ML18024A897

Monthly Operating Rept for June 1979

ML18024A897
Person / Time
Site:	Browns Ferry
Issue date:	07/01/1979
From:	Green D, Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A896	List: ML18024A895 ML18024A897
References
MOR-790630, NUDOCS 7907170126
Download: ML18024A897 (40)

Text

TENNESSEE VALLEY AUTHORITY, DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT June 1, 1979 - June 30, 1979 DOCKET NUMBERS'50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:

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Plant Superintendent

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TABLE OF CONTENTS Operations Summary

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'I 1

Refueling Information

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Significant Operational Events

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Average Daily Unit'Power Level.

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13 Operating Data Reports

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16 Unit Shutdowns and Power Reductions.

19 Plant Maintenance

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22 Outage Section Monthly Report.

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35

0 erations Summa The following summary describes the significant operational activities during the reporting period.

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

There were eight reportable occurrences reported to the NRC during the month of June.

Untt 2 The unit scrammed once during the.month.

On June 20, the reactor was manually scrammed due to arcing on "C" phase generator bus leads.

The generator bus lead arcing problem was caused by a broken grill on the bus duct cooling system.

Unit 2 The unit scrammed once during the month.

On June 23, the reactor scrammed on turbine stop valve closure due to EHC master trip and reset system depressurizing during weekly surveillance instructions.

Unlt 3

The unit scrammed once during the month.

On June.16, the reactor was manually scrammed due to high temperature on. "A" recirculation pump motor upper guide bearing.

Fati ue Usa e Evaluation The cumulative usage factors for the reactor vessel are as follows:

Location Usa e Factor Unit 1 Unit 2 Unit 3 Shell at water line Feedwater nozzle Closure studs 0.18813 0.17378 0.12399 0.10962 0.09805 0.07472 0.00407 0.00287 0.00255 Note:

This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.

Common S stems Approximately 1.69E+05 gallons of waste liquid were discharged containing 1.68E-01 curies of activity.

Cooling towers 1, 2, 3, 4, and 6 were operational.

installation of new fillmaterial on Tower 5 was completed.

Refuelin Information Unit 1 Unit 1 is scheduled for its third refueling beginning on or about November 20, 1979, with a restart date of January 5, 1980.

This refueling will load additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel.

There are 764 fuel assemblies in the core.

The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies and two 8 x 8 R fuel assemblies.

Because of modification work to increase spent fuel pool

3 Unit 1 (Continued) capacity to 3471 assemblies, present capacity is limited to 720 assemblies.

With present capacity, Unit 1 does. not have full core discharge capability in the pool.

Unit 2 Unit 2 is scheduled for its third refueling beginning on October 8, 1980, with a scheduled restart date'of December 12, 1980.

Resumption of operation on that date will require a-change in technical specifications pertaining to the core thermal limits.

Licensing information in support of these changes wi11 be submitted to the NRC before the outage.

This refueling involves

~k replacing some more 7 x 7 fuel assemblies with 8 x 8 R (retrofit) assemblies.

There are 764 fuel assemblies in the core.

At the end of the month, there were 132 discharged cycle 1 fuel assemblies and 268 discharged cycle 2 fuel assemblies in the spent fuel storage pool.

The present storage capacity of the spent fuel pool is 1080 assemblies.

Present planning is to increase that capacity to 3471 assemblies.

With present

capacity, the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core siischarge capability in the pool.

Unit 3 Unit 3 is scheduled for its next refuel outage beginning on September 1,

1979, with a scheduled restart date of November 20, 1979.

This refueling will involve loading additional 8 x 8 R (retrofit)- assemblies into the core, torus integrity modifications, core spray piping modifications, EECW piping changes, feedwater sparger modifications, and LPCI modifications.

Resumption of operation following refueling will require changes in technical specifications pertaining to the core thermal limits.

Licensing information in support of these changes will be submitted before the refueling.

There are 764 fuel assemblies presently in the core.

There are 208 fuel assemblies in the spent fuel storage pool.

The present licensed

. storage capacity'f the spent fuel pool is 1132 assemblies.

Si nificant erational Events Unit 1 Date Time Event 6/01/79 0001 Reactor thermal power at 99%'(sequence "A"), steady state 6/02 6/09 0020 0230 0700 0119 0221 0930 1730 Reduced thermal power from 99X to 80% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99X, steady state Reduced thermal power from 99% to 70% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 6/16 2000 2230 Reduced thermal power from 99% to 80X for removal of "A" condenser circulating water pump from service for maintenance Commenced turbine C.V. tests and SI's 6/17 0006 1103 1106 1550 1600 2112 2300 Turbine C.V. tests and SI's completed, holding for "A" condenser circulating water pump maintenance "A" condenser circulating water pump maintenance completed and placed in service "B" condenser circulating water pump out of service for maintenance "B" condenser circulating water pump maintenance completed and placed in service "C" condenser circulating water pump out of service for maintenance "C" condenser circulating, water pump maintenance completed and placed in service Reactor thermal power at 99%, steady state 6/20 1220

1252, 1740 2038 Commenced reducing thermal power from 99% to shutdown due to generator problems

("C" 'phase arcing due to a broken grill on the bus duct r~oling supply)

Reactor scram no.

