ML18024A594
| ML18024A594 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/02/1978 |
| From: | Dewease J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A593 | List: |
| References | |
| NUDOCS 7812190162 | |
| Download: ML18024A594 (32) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT November 1, 1978 November 30, 1978 DOCKET NUMBERS 50-259, 50>>260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by ant uperintendent V 818 190 lpga
TABLE OF CONTENTS Operations Summary Operational Data
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2 Maintenance
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3 Refueling Information
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3 Significant Operational Events
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Average Daily Unit Power Level Operating Data Reports
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o l2 Unit Shutdowns and Power Reductions.
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l5 Plant Maintenance Summary.
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o lg Unit 3 Refueling Outage Summary.
27 Unit l Refueling Outage Summary.
27
Ooerations Summa The following summary describes the significant operational activities during the reporting period.
ln support of this summary, a chronological log of significant events is included in this report and begins on page 5.
There were 7 Reportable Occurrences reported to the NRC during the month of November.
Untt 1 Significant operational events for unit 1 are tabulated by date and time beginning on page 5.
The unit scrammed once during the month of November.
On November 26, the reactor was manually scrammed to accommodate the scheduled refueling outage.
Power was administratively limited throughout the month by 60K "B" recirculation pump speed, with "A" loop out of service.
A summary of maintenance work is shown on pages 18 through 26.
Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 6,
The unit did not scram during the month.
A summary of maintenance work is shown on pages 18 through 26.
Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 7.
Unit 3 was shut down for refueling outage and startup testing until November 25.
Fuel loading was completed on November 9, and rod withdrawal for startup commenced on November 22.
erations Summa (Continued)
Unit 3 (Centdnned)
There were five scrams on the unit during the month.
On November 23, the reactor scrammed on APRM high flux, caused by cold water being introduced into the vessel in an attempt to maintain reactor water level.
The water level problems were caused by feedwater control problems which occurred due to a power switch in the control cabinets not being returned to "ON" before startup.
The reactor scrammed on November 24 due to a false reactor low-low water leve3 signal apparently caused by'personnel bumping these switches in the reactor building.
The reactor was-manually scrammed on November 24 when control rods began drifting into the core due to low scram pilot header air pressure.
Investigations did not reveal the cause of the low pressure.
On November 25 the reactor scrammed on low condenser vacuum which was caused by instabilities in the "A" SJAE.
On November 29 the reactor was manually scrammed to correct LPHM connections in-the drywell.
Approximately 1.1E+6 gallons of waste liquid were discharged con-taining approximately 1.5EO curies of activity.
Cooling towers 1 and 6 were operational this month for two liftpump operations.
Modifications by the tower vendor were continued on Tower 3 and Tower 2.
None of the towers had significant operational problems.
The average daily unit power level for units 1, 2 and 3 is shown on pages 9 through 11.
The operating data reports for all three units are shown on pages 12 through 14.
Unit shutdowns and power reductions for all three units are shown on pages 15 through 17'.
erations Summa (Continued)
Maintenance Major electrical, mechanical, and instrument maintenance activities during the month are described on pages 18 through 26.
Refueling outage activities for Unit 3 are summarized on page 27 'efueling outage activities for Unit 1 are summarized on page 27.
Refuelinm information Unit 1'nit 1 began its second refueling on November 26, 1978, with a restart date of January 8
, 1978.
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 was submitted in August 1978.
This refueling will load additional 8 X 8R (retrofit) fuel assemblies into the core, replacing presently loaded 7X7 fuel and will involve irstalling a new recirculation pump trip (RPT) system.'here are 764 fuel assemblies in the coze.
The spent fuel storage pool presently contains 168 spent 7X7 fuel assemblies and 156 new 8 X 8R fuel assemblies.
The present storage capacity of the spent fuel pool is 1080 assemblies.
Present planning is to increase that capacity to 3471 assemblies.
Pith present
- capacity, the refueling later in 1978 would be the last refueling that could be discharged to the spent fuel storage pool without exceeding that capacity and maintaining full coze dischazge capability in the pool.
n Unit 2 Unit 2 is scheduled for its second refueling beg~~ning on April 22, 1979, with a restart date of July 1, 1979.
Resumption of operation on that date will require a change in technical specifications pertaining to the coze thermal
4 Refuelin Enformat ion (Continued)
Unit 2 (Continued) limits.
