ML20058A099
| ML20058A099 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/30/1978 |
| From: | Dewease J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18024A487 | List: |
| References | |
| NUDOCS 7810160109 | |
| Download: ML20058A099 (34) | |
Text
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TENNESSEE VALLEY AUT110RITY DIVISION OF POWER PRODUCTION BROWNS FERRY NUCLEAR PLANT MONTilLY OPERATING REPORT September 1, 1978 - September 30, 1978 DOCKET NUMBERS 50-259, 50-260, and 50-296 LICENSE NUMBERS DPR-33, DPR-52, and DPR-68
'/
M Submit ted by _', _._
ant Superintendent nuwrut n
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l TABLE OF CONTENTS Operations Summary.
1 Operational Data.
2 4
Maintenance 2
Refueling Information 3
Significant Operational Events.
5 Average Daily Unit Power Level.
10 Operating Data Reports.
11 Unit Shutdowns and Power Reductions.
16 Plant Maintenance Summary.
19 Unit 3 Refueling Outage Summary.
31 s
he
b Operations Summary 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 September.
Unit 1 Significant operational events for unit 1 are tabulated by date and time beginning on page 5 The unit scrammed five times during the month of September. The unit was manually scran=ed on September 3 and 9 to investigate high drywell leakage. On September 11 the reactor scrammed en APRM high flux due to a recirculation flow spike caused by an unexplained sudden ramp in "B" recirculation pump speed. The unit was manually scrammed on September 14 due to recirculation flow problems found to be caused by FCV 68-3.
On September 20 the unit scrammed with no generator load during turbine warming due to turbine first stage pressure exceeding the 30% power bypass for turbine stop valve closure trip.
From September 23 to September 29 power was limited to 50% thermal power by the technical specifications, awaiting further analysis for single loop operation.
Af ter September 29, power was administratively limited by 50% "B" recircula-tion pump speed, with "A" loop out of service.
A surc. mary of maintenance work is shown on pages 19 through 30 Unit 2 Significant operational events for unit 2 are tabulated by date and time beginning on page 7.
There was one scram during the conth. On September 29 the reactor was manually scranned to investigate drywell leakage and to repair drywell equipment drain sump pumps.
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Operations Summary (Con't)
Unit 2 (Con't)
A summary of maintenance work is shown on pages 19 through 30.
Unit 3 Significant operational events for unit 3 are tabulated by date and time beginning on page 9.
The unit scram =ed once during the month of September. The reactor was manually scrammed on September 8 to accomodate the scheduled refueling outage.
A summary of maintenance work is shown on pages 19 through 31.
Common Systems On September 21, a head gasket failed on the radwaste waste filter.
The filter was repaired and returned to service within % 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Approximately 8.1 E+5 gallons of waste liquid were discharged containing approximately 6.9 E-1 curies of activity.
It is estimated that the use of auxiliary boiler steam during unit outages contributed 6.0 E+5 gallons of demineralized water to radwaste.
Cooling towers 1, 2, 3 (until September 18) and 6 were operational this month for two lift pump operations. Modifications by the tower vendor were begun on Tower 3 on September 18.
None of the towers had significant operational problema.
Operational Data The average daily unit power level for units 1, 2, and 3 is shown on 1
pages 10 through 12.
The operating data reports for all three units are shown on pages 13 through 15.
Unit shutdowns and power reductions for all three units are shown on pages 16 through 18.
t
-2a-Maintenance Major electrical, mechanical, and instrument maintenance activities durint: the month are described on pages 19 through 30.
Refueling outage activities for unit 3 are summarized or. page 31.
Refueline Information h
Unit 1 Unit 1 is scheduled for its second refueling beginning on November 10, 1978, with a restart date of December 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 August 1978. This refueling will load additional 8 X 8R (retrofit) fuel assemblies into the core, replacing presently loaded 7 X 7 fuel and will involve installing a new recirculation pump trip (RPT) system.
There are 764 fuel assemblies in the core. The spent fuel storage pool presently contains 168 spent fuel assemblies and 156 new fuel assemblies.
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 refueling later in 1978 would be the last refueling that could be discharged to the spent fuel storage pool without exceeding that capacity and maintaining full core discharge capability in the pool.
Unit 2 Unit 2 is scheduled for its second refueling beginning on April 22, 1979, with a restart date of July 1, 1979. Resumptf of operation on that date will require a change in technical specifications ;-
> ning to the core thermal limits.
Present scheduling is to submit licensing information in support of these changes before the refueling. This refueling will involve replacing some more 7 X 7 fuel assemblies with 8 X 8R (retrofit) assemblies.
There are 764 fuel assemblies in the core. At the end of September there were 132 discharged cycle 1 fuel assemblies in the spent fuel storage pool. There are presently 36 new 8 X 8 fuel assemblies in the spent fuel storage pool which were not loaded into the core during this cycle. The present storage capacity of
- Refueling Information (Con't)
Unit 2 (Con' t) 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 October 31, 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 8 X 8R (retrofit) assemblies, modifying the main steam relief valves to increase simmer margin, and installing a new recirculation pump trip (RPT) system.
There are 764 cycle 1 fuel assemblies in the spent fuel storage pool.
There are 208 new 8 X 8R (retrofit) assemblics present in the spent fuel storage pool. The present licensed storage capacity of the spent fuel pool is 1132 assemblies.
l l
l Significant Operational Events
_D_a__t e Time Event Unit 1 9/1 0000 Reactor thermal power at S6%, sequence B, holding CPR limited.
2230 Reduced thermal power from 86% to 73% for removal of "B" recirculation pump MG set from service for brush replacement and turbine CV tests and SI's.
