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{{#Wiki_filter:TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT October 1, 1978-October 31, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by P nt Superintendent)c 6'/ppypy TABLE OF CONTENTS Operations Summary~ | {{#Wiki_filter:TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT October 1, 1978 - October 31, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by P nt Superintendent | ||
~~~~~~~~~Refueling Information | )c 6'/ppypy | ||
~~3 Significant Operational Events................5'verage Daily Unit Power Level.o~9 Operating Data Reports o~~~~Unit Shutdowns and Power Reductions.............. | |||
l5 Plant Maintenance Summary.~~~o~Unit 3 Refueling Outage Summary...... | TABLE OF CONTENTS Operations Summary ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ l Operational Data .- . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 Maintenance ~ ~ ~ ~ ~ ~ ~ ~ ~ | ||
~~~~~~~~~~31 erations Summa 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 and begins on page 5.There were 6 Reportable Occurrences reported to the NRC during the month of October.Unit 2 Significant operational events for unit 1 are tabulated by date and time beginning on page 5.The unit did not scram during the month of October.Power was administratively limited throughout the month by 60K"B" recirculation pump speed, with"A" loop out of service, except for testing on October 25 at 70K pump speed.A summary of maintenance work is shown on pages 18 through 30;Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 6.There was one scram during'the month.On October 10 the reactor scrammed during surveillance testing when piping was accidently bumped;causing a false high water level signal in the scram discharge volume.A summary of maintenance work is shown on pages 18 through 30.Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 8.The unit was down the entire month for refueling. | Refueling Information ~ ~ 3 Significant Operational Events . . . . . . . . . . . . . . . . 5 | ||
A summary of maintenance work is shown on pages 18 through 31. | 'verage Daily Unit Power Level . o ~ 9 Operating Data Reports o ~ ~ ~ ~ | ||
erations Summa (Continued) | Unit Shutdowns and Power Reductions.............. l5 Plant Maintenance Summary. ~ ~ ~ o ~ | ||
Common S stems Approximately 8.92E-1 gallons of waste liquid were discharged containing approximately 7,p2E-1 curies of activity.Cooling towers 1, 2 (until October 2)and 6 were operational this month for two lift pump operations. | Unit 3 Refueling Outage Summary...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 31 | ||
Modifications by the tower vendor were continued on Tower 3 and modifications to Tower 2 began on October 2.None of the towers.had significant operational problems.erational Data 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.Maintenance Ma)or electrical, mechanical, and instrument maintenance activities during the month, are described on pages 18 through 3p.Refueling outage activities for Unit 3 are summarized on page 31. | |||
Refuel in Information Unit 1 Unit 1 fs scheduled for its second refueling begfnnfng on Nobember 18, 1978, wfth a restart date of December 20, 1978.Resumption of operatfon on that date will requfre a change fn technical speciffcatfons pertaining to the core thermal limits.Licensing informatfon in support of these changes was submitted fn August 1978.This refueling will load additional 8 X SR (retrofit) fuel assemblies into the core, replacing presently loaded 7X7 fuel and will involve installing a new recirculation pump trfp (RPT)system.There are 764 fuel assemblies fn the core.The spent fuel storage pool presently contafns 168 spent 7X7 fuel assemblies and 156 new 8 X 8R fuel assemblies. | erations Summa 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 and begins on page 5. | ||
The px'esent stox'age capacfty of the spent fuel pool fs 1080 assemblies. | There were 6 Reportable Occurrences reported to the NRC during the month of October. | ||
Present planning is to incxease that capacfty to 3471 assemblies. | Unit 2 Significant operational events for unit 1 are tabulated by date and time beginning on page 5. | ||
With present capacfty, the refueling later fn 1978 would be the last refueling that could be discharged to the spent fuel stoxage pool without exceeding that capacfty and mafnt~g full core discharge capability fn the pool.Unit 2 Unit 2 fs schedu1ed for fts second refueling beginning on April 22, 1979, with a restart date of July 1, 1979.Resumption of operatfon on that date will require a change in technical specfficatfons pertaining to the core thermal limits.Present scheduling is to submft licensing information in support of these changes before the xefuelfng. | The unit did not scram during the month of October. | ||
This refueling will involve xeplacing. | Power was administratively limited throughout the month by 60K "B" recirculation pump speed, with "A" loop out of service, except for testing on October 25 at 70K pump speed. | ||
some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies. | A summary of maintenance work is shown on pages 18 through 30; Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 6. | ||
There are 764 fuel assemblies fn the core.At the end of October there were 132 discharged cycle 1 7 X 7 fuel assemblies fn the spent fuel storage pool.There are presently 36 new 8 X 8 fuel assemblfes fn the spent fuel storage pool which were not loaded into the core during thfs cycle.The present storage Re fuelin Information (Continued) | There was one scram during 'the month. On October 10 the reactor scrammed during surveillance testing when piping was accidently bumped; causing a false high water level signal in the scram discharge volume. | ||
Unit 2 (continued) capacity of the spent fuel pool is 1080 assemblies. | A summary of maintenance work is shown on pages 18 through 30. | ||
Present planning is to increase that capacity to 3471 assemblies. | Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 8. | ||
With present capacity, the 1979 refueling would be the last refueling that could be discharged to the spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.Unit 3 Unit 3 began its first refueling on September 8, 1978, with a scheduled restart date of November 20, 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 July, 1978.This refueling involves 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.There are 143 fuel assemblies presently in the core.There are 829 fuel assemblies in the spent fuel storage pool.All but 208 of these will be reloaded into the-core for cycle 2..The present licensed storage capacity of the spent fuel pool.'is 1132 assemblies. | The unit was down the entire month for refueling. | ||
Si | A summary of maintenance work is shown on pages 18 through 31. | ||
~-10/5 1730 Control rod pattern established commenced po~er ascensions from 53X thermal power.2300 Reactor thermal power at 58X, holding for single recix'culation loop operation. | |||
10/7 0120 Reduced thermal powex from 58Z to 54X fox'urbine C.V.tests and SZ's.0530 Turbine C.V.tests and SZ's completed; increased thermal power to 58X holding for single recirculation loop operation. | erations Summa (Continued) | ||
10/12 1350 Reduced thermal powex from 58X to 50Z for recirculation pump test (STT.-160). | Common S stems Approximately 8.92E-1 gallons of waste liquid were discharged containing approximately 7,p2E-1 curies of activity. | ||
1540 Recirculation pump test (STI-160)completed/commenced | Cooling towers 1, 2 (until October 2) and 6 were operational this month for two lift pump operations. Modifications by the tower vendor were continued on Tower 3 and modifications to Tower 2 began on October 2. None of the towers. had significant operational problems. | ||
