitoring the discharge of the unit 1 reactor water cleanup (RWCU) nonregenerative heat exchanger initiated a spurious isolation of the RWCU system through the primary containment isolation system. This was an unplanned actuation of an engineered safety feature.

l An investigation was initiated to determine the cause of the isolation. The water temperature was verified to be well below the isolation setpoint.

During troubleshooting the relay controlled by the temperature switch reset to the normal position allowing the operator to reset the isolation logic. A loose solder connection that initiated the isolation was found in the temperature switch.

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,e Page 8 Descriotion of Event (Continued)

LEE The connection was repaired and the switch recalibrated. The system was returned to service the following day at 0945 hours0.0109 days 0.263 hours 0.00156 weeks 3.595725e-4 months . A brush recorder was temporarily connected to monitor switch behavior. No abnormalities were observed during the thirty hours the recorder was attached. No further actions are planned.

1-88-002 Engineered Safety Feature Actuation due to Personnel Error Durina Switch Calibration.

On January 6, 1988, at 1954 hours0.0226 days 0.543 hours 0.00323 weeks 7.43497e-4 months , with all three units defueled, four emergency equipment cooling water (EECW) pumps are inadvertently started due to a personnel error associated with the calibration of a raw cooling water (RCW) pressure switch. Low RCW pressure is a designed start signal for the EECW pumps. While returning a wire to its normal position it was allowed to momentarily contact an adjacent terminal position. This simulated a low RCW pressure and thereby completed the start logic for the EECW pumps. This was an unplanned actuation of an engineered safety feature.

The craft personnel performing the calibration returned the circuit to the normal configuration in accordance with the procedure. Operations personnel surveyed the panel for blown fuses or damage and found none.

Four EECW pumps were returr.ed to standby readiness by 2100 hours0.0243 days 0.583 hours 0.00347 weeks 7.9905e-4 months . The craft personnel involved were cautioned to exercise extreme care when working with energized circuits.

All instrument maintenance personnel will be provided with a description of the event.

1-88-003 Inadeauate Procedure Causes Inadvertent Start of Emergency Eauloment Coolina Water Pumoc.

On January 12, 1988, at 0043 hours4.976852e-4 days 0.0119 hours 7.109788e-5 weeks 1.63615e-5 months , with all three units defueled, four emergency equipment cooing water (EECW) pumps were inadvertently started due to a procedure deficiency. While attempting to put a raw cooling water (RCW) pump into service and take another pump out of service, the RCW header

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pressure dropped below the low pressure setpoint.

i This is a designed start signal for the EECW pumps. This was an unplanned actuation of an engineered safety feature, l

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Page 9 Descriotion of Event (Continued) 14E The assistant unit operator and the assistant shift engineer restarted the required RCW pumps and returned four EECW pumps to standby readiness.

The operating instructions for the RCW system will be revised to provide instructions for alternating pump's in and out of service.~ A review of this event will be provided to current operations personnel.

1-88-005 Diesel Generator and Emergency Eauioment Cooling Water Pumo Actuations Due to Personnel Error.

On January 22, 1988, at 1019 hours0.0118 days 0.283 hours 0.00168 weeks 3.877295e-4 months , a potential transformer fuse compartment was opened for inspection. This action resulted in the deenargization of a 4Ky shutdown board and the stare of a diesel generator (DG) and an emergency equipment cooling water (EECW) pump. Units, 1, 2, and 3 were defueled when this event occurred.

Operations restored normal power to the shutdown board and returned the DG and EECW pump to standby readiness by 1045 hours0.0121 days 0.29 hours 0.00173 weeks 3.976225e-4 months . These engineered safety feature actuations were a result of personnel error caused by a failure to observe posted warnings, inadequate communication, and inexperience. The personnel involved have been counseled on the event. Additionally the walkdown coordinator has reviewed the event with engineering and contract personnel to address the extent to which they can direct craft effort during a walkdown. A description of this event will be provided to maintenance, modifications, operations, and engineering groups. The walkdown procedure will be upgraded to include a planning review by a person with integrated plant knowledge when physical werk is required.

+-

V Page 10 Descriotion of Event (Continued)

LEE l-88-007 Residual Heat Removal Service Water Pumo Flow Not Demonstrated In Accordance With Technical SDecifications Due to Calibration Prior.

On January 27, 1988, at 1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months , with all units defueled, a calibration error was discovered in the four residual heat removal service water (RHRSW) pump flow instruments. An indicated flow of 4500 gpm corresponds to an actual flow of approximately 3400 gpm. It was caused by an error on the flow transmitter data sheet and failure to verify the NSSS supplied data sheet against the vendor flow orifice calculations for the flow element. All RHRSW pumps will be demonstrated operable with correctly calibrated flow instruments prior to returning to service. Vendor flow calculation data sheets will be obtained and will be verified for all flow loops with General Electric supplied data sheets.

1-88-008 Standbv Cas Treatment Relative Humidity Heaters Have Not Been Tested in Accordance with rechnical Soecifications Due to Inadeauste Procedures.

On January 20, 1988, during a programmatic upgrade of the Browns Ferry surveillance instructions it was discovered that the surveillance instruction which tests the standby gas treatment (SBGT) relative humidity heaters did not fully implement the testing described in the American National Standards Institute (ANSI) standard N510-1975 as required by technical specification (TS) 4.7.B.1.b.

All three trains of SBGT were declared inoperable.

ANSI N510-1975 had been incorporated into TSs by August 20, 1976. Since that time the reactors have been operated at power and fuel handling operations have been carried out.

Failure to implement a change to the TSs by revising the applicable surveillance instruction allowed operation outside of the TSs.

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Page 11 Description of Event (Continued)

LIE At the time of discovery all three units were defueled. All three SBGT trains had been previously declared inoperable for other reasone.

All fuel handling and operations over the spent fuel pools had been halted.

The surveillance instruction has been revised to fully incorporate the testing described in ANSI H510-1975. The revised surveillance instruction is currently being run on all three trains of SBGT.

Any deficiencies identified under the new surveillance instruction will be addressed or corrected prior to declaring the individual trains operable.

1-88-501 Safeauards Event On January 7, 1988, at 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months , with all units defueled, a Nuclear Security Services (NSS) supervisor, while conducting routine supervisory checks, discovered a NSS officer inatter.tive to his

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duties while assigned to a compensatory post. The compensatory post had been established earlier that day for the failure of an alarm zone of the perimeter intrusion detection system, due to adverse weather. The NSS supervisor immediately relieved the NSS officer of his duties, reestablished the compensatory post, and conducted of followup search of the area with the assistance of other NSS personnel. The Shift Engineer was notified of the event, and one-hour telephone call was made to NRC pursuant to the requirements of 10 l

CFR 73.71, Appendix G, I.c.

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OFFSITE DOSE CALCULATION MANUAL CHANGES FEBRUARY 1988 No changes were made to the Browns Ferry offsite dose calculation manual during the month.

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Page 13 RADWATE

SUMMARY

FEBRUARY 1988 Common The radwaste system performed as designed. Approximately 7.43E+05 gallons of waste liquid were discharged containing approximately 1.16E-02' curies of activity.

There were four spent resin shipments and one trash shipment during February. All shipments were to Barnwell, SC.

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Pcgo 14 Solid Radioactive Naste February 1988 Dewatered Spent Resin Snipments ( 1)

Volume of condensate / Waste resin shipped: 16.31 Cu.M. ( 576 Ca. F t.)

Total curies shipped: 17.8504

'>o l ume of reactor cleanup resin shipped:

N or. e Total curies sh:pped: N/A Date Shipped Disposal Facility Type of Resin 02/ 02/ 88 Barnwell, SC CNPS 02/ 12/'88 Barnwel1, SC CWPS 02/ 19/ 88 BarnwelI, SC CNPS 02/ 26/ 88 Barnwe11, SC CWPE C r y Ac tive Waste ( 1)

N o.T b e r of drums shipped:

None Volume:

N/A Total curies shipped:

N/A Number of toxes shipped:

10 Volume:

26.59 Cu.M (939.1 Cu.Ft.)

Total curies shipped: 0.3803 Date Shipped Disposal Facility Type of Package 02/ 18/ 88 Barnwel1, SC Boxes

( 1) All Shipments were by Sole-Use Truck t

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Pago 15 Solid Radioactive Haate ( Ccn t i nu ed)

February !?88 Summary Type Shipped to Packaged on Gross Curie Estimated of Barnwell Site Awaiting Content by Generation f or Naste During Month Shipment Type of Naste Next Month Compacted Drums O

Cu. F t. ( 2) 165 Cu.Ft.

0.00E+00 240 Co. F t. ( 2)

Boxes 837 Cu.F t. ( 2) 465 Cu.Ft.

