ML18024B099

Monthly Operating Rept for Oct 1979

ML18024B099
Person / Time
Site:	Browns Ferry
Issue date:	11/03/1979
From:	Learnen J TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024B098	List: ML18024B097 ML18024B099
References
NUDOCS 7911150462
Download: ML18024B099 (34)

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I TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT October 1, 1979 - October 31, 1979 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:

lant Superintendent

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I TABLE OF CONTENTS Operations Summary

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Refueling Information i

Significant Operational Events

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Average Daily Unit Power Level

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10 Operating Data Reports

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13 Unit Shutdowns and Power Reductions.

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16 Plant Maintenance

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19 Outage Summary

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

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

There were eleven reportable occurrences reported to the NRC during the month of October.

There were three revisions to previous reportable occurrences reported to the NRC during the month.

Un2t 1 There were no scrams on the unit during the month.

Un2t 2

The unit scrammed once during the month.

On October 29; the reactor scrammed due to turbine trip on load rejection from accidental'rounding of the sudden pressure trip circuit.

Un1t 3 The unit was down for refueling the entire month.

(EOC-2)

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 0.00415 0.19816 0.00303 0.00261 0.13020 0.10293 0.17510 0.11306 0.07865 Note:

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

Common S stems Approximately 6.54E+5 gallons of waste liquid were discharged containing 9.68E-l curies of activity.

Refuelin Information Unit 1, Unit 1 is scheduled for its third refueling beginning on or about January 2, 1980, with a restart date of February 18, 1980.

This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, and LPCI modifications.

There are 764 fuel assemblies in the reactor vessel.

The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies, two 8 x 8 R fuel assemblies, and 252 new fuel assemblies.

Because of modification work to increase spent fuel pool 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 September 1, 1980, with a scheduled restart date of October 7, 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 will be submitted to the NRC before the outage.

This refueling involves replacing some more 7 x 7 fuel assemblies with 8 z 8 R (retrofit) assemblies.

There are 764 fuel assemblies in the reactor vessel.

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.

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 discharge capability in the pool.

Unit 3 Unit 3 began its second refuel outage on August 24, 1979, with a scheduled restart date of December 6, 1979.

This refueling involves loading additional 8 z 8 R (retrofit) assemblies into the core, MSRV tailpipe routing, core spray piping modifications, 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 has been previously submitted.

There are no fuel assemblies presently in the reactor vessel.

There are 764 assemblies from the cycle 2 core, 208 discharged cycle 1 fuel assemblies and 144 new fuel assemblies in the spent fuel storage pool.

The present

4 I'torage capacity, of the spent fuel pool is 1528 assemblies.

With present,

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

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l Si nificant 0 er'ational Events Date Time Unit l

Event 10/01/79 0001 0037 0700 a

Reactor thermal power at 58%, holding for control rod pattern adjustment Control rod pattern adjustment completed, commenced power ascension Commenced PCIOHR from 75% thermal power 10/02/79 0700 2045 Reactor thermal power at 100%, steady state Reduced thermal power from 100% to 75% for removal of "A" reactor feedwater pump from service due to high vibration 10/03/79 1500 "A" reactor feedwater pump tagged out of service for maintenance (replacement of rotating assembly) 10/08/79 2215 "A" reactor feedwater pump maintenance completed and pump placed in service, commenced power ascension from 75% thermal power 10/09/79 0030 2300 10/11/79 1235 1900 Commenced PCIOHR from 82% thermal power Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 50% for removal of "B" reactor feedwater pump from service (replacement of rotating assembly) and control rod pattern adjust-ment Control rod pattern adjustment completed, commenced PCIOHR from 50% thermal power 10/14/79 1500 Reactor thermal power at 75%, holding for "B" reactor feedpump maintenance 10/15/79 2130 2230 "B" reactor feedpump maintenance complete and pump placed in service, commenced power ascension Commenced PCIOHR from 90% thermal power 10/17/79 0030 10/20/79 0030 0110 0255 1500 Reactor thermal power at 100%, steady state Reduced thermal power from 100% to 90% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOHR from 93% thermal power Reactor thermal power at 99%, steady state 10/21/79 1500 Reactor thermal power at 98%, rod limited (max. flow)

