ML20108A011
| ML20108A011 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/30/1984 |
| From: | Dupree D, Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8411140440 | |
| Download: ML20108A011 (40) | |
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY-OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION SEPTEMBER 1, 1984 - SEPTEMBER 30, 1984 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l
l Submitted By: -
l Plant Manager i
8411140440 840930 t
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TABLE OF CONTENTS Operations Sunnary . . . . . ... . .. . ... . .. . .. . .1 Significant Operational Events . .. .. .. . . . . . . . . . . 1-5 (
PORV's ard Safety Valves Summary . . ... . . . . . . . . . . .5-
. Reports
[ . Licensee Events . . . . . .. . . .. . . . . .. . . . . . 6-9 Diesel Generator Failure Reports . . . .. . . . . . . . . 9 Special Reports . . . . . ... ...... . .. . . . . . 10 Offsite Dcse Calculation Manual Changes . .. . . . . . . . . . 10 Operating Data I Unit 1 . . . . . . . . . . .... . ... . . . . . . . . 11-13 Unit 2 . . . . . . . . . .. . . . . .. . . .. . . . . . 14-17 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . 18-37 l
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4 Operations Summary
-September, 1984 The following summary describes. the significant operational l'
- activities for the month of September. In support of this summary, a
- chronological log of significant events is' included in this' report.
Unit 1 Unit'l was critical for 602.5-hours, produced 573,870 MWH (gross),
resulting in an average hourly gross load of 2,017,951 kW during the month.
There are 262.2 full power days estimated remaining until the end of cycle 3 fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached August 6, 1985. The capacity factor for the month was 67.4 percent.
There were no reactor scrams, and one manual shutdown, and one power reduction during the month.
Unit 2 Unit'2 was critical for 575.05 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />, produced 482,390 MWH (gross),
' resulting in an average hourly gross load of 906,493 kW during the month. The cycle 2 refueling outage began September 28, 1984. The capacity factor for the month was 56.6 percent.
There were six reactor scrams, one manual shutdown, and no power reductions during the month. ,
i Significant Operational Events 4
Unit 1 Date Time Event 08/01/84 0001 The reactor was in mode 1 at 99%
j power producing 1088 MWe.- The investigation continued to determine the lost generation.
0645 The cold leg accumulators were
! declared out of specification.
l Began. reducing power for a manual i shutdown.
i 0703 The cold leg accumulators were declared in specification. Began power ascension.
0920 The reactor obtained 100% power.
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Significant Operational Events
' Unit I o
(Continued)
~Date Time Event 4
09/19/84 1840 Power was interrupted to the UHI
~
valves when the power cables were cut by a core drilling crew. Began reducing power for a manual shutdown.
1922 The reactor was at 71% power and power was restored to the UHI valves.
Began power ascension.
2142 .The reactor obtained 100% power.
09-21-84 '2000 Began reducing power to remove the unit-from service to rapair the leaking feedwater drain line isolation valves.
2339 The reactor entered mode 2.
2343 The turbine was tripped.
4 09/22/84 0800 The reactor entered mode 3 and was still critical.
4 1030 The shutdown banks were inserted.
1520 The reactor entered mode 4.
1900 The reactor entered mode 5.
09/26/84 0412 The reactor entered mode 4.
1930 The reactor entered mode 3.
09/27/84 1447 The reactor was taken critical, entered mode 2.
I 09/28/84 1018 The reactor entered mode 1.
1158 The turbine was tied on-line.
1315 The reactor was in mode 1 at 30%
power producing 282 MWe. Held due to steam generator chemistry.
09/30/84 2040 Began power ascension.
l l 2359 The reactor was in mode 1 at 69%
l- , power and increasing. The unit load was 795 MWe.
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.Significent Optratientl Evrnte.
Unit 2
- te Date Time Event 09/01/84 0001l The reactor was in mode.l at 30%
power producing 288'MWe and was holding.due to steam' generator chemistry.
1007 Began power ascension.
2010 Held 75% reactor power awaiting repairs on'CBP 2A.
2050 2A CBP repairs were completed.
' Resumed power ascension.
09/02/84 0209- The reactor obtained 100% power.
09/04/84 '0532 -The turbine tripped due to low EHC pressure. -A reactor trip followed.
09/05/84 2210 The reactor was taken critical.
2245 The reactor was at 4% power and j holding due to chemistry.
09/06/84 0822 Began power ascension.
1000 The reactor was in mode 1 at 24%
power. The turbine tripped'followed
- by a reactor trip due to a Lo-Lo
. level in #4 steam generator. ,
09/06/84 1215 The reactor was taken critical.
l 1333 The reactor entered mode 1, the turbine was not on-line.
1416 The reactor was at 12% power when i the turbine tripped due to
- fluctuation in the EHC system.
1535 A Hi-Hi steam generator level tripped the turbine, the reactor l was at 16% power and the unit was not on-line.
- 1609 The unit was tied on-line.
i 1745 The reactor was at 30% power producing 245 MWe.
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Signifiernt Operntien71 Ev:nts Unit 2 (Continued)
Date Time Event-
.09/08/84 0001 Began power ascension.
2110' The reactor obtained 100% power, producing 1132 MWe.
09/09/84 0803 The turbine tripped followed by a reactor trip due to a neutral transformer overvoltage indication.
09/10/84 0240 The reactor was taken critical.
0412 The' reactor tripped due to a Lo-Lo steam generator level. The unit was not.on-line. !
0535 '
The reactor vas taken critical.
0625 The reactor entered mode 1.
0811 The unit was tied on-line.
0859 The turbine tripped due to a Hi-Hi steam generator level.
0901 The reactor was maintaining 30%
power when it tripped due to a Lo-Lo steam generator level.
1038 The reactor was taken critical.
1138 The reactor entered mode 1.
1217 The unit was tied on-line.
09/10/84 1253 The reactor tripped due to a Hi-Hi
- 4 steam generator level.
1255 The reactor was at 30% power when a Lo-Lo #2 steam generator level caused it to trip.
1433 Rod P-4 inshutdown bank A was declared inoperable. The unit began cool down to mode 5.
09/11/84 0157 The reactor entered mode 4.
0530 The reactor entered mode 5.
1841 Rod P-4 was declared operable.
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.Significant Operational Events Unit 2 (Continued) e Date Time Event 09/12/84- -0313 The reactor entered mode 4.
1018 The reactor entered mode 3.
2012 The reactor was taken critical.
09/13/84 1000 The reacter was in mode 2 at 4%
power and was holding due to -
chemistry and repairs to loop 2 feedwater reg valves.
1340 Began power ascension.
1448 The reactor entered mode 1.
1726 The unit was tied on-line.
2155 The reactor was at 30% power, producing 273 MWe and was holding due to steam generator chemistry.
09/17/84 0200 Began power ascension.
09/18/84 0900 The reactor obtained 100% power.
09/28/84 2000 Began a manual shutdown for cycle 2 refueling / modification outage.
2240 The reactor entered mode 2.
2245 The turbine was tripped.
2250 The reactor entered mode 3.
09/29/84 1923 The reactor entered mode 4 and was maintaining 340*F for a steam generator soak.
09/30/84 2359 The reactor was in mode 4. The refueling / modification outage i continues.
PORV'S and Safety Valves Summary No PORV'a or safety valves were challenged during the month.
Licensee Events and Special Reports The following Licensee Event Reports (LER's) were sent during September 1984, to the Nuclear Regulatory Commission.
~LER DESCRIPTION OF EVENT 1-84050 A spurious signal from_the chlorine detector caused a control room isolation (CRI) to occur at 0728C on August 7,_1984.
Both units were in mode 1 at 100% power. The monitor was found functioning properly after performing Surveillance Instruction (SI)-240, " Functional Test of Control Room Air Intake Chlorine Detection System." The cause of the spurious signal could not be found nor could the signal be reproduced.
The detector was determined to be operational and it was returned to service.
1-84051 Inspections at Sequoyah Nuclear Plant have identified the following additional items of noncompliance with Appendix R of 10 CFR 50. These inspections are part of an ongoing project to ensure compliance with Appendix R.
- 1. Interactions exist between train 'A' and 'B' at elevation 734 in the auxiliary control room. Train
'A' consists of cables for steam generator level control for motor driven auxiliary feedwater pump 1A-A (cables IV1083A, IV1061A, and IV1063A). Train 'B' consists of cables for steam generator level control for motor driven auxiliary feedwater pump IB-B (cables IV1123B and IV1103B). Also, at the location (cable tray PA-B) the above cables interact with those for auxiliary feedwater turbine driven pump (cables IM811A and ISG480).
- 2. Interactions exist between train 'A' and train 'B' at elevation 714 in the auxiliary building at column lines A-8 and Q. Train 'A' consists of cables to handswitch in the main control room (MCR) to AC breaker 1912 to 6900 shutdown boards (panel 6). Train 'B' consists of cables to handswitch in MCR of AC breakers 1728 and 1914 to 6900 shutdown boards 1B-B (panels 16 and 6). Also, interaction exists at same location with cable 1PP460B fcr handswitch in MCR to D/6 parallel operator or breaker 1726 and 1728 to 6900 shutdown board IB-B (panel 6).
- 3. Interactions exist between train 'A' and train 'B' at elevation 714 at column lines A-8 and Q. Train
'A' consists of cables IPP655A and IPP653A to motor driven auxiliary feedwater pump 1A-A. Train 'B' consists of cables IPP667B and IPP665B to motor driven auxiliary feedwater pump 1B-B. Also, interaction exists at the same location for turbine driven auxiliary feedwater pump (cables 1SG240A, IM1450, IV3241A, IV3251A, ISG480, ISG481, and ISG461).
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, Licensee Events and Special Reports I
(Continued)
LER DESCRIPTION OF EVENT 1-84051 (Continued)
The action statement for Technical Specification 3.7.12 was satisfied by utilizing firewatches in the effected areas that were established by other Appendix R commitments.
This action included the establishment of a roving fire watch in areas with fire detection and a dedicated fire watch in areas without fire detection.
1-84052 SI-144.2, " Control Room Emergency Ventilation System Test," was completed on both trains of the control room emergency ventilation system at 0100C on 08/17/84. Field calculations performed during the testing indicated both trains had passed the flow rate acceptance criteria of 4000 CFM i 10%. Subsequent engineering review of the test discovered that the field calculation of the duct area was in error. The duct area was incorrectly calculated in the field to be 3.67 ft.2 when the actual are a was 3.33 f t 2 ,
Recalculation of the flow rates using the correct duct area determined that the flow rates had actually been lower than acceptable. The recalculated flow rates were 3580 CFM for train 'A' and 3290 CFM for train 'B'. Both trains of the control room emergency ventilation system were declared inoperable at 0300C on 08/17/84 requiring entry into LCO 3.0.3.
