ML20084E233

Monthly Operating Rept to Nrc,Mar 1984

ML20084E233
Person / Time
Site:	Dresden, Browns Ferry
Issue date:	03/31/1984
From:	Jones G, Thom T TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8405020194
Download: ML20084E233 (38)

Text

I TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER BROWNS FERRY NUCLEAR PLANT MONTHLY OPER,ATING REPORT TO NRC March 1, 1984 - March 31, 1984 DOCKET NU!GERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Subciitted by'

/M Plant S orintendent 0405020194 840331 PDR ADOCK 05000249 R

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TABLE OF CONTENTS Operations Summary................

1 Refueling Information....................

3 Significant Operational Instructions.............

5 Average Daily Unit Power Level................

10 Operating Data Reports..........

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

16 Plant Maintenance................

19 Outage Maintenance & Major Modification...........

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I coerations su===rv March 1984 1

The folloting summary describes the significant operation activities during l

the reporting period.

In support of this summary, a chronological log of significant events is included in this report.

There were eight reportable occurrences and four revisions to previous reportable occurrences reported to the NRC during the month of March.

Unit 1 I

There were no scrams on the unit during the month.

Unit 2 There were no scrams on the unit during the month.

Unit 1 The unit was in cold shutdown the entire month for the unit's end-of-cycle 5 refueling outage.

i Prepared principally by B. L. Porter.

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Ooerations Su===rv (Continued)

March 1984 1

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f Fatinue Usane Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usnee Factor i

Unit 1 Unit 2 Unit 9 Shell at water line 0.00598 0.00486 0.00403 Feedwater nozzle 0.28845 0.21103 0.15429 r

Closure studs 0.23477 0.17236 0.13233 NOTE:

This accumulated monthly information satisfies Technical Sgcification Section 6.6. A.17.B(3) reporting requirements.

Comman System Approximately 6.98E+05 gallons of waste liquids were discharged containing approximately 3 22E-01 curies of activities.

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Ocerations Summary (Continued)

March 1984 Refueline Information i

Unit 1 Unit 1 ended its fif th refueling outage on January 2,1984. Unit 1 is scheduled for its sixth refueling beginning on or about February 8,1985 with a scheduled restart date of August 27, 1985. This refueling will involve loading 8x8R (retrofit) fuel assemblies into the core, replacing recirculation piping, work on "A" and "B" low-pressure turbine, upgrade hangers and anchors, and environmentally qualify instrumentations.

There are 764 fuel assemblies in the reactor vessel. The spent fuel stor-age pool presently contains 252 EOC-5 fuel assemblies, 260 EOC-4 fuel assemblies; 232 EOC-3 fuel assemblies; 156 EOC-2 fuel assemblies; and 168 EOC-1 fuel assemblies. The present fuel pool capacity is 3,471 locations.

Unit 2 Unit 2 is scheduled for its fifth refueling beginning on or about August 1, 1984 with a scheduled restart date of November 29, 1984. This refueling outage will involve leading additional 8X8R (retrofit) fuel assemblies into the core, finishing the torus modification, turbine inspection, finishing piping inspection, finishing THI-2 modifications; post-accident sampling facility tie-ins, core spray change-out, and feedwater sparger inspection.

There are 764 fuel assemblies in the reactor vessel. At the end of the month there were 248 EOC-4 fuel assemblies 353 EOC-3 fuel assemblies,156 EOC-2 fuel assemblies, and 132 EOC-1 fuel assemblies in the spent fuel storage pool. The present available capacity of the spent fuel pool is 861 locetions.

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coerations Su===rv (Continued)

March 1984 Unit "4 Unit 3 shutdown for its fif th refueling outage on September 7,1983, with 1

a scheduled restart date of August 1, 1984. This refuelir.g involves loading 8XSR (retrofit) assemblies into the core, finishing the torus modifications, I

postaccident sampling facility tie-in, core spray change-out, finishing TMI-2 modifications, turbine inspection, piping inspections for cracks, and i

changeout of jet pump hold-down beams.

There are O fuel assemblies presently in the reactor vessel. There are 248 new fuel assemblies, 764 EOC-5 fuel assemblies, 280 EOC-4 fuel assemblies, 124 EOC-3 fuel assemblies,144 EOC-2 fuel assemblies, and 208 EOC-1 fuel i

assemblies in the spent fuel storage pool. The present available capacity of i

the spent fuel pool is 150 locations.