3.75E-01 700 Cu. F t. ( 2)

Uncompacted Drums O

Co. F t. ( 2)

O Co.Ft.

0.00E+00 0

Cu. F t. ( 2)

Boxes 10 2 Cu. F t. ( 2) 502 Cu.Ft.

5.35E-03 450 C o. F t. ( 2)

Res:ns CUPS 720 Cu.Ft.(1) 1694 Cu. F t. ( 3) 1.79E+01 400 Cu.F t. ( l' PNCU 0

Cu.Ft.(1) 500 Co. F t. ( 3) 0.00E+00 30 Cu.Ft.

TCTAL5 1793 Cu.Ft.(2) 1132 Ca. F t. ( 4) 1.82E+0i 1300 cc.F t. ( 4)

Total volume ot' waste shipped during the month:

' 1793 Co. F t. ( 2)

Total /clume of waste shipped year to date:

3064 Cu Ft.

Unused 1098 burial volume al l oca t i on at Barnwell:

7S465 Cu.Ft.

( 1)

Ac tual r e sin vo' ume.

( 2)

Con t :< i n e-tur;al vo'ume.

3)

Ea t zmatec vol ume in separatcrs

( 4)

Does not include r+ sins

LIGUID RADWASTE MONTHLY OPERATING REPORT FEBRUARY 1988 FLOW RATE (GPM)

DATA PLOTTE R HE PRE 12 MONTHS TOTAL RELEASE (CI) 40.

2 RATEfapu)

HI 23.82 30 -

LOW 11.52 AVG 18.42 20.

1 TOTAL g

3 RELEASEfCT)

HI 0.05 LOW 0.01 10 -

AVG 0.03

() FLOWRATE kAR APR MAY N

L AUG OCT NOV DEC JAN kB

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EUGHAUT ff2Af 431 FILTER THROUGHPUTS l

8 GALLONS X 10 HI 0.25E+07 5

LOW 0.86E+06 AVG 0.15E+07 4.

FLOOR DRAIN HI 0.12E+07 N

LOW 0.49E+06 3.

Ill AVG 0.83E+06 LAUNORY HI 0.11E+05 2

g g LOW 0.00E+00 4

AVG 0.69E+04 g

0 MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB COST OF OPERATION o,ERirToN coottiRs3 THOUSANDS OF DOLLARS WASTE 134 HI 0.88E+05 120.

LOW 0.19E+05 110.

AVG 0.39E+05 FLOOR DRAIN 90 HI 0.57E+05 E

70.

LOW 0.21E+05

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60.

LAUNORY 50.

HI 0.18E+03 40.

LOW 0.00E+00 30.

AVG 0.43E+02 20.

10.

MAR APR MAY JUN JUL AUG SEP OCT NOV DEC JAN FEB F/A

.A.1E c0LLec10R Sv8Te, E LAUNORv ov5TE, FLOOR DRAIN SYSTEM STARTING 3-87 COSTS INCLUDE RESIN DISPOSAL l

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e' OPERATING STATISTICS l

Page 17 OPERATING DATA REPORT DOCKET NO. 50-259 DATE 03-01-88 CO WlETED BY J. D. Crawford TELEPHONE (205) 729-7507 OPERATING STATUS l Notes l

1.

Unit Nee:

Browns Ferry linit One l

l 2.

Reporting Period: February 1988 l

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Licensed Themal Power (Wt): 3293 4.

Nameplato Rating (Gross W e): 1852 5.

Design Electrical Rating (Net We) 1065 l

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Maximum Dependable Capacity (Gross We)_1098.4 l

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Maximum Dependable Capacity (Net N e) 1065 l

l 8.

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

N/A 9.

Power Level To Which Restricted, if Any (Net We):

N/A

10. Reasons For Restrictions, if Any:

N/A This Nnth Yr-to-Date Cumulative i1. Hours in Reporting Perlod 6%

I440 l19.I20

12. Number of Hours Reactor Was Critical 0

0 59.521.38

13. Reactor Reserve Shutdown Hours 0

0 6,997.44

14. Hours Generator On-l.ine 0

0 58.267.26

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (WH) 0 0

168,066.787

17. Gross Electrical Enorgy Generated (WH) 0 0

55.396,130

18. Net Electrical Energy Generated (WH)

-2003

-2831 53.703.571

19. Unit Service Fxtor 0

0 48.91

20. Unit Availability Factor 0

0 48.91

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

42.33

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

42.33

23. Unit Forced Outage Rate 100 100 41.%

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

25. If Shut Down At End Of Report Porlod, Estimated Date of Startup To bo delormined

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

Forocast Achloved INITIAL CRITICAllTY INITIAL ELECTRICITY COM.RCI AL OPERAT10N (9/77)

Pago 18 OPERATING DATA REPORT 00CKEI NO.

50-260 DATE 03-01-88 CO WLETED BY J. D. Crawford iELEPHONE (205) 729-2507 OPERATING STATUS l Notes l

1.

Unit Names Browns Ferry Unit Two l

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Reporting Period: February 1988 l

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Licensed Thermal Power (mit): 3293 l

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Nameplate Rating (Gross % ): 1852 l

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Design Electrical Rating (Not %) 1065 6.

Maximum Dependable Capacity (Gross % ) 1098.4 7.

Maximum Dependable Capacity (Not % )

1065 l

l 8.

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

N/A 9.

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

N/A

10. Reasons for Restrictions, if Any:

N/A This Month Yr-to-Date Cumilative

11. Hours in Reporting Period 6%

1440 l14.007

12. Nunter of Hours Reactor Was Critical 0

0 55.860.03

13. Reactor Reserve Shutdown Hours 0

0 14.200.44

14. Hours Generator On-Line 0

0 54.338.36

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 0 0

153.245,f67

17. Gross Electrical Energy Generated (MWH) 0 0

50.771.798

18. Not Electrical Energy Generated (MWH)

-1.973

-3.959 49.179.874

19. Unit Service Factor 0

0 47.66

20. Unit Availability Factor 0

0 47.66

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

40.50

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

40.50

23. Unit Forced Outage Rate 100 100 41.18

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

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

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

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COME RCIAL OPERATION (9/77)

Page 19 OPERATING DATA REPORT DOCKEl NO.

50-2 %

UATE 03-01-88 CO WlETED BY J. O. Crawford TFLEPHONE (205) 729-2507 OPERATING STATUS l Notes l

1.

Unit Names Browns Ferry Unit Three l

l 2.

Reporting Period: February 1988 l

l 3.

Licensed Thermal Po w (* t): 3293 l

l 4.

Nameplate Rating (Gross % ): 1152 l

l 5.

Design Electrical Rating (Net MWe) 1065 6.

Maximum Dependable Capacity (Gross MWe) 1098.4 7.

Maximum Dependable Capacity (Not MWe) 1065 l

l 8.

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

N/A 9.

Power Levol To Which Restricted, If Any (Not HWe):

N/A

10. Reasons For Restrictions, If Any:

N/A This Month Yr-to-Date Cumulative ll. Hours in Reporting Period 6%

1440

%.432

12. Nurrber of Hours Reactor Was Critical 0

0 45.306.08

13. Reactor Reserve Shutdown Hours 0

0 5.149.55

14. Hours Generator On-Line 0

0 44.194.76

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Gonerated (MWH) 0 0

131.868,267,

17. Gross Electrical Energy Generated (MWH) 0 0

43.473.760

18. Not Electrical Enorgy Generated (MWH)

-2.570

-7.228 42.033.920

19. Unit Sorvice Factor 0

0 45.83

20. Unit Availability Factor 0

0 45.83

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

40.93

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

40.93

23. Unit Forced Outage Rate 100 100 44.57

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

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be dotormined a

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

Forecast Achloved INITIAL CRITICALITY INITIAL ELECTRICITY COMERCIAL OPERAT10N (9/77)

Page 20 J

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 Unit One DATE 03-01-88 COMPLETED BY J.D. Crawford TRLEPHONE (205)729-2507 MONTH FEBRUARY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-1 17

-3 2

-1 18

-3 3

-1 19

-4 4

-1 20

-3 5

-1 21

-3 6

-1 22

-3 7

-1 23

-3 8

-4 24

-4 9

-3 25

-3 10

-3 26

-4 11

-3 27

-3 12

-4 28

-3 13

-4 29

-3 14

-4 30 15

-4 31 16

-4 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) l l

[

.Page'21 O

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 Unit Two D#.TE 03-01188 COMPLETED BY-J.D. Crawford TELEPHONE (205)129-2507 MONTH FEBRUARY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVER, (MWe-Net)

(MWe-Net) 1

-2 17

-3 2

-3 18

-3 3

-3 19

-3 4

-3 20

-3 5

-3 21

-3 6

-3 22

-2 7

-3 23

-2 l

8

-4 24

-3 3.