The control damper was adjusted to obtain an acceptable flow rate for train 'A'. Then train 'B' was checked and the flow rate found acceptable without further adjustment of the common damper. Both trains were declared operable at 0430C on 08/17/84.
1-84054 An 2033 CST on 8/27/84, at 100% power, SQNP Unit I experienced a reactor trip and turbine trip initiated from the steam flow-feed flow mismatch coincident with low steam generator level. Operations personnel complied with AOI-1, " Reactor Trip", and stabilized the unit in mode 3, hot standby, immediately after the trip. Simultaneous with the trip, reactor coolant system pressure channel PI-68-66 failed low. Prior to the trip all vital plant parameters were normal with no indication of steam flow-feed flow deviations or abnormal steam generator levels. Preliminary investigation revealed that the trip was actuated when instrumentation relay rack 1-R-15 experienced a loss of power. The relay rack breaker was reset and the trip cleared.
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.- Licensee Events and Special Reports (Continued).
LER DESCRIPTION OF EVENT
'1-84055 This LER involves two separate' incidents'that occurred on 08/20/84. Two doors (A207 and A206) are located in the ,
auxiliary building and give access to the roof. The outer door is a vital area-boundary door and is secured locked'.
At approximately 0700 CST on 8/20/84, maintenance personnel notified security that work wa: required on the roof and that a security guard was posted at.the door. Neither the maintenance. personnel nor security personnel were aware that the outer door was a part.of the Auxiliary Building Secondary Containment Enclosure (ABSCE) boundary. The work being performed on the roof required 110 volt power, so an extension cord was run through the door. At 0830 CST a-Field Services supervisor (who was aware of the boundary) told the men to shut the door and notified operations in the control room. An ASE was sent to the doors ~and verified that the doors were closed. The maintenance and security personnel still did not understand these requirements for closing the doors and they were reopened. The requirements for these doors as part of the ABSCE were reemphasized to maintenance management and the doors closed at 1330 CST.
The second door-breaching can be attributed to failure of communication between first-line management and personnel performing the work.
The major contributing factor to these breaches was the failure of a plant procedure to list which doors are part of the ABSCE boundary. The' control room does not issue security door control paperwork and was unaware of these breaches. The majority of auxiliary building doors are fire barriers and require a permit from Operations. The two doors involved are not fire doors, which also contributed to these two breaches of ABSCE.
1-84056 With unit 1 in mode I at 30% power and unit 2 in mode 1 at 40"A powcr, instrument mechanicc . utu .uiking on the toatne channel to unit 1 lower compartment radiation monitor (1-RM-90-106C). The train 'A' power to panel 0-M-12 was lost due to its power breaker on 120 VAC vital board 1-II opening. The loss of train ' A' power to this panel caused an inadvertent containment ventilation isolation from monitor 1-RM-90-106 and an auxiliary building ventilation isolation from the spent fuel pool radiation monitor (0-RM-90-101) which is powered from this same source. All safety systems actuated as designed when the signal was present and no abnormal actions occurred. Immediate communications between the instrument mechanics working on the monitor and Operations personnel allowed for quick identification of the breaker trip and action was taken to restore power to the panel and to re. set the CVI and ABI features.
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- . Licensee Events and Special Reports
'(Continued)
LER DESCRIPTION OF EVENT 2-84013 Prior'to the event, on 08/11/84, with unit-2 at 100% power
- (2235 psi and 578'F) one of the pressurizer safety valves (2-SRV-68-653) experienced some slight leakage across the:
seat.' . Relief from this safety valve is designed-to flow to the PRT, which has two rupture discs, if the tank pressure exceeds 85 psig. During operation prior to the
, event,LPRT and safety valve parameters were monticred by
. operations. personnel to ensure safe operation of the plant.
- All parameters -including level, temperature, and pressure
- in the PRT were~being maintained within prescribed operation limits. On the date of the event,. 08/20/84, with the PRT parameters within limits, one of~the two PRT discs ruptured i
prematurely. The rupture resulted in a small increase in radiation levels in the lower containment causing a containment'
- ventilation isolation initiated by radiation monitor RM-90-106.
- 4 There was no purging activity at the time of the event, therefore, the only isolation valves that closed were those i
to the radiation monitor itself and no inadvertent releases were made. Operations personnel initiated shutdown of the j
unit and notified the NRC by phone of the event in accordance with SNP REP IP-2. Unit shutdown (mode 3-Hot Standby) was completed at 1556 CST on 08/20/84.
t 2-84014 During a normal startup on 08/30/84, unit 2 was in mode.1 1 (2235 psig, 558*F) at 25 percent reactor power with the
'A' main feedwater pump in operation. The balance of plant
! operator was controlling steam generator levels with the j main feedwater regulator valves in manual control. During i switchover'of the steam generator level controls from manual I to automatic, steam generator #1 was overfed. The #1 steam generator high-high level trip setpoint was exceeded resulting
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, in a turbine trip and feedwater isolation. The reactor 4 operator immediately (with increasing level in the #1. steam
- generator) reduced reactor power in attempt to prevent an j anticipated automatic reactor trip. With reactor power at
- approximately 5 percent the steam generator level shrink
- due to the feedwater isolation resulted in a lo-lo level-in i the #3 steam generator which tripped the reactor. The unit j stabilized at 547*F following the reactor trip.
l Diesel Generator Failure Reports
}' There were no diesel generator fail." reports transmitted during the month.
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Special Reports There were no special reports transmitted during the month.
Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM this month.
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' OPERATING DATA REPORT:
DOCKET NO.:50-327-V L*' DATE. OCTOBER.611984~ D
' COMPLETED BY M.fG. EDDINGS L
. TELEPHONE (615)-870-6248 j OPERATING STATUS l 1
"1. UNIT NAMES ~'SEQUOYAH NUCLEAR PLANT, UNIT' 1 NOTESE'
,2.nREPORT-PERIOD: SEPTEMBER 1984' J3.fLICENSED' THERMAL-POWER (MWT) ,3411.O
'4. NAMEPLATE ~ RATINGS-(GROSS MWE):. 1220.'6
.l50 DESIGN-ELECTRICAL RATING (NET MWE): 1148.0 6.' MAXIMUM. DEPENDABLE CAPACITY'(GROSS MWE)t- 1183.0-
'7. MAXIMUM DEPENDABLE CAPACITY.-(NET MWE) 1148.O
'O.LIF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS "
3 THROUGH 7)SINCE LAST' REPORT, GIVE REASONSt____ ___
. - - - _ - - _ _ _ _ _ _ _ _ _ - - . _ =___
- 9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET-MWE)s____- - - -
.________ _ _ - - _- - - - - - = - - ==_ --
- 10. REASONS FOR RESTRICTIONS IF ANY _== _________ ___
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, THIS MONTH YR.-TO-DATE. CUMULATIVE--
11.-HOURS IN REPORTING PERIOD -720.00 6575.00 28512.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 602.50 3997.10 18438.66
- 13. REACTOR. RESERVE SHUTDOWN HOURS 0.00 0.00 0.00-
<14... HOURS GENERATOR ON-LINE 563.75 3786.80- 17899.95
! 15.. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 ^O.00
- 16. GROSS THERMAL ENERGY GENERATED-(MWH) 1767263.66 11704071.84 57195922.14
'17. GROSS ELECTRICAL ENERGY GEN. (MWH) 573870.00 3819860.00 19198996.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 549030.00 .3657409.00 18434337.00
- 19. UNIT SERVICE FACTOR 78.30 57.59 62.78 -
'20. UNIT AVAILABILITY FACTOR 78.30 57.59 62.76 '
121.: UNIT CAPACITY FACTOR (USING MDC NET) 66.42 48.45 56.32 j22. UNIT CAPACITY FACTOR (USING DER NET) 66.42 48.45 56.32 l 23. UNIT FORCED OUTAGE RATE 21.70 27.37 20.14
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
________________ ______________________ - ____==__-- -__= -____
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPI-
= - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - __ _______
i NOTE THAT'THE-THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT Sequoyah One DATE Octob~er210, 1984
, COMPLETED BY M. G. Eddings TELEPHONE (615) 870-6248-HONTH September DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,
1 1058 - 17 . 1068 2 1069 18 1076 3 1071 19 1051 4 -
1070 20 1078 5 1067 21 7
'.9.69 6 1075 22 0' 7 1074 0 23 8 1077- 24 0 9 1071 0 25 10 1074 0 26 11 1074 0 27 12 1074 28 121 13 1076' 29 257 14 1073 30 306
, 15 1073 31 i -
16 1076 INSTRUCTIONS ,
On this format,. list the average daily unit power level in HWe-Net for each day in
( the reporting month. 8 Compute to the nearest whole megawatt. .
. . .(9/77)
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UNIT SHUTDOWS AND POWER REDUCTIONS DOCKET NO. 50-327' UNIT NAME Seouovah one -
DATE october 5. 1984 COMPLETED BY M. C . ?Eddinas REPORT MONTH SEPTEMBER TELEPHONE (615) 870-6248 w e c yy
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@7 "e Licensee 'y Cause &' Corrective Eo. .Date & Oy 8 T;2 Event f*o E*a Action to R {i j 2 5g* Report # #1 &T Prevent Recurrence
- 5~ $55 N" S' 5
840921 F 156.25 A 1 . Steam leaks on feedwater drain lines repaired.
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F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled '
A-Equipment Failure (Explain) 1-Manual far Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source
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OPERATING DATA REPORT DOCKET NO. 50 2 328 DATE OCTOBER 5,1984 COMPLETED'BY D.C.DUPREE t TELEPHONE (615)S70-6248 OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORF PERIOD: SEPTEMBER 1-30,1984
- 3. LICENSED THERMAL POWER (MWT): 3411.0
- 4. NAMEPLATE RATING (OROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): '1148.0
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 8. IF CHANGES OCCUR IN CAPACITY RATINOS(ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:_______-___-
___ -- -------=_ _------- . - - - - . - - - - - -
- 9. POWER LEVEL TO WHICH RESTRICT ED, IF ANY ( NET MWE ) :--------
- 10. REASONS FOR RESTRICTIONS,IF ANY:___--------------------
THIS MONTH YR.-TO-DA'IE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 6575.00 20472.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 575.05 6124.75 16485.82
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE 532.37 5987.99 16142.31
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERA'IED (MWH) 1471237.65 19449577.30 51867645.11
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 482390.00 6620740.00 17652680.00
- 10. NET ELECTRICAL ENERGY GENERATED (MWH) 459346.00 6373689.00 16991426.60
- 19. UNIT SERVICE FACTOR 73.94 91.07 78.85
- 20. UNIT AVAILABILITY FACTOR 73.94 91.07 78.85
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 55.57 84.44 72.30
- 22. UNIT CAPACITY FACTOR (USING DER NET) 55.57 84.44 72.30
- 23. UNIT FORCED OUTAGE RATE 20.63 7.42 8.59
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
HacmberlL 1184_--_ ______________--- = _ _ - _ - - _ _ _ _ -
NOTE THAT THE THE YR.-TO-DATE AND CUMULAIIVE VALUES HAVE DEEN UPDATED.