112 manual from 35% thermal power to accommodate generator maintenance Generator problems resolved, commenced rod withdrawal for startup (sequence "A")

Reactor critical no.

129

Si nificant 0 exational Events Unit 1

'ate Event 6/21 0523 0545 2000 2325 Rolled T/G Synchronized generator, commenced'power ascension Commenced PCIOMR from 60% thermal power Reduced thexmal power from 65% to 60% for control rod pattern adjustment 6/22 0120 0300 Control rod pattern established, commenced power ascension Commenced PCIOMR from 70% thermal'ower 6/23 0800 1150 1200 1230 Reduced thermal power from 92% to 75% to avoid rod block ("B" high pressure heaters isolation),

"B" high pressure heaters placed in service Rod block cleared, commenced power ascension Commenced PCIOMR from 82% thermal power 6/24 0830 2340 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 85% for turbine C.V. tests and SI's 6/25 0120 0725 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99%, steady state 6/27 1025 1402 1445 1447 Reduced thermal power from 99% to 50% for removal of "A" recirculation pump MG set for brush replacement "B" recirculation pump brought to 100% flow for thermal power increase from 50% to 65%

"A" recirculation pump MG set brush replacement completed, reduced thermal power from 65% to 50%

for placing "A" recirculation pump in sexvice "A" recirculation pump trip (manual) due to high vibration, holding thermal power at 50%

6/28 0335 1010 1030 1545 Placed "A" recirculation pump in service, commenced power ascension Reduced thermal power from 90% to 80% to avoid control rod block ("B" high pressure feedwater heater isolation)

Control rod block cleared, commenced power ascension Commenced PCIOMR from 90% thermal power 6/29 0230 2313

'eactor thermal power at 99%, steady state Reduced thermal power from 99% to 90% for turbine C.V. tests and SI's

Si nificant 0 erational Events Unit 1

Date Time Event 6/30 0015 1500 2400 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99%, steady state Reactor thermal power at 99%, steady state

Si nificant 0 erational Events Unit 2 Date TDte Event 6/01/79 0001'050 0218 0611 0745 0758 Reactor critical, with startup in progress in contra[.

rod sequence "A"

T/G available for operation Synchronized generator, commenced power ascension.

Reduced thermal power from 15% to 0% for turbine overspeed'rip Turbine ovezspeed trips completed Synchronized generator, commenced'ower ascension 6/03 2020 2030 Isolated "A" string high pressure heaters for ma'intenance (head gasket leak)

Commenced PCIOMR from 55% thermal power 6/04 6/05 1945 0330 1945 2105 "A" string high pressure heaters restored to service Reactor-thermal power at 80%, holding for 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> fuel soak Reduced thermal power from 80% to 70% for removal of "C!'eactor feedpump from service for maintenance "C" reactor feedpump out of service for maintenance 6/08 6/09

- 2210 0145 0430 Reduced thermal power from 70% to 50% for control rod pattern adjustment Control rod pattern established, holding for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced PCIOMR from 50% thermal power 6/10 0700 Reactor thermal power at 73%, holding for "C",reactor feedpump maintenance 6/16 0045 0300 0444 0530 Commenced turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, holding at 73%

thermal for "C" reactor feedpump maintenance Maintenance on "C" reactor feedpump completed, commenced power ascension from 73% thermal'power Commenced PCIOMR from 80% thermal power 6/17 0530 0855 0900 1500 Reactor thermal power at 91% holding due to high condenser back pressure (3.7" Hg.).

Two condenser cooling water pumps in service

("C" CCWP out of service for maintenance)

"C" condenser cooling water pump returned to service Commenced PCIOMR from 91% thermal power Reactor thermal power at 94%, rods limited (max. flow)

Significant Onerational Events Unit 2 Date Time Event 6/20 '150 "A" condenser cooling water pump out of service for maintenance 6/21 6/22 1300 1355 1440 2300 2200 Reduced thermal power from 94% to 82% for removal of "A" condensate booster pump from service for maintenance (seal water leak)

"A" condensate booster pump maintenance

complete, and placed in service.

