ML18024A800
| ML18024A800 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1979 |
| From: | Dewease J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A799 | List: |
| References | |
| MOR-790430, NUDOCS 7905150352 | |
| Download: ML18024A800 (36) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT April 1, 1979 - April 30, 1979 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 Refueling Information Significant Operational Events
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5 Average Daily Unit Power Level
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13 Operating Data Reports Unit Shutdowns and Power Reductions.
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16
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19 Plant Maintenance
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22 Outage Section Monthly Report.
" 34
0 erations Summar The following summary describes the sign c
p ificant o erational activities during the reporting period.
Xn support of this summary a chronological logo s gn f i ificant events is included in this report.
es re orted to the NRC during There were three reportable occurrences rep the month of April.
Unit 1 d
i d
ing the month.
The unit scramm ed on A ril 2 The unit scramme tw ce ur P
ine tri.
The turbine trip occurred due to stop valve closure from a turb ne tr p.
as a result of a false mo sture s
i t e separator high level signal apparently f
loose sensing line on C2 moisture separator.
generated by vibration o a
oose The unit scrammed on pr A il 29 due to stop valve closure from a turbine trip.
e ur Th t bine trip occurred as a resultt of a false reactor high ed due to a breaker opening and resultant loss water level signal generate ue to a of power.
Unit 2 d i the month.
The unit was manually The unit scrammed once ur ng e m scrammed on pr A il 27 to accomodate the scheduled refueling outage.
Unic 3
The unit did not scram during the month.
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 0.18684 0.17378 0.11861 0.09515 0.10335 0.07339 0.00407'.00270 0.00243 Note:
This accumulated monthly information satisfies technical specification section 6.6.A.17.b(3) reporting requirements.
Common S stems Approximately 2.56E+05 gallons of waste liquid were discharge containing 1.55E-Ol curies of activity.
Cooling towers 1, 2, 3, and 6 were operational.
Repair work on Tower 4 began on April 10, and is to be completed by May 8.
Repair work on Tower 5 was completed on April 30.
Installation of new fillmaterial on Tower 5
continues.
Refuelin Information Unit 1 Unit 1 is scheduled for its third refueling beginning on or about December 15, 1979, with a restart date of January 25, 1980.
This refueling will load additional 8 x 8 R (retrofit) fuel assemblies into the core, replacing presently loaded 7 x 7 fuel.
Unit 1 (Continued)
There are 764 fuel assemblies in the core.
The spent fuel storage pool presently contains 322 spent 7 x 7 fuel assemblies and two 8 x 8 R fuel assemblies.
Because of modification work to increase spent fuel pool capacity to 3471 assemblies, present capacity is limited to 520 assemblies.
- pith present
- capacity, Unit 1 does not have full core discharge capability in the pool.
Unit 2 Unit 2 began its second refueling beginning on April 27, 1979, with a'cheduled restart date of June 7, 1979.
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 to the NRC in February.
This refueling will involve 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 (7 x 7) fuel assemblies in the spent fuel storage pool.
There are presently 268 new 8 x 8 fuel assemblies in the spent fuel storage pool.
The present storage capacity of the spent fuel pool is 1080 assemblies.
Present planning is to increase that capacity to 3471 assemblies.
With present
- capacity, the 1979 refueling would be the last refueling that could be discharged to the'pent fuel pool without exceeding tha't capacity and maintaining full core discharge capability in the pool.
Unit 3 Unit 3 is scheduled for its next refuel outage beginning on September 1,
1979, with a scheduled restart date of November 20, 1979.
This refueling will involve loading additional 8 x 8 R (retrofit) assemblies into the
- core, torus integrity modifications, core spray piping modifications, EECW
~.piping changes, feedwater sparger modifications, and LPCI modifications.
Resumption of operation following refueling will require changes in technical specifications pertaining to the core thermal limits.
Licensing information in support of these changes will be submitted before the refueling.
There are 764 fuel assemblies presently in the core.