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DOCKET No. 50-328 UNIT 'Sequoyah Two DATE October 5, 1984
, COMPLETED-BY D. C. Dupree TELEPHONE (615)870-6543 Mr. 3 D ATE-' October 5, 1984 COMPLETED BY D. C. Dupree REPORT MONTH September TELEPHONE ~ (615)870-6248
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@g = c Et Licensee y Cause & Corrgetive
- No. Date 8, O s. 8 302 F. vent $% 8% Action t;o ;
y -E s g 5g" Report .* #? - 2. '8 Prevent Recurrence 4/
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8 840905 F 34.62 A 3 . Low E.H.C. pressure.
9 840909 F 19.93 A 3 Neutral transformer'overvoltage.
.L 10 840910 F 3.98 G 3 Lo-Lo level steam generator #4.
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l'1 840910 F.- 3.30 A 3 Cond. DI'was bypassed due to high Delta 'P'-
during start up causing the MFPT and S/G's'
. to swing.
12 840910 F 76.55 A 3 Feed water reg.' valve to #4 S/G was sluggish j in' operations during start-up. MFPT would not reset.
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. F: Forced Reason: Method: Exhibit G-Instructions l S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee 4- C-Refueling '3-Automatic Scram. Event Report (LER) File (NUREG-1 D-Regulatory Restriction 4-Cont. of Existing 0161) j E-Operator Training & License Examination Outage j F-Administrative 5-Reduction G-Operational Error-(Explain) 9-Other '
5 l (9/77) H-Other (Explain) Exhibit I-Same Source 1
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uni' SliUTDOL% AND poker REDUCTIONS DOCKET NO.' 's0-32&
UNIT NAME Caqu @ M
'*' 1 DATE October _5, 1984-COMPLETED BY D.,_C. Dupree- -
REPORT MONTil September TELEPHONE (615)870-6248 i
u e
- 57 "a ep" Licensee Cause & Corrective No. Date y, O y. @ ]O@ Event $*o E*o Action to .
- 2E 2 5y" Report ? M'8 8.?- Prevent Recurrence o;f E" EN5 N" 5" u
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13 840928 S 49.25 C 1 Cycle 2 refueling / modification outage.
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F: Forced Reason: Method: Exhibit G-Instructions 'i S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Cont. of Existing 0161)'
E-Operator Training & License Examination Outage F-Administrative 5-Reduction C-Operational Error (Explain) 9-Other _5 (9/77) Il-Other (Explain) -Exhibit I-Same Source'-
g Plant Maintenance Summary The following significant maintenance items were completed during the-month of; September 1984:
Mechanical Maintenance
- 1. Intercept valve, 2-FCV-1-124, was leaking EHC fluid. A break in a weld was discovered and repaired.
U
- 2. The 1A stator cooling water pump was re-built and installed.
- 3. Pressurizer safety valve work continues.
- 4. Unstopped the boric acid line.
- 5. Unit 2 tripped due to insulation which fell out and shorted the buswork. The situation was corrected.
- 6. The EHC filters on the 2B pump were changed out fo.llowing a loss of pressure due to clogged filters.
- 7. Due to a blown gasket in the B Auxiliary Control Air Compressor, it was rebuilt. Both the intake and discharge valves were replaced. .
- 9. Installed a Dressler-type coupling ovsr a leak in a two-inch fire protection line at the diesel generator building. The coupling was installed to slow down the leak while a decision on the best method to isolate the leak was being made.
- 10. 1-RV-63-637 was believed to be leaking through. A pressure test was performed and the valve was good.
- 11. Installed Furmanite boxes on 1-VLV-3-549 and over an old box on 1-5-94. Both were injected with Furmanite to stop the leakage.
- 12. Furmanite was injected into 1-FCV-1-98 on IC1 MSR,1-FCV-1-235 on IC2, 3-549, 2-FCV-1-150, and into the B4 manway elbow on the B-1 heater, to stop leakage.
- 13. The rekeying of some plant doors due to the loss of some important keys continues. These doors include CSSC and non-CSSC doors in all areas of the plant.
- 14. Replaced the boric acid cone, pump suction valve operator (1-FCV-62-164).
15.' Scab plates were fitted up on ERCW lines because of leaks and thin places caused by cavitation downstream of the butterfly valve.
- 16. Shut-down to repair a leaking feedwater drain valve and a leaking steam generator #1 manway cover.
Plant Maintrninca Summery Page 1if 9 ^
ELECTRICAL MONTHLY REPORT FCR SEPTEMBER , .
DATE.... C0rPONENT..... FAILL'.:E DESCRIP TION. . . . . . CAUSE OF FAILURE......... CORRECTIVE ACTION,....... P RO4, . . .
09-07-84 2-RM-090-0120 PUMPS ON RAD MONITOR 120 BEARINGS ON MOTOR WORN REPLACED MOTOR AND HONE
- 1 AND 121 WILL TOT STAY OH OUT CAUSING ARMATURE TO CHECKED ROTATION.
EVEN WHEN FLOW THROUGH SHORT CUT PERFORMED COUNT RATE ON MONITOR IS UP MONITOR AND UERIFIED PROPER OPERATIONS '
RETURNED TO SERVICE 09-07-84 FFSV-001-0182 STEAM CENERATOR N2 LIMIT SWITCH OUT OF ADJUSTED LIMIT SWITCH NONE
-B BLOWDOWN HEADER FLOW ADJUSTMENT ISOLATION VALVE STAYS OPEN WILL NOT CLDEE
~
W-07-84 2-FCV-001-0007 STEAM GENERATOR #1 LIMIT SWITCH BRACKET TIGHTENED LIMIT SWITCH 2-84-144 j
-B BLOWDOWN FLOW CONTROL LOOSE BRACKET VALUE STICKING IN CLOSED .
POSITION ;
09-07-84 1-BCTC-202-6.9 6.9KV BREAKER SHUTDOWN BOLT BROKE rW TRIP COIL a S'liCHED OUT BREAKER AND f0NE '
WBRK BOARD 18 WILL NOT OPERATE PART OF BREAKER REBUILT ,
09-G7-b4 2-FCV-003-0047 STEAM GENERATOR #2 DIRTY CONTACTS ON CLEANED CONTACTS ON 2-84-136
-B ISOLATION VALVE DID NOT INTERLOCKS CONTACTS WERE INTERLOCKS -
.. CLOSE ON FEEDWATER HOT DROPPING OUT 7
- ISOLATION SIGNAL 'i 1 09-07-84 2-FCV-001-0029 INSULATICN FOR LEADS IS LEAG3 DETERIORATED s CLEANED ELECTRICAL LEADS NONE i DETERIORATED ON #4 MAIN ALLOWING MOISTURE TO AND REPLACE 0 COVERS STEA!1 ISCLATION VALVE CORRODE LEAD COVERS AND . s v 'g COULD POSSIBLE SHORT OUT
' i CONTROL POWER MSIV 09-07-84 2-FCV-001-0029 GREEN LIGHT WILL NOT BURN CONTACTS DIRTY ON SNAD CLEANED CONTACTS ON SNAP NONE j
-T WHEN VALVE IS IN CLOSED LOCK LOCK ,
POSITION a J 09-07-84 2-HTR A-030-015 AUX. BLDG. CAS TREATMENT BAD RELAY ON HEATER REPLACED RELAY 1 . NONE 6-8 HUMIDIFIER NATER WILL y, ,i NOT COME ON - T .
09-07-84 0-HTCK-234-110 RED LIGHT COES h3T COME BAD CONTROLLER ON HEAT REhLACEOCONTROLLER tdXI' S OH GREEN LIGHT ST/YS ON TRACE ,
ALL TIME WHEN THEMOSTATE d
s
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3 Plc.nt Maintsnince Summary~
Pag 2 2 cf. 9 ELECTRIC /L MONTHLY REPORT FOR SEPTEMBER , ..
DATE.... CLf90NENT..... FAILURE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION........ PR00... '
IS TURNED UP DN CVCS B1
- i EAT TRACE .
09-07-84 1-ACB-201 BREAVER OH 480 VOLT TRIP CGIL NO CHARGING REPLACED CHARCING MOTOR NGE SHUTDOUN BOARD WILL NOT MOTOR BURNT Up Ai@ TRIP COIL OPERATE 09-10-84 2-FSV-067-0182 UHEN VALVE IS FULLY OPEN LIMIT SWITCES OUT OF ADJUSTE0 LIMIT SWITCH NONE ,
^
-B ON SIS PLUP ROOM COOLER ADJUSTMENT 2B STATUS LIGHT IN CONTROL ROCM UILL NOT LIGHT UP l 09-10-84 0-TC-234-0311- RESET ON TRIP POINT BAD PLUG ON HEAT TRACE REPAIRED PLUG FOR HOE l S DRIFTS AR0uto CN CVCS CONTROLLER CONTROLLER, CHECKED ELECTRIC EAT TRACE CONTACTOR MID EAT CONTROL PANEL. B2-2 TRACEFCR OPERATIONS 09-10-84 0-CHR-031-0338 BUBBLES IN SIGHT CLASS OF FREON LOW A00ED FREON TO PROPER NONE
-B SHUT DOWN ROOM UATER LEVEL WITH P,-22 CHILLER PACKAGE A 16 h
09-10-84 1-CGRP-082-001 ALARM LIGHT UILL NOT NO CAUSE F0tJO FU'4CTIONALLY CHECKED HOE A-A FUNCTICH PROPIPLY ON 1A-A WORKING PROPERLY AT THIS DIESEL GENERATOR RELAY TIME PANEL 09-11-84 2-FCV-067-0354 LIGHT IN CONTROL ROOM LIMIT SWITCH OUT OF ADJUSTED LIMIT SUITCH NONE WILL NOT FOLLOW LIMIT ADJUSTMENT l SWITCH ON
! VALVE-PEETRATION ROOM COOLER A3 ERCW FLOW CONTROL VALVE t 09-11-84 2-FCV-067-0350 LIGHT IN CONTROL ROOM LIMIT SUITCH OUT OF ADJJSTED LIMIT SUITCH NONE WILL NOT FOLLOW LIMIT ADJUSTMENT SWITCH ON VALVE l -PENETRATION ROOM COOLER l A2 ERCW FLOW CONTROL VALVE l 09-11-84 0-MTR B-032-002 BREAXER WILL NOT TRIP OUT TRIP COIL BWNT DUT ON PLUGCED IN NEW COIL, NONE i
Plant Maintenanca Summary Pcga 3 cf 9 ;
ELECTRICAL MONTHLY REPORT FOR SEPTEMBER . , .