"C" condensate booster pump out of service for maintenance "C" condensate booster pump maintenance completed, commenced power ascension from 82% thermal power Reactor thermal power at 94%, rods limited (max flow)

Reduced thermal power from 94% to 72% for removal of "B" reactor feedwater pump from service.for maintenance (speed indicator) 6/23 0020 0111 0443 0510 0800 0855 1318 1404 1433 1535

, "B" reactor feedpump turbine maintenance complete and in standby Reactor scram no.

81 from 72% thermal power due to turbine trip while testing master trip solenoid valves e

Commenced rod withdrawal "B" master trip solenoid valve replaced "C" reactor feedpump out of service for maintenance Reactor critical no.

94 (sequence "B")

"B" condenser cooling water pump out of service for maintenance Rolled T/G Synchronized generator Commenced power ascension.

"B" condenser cooling water pump maintenance complete and placed in service 6/24 1239 Holding at 72% thermal power for "C" reactor feedpump maintenance 6/25 0745 1350 1500 1700 1715 1740 214~

'228 Commenced power ascension from 72% thermal power "C" RFP placed in service Holding thermal power at 82% for "C" RFP vibration checks Reduced thermal power from 82% to 72% for removal of "C" RFP from service Reduced thermal power from 72% to 50% for maintenance on bus duct "C" RFP removal from service for vibration check Increasing thermal power'from 50% to 73% after bus duct maintenance complete Holding for "C" RFP vibration checks

10 Si nificant 0 erational Events Unit 2 Date Event 6/26 1705 1800 1835 2000 "A" CCW pump maintenance complete and placed in service "C" RPP maintenance complete and placed in service Commenced power ascension from 73X thermal power

'ommenced PCIOMR from 86% thermal power 6/27 1000 Reactor thermal power at 95%, rods limited (max flow) 2300 Reactor thermal power at 94X, rods limited (max flow) 6/28 0700 Reactor thermal power at 93%, rods limited (max flow) 6/29 0700 Reactor thermal power at 92%, rods limited (max flow) i5 ~

6/30 0530 0630 1330 1407 2400 Reduced thermal power from 92% to 70% for turbine C.V.

tests and. SI's Turbine C.V. tests and SI's completed, holding for RTI 23A (reactor feedwater pumps controls)

RTI 23A completed, commenced power ascension Commenced PCIOMR from 90X thermal power Reactor thermal power at 94%, rods limited (max flow)

~ae

11 Si nificant Operational Events Unit 3

Date T1laR Event 6/01/79 0001 2315 Reactor thermal power at 99%, sequence "B", steady state Reduced thermal power from 99% to 85% for turbine C.V. tests and SI's 6/02 0115 0500 Turbine C.V. tests and SI's completed, commenced po~er ascension Reactor thermal power at 99%, steady state 6/09 2305 Reduced thermal power from 99% to 80% for turbine C.V. tests and SI's, 6/10 0250 1005 1830 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 6/15 2155 2350 Reduced thermal power from 99% to 45% for control rod sequence exchange from "B" to "A" Commenced turbine C.V. tests and SI's 6/16 0110 0205 1030 1318 Turbine C.V. tests and SI's completed, holding for control rod sequence exchange Control rod sequence exchange completed, commenced power ascension, sequence "A"

Reducing power due to high bearing oil temperature on "A" recirc~$ ~tion pump Reactor scram no.

73 (manual) from 37% thermal power ("A" recirculation pump problems) 6/17 2039 Reactor at cold shutdown 6/26 2153 2253 Maintenance to "A" recirculation pump completed, commenced rod withdrawal for startup Reactor critical no.

83 6/27 1425 1502 Rolled T/G Synchronized generator, commenced power ascension in control rod sequence "A"

6/28 1320 Commenced PCIOMR from 60% thermal power

12 Si nificant 0 erational Events Unit 3

Dace Time Event 6/29 1120 Reactor thermal power at 81%, holding due to recirculation pumps mismatch flow 1330

.Recirculation pumps balanced, resumed PCIOMR 6/30 0018 0125 0530 2230 2400 Reactor thermal power at 90%, holding for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, resumed P CION Reactor thermal power at 95%, rods limited (max flow)

Reduced thermal power from 95% to 72% for control rod pattern adjustment Holding at 72% for rod pattern adjustment (1) Equipment malfunction

13 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

UNIT 50-259 COMPLETED BY TELEPHONE 205/729-6846 MONTH June 1

7 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

I 1029 DAY AVERAGE DAILYPOWER LEVEL (MWe-iVet) 999 17 18 5

9

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10 12 13 14 15 16 1063 1064 1061 1055 1065 1083 1056 1061 1056 1055 1054 1019 19 10 21

'74 25 26 27 28

'19 30 31 1051 597 447 804 910 1043 1 47 1053 753 868 1045 1032 INSTRUCTIONS On this format.!ist the average daily unit power level in Mme.Net for each day in the reporting ntonth. ( i>>npute to the nearest whole megawatt.