9/2 0015 Turbine C.V. tests and SI's completed, holding at 73% thernal power for "B" recirculation pump MG set brush replacement.
0115 "B" r2 circulation pump MG set brushes replaced and pump placed in service.
0125
"*" r. circulation pump MG set removed from service for brush replacement.
0250 "A" recirculation pump MG set brushes replaced and pump placed in service.
0255 Cotrenced power ascension frca 73% thermal power.
1500 Reactor thermal power at 85%, CPR limited.
9/3 2200 Conmenced reducing thernal power from 85% for removal of unit from service for drywell maintenance to valve FCV-69-1 (excessive drywell leakage).
2245 Reactor scran no. 97 (manual)frca 40% thermal power to accomodate drywell naintenance to FCV-69-1.
9/5 2210 Maintenance to valve FC'.*-69-1 completed, commenced rod withdrawal.
2335 Reactor critical no. 109.
9/6 0200 Reactor nade subcritical with RPV at 1000 psi, holding for drywell entry for leak cheeks.
0340 Leak checks ccepleted, resumed startup.
0355 Reactor critical no. 110.
0725 Rolled T/G.
0757 Synchronized generator, connenced power ascension sequence "B".
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6 Significant Operational Events Date Time Event
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Unit 1 (continued).
9/7 1230 Reduced thermal power from 72% to 66% due to "B" recirculation pump trip during valve backseating operations.
1255 "B" recirculation pump returned to service commenced power ascension from 66% thermal power.
l 9/8 0930 Commenced PCIOMR from 75% thermal power.
9/9
-1945 Co=menced reducing thermal power from 86% for shutdown due to excessive drywell leakage. FCV 68-77 leaking.
2115 Reactor scram no. 98 (manual) from 42% thermal power to accommodate maintenance.
9/10 1630 Maintenance completed, commenced rod withdrawal.
1759 Reactor critical no. 111.
2008 Rolled T/G.
2022 Sychronized generator, commenced power ascension, sequence "B".
9/11 0530 Commenced PCIOMR from 67% thermal power.
Reactor scram (1) no. 99 from 73% thermal power on 1226 APRM hi hi flux.
Recirculation pumps ramped up.
1415 Commenced rod withdrawal.
1515 Reactor critical no. 112.
1702 Rolled T/G 1725 Synchronized generator, commenced power ascension sequence "B".
9/12 0015
' Commenced PCIOMR from 66% thermal power.
1703 Reduced thermal power from 90% to 80% due to "A" recirculation pump run back.
2332 Commenced reducing thermal power from 80% for shutdown due to flow problens on recirculation pump
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loop "A" (valve FCV 68-3 broken disc).
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-Significant Operational Events Date Time Event l
Unit 1 (continued)
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. i 9/14 0041 Reactor scram no. 100 (manual) from 40%
thermal power to accommodate maintenance.
f 2020 Unit at cold shutdown.
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9/20 0545 Maintenance outage completed, commenced rod withdrawal.
0625 Reactor critical no. 113.
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0700 Reactor suberitical due to rod block.
0820 Rod block cleared, commenced rod withdrawal.
t 0835 Reactor critical no..ll4.
1542 Reactor scram (
101 30% power / pressure setpoint no.
inadvertently reached during turbine steam chest warmup from 5% thermal power 1655 Commenced rod withdrawal.
i 1740 Reactor critical no. 115.
I 9/21 0030 Rolled T/G.
0102 Synchronized generator, commenced power ascension.
l 9/23 1500 Reactor thermal power at 50%, holding due to "A" J
recirculation loop out of service (pump discharge valve l
68-3 inoperable).
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9/29 1825 Commenced power ascension from 50% thermal power
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with rods.
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l 9/30 0900 Reactor thermal power at 56u.
2400 Reactor thermal power at 56%, holding due to "A" recirculation loop out of service.
I Unit 2
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9/1 0000 Reactor thermal power at 95% sequence "A" core f
flow linited.
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- t 2355 Reduced thernal power from 950' to 90% for turbine C.V.
l tests and SI's.
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Significant Operational Events Date Time
' Event
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Unit ' 2 (continued) 9/2 0100 Turbine C.V. tests and SI's completed, commenced power ascension.
0400 Reduced thermal power from 96% to 35% for brush replacement of both recirculation pump MG sets and control rod sequence exchange from "A" to "B".
0716 Brush replacement of both recirculation pump MG sets completed, holding for. control rod sequence exchange.
0800 Control rod sequence exchange from "A" to "B" completed, commenced power ascension.
1500 Commenced PCIOMR from 68% thernal power.
9/5 0600 Reactor thermal power at 97%, core flow limited.
9/6 1500 Reactor thermal power at 96%, core flow linited.
1 9/7 1500 Reactor thermal power at 96%, core flow linited.
9/11 1620 Reduced thermal power fron 96% to 92% due to one-half isolation en "B" main sterm line while performing SI.
1640 One-half isolation on "B" main steam line cleared and reset, commenced power ascension.
2300 Reactor thermal power at 96% core flow limited.
2320 Reduced thermal power from 96% to 70% for turbine C.V. tests and SI's.
9/12 0144 Turbine C.V. tests and SI's completed conmenced power ascension.
0255 Reactor thermal power at 96% core flow limited.
9/16 2325 Reduced thermal power from 96% to 70% for turbine C.V. tests and SI's.
9/17 0045 Turbine C.V. tests and SI's completed connenced power ascension from 70% thermal power.
0330 Commenced PCIOMR from 90% thermal power.
2300
, Reactor thermal power at 95%, core flow limited.
1 Significant Operational Events Date Time Event Unit 2 (continued) i 9/22 2235 Reduced thermal power from 95% to 90% for turbine C.V. tests and SI's.