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S Stanificant Operational Events Date Time Event Unit 1 3/1 0001 Reactor in startup after scram at 2311 on February 29, 1984.

0457 Commenced rod withdrawal.

1015 Reactor Critical No. 195 1310 Increasing reactor power for ST 8407 on Main Steal Line flow transmitter 1-25A.

1700 Reactor power at 20% for ST 8407 1735 ST 8407 complete, reducing thermal power.

3/2 0420 Rolled Turbine / Generator (T/G).

0443 Synchroni:ed generatori commenced power ascension.

3/3 0700 Commenced PCIOMR from 92% thermal power.

1100 Reactor thermal power at 935,12-hour fuel soak in progress.

2325 12-hours soak complete, commenced reducing thermal power from 88% for control rod pattern adjustment.

3/4 0100 Rod adjustment complete, commenced power ascension from 70% thermal power.

0200 Commenced PCIOMR from 80% thermal power.

1900 Reactor thermal power at 99%, maximum flow, rod limited.

3/8 1610 Commenced power ascension.

1700 Reactor thermal power at 1005, maximum flow, rod limited.

3/10 1438 Commenced reducing thermal power for RTI-23 (Feedwater Controls).

1540 Reactor thermal power at 64% for RTI-23 2130 RTI-23 complete, holding power at 64% for turbine control valve test and SI's.

2400 Turbine control valve test and SI's complete, commenced power ascension.

3/11 0200 Commenced PCIOMR from 945 thermal power.

1200 Reactor thermal power at 100%, maximum flow, rod limited.

2300 Reactor thermal power at 995, maximum flow, rod limited.

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6 Sienificant Ooerational Events Date Time Event Unit 1 (Continued) 3/12 0900 commenced power ascension from 995 1000 Reactor thermal power at 100%, maximum flow, rod limited.

2100 Reactor thermal power at 995, maximum flow, rod limited.

3/13 0700 Commenced power ascension from 995 power.

0800 Reactor thermal power at 100%, maximum flow, rod limited.

3/ 17 2232 commenced reducing thermal power for turbine control valve test and SI's, and control rod pattern adjustment.

3/18 0230 Reactor power at 625 for turbino control valve test SI's and control rod pattern adjustment.

0325 Turbino control valve test, SI's, and control rod pattern adjustment complete, commenced power ascension.

0515 Reactor thermal power at 995 holding due to Xenon transient.

0610 Reducing thermal power due to Xenon transient.

0640 Reactor thermal power at 97% due to Xenon transient.

0730 Commenced PCIOMR from 975 thermal power.

1100 Reactor thermal power at 1005, maximum flow, rod limited.

1700 Reactor thermal power at 995, maximum flow, rod limited.

3/20 1500 Reactor thermal power at 100%, maximum fAow, rod limited.

3/23 2245 Commenced reducing thermal power to improve "R" factor and perform SI's.

2325 Reactor thermal power at 885, "R" factor in limits, increasing thermal power.

2345 Reactor thermal power at 94% holding for SI 4 3. A.2 (CRD Exercise).

3/24 0122 SI 4 3. A.2 complete, commenced power ascension.

0200 Reactor thermal power at 965, holding for Xenon transient.

0955 Commenced power ascension from 965 thermal power.

1000 Commenced PCIOMR from 98%, thermal power.

1300 Reactor thermal power at 100%, maximum flow, rod limited.

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7 Sinnificant Ocarationni Events l

l Date Time Event L

l Unit 1 (Continued) 3/26 0555 "B" string low-pressure heaters isolated, reduced thermal power to 875 0558 "B" string low-pressere heater back 19. service, reacter i

power at 87$.

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0600 "B" string low-pressure heater isolated, reducing thermal power.

0900 Reactor thermal power at 855 "B" string inw-pressure heater limited.

0930 "B" string low-pressure heaters back in service, commenced power ascer.ston.

1030 Commenced PCIOMR trom 905 thermal power.

1430 Reactor thermal power at 1005, maximum ricw, rod l

limited.

3/31 2200 Commenced reducing thermal power for a control rod sequence exchange.

2400 Reactor thermal power at 575 for control rod sequence exchange.

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Data Time Event I

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Unit 2 i

3/1 0001 Reactor power at 945, maximum flow, rod limited.