(9(17 )

AVERAGE DAILYUNITPOWER LEVEL DOCKET iVO.

Browns Ferry 2

DATE COMPLETED BY TELEPHONE 205/729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL

{MWe.Net)

I 184 DAY AVERAGE DAILYPOWER LEVEL (MWe-Valet) 1007 17 5

6 7

9

- ~

10 13 15 16 324 448 752 819 784 774 611 779 772 779 777 773 777 867 IS 19 20 21

'71

~4 23 25 26 27 28

'l9 30 31 1010 1017 1013 999 985 212 729 718 810 1010 993 991 909 INSTRUCTIOiNS On this tormat.!ist the average daily unit poiver level in M~Ve.Net for each day in the reponing inonth. Compute to the nearest whole megawatt.

I')/771

15 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

50-296 UNIT Browns Ferry 3

7/1/79 COMPLETED BY Ted Thorn TELEPHONE 205/729-6846 MONTH DAY AVERAGEDAILYPOWER LEVEL (MWe-iVet) 1077 DAY AVERAGE DAILYPOWER LEVEL (MWe-iNet)

-12 17 IS 6

7 S

9 10 12 13 14 15 16 1049 1053 1048 1048 1028 970 1046 1046 1041 1005 327 19 20 21 22 24 25 26 27 2S

'79 30 31

-13

-10

-13

-13

-12 140 600 860 977 INSTRUCTIONS On this format.!ist the average dailv unit piiwer level in ilIWe.Net for each dav in the reporting inonth. Ciimpute to the nearest whole megawatt.

('t/771

16 OPERATING DATAREPORT OPERATIiNC STATUS

l. Unit Name:

~ -

2. Reporting Period:

3. Licensed Thermal Power (MWt):

3293

4. Namephte Rating (Gross MWe):

S. Design Electrical Rating (Net MWe):

1065

6. Mcsimem Depeerhirle Capsciry (Gress MWei: ~3 4

Notes DOCKET NO.

DATE ~Z9 COMPLETED BY J5cu~raatt'ELEPHONE2JQL~846

7. Maxunum Depend b eC p

. (N il e)

S. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

8.. Power Level To Which Restricted, IfAny (Net MWe):

. 10. Reasons For Restrictions. IfAny:

This Month 7.77 1.1. Hours ln Reporting Period

12. Number Ot'ours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line

15. Unit Reserve Shutdown Hours 0

16. Cross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 97.7

20. Unit Availability Factor

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Refuel outa e November 20 1919 Yr:to.Date 4,343 3,744.09 175.08 3640.84 0

10 879 112 3,595,820 3,501,966 83.8 83.8 75.7 75.7

5.9 Each)

Cumulative 43 081 23,975.68 4 74.21 23;332 '8 61 651 784 20,413,820 19,808,186 54 '

54.2 43.2 43.2 36.6 s

25. IfShut Down At End Of Report Period, Estimated Date of Startup:

26. Units In Test Status(Prior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY CORI AIER CIA L OPERATION (o/77)

17 OPERATING DATAREPORT DOCKET NO.

DATE ~~7 COMPLETED BY TELEPHONE 205 7

-6846 OPERATING STATUS I. Unit Name:

2. Reporting Period:

7

3. Licensed Thermal Power (MWt}:

4. Nameplate Rating (Gross MWe):

5. Design Flectrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

1065 Notes

.8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

.,9. Power Level To Which Restricted, IfAny (Net hAVe):

10. Reasons For Restrictions, lfAny:

This Month Yr:to.Date Cumulative 712.27 7.73 702.55 3 3

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,J I. Hours ln Reporting Period

12. Number Of Hours Reactor Was Critical 3 581.44

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line IS. Unit Reserve Shutdown Hours

17. GrnssEteeirieel Energy Genernred (EtWH)

~576 550 3 434 130

18. Net Electrical Energy Generated (MWH) 3,346,437

19. Unit Service Factor 97.6

20. Unit AvaihbiiityFactor 80.0

21. Unit Capacity Factor (Using MDC Net) 72.4

22. Unit Capacity Factor (Using DER Net) 72.4

23. Unit Forced Outage Rate 2.4 1 5

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

20,299.73 11,542.69 53

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0 5

596 249 17 747 918 17,236,601 51.

42.