9

-3 25

-3 10

-T 26

-3 11

-3 21

-3 12

-4 28

-3 13

-3 29

-3 14

-3 30 15

-3 31 16

-3 TNSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month.

Computo to the nearest wholo megawatt.

(9/77)

~. -. _ -. _ -

~.

~

Pago 22 AVERAGE DAILY UNIT POWER LEVEL DOCKt,I NO.

50-296 Unit Three DATE 03-01-88 CONPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH FRBRUARY 1988 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (NWe-Net)

(MWe-Net) 1

-6 17

-2 2

-6 18

-2 3

-6 19

-3 4

-6 20

-3 5

-6 21

-2 6

-6 22

-2 7

-7 23

-2 8

-6 24

-3 9

-6 25

-2 10

-6 26

-2 11

-3 27

-2 12

-3 28

-2 13

-3 29

-2 14

-2 30 15

-3 31 16

-3 TNSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

UNII SilUIDOWNS AND POWER R8? DUCT 10NS DOCKET NO.

50-259 UNIT NAME Ono DATE 03-01-88 REPORI MON fil February COMPLETED BY J D Crawferd TELEPHONE

(?OS1 774-7907

~

C

~,,

3 C_

! ICellsce 1

CJtate & Cottes,tive N' '

Date i

3?

{

j{5 Event

,. ?

Sl Action to fE 5

55:

Repora r fio go Ps: vent Recurrence g

o 6

315 02/01/88 F

696 F

4 Administrative hold to resolve various TVA and NRC concerns, i

i 2

3 4

I i orted Reawn.

Method I; xlubit C - Inst a nt tio.is S Ss hed uled A I quipment !~ailuse (Explarn)

! -Man ual for Prep.uation ot' Dara 11 Maintenance or Iest 2 -Manual Scram.

1.ntey Sheets f or Licemce

'O C Ref ueling 3-Automan te Steam.

INent Repost t1.1 R)I ile (N13RI G-D Regulaioey Restriction 4-Other II'splani)

Oteti I ()perator l's.uning & I at ense I sai:iination e

i adnunnreau.c g

s 0 Operational I u..1I splaial u

j

("/77)

Il ()ibesil splain)

I sinbir 1 S.nne Sours,

~ ~

1 UNIT SilUIDOWNS AND POWER REDUC 110NS DOCKET NO.

% 260 UNIT NAME Two

):

DATE 01-01-AA REPORT MONTil February COMPLETED BY J. D. Crawford TELEPHONE (205) 729-2507 4

E E

h I5CC"SCC

.El

}

Eo%

('ause & Currective y"

g#

2 2E 4

_E E e E, vent F?

El Action to 53 5

j d5 g RcPin f "

($ 0 5'

Prevent Recurrence 6

1 i

305 02/01/88 F

696 P

4 Administrative hold to resolve various TVA and NRC concerns.

J 4

qt 1

1 1,

i i

f 1

2 3

4 i

I. F uted Reason:

Method:

Exlubit G Inst:uctioins j

S St heduled A 1quipnient Failnie(Explain) l Manual for Psepanaison of Data 11-Maintenance or Tes 2-Manual Sesam.

1.nte> Sheets for l_icensee C-Refuciang 3 Autoinalic Strain.

I:

.it Repost (I.I:R) File (NtIRI G.

or on D Regulator) Rest iction 4-Orhes (1.xplanil 01611 i.-Operator Tsanung & I; tense I:xamination j

I - Adininist rative 5

N G Operational I iros (lixg.lar.il l'*/77 )

Il Othes (1 splanil I sinhit I S.nne Source i

~

i 1

t

.~

~

UNII~ SilUIDOWN3 AND POWER REDUCTIONS DOCKET NO.

50-296 UNIT NAM E Three DATE m-ni RA RI PORT MONTil February COMPLETED BY J. D. Cravofrd TELEPilONE (205) 729-2507 c

52 3

j Ei 1.icensee j t,

%'8 Cause & Correctsve Dale 5?

4 2sE Event

y 9

Action to jE 3 ;g =

Repor t =

6i U

$b Prevent Recurrence

?

v 6

157 02-01-88 F

696 F

4 Administrative hold to resolve various TVA and NRC concerns.

1 i

?

1 4

I I nced Renon Method :

1:xtubit G -Insieuctions S Ss hed uleit A i quipenent l'ailarc il xplain)

! Manual for Preparation of Data it-Maintenance of Test 2 -Manual Sciarn, I ntr> Sheets f or I.icernce C Returluig 4 Ataleen.itic Ss rain.

I. vent Repos t (1.1.R l I ile ( NilRI G.

mm D Regnlatory Restriction 4 Otlies (l.splain) 01ofn I Operator ltannop & 1 t ense 1.ununation I hinunist sat a.e 5

M G t pretational 1 e ven (l'sple.il C77)

II()lhes Il splanal I sinbit !. Saine Sonrs c

vvn nua tonr%.ou NUCLEAR PLANT OPERATING STATISTICS Browns Ferry Nuclear Plant Period Hours 696 Month Fohrnarv 19 RA Item No.

Unit No.

Unit 1 Unit 2 Unit 3 Plane 1

Averaoe Hourly Gross Load. kW 0

0 0

0 2

Maximum Hour Net Generation. MWh O

O O

O 3

Core Thermal Energy Gen. GWD (t)2 0

0 0

0 4

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

5 Gross Electrical Gen., MWh 0

0 0

0 5

6 Station Use, MWh 2003 1973 2570 6546 l

h 7

Net Electrical Gen., MWh

-2003

-1973

-2570

-6546 1

8 Static 1 Use, Percent O

O O

O 9

Acc;m. Core Avg. Exposure, MWD / Ton!

O O

6 10 CT EG This Month,10 GTU O

O O

O 11 MTt.G This Month,10 6 BTU 12 13 Hours Reactor Was Critical O

O O

O 14 Unit Use, Hours-Mm.

O O

IS Capacity Factor, Percent O

O O

O

}

16 Turbine Avail. Factor, Percent O

O O

O 17

_ Generator Avail. Factor. Percent O

O A

O 4r IS Turboaen. Avail. Factor. Percent O

O O

O 19 Reactor Avail.Littor. Percent O

O O

O 2

20 Unit Avail. Factor. Percent 0

0 0

0 21 Turbine Startups 0

0 0

0 22 Rjactor Cold Startur>s O

O O

O l

??

3 24 Gross Heat Rate, Blu/kWh 0

0

__O O

{

2S Net Heat Rate, Otu/kWh O

O

'O O

5 26 D

27 g

28 Throttie Pressure, Psig 0

0 0

0 ct 29 Throttle Temperature, "F 0

0 0

0 30 Exhaust Pressure, inh 3 Abs.

0 0

E 31 intake Water Temp.. *r 0

0 0

0 H

32 33 Main FeedWJter, M lb/hr

(

i 34 k

3S 36 37 Full Power Capacity, EFPO (3)

(4)

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

(4)

(4) y 39 Oil Fired for Generation, Galluns 4,340 2

40 Oil Heatina Vatue. Stu! Gal.

1 M. '700 41 Qjpiel Generation. MWh A 4' Max. Hour Net Gen. Max. Day Net Gen. Load M Wh Time Date MWh Date Factor, *4 2 43 0 0 0 N w Remarks: IFor GFNP this value is MWD /STU and for SQNP and WGNP this value is MWD /MTU. [ 2(t) indicates Thermal Energy. 3 .3_1nCormali_qnd utnisheA by_Bsactor Ana1ysis Group 2_Chattanocoa _ 4_Adminniattative hold. A ll A l\\ ~ [ Il Y lI1 >^/w n,,,, s., n..o.....

s N T ON o13C oiN IT E ' 0d t CVN 8 A EO 8 RI 9 E P T 1 V I I GT y TT E r C P a NE E ur R ER R K b O A e F 6 T C s r r a u e o X y H SGC t d T UN G /n io I TI A NA RT n, re UT UU M P SDO 7-fO G R NNO DITWT OH TO C UD A TE H E S R M ~ a ~ n in Z n c E c SU M t A n n la C h P Y v E o G e A tv a TIL u U tt T e s. I r B N O e A i C s L I n A 3 V + A A e D n N O A N G r o T" t 'u i f e i a i t i i i e I E r " a s. N A r N a. s T e i u l t n F U n n. O s U A et n n n u T w no Iii a i i i i t t e !i e I e e i I e. i U 9 im N r n 0 t

t. v m e

l e3 t I t t! t t 8 r e i 4 au4 I a l i 0, t n '. wT x. u 2 f m n 0 w m e u 0 W t.

c. 's, I

6 i

e i

i I s l* i i' i e i i e a u4 m a n A s y 2 v t Iji N lu 'm; r i Ii i i 8

i!

