ML20092M620
| ML20092M620 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/31/1984 |
| From: | Dupree D, Eddings M, Wallace P TENNESSEE VALLEY AUTHORITY |
| To: | NRC |
| References | |
| NUDOCS 8407020325 | |
| Download: ML20092M620 (29) | |
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TENNESSEE VALLEY AUTHORITY - DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PL NT - MONTHLY OPERATING REFORT ,
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TO THE - ,, NUCLEAR REGULATORY COMMISSION ' MAY 1, 1984 - MAY 31, 1984 . UNIT 1 , DOCKET NUMBER 50-327 i LICENSE NUMBER DPR i UNIT 2 s-DOCKET NUMBER 50-328-
.. e LICENSE NUMBER-DPR-79 i
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. Operations Susunary . -
. . . . . . . . . . . . . . . . . . . . . . .1 Significant Operational Events . . . . . . . . . . . . . . . . . 1-2 PORV's and Safety Valves Susumary . . .. . . . . . . . . . . . .2 s
, Reports o -Licensee Events . .- .- . .. . . .. . . . . . . . . . . . . . 3-4
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Diesel Generator Failure Reports . . . . . . . . . . . . . 4 1 Special Reports . . . . . .. . . . . . . . . . . . . . . .4 Offsite Dose Calculation Manual. Changes . . . . . . . . . . . .4 M - Operating Data
? Unit 1 . . , . . . . . . . . .. . . . . . . . . . . . . . . . 5-7 h Unit 2 . . . . . . '. . . . . . . . . . . . . . . . . . . . . 8-10
, Plant Maintenance Susunary . . . . . . . . . . . . . . . . . . . . 11-27 I:/
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Operations Summary l s .F7 May, 1984 - F3 The.following~ summary describes the significant operational , activities for-the month of May. In. support of this summary, a
' chronological log of significant events is included in this report.
_ Unit 1 : ! L Unit I was critical for 259.1 hours, produced 172,230 MWH (grosd), resulting.
.in an average ~ hourly gross load of 677,058 kW during the month. There are
-362.55 full power days estimated remaining until the end of cycle.3 fuel. 1 With.a capacity factor of 85 percent, the target EOC exposure would be reached
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1Julyc31, 1985. The capacity factor for the month was 19.6 percent. '
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.There were 2 reactor scrams, no manual shutdowns,'and no power reductions. .
Unit 2-- Unit 2 was critical for 728.6' hours, produced 799,390 MWH (gross), resulting-in an average hourly gross load of 1,091,583 kW during the
.. m month. ._There'are 80.42 full power days estimated remaining until the ,
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end offeycle 2 fuel. With a capacity factor of 85 percent,'the target 1 1EOC exposure would be reached September 3, 1984. The capacity factor ufor;the month was 88.6 percent. _ There was l' reactor scram, no manual shutdowns, and one power reduction during May. Significant Operational-Events Unit 1 Date- -Time Event
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. 05/01/84 0001 The reactor was in mode.5. The forced outage due to the' thimble guide tube leak was continuing.
05/04/84' 2040 The reactor entered mode 4. 05'/05/84 0526 The reactor entered mode 3. p -2329 The reactor entered mode 4. Reduced. pressure to repair the pressurizer relief valves. 05/06/84' 0520 The reactor' entered mode 5.
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ef ^ Significant Operational Events w . Unit 1 @ .~4 { (Continued)
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4, Date Time' Event 4-ES 05/09/84. 0010 The reactor entered mode 4.
, 0541 The reactor entered mode 3.
[\ l 05/10/84-1453 The reactor was taken critical. 1827 The unit was tied on-line.
's 2200 The reactor was at 30% power and
, ~ holding due to steam generator
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, , *La' chemistry.
5 3, 2322 The reactor tripped due to a Lo-Lo
, steam' generator level.
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, s 05/11/84 0850 The reactor was taken critical.
3, 1400 The reactor tripped due to a Lo-Lo M' number 2 steam generator level. t 2 1707 The reactor was taken critical. 1903 The unit was tied on-line. 3: 2200 The reactor was at 30% power, producing 299 MWe and was holding 3g for steam generator chemistry.
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05/12/84 0849 Began 1oad reduction for the turbine
~'A overspeed trip test.
1059 Holding at 29% turbine load because
;y; the feedwater flow regulating valves
.c _ .. were oscillating. Began load
. ascension to 30%.
2200 Holding 30% reactor power for the turbine overspeed trip test. 05/13/84 1032 Began load decrease for the turbine overspeed trip test.
.1232 The turbine was taken off-line for the trip test.