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Si nificant'0 erational Events Date Time 1 (Continued)

Event 10/23/79 1500 10/25/79 1500 10/27/79 0001 0105 0830 0845 1105 1500 1850 1910 Reactor thermal power at 98%, rod limited (max. flow)

Reactor thermal power at 97%, rod limited (max. flow)

Reduced thermal power from 97% to 50% for recirculation pumps MG set brush replacement "B" recirculation out of service from MG set brush re-placement "B" recirculation pump MG set brush replacement completed and pump placed in service "A" recirculation pump out of service for MG set brush replacement "A" recirculation pump MG set brush replacement completed and pump placed in service, commenced power ascension from 50% thermal power Reactor thermal power at 65%, holding for control rod pattern adjustment Control rod pattern adjustment completed, commenced power ascension Commenced PCIOMR from 80% thermal power 10/29/79 0700 10/31/79 2400 Reactor thermal power at 97%, rod limited (max. flow)

Reactor thermal power at 97% rod limited (max. flow)

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Si nificant 0 arational Events Unit 2 Data Talma Event 10/01/79 0001 Reactor thermal power at 99%, sequence "A", steady state

'I 10/05/79 0312 0430 0700 2345 Reduced thermal power from 99% to 89% for condensate demineralizer backwash and precoat Condensate, backwash and precoat completed, commenced power ascension Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 85% for turbine C.V. tests and SI's 10/06/79 0410 0430 1330 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 92% thermal power in contxol rod sequence "A"

Reactox'hermal power at 99%, steady state 10/12/79 2105 Reduced thermal power from 99% to 55% for "B" recircu-lation pump MG set brush replacement 10/13/79 0112 0225 0251 0330 0930 2300 "B" recirculation pump placed in service, "A" recircu-lation pump removed from service for MG set brush replacement "A," recirculation pump placed in service, commenced power ascension from 55% thermal power Reactor thermal power at 85%, holding for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed; commenced po~er ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 10/20/79 0105 0210 1500 Reduced thermal power from 99% to 95% for control xod drive exercise Control rod drive ezercise completed, commenced power ascension Reactor thermal power at 99% steady state 10/21/79 2350 Reduced thermal power from 99% to 90% foz turbine C.V.

tests and SI's 10/22/79 0030 0700 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99%, steady state a

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Si nificant Operational Events Date Time Unit 2 (Continued)

Event

. 10/25/79 1500 10/26/79 2335 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 85% for turbine C.V. tests and SI's 10/27/79 0130 0510 2300 10/29/79 1408 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 93% thermal power Reactor thermal power at 99%, steady state Reactor scram no.

86 on load rejection due to (1) inadvertent grounding of sudden pressure trip circuit

'10/30/79 0550 0942 1101 1124 2130 Commenced rod withdrawal Reactor critical no.

98 Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 55% thermal power in contxol rod, sequence "B"

10/31/79 2400 Reactor thermal power't 82%/PCIOMR in progress

Si nificant 0 erational Events Date Tfme Unit 3

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Event 10/01/79 0001 Unit shutdown with refueling operation for cycle 3 fuel in progress 10/31/79 2400 Refuel outage continues Personnel error (1)

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AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

11/03/79 COilIPLETED BY TELEPHONE 205/729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

I 885 DAY AVERAGE DAILYPOWER LEVEL QOVe.Net)

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1059 17 5

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8 10 12 13 14 15 16 1021 822 854 860 855 849 854 1035 1051 829 729 803 808 806 931 18 19 20 21 22 23 24 25 26 27 28 29 30, 31 1057 1059 1042 1044 1039 1039 1037 1032 1030 584-968 1030 1003 1004 INSTRUCTIONS On this f'ormat.!ist the avcra8e daily unit power tevei'in id!We-Net for each day in the reportin8 miinth. Compute to the nearest whole megawatt.