'ower | erational Data The average daily unit power level for units 1, 2, and 3 is shown on pages 9 through 11. | ||
2300 Reactor thermal power at 58X, holding for single recix'culation loop operation. | The operating data reports for all three units are shown on pages 12 through 14. | ||
10/21 2100 Reduced thermal power from 58X to 50Z for contxol zod staU.flow and leak tests (SIL-52).2155 Control rod stall flow and leak tests completed commenced power ascension. | Unit shutdowns and power reductions for all three units are shown on pages 15 through 17. | ||
10/22 0700 Reactor thermal power at 59Z holding for single recirculation loop operation. | Maintenance Ma)or electrical, mechanical, and instrument maintenance activities during the month, are described on pages 18 through 3p . Refueling outage activities for Unit 3 are summarized on page 31. | ||
Si ficant erational Events Date 22ne | |||
Unit 2 10/1 OOOO Reactor shutdown for scheduled outage, in hot standby mode.10/3 1221 | Refuel in Information Unit 1 Unit 1 fs scheduled for its second refueling begfnnfng on Nobember 18, 1978, wfth a restart date of December 20, 1978. Resumption of operatfon on that date will requfre a change fn technical speciffcatfons pertaining to the core thermal limits. Licensing informatfon in support of these changes was submitted fn August 1978. This refueling will load additional 8 X SR (retrofit) fuel assemblies into the core, replacing presently loaded 7X7 fuel and will involve installing a new recirculation pump trfp (RPT) system. | ||
Reactor thermal power at 20X, holding for primary containment leak rate test.(Air lock door).10/4 1717 | There are 764 fuel assemblies fn the core. The spent fuel storage pool presently contafns 168 spent 7X7 fuel assemblies and 156 new 8 X 8R fuel assemblies. The px'esent stox'age capacfty of the spent fuel pool fs 1080 assemblies. Present planning is to incxease that capacfty to 3471 assemblies. | ||
Commenced PCIOMR from 90X thermal power.Reactor thermal power at 98X, core flow.Limited.Reactor thermal power at 98X, core flow limited. | With present capacfty, the refueling later fn 1978 would be the last refueling that could be discharged to the spent fuel stoxage pool without exceeding that capacfty and mafnt~g full core discharge capability fn the pool. | ||
Si nificant 0 erational Events Data Time Event | Unit 2 Unit 2 fs schedu1ed for fts second refueling beginning on April 22, 1979, with a restart date of July 1, 1979. Resumption of operatfon on that date will require a change in technical specfficatfons pertaining to the core thermal limits. Present scheduling is to submft licensing information in support of these changes before the xefuelfng. This refueling will involve xeplacing. | ||
Reactor scram no.72 on erroneous scram discharge | some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies. | ||
10/11 0052 Reduced thermal power from 90X to 77X to compensate for xenon burn out.0252 | There are 764 fuel assemblies fn the core. At the end of October there were 132 discharged cycle 1 7 X 7 fuel assemblies fn the spent fuel storage pool. | ||
0200 | There are presently 36 new 8 X 8 fuel assemblfes fn the spent fuel storage pool which were not loaded into the core during thfs cycle. The present storage | ||
Si nificant 0 erational Events Dete Tine Event Unit 2 (continued) 10/21 0103 Maintenance to"C" condensate booster pump completed and both recirculation pump MG sets brush replacement completed, commenced power ascension. | |||
1700 | Re fuelin Information (Continued) | ||
0405 Control rod patt'ern established, commenced PCIOMR from 50X thermal power.10/30 2300 Reactor thermal power at 98X, steady state.10/31 2400 Reactor thermal power at 98X, steady state.Unit 3 10/1 0000 | Unit 2 (continued) 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 spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool. | ||
AVERAGE | Unit 3 Unit 3 began its first refueling on September 8, 1978, with a scheduled restart date of November 20, 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 July, 1978. This refueling involves replacing some of the | ||
Forecast Achieved | ~ | ||
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. | |||
If Any: | There are 143 fuel assemblies presently in the core. There are 829 fuel assemblies in the spent fuel storage pool. All but 208 of these will be reloaded into the- core for cycle 2.. The present licensed storage capacity of the spent fuel pool.'is 1132 assemblies. | ||
" II.~12.13. | |||
Forecast Achieved | Si ficant erational Events Date Theme Event Unit 1 10/1 0000 Reactor thermal power at 56X, holding for "A" recirculation loop being out of service control rod sequence "3". | ||
If Any: This Month Yr.-to-Date Cumuhtive ll.Hours In Reporting Period 12.Number Of Hours Reactor Was Critical 0 | 10/4 1046 Commenced special test no. 160 (single zecirculation loop operation mmcLmum flow) . | ||
Forecast Achieved | 1845 Special test no. 160 completed, reduced thermal power from 63X to 53X, holding for single recirculation loop operation and control rod pattern ad5ustment. | ||
I~ | ~ - 10/5 1730 Control rod pattern established commenced po~er ascensions from 53X thermal power. | ||
F: Forced S: Scheduled | 2300 Reactor thermal power at 58X, holding for single recix'culation loop operation. | ||
10/7 0120 Reduced thermal powex from 58Z to 54X fox'urbine C.V. tests and SZ's. | |||
0530 Turbine C.V. tests and SZ's completed; increased thermal power to 58X holding for single recirculation loop operation. | |||
10/12 1350 Reduced thermal powex from 58X to 50Z for recirculation pump test (STT.-160). | |||
1540 Recirculation pump test (STI-160) completed/commenced ascension. 'ower 2300 Reactor thermal power at 58X, holding for single recix'culation loop operation. | |||
10/21 2100 Reduced thermal power from 58X to 50Z for contxol zod staU. flow and leak tests (SIL-52). | |||
2155 Control rod stall flow and leak tests completed commenced power ascension. | |||
10/22 0700 Reactor thermal power at 59Z holding for single recirculation loop operation. | |||
Si ficant erational Events Date 22ne Event Unit 1 (continued) 10/25 1000 increased recirculation pump flow for 66X thermal power. | |||
1100 Reduced thermal power to 59X, holding. | |||
10/31 '400 Reactor thermal power at 59X, holding for single recirculation loop operation. | |||
Unit 2 10/1 OOOO Reactor shutdown for scheduled outage, in hot standby mode. | |||
10/3 1221 Commenced rod withdrawal for startup. | |||
1245 Reactor critical no. 84; Rolled T/G. | |||
2147 Synchronized generator, commenced power ascension. | |||
2205 Reactor thermal power at 20X, holding for primary containment leak rate test. (Air lock door). | |||
10/4 1717 Primary containment integrity established commenced power ascension from 20X thermaL power. | |||
10/5 L500 Commenced PCZOMR from:84X thermal power (Sequence "A"). | |||
LQ/6 L500 Reactor thermal power at 98X, core flow limited. | |||
10/7 2310 Reduced thermal power from 98X,to"85X for turbine C.V. | |||
tests and SZ's. | |||
10/8 0035 Turbine C.V. tests, and SI's completed, commenced power ascension. | |||
10/8 0230 Commenced PCIOMR from 90X thermal power. | |||
2200 Reactor thermal power at 98X, core flow. Limited. | |||
10/9 1500 Reactor thermal power at 98X, core flow limited. | |||
Si nificant 0 erational Events Data Time Event Unit 2 (ccntinned) 10/10 0947 Reactor scram no. 72 (1) on erroneous scram discharge volume high level during SI 4.1.A.8. | |||
1130 Commenced rod withdrawal 1245 Reactor critical no. 85 1445 T/G. 'olled 1503 Synchronized generator, commenced power ascension. | |||
10/11 0052 Reduced thermal power from 90X to 77X to compensate for xenon burn out. | |||
0252 Commenced power ascension from 77X thermal paver. | |||