There are 208 fuel assemblies in the spent fuel storage pool.
The present licensed storage capacity of the spent fuel pool is 1132 assemblies.
Si nificant 0 erational Events Unit 1 Date Time Event 4/1/79 0001 0030 2230 Reactor thermal power at 66%,
sequence "B", holding for control rod pattern adjustment Control rod pattern established, commenced PCIOMR from 66% thermal power Reactor thermal power at 97%, rod limited 4/2 1440 1635 1840 2000 2015 Reactor scram no.
110 from 97% thermal power due (1) to turbine trip and stop valve closure Commenced rod withdrawal Reactor critical no.
126 Rolled T/G Synchronized generator, commenced power ascension in sequence "B"
4/3 0250 4/5
'710 4/6 2145 Commenced PCIOMR from 60% thermal power Reactor thermal power at 96%,. rod limited Reduced thermal power from 96% to 70% for turbine C.V. tests and SI's 4/7 0115 0300 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 75% thermal power 4/8 2105 Reactor thermal power at 98%,.steady state 4/13 2330 Reduced thermal power from 98% to 85% for turbine C.V.
tests and SI's 4/14 0105 0400 0450 Turbine C.V. tests and SI's completed, reduced thermal power further to 75% for removal of "B" condensate booste pump from service for maintenance "B" condensate booster pump maintenance completed, placed pump in service, commenced power ascension Commenced PCIOMR from 90% thermal power 4/15 1500 Reactor thermal power at 98%, steady state 4/16 0217 0420 0445 1630 Reduced thermal power from 98% to 75% for removal of "A" reactor feedwater pump for maintenance "A" reactor feedwater pump maintenance completed, pump returned to service, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 98% steady state
Si nificant 0 erational Events Unit 1 Date TfRe Event 4/21 1915 2312 Reduced thermal power from 98% to 90% due to "C" string low pressure feedwater heaters isolation (broken air line)
Reduced thermal power from 90% to 85% for turbine C.V. tests and SI's 4/22 0100 0120 0700 Turbine C.V. tests and SI's completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state 4/25 0805 0810 1200 Reduced thermal power from 99% to 85% due to both recirculation pumps run back during SI (feedwater controls malfunction)
Commenced power ascension Reactor thermal power at 99%, steady state 4/26 4/27 1500 2300 Reactor thermal power at 99%, steady state.
Reduced thermal power from 99% to 75% for turbine C.V. tests and SI's 4/28 4/29 0025 0200 0730 1922 Increased thermal power to 90%, holding for control rod drive exercise Commenced PCIOMR from 90% thermal power Reactor thermal power at 99%, steady state Reactor scram no.
111 from 99% thermal power on turbine trip and stop valve closure due to loss of 120 volt preferred power ("C" shutdown board) causing feedwater control problems 4/30 0140 0355 0410 1600 1605 2250 2308 2400 Commenced rod withdrawal for startup Reactor critical no.
127 Reactor made subcritical, holding for changing out main transformer Resumed rod withdrawal for startup Reactor critical no. 128 Rolled T/0 Synchronized generator Reactor thermal power at 20%, with power ascension in progress (1) Equipment malfunction Cause unknown (2)
Si nificant 0 erational Events Unit 2 Date Time Event 0700 4/3 1500 4/1/79 0001 Reactor thermal power at 96%,
sequence "B", PCIOMR in progress Reactor thermal power at 99%, steady state Reactor thermal power at 99%, steady state 4/5 0015 0112 0200 0700 Reduced thermal power from 99% to 85X for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at 99%
4/6 2155 2345 Reduced thermal power from 99% to 90% for turbine C.V. tests and SI's Turbine C.V. tests and SI's completed, commenced power ascension 4/7 0010 0400 2200 Commenced PCIOMR from 95X thermal power Reactor thermal, power at 99%
Reduced thermal power from 99% to 88% for condensate demineralizer backwash and precoat 4/8 0235 0300 0700 Condensate demineralizer Sackwash and precoat completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at 99%
4/12 0125 0230 0700 Reduced thermal power from 99% to 85X for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 97X, rod limited 4/13 2325 2340 Reduced thermal power from 97% to 85% for turbine C.V.