DATE.... CDf190NENT. . . . . FAILURE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION......... PRO #n..
5 DN CONTROL SERVICE AIR BREAKER REPLACED MOTOR CUT OFF COMPRESSOR A SUITCH ACTUATOR ADJUSTED MOTOR CUT CFF SUITCH FUNCTIONALLY TESTED WORKING PROPERLY AT THIS TIME 09-11-84 2-XS-013-0161- PYROTRONICES DETECTOR IN BAD SMOKE DETECTOR REPLACED SMOKE DETECTOR NONE A UNIT #2 AUX BUILDING HEAT VENT ROOM ALARM STAYS IN FOR NO APPARENT REASON 09-11-84 1-FCV-072-0013 SEAL IN INTERLOCK ON CONTACTS DIRTY CLEANED CONTACTS WITH NONE CONTACTOR STUCK IN CLOSED FREON SOLVENT (MS-180)
POSITION ON CONTAINMENT FUNCTICNALLY TESTED SPRAY RECIRCULATING PUMP CONTACTS. NO FURTHER 18 TESTS REGUIRED 09-11-84 1-FCV-063-0073 SEAL IN INTERLOCK ON CONTACTS DIRTY CLEANED CCNTACTS WITH N0tE CLOSE CONTACTS IS STUCK FREON SOLVENT (MS-180)
IN THE CLOSED POSITION ON FROM APPROVED LIST OF b THE CONTAINMENT SUMP FLOW SOLVENTS (EMSL18)
T ISOLATION VALVE FUNCTIONAL TESTED CONTACTS NO FURTHER TEST REQUIRED 09-11-84 1-0XF-201-001B SI HEAT TRACE TRANSFORMER CONTACTS DIRTY CLEATED CONTACTS OF A tGE
-B "B" n0 TOR STARTER GUMMY STICKY SUBSTANCE AUXILIARY CONTACTS RED AND BLACK PUSH BUTTONS.
BLACK BUTTCNS SEEM TO BE HIGHER THAN HORMAL 09-12-84 2-LCV-003-0175 VALVE WAS VERIFIED CLOSED ACTUATION ARM ON LIMIT ADJUSTED ACTUATOR ARM 2-84-148
-A LOCALLY EUT RED AND GREEN SUITCH OF AUX) FEEDUATER LIMITS ARE ON LEVEL CONTROL VALVE OUT OF ADJUSTMENT 09-14-84 1-BCTB-201-DJ/ CSS AIR COMDRESSER A CONTACTS STUCK AND INSTALLED SPARE BREAKER NONE
\ II50-A BREAKER ON 480 VOLT SHUT CORRODED, SETTINGS OUT OF DOWN BOARD 1A2-A UOULD LIMITS NOT UORK
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Plent Maintenance Summary Pag; 4 of 9 a 9 ELECTRICAL MONTHLY REPORT FOR SEPTEMBER .
DATE.... QX1PONENT..... FAILURE DESCRIPTION.,.... CAUSE OF FAILURE......... CORRECTIuE ACTION,....... PRON,...
- i 09-14-84 0-LOCL-013-061 ALARM GN PAtEL UILL NOT GREEN CONDUIT SHCRTED OUT ECHL6097 LP10929 Note 6 CLEAR IN THE EXTERNAL ALARM COMPLETED TO USE ORANGE d HORNS CABLE EE5668 IS HON CONDUCTOR INSTEAD OF CONFORMING UITH CONTROL GREEN DRAWING PRINT #45U1699-33 09-17-84 0-ACU-311 AA CONTROL ROOM AIR WATER FLOW RESTRICTED TO ADJUSTED SUITCH AND VALE NONE CONDIT10NING UNIT WILL AIR CONDITIONER ON UATER FL0u NOT STAY RUNNING 09-18-84 1-GEN 8-082-000 DIESEL FAILED TO LOAD UP CPEN LOAD CAIN ON REPLACED LOAD SENSOR 1-84-287 1A-A TO 4 MEGAWATTS ELECTRICAL POTENTI0iETER CAUSED BY M0lyJLE IN 60 SECONDS PER BAD LOAD SENSOR F1ODlLE SURVAILANCE INSTRUCTIONS 7 PROBLET1 CLEARED WHEN OPERATOR WENT TO f1ANUAL 09-18-84 0-LOCL-013-061 ZONE 303 RELAY IS NO FAULT COULD BE FOUHD FUNCTIONALLY TESTED AND NONE
, 2 ENGERGIZED AND TROUBLE UCRKING PROPERLY AT THIS y ALARM IS PRESENT ON PANEL TINE i 0-L-612 09-18-84 1-XA-063-0064 LHEN STARTING 1A RHR PUMP ARM ON VALVE STEM DOESN'T INSTALLED OFF SET LIMIT N0tE FOR SI128 UINDOW N20 CAME HIT SWITCH LEVER CAUSING ARM FOR OPERATION IN AND WOULD N3T CLEAR LIMIT SWITCH NOT TO OPEN 09-18-84 1-RLY-082-00PO RELAY IS LOOSE TO THE LOOSE IN PLUG REPLACED PO RELAY AND NONE TOUCH CHATTERS WlEN CHECKED CPERATION OF TOUCHED SAr1E. DIESEL CENERATOR NOT INOP AT ANY TIME' 09-20-84 0-FCV-032-0094 VALVE OCCUSIONALY OVER j L1f1IT SWITCH ARM OUT OF ACJUSTE0 ARM ON LIMIT HONE TRAVELS DEFEATING AIR ADJUSTMENT SUITCH PURCE STEP FOR DRYER #2 09-20-84 2-FCV-063-0084 SIS CHECK VALVE ISOLATION LIMIT SUITCH ACTUATOR ADJUSTED LIMIT SWITCH NONE HEADER LEAX TEST SLIPPED ON SHAFT CAUSING ACTUATOR ON VALVE ISOLATION VALVE IS IN VALVE INDICATING LICHTS CLOSED POSITION VALVE RED AND GREEH TO STAY ON INDICATING BOTH RED AND GREEN
_ ~
Plarit Maintenance Sunsnary Pdg2(5cf-9:
~
ELECTRICAL 110NTit.Y REPORT FOR SEPTEPEER .
DA1E.... 021PONENT. . . . . . FAIL 6"E DESCRIPTION...... CAUSE OF FAILUR E. . . .. . . . . - CORRECTIVE ACTION,....... PR016. . . . .
09-21-84. 1-TE-072-0011- CONTF HMENT SPRAY PUMP B EMPLOYEES WERE USING THIS REPLACE 0 CONDUIT AbD- NONE L
B MOTOR INBOARD BEARING CONDUIT FOR A STEP OH INSTALLED TErPERTURE. .
" ^.
. TEMPEkTURE ELEMENT NOT CONTAIt#1ENT SPRAY Ptf9 B ELEENT TO TEMPERTURE WORKING MOTOR. CONDUIT IS BRONEN - WELL .
AND TEMPERTLRE ELErENT IS-COMPLETELY REMOVED FROM x TEl1PERTURE WELL 24-84 1-LCV-062-0192 A'80xIC ACID EVAPORATOR LIMIT SWITCH OUT OF ADJUSTED LIMIT SWITCH NDE ' -
--A DISCHAllG VALVE WILL NO ADJUSTMENT WILL NOT LET FULLY CLOSE VALVE FULLY CLOSE - >
25-84 >RE-090-0101- AUXILInRY BUILDING VENT BEARINGS IN Purp GAULDED MECHANICAL REPLACED'THE. NOE t-
.A MONIT0i! WILL NOT WORK CAUSING'110 TOR TO OVER PUMP AND ELECTRICAL HEAT AND SHORT OUT REPLACED THE (10 TOR 1
'09-25-84 2-LCV-003-0174 PREVENTIVE 11AINIANCE NO FAILURE FUNCTIOHALLY CHECKED TIMER AND FOUbl0 - 2-84-142 .
-B CHECK 74-B TIrlER -TO TO BE WORKING. SET TIMER-4 ENSURE IT WILL TIRE OUT! FROM 41.SEC. TO 30 SEC. -
(30 SECOND TIRE DELAY) STOP WATCH 902147 1-11-85
- TESTED PER M16.20
_ 09-25-84 0-XA-013 NO FAILURE MODIFICATION WORK UlOER LIFT ZOE WIRE AT PAELi NOE 4
WP 10009R ECN 5237 FOR ZONES 3498350 USING
. i HI6.20 PERFORf1 SI 234.4 O.
AFTER MODIFICATION.
INSTALL JUr;PER FOR ZONES 4
3498350 RECORD PER
, 11I6,20 TO CLEAR -TROUBLE 1 LIGHT-0:4 PAEL, RErIOVE JUNDER AFTER MODIFICATIGl
- 09-25-84 0-HTCK-0090S&P HEAT TRACE CIRCUIT THIS CIRCUIT Olt.Y HAS A . A11PS WERE CHECWED AND NOE i DISCHARGE LINE 1A BATP PRIl1ARY Alt) THE TEIPTURE FOUte TO SE CORRECT WAS FOUND IHOP DN .IS 165 11RA118938
- 09-25-84 0-HTCK-234-009 HEAT TRACE REPORTED BAO THIS CIRCUIT ONLY HAS A - Af9S WERE CHECKED AND- NOE
@&S ON 11RA240393 PRIrlARY AlO TE ; FOUND 'TO BE CORRECT ..