0700 Reactor power at 931, maximum flow, rod liatted.

1112 Commenced reducing thermal power to 605 to extend the fuel cycle into August 1984.

1300 Reactor thermal power at 615, dorated to extend fuel cycle.

l 1600 Reactor thermal power at 625, dorated to extend fuel l

cycle.

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I 3/3 2300 Reactor thermal power at 635, dorated to extend fuel cycle.

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3/9 2300 Reactor thermal power at 645, dorated to extend fuel cycle.

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3/12 1500 Reactor thermal power at 635, dorated to extend fuel I

cycle.

j 3/27 0700 Reactor thermal power at 621, dorated to extend fuel cycle.

3/31 2400 Reactor thermal power at 621, dorated to extend fuel i

cycle.

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l Sinniffonnt Ocerationni Events l

l Date Time Event Unit 3 3/1 0001 End-of-cycle 5 refuel outage continues.

3/31 21600 End-of-cycle 5 roruel outage continues.

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10 AVER AGE D \\lLY UNIT POWER LEVEL 50-259 DOCKET NO, UNIT I

DATE 4/1/84 COMPLETED DY Te11 Thon TELEril0NE 205/729-0834 MONill March 19R4 D\\Y AVERAGE DAILY PohtR LEVEL DAY AVElt AGE DAILY PohER LEVEL OlWe Neil opge.Seo 1075

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AVERAGE D Alb' UNIT POWER LEVEL DOCKET NO, 50-260 UNIT -

DATE 4/I/84 C0\\lPLETED BY Ted Thon 205/729-0834 TELEPHONE MONTil March 1984 DAY AVER AGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL (MWe Net) t MWe NetI g

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INSTRUCilONS i

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i OPERATING DATA REPORT l

i DOCKET NO. 50-259 DATE 4/1/84

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j COMPLETED BY Ted Thom TELEPilONE 205/720-0834 i

OPFR ATING STATUS j

l. Unit Name.

Browns Ferry - 1 Notes j

2. Reporting Period: March 1984

3. Licensed Thermal Power (MWt):

1293 t

4. Nameplate Rating (Gross MWe):

II52 1065

5. Design Electrical Rating (Net MWe):

6. Masimum Dependable Capacity (Gross MWe): _1098.4 1065 j

7. Masimum Dependable Capacity (Net MWe):

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8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Gi.e Reasons:

N/A i

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9. Power Lesel To hhleh Restricted.lf Any (Net MWe):

N/A j

10. Reasons For Restrictions.lf Any-

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This Month Yr. to Date Cumulatise

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11. llours in Reporting Period 744 2.184

_84,746 t

12. Number Of flours Resetor Was Critical

_733.75 1,942.28 51,748.40

13. Reactor Resene Shutdown llours 10.25 225.40 6,010.42 l

14. Ifnuts Generator On.Line 715.28 1.846.38 50,564.02 I

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15. Unit Reserve Shutdown flours 0

0 0

16. Gran Thermal Energy Generated (MWill 2,279.594 5,268,558 143,826.237 L

17. Grow Electrical Energy Generated (Mwil) 767.870 1,773,680

~47,419,300 i

18. Net Electrical Energy Generated (MWil) 749.475 1,727,016

_46,052,343

19. Unit Senice Factor 96.1 84.5 59.7 I

96.1 84.5 59.7

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20. Unit Availability Factor 94

/4.4 at.u 21 Unit Capacity Factor (Using MDC Nett

22. Unit Capacity Factor (Using DER Nel) 93.6 74.2 51.0

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23. Unit forced Outage Rate 3.9 14.2 23.5 j

24. Shutdowns Scheduled Oser Nest 6 MonthsiT)pe.Date.and Duration of Eacht:

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26. Units in test Status It'rint to Commercial Operationi forecast-Achiesed INiiliLCHITICAllIY j

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OPERATING DATA REPORT DOCKET NO. 50-260 DATE 4/1/84 CO.\\lPLETED BY Tod Thom TELEPilONE 105/729-0834 OPERATING ST \\TUS t

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1. Unit Name:

Browns Ferry - 2 Notes

2. Reporting Period:

March 14R4

3. Licensed Thermal Power (SlWt):

3293

4. Nameplate Ratin2 (Gross SIWE):

1152

5. Design Electrical Rating (Net blWe):

10M

6..\\tasimum Dependable Capacity (Gross SlWe): 1098.4

7. Stasimum Dependable Capacity (Net SlWe):

1065

8. If Chan;es Occur in Capacity Ratings (ltems Number 3 Through 7)Since Last Report, Give Reasons:

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9. Power Lesel To Which Restricted.lf Any (Net SIWE):