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j AVERAGE DAlLYUNITPO>VER LEVEL DOCKET NO UNIT DATE 50-260 13./03/79 COMPLETED 8Y Ted Thorn 205/729-6846 MONTH October 1979 DAY AVERAGE DAILYPOPOVER LEVEL (MWe.Net)

DAY AVERAGE DAILYPO>VER LEVEL (M)Ve-Net)

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106'9 17 10 12 13 l4 15 I6 1068 1071 1067 1066 1037 1064

'1075 1061 1069 1064 1014 968 1066 1070 1066 18 19 20 21 22 23 25 26 27 28 29 30 31

'066 1068 1064 1064 1063 1065 1069 1068 1071 1044 1067 625 275 748 INSTRUCTIONS Qn this format.!ist the average daily unit power level in Mme-Net for each day in the reporting 'tm)nth. Compute to the nearest whole megawatt.

AVERAGE DAILYUNIT'POWER LEVEL DOCKET NO.

UNIT 50-296 Bqi.owns Perry 3

1$/03/79 COMPLETED BY TELEPHONE 205/729-6846 MONTH October 1979 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)

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-5 DAY AVERAGE DAILYPOWER LEVEL (MWe Net)

-4 17 18 19 20 21 22 7.

8 10 13 15 16 5

24 25 26 27 28 29 30 31 INSTRUCTIONS On this format.!1st the average daily unit power level'in MWe.Net t'or each day in the repurring tnnnth. Ciunpute to the nearest whole megawatt.

{t)/77'I

~J OPERATIVG DATAREPORT

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DOCKET NO.

DATE ~};~

COMPLETED BY ~~rein TELEPHONE ~~ 846 OPERATING STATUS

1. Unit iVame

, 2. Reporting Period:

October 1

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross LIIWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Deoendable Capacity (Gross LXIWe)

7. Maxintum Dependable Capacity (Net MWe):

1098.4 1065 Notes

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

N/A

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

10. Reasons For Restrictions, IfAny:

This Month Yr:to-Date Cumulative 11.

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23.

24.

Hours In Reporting Period Number Of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (MWH)

Gross Electrical Energy Generated (AIWH)

Net Electrical Energy Generated (MWH)

Unit Service Factor Unit'vailabilityFactor Unit Capacity Factor (Using LWIDC Net)

Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate Shutdowns Scheduled Over Vext 6 Months (T Januar 1980 745 745 0

745 0

2 149 685 715 450 697,594 100 100

87. 9

87. 9 7 296 6,613.29 258.88

- 6495.36 0

19 440 265 6 400.780 6,230,965 89.0 89.0 80.2 80.2 4.8 ype, Date. and Duration of Each):

46 934 26 844.88 4 658.01 26186.70.

0 70 212 37 23 218 780 22,537 185 56.9 56.9 46.0 46.0 34.1

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

26. Units ln Test Status lPrior to Commercial Operation):

Forecast Achieved INIT)AL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

(')/77)

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OPERATING STATUS

1. Unit Name Browns Ferr 2

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

S. Design Electrical Rating (Net MWe):

7. Maximum Dependable Capacity (Net LIIWe):

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t OPERATING DATAREPORT Notes DOCKET NO.

DATE COMPLETED BY

'ELEPHONE A

5()~260 111103 79 Dot Green

~25~2~6846

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

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

10. Reasons For Restrictions, IfAny:

N A This Month Yr..to-Date Cumulative 11.

12.

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16.

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18.

19.

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21.

"2 23.

24.