41.1

25. IfShut Down At End Of Report Period. Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY CO.'ll!tIERCIAL OPERATION (6)/77)

18 OPERATING STATUS OPERATING DATAREPORT DOCKET NO.

DATE COMELETED BY Den Green TELEPHONE ~6229=6846 Notes I. Unit AVame V

2. Reporting Period:

June 1979

3. Licensed Thermal Power (MWt):

3293

4. Nameplate Rating (Gross MWe):

S. Design Electrical Rating (Net MWe):

1065

6. Maximum Dependable Capacity (Gross hOVe):

ndable aci v et We:

7.. Iaxtmum Depe Cap t

(N M

)

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons'.

~ 9. Power Level To Which Restricted, IfAny (Net iVIWe):

.10.. Reasons For Restrictions, IfAny:

This Month Yr.-to-Date Cumulative 20 447 4 343 720 4,013.45 17,104.65

- 474.2 329.55 1434.96 245.8 0

0 0

1,337 338 455,910 12 099,904 4,049,550 48,251,286 15,817,050 15,350,910 440,927

3,945,722 91.6 81.7 63.1 85.3 57.5 70.5 57.5 85.3 70.5 3.9 Date. and Duration of Each):

i 1979

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical-

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line IS. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (ilIWH)

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net)

22. I)nit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type.

fuel outage Se tember

25. IfShut Down At End Of Report Period. Estimated Date of Startup:

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIALCRITICALlTY INlTIALELECTRIC1TY-COhlMERCIALOPERATION

<o/77)

UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT ItIONTII DOCKET NO 50 259 I)mens Fort l

.<<Ulll1i COMPI.ETEI) IIY TEI.LI'IIONE ~~<~M6 Vo.

Date Vl

~

I I

rr

~A Lh:crtscc

. Event Rcport 4 A ~

o ~

Q D

C +

Callsc h Corrective Action lo Prevent Rccorrcnce 84 6/9 Derated for turb1ne C.V. tests and SI's 85 6/20 16.88 Generator roblems "C"

hase archon 86 6/27 Derated for "A" recirc pump MG set brush re lacement F: Forced S: Scheduled

(

t/72)'eason:

A-Equipment Failure (Explain)

II.maintenance or Test C.Refueling D.Regulatory Restriction E.Operator Training 8; Liccnsc Examination F.Adminis tra t ive G-Operational Error (Explain)

I I.Other (Explain) 3 Method:

I Manual 2.Manual Scram.

3-Autonmtic Scram.

4.Other (Explain) 4 Exhibit G - Instructions for Preparation of Data Entry Sheets for l.icensee Event Report (LER) File (NUREG-OI 6 I )

5'xhibit I

~ Sante Source

UNITSIIUTDOWNS AND PO)VER REDllCTIONS REPORT h(ON'fll DOCKET NO. 50-260'I~

COhli'LE1EIIIIY q)II~oI,I l)atc

~II C

YE I

rh IIII Ch rr,I A

EJ Liccnscc

. EUI.'ltl Rcport Ec C~

Eh Eh

'lE

~II ill'Cr C ~

C CI E ~

CJ Cause & Currcctivc Acthhn to Prevc>>l Rccurrcnce 87 6/8 Derated for cont:rol rod pattern ad ustment..

88 6/23 17.45 Turbine trip while testing master trii solenoid valves.

Master trip solenoid valve 're laced.

89

~ ~

6/25 Derated for removal of "C" reactor feed um.for vibration checks.

90 6/30 Derated for turbine C.V. tests and SI's.

F: Forced S: Scheduled (ht/77).

Reason:

A.Equipmcnt Failure (Explain)

B.h(aintcna>>ce or Test C-Refueling D.Regulatory Restriction F.-Operator Training &, Uccnsc Examination F.Administrative G-Opcralll)llJI Error (Explallt)

II.Other (Explai>>)

3 h(ethod:

I.hlanual 2 hlanual Scram.

3.Autontatic Scram.

4.Other (Explain) 4 Exhibit G - Instrucllolls for Preparatto>> ol Data Entry Sheets for I icc>>sce Event Report (LER) File (NUREG-OI6I) 5 Exhibil I - Sa>>tc Source

UNITSIIUTDOWNS AND POWER REI)UCllONS DOCKET NO.

I)AYE ~Ll19 COMPLETE)) UY TEI.I:I'IIONE ~5~I~II~

NIU.

Ihlc rl

~A UU E) rr E)

E J

E)~ III Lll:coscc livcnt Rcpolt sr Cause 4 CIIIrcl.'Ilvc ALlloo III Prevent Rccurrcncc 96 6/15 Derated for control rod sequence exchan e

97 6/16 P

265.73 A

Upper gruide bearings on oA" recirc iuln motor dama ed.*

98 6/30 S

Derated for control rod pattern ad ustment

• DCR will be submitted to provide each recirc pump with independent high and low oil level alarms.