1 9/23 0100 Turbine C.V. tests and SI's completed, commenced I
PCIOMR from 90% thermal power.
P 1800 Reactor thermal power at 97% core flow limited.
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f 9/24 1350 Reduced thermal power from 97% to 90% for removal of "B" string high pressure feedwater heaters from service for leak checks.
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9/25 2/20 thak checks completed on "B" string high pressure heaters.
CommencedPCIOMRfrom90kthermalpower.
2130 j
9/26 1645 Reactor thermal power at 97% core flow limited.
- ft 9/29 2100 Commenced reducing thermal power from 97% for-scheduled outage.
l 2315 Reactor scram no. 71 (manual) from 40% thermal I
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pcwer for scheduled outage.
I 9/30 2400 Reactor shutdown in hot standby mode.
l Unit 3 9/1 0000 Reactor thermal power at 67%,' administrative hold due to vacuum switch grounding problems of T/G.
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i 9/7 0545 Commenced power ascension from 67% thermal power.
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1500 Reactor thermal power at 77%.
9/8 2200 Commenced reducing thermal power for shutdown for refueling outage.
2300 Reactor scram no. 65 (manual) from 40% thermal power f
to acccmmodate refueling outage.
l 9/14 1945 Cormenced removing fuel assemblies frcm reactor vessel l
to fuel pool storage.
9/25 1400 Completed removing fuel from reactor vessel to fuel pool storage 9/30 2400 Refueling outage in progress with all fuel assenblies l
in the fuel pool storage.
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(1) Equipment malfunction.
(2) Operator error.
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, e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-259 Browns Ferry I.
WIT
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DATE U " Of**"
CO\\1PLETED BY 205/729-6846 TELEPHONE MONTil Santa"har 1079 DAY AVERAGE DAIL'Y POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe Net) 894
-8 g
37 80l
-11 2
18
-11 821 39 3
-10
-13 20
.- 4
-11 324 5
21 465 237 22 6
468 653 23 7
772 477 8
24
.477 744 25 9
473 43 26 i
go 464 486 d
. 11 27 12
- g 487 q
763 13 29 503
-.859 6
549 14 30
-7 31 15 16
-7 INS 1 RUCTIONS On this format. list the aserage daily unit power leselin MWe Net for each day in the reporting month. Compute tu
- 'the nearest whole^nsg2 watt.
(9177)
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_11 AVERAGE DAILY UNil POWER LEVIL 50-260 DOCKET NO.
Browns Ferry II glT 10-5-78 DATE Don Green C0\\lPLETED fly 205/729-6846 TELEPilONE MONTil Septembr-1079 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 1030 1031 g7 081 1032 2
18 1020 829 19 3
1019
- - 4 991 20 1013 1003 5
21 1037 1020 6
22 1008 1041 23 7
1002 1012 g
24 1031 961
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9 25 1030 10!.3 26 10 1010 1058 11 27 1005 1055 g;
28 991 1011 29 13 1016
-10 34 30 1028 15 3g 1010 16 INSTRUCTIONS On thn fornut.!nt the sserage daily unit p.mer fesel in MWe '4et for caeh day si the reporting anonth.Cmnpute to
' the nearest win.le'nsg2 42tt, (ii/77I
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O
o AVER AGE DAILY UNIT POWER LEVEL DOCKET NO.
54206 Browns l'erry III g,lT DATE 10/5/7R UO" I'YOU" CO\\lPLETED BY
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TELEPllONE MONT11 S ep t er.b e r, 1978 DAY AVER AGE DAILY P0h ER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Nett (MWe Net) g 37 673 2
33 8
684
-8 678 39 3
685 20
~0
~
4
~9 685 21 5
659
~7 6
22 742
-8 7
23
~8 772 24 8
9 25
-6
-11
~11
-3 10 26
~3
~
,27,
..... I1.
-10
-3 33
,3
~9
-5 13 29
~9
-5 14 30
~9
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15 31
~9 16 INSTRL'CTIONS On this forrnst. hst the.nerage daily unit piiwer leul in \\lWe Net for each day in the reporting in.inth. Compute to the nearest whole nwg: wart.
(9/77)
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OPERATING DATA REPORT DOCKET NO.
50-259 DATE 10/5/78 COh!PLETED ItY Don Green
- TELEPilONE
')ns / 7')o-6 846 OPER ATING ST ATUS B wns Ferry I Notes
- 1. Unit Name:
September 1978
- 2. Reporting Period:
- 3. Licensed Thermal Power 13tht):
3293 1152
- 4. Nameplate Rating (Gross 3theI:
1065
- 5. Design Electrical Rating (Net.\\tWe):
- 6. h!asimum Dependable Capacity (Gross 31We): 1908 1065
- 7. h!asimum Dependsb!c Capacity (Net alwe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:
9..P'ower Lesel To which Re tricted.!f Any (Net 51We):
N/A 10.' Reasons For Restrictions. !f Any:
This h!onth Yr..to Date Cumularise.