tests and SI's Commenced condensate demineralizer backwash and precoat 4/14 0025 0110 0300 0700 Turbine C.V. tests and SI's completed,.holding for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Commenced PCIOMR from 90% thermal power Reactor thermal power at 96%, rods limited
Si nificant 0 erational Events Unit 2 Date Time Event 4/15 0930 1706 1900 Reduced thermal power from 96% to 90% for removal of "A" string high pressure feedwater heaters from service for maintenance (leakage)
"A" string high pressure feedwater heaters maintenance completed and placed in service, commenced power ascension Commenced PCIOHR from 93% thermal power 4/16 0015 0210 0330 0700 Reduced thermal power from 95% to 85X for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Commenced PCIOMR from 95% thermal power Reactor thermal power at 96%, rods limited 4/20 0125 0223 0700 Reduced thermal power from 96% to 85% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 95%, rods limited.
4/21 0440 0545 0815 Reduced thermal power from 95X to 85% for condensate demineralizer backwash and precoat Condensate dermineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 95%, rods limited 4/22 0020 0130 0515 Reduced thermal power from 95X to 85% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 94%, rods limited 4/25 0140 0300 0330 Reduced thermal power from 94% to 85% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Reactor thermal power at 94%, rods limited 4/26 2200 Reduced thermal power from 94% to 70X for scram timing control rods
Si nificant Operational Events Unit 2 Date Time Event 4/27 0250 0345 1954 2213 Control rod scram timing completed, commenced power ascension Reactor thermal power at 93%, rods limited Commenced reducing thermal power for shutdown (scheduled refueling outage, cycle 3)
Reactor scram no.
76 manual from 35% thermal power 4/30 2400 Reactor at cold shutdown with cycle 3 refueling outage in progress
~ e t I
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~','D
10 Si nificant Operational Events Unit 3 Date Time 4/1/79 0001 0321 0700 1530 2315 Event Reactor thermal power at 70%,
sequence "B", holding for STI 162 (load following)
Commenced power ascension Commenced PCIOMR from 96% thermal power Reactor thermal power at 99%, steady state Reduced thermal power from 99X to 68% for maintenance to EHC (leakage) 4/2 0400 0700 Maintenance to EHC completed, commenced power ascension Reactor thermal power at 99%, steady state 4/6 0243 0542 Reduced thermal power from 99% to 90% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension 4/7'008 0120 0755 0940 1400 1500 2120 Reduced thermal power from 97X to 70% for turbine C.V.'ests and SI's Turbine C.V. tests and SI's completed, reduced thermal power from 70% to 50% for STI 162 (load following test-Phase 2)
Commenced power ascension, part of STI 162 Reduced thermal po~er from 90% to 80% for control rod pattern adjustment Control rod pattern adjustment completed, commenced power ascension Commenced PCIOMR from 95% thermal power
. Reduced thermal power from 99% to 50% for STI 162 (load following test) 4/8 0428 1155 1800 2303 Commenced power ascension, part of STI 162 Commenced PCIOMR from 90X thermal power
'Reduced thermal power from 99% to 50% for STI 162 (load following test)
Commenced power ascension, part of STI 162 4/9 0405 0810 1100 1830 Commenced PCIOMR from 90% thermal power Reduced thermal power from 95% to 85% for control rod pattern adjustment Control rod pattern ad)ustment completed, commenced PCIOMR from 85% thermal power Reactor thermal power at 99%, steady state
11 Si nificant 0 erational Events Unit 3 Date Time Event 4/12 2100 2215 2230 Reduced thermal power from 99% to 72% for control rod pattern ad/ustment Control rod pattern adjustment completed, commenced power ascension Commenced PCIOMR from 90% thermal power 4/13 1355 1910 2145 2300 Reactor thermal power at 99%, steady state Reduced thermal power from 99% to 85% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced power ascension Commenced PCIOMR from 88% thermal power 4/14 0140 0355 0700 Reactor thermal power at 90%, holding for turbine C.V.
