ML18024A944

Monthly Operating Rept for Jul 1979

ML18024A944
Person / Time
Site:	Browns Ferry
Issue date:	08/02/1979
From:	Alencourt H, Green D, Thom T TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A943	List: ML18024A942 ML18024A944
References
NUDOCS 7908140451
Download: ML18024A944 (31)

Text

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

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I Submitted By.

Plant Superintendent

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TABLE OF CONTENTS Operations Summary Refueling Enformation Significant Operational Events Average Daily Unit Power Level Operating Data Reports

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1'0 13 Unit Shutdowns and Power Reductions.

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16 Plant Maintenance

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19 Outage Section Monthly Report

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0 erations Summar 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 six reportable occurrences and one revision to a reportable occurrence reported to the NRC during the month of July.

Unit 1 The unit did not scram during the month.

Unit 2 The unit scrammed once during the month.

On July 29, the reactor was manually scrammed to repair an EHC fluid leak.

Unit 3 The unit scrammed three times during the month.

On July 17, the reactor scrammed due to condenser low vacuum caused by a broken air line (SJAE isolated).

The reactor was manually scrammed again on July 17 due to off-gas problems (high H concentration)

The reactor scrammed on July 21 due to APRM high flux caused by stop valve fast closure during surveillance testing.

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

Location Unit 1

"'nit 2 Unit 3 Shell at water line Feedwater nozzle Closure studs 0.18813 0.17378 0.12514 0.11028 0.10118 0.07472 0.00407 0.00291 0.00255 Note:

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

Common S stems Approximately 4.68E+04 gallons of waste liquid were discharged containing 3.77E-02 curies of activity.

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, two 8 x 8 R

fuel assemblies, and 45 new fuel assemblies.

51 new fuel assemblies are on the refuel floor and have not yet been placed in the pool.

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 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 will be submitted to the NRC before the'outage.

This refueling involves 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.

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.

Urd.t 3 Unit 3 is scheduled for its next refuel outage beginning on August 26, 1979, with a scheduled restart date of November 14, 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 spent fuel assemblies and 143 new fuel assemblies in the spent fuel storage pool.

One new fuel assembly is on the refuel floor but not in the pool.

The present licensed storage capacity of the spent fuel pool is 1132 assemblies.

Si nificant 0 erational Events Unit 1 Date TDte Event 7/Ol/79 0001 Reactor thermal power at '99% (sequence "A"), steady state 7/07 0200 0637 0842 Commenced reducing thermal power from 99% for control rod sequence exchange from "A" to "B" Reactor thermal power at 45%,

commenced contiol rod sequence exchange Control rod sequence exchange completed, commenced power ascension in control rod sequence "B"

7/08 1705 Commenced PCIOMR from 70% thermal power 7/10 1400 Reactor thermal power at 96%

(CPR limited until end of cycle) 7/14 0330 0525 1404 Reduced thermal power from 96% to 85% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 96%,

CPR limited 7/20 2355 Reduced thermal power from 96% to 80% for turbine C.V. tests and SI's 7/21 0120 0800 Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 95%,

CPR limited" 7/23 2110 2240 Reduced thermal power from 95% to 88% for control rod pattern adjustment Control rod pattern adjust'ment completed, commenced PCIOMR from 88% thermal power

7/24 0700 Reactor thermal power at 96%,

CPR limited 7/28 0300 0620 1030 2300 Reduced thermal power from 96% to 50% for both recirculation pumps MG set brush replacement Brush replacement for both recirculation pumps MG sets completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 96%,

CPR limited 7/29 1410 1415 Reduced thermal power from 96% to 80% due to recirculation pumps run back when Unit 2 was manually scrammed Commenced power ascension

Si nificant 0 erational Events Unit 1 Date Time Event 7/30 7I3l 0700 2400 Reactor thermal power at 95%,