N/A

10. Reasons For Restrictions.lf Any:

N/A i

This hionth Yr..to.Date Cumulatise

11. Ilours in Reporting Period 744 2,184

. 79,687

12. Number Of floun Resctor Was Critical 744 1,893.84 51,858.02 0

290.16 14,190.3Z

13. Reactor Reserve Shutdown llours

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14. Ilours Generator On Line t

15. Unit Resene Shutdown flours

16. Gross Thermal Energy Generated ISIWil) 1.574.676 5.034.528 145,179,573

17. Grow Electrical Energy Generated (5thil) 511.890 1,651,170 48,248,458

18. Net Electrical Energy Generated (SIWH) 499,613 1,606.188 46,864,791 1

17. Unit Senice Factor

.100 84.7 63.2

20. Unit Asailability Factor 100 84.7 63.2 63.1 69.1 33 2

21. Unit Capacity Factor IUsing SIDC Net)

22. Unit Capacity Factor IUning DER Net) 63.I 69.I

_ 55.2

23. Unit Forced Outage Rate 0

11.2 24.4

24. Shutdowns Scheduled Oser Nest 6 Stonths ti>pe. Date.and Duration of Eacht:

July 1984 - Refuel l

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25. If Shut Down \\t End Of Report Period. Estimated Date of Startup:

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26. Uniis in Test StatusIt'rior to Cmnmercial Operationo Futeca,t Achiesed I

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.0PERATING DATA REPORT l

DOCKET NO. _50-296 DATE 4/1/84 i

CO.\\lPLI'TED ItY _Ted Thom TELEPl!ONE ?ns/720-0834 P

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j. bit Namei Browns' Ferry 3 l

2. Regiorijng Period:

March 1984 1

3. Licensed Thermal Power (Mht):

3293

d. Nameplate Rating (Gross MWel:

1152 j

$. Design Electrical Rating (Nel MWe):

1065 1098.4 l

6. Matirhum Dep'endable Capacity (Gross MWel:

i 1065

7. Matim' m Dependable tapactly (Net MWe):

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8. If Changes Occur in Capacity Ratino (Irems Number 3 Througli 7) Since Last Report.Clic Reasons:

N/A i

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9. power Lesel To Which Hestricted.lf Any tNet MWe):

N/A N/A

10. Reasons Fnt Restriellons. lf Any:

This Month Yr..to.1).ite Chniutatise i

744 2184 62.ll2 j

11. Ilours in Reporting I'eriod 0

0 43.087.80 2

12. Number Of Il surg Hesetor Was Critical 0

0 3,878.13 f

13. Henctor Rnene Shutdown flours f,TT9'3. 71 --

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,14. llours Generator On.Line

15. Unit Resene Shutdown llours 0

0 0

3

16. Crow Thermal Energy Generated l\\lWill 0

0

_ 126.307.7tl 0

0 41.597.620 17 Grow Electrical Energy Generated IMWill

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l 18 Net Electrical F.nergy Generated (MWlu 0

0 40.375.256

19. Unit Senice Factor 0

0 67.9 0

0

'67.9 l

20. Unit Asnilability Factor 6.0 0

0 1

21. Unit Capacity Factnr IUsing M1)C Net, 0

0 61.0

22. Unit Capacity Factor IUsing DER Netl 0

0 16.4 2.1. Unit rurced Outage Rate r

24. Shutdowns Schedal.d Oser Nest 6 Montln IT> pe.Due.and Dur.ition sif f.icht:

2.1. If Shne Down At I:nd Of I eport Perioil. L, tim.utd D.ite ni St.ntup:

26. Units in f est Status Prior lo Cennmercial ops ration p.

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-259 UNIT NAME 1

DATE 4/1/84 REPORT MONTil March 1984 COMPLETED BY Ted Thom TELEPHONE 205/729-0834

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Reactor scram due to possible bumping of panel 25-6A 275 3/10/84 S

B Derated for RTI 23 '(Feedwater Control; and turbine CV tests and SI's.

j 276 3/17/84 S

B Derated for turbine control valve g

tests and SI's, control rod pattern adjustment.

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F: Fin ed Reason:

Methem!:

Exhibit G. Instructi ms s

S.%heduled A-l'apupment Fa !ureIEmplarn) 1-Enual for Preparatam ot' Data B-mintenance or Test 2 EnualScrarn.