tests and SI's Turbine C.V. tests and SI's completed, resumed PCIOMR Reactor thermal power at 99%, steady state 4/20 2200 Reduced thermal power from 99% to 40% for control rod sequence exchange from "g" to "3" 4/21 0330 0700 Control rod sequence exchange from "A" to "B" completed, commenced power ascension Commenced PCIOMR from 70%
4/22 1330 Reactor thermal power at 99%, steady state 4/24 0152 0500 1500 2155 Reduced thermal power from 99% to 85% for condensate demineralizer backwash and precoat Condensate demineralizer backwash and precoat completed, commenced PCIOMR from 85% thermal power Reactor thermal power at 99%, steady state
'educed thermal power from 99% to 65% for control rod pattern adjustment 4/25 0010 1200 Control rod pattern ad)ustment completed, commenced power ascension Commenced PCIOMR from 88% thermal power 4/26 1500 Reactor thermal power at 99%, steady state 4/28 0048 0230 0400 Reduced thermal power from 99% to 80% for removal of "C" reactor feedwater pump from service for maintenance due to high vibration Commenced turbine C.V. tests and SI's-Turbine C.V. tests and SI's completed, holding at 80%
thermal power for "C" reactor feedwater pump maintenance
12 Si nificant Operational Events Unit 3 Date Time Event 4/30 1244 1335 1400 1550 2400 "C" reactor feedwater pump maintenance completed and pump placed in service Commenced power ascension from 80% thermal power Commenced PCIOMR from 90% thermal power Reduced thermal power from 91% to 80% for removal of "C" reactor feedwater pump from service due to high vibration Reactor thermal power at 80%, holding for vibration checks on "C" reactor feedwater pump
AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
DATE COMPI ETED 8Y Ted Thorn TELEPHONE 205/729-6846 MONTH DAY AVERAGEDAILYPOWER LEVEL (MWe-Net)
I 44 950 1041 1021 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 17 18 19 20 21 1052 7
10 12 13 14 15
~ 16 855 989 1058 1056 1062 1059 1062 985 1060 1020 23 24 25 26 27 28 29 30 31 1061 1064 1056 1048 1051 848 INSTRUCTIONS.
On this format, list the average daily unit power level in Mme Net for each day in the reporting ntonth. Compute to the nearest whole megawatt.
(t)(77)
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0 AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
UNIT Bro~s Ferry 2
DATE
'~"'ELEPHONE 205/729-6846 MONTH A ril 1979 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net)
DAY AVERAGE DAILYPOWER LEVEI.
(MWe-Net) 03 17 S
10 12 13 14 IS 16 1076 1077 1077 1067 1069
~
1057 1067 1058 0
1050 1040 1022 1033 IS 19 20 21 22 23 24 25 26 27 28 29 30 31 1033 1027 1019 1015 1013 1013 1009 1001 979 866
-15 INSTRUCTIONS
'n this format, list the average daily unit power level in hIEVe Net for each day in the reporting month. Compute to the nearest whole megawatt.
(~)/77)
AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.
Browns Fer 3
DATE 5/2/7 COMPLETED BY TELEPHONE 205/729-6846 MONTH A ril 197 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1006 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) 1066 17 6
10 12 13 14 IS 16 992 1065 1067 1073 1028 811 793 946 1057 1064 1033 1060 1067 1069 18 19 20 21 22 24 26 27 28 29 30 31 1069 1061 1033 759 1042 1066 1017 917 1006 1088 842 864 866 INSTRUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.