720 6551 36529
- I-
- 11. Ilours In Reporting Period
- 12. Number Of flours Resetor Was Critical 492.42 SAR5.83 18865.71
- 13. Reactor Resene Shutdown flours 225.76 352.33 4,399.13
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- 14. Ilours Generator On-Line 466.35 5649.33 18325.46
- 15. UrJt Resene Shutdown ll:)urs 0
0 0
- 16. Gross Thermal Ener;y Generated (31WH) 944,359 15,778,415 48.151,644 291,740 5,171,o79 13,9 69, wj a
- 17. Gross Electrical Energy Generated (%1WH)
- 18. Net Electrical Energy Generated (51Wil) 280,607 5,012,892 15,501,239
- 19. Unit Senice Factor 64.8 86.7 50.2
- 20. Unit Asailability Factor 64.8 86.7 50.2
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36.6 71.9 39.8
- 21. Unit Capacity Factor (Using %1DC Nett 36.6 71.9 39.8
- 22. Unit Capacity Factor IUsing DER Net)
- 23. Unit forced Outage Rate 35.2 7.4 41.9
- 24. Shutduwns Scheduled Oser Nest 6 Slonths (Type. Date and burstion of Each):
Refuel outar.e Novenber, 1978.
25.,if Shut Down At End Of Report Perind. Estimated Date of Startup:
- 26. Units la Test Status (Prior io Commercial Operation):
- Forecast Achiesed I
INITI.\\ L CRiflCALITY
,JNITl4L ELECTRICITY C041\\lERCI \\L Ol'ER \\ TION
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m e -.e e e.w (4/77)
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OPERATING DATA REPORT DOCKET NO.
50-260-DATE 10/5/78
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COSIPLETED ltY Don g een
- " "# v-6846 TELEPIsONE OPERAT!NG STATUS I. Unit Name:
Browns Ferry II N*8'S
- 2. Reporting Period:
September 1978
- 3. Licensed Thennal Power (Stht):
3293
- 4. Nameplate Rating (Gross S!We):
1152
- 5. Design Electrical Rating INet S!We): - - - 1065
- 6. Stasimum Dependable Capacity (Gross $1We):
1098 5
- 7. Staximum Dependable Capacity INet S!We):
1065
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7)Since Last Report.Give Reasons:
9.. Power Level To which Restricted. If Anv (Net SIWE):
- 10. Reasons For Restrictions. If Any:
!GA This Stonth Yr to.Date Cumulative
- 11. Ifours in Reporting Period 720 6551
--31,440- -
- I-. -
- 12. Number Of flours Reactor Was Critical 695.25 4,004.78 14,573.01
- 13. Reactor Resene Shutdown flours 24.75 213.22 11,412.99
- 14. Ilours Generatur On Line 695.25 3900.55 13,933.91
- 15. Unit Resene Shutdown 1:ours 0
0 0
- 16. Gross Thermal Energy Generated (SIWil) 2.143.937 10,737,187 36,910,324
- 17. Gross Electrical Energy GenerateJ (AlWil) 715.42,0,_ _,
3,500,060 12,097,010_
- 18. Net Electrical Enirgy Generated (SIWil) 696,458 3,388.119 11,730,923
- 19. Unit Senice Factor 96.6 59.5 44.3
- 20. Unit Availability Factor 96.6 59.5 44.J 90.8 48.6-35.0
- 21. Unit Capacity Factor IUsing SIDC Net)
- 22. Unit Capacity Factor IU>ing DER Net) 90.8 48.6 35.0
+
- 23. Unit Forced Outage Rate 3*4
'*9 4v'L
- 24. Shutdowns Scheduled Oser Nest 6 stonths (Type.Date.and buration of Eacht 25.. If Shut Down At End Of Report Period. E timated Date of Start p:
26.. Unitiin Test Status (Prior to Commercial Operationn Forecast Achiesed INITIA L CRITICA LITY
,-)NITI-\\L ELECTRICITY COililERCI A L Ol'ER ATION (9/77) 6
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i OPERATISG DATA REPORT
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50-296 DOCKET NO.
DATE 10/3/7M COh!PLETED BY _ Don Green-*
l TELEPHONE 205/72o-6846 OPERATING STATUS Notes
- 1. Unit Name:
Bro ms Ferrv III
- 2. Reporting Period:
Sentember 1978 3293
- 3. Licensed Thermal Power (5tht):
1152
- 4. Nameplate Rating (Gross StWe):
1065
- 5. Design Electrical Rating (Net 5!We):
1098 5
- 6. Stasimum Deper:dable Capacity (Gross 51we):
W5
- 7. Staximum Dependable Capacity (Net SIWE);
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
- 9. Power Lese! To Which Reitricted.If Any(Net SIWE):
- 10. Reasons For Restrictions,if Any:
N/A This 5f onth Yr to.Date Cumulative 720 6551 13,895 f
II. Ilours In Reporting Period 191.0 5,503.25 12,198.92
- 12. Number Oflioun Reactor Was Critical l
- 13. Reactor Resene Shutdowa flours 40.11 494.nR 1087.40
- 14. Ilours Generator On Line 101.0 5415.34 11914.65
...15. Unit Resene Shutdown llaurs. - -
0 0-0-
i
- 16. Gross Thermal Energy Generated (StWil) 422,988 15,421,038 34,062,732
[
- 17. Gross Electrical Energy Generated (5!Wil) 137,690 5,044,430 11,078,300 IS. Net Electrical Energy Generated (51Wii) 129,637 4,886,896 10,737,802 i
- 19. Unit Senice Factor 26.5 82.7 85.7
- 20. Unit Availability Factor 26.5 82.7 85.7 16.9 70.0 72.6 21.. Unit Capacity Factor (Using StDC Net!
16.9 70.0 72.6
- 22. Unit Capacity Factor (Using DER Net)
- 23. Unit Forced Outa;re Rate 0
9.5 9.7
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- 24. ShutJuwns Scheduled Oser Nest 6 51onths(Type.Date,siid buration of Eacht.
November 1978
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior io Commercial Operationi:
Forecast Achiesed INITI-\\ L CRITICA LITY
,JNITI-\\ L ELECTRICITY Coil 5tERCl \\L OPER ATION i
.=__ -._
1 5r1-25a DOCKET NO.