I I': Forced S." Scheduled

('I/77)

Reason:

A-Equipment Failure (Explain) 8-hlaintenance or Test C-Refueling

- D Regulatory Restriction II Operator Training 4 Liccosc Examination F.Administrative G.Operational Error (Explain)

I I.Other (Explain) 3 hlethod:

I hlanual 2.Manual Scram.

3.Autoolat ic Scram.

4.Other (Explain) 4 Cxhlblt G - Instroitioos for Preparatioo of Data Entry Sheets Ior I.iccnsce Event Report (I.ER) File (NUREC-OI 6) )

5 Exhibit I ~ Saute Source

CSSC E UIPMENT BRONNB FERRY NUCLEAR PLANTUNLT~

MECHANICAL MAINTENANCE

SUMMARY

For the Month of %

'June 19 79 Page 1 of 2

SYSTEM COMPONENT NATURE OP MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OP MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 6/1

!D'ir Comp.

Inner cooler Coolers leak ing None Worn out rub-ber seals around tubes Leaking air Installed new cool.

~

er bundles with ne~

gaskets 6/4 Control Bay Chiller Oil cooler Not function ing None Air trapped in oil cooler High temp reading Installed aut ti<

on oil return air vent 6/4.

6/5 6/7 Feedwate FCV 5-25 Control RCW lA RCW pump B Contro Oil cooler Bay Chil ler

.Blown pack-ing Inspect and clean cooler tubes Leaking exce sively None None None Loose nuts Plugged tubes Pilter proble pipe broken Excessive water leak High temp on oil return Excessive water leak Tightened nuts on packing Removed cooler heads and cleaned cooler tubes.

Re laced heads Cleaned filters ~

Replaced broken ~

i e 6/7 6/10 RCW HPCI 1A Rx. Bldg. Packing leak Booster pump outboard end Suction pump. Water leak at bottom shaft None None Loose nuts Loose nuts on flange Packing leak Packing leak Tightened nuts Stopped leak Tightened fla Stopped leak 6/10 Rx. Bldg. Floor drain Packing leak Drainage sump pump None Loose nuts Packing leak Replaced check valve 6/12 RCW Strainer bac wash drive shaft ster leak None Sheared pin None Installed new pin 6/12 RCW Inboard and

. Packing leak outboard pum None Loose nuts on packing Packing leak Tightened packing Stopped. leak

CSSC E UIPHENT BRCUNE FERRY NUCLEAR FIANTUNIT~

HEQiANICAL MAINTENANCE SUHHARY For the Month of

'June 19~1 Page 2 of 2

DATE SYSTEH COHPONENT 6/13 Ventila-Air washer tion screens NATURE OP

~ HAINTENANCE Dirty screen EFPECT ON SAFE OPERATION OP THE REACTOR None CAUSE OP HALPUNCTION Operation RESULTS OF HALPUNCTION None ACTION TAKEN TO PRECLUDE RECURRENCE Cleaned screens 6/14 CRD 6/20 RCIC 6/20 Ventila-tion 6/20 RCW 6/25 RCW

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CRD pump 1A Isolation valve 71-570 Board room supply filters Outboard oiler bearing 1A RCW Booster pump Needs oil added Steam leak HHI 37 Leak around packing Packing leak None None None None None Oil level low Loose. nuts on packing Dirty filters Loose nuts bad packing Defective packing None Packing leak Improper ventilation Water leak Water leak Added oil to proper level Tightened packing stopped leak Changed filters Tightened packing Stopped leaks Replaced packing Stopped leak w'

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 2

MECHANICAL MAINTENANCE

SUMMARY

For the Month of "

June 19 79 Page 1 of 2 DA,TE SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF HALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 6/1 Rx. Water Recirc.

Valve 68-505 6/1 Condensate 2B pump Excessive water leak Packing leak None None Loose packing Water leak Mechanical seal Water leak Replaced with a new mechanical seal Replaced with new packing 6/1 Stator Cooling Water 2A pump inboard Seals leaking None Seals worn out Water leak around too much clear-seals ance on wear rin s Installed new bear-ings, seals, head

gaskets, wear rings 6/2 6/3 6/5 Feedwater Control Moisture Separator Moisture Separator Valve 221F 2CI pump 2A2 pump Missing parts Seals leaking Seals leaking None None None Parts missing from valve Loose packing Plug missing from seal Valve not working Water leak around packing Water leak Replaced 1/4 color flow valve guts Tightened nuts Stopped leak Installed with a new plug 6/6 6/8 Stator Cooling Water 2B pump Condensate 2A booster pump Seals leaking Water leak'one None Seals worn out Bad wear rings Broken nipple below valve Water leak at seals Water leak Installed new bear-ings, seals, head askets wear ri s

Replaced with n 1/4 nipple 6/8 RCW Heat exchanger Inlet line plugged None Line plugged up Preventing water from getting to heat exchan er Blew out line 6/9 RCW Platform drain Unit 2 Drain plugged None Drain stopped up Improper drainage Cleaned out drain

CSSC E UIPMENT BRGWNS FERRY NUCLEAR PLANT UNIT MECHANICAL MAINTENANCE SUE&fARY DATE SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION Page 2 of 2 RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 6/12 CRD 2A CRD pump Needs oil added None Low oil level Possible malfunction Added oil.