0635 Commenced PCIOMR from 85X thermal 'power (sequence "B"). | |||
2025 Reactor thermal power at 98X steady state. | |||
2055 Reduced thermal paver from 98X to 90X due to "C" string high pressure heaters isolation for maintenance (repair leaks) . | |||
10/12 0915 Increased thermal paver from 90Z to 92X with "C" string high pressure heaters out of service for leak repairs. | |||
10/13 1700 "C" string high pressure heater repairs completed and placed in service commenced PCIOMR from 92X thermal power. | |||
10/14 0700 Reactor thermal pover at 98X, steady state. | |||
2335 Reduced thermal paver from 98X to 85X for turbine C.V. | |||
tests and SI's. | |||
10/15 0026 Turbine C.V. tests and SI's completed, commenced power ascension. | |||
0200 Reactor thermal power at 98X steady state. | |||
10/20 2040 Reduced thermal paver from 98X to 45X for maintenance to "C" condensate booster pump (oil leak) and for brush replacement on both recirculation pump M.G- sets. | |||
Si nificant 0 erational Events Dete Tine Event Unit 2 (continued) 10/21 0103 Maintenance to "C" condensate booster pump completed and both recirculation pump MG sets brush replacement completed, commenced power ascension. | |||
1700 Commenced PCIOMR from 80X thermal powere 10/22 2300 Reactor thermal power at 98X, steady state. | |||
10/27 2250 Reduced thermal power from 98X to 85X for turbine C.V. tests and SI's. | |||
10/28 0140 Turbine C.V. tests and SI's completed, reduced thermal power from 85Z to 50X for control rod pattern ad5ustment. | |||
0405 Control rod patt'ern established, commenced PCIOMR from 50X thermal power. | |||
10/30 2300 Reactor thermal power at 98X, steady state. | |||
10/31 2400 Reactor thermal power at 98X, steady state. | |||
Unit 3 10/1 0000 Refueling outage in progress with all fuel assemblies in the fuel pool storage. | |||
10/29 1835 Commenced loading cycle 2 fuel.- | |||
10/31 2400 143 fuel assemblies reloaded into core. | |||
End of Month (1) Maintenance error during surveillance testing. | |||
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. -2 9 UNIT DATE COMPLETED BY TELEPHONE MON'Oi DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net) (MWe.Net) 17 18 588 19 588 558 20 585 21 583 | |||
'83 603 24 601 25 621 10 26 591 559 644 13 599 29 623 14 30 601 15 31 596 16 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 megawatt. | |||
E (o/77) | |||
10 AVERAGE DAlLYUNIT POWER LEVEL DATE 11-2>>78 COMPLETED BY TELEPHONE MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe.Ne!) (MWe-Net) 17'066 19 1065 223 20 1002 825 21 797 6 ~OZ7" 22 1033 1073 1090 24 1081 1030 1089 10 653 26 1053 27 1064 12 637 13 1032 857 14 1065 30 1007 IS 1054 31 1071 16 INSTRUCTIONS On this format, list the average daily unit puwer level in MNte.iNet for each day in the reporring month. Compute to the nearest whole megawat t. | |||
(()/771 | |||
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 50-296 | |||
* COMPLETED BY TELEPHONE R46 MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (Meet) 17 19 20 | |||
. 21 22 7. | |||
24 M3 10 26 w3 27 12 28 13 <<2 29 14 30 15 31 16 INSTRUCTIONS On this format, list the average daily unit power level in MV/e.Net for each day in the reporting month. Compute to the nearest whole megawatt. | |||
(t)(771 | |||
12 OPERATING DATA REPORT DOCKET NO. | |||
DATE COMPLETED BY QQ~+rggu, TELEPHONE ~244M46 OPERATING STATUS Notes | |||
: 1. Unit Name: | |||
: 2. Reporting Period: October 78 | |||
: 3. Licensed Tiiermal Power (MWt): | |||
: 4. Nameplate Rating (Gross MWe): | |||
10 5 | |||
: 5. Design Electrical Rating (Net MWe): | |||
: 6. Maximum Dependable Capacity (Gross MWe): | |||
: 7. Maxtmum Dependable Capactty (Net MWe). | |||
: 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: | |||
: 9. Power Level To Which Restricted, lfAny (Net MWe): | |||
: 10. Reasons For Restrictions, lf Any: | |||
is out of e P This Month Yr:to.Date Cumulative | |||
: 13. Reactor Reserve Shutdown Hours 0 352.33 4 399.13 14..Hours Generator On-Lme 745 6 424.33 19 070.~6 | |||
: 15. Unit Reserve Shutdown Hours 0 17,19,22 49,571,455 I7. Gross Electrical Energy Generated (MWH) <<5,617,560 16,435 5RA | |||
: 18. Net Electrical Energy Generated (MWH) 5 446 826 15 935 173 88.1 51.2 | |||
''*- | |||
: 19. Unit Service Factor | |||
. | |||
23 Unit. Forced. Outage Rate | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each): | |||
~M. IfShut Down At End Of Report Perio, Estimated Date of Startup: | |||
: 26. Units In Test Status {Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY IN ITIA L ELECTRICITY COMMERCIAL'PERATION | |||
<oP7) | |||
~ ~ | |||
13 OPERATING DATA REPORT DOCKET NO. | |||
DATE COMPLETED BY TELEPHONE ~~~-6846 OPERATING STATUS Notes ~ | |||
: l. Unit Name: | |||
. 2. Reporting Period: | |||
: 3. Licensed Thermal Power (MWt): | |||
: 4. Nameplate Rating (Gross MWe): | |||
: 5. Design Electrical Rating (Net MWe): | |||
: 6. Maximum Dependable Capacity (Gross MWe): | |||
et'e | |||
: 7. Maxtmum Dependable Capacity (N i I ). | |||
: 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: | |||
~ | |||
~ | |||
: 9. Power Level To Which Restricted, If Any (Net 5IWe): | |||
: 10. Reasons For Restrictions. If Any: | |||
" II. Hours.ln Reporting Period | |||
~ 12. | |||
: 13. Reactor Reserve Shutdown Hours | |||
. This Month ai Yr:to-Date Cumulative | |||
: 14. Hours Generator On Line | |||
: 15. Unit Reserve Shutdbwn Hours 16, Gross Thermal Energy Generated (MWH) 1 977 564 12 714 751 8 887 888 17. | |||
18. | |||
: 19. Unit Service Factor | |||
: 20. Unit Avaihbility Factor 89.9 62.6 45.4 | |||
: 21. Unit Capacity Factor (Using MDC Net) 81.6 51. 9 36.1 22 Unit Capacity, Factor (Using DER Net) 81. 6 51.9 36.1 | |||
: 23. Unit Forced Outage Rate | |||
: 24. Shutdowns Scheduled Over Next 6 Months (Type. Date:and Duration of Each): | |||
~A. IfShut Down At End Of Report Period, Estimated Date of Startup: | |||
: 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION (oI77) | |||
14 OPERATING DATA REPORT DOCKET NO. 50-296 DATE u-2-78 COhlpI.ETED 8Y Don Green. | |||
TELEPHONE ZO'~9=6846 OPERATING STATUS Notes | |||
: l. Unit Name. | |||
: 2. Reporting Period: | |||
: 3. Licensed Thermal Power (MWt): | |||
: 4. Nameplate Rating (Gross MWe): | |||
S. Design Electrical Rating (Net MWe): | |||
: 6. Maximum Dependable Capacity (Gross MWe): | |||
7' 2 axunum De pend aleb Cap aci ty(Ne tMWe' ). | |||
: 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. If Any: | |||
This Month Yr.-to-Date Cumuhtive ll. Hours In Reporting Period | |||
: 12. Number Of Hours Reactor Was Critical 0 5 503.2 | |||
: 13. Reactor Reserve Shutdown Hours 0 | |||
: 14. Hours Generator On-Line IS. Unit Reserve. Shutdown Hours 0 | |||
: 20. Unit Availability Factor 0 74.2 81. 4 | |||
: 21. Unit. Capacity Factor (Using MDC Net) 0 | |||
~M. Unit.Capacity. Factor (Using DER Net) 0 62.9 68. | |||
: 23. Unit Forced. Outage Rate 0'24. | |||
Shutdowns Scheduled Over Next 6 Months (Type. Date; and Duration of Each): | |||
Ã. IfShut Down At End Of Report Periotl, Estimated Date of Startup: | |||
: 26. Units ln Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhtM ERCIA L OPERATION (4/77) | |||
I ~ | |||
DOCKET NO. | |||
UNITSIIUTDOWNS AND POWER REDUCTIONS l ' | |||
COhIPLETED BY REPORT MONTH QQfd?hgZ. | |||
~P L | |||
l C ~ rc PJ P Lh:cllscc E~ El IA C | |||
o Cl0 Cause Ec Corrcclivc gA Q Action lo No. Dale ~ | |||
Event Vl P cL 0 | |||
U<a c cc P | |||
A~ ~ Cll Rcpurt ¹ cn C5 O CJ Prcvcnt Rccuncncc 3 4 F: Furccd Reason: Method: Exhibit G - lnstcuctions S: Scheduled A.Equipmcnt Failure (Explain) I -hlanual for Preparation of Data B hlalntenancc or Test 2.hlanual Scram. Entry Sheets for Licensee C.Rc fueling 3-Aulontalic Scram. Event Rcport (LER) File (NUREC. | |||
D Regulatury Restriction 4.Other (Explain) OI6I ) | |||
