ML18024B345
| ML18024B345 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/03/1980 |
| From: | Green D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024B344 | List: |
| References | |
| NUDOCS 8002190659 | |
| Download: ML18024B345 (34) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OP POWER PRODUCTION BROWNS PERRY NUCLEAR PLANT MONTHLY OPERATING REPORT January 1,
1980 - January 31, 1980 DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS DPR-33, DPR-52, AND DPR-68 Submitted By:
Plant SuPerintendent
TABLE OF CONTENTS Operations Summary
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Refueling Information Significant Operational Events Average Daily Unit Power Level Operating Data Reports Unit Shutdowns and Power Reductions.
Plant Maintenance
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Outage Summary
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0 erations Summa January 1980
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mM1, c4 Ak 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 twelve reportable occurrences reported to the NRC during the month of January.
Unit 1 The unit was manually scrammed on January 3 for EOC-3 refuel outage.
Unit 2 There were no scrams on the unit during the month.
Unit 3 There were two scrams on the unit during the month.
On January 17 and 18, the reactor scr'ammed due to high-high flux when reactor pressure spiked because of //2 main steam stop valve closure.
0 erations Summa (Continued)
January 1980 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 0.00423 0.20361 0.17971 0.00317 0.13592 0.11572 0.00291 0.10715 0.08728 Note:
This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.
Common S stems Approximately 1.45E+06 gallons of waste liquid were discharged containing 1.43E+00 curies of activity.
Refuelin Information January 1980 Unit 1 Unit 1 began its third refueling (EOC-3) on January 3, with a restart date of February 26, 1980.
This refueling will involve loading additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel, LPCI modifications, installing acoustical monitors on iiSRV's, and containment isolation modifications.
There are 764 fuel assemblies in the reactor vessel.
The spent fuel storage pool presently contains 650 spent 7 x 7 fuel assemblies, four 8 x 8 fuel assemblies, two 8 x 8 R fuel assemblies, and 20 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 x 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,
Refuelin Information (Continued)
January 1980 Unit 2 (Continued) 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 is scheduled for its third refueling beginning on September 6,
1980, with a scheduled restart date of October ll, 1980.
This EOC-3 refuel-ing involves loading additional 8 x 8 R (retrofit) assemblies into the core.
There are 764 fuel assemblies presently in the reactor vessel.
There are 144 discharged cycle 2 fuel assemblies and 208 discharged cycle 1 fuel assemblies in the spent fuel storage pool.
The present storage 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.
Si nificant 0 erational Events Unit 1
Date Time Event
" 1/01/80 0001 Reactor thermal power at 84%, all rods fully withdrawn, core limited 1/02/80 2120 Reduced thermal power 84% to 75% for special test number 165 (Rod Block Monitor) 1/03/80 0620; 0705 2220 2342 Special test number 165 completed, commenced power ascension Reactor thermal power at 82%, core limited Commenced reducing thermal power for unit shutdown for end of cycle 3
Reactor scram no.