i !i e l , i d, i e 'u n. 0 m 0 n. e m e c Y

s. a 4

s ? 2 h W o. 0 m M n 'a i e = i i' if e I 0!; i, u m c, u 4 g T n t/ S u ) 4 ht 3 o ( 9 w.n. W 0 u M ) e 1 t 's l t ' i e !l i l i! e i l i i o e n N 3 O se 9 W( g J 2 M i J t i l n a ~ e 2_ t A v v R n r 2 1 e i t '

. r e

i

i

, 4 i 5 I i !i i i i l 'n n c e 5 la wo 1 i u 1 c s P r n., tiil 4 e n. le 1 sa t g c n. 7 3 ta u E t. to l I i i t 8 e 8 t I i I w( R o ca s e R s T n r w C e G Ii I f i Ii !l I I i ti i II !l ii i 4 i !t tl 0 d ta en r n 7 8 9 2 3 4 5 6 7 M 9 0 1 ta 4 r e 9 v 1 2 3 4 $ 6 7 3 9 0 I 2 3 4 5 61 1 1 1 0 1 2 2 2 2 2 2 2 2 1 3 ro v x n. v o 1 1 1 1 1 1 2 2 a a e e T L G D Y

,1 N c T O N I J o AEO t MC T E mDDG D CVN RI A EP !T c V 1 I OT T T C vr C P s E NE n t'. R EA R K b 6 e c+ O A T F E C s r. r a u e o Y H SG E X / ht d TUN G o i I T I A o n r NA RT e UT UU M P SDO l F X G R mNO WT H TO C UD A H E T S R M se un l i tn o E A c SU d t A l n la C o P h E Y ra G e T lc I e v A i IL T t = u B N U a ~ r A O t L A is I n i V ~ m A dA D N oV n A T X_ u E

m. in i

i i i i i i I 8 , ' I r G r o T s A w N T t e* i N U e n O n U n. u et m, O !i. e X u T c u I e N R s, 8. i e i i i t l e I i i i s i e T X U H n _L t w m 0 0 i 0 8 3 l n 's,, 'a!; i ' i i ; i I I t t !; i i l i i I I 0 U S 4 s 1 2 6 b ty

n. m e

i u O 0 r e 8 ' i i ' i e ' i ' I' i s i' i i I i O 0 a a ', es e a s a p v A H ? r 4 6 t 2 9 o 5 n. N u m-e. : e ' i e i!E !i s I D i e 0 e n O 0 m e 's, i G 4 T 7, 4 s P 2 W b M o n.

n. u m-0 0

o i

'd,

. e ! , e ' i e t* [ s ! ! 0Ii 0 u T s, ? s 4 4 1r 2 h 6 t 8 d n W( 4 w 0 U u M ) e 1 t 's, ,i ' i i !l , I l e ' i i l , e ' ti i a o e W N 3 W( q ia u t s 9 v e a 2 s n. 2 2 ta A u r S R n t. e e I n G ,,. ;, i i ' , i 8 w I ia o i u s, t' t t i ii I !i t ! I e e

c w

s re P t n. l q r r g c n c E s w Ih a. n. le T 3 89 t ta en ( a s o' e R s T i i ~ ,, i i ,. e , e 1 , e e ' , a I i C R o s r d o r e O e t G ilI a s r n I h i (6i 6 n e g u1 2) 4 5 6 i a 9 0 1 1 1 1 1 6 7 8 9 9 1 2 o 1 2 3 4 5 1 a 36 7 8 9 0 1 sa A e J2 n s 1 1 1 1 2 22 22 2 2 2 3 3 t V w e e o T L G D T rilt!

hT ~ Q *nuDD 04r 1 E NW T t < ( C VN A AEO A Rt 9 E PG V 1 TTO f I O -r C a E NE o R ER r R K h f A o O N T ( C ]' r s a ru e o { Y H G E / ht d T N G n r U^OO iv I A o I RT i N %Pe UU L ] Q F O R D NO O WT c p H O C D A T E E R y tF* t egn i t

r E

o S c U d t A n i la m C P E Y r G a TI le A y u c L a T 1a I h U a B P O t A t IL s i A n A y t ~~. V i m r yl D re N F A g N s u E n t I a ' i i e o o G v T A e g r s r i T B n U U e O g e t w T mu i o i r, , e t i 1 i

i i

g e f I i i ' , i h NI T U n n. e I'. i ~ 3 t. n 3 O 's.Q*

i8 i

l 4 g I iI,; l i l i i i Yi I h no a u 2 t4 ru 2 ():l I}I fk w G o., u O u n i 6 6 e ' i g a ; ' ; e i ' e i g1 T D m ',s 2 v3 i, 4 1 l .a n ?

r s

to n. m. u 00 =. - Q D.

m. Gl

. i ' i , i '. t ; b h I ae_ 'i 1 6 4 m 2 g T -g w -i tX' i y

n. Q a

a. u C n

4 i , 8 ti I mM _ n g e. ,5 T n 2 Il l; i ht 8 o p Ijihiil; . g g ) 4 u n ( 9 s w e w 0 u M ) 1 t '. e i ( l r i s 6,; l , 3 t 1 i o e e N m 3 ( g an 9 w 9 n c. 2 3 M ta A i a. a. r 2 R o u r. e i i 4 , a i ' i i i,_h e i l a l e 5 la n G w 1 ) o r u,. s 1 c i T2 P t( m. ii 1i

!I I

f!iI [ s r g n o s t n. l T u 3 E a ta r4 t s o 'n

e i

f 8 e i 1 I i j p e R s T R o Cv o r e w to G !!l t {f 1 l1 i i l 0 i j l !Ih l d n ra n e g w f 3 4 ') / M9 0 I 2 3 4 S 67! i N n 2 2 D 1 I i 1 1 i 1 s 2 3 ,4* 22 ,4 2 s $I ia D6 8 o t a A e a s w u e e n I L G D I 4

t 8 9 Page 30 REACTOR POWER PERCENT FEBRUARY 1988 UNIT i P GCENT 100 90 30 70 00 go ADMINISTRATIVE HOLD 40 M M 10 - 0 4 * * * *

i ' *@%\\ @ @ s @ @ @ %* Of@@@@$$$#y b

UNIT 2 PGCENT 100 90 80 70 80 ADMINISTRATIVE HOLD 40 M M 10 0 % * * " *

i ' 'O%% @ @ s" @ @ O %* @ @ @ @ @ @ $ $ f f f UNIT 3 PD CENT 100 90 90 n

80 g ADMINISTRATIVE HOLD 40 M M 10 0 % * * * *

S * *@%%@@%"@@@@@ff@@@fffff l

h I$ e e MAINTEXANCE

SUMMARY

ELECTH1 CAL labud10AL BELT 10N page 31 MONTELY REPORT FEBRUARY, 1988 Unit Common Major Routine Activities -- General Electric generator specialist and technicians on site to repair unit two main generator stator cooling leaks. Major maintenance continues on 500 KV power circuit breaker number 5214. CIRCUIT BREAKER REBUILDS: 4160V 480/250V Total number of breakers to be rebuilt 303 494 Total number of breakers rebuilt 9 16 Completed this month 0 3 Parts are on order to rebuild circuit breakers. While troubleshooting the unit two preferred MMG to determine the cause of the breaker tripping before the MMG set was up to speed, it was discovered that the breaker thermal trip devices were undersized. New overloads have been ordertd and a DCR has been written to replace them. The 2C RHR pump motor was sent to the power ser' ice shop to be repaired after failing during a restart test. Time delay relays responsible for starting the RBCCW pumps were calibrated using setpoints provided by design. The Electrical Technical Section performed technical reviews on over 30 procedures during February, 1988. Fuse Control Program: A revision to BF 6.12 is in word processing. Drawings are being reviewed to add fuses to the fuse data base. Contract TSD 044: Information from the contractors will start being reviewed the first part of May, 1988. Modifications: Information for fuse block changeout for circuit protection is beginning to come in from modificationa. ELECTRICAL EQUIPMENT LIST: 435 drawings were received in February, 1988. 3985 drawings are in backlog. Repairs and restart testing complete on battery charger shutdown board "A". Received twenty 3DCU-9 batteries to replace previously identified weak or faulty batteries currently in use. Capacity test performed on D/G 3A battery. Battery at 109 per cent of rated capacity. Battery charger Shutdown board "B" out of service due to undocumented modification.