E-Operator Training dc Uccnsc Examinaliun F.Administrative 5 G<pecational Error (Explain) Exhibit I - Sante Source | |||
(~tin) I IPOthcr (Explain) | |||
IN 1 | |||
DOCKET NO. 50-26o UNITSHUTDOWNS AND POWER REDUCTIONS COMPLETED By Don Oreen | |||
~ ~ | |||
REPORT MONTH October CI EI Lice nscc Ew Cause h Corrective g g'>> Q 0 uU Dale Event ~ 4 Q Action lo C4 Report ¹ ro G Eu CJ Prcvcnl Recurrence 64 781001t P 69.78 A, Investigation of unidentified leakage into drywell and repair of drywell E ui ment Drain sum um . | |||
65 781010 5 '7 6 "Sensed" scram discharge volume high ater level when instrument mechanics nadvertently bumped piping with a ladder. | |||
66 781020 B crated to perform maintenance on "C" condensate booster um (oil leak). | |||
67 781028 H ontrol rod pattern ad)ustment. | |||
: 3. 4 F: Forced 'eason: Method: Exhibit C - Instructions S: Scheduled A Eqtripmcnt Failure (Explain) I Manual for Preparation of Data | |||
, P Maintenance oi Test 2 Manual Scram. 'ntry Sheets I'or Licensee C.Refueling 3.Automatic Scram. Event Report (LER) File (NUREC. | |||
D Regulatory Restriction 4.Other (Explain) OI6I ) | |||
E43perator Training Ec License Examination F-Ad jninist ra t ivc 5 C Opcratiunal Error (Explain) Exhibit I - Same Source (I/77) I I Other (Explain) j | |||
DOCKET NO. | |||
UNIT SHUTDOWNS AND POWER REDUCTlONS UNIT NAhlE DATE COMPLETED BY Don t'reen TELEPIIONE 205 7296846 P'o. | |||
Vg C ~ CO Llccnscc Cause Ec Corrcctivc Date Event Action to aK u< | |||
~ EA C Rcpurt ¹ Prcvcnt Recuncnce I | |||
64 781001 S 745 C 2 I 3 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) I-hlanu'al lor Preparation ol Data II-hlalntenancc or Test 2.hlanual Scram. Entry Shccts for Licensee f-Refueling 3.Aulontatic Scram. Event Riporl (LERI File (NUREG-D Regu'latory Restriction 4-Other (Explalttl OI6I ) | |||
E Operator Training h Liccnsc Examination F-Adndnistra tive G.Operatiunal Error (Explain) Exhibit I - Sante Source I I.Other (Explain) | |||
.BROWNS I'ERRY NUCLEAR PUNT UNIT | |||
~ MECllANICAL MAINTENANCE | |||
==SUMMARY== | ==SUMMARY== | ||
For the Month of'CTOBER 1978 I l | |||
.0/12 RHR Servic C-3&B-3 | For the Month of 'CTOBER 1978 I | ||
BROWNS FERRY NUCLEAR PUNT UNIT 3 MECHANICAL MAINTENANCE | l EFFECT ON SAFE ACTION TAKEN NATURE OP OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE DATE SYSTEM COMPONENT ', | ||
MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE | |||
.0/12 RHR Servic C-3 & B-3 ',Packing leak- None !Loose packing None Adjusted packing Mater RHR service jing System water pump | |||
.0/12 >RHR Servic C-RHR service Packing None Loose packing None Ad)usted packing Water water pump leaking System room strainer | |||
.0/18 Diesel Both fuel Dirty filters None Operation None Changed 2 filters on Generators filters 'on 1D "D" diesel diesel . | |||
.0/19 Diesel Clean 1-A & 1- Coolers were None Some mud in ltone Removed coolers Generators diesel genera- dirty coolers- heads, cleaned tor coolers needed cleaning coolers, replaced heads using new gasket | |||
.0D20 Service Al RHR Service, Float hyng up None Blown pipe plug None Repaired 'pipe plug Mater water pump System discharge air regief valve I | |||
BROMNS FERRY NUCLEAR PLANT UNIT MECIONICAL MAINTENANCE SUK4lRY For the Month of OCTOBER 19 78 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE TllE REACTOR MALFUNCTION MALFUNCTION RECURRENCE LO/1 Standby Valve 863-518 Packing blown None Morn out packing None Rephced valve Liquid Control System | |||
.0/2 Uigh-Pres- Coupling on Leaking at None Unknown None Tightened up union to sure Cool. line to oil union oil cooler ing coolers In5ection System | |||
.O/6 Control CRD Module Packing leak None Loose packing None ightened packing Rod Drive 38-11 Valve 1-85-39B | |||
.0/12 Control Rod CRD accum 26- Leaking around None Loose'packing Nona Replaced valve Drive 35 leaking N2 packing of around 85-229A valve 229 Control Rod ACRD suction Dirty filter Nona Operation None Replaced with clean lM.ve filters need / filters cleaning I | |||
lO/19 CoaiCP51 Rod Discharge Dirty filter None Operation Nona Replaced filter Drive .. filter >>B | |||
1 BROWNS PERRY NUCLEAR PQlNT UNIT 2 MECHANICAL MAINTENANCE SUGARY | |||
,P | |||
.Por the Month of OCTOBER 19 '78 EPPECT ON SAFE ACTION TAKEN SYSTEM COL fPONENT NATURE 6P OPERATION OP CAUSE OP RESULTS OP TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE reactor Outboard bear- ; Bad bearing, .None Unknown. None Replaced flywheel Protection ing on 2B bearing preferred M-G Nigh Val 2-73-552 Loose packing None Loose packing None Tightened nuts on Pressure HPCI vent valv gland gland bolts packing gland Cooling In)ection System Control Replace out- Leaking mech None Crack in seal None Replace bearing 0 Rod Drive board mech sea seal face rings, sleeve, mech on 2ACRD seal and new oil C) | |||
BROWNS FERRY NUCLEAR PUNT UNIT 3 MECHANICAL MAINTENANCE | |||
==SUMMARY== | ==SUMMARY== | ||
For the Month of OCTOBER 19 78 SYSTEM COMPONENT NATURE OF | |||
For the Month of OCTOBER 19 78 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION NALFUNCTIO RECURRENCE 0/4 Fttel Fool. A & B fuel pool Packing leak- None Operation None Ad)usted packing Cooling & cooling pump ing Demineral-izing System 0/8 RNR Syst: em RUR valve no. Leaking stem None Loose packing None Tightened packing nuts 74-12 0/11 Ventilation 3A Control rm Broken belts None Operation None Replaced belts System air handling unit | |||
.0/12 Fuel Pool Val 878-63 & Valves packing None Loose packing None Tightened valves pack-Cooling & 78-64 leaking ing Demineral-izing 0 12 Ventilation 3A Control bay Leaking oil None Bad "0" ring and None Replaced "0" rings. | |||
System chiller around peal bad seal and seal . | |||
CRD 3A,CRD pump Seepage around None Operation None ightened bolts on bolts and pump heads LO/17 Ventilation 0 -3 R.B. & R.R. Rust in air None Unknown None Flushed coils System supply fane line LO/20 EECW System Valve 67-66 Leaking flange None Loose flange None Tightened up and RllR "D" seal bolts stopped leak heat exchange outlet | |||
BROPNS FERRY NUCLEAR PLANT UNIT | |||
~ ~ | |||
HECIIANICAL MAINTENANCE | |||
==SUMMARY== | ==SUMMARY== | ||
For the Month of.. | |||
.0/24 CRD 10-23 | OCTOBER 1978 For the Month of .. | ||
I'a~ | I | ||
b I I II I~I I~~~I o: I | ;EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF = OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE i TIIE REACTOR MALFUNCTION MALFUNCTIO RECURRENCE 0/20 Fuel Pool ICV 78-64 (F/0) Packing leak- None Loose packing None Tightened packing Cooling & influent out ing Deminerali board valve zing Syste 0/23 CRD 3 ACRD pump Discharge None Operation None Changed filter filter dirty 0/24 RIIR System Valve 74-12 Packing leak>> None Loose packing None Tightened packing'nuts ing h | ||
!BROBXIE PERRX NUCLEAR PLANT UIIZT ELECTRICAI. | .0/24 CRD 10-23 Accumulator None Bad cartridge Nona Changed valve and valve didn't charge valve.and cap replaced cap missing | ||
MAINTENANCE SIWhRY i~For the Month of l OCTOBER l9 78 PAGE 1 Date | |||
'SFDI relay on | I I >> | ||
~ | |||
Returned to service.Checked ok.TR 106623.0/12/78 ire | ~ | ||
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~II I~'I I I I~I~~I I~~~I~I~~~~~~I~I~~~~'~~'~~~~I~~I~~I~I II~~I~~ | ~ I | ||
I~I I I~s I s~I~~~~Si I~~'~I | : 1. I ~ ~ ~ ~ ~ | ||
'esults of Malfunction Action Taken to preclude recurrence | II ~ . I ~ ~ I | ||
.UNIT 10/15 RWCU FR-69-35 intenance' | ~ ~ I I ~ ~ I I | ||
The majority of the miscellaneous valves have passed the LLRT either initially or after zepaiz.There are still six valves which are to be repaired and retested.A total of seven contzol rod drives weze changed out after pxoblems were en-cquntered with CRD 38-51 and 34<<23.The scram discharge header modification portions of the EECM piping change were completed. | ~ ~ | ||