CPR limited e

Reactor thermal power at 95%,

CPR limited

Si nificant 0 erational Events Date Time Unit 2

Event

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~'l 7/01 0001 0730 1130 1325 1435 Reactor thermal power at 99% (sequence "B"), steady state Reduced thermal power from 94% xo 60% for RTI 32A (Recirculation Pump Test)

Commenced power ascension from 61% to 72%, holding for control rod pattern adjustment RTI 32A completed Control rod pattern established, commenced PCIOMR from 72% thermal power 7/03 0430 Reactor thermal power at 99%, steady state 7/06 2310 Reduced thermal power from 99% to 80% for turbine C.V. tests and SI's 7/07 0040 0300 1500 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 7/13 0725 0835 0957 1735 Commenced reducing thermal power from 99% to 55%

for replacing main steam tunnel temperature switches Reactor thermal power at 55%, holding for replacement of main steam tunnel temperature switch Main steam tunnel temperature switch replacement completed, commenced power ascension Commenced PCIOMR from 90% thermal power 7/14 0700 Reactor thermal power at 99%, steady state 7/21 2337 Reduced thermal power from 99% to 90% for turbine C.V.

tests and SI's

7/22 0130 0700 Turbine. C.V. tests and SI's completed.,

commenced power ascension Reactor thermal power at 98%, core limited (QKLPD) 7/24 2023 2207 2335 Commenced reducing thermal power to 45% for control rod sequence exchange from "B" to "A" Reactor thermal power at 45%,

commenced control rod sequence exchange Control rod sequence exchange completed, commenced power ascension

Si nificant 0 erational Events Unit 2

Date Time Event 7/25 0125 1500 Commenced PCIOMR from 65% thermal power Reactor thermal power at 99%, s'teady state 7/27 2200 Commenced thermal power reduction from 99% to 50%

for both recirculation pumps M.G. set brush replace-ment 7/28

. 0635 1500 Recirculation pumps M.G. set brush replacement completed, commenced power ascension Commenced PCIOMR from 80% thermal power 7/29 1200 1355 1406 1800 2046 2309 2335 Reactor thermal power at 99%, steady state Commenced manual shutdown due to EHC leak Reactor scram no.

82 manual from 35% thermal power to accommodate maintenance to EHC EHC maintenance completed, commenced rod withdrawal Reactor critical no.

95 Rolled T/G Synchronized generator, commenced power ascension 7/30 1500 Commenced PCIOMR from 58% thermal power 7/31 2400 Reactor thermal power at 78%,

PCIOMR in progress

Si nificant 0 erational Events Unit Date TfIIB Event 7/Ol 0001 0100 0330 Reactor thermal power at 72% (sequence "A"), holding for control rod pattern adjustment Control rod pattern established~

commenced power ascension Commenced PCIOMR from 80% thermal power 7/O2 0530 Reactor thermal power at 99%, steady state 7/O7 0035 0145 0700 Reduced thermal power from 99% to 85% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99%, steady state 7/O8 0745 0830 1035 Reduced thermal power from 99% to 96% for flux shaping Commenced PCIOMR from 96% thermal power Reactor thermal power at 99%, steady state 7/10 0120 Reduced thermal power from 99% to 74% due to "A" reactor feedwater pump motor governing unit malfunction 7/11 1620 "A" reactor feedwater pump maintenance completed and placed in service, commenced power ascension 7/12 0130 2035 Commenced PCIOMR from '95% thermal power Reactor thermal power at 99%, steady state 7/14 0015 0250 0300 1500 Reduced thermal power from 99% to 85% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 98%, rod limited (max. flow) 7/17 7/18 0125 0135 0536 0823 1035 1404 0458 0814 1137 1158 Reduced thermal power from 98% to 40% due to "A" low pressure heaters and y)earn jet air ejector isolation Reactor scram no.

74 on condenser low vacuum from 40% thermal power, due to broken solder joint on con-trol air valve Control air repairs completed, commenced rod withdrawal Reactor critical no.