7 296 725 '3 6 486.01 114.41 19.57 6363.37 723.73 0

0 2,285,110 19 135 300 6,443,690 771,430 6 279 598 752 656

87. 2

97. 1 87.2 97.1 80.8 94.9 80.8 94.9 1.8 2.9 (Type, Date. and Duration uf Each):

Hours In Reporting Period Number Of Hours Reactor Was Critical Reactor Reserve Shutdown Hours Hours Generator On-Line Unit Reserve Shutdown Hours Gross Thermal Ener y Generated (MWH)

Gross Electrical Energy Generated (MWH)

Net Electrical Energy Generated (MWH)

Unit Service Factor Unit Avaihbility Factor Unit Capacity Factor (Using MDC Net)

Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate Shutdowns Scheduled Over Next 6 Months 40"945 23 204.30 11,591.12

=22,431.23 0

62,587,088 20,757,478 20 169 762 54.8 54.8 46.3 46.3 37.9

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

26. Units In Test Status lprior to Commercial Operation):

Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Iol77)

15" OPERATING STATUS OPERATING DATAREPORT DOCKET iVO.

)g-296 DAIE ~i'>

COilIPLETED BY ~~ on TELEPHONE ~Q29=6846 Notes

1. Unit Name:

Browns Perry"3 October 1979

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Namephte Rating (Gross Alee):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

Iaxi um De endable Ca acit Net iiiIWe:

8.4 1065 75m ppy()

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

N/A

9. Power Level To IVhich Restricted, IfAny (Net iltWe):

10. Reasons For Restrictions, IfAny:

N/A N/A This illonth Yr.-to-Date Cumulative 11.

12.

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15.

16.

17.

IS.

19.

20.

21.

"2 23.

24 Hours In Reporting Period Number Of Hours Reactor >Vas Critical Reactor Reserve Shutdown Hours Hours Generator On.Line Unit Reserve Shutdown Hours Gross Thermal Energy Generated (LSIWH)

Gross Electrical Energy Generated (MWH)

Net Electrical Energy Generated (i%IWH)

Unit Service Factor Unit Availability Factor Unit Capacity Factor (Using ibIDC Net)

Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate Shutdowns Scheduled Over iVext 6 Months 745 0

0 0

0 0

0 0

0 0

0 0

7 296 5,224.60 421.40

- 5,174.05 0

5 724 8

5 231 290 5.091.972 70.9 70.9 65.5 65.5 8.4 (Type. Date. and Duration of Each):

23 '400 18,315.80 1.,526.81 17,904.03 0

51 876.371 16 998.790 16,497,160 76.5 76.5

66. 2 66.2 9.2

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

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

Forecast Achieved Janua 12, 1980 liNITIAL CRITICALITY INITIAL ELECTRICITY COiWDIERCIALOPERATION (9(77)

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UNITSIIUTDO'LUNS A4D PO)UER REDUCTIONS DOCKET NO.

UNIl NAhlE DATE COMPLETED BY TELEPIIONE Brovns Ferr 1

205/729-6846 NII.

Dale rI

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Licensee Event Report 4

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0 Cause &,.Corrective Action lo Prevent Rccurrcnce

. 0 791002 Derated due to "A" Rx feed'pump high vibration 100 791011 Derated to replace rotating element in "II" Rx feed um 101 791027 Derated to replace brushes in both recirc.

um MG sets F: Forced S: Scl)eduled

('t/77)

Reason:

A-EIIuipmcnt Failure (Explain)

Ii.hlai>>tenance or Test C-Refueling D.Regrdatory RestriI.lion I.Operator Training k. Liccnsc Examination F Adtninistlalivc G'Oper:ltlInlal Lrror (I'.xplain)

I I Olllcr ( I:xplalll) 3 hiethod:

I -hianual 2.hianuaI Scram.

3.Autoluatic Scram.

4 Other (Explain)

. Exltiblt G - Instructions for Preparation of Data Lnlry SiteI.ts lor LII.I.nsec Event Rcport (LER) Filo (NOREG-OI6l )

Exhibit I - Same Source

UNITSIIUTD01UNS AND POIUER REDUCTIONS 79 DOCKFT NO 50-260 COhiPLETEI) BY No.