The CRD piping zeroute to the steam tunnel along with the CRD nozzle repaix'nd capping were completed. | ~ I ~ | ||
The recirculation pump trip (RPT)modification for unit 3 is essenti-ally completed with only post modification testing yet to be done.Other modi-fications which axe still underway aze the off-line zadiation monitor, the diesel dxiven fize pump, and the standby gas treatment changes.The zecirculation pump MG set x'otoz repair has been completed and an inspection is underway to see if there is any damage to the unit 1 rotors.The L-1 moistuxe removal modification has been completed and now reassembly of the low pzessuxe turbine and reactor feedpump tuxbine are complete except for the system oil flush.The mods on the HPCI and RCIC turbines aze also complete.}} | ~ ~ | ||
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BROBXIE PERRX NUCLEAR PLANT UIIZT ELECTRICAI. MAINTENANCE SIWhRY i ~For the Month of l OCTOBER l9 78 PAGE 1 ect on a e Action Taken Date System Component Nature of 'peration of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence | |||
,0/10/78 Diesel EHI 3 D/G 3AB G Redundant None 'SFDI relay on Did not meet timing Changed out SFDI rela Generators 3B, 3C and 3D tart test D/G 3a was out criteria of EHI 3 Ran SI 4.9.A.l.d of time tested ok with EHI 3. | |||
TR 87901 | |||
.0/12/78 Control Bay Control Bay erform routine None Dirty oil filter None Changed oil filter, Ventilatio Chiller 3B nd ma)or maint saturated from freon drier,'hanged s required drier, oil leaks repaired oil and Freon leaks, freon leaks. Changed faulty shaft oil system. Checked seal. Clogged and repaired instru-oil strainers. mentation. Returned to service. Checked ok. TR 106623 | |||
.0/12/78 ire Panel 25-327 ouble alarm None K2 relay not Trouble alarm in CR Replaced K2 relay. | |||
Pvotaotion n CR and not making contact and hot on local Tested ok. TR 91358 . | |||
n local panel panel BFRO 50-296-7827 I 0/14/78 ire Pnl 25-329 arm sounding None Bad smoke arm sounding with Replaced detector Protection ith no smoke detector 1802E o smoke 1082E. Checked ok. | |||
TR 91355 I | |||
LO/16/78 ieael Gen H2 Air Comp 'ompressor vill None Pressure svitch omp would not shut Replaced'ressure D/G 3D ot shut off was not opening ff and lifts safety switch. Inst Dept valve calibrated new switch psi. Checked ok. | |||
TR 106542 | |||
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BROIB5E FERRY NUCLEAR FLANT UNIT~ | |||
INSTRUMENT kfhIHTEHhHCE SRfMARY CSSC EQUIPMENT FOR TllE MONTH OF ~~-, 1978 t'ata System .'omponent Nature of Maintenance Effect on'afe Operation of the reactor Cause of Malfunction | |||
'esults of Malfunction Action Taken to preclude recurrence | |||
. UNIT 10/15 RWCU FR-69-35 intenance None | |||
' | |||
"..'ransfer | |||
. ~ | |||
lever missgng' Mould not work in auto None mode 10/17 Radiation 250 aintenance None Drive binding Could not run source None Monitoring check 10/12 Feedwater FI-3-78B alibration None Instrument drift Indicated flow with None no actual flow 10/23 Main Steam S-1-17A eplace None Broken temperature .switch One/half isolation on Hone primary containment 10/31 Neutron SRM-A eplace None Faulty drive caused SRM-A Inoperable Repaired Monitoring detector to deplete drive 10/31 Neutron SRM-A Drive epair. None Broken guide bear'ing . Detector would not None Monitoring drive 10/30 Neutron IRM C intenanch None Dirty connector, low Erratic signal Hone Monitoring pteamp gain. | |||
)5 | |||
31 Outa e Summa Unit 3 Octobex'978 The fuel bundles have been sipped and shuffled in order to permit coze reload. The completion of the GE vibration instrumentation removal and control xod operability checks have put fuel reloading about 18 days behind the original critical path schedule. | |||
All the MSXV's are completely zepaired and installed. The majority of the miscellaneous valves have passed the LLRT either initially or after zepaiz. There are still six valves which are to be repaired and retested. A total of seven contzol rod drives weze changed out after pxoblems were en-cquntered with CRD 38-51 and 34<<23. The scram discharge header modification portions of the EECM piping change were completed. The CRD piping zeroute to the steam tunnel along with the CRD nozzle repaix'nd capping were completed. | |||
The recirculation pump trip (RPT) modification for unit 3 is essenti-ally completed with only post modification testing yet to be done. Other modi-fications which axe still underway aze the off-line zadiation monitor, the diesel dxiven fize pump, and the standby gas treatment changes. The zecirculation pump MG set x'otoz repair has been completed and an inspection is underway to see if there is any damage to the unit 1 rotors. | |||
The L-1 moistuxe removal modification has been completed and now reassembly of the low pzessuxe turbine and reactor feedpump tuxbine are complete except for the system oil flush. The mods on the HPCI and RCIC turbines aze also complete.}} | |||
Revision as of 02:06, 22 October 2019
| ML18024A518 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/02/1978 |
| From: | Green D TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A516 | List: |
| References | |
| NUDOCS 7811140140 | |
| Download: ML18024A518 (33) | |
Text
TENNESSEE VALLEY AUTHORITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTHLY OPERATING REPORT October 1, 1978 - October 31, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68 Submitted by P nt Superintendent
)c 6'/ppypy
TABLE OF CONTENTS Operations Summary ~ ~ ~ ~ ~ ~ ~ ~ ~ e ~ ~ l Operational Data .- . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 2 Maintenance ~ ~ ~ ~ ~ ~ ~ ~ ~
Refueling Information ~ ~ 3 Significant Operational Events . . . . . . . . . . . . . . . . 5
'verage Daily Unit Power Level . o ~ 9 Operating Data Reports o ~ ~ ~ ~
Unit Shutdowns and Power Reductions.............. l5 Plant Maintenance Summary. ~ ~ ~ o ~
Unit 3 Refueling Outage Summary...... ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 31
erations Summa 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 and begins on page 5.
There were 6 Reportable Occurrences reported to the NRC during the month of October.
Unit 2 Significant operational events for unit 1 are tabulated by date and time beginning on page 5.
The unit did not scram during the month of October.
Power was administratively limited throughout the month by 60K "B" recirculation pump speed, with "A" loop out of service, except for testing on October 25 at 70K pump speed.
A summary of maintenance work is shown on pages 18 through 30; Unit 2 Significant operational events for Unit 2 are tabulated by date and time beginning on page 6.
There was one scram during 'the month. On October 10 the reactor scrammed during surveillance testing when piping was accidently bumped; causing a false high water level signal in the scram discharge volume.
A summary of maintenance work is shown on pages 18 through 30.
Unit 3 Significant operational events for Unit 3 are tabulated by date and time beginning on page 8.
The unit was down the entire month for refueling.
A summary of maintenance work is shown on pages 18 through 31.
erations Summa (Continued)
Common S stems Approximately 8.92E-1 gallons of waste liquid were discharged containing approximately 7,p2E-1 curies of activity.
Cooling towers 1, 2 (until October 2) and 6 were operational this month for two lift pump operations. Modifications by the tower vendor were continued on Tower 3 and modifications to Tower 2 began on October 2. None of the towers. had significant operational problems.
erational Data 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.
Maintenance Ma)or electrical, mechanical, and instrument maintenance activities during the month, are described on pages 18 through 3p . Refueling outage activities for Unit 3 are summarized on page 31.