UNIT SIIUTDOWNS AND POWER REDUCTIONS UNIT NASTE Reo""9 b rrv I DATE I"/5/78 e
REPORT A10NTil Sentember 197g
. COSIPLETE! Y on e
f t
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Y Licensee -
E r, cause A corrective o
N Dat'e g
3g 4
,5 s E Esent g?
El Action to j'
y:
E jgg Report 2r mV Prevent Ree'trrence 6-d 50 780903 F
57.2 A
2
}faintenance Outage to repair FCV-69-1 and identify leakage of FCV-6R-77.
51 780909 F
23.12 A
2 Maintenance Outage to identify Jenkage into drywell (FCV-68-77).
52 780911 F
4.98 A
3 Rx scram due to hi hi APPJi flux.
g e
53 780914 F
159.02 A
2 Rccire. flow problems due to trouble with FCV-68-3.
55 780920 F
9.33 C
3 Rx scram on turbine stop valve closure signal (pressure setpoint inadvertently reached during turbine cl.est trarming).
1 I
2 3
4 F: Forced Reason:
i Method:
Exhibit G. instructions S: Schedufed A Equipment Failure (Expbin) 14!anual for Preparation of Data Bataintenance of Test 24hnual Scram.
Entry Sheets for Licensee C-Refueling 3 Automatic Scram.
Event Report (LERI File (NUREG.
L Operator fraining & License Examination 4-Other (Emplain) 0161)
D RcEulatory Restriction F-Administrative 5
G Operational E ror(Eqtain)
Exhibit I. Sam Source.
(9/77)
II Ot her (Explain}
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- 5
. I-5 0-h'.n DOCKET NO.
UNIT S!!UTDOWNS AND POWER REDUCT10NS UNIT NAME ltrouns verry II DATE 10-b78 1
COMPLETED IW n,,
f REPORT MONTil 9eatenhor 1978 I
L E
E jg 3
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Licensee -
$v, h
Cause & Corrective
- q...
Date c;
3g i
.E s 5 Event g7 g3 Action to l
f5 5
3 ;g =
Report e in U O
Prevent Recurrence H
o 5
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0 61 780902 S
i Derated for control rod sequence exchange from A to II.
t 62 780911 S
Derated for turbine control valve test and SI's.
b 63 780916 S
Derated for turbine control valve y
test and SI's.
i 64 780929 F
24.75 A
2 Investigation of unidentified leak-age into drywell and repair to dryvel L
eqinipment drain sump pump.
t P
I 2
3 4
F: Forced Reason:
t Method:
Exhibit G-Instructions S: Scheduled A.Eituipment Failure (Explain)
I-Manual for Picparation of Data 2-Manual Scram.
Entry Shecis for Licensee It-Maintenance of Test 3
3 Automatic Scram.
Event Report (LER) File (NUREG-C-Itefueling D llegulato y Restriction 4 Other (Explain) 0161) 1:-Operator Training & License Examination F-Asiministrative 5
G-Operational 1:s rur (Explain)
Exhibit I Same Source.
(9p7) 11 Other (Explain) j l
t i
1 m
t DOCKET NO.
50- N.
UNITSilUTDOWNS AND POWER REDUCTIONS UNIT NAME Brotms Ferry III DATE 10/5/78 c onn
. COMPLETED ItY Don r
REPORT MONTil Sentember 1978 TELLPilONE 70%-7')o / CR 46 c
3?
3 4 E~
Licensee.
E-r,,
{*3 Cause A Corrective Attion to No.
Date i
3y s
j~$
Event gy g'
Prevent Recurrente
$5 5
~ f3 g Repori
- mU H
o v
Q e
4 64 780908 S
529 C
2 4
IH cn t
I 2
3 4
Method:
Exhibit G. Instructions F: Forced Reason:
S: Schedufed A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.
Entry Shecis for Licensee C-Refueling 3-Automatic Scram.
Event Report (LER) File (NUREG.
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D Regulatory Restriction 4-Other (Explain) 0161)
E-Operator Training & License Examination F Admimstrative -
5 G Operational Leror (Explain)
Exhibit I Same Source (9/77) 110:her (Explain) 6
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bro" tis FERRY NUCLEAR PLANT UIIIT Cotot0M etECllANICAL MAINTEIL\\NCE SUM:!ARY CSSC EQUIPME!!T SEPTEMBER 19 78 For the Month of ACTIO:3 TAKEN EFFECT ON SAFE DATE SYSTEM COMPONENT NATURE OF OPERATIOII 0F CAUSE OF RESULTS OF
- IU PRECLUDE MAINTEllANCE Tile REACTOR MALFIR;CTION
!!ALFUtiCTION RECilRREf!CE 78 Fuel pool Air motors unit Air motor slot None Unknown None Cleaned air motor cooling &
one operating deminiliz-ing system 78 Fuel pool "C"
fuel pool lilow head None Unknown None li. P. survey, replaced lead gasket, manway cooling &
inspect, hole gaskets ing system leaks on pipe and pipe flange gasket, flange under-Inspect with 40 PSI.
neath vessel No leaks at 40 PSI. 78 RilR service Air relief Float and seat None Unknown None Installed new air water sys.
valve on Cl was bad relief valve P.ilRSW pump 78 RilR servici D-3 R!lRSW Packing leak None Unknown None Repaired and adjust packing water sys.