117 from 35% thermal power manual to accommodate refueling outage (EOC-3) 1/11/80 0500 1/31/80 2400 Commenced fuel handling operation Refueling outage (EOC-3) continues
Si nificant 0 erational Events Unit 2 Date Time Event 1/01/ 80 0001 1/06 /80 0005 0025 0040 2320 Reduced thermal and SI's (tests Commenced power Reactor thermal Reduced thermal and SI's power from 98% to 85% for turbine CV test were not performed) ascension power at 98%, rod limited power from 98% to 85% for turbine CV test Reactor thermal power at 98%, rod limited, sequence "B"
1/07/80 0200 0830 1413 Turbine CV tests and SI's completed, commenced PCIOMR Reactor thermal power at 98%, rod limited Reduced thermal power from 98% to 77% for removal of "A" condensate pump from service (high vibration) 1/10/80 1500 1/13/80 1327 1535 Reactor thermal power at 77%, holding for "A" condensate pump maintenance
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"A" condensate pump maintenance completed and pump placed in service, commenced power ascension Reactor thermal power at 96%, rod limited 1/14/80 2300 1/15/80
- 1320, Commenced PCIOMR from 96% thermal power Reactor thermal power at 97%, rod limited 1/17/80 1/19/80 1500 1807 2255 1/21/80 2116 Reactor thermal power at 97%, rod limited Reduced thermal power from 97% to 78%- for removal of "C" reactor feed water pump from service for maintenance (high vibration) 4 Reduced thermal power from 78% to 53% for'removal of "B" recirculation pump MG set for brush replacement "B" recirculation pump MG set brush replacement completed, commenced power ascension 1/22/80 0700 Reactor thermal power at 78%, holding for "C" reactor feed pump maintenance 1/25/80 2130 Reduced thermal power from 78% to 50% for control rod pattern adjustment 1/26/80 0035 0200 2300 Control rod.'pattern adjustment completed, ascension Commenced PCIOMR from 60% thermal power Reactor thermal power at 74%, holding for pump maintenance commenced power "C" reactor feed
Si nificant 0 erational Events Unit 2 Date Time Event 1/28/80 0410 Increased thermal power from 74% to 78%, holding for "C" reactor feed pump maintenance 1/29/80 1030 1200 "C" reactor feed pump maintenance completed, commenced power ascension Commenced PCIOHR from 80% thermal power 1/31/80 2400 Reactor thermal power at 98%, rod limited
Si nificant 0 erational Events Unit 3 Date Time Event 1/01/80 0001 1/16/80 0220 0345 1424 1517 Unit at cold shutdown for maintenance (alternate power supply from cooling tower transformers to Unit 3 shut-down bus tie board) e Maintenance completed,.commenced rod withdrawal Reactor critical no.
89 Rolled T/G Synchronized generator, commenced power ascension 1/17/80 0511 0955 1244 1910 1952 Reactor scram no.
80 from 75/ thermal power while testing the no.
2 stop valve which closed causing a reactor scram due to pressure spike Commenced rod withdrawal Reactor critical no.
90 Rolled T/G Synchronized generator, commenced power ascension 1/18/80 0430 0606 0949 1127 1135 Commenced PCIOMR from 52% thermal power, sequence "A"
Reactor scram no.
81 from 60% thermal power on high APRM flux while performing number 2 turbine stop valve test Commenced rod withdrawal Reactor critical no.
91 Reactor made subcritical for EHC maintenance 1/19/80 2044 2230 1/20/80 0240 0312 1530 EHC maintenance completed, commenced rod withdrawal Reactor critical no.
92 Rolled T/G Synchronized generator, commenced power ascension Commenced PCIOMR from 67% thermal power 1/22/80 0700 1/25/80 1500 1845 2300 Reactor thermal power at 98%,
maximum turbine power Reduced thermal power from 98% to 95% for LPRM calibration and TIP run LPRM calibration and TIP run completed, commenced power ascension Reactor thermal power at 98%, rod limited 1/26/80 0020 0145 0840 1823 1925 Reduced thermal power from 98% to 85% for turbine CV tests and SI's Turbine CV tests and SI's completed, commenced power ascension Reduced thermal power from 92% to 82% for control rod mainte-nance (replaced filters and drive direction control valve on CRD 18-55)
Completed maintenance on control rod 18-55, commenced power ascension Reactor -thermal power at 98/, rod limited
Si nificant 0 erational Events Unit 3
Date Time Event 1/29/80 1643 Reduced thermal power from 98% to 75% for removal of "C" reactor feed pump from service for balancing the shaft (high vibration) 1/30/80 0807 0930 1500 "C" reactor feed pump power ascension Commenced PCIOHR from Reactor thermal power placed in service, commenced 92% thermal power at 98%, rod limited 1/31/80 2400 Reactor thermal power at 98%, rod limited