TEl1PERTURE IS 168. >
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" b m .-. y q
Plant Maintenance Sununary '
Psgb_6 ef 9c ELECTRICAL MONTHLY REPORT FOR SEPTEFEER ;- .
z0 ATE.... CDNPONENT..... FAILURE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION,....... PR00... .
09-25-84 0-HTCK-234-010 SAMPLE VALVE HEAT TRACE CIRCUIr TO
- D AMPS WERE CHECKED AND NOE ~
OP1S 0-ULV-062-1056 WAS BORIC i.CID TANKS "C" UAS HEAT TRACE WORKING _'
REPORTED BAD ON MRA248393 REPORTED BAD ON PROPERLY AT THIS TIME-MRAE248393-09-26-84 2-MTR B-062-023 PUMP KEEPS TRIPPING OUT LEAD TO MOTOR STARTER.HAD REPLACED BAD CRIMP OM~ N0E 2-B ON BORIC ACID TRANSFER BAD CRIMP ON TERMINAL LUG TERMINAL LUG TO MOTOR PUMP 28-8 STA8tTER PER MODIFICATION AND ADDITIONS INSTRUCTI(N 12-09-26-84 1-MTR B-077-000 REACTOR COOLANT DRAIN THERM 0AL OVERLDADS BAD REPLACED'0VERLOADS IN. HOE -
'6 TANK PUMP 18 KEEPS BREAKER TRIPPING OUT 09-27-84 1-AHU-313-0001 TEMPERTURE IN ROOM TOO 480 VOLT BOARD ROOM 18-B CHECKED UNIT AfD IT IS NOE B-B UARN 89 AIR HANDLING UNIT AND GPERATING PROPERLY AT '
CHILLER PACKAGE WILL NOT THIS TIME REMAIN RUINING 09-27-84 0-CHR-313-0338 NO FAILURE OIL LOW OIL BELIEVED TO BE LOW CECKED OIL LEVEL AND' s NOE '
-A FOUte TO BE NORMAL (NO
] ' OIL ADDED) 09-27-84 0-FCD-30-0122 CASK LOADING AREA DAMPER DIRTY CONTACTS CLEANED CONTACTS CHECKED NOE ,
DID NOT ISOLATE ON RELAY WORKING PROPERLY'AT
, i AUXILIARY BUILDING THIS TIME 5' ISOLATION SIGNAL FROM 0-RM-90-0102 FUEL POOL RAD MONITOR 09-27-84 1-AHU-030-0162 FUEL POOL RAD MONITOR DIRTY CONTACTS CLEANED CONTACTS CHECKED- NONE 1 0-RM-90-102 DID NOT STOP RELAY WORKING PROPERLY AT-OH. AUXILIARY BUILDING THIS TIMEL .
ISOLATION SIGNAL-09-27-84 1-AHU-030-0159 1A AUXILIARY BUILDING DIRTY CONTACTS CLEANED CONTACTS CHECKED NOE GEERATOR EXHAUST FAN DID RELAY WORKING PROPERLY AT NOT STOP.ON ISOLATION ~,
THIS TIME SIGNAL FROM 0-RM-90-102 I FUEL POOL MONITOR 9
= . _ - - --
Plant' Maintenance Summary Pigi 7 of.9'
~ '
ELECTRICAL MONTNLY REPORT FOR SEPTErsER - .- .-
DATE.... 0011P'0HENT. . . . . FAILURE DESCRIPTION......- CAUSE OF FAILURE.........- CORRECTIVE ACTION........ PR00...
28-84 1-ItNB-250-000 'RESULTS OF TESTS RAN AT
~
REPLACE C1 Ato C6 REPLACED CAPACITOR BANKS NOFE s:
'N-E WATTS BAR IN THE WEEK CF CAPACTOR BA>ES PER PEl10 C1 AND C6 PER-
' JUNE 19 1984 DN VITAL FR0ft Jf1 MCGRIFF TO J MODIFICATION AND-INVERTERS KRELL DATED JULY 25 1984 ADDITIONS INSTRUCTION 9 1 PEMD ATTACHED 12 . v.
0 09-28-84 1-INVB-250-000 RESULTS OF TESTS RAN AT' REPLACED C1 Ato C6 REPLACEDCAPACITORBANNS NONE L-D WATTS BAR IN THE WEEK CF CAPACITOR bat 4(S PER rEl10 'C1 AND C6 PER JUNE 19 1984 OH VITAL . FROM J1111CGRIFF TO JB MODIFICATION AND ea .
INVERTER KRELL DATED JULY 25 1984 ADDITIONS INSTRUCTION 91 tEMO ATTACED 12 09-28-84 1-ItNB-250-000 RESULTS OF TESTS RAN AT REPLACED C1 AF9 C6 REPLACED CAPACITO'4 BANKS HONE.
R-F WATTS BAR IN THE WEEK CF CAPACITOR BANsi PER F1Ef10 ' C1 A>0 C6 PER-JUNE 19 1984 ON VITAL FROM JI1 f1CGRIFF TO J MODIFICATION AND INVERTER KRELL DATED Jul.Y 25 1984 ADDITIONS INSTRUCTION 9 12 f1EMO ATTACFED 12 09-28-84 1-ItNB-250-000 RESULTS OF TESTS RAN AT REPLACED C1 AND C6 REPLACED CAPACITOR BANKS' NOME T-G WATTS BAR IN THEWEEK OF CAPACITOR bat 4G PER PEl10 C1 AND C6 PER '
13 JUNE 19 1984 DN VITAL FROM JM f1CGRIFT TO J . F10DIFICATION AFD y INVERTER KRELL DATED JULY 25 1984 ADDITIONS ~ INSTRUCTION 9.1 f1EMO ATTACHED 12.
09-29-84 2-GENE-082-000 FUSES ON EXITATION PANEL 24 VOLT D.C. D:tIVE f10TGR REPLACED 24 VOLT D.C. 2-84-163 2A-A -0F UNIT 2 DIESEL BAD DRIVE 110 TOR AND #9 JUSTED GEfERATOR 2A-A KEEPS .CAf1 LIMITS. 1, BLOUING AFTER FUSES HAVE BEEN REPLACED ON FO-3 AND FU-4
, 09-29-84 1-BDE-250-00NG FREGUENCY 11ETER WILL NOT FREGUENCY FETER BAD ' REPLACED METER NONE
-F CALIBRATE ON TIE 120 UOLT '
l A.C. VITAL INSTRUrENT
! POWER 1-III a
! 09-29-84 1-FCV-001-0004 11AIN STEAM ISOLATION LIl1IT SWITCH B O INSTALLED LIf1IT SWITCH NOFE.
VALVE LOOP 1 LIl1IT SWITCH AND VERIFIED UCRKING TEST LIGHT STAYS ON PROPERLY AT THIS TIl1E. -
- . 09-29-84 1-FCV-001-0022 VALVE IS CLOSED AND GREEN LI!1IT SUITCH B!O REPLACE 0 LIMIT SUITCH NONE, LIGHT WILL NOT ILLUl1INATE
(
4
Plant Mzintenance Summary; .Pigy 8'ef 9. ..~
ELECTRICN. MONTHLY REPORT FOR SEPTEMBER
-DATE.... COMPONENT. . . . . ' FAILURE DESCRIPTION...... CAUSE OF FAILURE....'..... CCRRECTIVE ACTION........ PRON,...; _
~09-29-84 1-FCV-030-0056 LIMIT SWITCH OUT OF DIRTY CONTACTS CLEAMI) CONTACTS NOE '
~
ADJUST 11ENT
.09-29-84 1-ZS-087-0023 DURItC NODIFICATION FOR CCHSTRUCTION DRILLED INTO TEMPERARY CABLE WAS84-335 THE FIFTH VITAL BATTERY POWER CABLE TO FCV-87-23 CONECTED. BETWEEN THE THE POWER CABLE WAS DAMAGEING TE CABLE JUtCTION BOXES 'FOR VALVES DAMAGED FCV-87-23 AilD THE POWER CABLE FRDM THE MAIN <
CONTROL ROOM TO THE' ~ -
^
JUNCTICN BOX 09-29-84 1-MTR B-030-010 FAN DID NOT STOP DH NO PROBLEM FOUND FutCTIONALLY TESTED . H0tE 3 ISOLATION SIGNAL FROM OPERATING HORT1AL AT THIS . ,
0-Rft-90 FUEL POOL RAD TIf1E ~
f10NITOR IN AUXILIARY '
3
, BUILDING 09-29-84 2-PS-003-0160A LOOP 1 PIPE BREAK LIGHT CABLE 2V1045(WIRE N15F3' CHANGED TO CORRESPOND 2-84-142
-B COMES ON WHEN TERRY AND #1FH-120V.D.C) LAID WITH DRAWING 45W603-5 1 TURBINE STARTS DOWN WITH CABLE 25G501 7 (WIRE #8FP11 Ate f13D24-24VAC) IN PS-3-1608 2
09-29 2-FSV-063-0077 LIMIT SWITCH WILL NOT ACTIVATOR ARM ON LIMIT-' ADJUSTED ACTIVATOR ARn 00 NONE-
-A CLEAR SWITCH OUT OF ADJUSTENT LIMIT SWITCH
, 09-29-84 1-FCV-087-0021 NO FAILURE RETURNETO NO FAILURE RETURNE0 TO NORMAL HONE
, NORMAL CONFIGURATION CONFIGURATION 1-FCV-87-21' PER
, SNI-1-87-6 09-29-84 2-ZS-003-0048 STEA!1 GEERATOR N2 FEED HO PROBLEM FOUt0 HAD OPERATIDH STROKE- NONE:
WATER REGULATOR VALVE VALVE SEVERAL TIMES- -
OPEN LIf1IT SWITCH IS NOT OPERATING HORf1AL' AT THIS MADE UP TIf1E -
'09-29-84 2-AHU-313-0514 480 VOLT BOARD ROOM AHU THERf10 STAT AIR LINE 'UNCRIMDED AIR LINE NONE
+ -B 2B WILL NOT RUN CRIMPED ELOCKING UNIT, FR0f1 RUNNING ,
09-29-84 1-FCV-001-0147 t1AIN STEAf1 ISOLATION , LEVER ON LIMIT. SWITCH OUT ADJUSTED LEVER ON lit 1IT- HONE '
s .
II
= -'J
Plant Maintenanca Summary P2gn 9 ef 9' ELECTRICAL MONTHLY REPORT FOR SEPTEMBER . .