Present scheduling is to submit licensing information in support of these changes before the refueling.
This refueling will involve replacinm some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies.
There are 764 fuel assemblies in the core.
At the end of November there were 132 discharged cycle 1 7 X 7 fuel assemblies in the spent fuel storage pool.
There are presently 36 new 8 X 8 fuel assemblies in the spent fuel storage pool. which. were not loaded. into the core during this cycle.
The present storage capacity of the spent fuel pool is 1080 assemblies.
Present planning is to increase that capacity to 3471 assemblies.
Pith 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.
Undt 3
Unit 3 finished its erst refueling outage on November 25, 1978.-
This refueling involved replacing some of the present 8 X 8 fuel assemblies with 8X8R (retrofit) assemblies, modifying the main steam relief valves to increase simmer margin, and installing a new recirculation pump trip (RPT) system.
Unit 3 is scheduled for its next refuel outage beginning on August 30, 1979.
This refueling will involve loading additional 8Z8R (retrofit) assemblies into the cora.
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 of the spent fuel pool is 1132 assemblies.
Si nificant 0 erational Events Unit 1 Date Time Event 11/1 nooo Reactor thermal power at 59K, holding for single re-circulation loop operation Seauence A
11/3 2250 Reduced thermal power from 59,. to 53".. for turbine CV tests and SI's 11/4 0045 Turbine CV tests and SI's completed commenced power ascension 0110 Reactor thermal power at 59K, steady state, holding for single recirculation loop operation 11/10 230n Reduced thermal power from 59'". to 53/ for turbine CV tests and SI's 11/11 03n5 Turbine CV tests and SI's completed, commenced power ascension 0510 Reactor thermal power at 59/, steady state, holding for single recirculation loop operation 11/17 2325 Reduced thermal power from 597 to 53'. for turbine CV tests and SI's 11/18 0330 Turbine CV tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 597, holding for single re-circulation pump loop operation 11/24 2350 Reduced thermal power from 59K to 53K for turbine CV tests and SI's 11/25 0135 Turbine CV tests and SI's completed, commenced power ascension 0700 Reactor thermal power at 59Ã, holding for single re-circulation pump loop operation 11/26 0340 Reduced thermal power from 5",7 to 5ni, for scram timing control rods 0515 Scram timing control rods completed, commenced power ascension 0700 Reactor thermal power at 59K, holding for single re-circulation pump loop operation
Si nificant 0 erational Events Unit 1 (Continued)
Date Tine 11/26 1525 Event Commenced reducing thermal power'rom 59%%u to shutdown for refueling outage 2053 11/30 2400 Reactor scram no.
102 manual from 35%%u thermal power to accommodate refueling outage Unit off for reload 2, cycle 3 refueling outage Unit 2 11/1 11/3 0000 2330 Reactor. thermal power at 98%%u steady state Sequence A
Reduced thermal power from 98%%u to 85%%u. for turbine CV test and SI's 11/4 0200 Turbine CV tests and SI's completed, commenced power ascension 0700 11/10 2350 Reactor thermal power at 98%%u steady state Reduced thermal power from 9R%%u to 7n%%u for turbine CV tests and SI's 11/11 0210 Turbine CV tests and SI's completed, commenced power ascension 2230 11/12 0700 11/17 2308 11/18 0345 Commenced PCIOHR from 90%%u thermal power Reactor thermal power at 98%%u, steady state Reduced thermal po~er from 98%%u to 70%%u. for turbine CV tests and SI's P
Turbine CV tests and SI's completed, commenced power ascension 0700 11/19 0400 11/25 0130 Commenced PCIOMR from 85%%u thermal power Reactor thermal power at 98%%u., steady state Reduced thermal power from 98%%u to 9n%%u for turbine CV tests and SI's 040n 1600 11/30 2400 Turbine CV tests and SI's completed commenced PCIOHR Reactor thermal power at 98I.; steady state Reactor thermal power at 98%%u; steady state
Si ificant 0 erational Events Date Time Utft 3 Event 0000 Unit shutdown for refueling with fuel loading operation in progress 11/9 0150 Fuel loading operation complete with all 764 fuel assemblies placed in the reactor vessel 11/22 1158 Commenced rod withdrawal for startup (Sequence "B")
1300 11/23 1608 Reactor critical no.