10 AVERAGE DAILYUiVITPOWER LEVEL DOCKET NO.
UNIT COMPLETED BY Ted Tham TELFPHOiVE 205/729-6846 MONTH January 1980 DAY AVERAGE DAILYPOWER LEVEL (MWe.iVet) 883 836 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)
-3 17 18
~-3 10 12 13 14 15 l6 788
-10 19 20 21 22 23 24 25 26 27 28 29 30 31
-2 INSTR UCTIOiVS On this tonnat. !ist the average daily unit power level'in/)we Net for each day in the reporting month. Ciimpute to the nearest whole megawatt.
('>/77)
11 AVERAGE DAILYUiVITPOPOVER LEVEL DOCKET NO.
50-260 UNIT COMPLETED IIY Ted Tham TELEPHOiNE 205/729-6846 MONTH January 1980 DAY AVERAGE DAILYPO'IVER LEVEL (ilI1Ve-Net) 1084 DAY AVERAGE DAILYPOPOVER LEVEL (MWe-Net) 1050 17
': ~ 3 7
8 10 12 13 14 IS 16 1042 1071 1063 1066 944 819 829 82 1039 1045 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1077 958 799 810 830 821 820 801 727 781 818 841 1014 1058 INSTR UCTIONS On this format,!ist the avcra8c daily unit pointer level'n Mme-Net for each day in the repiirtin8 iniinth. Compute to the nearest whole mcgawat t.
(')/771
12 AVERAGE DAlLYUNITPOWER LEVEL DOCKET NO.
50-296 UNIT
~ 3 DATE CO!iIPLETED BY 2
8 ilIONTH Januar 1980 DAY AVERAGE DAILYPOWER LEVEL (MWe.Net)
I
-10 DAY AVERAGE DAlLYPOWER LEVEL (MWe Net) 224 17
':- 3 4
5 6
10 12 13 14 15 16
-10
-10
-10
-10 177 IS 19 20 21 22 23 24 25 26 27 28 29 30 31 169
-12 5 6 8 945 1064 1075 1068 1056 922 1025 1077 987 985 1067 INSTRUCTIONS On this format. !is: the average daily unit power levei'in iblEVc.Nct for each day in the reporring month. Compuu to the nearest whole megawat t.
(9 I77)
13 OPERATING STATUS OPERATING DATAREPORT
'o DOCKET NO.
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~50-259 DATE COMPLETED BY TELEPHONE ~~o -6846 Notes Browas Ferry 1
- 1. Unit Name:
- 2. Reporting period:
Jartua 1980
- 3. Licensed Thermal Power (4~OVt):
- 4. Nameplate Rating (Gross 41DVe):
- 5. Design Electrical Rating (Net hOVe):
- 6. 4Maximum Dependable Capacity (Gross MIVe):
De endable Ca acit Net Mme:
7.
4 Iavtmum p
p y (
)
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N/A r
- 9. Power Level To which Restricted, IfAny (Net Mme):
N/A
- 10. Reasons For Restrictions, IfAny:
- 11. Hours In Reporting Period
~ 12. Number Of Hours Reactor 1Vas Critical
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
'16. Gross Thermal Energy Generated (M')VH)
- 17. Gross Electrical Energy Generated (MlVH)
- 18. Net Electrical Energy Generated (MPH)
- 19. Unit Service Factor
- 20. Unit AvaihbilityFactor
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DFR Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months This Month 744 7.1.
0 71.7 0
84 2
Yr.-to-Date 744 0
F 71.7 0
23 547 973 61 960 61 960
'57 164 57,164
.6 9.6 7.2 7.2 0
9.6 9.6 7.2 7.2 0
(Type. Date. and Duration uf Each):
Cumulative 48,242 4,689.