DAT?...p. CDMPONENT. . . . . FAILURE DESCRIPTION...... CAUSE OF FAILURE......... CORRECTIVE ACTION ....... PROM ...
VALVE BY PASSINDICATES OF ADJUSTMENT SUITCH THROTTLED WEN VALVE IS ;
OPEN 09-29-84 1-FCV-001-0022 MAIN STEAM ISOLATION LIMIT SUITCH OUT OF ADJUSTED LIMIT SUITCH NONE VALVE (LOOP 3) LIMIT ADJUSTMENT SUITCH INDICATES OPEN UHEN VALVE IS CLOSED 84-08-09 04fTR B-032-002 TRIP COIL SHORTED OUT AND SHORT TO CROUND REPLACED TRIP COIL- NONE 5 BURNT UP 65 records listed.
Plant-Meinten:nce Summary (Continued)-
Instrument Maintenance- -
- 1. During the month, there were eight auxiliary building vent isolations and one containment vent isolation on unit 1. Seven of the eight ABIs were the result of high background radiation levels primarily associated with spent fuel pit water quality. The other ABI occurred during filter change out.on the auxiliary building radiation monitor. The unit 1 CVI was caused by flow switch chatter due to low sample flow in the lower containment radiation monitor.
During the month, a modification to the upper level discriminator circuit, ECN-6151, was incorporated on total gas and air particulate channels. Also time delay relays were' installed, ECN6137, for the spent fuel pit area monitors.
- 2. The monthly ~ calibration of the,UHI level switches found all switches for unit 1.and 2 within Technical Specification tolerance.
- 3. Temperature and flow instrument _ channel for the flow of the diffuser pond to the river received maintenance this month. Lightning storms during the month caused several failures. Flow element 230B was replaced and both temperature channels were repaired. All channels were recalibrated and remain in service. Lightning arrestors have been installed and proper groundin'g of the channels was implemented.
Unit I
! 1. Containment sump level transmitter 1 LT-63-178 drifted high. The filled senseline was topped off with oil, the transmitter recalibrated and returned to service.
- 2. Implemented FCR 2634, ECN 6055, which restored a 0-600 psi channel for RCS pressure. This FCR fully implemented the requirement for RCS wide range pressure PAM channels. TACF 84-0083-68, which was initiated in July, was cleared.
- 3. During the month, number 2 governor valve _ experienced fluctuations which resulted in minor load changes. The fluctuations were originating in the speed error channels of the AEH controller. Defective electrolytic capacitors were found on three circuit boards. Six (6) 4 circuit' boards were replaced with spares-during the forced outage of 9/24. The spare boards were calibrated and returned to service.
No problems with the AEH controller were experienced during startup and subsequent operation.
,e ,e -
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Pltnt Mtintenenca Summary 4
(Continued)
Instrument Maintenance' '
(Continued)
Unit 2
- 1. Following the reactor trip on'8/5/84,:a pipe break detection alarm occurred for loop .1 of turbine driven auxiliary feedwater system.
Both pipe break pressure switches were out of tolerance and a wiring
. error was found. The wiring was corrected. A special test instruction
--was written and performed to resolve discrepancies found during troubleshooting. During performance of the test a cable was found '
' improperly labled. .The pipe break switches on the other loops were inspected. A switch on loop 3 was found corroded and was replaced.
All switches are scheduled to be replaced with 0588 qualified replacements during U2C2 outage.
- 2. After a series of reactor trips early in the month, Operations Section requested that feedwater and steam generator controls be calibrated.
Controllers and reg valves were checked for loops 2 and 3. Minor adjustments were made. No problems were encountered during the subsequent startup.
- 3. Other maintenance work is shown on the attached list.
e l
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Plant Maintenance Summary Page l'of 5 I * '
INSTRU1ENT MAINTENAEE MONTM.Y SIM1ARY 10-10-84 COM f5t.C0 5 U FttiC SYS ADDRESS. DATE. . . . DESCR IPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . . . . . . . . . . . . . . . . . . . . .
i A047818 0 PS 082 262 09/17/84 0-PS-082-262, REPLACE DEFECTIVE PRESSLRE SWITCH THE PRESSURE SWITCH LAS leT OPERATING I
AlO CALIBRATE - SEEDED FOR SI-170.4. PROPERLY. REPLACED TE DEFECTIVE SWITCH, 2
CALIBRATED AND LEFT B4 SERVIE I
A101878 0 PI 032 88 09/26/84 0-PI-032-88, VERIFY /RECAL AS ECESSARY OUT OF CAL. RECAL Ale RETIRED TO SERVIE.
! A101944 2 PDS 065 970 09/19/84 2-PDS-065-970,PDS STATUS LIGHT IS IMOP. FOLDO THE CONTACIS ON TE EMt8N SWITCH lERE DLRING PERFORMAK E OF SI 188. INVESTIGATE ADO FOUto DIRTY. CLEAED TE CONTACTS 1 REPAIR. VERIFIED CALIBRATION MG RETLRED TO SERVIE.
i A102264 0 FR 027 230A 09/13/84 0-FR-027-230A,RECGt0ER IS DRIVEN HARD UPSCALE THE RECORDER WAS DRIEN WSCALE OLE TO
! TE FLOW 110DIFIER. DUT OF CAL. REMOVED
! TE FLOW 1100IFIER FRG1 SERVIE RECALIBRATED 8 RETURIED TO SERVIN A102278 2 LEV 003 172 09/27/84 2-LCV-003-172,REPl. ACE RELAY SLSASSEFBLY ON VALVE A REQUEST WAS SUBL 11TTED TO CHAICE TtE POSITIOER WITH HIGH TEWERATtRE F100EL RELAY TO A HI TEMP RELAY ON T E STEAN l GEERATOR #2 LEVEL CG4 TROL VALVE.
REPLACED TE RELAY G4 TEH PC3ITISER
, WITH A HIGH TEW. ftX1A.E. VERIFIED
, OPERATION AlO RETtRIED TO SERVIE.
A102279 2 LEV 003 173 09/27/84 2-1.CV-003-173,REPtACE RELAY St2ASSEfBLY ON VALVE A REGUEST WAS SUBMIT 1ED TO CHANGE TE POSITIOER WITH HIGH TEW.1100EL RELAY TO A HI TEr1P. IELAY ON TE STEM 1
, i EERATOR #2 LEVEL CENTRE. VALVE.
! WITH A HIGH TEW. DERRA.E. VERIFIED i OPERATION Ale RETLRIED TO SERVICE.
i A121559 1 Rl1 090 106C 09/04/841-Ri1-090-106C. MIN 110DULE FAILS DOWNSCALE TE f100ULE WAS FAILIls 00L86 SCALE OCCASSIONALLY BRIICIls IN INST.11ALF. ALAR 116 BRIICING IN TE INSTIEJrENT HALFLACTION i ALAR 11. REPAIRED TE HIGH VOLTAGE Col #ECTOR ON TFE DETECT.8 REPLACED POLER SUPPLY.
! A121647 1 PIS 087 22 09/18/841-PIS-087-22,CECK PIS-87-22 CALIBRATION. DVl1 READOUT 11ETER BAD. REPLACED TE DVl1 PRESSLRE IDCICATIG4 IS TOO HIGH. READOUT lETER ADO VERIFIED CALIBRATION A121670 1 FI 063 92C 09/01/84 1-FI-063-92C,THIS ItOICATOR IS IlOICATING 500 TE IleICATOR WAS ItOICATIts 500 GALLONS GALS l#EN TE FI-63-92A IS IleICATING 0 GPff, PER MIMJTE WHEN A SIttR.AR Il@ICATOR WAS THIS ItOICATOR DEEDS CALIBRATION; PLEASE REPAIR. READING 0. TtE TOLLERMCE RANGE WAS CHECI(ED MD EVERYTHIls WAS WITHIN ACCEPTANCE CRYTERIA.
A121741 1 FIS 063 43 09/18/841-FIS-063-43,CECK FLOW TRANSMITTER, CALIBRATE, HAIRLIFE IleICATOR mfd FALt.EN OFF OF OR REPAIR AS ECESSARY. ALARl1 IN Il@ICATING 10 FIS. REINSTALLED TFE HAIRLIE SCALE, FLDW & LOCAL NOT SCWIP FLOW. ZERCED TE INDICATOR VERIFIED OPERATION NO RETURED TO SERVICE.
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a Plant Maintenance Summary Page 2 of 5 INSTRUENT MAINTENAEE temR.Y Surt1ARY 10-10-84 _ -
a Corp FR.C(N9 U RBC SYS ADDRESS. DATE.... DESCRIPTION..................................... CORRECTIVE ACTION....................... -
l 4 A122654 1 LI 068 320 09/24/841-LI-068-320,PERF(Rf1 LOOP CALIBRATION CECK ON THE SENSE LIES AW TE TLEING NAD LGBT LI-68-320. PARTIAL LEG BECAUSE (F A LEAK ON SENSE LIE GOING TO 1-PT-61F322. BACK FILLED, -l VERIFIED CAL AND RETLMED TO SERVIE.
4 A231904 1 PS 062 244 09/10/84 1-PS-062-244, SWITCH DOES NOT REPEAT. EEDS TO TE PRESSLRE SWITCH IRS teT REDEATIIC.
BE REPLACED. REPLACED TE DEFECTIE tRIITCH, CALIBRATED AND RETLRIED TO SERVIC2.
] A233378 2 FCV 003 09/11/84 2-FCV-003 ,CECK STRONE OF 2-FEV-3-14B TE FEEDWATER CONTROL VALVE WAS ICT 4
OPERATING PROPERLY. DECNED TE STRONE OF TE VALVE, Ale RERRED TO SERVIE j A233379 2 FCV 003 90 09/11/84 2-FCV-003-90,CECK STRONE OF 2-FCV-3-90 THE FLOW CONTROL VALE WAS NOT OPERATING
- PROPERLY. VERIFIED OIERATION OF VALVE' j STRONE Ale RETURNED 10 SERVIE i A233384 0 PS 032 88 09/25/84 0-PS-032-88,CECK CALIB 0F P.S. SWITCH OUT OF CAL. RECAL SUITCH.
A233385 0 PS 032 88A/B 09/25/84 0-PS-032-88A/B,CECK CALIB 0F P.S. PS-32-88 OUT OF CAL. RECAL SWITCH.