84 Synchronized generator, commenced power ascension Reactor scram no.

75 (manual) from 40% thermal power due to offgas problems (high H2 concentration)

Commenced rod withdrawal Reactor critical no.

85 Rolled T/G Synchronized generator, commenced power ascension

Si nificant 0 erational Events Unit 3 Dace Time Event 7/19 1245 Commenced PCIOMR from 75% thermal power 7/20 7/21 2005 2140 0003 0320 0540 0953 1021 2230 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 50% for recirculation pump M.G. set brush replacement Reactor scram no.

76 from 50% thermal power on APRM high flux during SI Commenced rod withdrawal Reactor critical No.

86 Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 65% thermal power 7/22 0920 1005 1230 Reduced thermal power from 73% to 55%, for control rod pattern adjustment Control rod pattern adjustment completed, commenced power ascension from 56% thermal power Commenced PCIOMR from 68% thermal power 7/24 7/25 1630 1820 2215 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 72% due to "A" reactor feedwater pump isolation (controls malfunction)

"A" reactor feedwater pump placed in service, commenced power ascension 7/26 0733 1500 Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 7/28 7/30 0105 0425 1500 1210 1600 2000 Reduced thermal power. from 99% to 85% for turbine C.V.

tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 95% for removal of "A" string high pressure heaters from service (LCV 6-62 not functioning properly Commenced power ascension, Reactor thermal power at 99%, steady. state 7/31 2400 Reactor thermal power at 99%, steady state Equipment malfunction (1)

10 AVERAGE DAlLYUNITPOWER LEVEL DOCKET NO.

COMPLETED BY T. Thorn TFLEPHONE 205/729-6846 MONTH

Juan, 1979 DAY AVERAGEDAILYPOWER LEVEL (MWe-Net) r 1035 1039 1045 1027 1041 573 DAY 17 18 19 20 21 22 23 AVERAGE DAILYPOWER LEVEL (Mme.Net)

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1004 1007 1005 1001 98 aoo4 996 8

10 12 13 14 15 16 700 886 1009 aoo6 1018 1014 011 1016 1010 24 25 26 27 28 29 30 31 1000 1004 1003 1019 894 1016 998 1001 INSTRUCTIONS On this format.!ist the average daily unit power level in MWe.Net for each day in the reporting month. Cotnpute to the nearest whole megawatt.

(')/771

AVERAGE DAILYUNITPOWER LEVEL DOCKET NO UNIT DATE COMPLETED BY v

B~wns Ferry 2

TELEPHONE 205/729-6846 MONTH DAY AVERAGEDAlLYPOWER LEVEL (MWe-Net) 761 DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net)

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1061 17 10 12 13 14 15 16 8 6 1064 1043 1038 1046 1056 1059 1018 1060 1066 890 1062 1068 1061 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1065 1067 1059 1053 1064 864 1033 1027 684 598 689 921 INSTRUCTIONS On this format.!ist the average daily unit power level in LIIWe.Net for each day in the reporting month. Compute to the nearest whole megawat t.

(9I77 l

12 AVERAGE DAlLYUNITPOWER LEVEL DOCKET NO.

UNIT DATE 8~2-79 COMPLETED IIY T. Thon TELEPHONE 205/729-6846 MONTH DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 881 DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) 17 7.

10 12 13 14 15 16 1048 1057 1043 1034 1036 1036 1043 763 848 1038 1045 1021 1038 1025 18 19 20 21 22 23 24 25 26 27 28 30 31 190 794 975 311 733 863 956 1026 996 1060 1016 1033 1005 995 INSTRUCTIONS On this format. list the average daily unit power level in iIWe-Net for each day in the reporting >nonth. Ciimpute to the nearest whole megawatt.