Jump
-2 78 RilR servici A-1 HilRSW Packing 1eak None Unknown None Replaced packing
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water sys.
pump s 70 Diesel "B" air c'om-
!! cad gasket None Operation None Replaced head gasket
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gen sys-pressbr on 3A blown
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diesel I
t BP'" tis l EltitY 1:UCIJA1: PtAllT UNIT I
r!ECHANICAL R\\l!!TEtal!CI: SUt 2!ARY CSSC EQUIPrfENT For the Month of SEPTEMBER 19 78 9
ACTION TAKEN EFFECT ON SAFE DATE SYSTEli COMPONEIIT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE MAINTENANCE Ti!E REACTOR MALFUNCTION M?sLFUNCTION RECURRENCE 5-78 Station Drywell floor Pump bearings None Operation None Replaced pump bearings Drainage drain sump bad pump "!!" 78 liigh pres-FCV l-26-79N Deluge valve None Unknown Would not reset valve Reset deluge valve sure fire open protection system t
- 5-78 Reactor FC0 64-9 Diaphragm None Unknown None Installed rebuilt air cylinder bldg vent leaking system Unknown None Replaced 0-rings 78 Elevators Drywell doors Doors will not None system pass air test sys no 203
- 78 Elevator Equipment Patch leaking None Unkhown Hone Installed new patch on 2 door air seal system access door 2 equipment tunnel Rx sys no 203 building
. 78 Control rod Scram discitarge Valves were None Unknown None Adjusted stroke on valve Icaking througi system
. 78 Standby SLC 1A pump Intake & dis-None Unknown None
!!achined and lapped valves liquid charge valve control syt.
leaking
1 BP ";S FERRY NUCLEAR PLANT UNIT IECliANICAL MAINTE!;\\MCE SU!StARY o
CSSC EQUIP"FUT For the Month of SEPTEMBER 1978 ACIlG:( TAKEN EFFECT ON SAFE n*sIE SYSTD!
COMPONENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE R\\INTENANCE
'nlE REACTOR KiLFINCTION MALFUNCTION RECURRENCE 78 Control CRD Accum.
Accumulator None Unknown Ncne Replaced accu =ulator rod drive 42-43 leaking system
-1!.-78 Standby valve 63-518 Packing gland None Operation None Tightened packing gland liquid loose control system 78 Reactor Equalizing Packing leak Nene Unkncun Nene Replaced valves water valves recirc.
FCV-68-33 system FCV-68-35 9-78 Reactor FCV-68-77 Bad packing None Unknown None Repacked valves water FCV-68-79 leak recirc.
systen 8 78 RWR 68-3 & 68-1 Loose packing None Unkneun None Tightened packing installed lamp on system 68-33 68-1 6 68-33
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-25 78 Control Valve Packing leak None Unknown None Tightened packing nuts rad drive
- 2-85-539B systen
___ 7E Control FCV-85-8 Packing gland None Packing too Bent packing gland Straightened packing rod drive too tight &
tight gland system pulled crooked e
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VI!S FERRY NUCLEAR PLANT UNIT __
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MECIIANICAL fiAINTErnNCE SUMMRY CSSC EQUIPMENT For the Month of SEPTEMBFp 1978 ACTION TAKEN EFFECT ON SAFE DATE SYSTDI CO !PO:;ENT NATURE OF OPERATION OF CAUSE OF RESULTS OF TD PRECLUDS
!!AINTENAf;CE 111E REACTOR MALFUNCTION MAIJUNCTION RECURRENCE l-1-78 Fuelipool 2A fuel pool Packing leak None Operation None Adjusted packing cooling cooling pump system 8-7-78 Control CRD pump motor 1/4 nipple None Unknown None Replaced 1/4 nipple with new one rod drive "A"
broke off system 7-13-78 IIPCI systet llPCI steam Collar out of None Operation None Collar adjusted exhaust adjustment 4
7-15-78 IIPCI systet valve 73-16 Packing leak None Unknown None Tightened packing 1-15-78 PJIR service RilRSW outlet Packing blown Ncne Operation None Repacked valve
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7 water valve 46B out system 3-21-78 Fire 2-26-1119 Packing leak None Unknown None Tightened packir.r; protection F.P. header system 9-21-78 Control A-CRD pump Dirty filters None Operation None Changed filters rod drive system.
6 B'
'US FERRY NUCLEAR PIANT '2ilT_
IJ.CIIANICAL MAINTE!nNCE SUIEiARY CSSC EQUIPMENT For the Month of SEPTEftBER 1978 I
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ACTION TAKEN EFFECT ON SAFE MTE SYSTDI COMPONENT, NATURE OF OPERATION OF CAUSE OF RESULTS OF TO PRECLUDE
!!AINTENANCE Tile REACTOR MALFUNCTION NALFUNCTION RECURRENCE 9-26-71, Air Con. in Line stopped None Unknown Water dripping on Used nitrogen to shutdown board unstop drain.
"C" shutdown up room
!-30-78 Station 2A drywell Pump no good None Operation Pump would not pump Rebuilt pump completely Drainage equip. drain sump pump
'-31-78 Station Drywell FDSP Coupling None Operation None Installed new spider
& adjusted impeller Drainage spider worn out on "A" pump 78 Station -
Drywell equip.
Coupling None Operation None Installed new spider, Drainage drain sump spide'r vorn impeller, brushing, coupling, & bearing.
pump out m-L w'
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";S TERRY NUCLEAR FIANT UNIT _ 1 MECIIANICAL MAINIE!"NCE SU?S!ARY CSSC EOUIPMENT
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For the Month of SEPTEMBER 19 78 d'
EFFECT 0:: SAFE ACTIOli TAKEN
,,,.4a DATE SYSTE21 COMPONENT NATURE OF orERATION OF CAUSE OF RESULTS OF ID PRECLUDE MAI!iTENANCE
'lllE REACTO'l R\\LFUNCTION MALFUNCTION RECURRENCE
'-8-78 Vent. syst.