Checked for leaks 6/22 High Pres-2-26-757 isola-sure Fire tion valve Protection Packing leak None Loose packing Mater leaking around Tightened packing packing Stopped leak 6/23 Rx. Feed-water 2C feedpump Discharge check valve sticking open

None, Dirty check valve Check valve sticking Disassembled, open cleaned and repai~

and installed

CSSC E UIPMENT ERONNE FERRY NUCLEAR FIANTUNIT~

hKQlANICAL MAINTENANCE SURGERY For the Month of

• June 19 79 Pa;el af 2 DATE SYSTEM 6/2 RCW COMPONENT Heat exchanger NATURE OF MAINTENANCE Steam leak EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION Leaking valve RESULTS OF Causes room temp.

alarm to come on Component 9-3 ACTION TAKE TO PRECLUDE RECURRENCE Repaired leak on heat exchanger,.

6/7 Fuel Pool Filter Demin.

3A cooling pump Noise in pump None Defective parts in pump Excessive vibration and packing leak Rebuilt pump Replaced shaft a~

bearings 6/8 CRD 6/9 RCW "A" Exhaust Filter 3B inboard pump Dirty filter Packing leak

None, None Filter stopped up Loose nuts on packing Improper filter Water leak around packing Cleaned and replaced filter Tightened nuts stopped leak 6/11 Diesel Gen. Bldg.

Heating and Vents 3C diesel gen.

Coolers dirty None Mud stopped up coolers r

Overheating of coolers Cleaned both coolers, Replaced heads using new gaskets 6/13 6/15 Condensate 3D vessel Demin.

Equip.

Ac-. Rx. Zone cess Exhaust Fan B

Leaking head gasket Improper closing of damper None None Defective man-hole gasket Fan windmilling backwards when a fan is running Leaking water Improper ventilation Replaced manhole gasket Checked acd ad]ud dampers 6/18 RCW RCW strainer Dirty straine None Dirty strainer None Cleaned and replaced strainer 6/18 SLC SLC 63-7B Replacement of support brack-ets None Pipe vibrating Excessive pipe vibration Tightened loose brackets

BROHNS FERRY NUCLEAR PIANT UNIT 3

MECIIANICALMAINTENANCE

SUMMARY

DATE SYSTEM COMPONENT g ~

NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION Page 2 of 2 RESULTS OF 5IALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 6/19 Feedwater Control FCV 32-63 Valve sticks while closing None Valve sticking Improper closure of valve Applied penetrating oil and worked valve several times 6/21 Ventila-tion Bus duct cool-ing filters MMI 37 None Dirty filters '-

Improper. ventilation

. Removed and steam cleaned filters 6/22 Condensate Demin.

"F" vessel elements Change filter Replace heads with new gas-kets None Dirty filters Leaking gaskets Leaking 'gaskets Filters clogged Changed out filte Replaced gaskets on heads

CSSC E UIPMENT BRONNE PERRY NUCLEAR PLANT UNIT Common

&KQQNICALMAINTENANCE SUMfARY DATE SYSTEM 6/1 RHRSW COMPONENT "A" 3 pump EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR Rebuild pump None CAUSE OF MALFUNCTION Pump worn out shaft broken RESULTS OF MALFUNCTION Pump out of service ACTION TAKEN TO PRECLUDE RECURRENCE Rebuilt pump Replaced with new parts 6/1 Aux. Boil-er Feed-water Pump "B" feedwater pump Leaking pack-None ing Blown seal Packing seal leaking Replaced old seal wit)t new one 6/1 Aux. Boil-er "A" boiler Small water leak None Loose head on boiler drum Water leaking from head Tightened bolts on yoke, stopped leak 6/1 CCW 3C pump Lub seal leaking None Bad packing in pump Water packing leak Repacked pump Stopped leak 6/4 6/5 RHRSW

~ m+

I Main Steam Bl pump FCV-1-168 Packing blow None Packing leak None Unknown Unknown Leaking at pack-ing None Tightened packing Stopped leak Replaced valves 6/7 Demin.