74 Reactor scram no.
66 from 5?,'hermal power on APRM (1) hi flux due to reactor feed pumps control problems 1719 1840 11/24 0950 Commenced rod withdrawal Reactor critical no.
75 Reactor scram no.
67 from 10?.'hermal power on (2) false low-low reactor water level signal 1140 1231 Commenced rod withdrawal Reactor critical no.
76 181'9 Reactor scram no.
68 (manual) from 10?'hermal vower due to low scram pilot air header pressure (control rods drifting) 2150 11/25 0946 Reactor critical no.77 Reactor scram no.
69 from 101 thermal power on (3) low vacuum due to "A" steam jet air ejector instability 1107 1205 1547 1910 2218 2237 Commenced rod withdrawal (Sequence "B")
Reactor critical no.
78 Rolled T/G Synchronized generator Turbine trip on overspeed trip test from 5?,'hermal oower Synchronized generator, commenced power ascension
Si nificant 0 erational Events Date Time Unit 3 (Continued)
Event 11/26 0545 Reactor thermal power at 23/, holding for control rod scram timing (RTI-5) 11/27 1407 Commenced reducing thermal power from 23Ã to
- 57. for turbine trip to perform recirculation pump trip (RPT) test 1430 Turbine tripped at 5Z thermal power 1440 Recirculation pump trip test complete, commenced rod withdrawal for startup (Sequence "B")
1705 1735 Rolled T/G'ynchronized generator, commenced power ascension 11/28 0925 11/29 0100 Increased thermal power to 4%'for continuing control rod scram timing Reactor scram no.
70 (manual) from 4M thermal power (1) for corrections to LPRM connections 11/30 1450 2040 2400 Commenced rod withdrawal (Sequence "B")
Reactor critical no.
79 Reactor critical with startup in progress Maintenance error (1)
(2)
Cause unknown Equipment malfunction (3)
9 AVERAGE DAILYUNITPOWER'LEVEL DOCKET NO.
12-02-78 COMPLETED BY MONTH November 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 591 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 600 17 602 10 12 13 l4 IS 16 594 88 585 586 602 602 580 599 601 601 606 576 19 20 21 22 26 27 29 30 31 608 611 603 606 607 614 601 515
-8 INSTRUCTIONS On this format, list the average daily unit power level in Mme.Net for each day in the reporting month. Compute to the nearest whole megawat t.
(91771
l 10 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO 50-260 BrotIns Ferry T.Z 12-04-78 DATE COMPLETED BY TELEPHONE MONTH November 1978 DAY AVERAGE DAILYPOWER I.EVEL (MWe Net)
I, 1086 DAY AVERAGE DAILYPOWER LEVEL (MWe Net) 1062 17 2
9'0 11 12 13 14 I5 16 1071 1056 1069 999 1062 1064 1071 1081 1026 18 20 21 22 24 26 27 29 30 31 909 1072 1074 1068 1070 1063 1083 1007 1078 1056 1084 1055 1074 INSTRUCTIONS On this format, list the average daily umt power level in Mme Net for each day in the reporting month. Compute to the nearest whole megawatt.
(~)/77)
11 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
50-296 Browns Ferry III 12-04-78 COMPLETED BY TELEPHONE MONTH November 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe.Net)
DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)
~7 17 18 19 20 21
-10
~
10 II 12 13 IS 16
-6 24 25 26 27 28 29 30 31
-10 22 163 151 299 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reportina month. Compute to the nearest whole megawatt.
(9I771
12 OPERATING DATAREPORT OPERATING STATUS I. Unit Name Browns Ferrv l
- 2. Reporting Period:
November 1978
- 3. Licensed Thermal Power (hIWt):
- 4. Namephte Rating {Gross hIWe):
S. Design Electrical Rating (Net MWe):
- 6. maximum Dependable Capacity {Gross MWe):
1098.4 Notes DOCKET NO.
DATE ~2-02-78 COMPLETED By Don Green TELEPHONE ~Z?~-6846
- 7. Maximum Dependable Capacity (Net MWe).
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, If>ny(Net hIWeJ:
10 R~onsForResuictions lEAn amSPe recirculation looP oPeration.
"A" recirc.
loo'n is out of service due to pump discharge valve 68-3 bein inonerable.