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r 2 cA Licensee Event Rcporl 8

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~ Cause &. Corrective Action lo Prevent Rccurrcnce I.03 791012 crated for brush replacement in both recirc.

um MG sets 04 791029

21. 27 H

urbine trip on load reject due to personnel error while testing relays in switch ard F: Forced S: Scheduled Reason:

A.E<iuiprnent Failure (Explain)

B hiainte>>a>>ce or Test C-Refueling 0 Ret.olatory Restriction li Operator Tralninl, & Uccnsc Examination I'.Adndnistratlve C< Operational I:rror (I!xplain)

II Other (I xplain) 3 hicthod:

I hianual 2-hianual Scram.

3-Automatic Scram.

4-Other (Explain) 4 Exhibit G - Instructions for Preparation of Data Entry Sheets lor Licensee Event Rcport (LER) Fll<stNOREG-OI6li Exhibit I - Sante Source

UNITSIIUTDOWNS A4D POWER REDUCTIONS REPORTMONm october 1979 DOCKET NO 50-296 UNIq NAhIE Browns Ferr 3

COhIPLETED IIY Nii.

Dale rr Cl gr~Ir

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Licensee Event Rcport 4

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OC Cl9 Cr Cause &,Corrective Action to Prevent Recurrence 0'09 791001 745 Refueling F: Forced S: Scheduled

('I/77)

Reason:

A Equipment Failure (Explain) l).hlaitltenance or Test C-R fueling I) Itet,uiatory Restriction

l. Operator Trainint, & Liccnsc Examination F Adnllnisllativc C Opclatio>>al Lrror (Explain)

II.Other (I:xplain)

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3 h(ethod:

I -hlanual 2-hlanual Scram.

3-Automatic Scram.

4 Other (Explain) 4 Exhibit G - Instructions for Preparation of Data Entry Sheets tor Licensee Event Rcporl (LER> File (NVREC-OI6I)

Exhibit I Shanti Sour<<

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CSSC E UIPHENT BROfJNS FERRY NUCLEAR PLANT UNIT 1

?fECHAHICAL ffAIHTEN&CE SUKfARY DATE 10/6 SYSTEH Control Bay Chiller COHPONENT Raw Cooling Hater Valve EFFECT ON SAFE NATURE OF OPERATIOH OF HAINTENANCE THE REACTOR Packing leak None CAUSE OF ffALFUNCTION Loose nuts on packing RESULTS OF MALFUNCTION Leak on the raw cooling water valve ACTION TAKEN TO PRECLUDE RECURRENCE Tightened packing and stopped leak 10/1(

NPCI

)ruptured disk Dipk ruptured None Disk ruptured Ruptured HPCI disk Replaced with a new disk 10/l~

Rx. Bldg.

Doors Doors at RFP room Door will not lock None Loose screws Door would not lock Tightened all loo

screws, adjusted door, lubricated lock

CSSC E UIPMEHT BROWS FERRY NUCLEAR PLANT UNIT 2

MEalAHICAL MAINTENANCE

SUMMARY

For the Month of DA'IE SYS TEM 10/17 RllR COMPONENT Valve 74-52 NATURE OF lfAINTENANCE Packing leak EFFECT ON SAFE OPERATION OF TllE REACTOR Hone CAUSE OF MALFUNCTION Loose packing RESULTS OF MALFUNCTION Packing leaking ACTION TAKEN TO PRECLUDE RECURRENCE Tightened loose packing on valve 10/1 Ventila-tion 10/1 HPCI Battery board room filters Valve 73-35 Fi'lters need c3,caning Millpot open Hone None Dirty filters Pressure seal Valve not operable Changed out dirty

.i filters I

Removed bonnet and replaced seal 10/21 RllR Outlet valve 23-34 Valve leaking around valve stern Hone Packing leak Leaking valve Tightened packing gland and stopped leak