I'>/77)

13 OPERATING DATAREPORT DOCKET NO.

DATE

'5 2-29 COhIPLETED BY Ddt Greert TELEPHONE 2~05 729-846 OPERATING STATUS

1. Unit Name:

Brows e

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross hIWe):

5. Design Electrical Rating (Net MWe):

Notes ed

7. Maximum Dependable Capacity (Net MWe):

8. IfChanges 0'ccur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason's:,.":

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

10. Reasons For Restrictions, IfAny:

This Month

11. Hours In Reporting Period

" 744

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 744

15. Unit Reserve Shutdown Hours 0

17. Gross Electrical Energy Generated (MWH) lg. Net Electrical Energy Genere ted (gttyH)

~220 026

..19. Unit Service Factor 100

20. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net) 22: Unit Capacity Factor (Using DER Net)-

23. Unit Forced Outage Rate 0

24. Shutdowns Scheduled Over Next 6 ihlonths (Type. Date. and Dura Refuel Outage November 20, 1979 Yr:to-Date 4 488.09 175.08 4,384.84 0

13 175 365

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4 231 991

86. 2

86. 2 78.1 78.1 5.0 tion of Each):

Cumuhtive 43 '825 24 719.68 4,574.21.

,07

'0 63 948 037 21,164,580 20 538 211 54.9

54. 9 35.9 I.e' e

in n' e

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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 COMMERCIALOPERATIGit(

<>)

14 OPERATING DATA'REPORT DOCKET NO. 50-260 DATE ~2 COMPLETED BY D>> ~<<crt TELEPHONE~

OPERATING STATUS Notes I. Unit Name:

. 2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross iMWe) et IIWe:

1098.4 1065

7. Maxmmm Dependable Capactty (N i

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8. IfChanges 0'ccur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

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

10. Reasons For Restrictions, IfAny:

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) l7. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH)

. 19. Unit Service Factor

20. Unit'vailabilityFactor

21. Unit Capacity Factor (Using ilIDCNet) 22.. Unit Capacity Factor (Using DER Net)-

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months This Month 744 737.33

.67 734.52 2 243 971 Yr.-to-Date 5,087 72.65 4,207.47 0

12,388,432 98.7 92.4 92.4 1.3 4,078,308 82.7 82.7 75.3 75.3 1.5 (Type, Date. and Duration of Each):

Cumulative 21 037.06 11,549;36 20,275.33 0

55,840,220 18;499,288 52.3.

52.3 3.6 40.2

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

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

INITIALCRITICALITY INITIAL ELECTRICITY COMMERCIALOPERATION Forecast Achieved

<<I77)

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OPERATING STATUS

l. Unit Name:

2. Reportihg Period:

, 3. Licensed Thermal Power (MWt):

4. Namephte Rating (Gross MWe):

5. Design Electrical Rating (Net ilIWe):

7. Maximum Dependable Capacity (Net MWe):

OPERATING DATAREPORT Notes DOCKET NO.

DATE COMPLETED BY TELEPHONE 2

2 -6846

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

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

10. Reasons For Restrictions, IfAny:

This illonth Yr:to-Date Cumulative

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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 (MWH)

Net Electrical Energy Generated (MWH)

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

Unit Capacity Factor (Using DER Net)

Unit Forced Outage Rate Shutdowns Scheduled Over Next 6 hlonths

.Refuel Outage August 26, 744

'713.40 30.6 702.78 0

2 118 0

692 940 673 104 94.5

~ 94.5 84.9 8

~ 9 5.5 5 087 4726.85 360.15 4 79.22 14 218 607 4 742 490 4,618,826 92.0 92.0 85.3

85. 3 8.0 (Type, Date. and Duration of Each):

1979 21 1

1 17 818.05 1465.56 17 409E'20

'0 16 509 990 16,024,014 82.2 82.2 7

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71.0 9.1

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

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

Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COilDIERCIALOPERATION (o/77)

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~ ~ ~r UNITSIIUTDOWNS AND POlVER REDUCTIONS REPORT hIONTH DATE 8-2-79 CohlPLETED BY NII.

l)atc I I VlIJ L

J J= ~ec Q

Licenscc Event Report sr 4J~

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U F tJ p3 Cause &, Corrective Action lo Prevent Recurrcncc 87 88 790707 790728 H

Derated for control rod sequence exchange.