Control bay Dirty filters None Operation None thanged filters Opdf) tion None Changed filters
'-15-78 Control 3A CRD suction Suction filter s None rod drive filter need changing system 78 Rx water FT 68-10 Line stopped None Operation None Unstopped line recirc.
up system i
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i onGL'US FERRY UUCLEAR PLANT UNIT 1
CSSC EOt!IPMENT ELECTRICAL MAINTENANCE
SUMMARY
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For the Month of So rit er fie r 19 78 -
"'Effect on Sate Action Taken Dr.tc Systes Ccepone'nt Uature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 9/4 Fire Fire Protec-Smoke Alarm in None Smoke detector Failure of smoke Replaced smoke detecto Protection tion Panel on Panel 1 full of water detector Performed SI 4.11.C.1 1-25-287 287 due to inadver-and
.5.
TR 102148 tent initiation of system while troubleshooting a,nother problem i
I 9/4 Fire Fire Protectin Trouble alarm None Bad control modula Trouble circuit Replaced control modult Protection Panel 25-311 in and will not defective Perforced SI 4.11.C.3 clear and.4 on Panel.
TR 114447 9/5 Diesel D/C D Lube oil heater None Loose wire tube oil heater not Replaced overload da Gene rato r overload assem-working assemblyandwiresY'!
bly and wires heater operated cor-burned rectly. TR 114443
-9/7'
!!onitoring to operate tact properly fied proper operations Radiation ~ :X5 902135A Switch failed None Bad switch con-Switch didn't operateReplaced switch.. Veri" properly TR 63696 9/10 4-kV Shut-ACD 1716 Breaker will None Mechanical link-Breaker would not Adjusted mechanical down boanh not trip age to trip coil trip linkage and repaired out of adjustment test pushbutton.
Test pushbutton Tested o.k. TR 114408 Joesn't operate 9/14 SLC SLC pump motor 'otor h2aters None Bad motor heaters lleaters did not heat Replaced heaters lA do not operate motor Checked out o.h.
TR 84143 and 84173 9/15 Control BayControl Bay Not cooling None Bad tubes in Cooling water to Peplaced tubes. Cool-Ventilatin Chiller A chilled water controller only 51 or 52 F.
Ing water properly.
TR 105251 e
0
Et:0'.? tis FERRY 1:UCLEAR PLANT UNIT CSSC EQUIIMENT ELECTRICAL tultiTEIUdCE SUICIARY PAGE 2 of 2 For the ifonth of s o n e n-k n,.
19 g Effect on Safe Action Taken Dcte System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence 9/19 Recire FCV 68-35 No indicating Mone Coll burned up No indicating lielts Replaced coil, tested lights in relay o.k.
TR 105221 9/19 Raw Ser-PA 25-31 Alart. wouldn't
!!one Level switch out Alarm wouldn't cicar Adjusted Icvel switch.'
vice water cleat of adjustrnent Tank periodically Verified proper oper '
running over and 2A ation.
TR 105225 RSW pump not shuttin ;
off
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r,RO'.'NS FERRY NUCLEAR PLANT U';IT _2 CSSC EQUIPMENT ELECIRICAL MAINTENANCE SUM!ARY For the I!onth of sener-ser 192 8
Effect on Saic Acticn.Taken Nature of Operation of Cause of Results of To Preclude Dcte Sya w Cc=ponent Maintenance The Reactor Malfunction Malfunction Recurrence i
t 9/7 I
SLC 2B motor Motor heaters None Motor heaters Motor heaters not Replaced r.otor heat-heaters not heating defective heating ers 88357, 98143, 74718, 83667, 92769, 92834, 101839, N 101587 and 115080
? 9/12 Control Flos switch
' Alarm will not
!;one Blow switch Alarm would not cleared and adjusted Bay 31-174A clear stuck clear flow switch.
Alarm l
Ventila-cleared. TR 101721 tion u
9/19 Fire Pro-XS 39-67XA Bad detector None Bad detector Defective detector Replaced detector.
tection Performed SI 4.ll.C.1 and
.5.
TR 87785 9/26 Radiation RM.90-55 Pump motor None Bad bearings of Blown fuse Replaced motor and Menitoring blowing fuses pump motor verified proper opera-tion.
TR 110204 i 9/30 RilR llCV 74-55 Position light None Limit out of No position indica-Adjusted limit switch.
l doesn't burn adjustment ting light Indicating light working PROPERLY l
, Limit switch out Received half scram Adjusted Jimit switch.
9/30 Main FCV l-14 Limit switch None l
Steam dropping out of adjustment with valve greater Verified proper opera =
SAK-3A than 90% open tion. TR 109119, 102109 i 9/30 RPS RPS MG Set 2A Failure to tril None Bad overvoltage MG Set won't trip Replace overvoltage MG set when relay card on overvoltage relay card.
Completed testing overvo-EMI 13.
TR 66600 Itage relay 9/30 RPS RPS MG Set 2B Failure to trip None Bad overvoltage MC Set won't trip Repaired overvoltage l
MG Set when test-relay card on overvoltage relay card. Complete ing overvoltage EM,1 13.
TR 106661 relay
! 9/30 Main MSRV l-23 Sellows leakagc
.'cne Connector to Internittent alarn.
Peplaced connector.
-i Steam alarm comes in pressure switch Ground on battery Checked out o.k.
eb intermittently bad board ground cleared.