1 27;684.4X 74 320.645 24 580 420 23,859,132 57.4 57.4 46.4 46.4 32.9
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status {Priorto Commercial Operation):
22 80 Forecast Achieved INITIALCRITICALITY INITIAL ELECTRICITY COhihIERCIAL OPERATION (o/77)
14 OPERATING STATUS I. Unit Name:
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Namephte Rating (Gross MWe):
5: Design Electrical Rating (Net MWe):
a i m De endable a acit Net ilDVe:
OPERATING DATAREPORT Notes DOCKET NO. 50.-'260 DATE 2~2 COMPLETED BY ~~~>~
TELEPHONE ~~o" 46
- 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:
N A
- 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)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit AvaihbilityFactor
'1.
Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months This Month 744
~ 744 0
744 0
Yr.-to-Date 744 744 0
744 0
100 87.0 87.0 0
100 87.0 87.0 0
(Type. Date.and Duration of Each):
Cumulative 43.,153 25,228.48 11,774.94
24 408.31 0
56.6
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47.9 47.9 36.1
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 6. Units In Test Status IPrior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY CORDI E R CIAL OPERATION (oi77)
15 OPERATING DATAREPORT DOCKH NO DBTE 2'-BO COBVPLETED BY n
TELEPHONE 205 729-6846 OPERATING STATUS Not.es
- 1. Unit Name'rovrns Fer 3
- 2. Reporting period:
Januar 1980
- 3. Licensed Thermal Power (hIWt):
- 4. Nameplate Rating (Gross hIWe):
- 5. Design Electrical Rating (Net hIWe):
1065 b e a acit Net MWe:
ed
- 7. Maximum Dependa I
C p y (
)
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
N A N/A
- 9. Power Level To Which Restricted, IfAny (Net ice):
- 10. Reasons For Restrictions, IfAny:
N/A This Month 'r.-to-Date
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Cumulative 2
08 19 239.98 332.43 1,658.31 17 868 842 54 020 224 17 708 560 305 980 17,182,055 294,282 41.5 73.2 73.2 41.5 63.0 37.1 3.0
, 12. Number Of Hours Reactor >Vas Critical 332.43
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line
- 15. Unit Reserve Shutdown Hours
'16. Gross Thermal Energy Generated (MWH) 912 358 ly. Gross Electrical Energy Generated (bttVH) 305 980
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit AvailabilityFactor 41.5
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over'Next 6 Months (Type. Date. and Duration of Each):
a
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COhlhIERCIAL OPERATION (o(77)
UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT htONTII DOCKET NO.
UNITNAhtE DATE COMPLETED IIY TELEPItONE 50-259 Don Green 205 72 -68 Date r)
~fl)
Cl fP
~ )/l Liccnsec Event Rcport 0'
)
C0 u Q
C ~
Cause &Corrective A).lion lo Prevt.nt Rct.urrcn).e 108 800103 672.3 2
I F: Forced S: Scheduled
()>/77)
Reason:
A Equipment Failure (Explain) t).htaintenance or Test C.Refueling D-Itcgulatory Restriction I:..Operator Training & Liccnsc Examination I"Adnun)St ra live G.Operational Error (Explain)
I I.Other (Iixplain) 3 Method:,
I.Manual 2 Manual Scram.
3-Aulonlat ic Scram; 4-Other (Explain) 4 Exhibit G - Instructions for Prcparalion of Data Entry Shccls I'or Licensee Event Rcport (LERIFile (NOREG-OI6I).
5'xhibit I - Sante Source
1 UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNITNAhlE.
DATE COh(PLETED DY TELEPHONE 50-260 Don Green Ni>.