Derated

. to replace brushes in both recirc.

pump M-G sets..

F: Forced S: Schedulell III/77)

Reason:

A Equipment Failure (Explain)

B.hlaintenance or Test C.Refueling I) Regulatory Restriction Ii-Operator Training &, Liccnsc Examination F-Adnlinlstrallvc G.Operational Error (Explain)

I I Other (Explain)

Method:

I.hlanual 2.hIanual Scram.

3.Automatic Scram.

4-Other (Explain)

Exhibit G Instructions rof Prcparatlon of Data Entry Shccls I'or Liccllsee Event Rcport (tLl(lFile (NURE-GOI6 I

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lixhibit I

~ Salnc Sou<<c

UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

UNITNAhlE DATE COMPLETED BY TELEPHONE 50-260 8-2-79 205 729-6846 91 92 Date 790701 790713 r~

Vlrjo B

B I

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C/7 $

Liccnsec Event Report ¹

~ g EIpVl p 0 E ~

Cause &, Correct tve Action to Prevent Rccurrcnce Derated for RTI32A (Recirc Pump Test Derated for main s team tunnel temp.

switch replacement

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93 790724 Derated for control rod squence exchange 94 790727 Derated

. for recirc.

pump H-0 set brush replacement 95 790729 P

9.48 A

EHC Oil Leak F: Forced S: Schcduierl Reason:-

A.Equipmcnt Failure (Explain)

B hlaintenancc or Test C-Refueling D-Regulatory Restriction L'-Operator Training &, Liccosc Examination F-Administ rat ive G.Operational Error (Explain)

I I Other (Explain) 3 hlethod:

I.hlanual 2 Manual Scram.

3-Automatic Scram.

4-Other (Explain)

Exhibit G - Instructions for Preparalioo of Data Entry Sheets for Liccrtsee Event Report (kLrRI.Pile (NUREG-OI6I )

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Exhibit I - Sante Source

~'P UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-296 DATE COMPLETED DY Nii.

l)alc b

r>

o J

fP~

L A

V~ C/)

Licensee Evcnl Report >

a

~ C 4I Q

O I~

lo Cause & Corrective Aclion lo Prevent Rccurrcnce 99 790710 100 790717 9.02 A

A Derated due to "A" reactor feed pump motor governing unit malfunction Condenser low vacuum, due to a broke weld on a control air valve.

101 790717 102 790720 103 790721 104 790725 21,90 10.3 A

B High H2 concentration in the off gas system Derated for recirc pump MG set brush replacement AP&I High flux during testing Derated due to "A" reactor feedwater pump controls malfunction F: Forced S: Schedule<l I'I/77)

Reason:

A-Erlulpment Failure (Explain)

II Maintenance or Test C.Refueling D Regulatory Restriction E Opcfalor Training &. Liccnsc Examination F-Administrative G.Operational Error (Explain)

I I Other (Explain)

Method:

I-Manual 2-Manual Scram.

3-Autontalic Scram.

4 Other (Explain)

Exhibit G - Instructions for Preparatioll of Data Entry Sheets lor Licensee Event lteport (I:ERII'ilcINUREG.

OI6I )

Iixltibit I Same Source

CSSC E UIPMENT BROWS FERRY NUCLEAR PLANT UNIT 1

MECHANICAL MAINTENANCE

SUMMARY

SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION Page 1 of 2 ACTION TAKEN TO PRECLUDE RECURRENCE 7/5 lA CRD Suction Filter needs Filter changing None Unknown Improper Suction Replace with new filters 7/6 Control Air Ai Compressor Drain trap not working None Trash inside

'trap Trap not working Cleaned out trap 7/9 7/ll RCIC RCIC RCIC Turbine Low oil level Packing leak o Pater leak main supply valve None None unknown Loose nuts and Ferrile None Water leak Added 5 quarts t

proper oil level.