Refuel in Information Unit 1 Unit 1 fs scheduled for its second refueling begfnnfng on Nobember 18, 1978, wfth a restart date of December 20, 1978. Resumption of operatfon on that date will requfre a change fn technical speciffcatfons pertaining to the core thermal limits. Licensing informatfon in support of these changes was submitted fn August 1978. This refueling will load additional 8 X SR (retrofit) fuel assemblies into the core, replacing presently loaded 7X7 fuel and will involve installing a new recirculation pump trfp (RPT) system.
There are 764 fuel assemblies fn the core. The spent fuel storage pool presently contafns 168 spent 7X7 fuel assemblies and 156 new 8 X 8R fuel assemblies. The px'esent stox'age capacfty of the spent fuel pool fs 1080 assemblies. Present planning is to incxease that capacfty to 3471 assemblies.
With present capacfty, the refueling later fn 1978 would be the last refueling that could be discharged to the spent fuel stoxage pool without exceeding that capacfty and mafnt~g full core discharge capability fn the pool.
Unit 2 Unit 2 fs schedu1ed for fts second refueling beginning on April 22, 1979, with a restart date of July 1, 1979. Resumption of operatfon on that date will require a change in technical specfficatfons pertaining to the core thermal limits. Present scheduling is to submft licensing information in support of these changes before the xefuelfng. This refueling will involve xeplacing.
some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies.
There are 764 fuel assemblies fn the core. At the end of October there were 132 discharged cycle 1 7 X 7 fuel assemblies fn the spent fuel storage pool.
There are presently 36 new 8 X 8 fuel assemblfes fn the spent fuel storage pool which were not loaded into the core during thfs cycle. The present storage
Re fuelin Information (Continued)
Unit 2 (continued) 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 spent fuel pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Unit 3 Unit 3 began its first refueling on September 8, 1978, with a scheduled restart date of November 20, 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 July, 1978. This refueling involves 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.
There are 143 fuel assemblies presently in the core. There are 829 fuel assemblies in the spent fuel storage pool. All but 208 of these will be reloaded into the- core for cycle 2.. The present licensed storage capacity of the spent fuel pool.'is 1132 assemblies.
Si ficant erational Events Date Theme Event Unit 1 10/1 0000 Reactor thermal power at 56X, holding for "A" recirculation loop being out of service control rod sequence "3".
10/4 1046 Commenced special test no. 160 (single zecirculation loop operation mmcLmum flow) .
1845 Special test no. 160 completed, reduced thermal power from 63X to 53X, holding for single recirculation loop operation and control rod pattern ad5ustment.
~ - 10/5 1730 Control rod pattern established commenced po~er ascensions from 53X thermal power.
2300 Reactor thermal power at 58X, holding for single recix'culation loop operation.
10/7 0120 Reduced thermal powex from 58Z to 54X fox'urbine C.V. tests and SZ's.
0530 Turbine C.V. tests and SZ's completed; increased thermal power to 58X holding for single recirculation loop operation.
10/12 1350 Reduced thermal powex from 58X to 50Z for recirculation pump test (STT.-160).
1540 Recirculation pump test (STI-160) completed/commenced ascension. 'ower 2300 Reactor thermal power at 58X, holding for single recix'culation loop operation.
10/21 2100 Reduced thermal power from 58X to 50Z for contxol zod staU. flow and leak tests (SIL-52).
2155 Control rod stall flow and leak tests completed commenced power ascension.
10/22 0700 Reactor thermal power at 59Z holding for single recirculation loop operation.
Si ficant erational Events Date 22ne Event Unit 1 (continued) 10/25 1000 increased recirculation pump flow for 66X thermal power.
1100 Reduced thermal power to 59X, holding.
10/31 '400 Reactor thermal power at 59X, holding for single recirculation loop operation.
Unit 2 10/1 OOOO Reactor shutdown for scheduled outage, in hot standby mode.
10/3 1221 Commenced rod withdrawal for startup.
1245 Reactor critical no. 84; Rolled T/G.
2147 Synchronized generator, commenced power ascension.
2205 Reactor thermal power at 20X, holding for primary containment leak rate test. (Air lock door).
10/4 1717 Primary containment integrity established commenced power ascension from 20X thermaL power.
10/5 L500 Commenced PCZOMR from:84X thermal power (Sequence "A").
LQ/6 L500 Reactor thermal power at 98X, core flow limited.
10/7 2310 Reduced thermal power from 98X,to"85X for turbine C.V.
tests and SZ's.
10/8 0035 Turbine C.V. tests, and SI's completed, commenced power ascension.
10/8 0230 Commenced PCIOMR from 90X thermal power.
2200 Reactor thermal power at 98X, core flow. Limited.
10/9 1500 Reactor thermal power at 98X, core flow limited.
Si nificant 0 erational Events Data Time Event Unit 2 (ccntinned) 10/10 0947 Reactor scram no. 72 (1) on erroneous scram discharge volume high level during SI 4.1.A.8.
1130 Commenced rod withdrawal 1245 Reactor critical no. 85 1445 T/G. 'olled 1503 Synchronized generator, commenced power ascension.
10/11 0052 Reduced thermal power from 90X to 77X to compensate for xenon burn out.
0252 Commenced power ascension from 77X thermal paver.
0635 Commenced PCIOMR from 85X thermal 'power (sequence "B").
2025 Reactor thermal power at 98X steady state.
2055 Reduced thermal paver from 98X to 90X due to "C" string high pressure heaters isolation for maintenance (repair leaks) .
10/12 0915 Increased thermal paver from 90Z to 92X with "C" string high pressure heaters out of service for leak repairs.
10/13 1700 "C" string high pressure heater repairs completed and placed in service commenced PCIOMR from 92X thermal power.
10/14 0700 Reactor thermal pover at 98X, steady state.
2335 Reduced thermal paver from 98X to 85X for turbine C.V.
tests and SI's.
10/15 0026 Turbine C.V. tests and SI's completed, commenced power ascension.
0200 Reactor thermal power at 98X steady state.
10/20 2040 Reduced thermal paver from 98X to 45X for maintenance to "C" condensate booster pump (oil leak) and for brush replacement on both recirculation pump M.G- sets.
Si nificant 0 erational Events Dete Tine Event Unit 2 (continued) 10/21 0103 Maintenance to "C" condensate booster pump completed and both recirculation pump MG sets brush replacement completed, commenced power ascension.
1700 Commenced PCIOMR from 80X thermal powere 10/22 2300 Reactor thermal power at 98X, steady state.
10/27 2250 Reduced thermal power from 98X to 85X for turbine C.V. tests and SI's.
10/28 0140 Turbine C.V. tests and SI's completed, reduced thermal power from 85Z to 50X for control rod pattern ad5ustment.
0405 Control rod patt'ern established, commenced PCIOMR from 50X thermal power.
10/30 2300 Reactor thermal power at 98X, steady state.
10/31 2400 Reactor thermal power at 98X, steady state.
Unit 3 10/1 0000 Refueling outage in progress with all fuel assemblies in the fuel pool storage.
10/29 1835 Commenced loading cycle 2 fuel.-
10/31 2400 143 fuel assemblies reloaded into core.
End of Month (1) Maintenance error during surveillance testing.
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. -2 9 UNIT DATE COMPLETED BY TELEPHONE MON'Oi DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAlLYPOWER LEVEL (MWe-Net) (MWe.Net) 17 18 588 19 588 558 20 585 21 583
'83 603 24 601 25 621 10 26 591 559 644 13 599 29 623 14 30 601 15 31 596 16 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 megawatt.
E (o/77)
10 AVERAGE DAlLYUNIT POWER LEVEL DATE 11-2>>78 COMPLETED BY TELEPHONE MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe.Ne!) (MWe-Net) 17'066 19 1065 223 20 1002 825 21 797 6 ~OZ7" 22 1033 1073 1090 24 1081 1030 1089 10 653 26 1053 27 1064 12 637 13 1032 857 14 1065 30 1007 IS 1054 31 1071 16 INSTRUCTIONS On this format, list the average daily unit puwer level in MNte.iNet for each day in the reporring month. Compute to the nearest whole megawat t.
(()/771
AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 50-296
- COMPLETED BY TELEPHONE R46 MONTH DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL (MWe-Net) (Meet) 17 19 20
. 21 22 7.
24 M3 10 26 w3 27 12 28 13 <<2 29 14 30 15 31 16 INSTRUCTIONS On this format, list the average daily unit power level in MV/e.Net for each day in the reporting month. Compute to the nearest whole megawatt.