2 Page 32 Electrical Technical Section Monthly Report Material for main charger no. 1 on site and repairs underway. An electrical engineer from the Electrical Technical Section attended a battery maintenance and testing seminar in February, 1988. Signature analysis began on February 17, 1988 with seven valves completed. Currently working two crews. One crew is continuing with environmental qualifications and final inspections, with twenty-eight final inspections complete. The other crew is doing signature analysis. Workplans 2222-84, 2224-84, and 2226-84 were revised during February, 1988 to support work on systems 73, 69 and 1. l l .. _.. _ - ~

l uuuute.iunu wounivau ouvitun MONTHLY REPORT Page 33 l FEBRUARY 1988 I. WORK TIME SCHEDULE Received / Assigned Completed QpeJ1 Red Folders 5 1 12 Orange Folders 2 5 10 Yellow Folders 0 0 1 Blue Folders 5 5 5 Purple Folders 0 1 0 Active Engineering Assignments 0 1 16 Engineering Backlog 0 5 65 New Engineering Assignments 0 0 0 Completed Sngineering Assignments 0 6 0 II. COMMITMENT TRACKING Licensing Issues (NCO & SLT) NCO O 4 21 SLT 0 1 3 P0RS Tracking Items (BFC) 2 2 1 CAQRs 6 1 11 Average Age of CAQRs Two months and five days Employee Concerns 0 0 1 Safety Issues List 0 0 0 III. STAFFING LEVELS AND TRAINING Personnel Approved Headcounts Current Headcounts ASP 29 ATL 5 HTL 0 Contractors _1 TOTAL 39 IV. OVERTIME 5.7% V. PROCEDURES 5 procedures PORC approved 1 procedures sent to Word Processing VI. 15 Outstanding Status "H" MRs 4 OUTSTANDING STATUS "Q" MRs l

Page 34 I&C TECHNICAL FEBRUARY 1988 I. Work Item Schedule Received / Completed Open Assigned Red Folders 2 3 1 Orange Folders 1 0 9 Yellow Folders 0 0 0 Blue Folders - 3 2 2 Total Assignments Active Engineering Assignments 8 11 47 Engineering Backlog 14 II. Consnitment Tracking Licensing Issues (NCO & SLT) NCO O 2 16 SLT 1 0 7 PORS Tracking Items (BFC) 0 0 3 DR 0 2 0 CAR 0 0 0 CAQR (Onsite) 1 1 13 CAQR (Off-site) 1 1 0 Average Age of CAQRs 6.25 months Employee Concerns 0 0 0 Safety Issues List 0 0 0 TII. Staffing Levels and Training Approved Headcounts Current Headcounts yPsonnel ASP 17 13 ATL 4 5 HTL 0 0 Contractors 4 TOTAL 21 22 IV. Overtime 10.5% V. Procedures 86 procedures were sent to Word Processing

Page 35. I&C TECHNICAL FEBRUARY 1988 StJMMARY The major activities of the month involved preparation of procedures to support the retest schedule and the scheduled NRC SI review. Sealing and Setpoint Documents to support:these procedures are also being issued. Y I l l

_ ~. MECHANICAL. TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0) FEBRUARY 1988 Common No major nonroutine activities. 1. Closed the following commitments: a. IE Notice 87-039 - Control of Hot Particle Contamination at Nuclear Power Plants b. INPO O&MR 317 - System Flow Rates Degraded by Replacement Pump Impellers c. NCO 870045002 - RHRSW Pump d. R35 880128 148 - Spare Wheel Forgings for Turbine Rebuild Project e. R35 880203 299 - Approval of Master Specification MS-NEB-009 f. R35 880204 338 - Approval of Master Specification MS-MEB-007 g. R35 880204 339 - Approval of Master Specification MS-MEB-003 h. R35 880208 438 - Approval of Master Specification MS-NEB-013 i. R35 880208 439 - Approval of Master Specification MS-CEB-010 J. R35 880208 440 - Approval of Master Specification MS-MEB-010 k. R35 880209 468 - Approval of Master Specification MS-MEB-005 1. R35 880210 501 - Orientation of Nuclear Supervisors m. R35 880217 639 - Approval of Master Specification MS-CEB-001 n. R35 880222 722 - Approval of Master Specification MS-MEB-013 o. G-29(RO) - PS 3.M.9(RO) p. G-29(RO) - SA-U-6(R1) q. G-29(RO) - GM-FC-P-2(R3) r. G-29(RO) - GM-FC-U-2(R3) s. G-29(RO) - GT-P-1(R3) t. G-29(RO) - PS 2.M.1.1 Add.2(R4) u. G-29(RO) - PS 3.M.3.1 Add.4(R3) 1

MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0) FEBRUARY 1988 v. G-29(RO) - PS 1.C l.2 Fig.1(R2) v. G-29(RO) - PF1079(RO) - Pure'ase Specification for Soldering Filler Metals x. N-GP-7(RO) - Verification of Component Support Settings y, NQAM,II,5.1(RS) - Generic Procedure - Inservice Inspection z. NQAM,II,6.3(Rl) - Non-destruction Examination aa. SRN-G-32 Bolt Anchors Set in Hardened Concrete bb. SRN-G-38 Installing Insulated Cables Rated up to 15,000 Volts cc. SRN-G-51 Grouting and Dry-Packing of Base Plate and Joints dd. SRN-G-34 Repair of Concrete ee. SRN-G-66 Installation, Inspection, and Testing of Maxi-Bolt Undercut Anchors ff. ROO 880216 563 - Purchase of a Cracked GE Rotor Wheel gg. ROO 880219 698 - G-53 Bolting Material - Proposed Revision 2. The following instructions were approved, revised, or cancelled, a. MCI-0-001-VLV007 - Main Steam Startup Bypass Valves; Disassembly, Inspection, Rework, and Reassembly b. MCI-0-001-VLV012 - Reactor Feedwater Pump Turbine Low-pressure Stop Valves FCV-1-123, FCV-1-131, and FCV-1-139; Disassembly, Inspection, Rework, and Reassembly c. MCI-0-002-FMP007 - Condensate Booster Pump Auxiliary 011 Pump; Disassembly, Inspection, Rework, and Reassembly d. MCI-0-032-VLV002 - Drywell Air Operated Suction Flow Control Valves FCV-32-62, and 32-63; Disassembly, Inspection, Rework, and Reassembly e. MCI-0-033-CMP 003 - Service Air Compressor E, Norberg Type V-100; Disassembly, Inspection, Rework, and Reassembly f. MCI-0-073-TRB001 - High-pressure Coolant Injection Pump Turbine - Terry Turbine CCS; Disassembly, Inspection, Rework, and Reassembly g. MCI-0-099-DRV001 - Reactor Protection Syster. Motor Generators A & B; Disassembly, Inspection, Rework, and Reassembly

Page 38 MECHANICAL TECHNICAL SECTION MONTHLY REPORT-COMMON UNIT ONLY (UNIT 0) FEBRUARY 1988 h. MCI-0-252-DRV001 - Unit Preferred Motor Generator (MG) Set;

Disassembly, Inspection, Rework, and Reassembly 1.

MCI-1-069-VLV004 - Reactor Water Cleanup j. MMI Removal, Repair, Replacement, and Testing of Control Rod Drives k. MMI Main Steam Relief Valves 1. MMI Control Rod Drive Hydraulic Control Unit Module (Repair, Removal, and Peplacement) m. MMI Preventive Maintenance Program - Filters n. MMI Hydraulic Shock and Sway Arrestor - Bergen Paterson and Grinnell, Unit Removal; Disassembly, Reassembly, and Replacement o. MMI Maintenance of CSSC/Non-CSSC Valves t.nd Flanges p. MMI-59A - Instructions for Removal and Installing Pacific Scientific Mechanical Snubbers and the Torus Dynamic Restraints q. MMI-il6 - Inspection and Maintenance of Doors r. MMI-153 - Temporary Ventilation for the Electrical Equipment Rooms 3. The following CAQRs (Conditions Adverse to Quality Reports) were closed. a. BFP 87-580 - Discrepancy identified between bolt material as specified b. BFP 87-815 - Stainless clad portion of upper tube sheet c. BFP 87-885 - Reactor building equipment door (3 & 4 #226) seals l d. BFP 87-932 - Bolts retaining the snubber base and the extension not safety wired e. BFP 88-0031 - Proper veld maps and weld data sheets initiated prior to welding 4. The Mechanical Technical Section devoted 3DD hours to training during the month of February. 0996G CLG I ~._

c Page 39 MODIFICATIONS MONTHLY REPORT FEBRUARY 1988 MAJOR WORK PERFORMED ECW NARRATIVE App:ndix R P0808 Continued conduit and cable work on control power circuits (work plan 2048-87 and 2047-87). P0885 Continued conduit and support work on RB fire detectors (work plans 2012-87, 2013-87, 2014-87, and 2015-87). P0883 Continued changeout of fuses and fuse blocks (work plan 2112-87). P0889 Continued reroute of conduit for separation (work plan 2053-87). P0913 Completed craft work on fuse and fuse block replacement (work plan 1022-86). Environmental Qualification P3019 Field completed System 11 pressure switch replacement. P3092 Field completed FIS 74-50 and 64 replacement. P3145 Continued electrical conduit sealing activities (work plans 2073-85, 2074-85, 2075-85, and 2078-85). P3180 Continued electrical work assiciated with containment penetration replacement (work plans 2036-87 and 2105-87). P3205 Continued small piping and support work on H02 2 analyzer lines (work plans 2158-87, 2159-87, 2199-87, 2200-87, 2160-87, 2161-87, 2162-87, 2201-87, 2202-87, and 2163-87). P7039 Started craft work on transformer 2A replacement (work plan 2073-88).