16 OPERATING DATAREPORT DOCKET NO. 5~
DATE ~9 COMPLETED BY ~ZORIL TELEPHONE 2QSLZ~46 OPERATING STATUS
- 1. Unit Name:
Bro~s Ferr
- 2. Reporting Period:
A ril 1979
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maximum Dependable Capacity (Net MWe):
Notes
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net ilIWe):
- 10. Reasons For Restrictions, IfAny:
This Month
-219
- 12. Number Of Hours Reactor Was Critical
'4
~ 53
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown Hours
- 16. Gross Thermal Energy Generated (MWH) 2~ 145 926
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor 95.5
- 20. Unit AvailabilityFactor
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outage Rate 4.5
- 24. Shutdowns Scheduled Over iVext 6 iilonths (Type, Date, and Duration Yr:to-Date 2 287.86 167.31 2193.
0 6 294 977 2,100,300 2 044 386 76.2 76.2 66.7 66.7 8.8 of Each):
Cumulative 22 519.45 4566.44 21885.0 0
57 067 649 18,918,300 18 356 606 52.6
- 52. 6 41.4 41.4 38.0
- 25. IfShut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units ln Test Status (Prior to Commercial Operation):
Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCJA L OP ERATION (o/77)
17 OPERATING DATAREPORT DOCKET NO.
DATE 5
2 79 COMPLETED BY Don Green TELEPHONE ~L229-6846 OPERATING STATUS 3293 1152 I. Unit Name:
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross AIWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
1065 1098.4 Notes
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, IfAny (Net MWe):
- 10. Reasons For Restrictions. IfAny:
This Month Yr.-to-Date 2781.07
- 12. Number Of Hours Reactor Was Critical 646 22
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On.Line
- 15. Unit Reserve Shutdown Hours 0
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH) 669,399
- 19. Unit Service Factor 89.9
- 20. Unit AvailabilityFactor
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 87.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of 646.22 687,850 25.15 2770.40 0
8 386,684 2,857,580 2,784,696 96.2 96.2 90.8 90.8 Each):
Cumulative 365'28 19499.36 11501.86
'18838.26" 51,838 472 17,171,368 16,674,860 51.6 51.6 42.9 42.9 41.
- 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 COMMERCIALOPERATION
18 OPERATING DATAREPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE 2QQ;~846 OPERATING STATUS Notes
- 1. Unit Name:
Browns Per 3
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross ilIWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe): 1 9
7 Maximum De endable Ca acit Net MWe:
p p
y(
)
- 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:
N A This Month Yr:to.Date Cumulative 2 865.15 13.85 2,857.37 0
8,835, 734 410 2 958 630 716 288 886 590
- 12. Number Of Hours Reactor Was Critical 719
- 13. Reactor Reserve Shutdown Hours 0
- 14. Hours Generator On-Line
- 15. Unit Reserve Shutdown floors 0
- 16. Gross Thermal Energy Generated (MWH)
I7. Gross Electrical Energy Generated (MWH)
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor
- 20. Unit AvailabilityFactor
- 21. Unit Capacity Factor (Using MDC Net)'4
~ 1
- 22. Unit Capacity Factor (Using DER Net) 94.1
- 23. Unit Forced Outage Rate 0
.8
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date. and Duration of Each):
ta e
Se tember 1
1979 15 956.35 1119.26
~15, 0
'14 726,130 14 291,778 82.1 2.1 70.7 70.7 8.0
- 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 INITIALELECTRICITY COMMERCIALOPERATION (o/77)
~I UNITSIIUTDOWNS ANDPOiUER REDUCTIONS REPORT MONTII DOCKET NO.
COMPLETED BY Nir.