This Month Yr.-to-Date Cumulative 720 8016
- 11. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical
, 13. Reactor Reserve Shutdown Hours
".14. Hours Generator On-Linc
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (hIWH)
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit AvailabilityFactor
- 21. Unit Capacity Factor (Using MDC Net)
"". Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months 20.88 7,251.71
.33 620.88 7 045.21 0
18 399 443
.l.,201, 217 382 420 5 999 980 5 817 873 371,047
~
86.2 87.9
- 87. 9 48.4
- 68. 1 48.4 68.1 0
6.0 (Type, Date, and Duration of Each):
37 994 20 231 59 4,3a9.13 19 691.34 50 772 672 16 306 220
'51. 8
- 51. 8 40 3
~40.2
~
~ J I
I
- 25. IfShut Down At End Of Report Periog. Estimated Date of Startup:
- 26. Units ln Test Status {Priorto Commercial Operation):
Forecast a
a Achieved INITIALCRITICALITY INITIALELECTRICITY COhIMERCIALOPERATION
<a177)
13 OPERATING DATAREPORT DoczzT No.50-26n
'DATZ, ~n s
COMPLETED BY TELEPHONE ~n -22~-6846 OPERATING STATUS Notes 1.'nit Name:
- 2. Reporting Period:
November'978
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity {Gross MWe) 8 4 1065
- 7. Maximum Dependable Capacity (Net ilIWe):
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net MWe):
- 10. Reasons For Restrictions. IfAny:
Yr. to.Date This Month Cumulative 32 an5 15 974.29 720
' l. Hours In Reporting Period
'2. Number Of Hours Reactor Was Critical 720
'13. Reactor Reserve Shutdown Hours
'4. Hours Generator On4.ine
- 15. Unit Reserve Shutdown Hours"W""i
- 17. Gross Electrical Energy Generated (MWH)
~~Q
- 18. Net Electrical Energy Generated (MWH)
.19. Unit Service Factor
- 20. Unit AvailabilityFactor
- 22. Unit Capacity Factor (Using DER Net) 99.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date. and Duratio Refue1 Outage Atsril 1979 n
15 323'86 an n
4 948 548 4 798 035 13 140 839 66.0 46.6 46.6 66.0 56.2 37.5 56.2 5.0 47.0 n of Eachl:
- 25. IfShut Down At End Of Report Periog. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMibIERCIALOPERATION (a/77)
14 OPERATING STATUS OPERATING DATAREPORT DOCKET NO.
50-296 DATE
-F2-78 COMPLETED BY TELEPHONE
'rr-729-6846 Notes
- 1. Unit Name
- 2. Reporting Period:
November 1978
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross iMWe):
~
S. Design Electrical Rating (Net 4%(We):
~
- 6. Maximum Dependable Capacity (Gross MWe):
1098.4 1065
- 7. 4Maximum Dependable Capacity (Net MWe):
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net ilIWe):
- 10. Reasons For Restrictions, IfAny:
This Month Yr:to-Date Cumuhtive 720 8016 5,651.53 12 347.20 17.92 74.43 5 489.77 0
34 137 864 11 094 850 0
75 132 15 496 170 5,060,980 10,737,802 1
282 68.5
- 10. 3
- 78. 1 68.5 10.3 78.1 57.4 57.4 1.5 65.7 10.1 38.7 10.0 (Type. Date;and Duration of Each):
- 11. Hours ln Reporting Period
- 12. Number Of Hours Reactor Was Critical
- 13. Reactor Reserve Shutdown Hours
~14.'ours Generator On-Line IS. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor,
- 20. Unit AvaihbiiityFactor
- 21. Unit Capacity Factor (Using MDC Net)
H.. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months
- 25. IfShut Down At End Of Report Periog, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATIOiV (9/77)
UNlTSllUTDOWNS ANDPOWER REDUCT(ONS REPORT MONTH5~>e>>~et'OCKET NO.