1345 Tied the unit back on-line. 1400 The reactor was at 30% power and holding for steam generator chemistry. 05/14/84 2255 Began power ascension. 05/15/84 1120 The reactor was at 54% power and holding due to problems with the E.H.C. panel. 1340 Began power ascension. 2040 The reactor was at 75% power and was holding for incore/excore
,3 probe calibration.
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E. Significant Operational Events Unit 1 (Continued) Date Time Event 05/18/84 1735 Began power ascension. 2205 The reactor was at 90% power and was holding to verify the reactor coolant system flow calculations. 05/21/84 1640 Began power ascension. 1942 The reactor obtained 100% power. 2234 The reactor tripped due to generator electrical trouble. l05/31/84 1153 The reactor entered mode 2. 1210 The reactor was taken critical. 1650 Tied the generator on-line. 1830 The reactor obtained 30% power, producing 276 MWe. 2359- The reactor was in mode 1 at 30% power, producing 276 MWe and was holding due to steam generator chemistry. s Unit 2 Date Time Event 05/01/84 0001 The reactor was in mode 1 at 100% power, producing 1164 MWe. 05/18/84 2217' Began reducing reactor power to add oil to reactor coolant pump #3. 05/19/84 0730 _The reactor was at 30% power, producing 285 MWe. 1157 The reactor tripped on a Lo-Lo steam _ generator level after MFPT A tripped when the BOP operator. isolated ~the oil pump isolation valve. MFPT B was already off-line.
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.05/20/84- .0328 The reactor was taken critical.
1757' Tied the unit on-line. 1835' The reactor was in mode 1 at 30% power, producing 333 MWe and holding-due to steam. generator chemistry.
L I Significant Operational Events k Unit 2 (Continued) Date Time Event 05/22/84 1648 Began power ascension. 1826 The reactor was at 38% power, producing 405 MWe and was holding for maintenance on LCV-6-106A. 1948 Began power ascension. 05/23/84 0500 'The reactor was holding at 98% power for tests results confirming actual reactor power level. 1238 Began power ascension. L 1400 The reactor obtained 100% power, producing 1160 MWe.
.05/31/84 2359 .The reactor was in mode 1 at 100% reactor power, producing 1160 MWe.
PORV'S and Safety Valves Summary No PORV's or' safety. valves were challenged during the month. Licensee Events and Special Reports The following~ Licensee Event.ReportsL(LER's).were sent during May 1984, to the Nuclear Regulatory Commission. LER DESCRIPTION OF EVENT 1-84023- This event'was discovered at 1309C on April 2, 1984,-while unit 1 was in mode 5 and unit 2 was in mode 1. While performing surveillance instruction (SI) 92,." Remote Shutdown Monitoring Instrumentation - Pressurizer' Pressure Channel Calibrations," the alarm indicating lights on the bistables of the power-operated relief valves (PORV) appeared to be reversed for the correct bistable action. The wiring and operation of the bistables and controller module was investigated and thought to be incorrect. The wiring on the PORVs for both units was modified to this new position. Later, the wiring and bistable operation was reviewed and more thoroughly investigated with additional information and drawings. This additional investigation showed that the PORVs had been modified to an inoperable (reverse from normal) state.
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- Licensce Events end Special Reports
-(Continued) a LER DESCRIPTION OF EVENT i 84023 (Continued)
The PORVs were immediately blocked on the operating unit while both PORVs on both units were rewired and tested , to be in the correct wiring configuration and operating- ! correctly. The surveillance instruction has been revised , to. explain PORV operation and to give details of bistable ; action. The administrative instruction (AI-25) has been revised.to better control wiring changes.
;1-84024f This event was discovered at_13300 on April 13, 1984,
.while unit I was in mode 3. Unit I entered mode 3 at 0950C on April 12, 1984.
A limiting condition for operation.(LCO) in the technical f specifications was not met and a change from mode 4 (less than 350 degrees F) to: mode 3 (greater than 350 degrees F) > was made. A level transmitter (LT) for steam generator ,
' number one'was inoperable. The-associated bistables for :
.the. level transmitter were already tripped due to another LCO. Personnel.fsiled to realize that more than one LCO ,
applied to_this LT. The LCO.that was recognized allowed j operation until'the next required functional test in the applicable mode. Another'LCO was overlooked, and it did i not, permit a mode change. 1-84025 At,1500C on April 15, 1984, sampling of the reactor coolant : system (RCS) for boron-concentration was initiated. This '
. sampling caused pressurizer level transmitter 1-LT-68-320 to become inoperable due to a modification during the ,
previous outage which: routed the sense line from the low , sideLtap of.the instrument. This event was detected at- ' 1715C after a' change from mode 3'to mode 2 was completed.
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Two LCOs;are involved with this event. LCO 3.3.1.1 is
- applicable in mode 2, and LCO 3.0.4 is not applicable.