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CSSC E UIPllEHT BROWS FERRY NUCLEAR PLANT UNIT 3

hlECllANICALliAINTEHAHCE SUMHARY For the Honth of OCTOBER 19

.,4YTE SYSTEll COHPONEHT i O/1 High Pres-Valve 3-26-89 sure Fire Protec-tion NATURE OF llAINTEHANCE Valve leaking EFFECT ON SAFE OPERATION OF TllE REACTOR None CAUSE OF NALFUHCTION Loose bolts on nipple RESULTS OF MALFUNCTION Leak at nipple ACTION TAKEN TO PRECLUDE RECURRENCE Removed nipple, redoped and tightened i.o/1 High Pres-Valve 3-26-89 sure Fire Protection Valve leaking None goose bolts Nipple leaking Tightened up

bolts, stopped leak lo/1 RllR lo/1 CRD Suction pump CRD module 22-43 Leak 'at nipple Hill not hold pressure None None Bad nipple Loose cap Leak at nipple Loss of pressure in module Cut out and replaced old nipple Tightened cap and stopped leak lO/1 High Press "C" Fire pump Fire Protection Inspection None Pit inspection Strainer +as off pump suction Replaced pump and"-=~

strainer

BROWNS FERRY NUCLEAR PLANT UNIT 1[EC[IANICALMAINTENANCE SUM[ARY For the Month of October l9 79 DATE SYSTE[i 10/6 M[R COMPONENT All RUR pumps NATURE OF HAINTENANCE i[HI 29 EFFECT ON SAFE OPERATION OF Ti[E REACTOR None CAUSE OF MALFUNCTION To perform MMI 29 RESULTS OF

((ALFUNCTION MMI 29 ACTION TAKEN TO PRECLUDE RECURRENCE Performed HMI 29 on all pumps 10/1'iesel Generator All diesel generator HMI 30 None Heed to perform

.'HMI 30 MMI 30 Performed 5[HI 30 on all diesel generators I

BROVHE PERRY VVCLEAR PLRHY VVYY 1

ELECTRICAL 1fAINTENANCE Sm&fARY por the 1fonth of October 19 79

~ I Date System Component Nature of Maintenance ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunc tion Action Taken To preclude Recurrence 10/17/79 HPCI 1 PCV-73-27 (pump suction SP valve)

Valve Millnot Not applicable open Dirty limit switch contacts Valve inoperable Cl,caned contacts,.

tested OK.

TR 124154 LER BERO 50"259/7928 10/20/79 RCIC RCIC gland seal vacuum pump motor Motor grounded Not applicable Motor grounded Vacuum. pump inoper-able Replaced

motor, checked rotation, ~

verified proper operation, TR 1306S1

BRORWR PERRX NUCLEAR PLANT URLT 2

ELECTRICAL MAINTENANCE StMSRY Por the Month of October 1979 Date

'System Component Nature of Maintenance

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ect on a

e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To preclude Rocurrence 10/21/79 HPCI (PCV-73-35) test valve bypass con-densate motor leads Motor leads burned up Not applicable Failed leads Valve inoperable Replaced motor ariQ heater overloads, performed EMI 16 and EMI 1&, checke~

OK.

TR 138077

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BRORHR FERRF

'UUULEAR FLARE UULF ELECTRICAL MAINTENANCE SlMfARY'k.

Date 10/11./79 System Residual heat removal Component 3-FCV-74-77 (shutdown cooling HS isolation valve) motor Nature of Maintenance, Inspec t brushes and commutator

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ect on a

e Operation of The Reactor Not applicable Cause of Malfunction Oil and water in motor brushes disintegrated Results of Malfunction I

Motor inoperable Action Taken To Preclude Recurrence Motor removed and sent to service shop for reconditioning, returned and re-installed, performed EMI 18 and EMI 34, checked OK.