UNlTNAhlE DATE COMPLETED DY TELEPHONE 0-2 rt 12-04-7(t 9o-Dale C'
C1 Cl O
U< c
~ tA Licenscc Eve rit Rcport sr E~
El El ro 6 EIc~
o 0 Q
O E Q CJ Cause Sc Corrective Action lo Prcvcnt Recurrence 55 781128 S
99 12 C
Refueling F: Forced S: Schcdoletl (9/77)
Reason:
A.Equipment Failure (Explain) 8-hlaintcnancc or Test C.Refueling D.Regulatory Rcstriclioo F. Operator Training A (3ccosc Examination F.Administrative G Operational Error (Explain) llOther (Explaio) 3 hlethod:
l -hlanual 2.Manual Scram.
3.Aulontalic Scram.
4 Other (Explain) 4 Exhibit G - Instructions I'or Preparatitm of Data Entry Slteets I'or Licensee Event Report (LL'R) File (NUREG-OI6I )
Exhibit l ~ Sante Source
UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT MONT)I DOCKET NO.
UNITNAhIF Browns Fer T T.
DATE 12-A -78 COMPLETED BY Don freest No.
Date C ~
ClBK A~
rr 5
Ul tJ C 0
<Sec
~(A g Licenscc Event Rcport ¹ C:
El~IIl p 0
- p. ~p C ~
CJ Cause &Corrective Action to Prevent Recurrcncc F: Furred S: Scheduled Reason:
A.Equipment Failure (Explain)
B.htalntenancc or Test C-Refueling D.Regulatory Restriction E-Operator Training & Liccnsc Examination F-Administrative C.Operational Error (Explain)
II.Other (Explain) hlcthod:
I.hlanual 2-hlanual Scram.
3-Automatic Scram.
4.Other (Explain)
Exhibit C ~ Instructions for Preparation oi'ata Entry Sheets for Licensee Event Report (LER) File (NUREG-OI6I )
Exhtbtt I - Satnc Source
- h
~ r
~ 7
,il h
-el 1,
'Ji~
-'4:
tAI i.
J;
]at'$
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- a'c,
- .~. C
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,j't vi "P.,
'S~'i T
.n" Dale 78 11 01 I
78 11 25 66 78 11 27 67 78 ll 29 I
F: Forced S: Scheduled
()/77)
REPORT h(ONTII IA I
tSB~
A~
Z
~A Q
fP, t4 C
~Vl g Licenscc Event Repurl rr QEu O
CJ S
595.17 C
.32 B
3.08 B
47.0 A
Reason:
A.Equipmcnt Failure (Explain)
Q.hiaintenance or Test C.Refueling D Regulatory Restrlcliun E.Operator Twining Ec License Exartdnatiun F.Adniinislralive G.Operational Error (Explain)
I I Other (Explain) 3 Melhod:
I -hlanual 2-hlanual Scram.
3-Autuinatic Scranl.
4-Other (Explain)
UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO'.
COh(PI.ETEP By Don r;reen TELEPIIONF 205-729-6846 Cause 4 Currcclivc Act lull lu Prcvcnt Rccuncnce No shutdown (turbine over speed test)
No shutdown (turbine trip for recir-culation pump trip test).
LPRM connections were improperly installed.
Exhibit G - Inst rucliuns
~
fur Preparation of Data Entry Sheets Iur Liccnsec Event Report (LER) File (NUREG.
OI6I )
5 Exhibit I - Sante Source
BRCNNB BURRY NUCLBRR PIRNT UNIT~
MECllANICALMAINTENANCE SUGARY For the Month of November 19 78 DATE SYSTEM ll/1 SLC 11/6 RCIC 11/8 RBCCM COMPONENT Valv) 1-63-518 Pedestal slid-ing foot Valve XV 100
't.ONE OF R'iNTHNANCE Valve: - ked MMI ?2 Installed-annubar.
EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION Packing blown N/A Defected annubar RESULTS OF MALFUNCTIO Leak N/A Annubar failure ACTION-TAKEN TO PRECLUDE RECURRENCE Repacked valve MMI 22 Installed annubar 11/11 RCIC Turbine Inboar bearing
.Added ril N/A Excessive oil use Added oil
CSSC E UIPHEHT CROWNS PRRRY NUCLRILR PIANT UNTT~
MECHAHXCAL MAINTENANCE
SUMMARY
For the'Month of November 1978 SYSTEM Various COME'ONENT Snub ers
< NATURE OF MAINTENAI:CE Inspection EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION N/A H/A RESULTS OF MALFUNCTION ACTXOH TAKEN TO PRECLUDE RECURRENCE Visual inspection of all snubbers
.1/7
'1/9 Primary Cont.