Date rl o
PJ I
C CO V 4
m 5cc V
C
~ CA CI Licensee Event Report 0 Q ~
~m 0C O
O CJ Cause Ec Corrective Action to Prevent Recurrence 74 75 76 77 78 79 04 02 79 04 06 79 04 14 79 04 16 79 04 28 79 04 29 F
5.58 26.77 Moisture separator fH level caused sto valve closure Derated for turbine C.V. tests Derated for "B" condensate booster um maintenance Derated for "A" reactor feedwater um maintenance Derated for turbine C.V. tests Turbine sto valve closure F: Forced S: Scheduled Reason:
A.Equipment Failure (Explain)
B.hlaintenance or Test C-Refueling
- D-Regulatory Restrictiun E-Operator Training & License Examination F-Administrative G-Operalloltal Error (Explain)
Il Other (Explain) hiethod:
I -hlanual 2-hlanual Scram.
3-Automatic Scram.
4.Other (Explain) 5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-OI 6I)
Exhibit I - Same Source
UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO.
UNITNAhIE DATE COhIPLETED BY
'ELEPHONE 50-260 Browns Ferr 2
Don Green No.
Date
~= 5 hK f4 ~
~ fY u~ C
~ Ch CI Licensee
- Event Report 4 CQ o 0 wG c
~
~Vl o ~
E ~
Q Cause Ec Corrective Action to Prevent Recurrence
. ~
85 79 04 26 Derated for scram timin control rods 86 79 04 27
,72. 78 Refuelin I
F: Forced S: Scheduled Reason:
A-Equipment Failure (Explain)
B.hiaintenancc or Test C.Refueling
~ D Regulatory Restriction E.Operator Training'iccnsc Examination F-Administ ra t ive G.Operat tonal Lrror (Explam)
I I Other (Explain)
Method:
I.hlanual 2.hlanual Scram.
3.Automatic Scram.
4-Other (Explain)
Exhibit G - Instructions for Preparation oi'ata Entry Sheets for l.ic<<nsee Event Report (LER) File INUREG.
OI6 I )
Exhibit I - Satnc Source
VNlTSl(UTDOlVNS ANDPOWER REDUCTIONS DOCKET NO 50-296 COMPLETED BY N<i.
Date r>
P EA u
Licensee
- Event Report 0 C<
0 4J
~ D
~n cn G C
~
OQ U E ~
Q Cause &, Corrective Action to Prevent Recurrence 86 79 04 01 87 79 04 07 88 79 04 07 89 79 04 08 90 79 04 12 91 79 04 20 92 79 04 24 93 79 04 28 Derated for EHC maintenance (leaks e)
Derated for turbine C.V. tests Derated for STI 162 (Load Following Test)
Debated for STI 162 (Load Following Test Derated for control rod pattern ad ustment Derated for control rod sequence exchan e from "B" to "A" Derated for control rod pattern ad ustment Derated due to high vibration on "C" Rx feed um F: Furced S: Scheduled Reason:
A-Equipmcnt Failure (Explain)
B-hlaintenance or Test C-Refueling D.Regulatory Restriction E.Operator Training & Liccnsc Examination F-Administrative G-Operational Error (Explain)'i-Other (Explain) 3 Method:
I -hlanual 2 hlanual Scram.
3.Autotnatic Scram.
4 Other (Explain) 4 Exlubtt C - lnstructtons for Preparation of Data Entry Sheets for Licensee Event Report (LER) File(NUREG-OI6I )
5 Exhibit l ~ Same Source
CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT Common MECllANICALMAINTEKKNCE
SUMMARY
For the Month of APril 19 79 4/5 SYSTEM Ventilatio COMPONENT Board and Spreading Room Supply Fans NATURE OF MAINTENANCE Dirty Filter EFFECT ON SAFE OPERATION OF THE REACTOR None CAUSE OF MALFUNCTION Operation RESULTS OF MALFUNCTION None ACTION TAKEN TO PRECLUDE RECURRENCE Replaced filters 4/17 Rx. Bldg.