TR 139669 10/24/79 Ventila-tion Vent board B

emergency feed breaker 83 relay 83 relay failed Not applicable Burned up 83 relay Board would not transfer properly Replaced 83 relay, checked OK.. TR 125261 M

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CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 1

INSTRlkKNT MAINTENANCE

SUMMARY

FOQ THE MONTH OP October 19 79 DATE SYSTEM CO~PONENT NATURE OP 1$,INTENANCE EPFECT ON SAPE OPERATION OF THE REACTOR CAUSE OP 1fALF UNCTION RESULTS OP MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 10/5 Control rod drive PC-85-38 Calibration None Setpoint adjustment Alarm when pressure is correct None 10/19 Neutron monitor-ing Repair None Faulty quad trip card Light illuminates with no HI-HI TRIP in None 10/23 Primary contain-ment H E-76-38 2

Replace None Sensor degrada-tion Indicated high hydrogen with sample applied

~ ~

DCR to replace system

CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE Slk&1ARY FOR THE MONTH OF I

1 DATE SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF IfALF UNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 10/1 Radiation monitor-ing RM-90~136"A Calibrate None Setpoint Alarms on low sample values None 10/2 Neutron monitor-ing LPRM 2D-16-41 Repair None Faulty card False downscale indication None 10/3 Neutron monitor-ing LPRM 32-33B Repair None Faulty power supply Failed downscale None 10/5 Recircula-tion FQ-68-5 Calibrate None Gaid ad)ust Gain drift None 10/23 Primary contain-ment LI-64-66 Calibrate None Setpoint drift Indicated low None

CSSC E UIPMENT BROGANS FERRY NUCLEAR PLANT UNIT 3

INSTRIBENT MAINTENANCE Sl&MARY FOR TILE MONTl[ OF October 19 79 SYSTEM COMPONENT NATURE OF MAINTENANCE EPFECT ON SAPE OPERATION OF THE REACTOR CAUSE OP MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE

!I RECURRENCE 10/11 Primary contain-ment LI-64-54 Calibrate None Instrument drift Did not agree with redundant indicator None 10/11 Contain-ment inerting TI-76-15 Replace None Indicator failed, partia1ly shorted Palse indication None 10/17 Primary contain-ment TI-64-524 Calibrate None Zero shift Palse indication Hone 10/19 Primary contain-ment PM-64-37 Calibrate None Zero shift High flow indication None 10/26 Control rod drive RPIS 34-31 Replace None Faulty full-in switch Rod block None

29 OUTAGE SKiMARY October 1979 The Unit 3, cycle 2 refueling outage is approximately 12 days behind schedule and without any further delays, the projected completion date is December 4, 1979.

The feedwater sparger modification was completed October 22, with the removal of the feedwater sparger working platform.

The total time for completion of this modification from the time General Electric first installed the sparger platform was 37 days.

The completion of this modification was a major milestone as several gobs had to be completed bg the end of the sparger modification.

As for critical path, General Electric has completed the removal of the vibration instrumentation and the core plug removal and replacement.

Presently the flooding of the reactor pressure vessel and water cleanup is underway in preparations for core reload.

The LPCI modification work is still underway as testing revealed a

problem with the logic reset.

A revision to stop the automatic initiation of the RHR pumps, once logic is reset, will be made and the simulated auto-matic initiation portion will be repeated.

The Electrical Maintenance Instruction 7 on electrical boards has been completed.

The ASEA transformer changeout has been completed as all electrical tests have been performed.

Checkouts of the transformers and protective relays are in progress in preparations for back feeding the unit.

The turbine and generator maintenance is progressing well and is nearing completion in preparation for the generator air test.

30 r

I.

I OUTAGE

SUMMARY

(Continued)

Octobei. 1979 Major modifications that are essentially complete are the core spray piping changeout, the reactor watex clean-up tie-in to the 4" feedwater "A"

line, installation of the residual heat removal crosstie valve (74-150); and the installation of the MSRV tailpipe.

A major setback for the Unit 3, cycle 2 outage occurred on October 7, when the RHR "B" heat exchanger fell about 20 feet after a chain broke on the lifting hoist.

A complete inspection of the heat exchanger (shell,

tube bundle, and structural steel) and concrete is underway by outage engineers and Engineering Design.

Repair'ork is currently in pxogress.