SLC Drywall to tor ua air comp-ressor 2B pump R
Oil reple irish ment Installei new packing and
.ad5usted N/A Pump needed
,packing Low oil level Leak Filled oil level Installed new packingl and ad)usted Ll/15 Doors Personnel air lock door Lubricated an ad)usted Latch and keeper
~ -
misad)ustment Loss of seal Lubricated;and ad)ui tei lock, keeper and seals 11/16 HPCI'pray nozzle at HPCI on hig press fog fire prot.
Opened drain valve Header full of water Leak Opened drain valve 11/21 EECW Valve~.2-67-571 Cleaned. out and flushed line Stopped up with mud Ho flow through valv Cleaned out and flushed line
,1l/.23 EECH.
> Valve 67-637
./
Packing Loose packing'eaking valve Tightened packing gland 11/24 Primary Contain-ment Valve 2-,64-578 Loosened 1 ack ing gle;.d Packing gland too tight Hard to open and close Loosened packing gland
DROWNS FERRY NUCLEAR PLANT UNIT 3
MECIIANICALMAINTENANCE SUMIIARY For the Month of November 19 7&
SYSTEM COMPONENT NATURE OF MAINiTENANCE EFFECT ON SAFE OPERATION OF TIIE REACTOR CAUSE OF a MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE RCIC Inboard tur-bine bearing Low oil level N/A Low oil level Filled with oil 11/9 RClC Fuel pool cooling RCIC pot. leve Float free SW LS 71-5 Fuel pool cool Leak s:"op ing pump
~.
Float stuck Loose packing Stuck switch Packing leak Freed float Ad5usted packing
-11/13 11/21 11/22 ll 27 11 29 EECW EECW EECW CPD Stabiliz-ing tralve FCV 3-67-83 3-7-59li FCP 3-67-50 la 3 52 Filter Ire-placement Valve 'leak stop Frozen valve Valve leak stop Valve leak stop Dirty filters Valve leak Rusty valve.
Valve leak Pipe broke H20 pressure drop Valve leak I
Valve inoperative Valve leak i Valve leak I
Replaced, filter Ad)usted diaphragm
- spring, Unstuck and lub'ri-cated Tightened packing.
gland Installed 1 2 S.S.
plug 11/30 11/3 control Rod---.
CRD 30<<59 CRD 3-26-35 Changed'alve Change'cc <miilator Solenoid valve not seating Bad accumulator I
I Solenoid Valve not seating I
I Bad accumulator Changed valve i
Changed accumulator
CSSC E UIEtKNT URClClS PEllRY NUCLEAR PLANT UllIT EIECTRICAL HAINTENAllCE SQSIARY For the Month of November 19 78, Date System Component liat~re of Maintenance ect;on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 11/7 Primary Cont.
XA-6g-16 64-8,64-64B SGT pressure limiter open and lockout alarms will no reset after SGT rw.
None Motor bad on
~ 64-16 Open and lockout alarms would not reset I
Replaced motor. on 64-16, gumpered 64-8 and 64-64B to reset.
Checked ok.
Ann.
cleared.
TR 105548 11/6 Diesel.
Generator Diesel Gen.
C and D
Perform SI 4.9.A.l.d None None STOL1 relay was bad
.on "C" D/G.
Ann.
relay for circui't malfunction was bad on "D"-D/G.
Replaced bad-relays.
Ran SI 4.9.A.l.d Checked ok; TR 87915 11/23 Diesel
. 480V D/G Generator Aux. Bd. A 480U D/G AUK.
Bd. A Room ventilati~n supply dr~per id stuck open None Bad damper moto Improper ventilatip Replaced'ldamper motor.
Checked ok TR 107169
.BRIRRIB FERRY RUCLEAR FLARE IRIYY
.R ELECTRICAL MAINTENANCE
SUMMARY
por the Month of November 19 78 Date System Component Votre of Mai-. "nance ection a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 11/12 Off-Gas CVT relay CVT Relay is burnt u'.
None Bad CVT coil Gas dilution fan 2B could not be trans-ferred A
Replaced CVT coil Checked ok.