Entry Sheets ti>r Ixensee C-Ret'ueling 3-Autom.stic Scram.

Event Report t! ERI File INtrREG-D Regulat.wy Restractne 4-Otler iEaplam) 016lI I 4)perator Trainmgi I wenw Exananaanm i

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1 DOCKETNO. W 260 I

UNITSifUTDOWNS AND POWER REDUCTIONS UNIT NAME 2

DATE 4/1/84 COMPLETED BY Tod Thnm REPORT MO.VfHMarch 1984 TELEPHONE 205/729-0834 1

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Entry Sheets for Licensee C.Refucimg 3-Autimurc S ram.

Esen Repors tLLRIFdetNUREG-l I) Regular.wy Restracinn 44hher (E mplaan t 0161) 8 Opesas..: Tenning A I stenw I uunnatum 11AJrisontratex 5

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50-296 DOCKET NO.

UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT N AME 3

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. C b!ES FER.C LCCLEAR P!. ANT UNIT 1 BF EMSIL 30 CSSC EQUIPME';T ELECTRICAI. MAINTENANCE StTtARY

~

9/29/82 For the Month of March 19 84 l

Effect on Safei Action Taken Nature-of Operation of 3 Cause.of Results of To Preclude Date System Component Maintenance The Reactor I

Malfunction i

Malfunction Recurrence 1984

, 2/25 High-pres-Gland seal Replaced motor None FCV 73-16 not Motor grounded IIPCI None sure cool-exhauster per EMI-33 fully closed caus-- taken out of service ant inject -

ing steam to flow to repair ion on motor 3/2 Standby Diesel genera-Adjusted RPM None Drift Meter inaccurate None diesel tor "D" meter genera.or

,3/2 Standby Diesel genera-Replaced defec-None Bad switch Operator unable to fNone diesel tor "D" motor-tive micro-achievemaximumspeedj--

w generator operated switch potentiometer

'3/7 High pres-liPCI steam Torque switch None Unknown Valve not fully closed None sure cool-supply valve was adjusted ant per' EMI-18 injection 3/10 Control liS-85-47 CRD Replaced springs None Overwork of Notch override None e'

rod drive notch override switch inoperable t

~

^ 3/14 Unit Unit preferred Remove annuncia-None Undetermined Unit preferred supply None j

Preferred og set tor wires for abnormal alarm was 120V AC relay 13K per masked TACF 1-84-080-2S2 1

3/3 contain-Oxygen Analyzer Pump and motor None Suspected bear-Oxygen analyzer None ment sample inlet replaced ing problems inoperable inerting pump I

i'

l r.i p.

BR0'w?is FERRY !;UCLEAR 1*LANT UNIT 1

BFEMEIL30 4

CSSC EQUIPMENT ELECTRICAL !!AINTENANCE S001ARY f

9/29/82 1

For the Month of March 19 84 k:

l f Effect on Safe i

Action Taken l }

Nature of Operation of Cause.of Results of To Preclude i

Date System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1984

~

[3/24 Neutron IRM-E select Replaced switch None Cyclic fatigue None None monitoring switch per EMI-23 3/24 4kV shut-4kV breaker Changed capaci-Nonc Open capacitor Breaker did not None down tor on charging from normal use operate properly in boards and motor test position busses 3/25 Radiation Radiation Reversed rota-monitoring monitor 90-251 tion on CAM None Undetermined Monitor blowing L None y

motor fuses-i P

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CSSC EQUIP 1E:.T ELECT 31 CAL MAINTENANCE S120t\\RY

~

9/29/82 For the 5'$ nth of March 19 84 i

Effcct on Safe, Acti.an I.eken Nature of i

Operation of I Cause.cf Res.ults of f To Preclude

' Date !