Date gP)r N Jn Q
CL C
Liccnscc Event Rcport ~
~
CJ~
0C la C ~
O Cause A. Ct>ffccl>ve Acl>on lo Prevent Rccurrcnce 113 800107 114 800119 115 800121 S
116 800125 A
A B
Derated for maintenance to "A" condensate um (hi h vibration)
Derated for "C" reactor feedwater um maintenance (hi h vibration)
Derated for "B" recirculation pump MG set brush re lacement Derated for control rod pattern ad ustment F: Forced S: Scheduled Reason:
A.I'.quipment Failure (Explain) ll.hlaiotcnancc or Test C.Rct ucling D Regulatory Restriction I'. Ot>erat>>r Training & Liccnsc Exa>nination I'.Ado>ioistralivc G Opc f'> ti>o>al Lrrur (Explain)
I I Other (Lxpla>n) hlethod; l hlanual 2.htaoual Scram.
3-Aututnatic Scram.
4-Other (Explain)
Exhibit G - Instructions for Preparation of Data Lorry Sheets Iof I.>ecosoc Event Report (I.I!RTPili'(NOREG-Ol 6l )
Exhibit I - Sao>c Source
UNITSIIUTDOWNS AND POWER REDUCTIONS REPORT MONTII
'DOCKET NO.
50 296 UNITNAMF Browns Ferr 3
COMPLETED BY N<I.
Date I
J
'a n
Z IN Licen sec Event Rcport +
C 0
D Q
Q Cause &. Corrective Action to I'revcnt Rccurrcnce 112 800101 113 800117 114 800118 115 800129 375.28 A': 2 14.69 A
3 45.10 A
A Installation of overhead cables from cooling towers transformers to bus ti boards continues.
During testing no.
2 stop valve close causin a s ike in reactor ressure.
APRM high flux while performing no.
2 stop valve test.
Unit remained down for maintenance to the EHC s stem.
Derated for "C" reactor feedwater pum balancin (hi h vibration).
F: Forced S: Scheduled
('t/77)
Reason:
A Equipment Failure (Explain)
B.IIIaintenance or Test C.Refu'cling D.Regulatory Restriction li-OIIcIIItorTraining & License Examination I -hd IniIIislrativc G (Jpcr:Illollai I:rrt)f(Explain)
I I.OIhcr (I:xplaIn)
Method:.
I.hlanual 2 Manual Scram.
3.Automatic Scram.
4-Other (Explain)
Exhibit G - Instructions I'or Preparat tun of Data Entry Shccls for Ltccnsec Event Report (LER) File (NOREG-OI 6 I )
Exhibit I ~ S:Intc Source
CSSC E UIPHFNT BROWNS FERRY NUCLEAR PLANT UNIT 1
MECIQliICALMAINTENANCE
SUMMARY
For the Month of January 19 80 Page 1 of 4 BATE SYS TEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF IfALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 1/12 Off-Gas 1/16 CRD 1-66-138, 617 o8 26-23, 30-27, 22-23, 26-27, 18-23, 22-27, 14-23, 18-27, 10-23, 14-27, 06-23, 10-27, 18-31, 22-31,
~26-31, 26-39, 22-39, 18-39, 14-39 Repack Randomly sampled and rebuilt 38 scram pilot valves None None Packing Leaking Random sample preventative maintenance Leaking Rebuilt valves Replaced packing Rebuilt all 38 valves consisting of body 0-rings and plunger 1/2 Recirc.
FCV 68-77 Adjust and/or repack with graffoil None Preventative Maintenance Leaking Checked adjustment on packing 1/16 CRD
'26-23, 30-27, 22-23, 26-27, 18-23, 22-27, 14-23, 18-27, 10-23, 14-27, 06-23, 10-27, 18-31, 22-31, 26-31, 26-39, 22-39; 18-39, and 14-39 Random sampled arid rebuilt.
19 hydraulic control unit cartridge valves None Random sample preventative maintenance P M Rebuilt valves eplaced all 19.
draulic control artridge valve acking
BROWSES FERRY NUCLEAR PIAHT UNIT 1
HEC1QQIICAL HAINTEKKNCE
SUMMARY
Page 2 of 4 SYSl'EM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE PECURREhCE 1/16 CRD Modules N6.