Pago 40 MAJOR WORK PERFORMED ECN NARRATIVE SLismic Issues P0370 Continued structural work on seismic qualification and designation of block walls (work plans 1030-87, 2092-87, and 3024-87). P0361 SMMI rework of tcrus attached piping and drain supports continued. Work plans 2067-84, 2160-85, 2074-84, 6787, 2080-84, 2059-84, 2170-87, and 2208-87 were field completed. P0859 Continued work on non-CED attachments and catwalks R9 and 13 (work plans 2066-87, 2205-86, 2140-87, 2194-87, and 2207-87). P0933 Completed craft, work seismic qualification of Unit 2 RB elev 593-621 c'.ouit (work plans 2010-87 and 2157-87). P0998 Drywell catwalk upper elevation work continued on a concerted basis (work plans 2147-87 and 2148-87). P2036 Continued additional 79-14 support fixes to CRD return piping (work plan 1036-87). P2044 Completed craft work on Unit 1 RB drain and sump pump 79-14 modifications (work plan 1033-87). P2054 Completed craft work on additional 79-14 fixes to RBCCW piping (work plan 1034-87). P2064 Completed craft work on additional 79-14 fixes to Unit 3 RB floor drain piping (work plan 3033-87). P2088 Started field work on aditional 79-14 fixes to fuel pool cooling system (work plan 2274-87). P2154 Started field work on RHRSW and EECW 79-14 fixes (work plans 0015-88, 0017-88, and 2062-88). P7018 Started craft work on drywell HVAC seismic qualification (work plans 2282-87, 2281-87, 2280-87, 2279-87, and 2228-87). -a -....,n

Page 41 e MAJOR WORK PERFORMED ECN NARRATIVE Snicnic Issues (Ccatinued) P7029 Continued repair of lower drywell structural steel (work plan 2234-87). P7083 Started craft work on common area tubing seismic qualification (work plans 0008-88, 0009-88, and 0010-88). P7085 Started craft work on Unit 2 tubing seismih qualification (work plans 2059-88 and 2060-88). TM1 Mods P0324 continued electrical work on high-range containment radiation monitors (work plans 2160-86 and 2241-84). P0354 continued sample line work on stack radiation monitor (work plan 2142-85). Appandix J P0959 Support installation continued on RBCCW system (work plan 2122-87). Othsr P0085 Started reroute of conduit on drywell pressure and temperature upgrade (work plan 2192-87). P0286 Continued work on yard security lighting (work plans 0017-86 and 0022-86). P0284 Continued fabrication and installation of seismic conduit supports for the acoustic monitoring system (work plan 2205-84). P0384 Continued tubing and electrical work on containment purge valves (work plan 2049-86). P0392 Continued SMMI rework of scram discharge volume supports. P0569 Continued support work on RPV vent line (work plans 2051-84 and 2204-84). P0761 Field completed RB HVAC intrusion barrier installation. P0612 Continued support work on flex lines to MSRVs (work plan 2266-87).

f Page 42 MAJOR WORK PERFORMED ECM NARRATIVE Other (Continued) P0720 Continued work of jet pump instrumentation lines (work plan 2109-85). P0956 Continued installation of duct and duct supports for new shutdown board room KVAC (work plans 2156-87, 2228-87, 2229-87, 2248-87, 2253-87, 2254-87, 2262-87, 2268-87 2155-87, 2263-87, 2250-87, and 2249-87). P1001 Recirculation Loops A and B support work continued (work plans 2283-87, 2284-87, 2009-88, 2008-88). PS269 Installation of supports for uninterruptable demineralized water correction for torus water level transmitters cont *.aed (work plan 22a?-G7). p5480 Insta11stiqn of vessel drain supports conti ued (vork plan 2218-87). S PS291 Continued rcactor water level instrument sense line modtsication (work plans 2153-87, 2154-87, and 2232-86). P5434 Continued Icici transmitter sense line reroute (work plan 2187-87). N/$ Completed work required to allow removal of Unit 2 condenser tubes for replacement.

e TVA GEXERATING AVAILABILITY DATA SYSTEM (GADS} 3VEXT REPORT t b .i i (

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4 e OTHER REPORTS J

Page 46 CHEMISTRY SUfflARY TEBRUARY 1988 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and i chloride have not been exceeded. Unit 2 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant. remained within technical specification and fuel warranty limits during the month. This calendar year, j the technical specification and fuel warranty limits for conductivity and l chloride have not been exceeded. Unit 3 The conductivity of the reactor coolant remained within technical I specification and fuel warranty limits during the month. Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not been exceeded.

PRIMARY COOLANT CHEMISTRY Page 47 l FEBRUARY 1988 Parameter Unit 1 Unit 2 Unit 3 1. Gross Radioactivity a. Crud (filter) (pci/ml) High N/A N/A N/A Low N/A N/A N/A. Average N/A N/A N/A b. Filtrate (pci/ml) j High N/A N/A N/A-J Low N/A N/A N/A Average N/A-N/A N/A. 3 - 2. Milipore Iron (Fe. ppb) High N/A N/A .N/A Low N/A N/A N/A Average N/A N/A N/A 3. Tritium (pci/ml) High 6.24E-05 6.48E-05 1.32E-04 i Low 5.53E-05 5.35E-05 1.19E-04 t Average 5.86E-05 6.14E-05 1.26E-04 4. Iodine-131 (pci/ml) [ High (LLD <LLD (LLD Low (LLD <LLD <LLD Average <LLD. <LLD <LLD j i 5. Iodine-131: Iodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 1 ? 1 t ., _. ~ - - - -. -. - -

Pcg2 48 PRIMARY C001. ANT CHEMISTRY (Continued) FEBRUARY 1988 Parameter Unit 1 Unit 2 Unit 3 6. Chloride (ppb) High <10 <10 <10 Low <10 <10 <10 Average <10 <10 <10 7. pH@25"C High 6.4 6.2 6.2 Low 5.8 5.8 5.6 Average 6.1 6.0 5.4 8. Conductivity (pmho/cm025 C) High 0.17 0.95 0.40 Low 0.10 0.58 0.080 Average 0.14 0.78 0.22

Pago 49 -CHEMISTRY

SUMMARY

(Continued) FEBRUARY 1988 Environmental Technical Specification Reauirements The ambient upstream river temperatures (24-hr. avg max) averaged 45.4*F ranging from a high of 48.9'F on February 29 to 41.6*F on February 13. The downstream temperature varied from 48'F on February 29 to 41.7'F on February 14. The downstream temperature averaged 45.0 for the month. The greatest temperature change was 0.9* F on February 7. The sedimentation pond (DSN 102) remained out of service for the entire month. Repairs were completed on February 10. The pond is to be refilled with the river water to determine if the repairs were successful. Compliance problems continued to experienced from the Unit 1 and 2 control bay drain discharge (DSN 110). The total suspended solids (TSS) concentrations exceeded the NPDES permit limit of 100 mg/L in three of 30 samples taken. The sewage lagoon operated in compliance for the month. The BOD concentrations ranged between 13 mg/L and 28 mg/L while TSS ranged between 13 and 42 mg/L. The discharge flow averaged 49,488 gallons per day (gpd) and varied between 31,248 gpd and 85,968 gpd. l l ,a ,.n,, ---e - - + e -,-e, .e

l "- n..'. e Page 50 AIRBORNE RELEASES (1) FEBRUARY 1988 SUMMATION OF ALL RELEASES UNIT THIS MONTH A. FISSION AND ACTIVATION GASES 1. TOTAL RELEASE CI < 6.98E 01 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC < 2.89E 01 3. PERCENT OF TECH. SPEC. LIMIT (0 15 CI/SEC) 0 00E-01 B. IODINES 1. T7TAL IODINE - 131 CI < 1.56E-04 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC < 6.44E-05 3. PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 C. PARTICULATES 1. PARTICULATES WITH HALF-LIFES > OR = TO 8 DAYS CI < 7.86E-04 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC < 3.25E-04 3. PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 0.00E-01 4. GROSS ALPHA RADI0 ACTIVITY CI 5.57E-07 D. TRITIUM 1. TOTAL RELEASE CI 5.47E-02 2. AVERAGE RELEASE RATE FOR PERIOD UCI/SEC 2.26E-02 3. PERf.2NT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 1.03E 00 4. OROUND LEVEL RELEASE CI 5.45E-02 5. ELEVATED RELEASE CI 2.46E-04 (1) REPORTING PERIOD 28 DAYS I