Sv:ste:2 Co.ponent Msintenance The Reactor M;ilfunction Malfunction i Recurrence i ) 1984 l

f 3/9 Annunciator Annunciator Replaced None Card relay stick-Horn sticking None

& sequen-horn relay sounder card ing tial panel 9-5 events recorder 3/14 Reactor Relay RIB Replaced relay None Bad relay N/A None building panel 9-36 heating &

i ventila-tion i

w 3/22 Core spray 2B core spray Added oil to None N/A N/A

'None cooling pump lower bearing per EMI-64

{;

3/24 4kV shut-4kV breaker Tightened.

l None Loose trip Breakertripfreeon{None i,

down cleaned and mechanical link-first closing i

boards &

lubricated age i

busses mechanical

{

linkage l

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3/27 Reactor Surge tank low: Cleaned and lNone Envircamental Switch failed to None l lubricated l

conditions pick up on low level building Icvel switch

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closed

, level switch cooling j

mechanism j

water I

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BROWNS FERRY N" CLEAR PLANT UNIT 3

BF EMSIL 30

^EE'"

CSSC EQUIPMENT ELECTRICAL MAINTENANC;. SLW!ARY 9/29/82 For the Month of March 19 84 Effect on Safe Action Taken Nature of Operation of Cause.of Results of To Preclude j

Dat9 System Component Maintenance The Reactor Malfunction Malfunction Recurrence a

1984

. 3/6 Residual HEA relay Replaced coil None Cracked coil N/A Used different

]

4 heat 10A-KSB assembly spool type replacement 8

removal 3/6 Residual HFA relay Replaced coil None Cracked coil N/A Used different heat 10A-Kl8B assembly per spool type coil as removal SEMI-40 replacement 3/7 CO2 stor-CO2 storage Added freon None Slow leak None Expansion valve.

age, f' ire tank at U3 ordered protection diesel

& purging g

3/8 Residual HEA relay Replaced coil None Cracked coil N/A Used a different heat 10A-K15B assembly per spool type coil as re-i removal SEMI-40 placement

, 3/10 Reactor SCRAM reset Cleaned and None Dried grease and Switch sticks in None l

3 protection switch repaired switch dirt in switch group 1/4 reset I

position handle position handle position assembly 3/14 Reacter Relay IB Replaced relay None K/A N/A None j

building panel 9-36 per EMI-23 heating &

g

,I.

ventilatior

,1 I

J/IS Fuel oil Isolation Adjusted opera-None Broken spring N/A None valve ting arm on in limit switch ISV 18-653 limit switch

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[FEMIL30 g

unvWNS FERRY NUCLEAR l'LANT UNIT 3 CSSC EQUIPMENT ELECTRICAI. MAINTENANCE SDNARY

~

9/29/82 For the Month of March 19 84 3

)

Effect on Safe Action Taken i

Nature of Operation of Cause.of Results of~

To Preclude

'Dato System Component Maintenance The Reactor Malfunction Malfunction Recurrence 1984

.{3/24 Reactor 3A recirc Replaced motor None B phase open Suction valve would None l

{

water pump suction per EM1-18 not close recircu-valve

?

lation FCV 68-001 f

I 3/26 Reactor-RBCCW 3B Installed in-None N/A N/A None building motor board and out-closed board bearings cooling i

water-l

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CSSO EQUIPMENT ELECTRICAL !!AINTENANCE SDIMARY Appendix B 9/29/82 For the Month of March 84 gg Effect on Safe, Action Taken Nature of Operation of i Cause.of Results of To Preclude Dat*

System Component Maintenance The Reactor Halfiinction l

Malfianction Recurrence 1984

+3/19 4kV shut-Auxiliary re-Replaced relay None Material defect N/A None down boards lay board C coil mechanism and busses l

3/20 CO2 storage, Pump station Replaced printet None Bad printed cir-Trouble alarm None f

fire pro-kiddie panel circuit card cuit card XA-39-72A2 stayed in tection &

25 296 purging I'

3/29 High-pres-Diesel fire Replaced 12v None Improper sensor Alarm stayed in whil Installed corrg t sure fire pump voltage sensor with 24v attempting to. start. sensor _

protection sensor relay sensor pump from control room 1

e I

i

29 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 A.

Critical Path Activities 1.

P0392 CRD Scram Discharge Header Modification piping weld joint summary:

a.

Of 205 required 3/4-inch welds,150 are complete (73%).

b.

Of 28 required 1-inch welds, 16 are complete (57%).

c.

Of 76 required 2-inch welds, 37 are complete (49%).

d.

Of 4 required 3-inch welds, 3 are complete (75%).

e.

Of 24 required 4-inch welds, 16 are complete (67%).

f.

Of 10 required 6-inch welds, 6 are complete (60%).

2.

ECN P0392 Hanger / Support summary:

2 a.

Forty-seven locations require removal only; 25 of these are complete.

b.

Eighteen locations required removal and (new) reinstallation; none complete (2 started),

c.