26-23, 30-27$
22-23, 26-27, 18-23, 22-27, 14-23; 18-27, 10-23, 14-27, 06-23, 10-27, 18-31, 22-31, 26-31, 26-39, 18-39, 14-39 Random sample and rebuilt scram pilot valve dia-phragm None Preventative Maintenance random sampling P.H.
New diaphragms Installed 38 scram installed valve diaphragms TR 137620 1/10 Recirc.
1-68-552,
-554 Leaking throu x
Hone Inner seats loos Tightened valve seat ightened inner seatq.
1/15 1/18 1/18 1/20 1/20 1/20 1/2 1/2 Off-Gas.
Recirc Recirc Recirc Recirc Recirc FSV 1-176B "A" pump Hodule 06-15 FCV 68-1 FCV 68-79 FCV 68-3 FCV 68-35 FCV-68-33 Broken Stem Filter dirty Leaking through SH Check packing SM Packing Loose SM Check Packing SH Check Packin SM Check Packing None None None None None Nore None None Broken Stem Dirty filter Trash Under seat Packing leak Packing leak None None None Stem broken Filter dirty Vould not close completely Leaking packing Leaky packing None hone None Removed bonnet and stem, machined and installed new stem nd replaced bonnet hanged filter one hecked adjustment n packing djusted packing hecked packing Checked packing Checked packing
CSSC EOUIPhfrNT BROWNS FERRY NUCLEAR PLANT UNIT 1
MECHANICAL MAINTENANCE SUMO.RY Page 3 of 4 DATE SYSTEH 1/21 RCIC COMPONENT FCV 71-2 NATURE OF MAINTENANCE SM Adjust and/or repack packing EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION SM Packing check RESULTS OF MALFUNCTION None ACTION TAKEN TO PRECLUDE RECURW~t CE Checked packing 1/21 HPCI 1/2 HPCI FCV 73-3 FCV 73-2 Packing leak Press.
seal leak None None Pressure seal leaking Press.
seal leaking Leaking steam Pressure seal ring needed tightening Installed new pressur~
seal ring, repacked valve and installed 1-;73-584 and 585 i
Adjusted,packing
'g1 and 1/23 RWCU 1/2 RWCU HCV 69-500 FCV 69;2 SM P"cking SM Packing None.
None None Packing gland loose None Leaking
'Checked packing
~'
Tightened packing gland 1/2 RWCU FCV 69-1 SM Packing None None None Checked packing 1/2 Fire Protection 1-26-797 Stem off seat None Would not open Installed new valve Replaced with new valve 1/2 HP('I 1/2 CRD 1/2 CRD HPCI cooling water line Accumulate r 58-23 Directional control valve Uni,on leak Will not close Will not settle back None None hone Service Rupt;ured valve cartridge Unknown Union leak Valve cartridge ruptured None Cleaned znd tightene union Installed new valve cartridge Operated a rumber of times
CSSC EOUIPlIENT BROWHS FERRY NUCLEAR PlANT UNIT 1
MECllANICALMAINTENANCE SU1 MRY For the Month of january 19 Page 4 of 4 DATE SYS~
COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF TllE REACTOR CAUSE OF MALFUNCTION ACTION TAKEN RESULTS OF TO PRECLUDE MALFUNCTION
~
RECURRENCE 1/31 Feedwater 3-552, 3-553 Leaking throu h Steam Steam leak Replaced with rew val es Installed three each new valves 1/2
~
HPCX 1-73-584,
-585 Leaking through None Valve leaking through seat Would not isolate completely 1
Installed new valve
BROWNS FERRY NUCLEAR PLANT UNIT 2
MECHANICAL ?JAINTENANCE SUJJMARY 1/15 SYSTEM jjPCI COMPONENT 73-587 EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR Leaky packing None CAUSE OF MALFUNCTION Service RESULTS OF MALFUNCTION Leak on packing ACTION TAKEN TO PRECLUDE RECURRENCE Tightened. packing glanc.