TR 109153
,BRNlgg FERRY RUCLEAR PLANT UHIY~
ELECTRICAL MAINTENANCE StJMMARY s
For tlie Month of November 19 78 Page 1 of 3 Date System Component Nature of Hai~".enance ect on a e Operation of The Reactor Cause of Halfunction
'esults of Malfunction Action Taken To Preclude Recurrence CRD CRD Modu1e 10-'23 Hi-water level alarm w4;i not clear Nona Scram accumula-tor level switch bad Hi-water level alar would not clear Replaced scram accumu lator level switch.
Performed EMI 50.
Checked ok.
TR 106596 Core Spray PCV'75-11 Seal in on-tact ig.ot picking up None Close contacts not sealing in.
Seal in contact bent Seal in contact is not picking up when you go to open with 75-llA; When you release the )and switch the valves g
stops Ad5usted seal in contact.
Checked ok
BD 3A Voltmeter ont Voltmeter not 480V S;D..Bd working 3k None Meter was bad I
Voltmeter would not work Replaced voltmeter Checked ok TR 96668 ll 2 Air Cond.
Control Bay Chiller 3A
~
~
FCV 74-1 Perform routin and ma5or main as required.
Repair oil lea FCV 74-1 will not operate by motor None.
None'ormal use s
Motor was bad Dirty freon filter, Dirty oil filter, water regulation valve defective, panel. gauges out of calibration oil leaks on unit Valve could not be operated )y motor Repaired oil'eaks, I
replaced freon filter~,
oil filter. Charged system with Freon 22.
Repaired water regu
'ating valve and calibrated paneL gsagas.'hackad ck TR 106622 I
Replaced motor.
Ran EMI 18.
Checked ok TR 114330
BRIRHIR FERRY HUCLEAR FLAHY UIIYY 3
ELFFCTRICAL MAINTENANCE SUMfARY For the Month of November 1978 Page 2 of 3 System Component I
ect;on a e Nature of Operation of Maintenance The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence ll/2 11/11 Primary Cont.
I Limit switches on FCO-64-14 and FCO-64-13 Diesel Dia hragm on Generator pressure switc
- AP2, Diaphragm is blown on AP2 Limit s:itches need adJusting on FCO-64<<14 and FCO-64-13 None None AP2 press.
sw.
bad
.Limit switches out of adjust-
. ment Low pressure alarm was inoperable
.Air supply inboard isolation damper not working correct ly Replaced AP2 and I.M. calibrate'd it.
Alarm cleared TR 110084 Ad)usted limit switch I
Checked ok.
TR 110042 TR 110043 11/14 Neutron IRM select but Monitoring tons IRM select but tons will not indicate full in position 25-14 None Relays 7C-K9M, 7C-K7M, 7C-K7C, and 7C-K7F had burned up coils Select buttons'ot giving correct in-dications I
Replaced relays 7C-K9M and 7C-K7M and replaced coils in relays 7C-K7C and 7C-K7F, Checked ok TR 110031 14+5-
.CRB HR-RR-AB-Control switch Control swatch is broken None Hand switch is
=
broken on, HS-85-48 Control switch vill Replaced atop plate not operate on hand switch:
HS S5-4S, Checked ok TR 114353 11/16 HPCI i
HPCI gland steam exhauste HPCI gland ste exhauster thc"ma s out after 2 min.
None LeaH contact cli on breaker was loose on finger HPCI gland steam exhauster thermaled out after 2 min.
- Tightened clip to breaker finger, Checked ok.
TR 116306 ll/21 Neutron Monitoring D-SRM D-SRM hm both in-'out light and wil'ot move None Coil bad in relay. 7CK7K In-out lights both Replaced coil in are on and SRM vill relay 7CK7K.
Checks
'ot move ok.
TR 116398
(BROIOIE FERRY ÃIJCLEAR FLARE UIIYY~
ELECTRICAL MAINTENANCE
SUMMARY
Page 3 of 3 Date 11/21 System Primary Cont.
Component Relay 16AK68 Nature of Main'nance 16M(68 is chattering and arcing
~
ect on a e Operation of The Reactor None Cause of Malfunction Bad relay and resistor Results of Malfunction Power ann. circuit would not operate properly Action Taken To Preclude Recurrence Replace relay and resistor.
Checked ok.
TR 116801 11/21 Primary Cont-.
Relay 16$-K23 on pnl 9-42 Burn out-'coil on lnb-K 3 None Bad coil Improper ann.
e I
Replaced coil on relay.