Thirty-eight locations require new hangers; 6 of these are complete.

d.

Four locations require modification to the existing hanger; none complete.

e.

Twelve locations require inspection of the existing hangers; none are complete.

f.

Total number of hangers affected by P0392 work is 119 3

P0538 - All welds have been completed and are undergoing x-ray.

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30 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 B.

Refuel Floor:

A cold proof test was run on the overhead crane on March 1.

In-vessel visual inspection was completed on March 5 An ultrasonic test inspection was completed on March 7 on the jet pump hold-down beams. This inspection revealed no problems and resulted in the deferment of the changeout modification, PO450. MMI-34 was completed on the bridge crane on March 26.

C.

Balance of Plant All work was completed on "B" and "D" Residual Heat Removal (RHR) heat exchangers. Loop II of RHR was released to Operations on March 30 in order to change loops and allow for maintenance on Loop I components.

Maintenance work on A, B, and C condensers continued. Probolog work continued on vr tous equipment. Probolog work was completed on all six waterboxes with a total of 14 tubes requiring plugging.

Probologging cf 3B steam jet air ejector was completed with 4 tubes required plugging.

"A" and "C" string feedwater heaters were closed with "B" string being opened in preparation for work.

D.

Turbine On "C" low-pressure turbine, #1 through four couplings were aligned and are complete. The thrust bearings were assembled.

Pinch checks were performed and bearing caps were installed on #4, 6, and 8.

The #4 exciter coupling was aligned.

The auxiliary oil pumps on A, B, and C reactor feedpump turbine (RFPT) were run.

"A" RFPT was also aligned.

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31 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 E.

lESI IHSI began on March 13, 1984. By the end of the March report period, nine core spray and 13 RWCU identified welds were completed. Treatment of the recirculation system welds is continuing with 29 of 96 identified welds complete. Of the 147 identified welds, a total of 51 are complete at present.

F.

Other Mechanical Work 1.

EECW wall thickness measurements were made and completed.

Analysis found no minimum wall thickness problems to exist. This information allows the piping replacement modification to be deferred.

2.

Repair work on valve 3-74-67 was completed. The stem was found broken in two places. A segment of break area was cut for analysis. This analysis showed that the reason for the break was a result of overload, not fatigue. The valve was repaired and reassembled.

EMI 18 was run on March 25.

The valve passed Local Leak Rate Test (LLRT).

on March 26.

3 P0547 Replacement of Recircul. tion Valves - Work continued during the month. All work is complete except for one hanger that had not been previously addressed.

Completion of work is awaiting the revision of the wcrk plan to address the new hanger.

4.

Main Steam Relief Valves (MSRV's) - Parts list arrived from Target Rock. Five valves are onsite from Wyle Labs.

Wyle is to begin steam tests on three more.

Installation of MSRV valves is being deferred until completion of IHSI due to interferences.

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OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 F.

Other Mechanical Work 5.

Main Steam Isolation Valves (MSIV's) - Four valves require maintenance. These valves are "A" and "D" inboard and "A" and "C" outboard. This work is continuing and is approaching critical path.

6.

P0686 Control Rod Drive (CRD) rebuild room drain line - This work was put on hold until material delivery.

7.

P0666 Install 1" Bypass Line - This work was completed.

4 8.

L1970 EECW piping replacement on diesel-generator prefabrication work is continuing.

Prefabrication on units 1 and 2 diesel generator is 100-percent complete and prefabrication on unit 3 is 80-percent complete.

9 P0684 torus vacuum breaker work is continuing.

10.

P0501 Modify hanger support for RFWS All work completed except for insulation reinstallation.

11.

P0612 Install 1/2" Stainless Steel Flex Line - MSRV breaker installation will be required to complete hanger designs.

12.

Work is continuing on the functional test of the hydraulic anubbers.

13 P0689 Stainless Steel Overlay to 64-Series Valves - Work is continuing but moving slow due to manpower limitations.

14.

P0691 Modify 64-Series Valves - Work is continuing but moving slow due to manpower limitations.

15 P3130 Replace Flow Solenois Valves - Work is continuing.

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33 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 G.

Electrical / Instrumentation:

1.

Recirculation Motors "A" motor was run satisfactorily on March 1.

"B" motor was run satisfactorily on March 5.

2.

P0533 Torus Temperature Monitoring Devices - Work is continuing and is 87-percent complete excluding work on sequential events recorder.