. A233386 1 FEV 001 107 09/25/841-FCV-001-107 CECK STRONE OF STM DLR9 VALVE fCV STRONE DUT OF CAL. RESTRONED UALVE -
l A233388 1 LT 063 109 09/26/84 1-LT-063-109,C ECK CALIB. OF LT-RETURN TO ME Af9LIFIER 3BOARD lAS FOLM) BAD DE TO
! SERVIE. AN ELECTRONIC PROBLErL REPLACE 0 T E 4 #9LIFIER BOARD, RECA.ISRATED XFfTR Ale
! RETURED TO SERVIK.
! A239986 1 PT 068 322 09/25/841-PT-068-322,REPLKE DEFECTIVE FITTING Al@ SENSE THE TRANSMITTER HAD LDST PARTIAL LEG
!: LIE BECAUSE OF A LEAK ON TE SEMBE LIES.
d d REPLACED TE FITTIIES Ale SENSE LIES.
- 'A247597 2 PS 003 1400 09/19/84 2-PS-003-140B, NIM CLEAR DISCREPAICIES F0l#G ON .THE SWITCH WAS FOUlO WITH CORROSION ON
. F1R A292752 IT CAUSING IT NDT TO PERFORM ITS i INTEICED FUNCTION. REPLACED TE SWITCH, i CALIBRATED Ale RETLRIED TO SERVIE.
l A279294 2 XX 003 LOOP 2 09/13/84 2-XX-003-LOOP 2,CECK LOOP 2 SG LVL CONTROLLER A REtlEST WAS 11ADE TO VERIFY LOOP l OPERABILITY. VERIFIED (PERATION AIG i
RETURED TO SERVIE. le PROBLEM F0t#C.
A279295 2 XX 003 09/13/84 2-XX-003 ,CECK LOOP 3 SG LEVEL CONTROLLERS A REGUEST WAS ItADE TO VERIFY LOOP -
OPERABILITY. VERIFIED OPERATION AlO l RETUE 0 TO SERVICE. ND PROBLEM WAS i FOUND.
09/11/84 2-FCV-003-35, CHECK STRONE OF SG LOOP 4 FR0ft T}E FLOW CONTROL VALE FOR TE STEAM l A279297 2 FCV 003 35 1 C(DITROLLElt GEERATOR #1 FEEDWATER WAS ICT OPERATIls
! Pfl0PERLY. VERIFIED IROPER VALVE STRONE l OFERATION AIS RETLRIED TO SERVIE i A282207 1 Pl1 068 SPARE 09/12/841-PfF068-SPARE, VERIFY PROPER IPERATION AH OPERATIONAL CECK WAS RE8LESTED FOR j (FUCTIONAL CECM) AIS RETLRN TO POER STORES. TFE PRESSLRE MONITOR. PERF(RfED l FLHCTIONAL CHECK.
Plant Maintenance Sucunary Page 3 of'5
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INSTRlkENT FIAINTENANCE FONTtt.Y SurtlARY 10-10-84 , u .
- CO.
PR.CWP U Fl8C SYS ADDRESS. DATE. . . . DESCR IPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . . -
. A282210 1 LT 063 109 09/25/841-LT-063-109,CECK CAL OF TRAletiITTS AFTER A REGUEST WAS MADE TO VERIFY
- BLIle FLANGES ARE INSTALLED CALIBRATION. VERIFIED CALIBRATION Ale l FOUFO NO PROBLDIS.
A282952 2 FCV 003 103 09/10/84 2-FCV-003-103,FOR PROPER SIGNAL AfD VALVE AREGUEST WAS tlADE TO CECK FOR PROPER
! OPERATOR SIGNAL Ale VALVE OPERATION. VERIFIED
! TE STROKE ON TE f1AIN REGlR.ATOR VALVE i A283609 0 FR 027 2308 09/06/84 0-FR-027-2308,TROLSLESHOOT LOOP RECORDER IS TE LOOP RECOROG WAS DRIVEN HARD i DRIVEN HARD LPSCAE. UPSCALE. REPLACED 7tE CIRCUIT BOARD FGt l PX & 8UFFER ON TIE FLDW RECORDER CALIBRATED & RETURED TO SERVIE A285263 1 068 RVLIS 09/04/841--068-RVLIS,REfDE RVLIS SYSTEl1 TRAIN A88 FRG1 THE TRAIN ASB 0F TE R.V.L.I.S. SYSTErl SERVIE A!O PERFORrl A SANLE CECK E CARD ERE REelESTED BY TE SYSTErl EBCIEER TO
! Col #ECTORS FOR HAIRLIE CRACMS PER TtE ATTACDED CECK FOR CRANS IN TIE CIRCUIT BOARDS.
i LESTIM200SE TECH. BlLLE CECNED FOR PROBLErs AfD FOL89 IDE l A285761 0 PX 090 SPARE 09/05/94 0-PX-090-SPARE, REPAIR XFORrER - 24VDC THE POWER SLPPLY WAS DET WERATIls l PROPERLY. REPLACED 15E TRAISISTut AfD
! 11ADE A FUNCTIONAL C6ECK.
l A285773 0 PX 090 SPARE 09/05/84 HX-090-SPARE,+24 VOLTS DRW TO 9 VG.TS LAGER TE 24 VOLTS POLER SLPPLY WAS NOT l6 LOAD SHOWING ITS APPROPRIATE. REPLACED A BAD ly TRANSISTOR AND VERIFIED WERATION.
A285776 0 PX 090 SPARE 09/06/84 0-PX-090-SPARE. REPAIR PX, FAILS l#@ER LOAD TE POER SUPPLY WAS FAILIts l#OER LOADS DUE TO A BAD CAPACITIR. REPLACED A BAD i
CAPACITOR & VERIFIED OPERATION.
' A285777 0 PX 090 SPARE 09/06/94 0-PX-090-SPARE, REPAIR PX, FAILS UNDER LOAD THE POWER SUPPLY WAS FAILIls LACER FlR.L I LDADED CODOITION. REPLACED A REGILATOR l Ale A CAPACITOR Ale ERIFIED GPERATION.
I A285780 0 PX 090 SPARE 09/06/84 0-PX-090-SPARE, REPAIR PX SUPPLY - 2400C THE POWER SLPPLY WAS NOT OPERATIls PROPERLY. FULAG A BdRE WIRE I44ICH WAS I REPAIRED.
A285787 0 PX 090 SPARE 09/17/84 0-PX-090-SPARE, poler SUPPLY PEASLRES +31.6V & THE POLER SUPPLY WAS NOT FLDICTIONING i i -23.7V INVESTIGATE Ale REPAIR. PROPERLY. REPAIRED TE POWER SUPPLY ADO RETURED TO SERVIE.
l A285998 1 LI 063 178 09/10/841-LI-063-178,1-LI-63-178 CONTAIffENT Sur58 EVEL TNE OIL FILL IN T6E 1RANSilITTER WAS LOW.
- IDDICATOR READIlE 3E HIGER THAN OTER TOPPED OFF THE DIL FE.L, VERIFIED l ASSOCIATED LEVEL Il@ICATORS TRANSl*ITTER CALIBRATIDN, & RETURIED TO
! SERVIE.
.' A28600:' 2 FR 003 90 09/10/84 2-fR-003-90,PLEASE REPAIR BLUE PEN ON FLOW TE BLLE PEN ON TtE FLOW RECORDER WAS
! RECGtDER. NDT PRINTING. TIE Bi1E PEN WAS CALIBRATED 8 RETURDED TO SERVIE.
A286564 0 lirl 090 SPARE 09/13/84 (Htit-090-SPARE,RP-1 HAS ND SIGNAL, REPAIR AS TE poler SUPPLY WAS NDT OPERATIls IEEDED. PROPERLY. CHA0EED OUT SEVERAL REGISTORS
{
Plant Maintenance Summary' Page 4-of 5 INSTRt#ENT f1AINTENAEE PENTit.Y SurBIAltY 10-10-84 N 1 Corp l FR.CW9 U RBC SYS ADDRESS. DATE. . . . DESCRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . . -
! Ale A CAPACITOR ALSO TE SCALE NAD WAS
- REALIGEO.
j A287090 2 N2AN 043 200 09/05/84 2-N2AN-043-200, min CHANGE OUT INSTRurENT TEST TE NYDROGEN ANALYZER WAS IN EED OF A t GAS BOTTLES TO CLEAR N2AN 43-2000 LOW GAS CHANGE OUT IN GAS BOTTLS. VERIFIED PRESSINtE OPERABILITY AE REPLEED TE SUPPLY j BOTTLE Ale RETIAtED 10 SERVIE.
A287096 2 LIC 003 164 09/04/84 2-LIC-003-164,UPON AFWP START SIGNAL CONTROLLER THE WIRING PLUG UAS leT PLUGGEO IN 1 OPENS VALVE WIDE (PEN CAlet0T GET CONTROLLER IN PROPERLY. REPOSISTI0 LED TE WIRIls PLUG i F1AN. ON ft-4 TO CLOBE VALVE AUTD-SET POINT ON TE 1100tLE Ale LEFT IN SERVIE. .
LOERING WIll ICT CLOBE VAL
- A288606 1 151 090 112 09/17/841-Rft-090-112,CECK 1129 RADIATION DETECTOR F0ft TE F10NITOR WAS NOT (PERATIls PROPERLY.
?
PROPER CIRCUIT (PERATION FOLAC TE IODIE FLOW RATES TO BE OUT OF 3 ADJUSTfENTS.
A288638 1 FCV 001 7 09/25/841-FCV-001-7,rIn TE AIR REGtLATOR IS LEAKING A REGULATOR EEDLE STIAX INSIDE REGILATOR LaRf;E Af10lDIT OF AIR - EEDS TO BE REPAIRED WHILE ORFIT. CLEAIED REGIAATGt & REASSEfBLED, i U-1 IN PEDE 5 REINGTALLED, 8 SET TO 45 PSI.
A288664 1 085 B8 09/25/841--085-B8, RCD BOTTW1 LIGHT FGt B8 ROD-CONTRG. ROD BOTTW1 BISTABLE LIGHT POT ON.
BACK "C" GR0lp 1 DID NOT CLEAR l#EN PLLLIls REDS REPLACED BAD BISTABLE CARD.