Closed Cooling Water Discharge check valve from equip.
drain sump pump Valves in backward None Unknown None Turned valves and replaced 4/27 RllRSW A-1 RHRSW pump Packing leak None Operation None Tightened packing 4/27 RllRSW C-3 RHRSW pump Packing leak None Operation None Tightened packing 4/27 RHRSW D-3 RHRSW pump Packing leak None Operation None Tightened packing
CSSC E UIPMENT BRONNB FERRY NUCLEAR PLANT UNIT 1
MECHANICAL MAINTENANCE SUGARY 19 79 SYSTEM COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF IfALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 4/1 HPCI FCV.73-35 Shaft bent an bearings bad None Operation None Replaced shifter shaf and bearings 4/1 1-PCV-25-2 Valve dirty and regulator not set pro-perly Non'e Normal wear None Disassembled an cleaned valve, set regulator 4/9 CRD 85-50-19 Valve leaking through None Operation None Lengthened stem and stopped leak
CSSC E UIPMENT BROWNS FERRY NUCLEAR PIANT UNIT 2
MECHANICAL MAINTENANCE
SUMMARY
DATE SYSTElf COMPONENT EFFECT ON SAFE NATURE OF OPERATION OF MAINTENANCE THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 4/3 Ventila-tion
'2A. Reactor bldg. exhaust fans Loose belts None Operation None Tightened belts 4/10 HPCI U-2 HPCI Booster Pump Leaking Unto None Operation None Tightened union
CSSC E UIPMENT BROWNS FERRY NUCLEAR PLANT UNIT 3
MECHANICAL MAINTENANCE
SUMMARY
SYSTEM COMPONENT NATURE OF MAINTENANCE EFFECT ON SAFE OPERATION OF THE REACTOR CAUSE OF MALFUNCTION RESULTS OF MALFUNCTION ACTION TAKEN TO PRECLUDE RECURRENCE 4/l "A" CRD discharge filter Dirty Filter None Operation None Changed filter 4/4 RHR - SM pump D-3
'Pac4ng leak.
None Operation None Ad)usted packin 4/4 RHR SM Pump C-3 Packing Leak None Operation None Ad5usted packing
CSSC E UIBfENT BROlPilS PERRY BUCLEAP, PL62IT M)ZT ELECTRICAL MAINTENANCE SDBfARY For the tfonth of Page 1 of 3 System 3>>30-79 HPCI Component HPCI drain level switches LS 73-5 Nature of Maintenance Scheduled maintenance E
ect on a e Operation of The Reactor N/A Cause of Malfunction.
LS73-5 corroded Results of Malfunction Level not control-ling properly Action Taken To Preclude Recurrence Replaced switches.
Checked OK.
TR 112088 4-3-79 Fire pro-tection Class "A"
supervised detector alarm cir-cuits and circuits from panel to con-trol room Scheduled maintenance N/A (1). Panel 9-2, A spreader rm.
(R-3, R-6 zone A heat) would (2) Above would not light from pnl 25-323 Alarm would not come in Replaced relay in panel 25-323 to light annunciator in panel 9-2.
Tested OK.
LER 259/797 TR 130004 4-12-79 tandby iesel gen-erator sys.
uD'( diesel generator-time delay relay (SFD2)
Relay operat-e ting spurious-ly N/A Bad relay Improper operation (discovered while performing EMI 3)
Replaced relay and times in accordance with EfI 15 and SZ 4.9.A.l.d.
Tested OK.
TR 13 6
4-17-79 ir con-itioning "B" control bay chiller Chiller trip-ping on low oil pressure N/A Dirty oil filter Chiller not operat-ing properly Replaced oil filter, checked oil pressure normal.
Tested OK.
TR 129544
ERONNE PERRY 'NUCLEAR PLANT UUZT 1
ELECTRICAL MAINTENANCE SV11MARY Page 2 of 3 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 4-18-79 entilation Diesel genera tor building exhaust fans dampers (1) A and
{2) B (1) IIAII exhaust fan damper in "A" room will not close (2)
IIBII exhaust fan damper in "C" room will not close N/A (1) "A" exhaust fan damper motor defective (2) "C" room damper had faulty auxil-iary contact (1) and (2) dampers locked in open posi-(1) Replaced motor.