Work plan is lacking on the recorder.

3 PO415 Temperature Instrumentation - Reactor feedwater nozzles. Work is 46-percent complete excluding thermocouple removal of STEAR 82-03 4.

P0322/323 Containment Pressure / Torus Level Transmitter Replacement -

Work is 60-percent complete and continuing.

5 P0392 (Instrument portion) - Work is 20-percent complete and continuing.

6.

PO422 Provide Redundant Class IE Protection - Work is 60-percent complete and continuing.

7 TIP Maintenance - Taken off schedule on March 4 until materials that are lacking arrive.

8.

PO479 Emergency Lighting - Work is 45-percent complete and continuing.

The previous mentioned work does not identify the new seismic hanger requirements on conduit.

9 P0672 Removal of associated wiring from Panels 25-5A, 6A, etc. - This work is 100-percent complete.

H.

Torus Torus sandblasting by Williams Contractor was completed on March 22.

Other work was as follows:

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34 OUTAGE MAINTENANCE & MAJOR HODIFICATION MANAGD!ENT MARCH 1984 H.

Torus (Continued) 1.

Torus internal modifications - Painting work was completed and heat cure treating began. Heat cure is complete in 7 of 13 bays, bays 6 thru 12.

2.

Attached piping and prefabrication work continued during March.

The scope of work increased from 377 supports to 454 with the receipt of I

additional drawings. At present, 228 supports are complete.

3 The floor was stripped and painted in the new turbine decontamination i

facility. Work was halted awaiting a work plan revision and due to 1

lack of manpower.

4

~

I.

Planning and Schedulina 1.

The main thrust of the planning and scheduling effort this report period has been the implementation of the unit 3 cycle 5 outage 1

schedule that reflects the remaining outage work activities. Work is still being stalemated in some areas due to lack of work plan

approval, j

2.

An effort is continuing on the preparation and scoping of work for unit 2 cycle 5 refueling outage.

J.

ALARA 1.

Provided continuous health physics coverage for radiography.

2.

Decontaminated 74-67 valve and stem.

3 Cleaned and deconned RWCU pump access areas.

4.

Installed shielding on RWCU lines and risers in drywell.

5.

Decontaminated "B" and "D" RHR heat exchangers.

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35 OUTAGE MAINTENANCE & MAJOR MODIFICATION MANAGEMENT MARCH 1984 J.

ALARA (Continued) 6.

Placed shielding on 28-inch recirculation suction lines and 12-inch l

risers to reduce exposure level.

J 7

Installed lead shielding in drywell at recirculation pumps and valves on Eley. 550'.

8.

Held pre-job briefing on IHSI.

K.

Administrative The overtime percentage for the month of February was 12-percent with 85,873 straight time hours and 11,650 overtime hours.

As of February 28, i

1984, year-to-date overtime percentage was 20-percent, 699,966 straight.

time hours and 173,850 overtime hours. The overall goal of the overtime percentage is 17-percent.

The Outage & Maintenance budget for February.'as 32,962,184 and the expenditures were $1,285,749 with year-to-date budget being $13,802,614 and actual year-to-date expenditures being $14,220,763 The capital budget was

$6,718,542 and the expenditures were 42,416,086 with year-to-date budget being $18,874,300 and actual year-to-date expenditures being $10.581,087.

05erall budget was $9,680,726 and the overall expenditures were $3,781,835 with year-to-date budget being 432,676,914 and actual year-to-date l

expenditures being 424,801,850.

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TENNESSEE VALLEY AUTHORITY Browns Ferry Nuclear Plant P. O. Box 2000 Decatur, Alabama 35602 APR 10198t.

Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:

Enclosed is the March 1984 Honthly Operating Report to NRC for Browns Ferry Nuclear Plant Unita 1, 2, and 3 Very truly yours, TENNESSEE VALLEY AUTHORITY

/b - )

G. T J es Pow-lant Superintendent Enclosures cc Director, Regien II INPO Records Center Nuclear Regulatory Commission Institute of Nuclear Power Office of Inspection and Enforcement Suite 1500 101 Marietta Street 1100 Circle 75 Parkway Atlanta, GA 30303 (1 copy)

Atlanta, GA 30389 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission Washington, D. C.

20555 (10 copies)

Mr. A. Rubio, Director Electric Power Research Instituto P. O. Box 10412 Palo Alto, CA 94304

+%

1i i An Loual Oppo# tunity Eruployce I

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