Tightened all fittings and Ferrile 7/ll 7/12 HPCI CCW HPCI 1A pump Failed SI test Packing leak Possible shutdown of unit None Overspeed trip Bad packing No set screw on trip mechanism low oil discharge pressure Water leak at seal Installed new piston oil rings, ad)usted changed oil reassem-bled HPCI Replace with new packing 7/13 RHR Service water Drain line discharge valv leaking None Loose packing Water leaking around seal Tightened packing Stopped leak 7/13 HPCI HPCI Exhaust dia-phragm busted Possible failure of HPCI Ruptured disc HPCI out of service Replaced with n~

diaphragm 7/16 Fuel Pool Demin.

lA fuel pool cooling pump Packing leak None Loose packing Water leaking around Adjusted packing packing Stopped leak

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CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 2

?KCHANICALMAINTENANCE

SUMMARY

For the Month of

" y 19 79 SYSTEM COMPONENT NATURE OF

? fAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 7/5 CCW Cond.

2A Booster pump Low oil level None Unknown None Added oil to proper level 7/9 7/10 CCW RCIC 2C booster pump Low oil level Valve 71-570 Packing leak None None Unknown Loose nuts on packing None Water leak at packing Added &1 to proper level Tightened nuts adjusted packin~

Stopped leak 7/10 RCIC Valve 570 Packing leak None Loose pqcking Water leak at packing Tightened packing Stopped leak 7/la CCW 2C pump Water leak None Line stopped up Water leak Unstopped line Cleared and tightened line 7/15 Turbine 2A fan motor Bldg. Vent Motor burned up None Unknown Burned out motor Replaced with new motor 7/17 7/21 HPCI CRD HPCI "A" discharge filter Check over-speed trip Filter dirty Possible failure of HPCI None Unknown Filter stopped up None None Adjusted overspeed trip.

Replaced bal; and tappet.

Adjusti oil to overspeed reset Replaced with n filter 7/21 Reactor Feedwater Isolation Valve 616 Packing leak

,None Loose packing None Tightened packing Stopped leak

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BROWNS FERRY NUCLEAR PLANT UNIT Common MECHANICAL >JAINTENANCE

SUMMARY

For the Month of SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR r

CAUSE OF MALFUNCTION RESULTS.OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 7/1 Intake EECW Strainer Excessive packing leak None Defective pack-ing Excessive water leak Replaced packing 7/1 Intake D "3" pump Excessive pac ing leak-None Defective pack-ing I

Excessive water leak Replaced packing 7/1 Intake C "3" pump Excessive packing leak None Defective pack-ing Excessive water leak Replaced packing 7/1 7/16 7/16 Intake Intake Intake Spare screen wash pump C3.RHR Pump D "3" pump Packing leak Bad packing leak Bad packing leak None None None Loose packing Loose packing Defective packing Water leaking at packing Water leak at packing Excessive water leak Tightened packing Tightened packing stopped leak Replaced with new packing 7/16 RHRSW C3 pump Bad packing leak None Loose packing Water leak at packing Tightened packing 7/22 RHRSW C3 pump Bad packing leak None Defective pack-ing Water leak at packing Replaced packing 7/22 RHRSW D3 pump Bad packing

leak, None Defective packin Water leak at pack-ing Replaced packing

RRUVUR PERilE UUCLEiU'LZilP URZP ELECTRICAL Mh.INTENANCE SlWfARY For the?fonth of July 1979 Page 1 of 1 Date

.r System'omponent Nature of Haintenance E

ecton

'a e

Operati.on of The Reactor Cause of Halfunction Results of

~falfunctfon Action Taken To Preclude Recurrence 7/12/79 kir Cond.

"B" Control Bay Chiller purge unit Pan Inoper.

n/a Broken Belt 6 bent blade Fan Inoperable Replaced Belt 6 blade tested o.k..