Water "C" Water pump Packing leak None Unknown Water leak

,Tightened packi g

6/9 Off-gas Vent Tubing Replace hose None on fan Unknown None Replaced hose on fan 6/9 6/1 6/2 Fire Protec-tion Ventila-tion Ventila-tion "B" fire pum Chem.

Lab ai handling fil ters Air handling filters Packing leak MMI 37 MMI 37 None None None Blown packing Filters. need changing Filters need changing Watei leak None" None Repacked pump.

Stopped leak Changed filters Cleaned filters

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CSSC E UIPHENT BROKER FERRY RBCLEAR PLARY 'UliYY 2

-ELECTRICAL HAINTENANCE SIMMARY For the Honth of June 19 79 Page 1 of 2 Date

'System Component Nature of Haintenance ect on a e Operation of The Reactor.

'ause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 5-23-79 Not I

pre-viously report-ed RCIC Electronic overspeed monitor Defective

'overspeed monitor '

None Electronic* over-. Electronic over-speed monitor speed inoperable failed Replaced electronic overspeed monitor.

Checked OK.

TR.

137802 5-29-79 Not pre-viously report-ed Control rod drive CRD 02-39 CRD withdraw Not applicable solenoid coil cycle Failed solenoid CRD withdraw cycle valve coil inoperable Replaced solenoid valve coil.

Checked OK.

Functionally TR 124783 6-1-79 RCIC Electronic overspeed monitor Defective overspeed monitor None Electron'ic.over-RCIC inoperable, speed monitor couldn't reset trip failed

'oil Repaired overspeed monitor.

Tested OK.

TR 124701 BFRO 260/7912 6-4-79 Re"ctor core iso lation cooling RCIC turbine speed control Speed control Not applicable inoperable Hagnetic'pickup Turbine overspeeding shorted due to bearing failure Replaced magnetic pickup.

Performed EHI 37 Checked OK

.TR 124735 and 124739 6-4-79 Control HS-85-48 (rod rod drive notch switch)

Switch inop-erable Not applicab3.e Failed switch nable to properly otch rods Replaced switch, verified rods notched properly.

TR 124758

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CSSC E UIH'KNT BROIPifE FERRY UUCLEAR PLPIlY UllIY 3

ELECTRICAL MAINTENANCE SRlMARY For the Month of June 19~

Page 2 of 2 Date System Component Nature of Maintenance ecton a e Operation of The Reactor

'ause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 6-23-79 RCIC HPCI RHR core spray cooling Testable check valves 71-40 75-26 74-54 74-68 75-54 73-45 Check Reed '

sw5tches for proper adju'st ment getting improper light indi-cation Not".applicable Reed switches

.out of adjust-'.

ment False indication of valve position Ad)usted switch for 74-54, replaced switch for 74-68, Tested OK.

Checked 75-26, 75-54, 71-40, and 73-43 OK.

TR's

122606, 131029, and 124495 6-25-79 4

~ ~

FCV 74-78 reactor head spray inboard isolation valve motor insulation Improper insulation'ot applicable Improper insula tion'one Replaced motor with one having RH in'pula-

tion, TR 7478 6>>28-79 RCIC Speed indica-No speed indi-None tion cation when running SI Open wires',at magnetic speed pickup RCIC inoperable Repaired magnetic.

pickup. " Ran SI to verify RCIC operable.

TR 122698

CSSC I'IBKNT BRONHS FERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE

SUMMARY

FOR"ERE'NONXH OF f'

19-79 Unit 2 SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 6-13 Standby liquid control LI-63-1 Repair None Build<<up of Boron on sensing line Low indication None Unit 3 6-21 6-22 Neutron monitoring Control rod RPIS probe drive 34-35 Replace Replace None None Detector deple-tion Faulty 10's Low level indication None No 10's indication 'one 6-22 5-22 Control rod drive Control rod drive RPIS probe 42-19 RPIS probe 46-39 Replace Replace None None Faulty units switch Faulty thermo-couple No 04 indicati'on High temperature indication None None

35 OUTAGE SECTION MONTHLY REPORT June, 1979 Major work areas for the outage section consisted. of decontamina-tion efforts and modifications during the month of June.

Clean-up and decon efforts have been underway since the Unit 2, cycle 2 refueling outage.

Modification work was continuing on the hypochlorite building and power supply; the security system which includes the magnetic switch installation and "E" field modification; the installation of the high density storage racks; and the installation of the MOV boards for the LPCI modification.

Preparations were being made to receive fuel for the upcoming outages.

Information was gathered for the installation of the two direct, permanent NRC hot line telephones; and five temporary NRC lines were set upe The modification to the 4kV capacitor banks fo'r the cooling tower lift pump motor and CCV pump motors were completed and placed in service.

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