Cl~ecked ok TR 116802 TR 114374 11/22 RCZC FCV,71-10 FCV 71-10 has no,indications light.
None LS3 and LS4 on FCV 71-10 limit arms are out of ad)ustment
~ No indicating light Ad)usted',limit arms, Checked ok.
,TR 116393 11/22 Main Steam FCV 1-27 Red end Eeeen
'ndicating lights are botl on with valve clos'ed None Actuator loose on limgt switch Red and green light both on with valve closed Ad)usted limit switch and tightened actuator.
Checked ok.
TR 114385.
ll/24 11/25 Diesel Gen Neutron Monitoring 3B D/G
~
llFll ZRM Lube oil circu lating pr >n appears t 'av bad bearing Bad con~ector on "F" ZRM None NJne Bad bearings on drive motor
, Pin pulled loose from wire.
Noise and bearing heating up Improper operation of "F" IRH Bearings replaced Checked ok.
TR 114384 Replaced pin on wire and soldered aBnnectioq Checked ok TR 67697
CSSC E UIPHEHT OROUNS PERRY NUCLEAR PLANT UNIT 1 2 3 INSTRUtlEtlT tfAIHTEtbNCE SUMtfARY
'OR'llE llONTE OF November, 197E Date System Component Nature of Maintenance Effect on Safe Operation of the reactor Cause of
,. Malfunction Results of Malfunction Action Taken to preclude recurrence
'.l/15 Standby Liquid Control LI-63-lB JHIT 1 ll/13 Primary PDT-64-138 Containment Calibrati"n
,calibratiE n None None Zero Shift
~
I v
Gage needed rezeroing Did not agree with redundant indicator Did not agree with stick measurement None
'I None SNIT 2 11/6 RCIC 11/10 CRD UNIT 3 11/1 RPIS 11/17 Standby Liquid Control 11/19 RCIC 11/21 RPIS 11/21 RPIS ll/24 HPCI ll/26 Primary Containment
~11/30 PIS FI-71-1A v ~
Pds-85-63,64 Pdobe 34-35 LI-63>>1B
'l-71-1B I
Probe 34-35 Probe.30-51 22-39 FT-73-33 PDI-64-137,138 I
J Probe 42-43 Calibration Replace Replace Calibration.
Calibration Replace Replace Calibr>tb h
Calibrate Replace None None None None None None None None None None Zero Shift Gages damaged I
Bad "4" switch in IO's Column Cage needed rezeroing Zero Shift BaEI reed switches Bid reed switches.:
Zero Shift Zero Shift Bad reed switch Indicatedl flow when out Iof service Indicated high 5 P No. "4'n IO's Column Didl not agree with 1X of stick measurement Indicated flow when shut down No 10, ll, 14, 15, 18 or 40 indication o
OD thru 09 indicatio Indicated flow when off eadings did not agree o "04" indication None None None None None None None None None I
None 'E3 '
27 OUTAGE SECTION MONTHLY REPORT November 1978 Puel loading for unit three was completed November 9, 1978, and investigations into rod problems resulted in the changeout of the rod 46-39 and realignment of the fuel support casting.
These rod problems and corrective actions lost a total of 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> in critical path time.
The RPV leak rate test identified the following leaks:
Instrumentation flange, 2" Vent line in the drywell, valve 43-13 leaking, MSSV 1-537, bonnet leak on 74-54, and CRD flange leaks.
Subsequent repairs and changeout of the safety valve caused the startup testing to slip from November 20 to November 22, 1978.
A1l. refuel floor activities were completed November 20, when the shield blocks were installed.
All dryweU. work, modification work and instrument work were completed November 21, 1978 except for post-mod tests and those tests to be completed during the startup testing sequence.
The Held breakers were closed on unit 3 on November 25, ending the unit 3 cycle 1 refueling outage.
Preparations commenced immediately for the unit,l refuel outage which began November 26 at 8:53 p.m.
Vessel disassembly of unit 1 went smoothly with only minor delays.
The initial drywell entry revealed leaks on 68-33, -77 and 3-99, 98.
The A, C, and D MSIV's failed the Local Leak Rate Test (LLRT) and will be repaired.
At the end of the period the unit 1 outage is approx&ately 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> behind the overall planned outage.
0 4