1/22 CRD 2A pump Lcw oil level. None Lcw oil cooling water lines Low oil Added oil to speed reducer
- 1/23 Pump 2A Bearing and oil change None Service and bearing wear L'irty oil Drained oil, cleane
- casing, changed bea
- ings, added new oil and greased
~ 1/30 FCIC Inst. hangers Loose hanger None Vibration Hangers off inst.
lines Installed new hangers 2-74-2 Valve stem guard off None Vibration Valve stem cover off limitorque operator Reinstalled valve stem cover
CSSC E UIPHENT BROWS PERRY NUCLEAR PLANT UNIT HEC33ANICAL Y~gl3<TERQlCE SUHHARY por the hoorh of.
Jaroary yy 80 Page 1 of 2 DATE SYSTEll COMPONENT NATURE OP MAINTENANCE EPPECT ON SAFE OPERATION OP T33E REACTOR CAUSE OF YALPUNCTION RESULTS OF 31ALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 1/2 RCIC 3<ain Steam FCV 71-3 3-1-56 Leaking flang Leaking flang None Hone Service Service Flange leak Flange leak Tightened packing and seal ring TR 158730 Tightened leak TR 158732 1/3 1/4 Peedwater 3-554 "A" sucj:ion
, filter Gasket leak Dirty filter None None Wrong gasket installed Dirty filter Leaking gasket High Replaced gasket with new and correct gasket TR 158731 Installed new filter.
TR 158092 ~
1/4 Cc re Spray "A" pump dis-charge - lower elbow Leaking None Broken nipple and loose fitting Seal water leak Replaced ni,pple and tightened loose fittings.
TR 158740 1/7 CRD 1/9 1/11 CRD East filter PCV-69-2 Actuator 30-27 Dirty filter Press.
seal leak Leaking packing None None None Dirty filter Service Service Dirty filter Leaking press.
seal Leaking packing Installed new filter.
TR 158761 Replaced pressure seal.
TR 132400 Tightened packing.
TR 150628
CSSC E UXPMENT BRO'fJNS FERRY NUCLEAR PLANT UNIT 3
-MECliANICALMAIHTENANCE
SUMMARY
For the Month of January 19 80 Page 2 of 2 DATE SYSTEM 1/17 CRD COMPONENT "B" discharge filter EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR Dirty filters None CAUSE OF tfALFUNCTION Dirty fi1ter RESULTS OF MALFUNCTION High gp ACTION TAKEN TO PRECLUDE RECURRENCE Replaced filter with new one.
1/17 RHR "b" pump discharge check valve Flange leak hone Flange leak Flange leak Tightened flange TR 158077 1/28 CRD 3A pump Cooler and piping dirty None Dirty tubes and piping Not cooling properly Cleaned cooler and piping TR 151532 1/29 CRD 3B pump Cooler and piping dirty None Dirty tubes and piping Not cooling properly Cleaned cooler and v'
piping.
TR 151533
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CSSC E UIPHENT EROl'HS FERRY 'EIICLEAR PLAitY VtiIY ELECTRICAL MAINTENANCE SE'MARY I'or the Month of January 19 80 Date System Component Nature of Maintenance E
ect on a e Operation of The Reactor
'ause of Malfunction Results of AMalfunction Action Taken To Preclude Recurrence 1-30-80 D/G "B" battery charger D/G I Bll battery charger or exhaust fan Abnormal
'larm wi11 not clea'r None Bad resistor
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. Resistor burned copen in D/G "B" charger Replaced resistox, checked charge vol-tage.
Voltage same as A
char ger Checked OK.