(t)(771
12 OPERATING DATA REPORT DOCKET NO.
DATE COMPLETED BY QQ~+rggu, TELEPHONE ~244M46 OPERATING STATUS Notes
- 1. Unit Name:
- 2. Reporting Period: October 78
- 3. Licensed Tiiermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
10 5
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
- 7. Maxtmum Dependable Capactty (Net MWe).
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted, lfAny (Net MWe):
- 10. Reasons For Restrictions, lf Any:
is out of e P This Month Yr:to.Date Cumulative
- 13. Reactor Reserve Shutdown Hours 0 352.33 4 399.13 14..Hours Generator On-Lme 745 6 424.33 19 070.~6
- 15. Unit Reserve Shutdown Hours 0 17,19,22 49,571,455 I7. Gross Electrical Energy Generated (MWH) <<5,617,560 16,435 5RA
- 18. Net Electrical Energy Generated (MWH) 5 446 826 15 935 173 88.1 51.2
*-
- 19. Unit Service Factor
.
23 Unit. Forced. Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date. and Duration of Each):
~M. IfShut Down At End Of Report Perio, Estimated Date of Startup:
- 26. Units In Test Status {Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY IN ITIA L ELECTRICITY COMMERCIAL'PERATION
<oP7)
~ ~
13 OPERATING DATA REPORT DOCKET NO.
DATE COMPLETED BY TELEPHONE ~~~-6846 OPERATING STATUS Notes ~
- l. Unit Name:
. 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
et'e
- 7. Maxtmum Dependable Capacity (N i I ).
- 8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:
~
~
- 9. Power Level To Which Restricted, If Any (Net 5IWe):
- 10. Reasons For Restrictions. If Any:
" II. Hours.ln Reporting Period
~ 12.
- 13. Reactor Reserve Shutdown Hours
. This Month ai Yr:to-Date Cumulative
- 14. Hours Generator On Line
- 15. Unit Reserve Shutdbwn Hours 16, Gross Thermal Energy Generated (MWH) 1 977 564 12 714 751 8 887 888 17.
18.
- 19. Unit Service Factor
- 20. Unit Avaihbility Factor 89.9 62.6 45.4
- 21. Unit Capacity Factor (Using MDC Net) 81.6 51. 9 36.1 22 Unit Capacity, Factor (Using DER Net) 81. 6 51.9 36.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date:and Duration of Each):
~A. IfShut Down At End Of Report Period, Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION (oI77)
14 OPERATING DATA REPORT DOCKET NO. 50-296 DATE u-2-78 COhlpI.ETED 8Y Don Green.
TELEPHONE ZO'~9=6846 OPERATING STATUS Notes
- l. Unit Name.
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
- 4. Nameplate Rating (Gross MWe):
S. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
7' 2 axunum De pend aleb Cap aci ty(Ne tMWe' ).
- 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. If Any:
This Month Yr.-to-Date Cumuhtive ll. Hours In Reporting Period
- 12. Number Of Hours Reactor Was Critical 0 5 503.2
- 13. Reactor Reserve Shutdown Hours 0
- 14. Hours Generator On-Line IS. Unit Reserve. Shutdown Hours 0
- 20. Unit Availability Factor 0 74.2 81. 4
- 21. Unit. Capacity Factor (Using MDC Net) 0
~M. Unit.Capacity. Factor (Using DER Net) 0 62.9 68.
- 23. Unit Forced. Outage Rate 0'24.
Shutdowns Scheduled Over Next 6 Months (Type. Date; and Duration of Each):
Ã. IfShut Down At End Of Report Periotl, Estimated Date of Startup:
- 26. Units ln Test Status (Prior to Commercial Operation): Forecast Achieved INITIALCRITICALITY INITIALELECTRICITY COhtM ERCIA L OPERATION (4/77)
I ~
DOCKET NO.
UNITSIIUTDOWNS AND POWER REDUCTIONS l '
COhIPLETED BY REPORT MONTH QQfd?hgZ.
~P L
l C ~ rc PJ P Lh:cllscc E~ El IA C
o Cl0 Cause Ec Corrcclivc gA Q Action lo No. Dale ~
Event Vl P cL 0
U<a c cc P
A~ ~ Cll Rcpurt ¹ cn C5 O CJ Prcvcnt Rccuncncc 3 4 F: Furccd Reason: Method: Exhibit G - lnstcuctions S: Scheduled A.Equipmcnt Failure (Explain) I -hlanual for Preparation of Data B hlalntenancc or Test 2.hlanual Scram. Entry Sheets for Licensee C.Rc fueling 3-Aulontalic Scram. Event Rcport (LER) File (NUREC.
D Regulatury Restriction 4.Other (Explain) OI6I )
E-Operator Training dc Uccnsc Examinaliun F.Administrative 5 G<pecational Error (Explain) Exhibit I - Sante Source
(~tin) I IPOthcr (Explain)
IN 1
DOCKET NO.50-26o UNITSHUTDOWNS AND POWER REDUCTIONS COMPLETED By Don Oreen
~ ~
REPORT MONTH October CI EI Lice nscc Ew Cause h Corrective g g'>> Q 0 uU Dale Event ~ 4 Q Action lo C4 Report ¹ ro G Eu CJ Prcvcnl Recurrence 64 781001t P 69.78 A, Investigation of unidentified leakage into drywell and repair of drywell E ui ment Drain sum um .
65 781010 5 '7 6 "Sensed" scram discharge volume high ater level when instrument mechanics nadvertently bumped piping with a ladder.
66 781020 B crated to perform maintenance on "C" condensate booster um (oil leak).
67 781028 H ontrol rod pattern ad)ustment.
- 3. 4 F: Forced 'eason: Method: Exhibit C - Instructions S: Scheduled A Eqtripmcnt Failure (Explain) I Manual for Preparation of Data
, P Maintenance oi Test 2 Manual Scram. 'ntry Sheets I'or Licensee C.Refueling 3.Automatic Scram. Event Report (LER) File (NUREC.
D Regulatory Restriction 4.Other (Explain) OI6I )
E43perator Training Ec License Examination F-Ad jninist ra t ivc 5 C Opcratiunal Error (Explain) Exhibit I - Same Source (I/77) I I Other (Explain) j
DOCKET NO.
UNIT SHUTDOWNS AND POWER REDUCTlONS UNIT NAhlE DATE COMPLETED BY Don t'reen TELEPIIONE 205 7296846 P'o.
Vg C ~ CO Llccnscc Cause Ec Corrcctivc Date Event Action to aK u<
~ EA C Rcpurt ¹ Prcvcnt Recuncnce I
64 781001 S 745 C 2 I 3 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) I-hlanu'al lor Preparation ol Data II-hlalntenancc or Test 2.hlanual Scram. Entry Shccts for Licensee f-Refueling 3.Aulontatic Scram. Event Riporl (LERI File (NUREG-D Regu'latory Restriction 4-Other (Explalttl OI6I )
E Operator Training h Liccnsc Examination F-Adndnistra tive G.Operatiunal Error (Explain) Exhibit I - Sante Source I I.Other (Explain)
.BROWNS I'ERRY NUCLEAR PUNT UNIT
~ MECllANICAL MAINTENANCE
SUMMARY
For the Month of 'CTOBER 1978 I
l EFFECT ON SAFE ACTION TAKEN NATURE OP OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE DATE SYSTEM COMPONENT ',
MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE
.0/12 RHR Servic C-3 & B-3 ',Packing leak- None !Loose packing None Adjusted packing Mater RHR service jing System water pump
.0/12 >RHR Servic C-RHR service Packing None Loose packing None Ad)usted packing Water water pump leaking System room strainer
.0/18 Diesel Both fuel Dirty filters None Operation None Changed 2 filters on Generators filters 'on 1D "D" diesel diesel .