Page 51 AIRBORNE RELEASES (CONTINUED) FEBRUARY 1988 ELEVATED RELEASE 5 A. FISSION GASES UNIT _THIS MONTH KR-85M CI < 7 55E-02 KR-85 CI < 3.55E 01 KR-87 CI < 2.50E-01 KR-88 CI < J.78E-01 XE-133 CI < 1.50E-01 XE-135M CI < 2.23E-01 XE-135 CI < 9.81E-02 XE-138 CI < 6.23E-01 OTHERS(SPECIFY) TOTAL FOR PERIOD CI < 3 73E 01 B. 10 DINES I-131 CI < 3.54E-06 l I-133 CI < 3.49E-05 I-135 CI < 1.52E-06 TOTAL FOR PERIOD CI < 4 00E-05

.C Page 52 AIRBORNE RELEASES-(CONTINUED)

FEBRUARY 1988 ELEVATED RELEASES f C. PARTICULATES UNIT THIS MONTH SR-89 CI < 2.52E-07 + SR-90 CI < 1 20E-07 CS-134 CI < 1.81E-06 CS-137 CI < 1.77E-06 BA-140 CI < 1 17E-05 LA-140 CI < 5.63E-11 OTHERS(SPECIFY) TOTAL FOR PERIOD CI < 1.56E-05 D. TRITIUM CI 2.46E-04 i I { i n l \\ /

Page 53 AIRBORNE RELEASES (CONTINUED) FEBRUARY 1988-GROUND RELEASES A. FISSION OASES UNIT - THIS NONTH KR-85M CI < 8.41E-02 KR-85 CI < 3.09E 01 KR-87 CI < 2.21E-01 KR-88 CI < 3.07E-01 XE-133 CI < 2.14E-01 XE-135M CI < 1.18E-01 XE-135 CI < 9.11E-02 XE-138 CI < 5.36E-01 OTHERS(SPECIFY) L TOTAL FOR PERIOD CI < 3.25E 01 B. 10 DINES I-131 CI < 1.52E-04 I-133 CI < 3.22E-04 I-135 CI < 3.10E-01 TOTAL FOR PERIOD CI < 3.11E-01 h J i -y ~ v-. .--s.r----.y.,m-- =-, c=, -m--,w--g,--, n.,e- ,v,

e Pago 54 AIRBORNE RELEASES (CONTINUED) FEBRUARY 1988 . GROUND RELEASES j ~ C. PARTICULATES UNIT THIS NONTH j l SR-89 CI < 1.77E-06 SR-90 CI < 1.23E-06 CS-134 CI < 7.40E-05 CS-137 CI < 1.62E-04 BA-140 CI < 5.05E-04 LA-140 CI < 2.59E-05 i OTHERS(SPECIFY) TOTAL FOR PERIOD CI < 7 70E-04 D. TRITIUM CI 5.45E-02 1 _ _. _. _ _. -.. _. _. _. _ _ _ _ _ _. _ ~.,

Paga 55 BROWNS FERRY NUCLEAR PLANT MONTNLY-REPORT CALCULATIONS LIQUID RELEASES FEBRUARYr 1988 RADI0 ACTIVE LIQUID EFFLUENTS 1. GROSS RADI0 ACTIVITY UNITS a) TOTAL RELEASE CURIES 1.16E-02 b) AVERADE DILUTED CONCENTRATION RELEASED UCI/ML 9.98E-10 c) PERCENT OF APPLICABLE LIMIT (1E-07 UCI/ML) 9.98E-01 2. TRITIUM a) TOTAL RELEASE CURIES 8 43E-02 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 7.24E-09 c) PERCENT OF APPLICABLE LIMIT (3E-03 UC1/ML) 2.41E-04 (1) 3. DISSOLVED NOBLE GASES a) TOTAL RELEASE CURIES 1.60E-03 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.37E-10 c) PERCENT OF APPLICABLE LIMIT (2E-04 UCI/ML) 6.8SE-05 4. GROSS ALPHA RADI0 ACTIVITY a) TOTAL RELEASE CURIES 2.23E-04 b) AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 1.91E-11 '5. VOLUME OF LIQUID WASTE TO DISCHARGE CANAL LITERS 2.81E 06 h 6. VOLUME OF DILUTION WATER LITERS 1.16E 10 (1) INCLUDES XE-133, Xe-135, AND OTHERS 1

'Pcg3 SE BROWNS FERRY NUCLEAR PLANT MCNTHLY REPORT CA!.CULATIONS LIQUID RELEASES FEBRUARY, 1988 UNITS ISOTOPES RELEASED CI < 1.29E-03 CR-51 2.54E-06 MN-54 C0-58 < 1.29E-04 < 2.41E-04 FE-59 9.80E-04 CO-60 4.74E-04 ZN-65 NB-95 < 1 14E-04 ZR-95 < 2 25E-04 MOTC-99M < 1 15E-04 I-131 < 1 70E-04 XE-133 < 2.90E-04 CS-134 1 84E-03 XE-135 < 9 51E-05 4 68E-03 CS-137 BA-140 < 6 45E-04 LA-140 < 7.37E-05 CE-141 < 1e91E-04 SR-89 < 1 26E-04 SR-90 < 6.49E-05

Page 57 BROWNS FERRY NUCLEAR PLANT NONTHLY REPORT CALCULATIONS LIQUID RELEASES FEBRUARY, 1988 0THERS UNITS j CI KR-85 1.40E-03 I

Page 58 BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULATIONS LIQUID RELEASES FEBRUARY, 1988 LAUNDRY DRAIN VOLUME RELEASED 1 9681.5 GALLONS FLOOR DRAIN VOLUME RELEASEDI 732949 5 0ALLONS WASTE SAMPLE TANK VOLUME RELEASED! 0.0 GALLONS DISTILLATE TANK VOLUME RELEASED! 0.0 GALLONS LOCATION OTHER THAN RADWASTE VOLUME RELEASED! 0.0 GALLONS TOTAL VOLUME RELEASED TO IHE RIVER! 742630 9 GALLONS HIGHEST BATCH ACTIVITY RELEASED FOR HONTH! 1.26E-08 UCI/HL A/D LON0EST RELEASE TIME FOR MONTH! 295 MINUTES SHORTEST RELEASE TIME FOR MONTH! 187 MINUTES TOTAL TIME OF RELEASES FOR MONTH! 7148 MINUTES AVERAGE TIME FOR BATCH RELEASES! 265 MINUTES COMPOSITE INFORMATION! j COMPOSITE CI AFTER DILUTION UCI/ML RELEASED UCI/ML SR-89 < 4.48E-08 < 1.26E-04 < 1.08E-11 SR-90 < 2.31E-08 < 6.49E-05 < 5.57E-12 l H-3 3.00E-05 8.43E-02 7.24E-09 OROSS ALPHA 7.93E-08 2.23E-04 1.91E-11 ( l NUMBER OF BATCHES RELEASED! 27 ) NUMBER OF ADMINISTRATIVE LIMIT VIOLATIONS! O l NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS! 0 l l l

RESIN USAGE REPORT FEBRUARY 1988 RESIN CONSUMED (CU.FT.) % of Total Brad POWDEX ECODEX ECOSORB EPIFLOC Total Radwaste Floor Drain Filter 51.0 0 112 0 0 53 165 Waste Demineralizer 0 0 0 0 0 0 0 Waste Filter 36.5 0 103 0 15 0 118 Fuel Pool Demins 0 0 0 0 0 0 0 Reactor Water Cleanuo Unit 1 0.6 0 2 0 0 0 2 Unit 2 1.8 0 6 0 -0 0 6 Unit 3 0.6 0 2 0 0 v 2 Cond. Demins Unit 1 0 0 0 0 0 0 0 Unit 2 9.5 0 30 0 0 0 30 Unit 3 0 0 0 0 0 0 0 Totals 100 0 255 0 15 53 323 r

FUEL CLADDING INTEGRITY PARAMETERS FEBRUARY 1988 Unit 1 Reactor Water Iodines (uci/sec.) Date I-131 I-132 I-133 I-134 I-135-Unit in Outage Eission Gases at DischarRe of SJAE (uci/sec) Daig Elgy HW1 Xe-133 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (uci/sec.) Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at DischarRe of GJAE (uci/sec) Ratg Elgy ME1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.) Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec) Dals Eing MW1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage i J