TR 151627 P
CSSC E UIEMNT BROTHE EERRX EUOLEAR PLSilT UllXT 2
ELECTRICAL MAINTENANCE SALARY Date
'System Component Nature of Maintenance E
ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 1-17-80 Control air FSV-2-32-91 does not have red light burning Red light is not burning when valve is open None' Limit switch is out of ad)ust-.
ment Limit switch out of ad)ustment Ad)usted limit switch on open unit so red light would work when valve was open.
Functioned FCV 91 and lights checked OK.
TR 146339
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CSSC EQUIPMENT BROGANS FERRY NUCLEAR PLANT UNIT INSTRUMENT MAINTENANCE
SUMMARY
FOQ THE MONTH OF January 19 80 DATE.
SYSTBf Unit 1 1-2-80 Standby Liquid Con-trol COMPONENT TIC-63-2 NATURE OF MAINTENANCE Calibrate EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION Setpoint Drift RESULTS OF MALFUNCTION Temperature Lower Than Normal
. ACTION TAKEN TO PRECLUDE RECURRENCE None Unit 2 1-2-80 adiation onitoring RM-90-250 Repair None Leak in Hose Flow Rate Cycling
. None Unit 3 1-2-80 ain Steam FT-1-50, Pdis-1-50A,B C
& D Vent None Air in Sensing Line Instrument Spiking with Pressure Change None l-2-80 rimary Con tainment LI-64-66 LI-64-54 Calibrate None Instrument Drift Did not agree with Redundant Indicator None 1-8-80 1-9-80 Primary Con tainment Primary Con tainment FT-64-37 PR-64-50 Calibrate Repair None None Instrument Drift Inop, Recorder Am Reading did not agree with pilot traverse
.No response on Recorder None None 1-10-8 RHR Service Cater 1-18-8 Residual Heat Removal PM-23-48 PIS-74-64 Replace Calibrate None None.
Faulty Flow Modi-fier Setpoint Drift Incorrect Flow Indi-cation Minimum Plow Valve Did Not Close Off At Proper Flow Rate None None
OUTAGE
SUMMARY
January 1980 Unit 1 The, Unit 1 cycle 3 refueling outage started late January 3, with reactor shutdown at 2342 hours0.0271 days <br />0.651 hours <br />0.00387 weeks <br />8.91131e-4 months <br />.
(Assumed outage start point for record purposes is 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on January 4.)
The planned outage was scheduled for 48-1/2 days (breaker-to-breaker).
In addition to refueling the
- reactor, other major work planned includes: modifications to the number four feedwater heaters; the integrated leak rate test (ILRT); MSIV and MSRV valve work; selected control rod drives (34-27, 46-39, 34-19 and 38-39); low pressure turbine "C" inspection; inspection and repair of A and D control valves, combined intercept valve 1Al and 1B2, main stop valve 1, and bypass valves 1, 2, and 3; changeout of rotating elements of the reactor feed pumps; eddy current testing on feed water heaters and condensers; LPCI modification; addition of relief valve position indicators; and pipe hanger and configuration inspection.
The shutdown was normal and vessel disassembly proceeded without major problems.
The removal of LPRM maintenance interference fuel assemblies was delayed due to bridge malfunction and search efforts for missing objects.
The refueling shuffle started on January 16, at 1642 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.24781e-4 months <br />, approximately 2-2/3 days behind schedule with fuel movement (FATF) step f/137.
In spite of having to dechannel and inspect the old fuel bundles being reloaded (116 'total) into the core for dropped fuel tags, the required refueling operation was '
32 OUTAGE
SUMMARY
(Continued)
January 1980 Unit 1 (Continued) proceeding on schedule at the end of the month.
Scheduled modifications were also on schedule.
The MSIV and H4 check valve repairs are behind the schedule due to problems.
The turbine work was on schedule;
- however, the stop and bypass valve work is awaiting completion of the MSIV outboard valve repairs.
Unit 3 The modification to provide an alternate power supply to the shut-down bus tie board as originally designed (four bundles) was completed and energized on January 29.
Work is continuing on installation of two additional bundles.