.0/19 Diesel Clean 1-A & 1- Coolers were None Some mud in ltone Removed coolers Generators diesel genera- dirty coolers- heads, cleaned tor coolers needed cleaning coolers, replaced heads using new gasket
.0D20 Service Al RHR Service, Float hyng up None Blown pipe plug None Repaired 'pipe plug Mater water pump System discharge air regief valve I
BROMNS FERRY NUCLEAR PLANT UNIT MECIONICAL MAINTENANCE SUK4lRY For the Month of OCTOBER 19 78 EFFECT ON SAFE ACTION TAKEN DATE SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE TllE REACTOR MALFUNCTION MALFUNCTION RECURRENCE LO/1 Standby Valve 863-518 Packing blown None Morn out packing None Rephced valve Liquid Control System
.0/2 Uigh-Pres- Coupling on Leaking at None Unknown None Tightened up union to sure Cool. line to oil union oil cooler ing coolers In5ection System
.O/6 Control CRD Module Packing leak None Loose packing None ightened packing Rod Drive 38-11 Valve 1-85-39B
.0/12 Control Rod CRD accum 26- Leaking around None Loose'packing Nona Replaced valve Drive 35 leaking N2 packing of around 85-229A valve 229 Control Rod ACRD suction Dirty filter Nona Operation None Replaced with clean lM.ve filters need / filters cleaning I
lO/19 CoaiCP51 Rod Discharge Dirty filter None Operation Nona Replaced filter Drive .. filter >>B
1 BROWNS PERRY NUCLEAR PQlNT UNIT 2 MECHANICAL MAINTENANCE SUGARY
,P
.Por the Month of OCTOBER 19 '78 EPPECT ON SAFE ACTION TAKEN SYSTEM COL fPONENT NATURE 6P OPERATION OP CAUSE OP RESULTS OP TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION RECURRENCE reactor Outboard bear- ; Bad bearing, .None Unknown. None Replaced flywheel Protection ing on 2B bearing preferred M-G Nigh Val 2-73-552 Loose packing None Loose packing None Tightened nuts on Pressure HPCI vent valv gland gland bolts packing gland Cooling In)ection System Control Replace out- Leaking mech None Crack in seal None Replace bearing 0 Rod Drive board mech sea seal face rings, sleeve, mech on 2ACRD seal and new oil C)
BROWNS FERRY NUCLEAR PUNT UNIT 3 MECHANICAL MAINTENANCE
SUMMARY
For the Month of OCTOBER 19 78 EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE THE REACTOR MALFUNCTION NALFUNCTIO RECURRENCE 0/4 Fttel Fool. A & B fuel pool Packing leak- None Operation None Ad)usted packing Cooling & cooling pump ing Demineral-izing System 0/8 RNR Syst: em RUR valve no. Leaking stem None Loose packing None Tightened packing nuts 74-12 0/11 Ventilation 3A Control rm Broken belts None Operation None Replaced belts System air handling unit
.0/12 Fuel Pool Val 878-63 & Valves packing None Loose packing None Tightened valves pack-Cooling & 78-64 leaking ing Demineral-izing 0 12 Ventilation 3A Control bay Leaking oil None Bad "0" ring and None Replaced "0" rings.
System chiller around peal bad seal and seal .
CRD 3A,CRD pump Seepage around None Operation None ightened bolts on bolts and pump heads LO/17 Ventilation 0 -3 R.B. & R.R. Rust in air None Unknown None Flushed coils System supply fane line LO/20 EECW System Valve 67-66 Leaking flange None Loose flange None Tightened up and RllR "D" seal bolts stopped leak heat exchange outlet
BROPNS FERRY NUCLEAR PLANT UNIT
~ ~
HECIIANICAL MAINTENANCE
SUMMARY
OCTOBER 1978 For the Month of ..
I
- EFFECT ON SAFE ACTION TAKEN SYSTEM COMPONENT NATURE OF = OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE i TIIE REACTOR MALFUNCTION MALFUNCTIO RECURRENCE 0/20 Fuel Pool ICV 78-64 (F/0) Packing leak- None Loose packing None Tightened packing Cooling & influent out ing Deminerali board valve zing Syste 0/23 CRD 3 ACRD pump Discharge None Operation None Changed filter filter dirty 0/24 RIIR System Valve 74-12 Packing leak>> None Loose packing None Tightened packing'nuts ing h
.0/24 CRD 10-23 Accumulator None Bad cartridge Nona Changed valve and valve didn't charge valve.and cap replaced cap missing
I I >>
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BROBXIE PERRX NUCLEAR PLANT UIIZT ELECTRICAI. MAINTENANCE SIWhRY i ~For the Month of l OCTOBER l9 78 PAGE 1 ect on a e Action Taken Date System Component Nature of 'peration of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence
,0/10/78 Diesel EHI 3 D/G 3AB G Redundant None 'SFDI relay on Did not meet timing Changed out SFDI rela Generators 3B, 3C and 3D tart test D/G 3a was out criteria of EHI 3 Ran SI 4.9.A.l.d of time tested ok with EHI 3.
TR 87901
.0/12/78 Control Bay Control Bay erform routine None Dirty oil filter None Changed oil filter, Ventilatio Chiller 3B nd ma)or maint saturated from freon drier,'hanged s required drier, oil leaks repaired oil and Freon leaks, freon leaks. Changed faulty shaft oil system. Checked seal. Clogged and repaired instru-oil strainers. mentation. Returned to service. Checked ok. TR 106623
.0/12/78 ire Panel 25-327 ouble alarm None K2 relay not Trouble alarm in CR Replaced K2 relay.
Pvotaotion n CR and not making contact and hot on local Tested ok. TR 91358 .
n local panel panel BFRO 50-296-7827 I 0/14/78 ire Pnl 25-329 arm sounding None Bad smoke arm sounding with Replaced detector Protection ith no smoke detector 1802E o smoke 1082E. Checked ok.
TR 91355 I
LO/16/78 ieael Gen H2 Air Comp 'ompressor vill None Pressure svitch omp would not shut Replaced'ressure D/G 3D ot shut off was not opening ff and lifts safety switch. Inst Dept valve calibrated new switch psi. Checked ok.
TR 106542
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BROIB5E FERRY NUCLEAR FLANT UNIT~
INSTRUMENT kfhIHTEHhHCE SRfMARY CSSC EQUIPMENT FOR TllE MONTH OF ~~-, 1978 t'ata System .'omponent Nature of Maintenance Effect on'afe Operation of the reactor Cause of Malfunction
'esults of Malfunction Action Taken to preclude recurrence
. UNIT 10/15 RWCU FR-69-35 intenance None
'
"..'ransfer
. ~
lever missgng' Mould not work in auto None mode 10/17 Radiation 250 aintenance None Drive binding Could not run source None Monitoring check 10/12 Feedwater FI-3-78B alibration None Instrument drift Indicated flow with None no actual flow 10/23 Main Steam S-1-17A eplace None Broken temperature .switch One/half isolation on Hone primary containment 10/31 Neutron SRM-A eplace None Faulty drive caused SRM-A Inoperable Repaired Monitoring detector to deplete drive 10/31 Neutron SRM-A Drive epair. None Broken guide bear'ing . Detector would not None Monitoring drive 10/30 Neutron IRM C intenanch None Dirty connector, low Erratic signal Hone Monitoring pteamp gain.
)5
31 Outa e Summa Unit 3 Octobex'978 The fuel bundles have been sipped and shuffled in order to permit coze reload. The completion of the GE vibration instrumentation removal and control xod operability checks have put fuel reloading about 18 days behind the original critical path schedule.
All the MSXV's are completely zepaired and installed. The majority of the miscellaneous valves have passed the LLRT either initially or after zepaiz. There are still six valves which are to be repaired and retested. A total of seven contzol rod drives weze changed out after pxoblems were en-cquntered with CRD 38-51 and 34<<23. The scram discharge header modification portions of the EECM piping change were completed. The CRD piping zeroute to the steam tunnel along with the CRD nozzle repaix'nd capping were completed.
The recirculation pump trip (RPT) modification for unit 3 is essenti-ally completed with only post modification testing yet to be done. Other modi-fications which axe still underway aze the off-line zadiation monitor, the diesel dxiven fize pump, and the standby gas treatment changes. The zecirculation pump MG set x'otoz repair has been completed and an inspection is underway to see if there is any damage to the unit 1 rotors.
The L-1 moistuxe removal modification has been completed and now reassembly of the low pzessuxe turbine and reactor feedpump tuxbine are complete except for the system oil flush. The mods on the HPCI and RCIC turbines aze also complete.