WASTE TREATMENT SYSTEM THROUGHPUTS FEBRUARY 1988 FLOOR FLOOR FLOOR DRAIN DRAIN DRAIN 3,,, GAL-7.68E+0ii COLLECTOR FILTER SAMPLE 6At 7.33E+05 ~ TANK TANK (2) CtFT: 165.00 6AL: 7.68EM5 i 1 GFD: 1.20Ed3 jf I f LAUNDRY l 6AL: 3.48E+04 EPD: 3.34E42 DRAIN = s.ww3 CANAL s TANK sPD: 2.58E+E -l GP2 3.10E+04 ,,e ,,,,g.,5 E 7.43E+05 I ECW: LED WATER GPR 0.00E+00 gat 0.00E+00 N Ifif1 r WASTE WASTE WASTE WASTE sPO: 0.00E+00 COLLECTOR SAMPLE FILTER DEMINERALIZER R 0.00E+00 TANK TANK l (1) CtFT: 118.00 (3) ClFT: 0.00 6AL: 9.33E+05 8 e l O (1) CIFT POWEX 103.00 CUFT ESIN E FIBER MIXTURE: 0.00 CUFT ECOSORB: 15.00 f GPD: 3.22E+04 j (2) CUFT P0eet 112.00.CUFT ESIN & FIBER NIXTURE: 53.00.QFT ECOSORB-0.00 9. STORAGE 1 (3) BEAD ESIN ~ ' TANK l

r. L . O e Page 62 o. TESTING

SUMMARY

FEBRUARY 1988 Surveillance Testina Unit 0 A total of 54 -surveillance tests were completed per 31 different test instructions. Unit 1 A total of 138 surveillance tests were completed on unit 1 per 36 different test instructions. Unit 2 A total of 168 surveillance tests were completed on unit 2 per 24 different test instructions. l Unit 3 A total of 72 surveillance tests were completed on unit 3 per 22 different test instructions. 1 i l J

Page 63 o TESTING SUPMARY (Continued) FEBRUARY 1988 Channes. Test. and ExDeriments Reauirina Authorization From the'NRC Pursuant to 10 CFR 50.59(a) There were no revisions for unit 1, 2, and 3 technical specifications. Changes. Tests. and ExDeriments not Reauirina Authorization from NRC Pursuant to 10 CFR 50.59(a) There were no special tests completed for this month.

f..'.

o ~ ^ e. Page 64 e REACTOR VESSEL FATIGUE USAGE EVALUATION FEBRUARY 1988 The cumulative usage factors for the reactor vessel are as follows: Usaae Factor Location Unit 1 Unit 2 Unit 3 Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 Closure studs 0.24204 0.17629 0.14360 1 l l I l l )

v, c Page 65 CHANGE IN PROCEDURE o l FEBRUARY 1988 There were 385 revisions to plant instructions during the month; 383 instructions were changed primarily for correction, and the remaining 2 revisions related to safe operation of the plant. PLANT INSTRUCTION REVISIONS FEBRUARY 1988 Category Instruction Reason for Reauest Change in SDSP 13.1 Restart Test To incorporate temporary change 07, Response to Program additional corrective actions per LER, IE BPQ-87-0534, program improvements Bulletin, NRC and correct typographical errors, Inspection program changes implementing Report, OPQA admendment 134 for Unit 2 Tech. Audit, etc. Spec. and to update reference list. SDSP 12.2 Development To incorporate additional corrective of System Test Specifications actions per BPQ-87-0534, program improvements and to update references. l l I l 1 l

e e' e CHANGE IN FACILITY DESIGN c. page 66 .e FEBRUARY 1988 Package Number Description Safety Related ECN P0943 - Assoc. Electrical (WP&IR 1002-87) Installed / modified Equipment - Unit 1 supports for conduits in Class I structures for interim operation of unit 2. This covered the unit 1 reactor building elevations 565' - 593'. The ECN was totally completed as it only covered unit 1.

The modifications did not change or affect any safety related system already existing in the plant.

Implementation of the ECN provided assurance that the affected conduit systems meet the design requirements. Based on this, the margin of safety was not reduced. ECN P0941 - Assoc. Electrical (WF&IR 3008-87) - Documented inspections, Equipment - Unit 3 evaluations, analysis, calculations, and drawings for the seismic qualification of conduit. The conduits covered by this ECN are those located in the unit 3 control bay, except the spreading room, installed in class I structures prior to May 1984. The ECN was totally completed as it only covered these conduits for unit 3.

The modifications did not change or affect any safety related system already existing in the plant.

Implementation of the ECN provided assure.nce that the affected conduit systems meet the design requirements. Based on this, the margin of safety was not reduced. ECN P0939 - Assoc. Electrical (WP&IR 0003-87) - Modified conduit supports Equipment - Common for seismic qualification. This ECN covered the class IE conduits at the intake pumping station and tunnel. The ECN was totally completed. The modifications ensure that the safety related conduits are seismically supported. The modifications did not affect any system's operation and provided added assurance that the affected systems will operate as required. Based on this, the margin of safety was not reduced. /

CHANGE IN FACILITY DESIGN (Continutd) FEBRUARY 1988 Packane Number Descriotion Safety Related ECN P0901 - CAD (WP&IR 2128-86) - Installed CAD System piping-System - Unit 2 supports in the reactor building, elevation 565'. (WP&IR 2129-86) - Piping installation of CAD system to drywell control air crosstie. The ECN was totally completed as 4. only covered unit 2. A seismic analysis was performed by DNE. All systems affected by the change continue to function as described in the Tech. Specs. Based on this, the margin of safety was not reduced. ECN P3205 - Containment (WP&IR 2164-87) - Removed conduit and Inerting System - Unit 2 cable associated with flow solenoid valves, FSV 76-51, -52, -53, -54, -61, -62, -63, and 64. A very small portion of the work covered by the ECN was completed. ECN P5189 - Fuel Pool (WP 0005-85) - As-constructed drawings to Cooling - Units 1, 2, 3 show valves 78-505 and 78-510 normally open. The ECN was completed for all 3 units. No physical work was involved. The drawings were revised to reflect original and proper fuel pool cooling system configuration. The function of the system was not changed, therefore, the margin of safety was not reduced. ECN P0872 - Primary (WP&IR 2032-87) - Installed HVAC duct, Containment - Unit 2 dampers, and supports for the reactor building ventilation system. (WP&IR 2031-87) - Installed HVAC duct, dampers, and supports for the reactor building ventilation system, elevation 593'. \\. a

r. = ] i CHANGE IN FACILITY DESIGN (Continutd) e FEBRUARY 1988 Package Number Descriotion Safety Related ECN P0872 (Continued) (WP&IR 2033-87) - Installed HVAC duct, dampers, and supports for reactor zene exhaust systes, unit 2 reactor building, elevation 63920'. (WP&IR 2056-87, WP&IR 2064-87) - Installed HVAC duct, dampers, and supports, unit 2 reactor building, elevation 621.25. (WP&IR 2035-87) - Installed HVAC duct, dampers, and supports in unit 2 reactor building, elevation 621 and 639. (WP&IR 2156-86) - Fabricated and installed control Bay HVAC duct and supports. (WP&IR 2057-87) - Installed HVAC duct, dampers, and supports for reactor building ventilation system. This work was in the unit 2 reactor building, elevation 639. (WP&IR 2059-87) - Installed HVAC duct, dampers, and supports for reactor building ventilation system, elevation 621. The ECN was only partially implemented. Many workplans remaining to be closed. /

0 li'f..; ; ; - t o, . j / -3 1 I Page 69 s T CHANGES IN PLANT ORGANIZATION ,[ FEBRUARY 1988 i i There was one change in plant staff for those positions designated as key supervisory positions, Raymond R. Weedon, Manager Group, Plant Manager. f P i 1 l r l

p..,,, ' + Page 70 9 ACCIDENTS FEBRUARY 1988 There was one loss-of-time accident during the month.

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. __50-259 UNIT NAME One DATE O2/01/88 REPORT MONTH January COMPLETED BY J. D. Crawford TELEPHONE (?n9) 774-7607 1 ~ E E w. Dare P_ 5 'h E N-k_"4 C'"5' A C"','c'8ive p b.3 0 5se vent g Actio, o 35y Report = us V oO E }L Psevent Recurrence 6 315 01/01/88 F 696

F 4

Administrative hold to resolve various TVA and NRC concerns. i i I s F: Forced 3 Reason: 4 Method: S Stheduleil Exinbit G Instructions A-1:quipment Failure (Explain) !-Manual li. Maintenance oi Test for Preparaison of Data 2 Manual Scram. C-Refueling Enti> Sheets for 1.icensee D Regulaioa> Restriction 3 Automatic Stram.

o Evens Repois (l_I:R) File (NtlRI.G-j j

l i -Operator Trainmg & IAense lixaminaimn 4 Other ilixplaml 0161) m F-Adnunisisati.e G Operational Liini(Expl.im) 5 [ i t9/77 ) Il Othei ( f.xplam) I stubit I Same Source

Revision for January r

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ML20148E735

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