063 99 09/26/84 1-LI-063-99, min LEVEL PEGGED MIGN THERE WAS A BAD CIRCLET BOARD DLE TO AN l A288708 1 LI j ELECTRONIC FAILlBE. IEPLACED TE CIRCUIT lg, BOARD, RECALIBRATED 1E TRANSt1ITTER Ale ,
- 8 RETURED TO SERVIM. .
i A288713 1 LI 003 107 09/25/84 1-LI-003-107, min 1-LI-3-107 M4 S/G LEVEL Ile. TE NIGN SIDE DitAIN VALVE WAS F0lBC READDC APPRCX.15E LOWER LEAKING ADO TE TRAN31tTTER WAS F0 TAC OUT OF CALIBRt. TION.. llE DitAIN VALVE WAS n twn, TE TRAMBilITIER RECALIBRATED, 8 RETURED TO SERVIK.
A288723 1 PCV 001 12 09/23/841-PCV-001-12, BAD AIR LEAK ON VALVE POSITIOPER ON A GASKET WAS BAD CAUSEls TE VALVE 1-PCV-01-12 POSITIOER TO LEAK. TILE GASKET WAS
- REPLACED, VALVE WAS STROKED FR0tl CONTROL R00ft 8 SYSTEl1 RETtAtlED TO SERVIE.
l A288733 1 PI 068 301 09/26/841-PI-068-301,1-PI-48-301 PRT PRESSLNtE IlGICATENt TE PRESSI.RE TRANSr!IITER WAS FOUDO OUT READIls LESS THAN 0 IA(ILE 1-PI-68-31K IN BACKLF OF CALIBRATION DUE TO DitIFT.
CSITROL R00ft READDE 1.4 PSIG. RECALIBRATED TE TRAMit1ITTER Al@
j RETURED TO SEltVIE.
i A288737 1 LI 003 107 09/26/84 1-LI-003-107,1-LI-3-107 164 S/G CHAPBEL 2 NARROW - THE SENSE LINiS TO TE TRANSf1ITTER LERE *
! 2 CatFANION NAltROW RANGE Ile.1-LI-3-110-108. FILLED TE SENSE LIIES AfD RETURED TO l REPAIR SERVIE.
! A288745 1 085 84 09/27/841--085-84,RG) BOTT0ft LIGHT SIAITDOWN BA>5C "A" ROD BOTIOrt BISTABLE Gli 0F CAL. RECAL
' git 0lp 2 ROD B4, LIGHT GOES OFF AT 4-1/2 STEPS ROD BOTT0t1 BISTABLE.
Plant Maintenance Summary Page 5 of.5
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INSTRifENT MAINTENAEE FDmLY SurTIARY 10-10-84 PAGE 5 CEN9 FR.CG9 U F194C SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . .
1 OUT Ale COES ON A 2-1/2 STEPS lei!LE INSERTING 3 R(DS.
j A292754 2 PS 003 150A 09/14/84 2-PS-003-150A, min CECK SWITCH UIRING PER A REGUEST WAS MADE TO CEtk TE SWITCH d
ATTACED IMI-134 UIRIlG. SWITCH WIRIls WAS VERIFIED Ale !
I RETWED TO SERVIE. E PROBLEM F0 TAG.
A292755 2 PS 003 1508 09/14/84 2-PS-003-15CS, MIN CECK SWITCH WIRING PER CECK TE SWITCH UIREC. VERIFIED WIRIE ATTACED IMI-134 Ale RETIRED TO SERVICE. HD PROBLEM FOUND.
A292757 2 PS 003 165A 09/14/84 2-PS-003-165A, uIn CECK SWITCH WIRING PER THE PRESSURE SWITCH tmS REG E STED TO ATTACED IMI-134 HAVE WIRING CECK. DECNED TE WIRIls
< Ale RETIRED TO SERVEE. E PROBLEM
- r0uie.
j A292758 2 PS 003 1658 09/14/84 2-PS-003-1658, min CECK SWITCH WIRING PER TE PRESSURE SWITCH IAS REGUESTED TO i ATTACED IMI-134 HAVE WIRING CECK. CIECIED TE WIRING j Ale RETtRED TO SERVEE. le PROLEM i
FOUle.
A293168 2M 090 120 09/04/84 2-RrF090-120,PERFGtM SI 28A.2 DN MONITOR. THE RADIATION MONITOR WAS REtlESTED TO j, HAVE A CALIBRATION CECK. PERFORtED TE jy CALIBRATION CECK Ale RETLRED TO j' SERVICE.
A293169 2 Irl 090 121 09/04/84 2-RfF090-121,PERFGttl SI 281-2 ON 110NITOR THE RADIATION NONITOR WAS teT OPERATIE 1
PROPERLY. PERFORtED TE C0lMT RATE ON TE RADITION IDlITGt Ale RETLRED TO j SERVICE. .i
- A293235 1 FCV 001 25 09/25/841-FCV-001-25, AIR REGILATOR 8 LOWING OUT OF REG. DE AIR REGUL ATOR WAS REPORTED BLOWIls i
BLEED HOLE AIR. REMOVED TE REIRA.ATOR DISASSEFSLED
, Ale RETIGHTENED Ale IETLRED TO SERVICE.
1 j 55 records listed.
l l i l !
- i l
5
T1 7 q.;.
Plant Maintenance Summary l
(Continued)
Modifications Group
.1. 'ECN 5237 - Hot Laundry The fans were test.ran and were overheating. This problem was resolved but the entire system has not been tested. Work will be discontinued until U2C2. refueling outage is completed.
- 2. ECN 5645 - Steam Generator Blowdown' System - Unit 2 Pre-outage instrumentation work was completed. Tie-ins will be completed during U2C2 refueling outage.
- 3. ECN 2768 - Reactor Pressure Vessel Level Indication System (RVLIS) (Unit 2)
Variances initiated during August were completed and returned from the Office of Engineering (OE). Prefabrication work on hangers and installation was completed. The' final workplan (seal table tie-in) was placed in the approval cycle.
All auxiliary building conduit work was completed this month.
Preliminary work in annulus began.
- 4. ECN 2780 - Post Accident Sampling Facility - Unit 2 Minor HVAC hanger work, sealing of the enclosure ~and miscellaneous-tubing work was completed. Preop testing on the HVAC began.
The sampling system is nearing completion, with ceveral devices energized and undergoing functional testing.
- 5. ECN 6055 - Wide Range Pressure Transmitter to the RVLIS Panel Prefabrication activities were completed.
The sampling and air conditioning systems were turned over for vendor functional testing.
- 7. ECN 5024 - Lay-up Water Treatment Prefabrication activities required for the U2C2 refueling outage were completed. Fif teen of the seventy operator valves are completed.
- 8. ECN 5009 - ERCW Piping Change-Out All of the prefabrication work that could be done was completed.
1
,. Plsat Maintenince Summary
~
(Continued)
Modifications Group .
, (Continued)'-
'9. NUREG 0588 5895/ Solenoids .The accessible solenoids valves on.this ECN were changed out. The remaining work will.be completed during U2C2 refueling outage.
6032/H2 Analyzer Relocation All pre-outage work was completed. Final
-relocation will be completed during the U2C2 refueling outage.
5883/ Pressure Switch All pre-outage work was completed Final-Relocation relocation will-be completed during the i U2C2 refueling outage.
6200/ Pressure-transmitter All pre-outage work was completed. Final Relocation relocation will be. completed during the U2C2 refueling outage.
j 10. ECN 6206 - Paint CST "B" f The workplan for this outage activity was written and approved.
- 11. ECN 5373 - Condensate Demin. System Mod.
l The final design utilizing raw cooling water instead of ERCW was approved by Office of Engineering. The workplan was revised and submitted for approval.
A
A workplan to reroute a piping interference during the U2C2 refueling outage was written and submitted for approval.
i 14. ECN 5631 - Hand Rails at CCW Pump Station This work was started and is approximately 50% complete. It will be placed in hold until after the U2C2 refueling outage.
- 15. ECN 5773/6196 - PZE HGR MODS Several meetings were held regarding the final fix. The current plan is to modify nine supports plus as many of the remaining 30 as possible during the U2C2 refueling outage. A workplan for the first nine was i written and submitted for apprcval.
t
+
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. s
-Plant Maintenance Summary (Continued)'
- 3. ,
-Modifications Group (Continued) .
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- 16. L DCR 1739 -'VAACS' Computer Installation Conduit, cable and material installation continued.
- 17. ECN 5198 - Technical Support Center All outside conduit work was completed, cable pulling is 80%. complete.
P250 - DPM 50 intertie is completed to the point of functional testing and termination of the signal cable.
- 18. ECN 5604 - Wells Fargo Alarm 4
t All but one set of alarms are ready for functional testing.
4
- 19. Evacuation Alarms Unit valve' room and the letdown heat exchanger room is completed. Work will be suspended until after the refueling outage. Estimated eight weeks of work remains.
I
- 20. ECN 5770 - Rad Mod Condenser Exhaust The monitor was completed and turned over for functional testing.
i
- 21. ECN 5846 - Remove Relay 62 from Shutdown BD Breakers The last breaker was completed this month.~
- 22. ECN 5865 - Relocate LA-77-124 t Approximately 90% of the conduit is installed.
- 23. ECN 5867 - Fuel Transfer System i
Both upenders have been functional tested. Remaining work is the checkout of the transfer cart and setting the limits.
- 24. ECN 5382 - Temperature Switch Replacement l Conduit, cable and instrument-installation has started.
- 25. ECN 5883 - Replacement of Flow Switches Conduit work commenced this period.
l i
- 26. ECN 6832 - Relocate H2 Analyzer Conduit and cable pulls are 80% complete.
t E
1
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1
,'. TENNESSEE VALLEY AUTHORITY '
,( :
Sequoyah Nuclear Plant
=(' .
L P.' O.} Box 2000 Soddy-Daisy, Tennessee =37379 ,
October 15, 1984
-Nuclear Regulatory Commission Office of Management.Information and Program Control Washington, DC- 20555 Gentlemen:
Enclosed is the September 1984 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant. .
Very-truly yours, TENNESSEE VALLEY AUTHORITY L-
,. P. R. Wallace Plant Manager- -
Enclosure cc (Enclosure):
Director, Region II Director, Office of Management Nuclear Regulatory Commission Information and Program Control Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta Street Washington, DC 20555 (2 copies)
- Suite 3100 Atlanta, GA 30323 (1 copy) INPO Records Center Suite 1500 Director, Office of Inspection 1100 circle 75 Parkway and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
{ Mr. A. Rubio, Director Electric Power Research Institute P. O. Box 10412 Palo' Alto, CA 94304 (1 copy)
Mr. R. C. Goodspeed MNC 461 Westinghouse Electric Corporation P. 0.. Box 355 Pittsburgh, PA 15230 (1 copy)
Y I l
(
An Equal Opportunity Employer