TR 8143309

EROLVE FERRY NUCLEAR 'PLPXT UUYT 2

ELECTRICAL HAINTENANCE SDQfARY For the Month of Page 1 of 1 Date System'omponent Nature of Maintenance E

ect on a

e Operation of The Reactor Cause of Malfunction Results of Nalfunc tion Action Taken To Preclude Recurrence 7/16/79 Residual Heat Re-moval ser-vice water Cl RHR SM pum motor SBM switch Replace switch n/a Bad contact on switch Switch contact in-Installed a new switch operable.

Used spare removed JIMR, tested contact until new o.k.

TR'8 96886 switch available 7/20/79 High press coolant injection 2 FCV-73-16, motor-torque switch Failed torqu switch n/a (HPCI inoperable for maintenance at the time)

Switch failed Valve would not open Replaced torque sw Performed EMI-18 TR134191 - checked o.k 7/27/79 Primary contain-ent system FCV-64-21 Loss of proper valve indication n/a Coil in 16AK40 relay failed FCV-64-21 inoperable Replaced relay coil.

ested o.k.TRII134865 ER No.

FRO 50-260/7918

BROitVS FERRY NUCLEAR PLANT UNIT 3

ELECTRICAL MAINTENANCE SU1'ÃARY For the kfonth of Ju>>

1979 Page 1 of 1 7/1S/79 System '

Component RBCCM pump motor-out board and in board bearing Nature of Haintenance Bearings running hot E

ect on Sa e

Operation of The Reactor n/a Cause of Nalfunction Failed bearings Results of

~malfunction kfotor bearing temperatures high Action Taken To Preclude Recurrence Replaced in board and out board Bearings checked vibration and temperatures all o TR8 134604 7/24/79 High press coolant in5ection 3

FCV 73-S, False in-limit switche dication of position n/a Limits. out of ad) ustment Both opened 6

closed lights on with valve in closed position Adjusted limits o.k.

TR8 134627

t CSSC EQUIPMENT BROWNE PERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE SENARY For the Month of July 1979 Date Unit I System None Component None Nature of.

Maintenance None ect on ba e Operation of The Reactor None Cause of Malfunction None Results of Malfunction None None Action.Taken To Preclude Recurrence Unit 2 j7-9 I

Control rod drive Pds-85-63 Replace None Gage over-pressurized Indicated High DP None IYJnit 3 7-2 Radwaste FT-77-6, 16 Calibrate None Zero Drift

~Indicated flow with None bivalves closed Primary Contain-

'ment Pds-64-137B, Pds-64-138B Repair None Bad relays in alarm unit Compresser did not

trip at setpoint None

-13 Control Air PS-32-64A, B

PS-32-67A, B

Calibrate None Instrument drift 'Only pump B Cycled on and off None g-24 Feedwater LC-46-5 Repair.

None Low Output Did not maintain level setpoint None

28 OUTAGE SECTION MONTHLY REPORT July 1979

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Preparations are being made for the unit 3 refueling outage.

Major work area during the month of July consisted of prefabrication on major modifications, building storage and work areas

needed, and preparing the necessary load centers for areas where major work is scheduled during the outage period.

Other preparatory work includes making certain all work is defined and assigned to the work item listing.

Work is progressing at the service shops for the torus modification with all quenchers being completed for unit 3 and work started on unit 1 quenchers.

The modification to pipe the CRD water to the RWCU pump seal heat exchanger is nearing completion for units 1 and 2.

Work is progressing on the LPCI modification even though some material problems exist.

Other modification work underway was the hypochlorite building, installation of the oil sump pump was completed, installation of magnetic switches and cables pulling for the secondary alarm station and E-field on the security modifications, installation of the high density storage racks and installation of the transfer slot canal expansion joint.

All unit 3 fuel has been received and inspected and shipments of unit 1 fuel are currently in progress.

The disposal of control rod racks -and spent fuel racks is still underway and will be completed before the start of the unit 3 refueling outage.