(2) Replaced acx iary contact.
Tested OK.
TR 117926 4-22-79 Emergency equipment cooling water "D" EECW pump discharge strainer motor - cir-cuit breaker Circuit break-er faulty N/A Faulty circuit breaker Strainer motor will not run Replaced circuit.
Breaker tested OK.
TR 128083 4-24-79 Battery boards U-1 250-V mai battery SI 4.9.A.2.C N/A Biannual surveil-Found humming in lance ACl relay due to metal shaving Removed metal shaving from ACl relay. SI completed.
TR ll 4-26-79 Air condi-1-B, control tioning bay chiller Tripping on low oil pressure N/A Reservoir and oil p'ump jet dirty Chiller tripping on low oil pressure Cleaned reservoir and oil pump )et, changed oil'ilter and freon filter.
Tested OK.
TR 127109
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CSSC E UIPMENT ERONNS PERRY NUCLEAR PLRNY UNYY 2
ELECTRICAL MAINTENANCE SALARY Page 2 of 2
~ 5 Date System Component Nature of Maintenance ect on a e Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence 4-23-79 Ventilat-ing U-'2, 250-V battery room supply fan 2A motor Motor trips out N/A Overload set at 100%
Tripping out at full load Reset overload to 115(..
Tested OK.'R 126913 4-29-79 Neutron monitor-ing "E" IRMP cable Defective
.:=.
cable N/A Bad.cable IRM will not operat Installed new cable and connector per EMI 5.
Checked OK.
TR's 115425 and 105406
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EROVRE FERRY RUCLEAR PLARY URLY ELECTRICAL MAINTENANCE S CHARY For the Month of April
. 19 79 Page 2 of 2 Date 4-20-79 System Air condi tioning Component 4160-V shut-down bd.
room chiller Nature of Maintenance "Air condition er abnormal" alarm E
ect on a e Operation of The Reactor N/A
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Cause of Malfunction Freon charge low Results of Malfunction Alarm will not clear Action Taken To Preclude Recurrence Added freon.
Operation tested'ormal.
TR 128846 (alarm clear) 4-24-79 Raw ser-vice water 3A raw ser-.".
vice water pump motor Motor trip-ping out N/A Motor leads burned Motor trip Replaced
- leads, meggered motor.
Checked OK.
TR 128830
CSSC Equipment BRONNR PRRRY NUCLEAR PLRNT UNIT I & 3 INSTRUMENT MAINTENANCE SUQfARY For the Month of April 19 79 Date System Component Nature of Maintenance ect on Sa e
Operation of The Reactor Cause of Malfunction Results of Malfunction Action Taken To Preclude Recurrence Unit I Primary Contain-'ent PdT-64-138 Calibration None Zero drift Redundant indicators do not agree New design trans-mitters to be installed Unit 3 4-23 Radwaste Fq-77-16 Calibrate Nqne Zero drift Indi:cated"'%low with pump off None 4-23 Contain-ent nerting H2H-76-38 Replace None Sensor failure Indicated 5% H2, lab sample was aero New system to be installed
34 OUTAGE SECTION MONTHLY REPORT Much of April was spent toward planning and work preparations for the Unit 2, Cycle 3 outage which began with shutdown at 2213 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.420465e-4 months <br /> on April 27, 1979.
The outage is scheduled for 42 days.
Since no significant invessel work or ma)or modifications requiring critical path time are scheduled for the Unit 2, Cycle 3 outage, it should be the shortest scheduled refueling outage to date.
Training in preparation for the refueling outage and all the mandatory prefab work was completed in April for gobs scheduled,:during the outage.
Some major efforts were expended on non-outage work such as security and cooling tower modifications.
In conjunction with the Unit 2 effort, the planning and prefabrication work for the upcoming outages such as the torus and LPCI modifications were underway.
To date, the Unit 2, Cycle 3 outage is progressing very well, and at this time it is slightly ahead of schedule.