Y I
TR 106656, 109101 and l '115412 l
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uttOWS FERRY NUCLCidt PLANT UNIT
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CSSC E()UIINENT ELECTRICAL MAINTENANCE SUIDIARY For the Month of e g n e,s g r 192 8
Effect on Safe Action.Taken Date System Component Nature of Operation of Cause of Results of To Preclude Maintenance The Reactor Malfunction Malfunction Recurrence s
8/19, Fire Smoke detector Sroke d% ctor None Age and dust Alarm would not Cleaned detector and 9/2; Protection 39-19B brit ging in accumulation on cicar eventually replaced.
9/4, alarm detector Performed SI 4.11.C.1 9/5 and
.5.
TR 114893, 114804, 114631,
- 114698, BFPO-50-296/7823 9/8 NPCI FCV 73-23 No indication None Limit switch No open indication Tightened and adjusted in control loose and out of in control room limit switch.
room adjustment Checked o.k.
TR 114237 9/11 Fire XS-39-26G Spurious Alarm None Age and dust Alarm would not Changed out detector Protection Smoke detector accumulation on clear and performed detector SI 4.ll.C.1 and.5 TR 114243 667475 9/24 Fire Pro-XS-39-93KB Detector alarmo None Age and dust Intermittent Changed out detector tection without reason accumulation on
. alarm Performed S1 4.11.C.1 0
8 on detector and
.5.
TR 91438 BFRO-50-296/7326 f9/29 Core Spray IICV 75-1 Limit switch None Limit switch Improper position Cleaned limit switch.
l for valve posi-sticking indication Verified, proper opera-l tion indicat--
tion. TR 91498 ing lights not working h
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BROU:1S FERRY UUCLEAR PLANT UNIT 162 s
INSTRintENT !!AINTENANCE SUltliARY
/
I FOR Tile 110NTl! 07 SEPT.
. 1978 I
CSSC EQUIP!!ENT Action Taken Effect on Safe Results 'ofi to preclu.fe Nature of Operation of Cauce of Malfunction"'"
!!alfunction.
recurrence
,Date System Co:1ponent.
11aintenance the reactor.
i i
I
!ait 1
-1 Recirc.flou SC-90-3A Repair None Fanity manual control Erratic ControY
~i T'eriodic potentiometer i
i replacement cont.rol
- 6 Recirc FM-68-49B Repair None CMicitor'shortedto Total, core flow 1 css None terminal strip than adtual
'-15
- tecire flou SC-96-3B Repair rione Faulty manual control Erratic Cont ro'l' Periodic control PIC-96-1 potentiometer replacement
"-15 7eeduater SC-46-8A,9A,10A Repair 3
- ontrol y
l Init 2 l-11 H.li. S IRif Bi Repair lone D Ety contacts Errati : Indication
' lone 2
1 1-15 Feedwater SC-46-8A,9A,10A Periodic fo'ne F$tilty manual control Errati : control
'eriodic Control Replacement por.'entiomet er teplacement Recirc SC-96-3A,3B Flow PIC-96-1
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Control 1-22 RUCU TS-69-30E Replacement None \\
Pdu'lty switch liinh alarm would not None
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clear
[f l
1-30 RPIS Probe 10-23 None
' L1d probe buffer card -
Super imposed 02 I"
units.
None Radwaste FS-77-14 None lefective Level' switch 0.U. equipment drain
,None I
(
sump pump would not start n_
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1 3
BRob".:S FERRY !!UCLEAR PLANT U !IT 113STRU'.!P.11T 11A11;TEliAt;CE SUIf!!ARY i
l FOR Tile !!O!;Til 0F Sept.
,1978 '
- SC EQUII'!!E
- 1T Action'Taken 1
Effect an Safe-Results of to preclude Cause of i
recurrence Itature of Operation of ifalfunc' tion? '"
Malfunction' the reactor.'
s t r.
Systen Component.
Maintenance nit 1 i
Indicadlon did not None 9-1 P rimary LI-64-54B Calibration None
- 7. erd Shift e.,
agree i
I containmen Ba'd ' Detect or :
High rrdiation-None s
9-1 Rad.
R!f-90-133B Fepair' IIone Indicat ion monitor 9 19 ECIC PDIS-71-1B Calibration None Tnstrument Drift Indicat ed flod Uith tione unit si utdown e
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Outage Summary I
(BFNP - Unit 3)
September 1978 l
l I
The drywell and reactor pressure vessel have been disassembled in l
4 order to allow unloading of fuel for remaining RPV vibration instrumentation i
and conducting a major inspection and repair of the CRD nozzle. The CRD return i
to the vessel will be capped and rerouted to the reactor water cleanup system return.
l The fuel was unloaded in eight days instead of the scheduled nine days. Neutron sources and holders have been removed, and 43 local power range monitors are being replaced with longer-life models. Other major work included leak check and i
eddy current testirg of the feedwater heaters and condenser water boxes. The major containment isolation valve testing has shown an initial tes' ting failure rate of r
approximately 50 percent, including six of eight nain steam isolation valves j
requiring repair. Major motor testing was completed with one drywell blower notor failing the inspection. Cleanup and inspection of electrical boards is approximately 50 percent complete, and the contact retainer arms are being chcnged out on CSSC L
system breakers. The inspection and testing of mechanical and hydraulic snubbers P
is complete. To date, four control rod drives have been changed out _and will t
i continue for two additional drives after LPRM work is complete. Prefabrication i
and piping work on the CRD reroute and scram discharge header are underway.
There are several major modifications requiring electricians, including the off-line radiation monitoring, diesel driven fire pump, recirculation pump trip l
modification and standby gas treatment modifications.
The main steam relief valves have been sent to the service shop for bore modification, while the valve base assemblies were rabuilt onsite. The major turbine inspection of the -low pressure "A" turbine, all reactor feed pump turbines L
and intercept and control valves were completed.
l i
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