- After mode'2 was-reached, the bistable was tripped at 1748C.with the instrument discovered inoperable at 1715C.
LCO 3.3.3.7 is for accident monitoring instrumentation and allows seven days to return the: instrument operable, but * {3.0.4 is applicable (i.e., no mode change with instrument-inoperable). .LCO 3.'3.3.7 is applicable for modes 1, 2, and
- 3. and the instrument should have been made operable prior
^ to mode change. The cause of this event has been attributed , to the failure of the operator to realize LT-68-320 as t inoperable.
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1-84026' At 2148 on April 17, 1984, unit I experienced a reactor trip. Unit I was in mode 1 at 30% reactor power just prior to the event. A turbine trip occurred due to failure of a generator stator cooling water pump. Subsequent Lo-Lo level in steam ; generator number three resulted in a reactor trip from
= approximately 18% reactor power. Unit I stabilized at 547 )
~ degrees F following the reactor trip. ;
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(Continued) s . LER - DESCRIPTION OF EVENT
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84027- 'This LER involves three separate incidents. .The first containment ventilation isolation (CVI) occurred at 1642C on April'20, 1984 while. unit 1 was in-mode 5. The second CVI occurrediat 1055C on April 25, 1984 and the third CVI
. occurred at 1116C on April 25, 1984.while unit I was in mode 5.-
-A ! high radiation alarm was actuated which caused a
. containment ventilation isolation (CVI) to occur.
' Investigation revealed that.a. voltage spike occurred as a result of electromagne;ic interference (EMI) which was generated by slippage of the filter paper in two incidents and stray signals in.another incident. Radiation levels
_ . were not above normal during this time. 1The inadvertent high radiation alarm was -ret and the monitor was returned to service. A time %.ey is being added to the actuation signal to allow e ime fur spikes to decay.
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1-84028 The-ABI occurred.at 2358C on April 17, 1984, while unit I was in mode 3. A high radiation alarm was actuated which caused an auxiliary building isolation (ABI) to occur. Investigation
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revealed that personnel were placing boric acid. evaporator
'B'~in service and draining the vent header at the same time that the volume. control tank was being burped (vented).
This simultaneous _ action increased.the. vent header pressure and caused excessive gas to be vented causing the auxiliary building ventilation system to isolate.
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1-84029 This LER involves three separate incidents. The first-auxiliary building isolation (ABI)- occurred at 1205C on
!May 7, 1984,'while unit I was in mode 5 and unit 2 was in mode 1. The second ABI occurred at 2341C on May 7, 1984, while unit I was in mode 5 and unit 2 was in mode 1. The third ABI occurred at 0828C on May 8,~ 1984, while unit I
'was-in mode 5 and unit 2 was in mode 1.
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A.high radiation alarm was actuated which caused an . auxiliary
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1 building. isolation (ABI) to occur. Investigation revealed that in two incidents, because detector output is not stable and the ' radiation level is so close to the setpoint, normal fluctuations of the detector tripped the alarm. In another incident, the power source for a radiatin monitor was transferred from one board to another which caused an alarm. y Radiation. levels were not above normal during this time.
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'Lictaten Events and Special Reports
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_(Continued) LER DESCRIPTION OF EVENT
.1-84030' On April 19, 1984, unit I was in mode 1 (2235 psig, 558 degrees F) at 30% reactor power with maintenance personnel cleaning the incore detector thimble tubes. A high pressure connection'on the thimble tube at the seal table failed resulting in a reactor coolant system pressure boundary leak of approximately 25-35 gpm and ejection of one incore detector. thimble tube at 2100 CST.
Diesel-Generator Failure Reports There were no diesel-generator failure reports transmitted during the Special Reports
- There were no'special' reports transmitted during the month.
Offsite Dose Calculation Manual Changes There were not any changes to the Sequoyah-Nuclear Plant ODCM during
, : the month.
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. OPERATING DATA REPORT DOCKET NO. 50-327 DATE JUNE 11,1984 COMPLETED BY M. G. EDDINGS TELEPHONE (615) 870-6196 OPERATING STATUS 1". UNIT-NAME: SEQUOYAH-NUCLEAR PLANT, UNIT 1 NOTES:
12.iREPORT PERIOD: MAY'1984
- 3. LICENSED.THERMALzPOWER(MWT): 3411.0
- 4. NAMEPLATE RATING (GROSS 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):
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1148.0-
- 8. IF-_ CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3'THROUGH'7)SINCE LAST REPORT, GIVE REASONS:_______-___-
u________-_________ _-_________-___-_-________-______-
'9'.- POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):________
- 10. . REASONS FOR RESTRICTIONS,IF ANY:__- _______-_______-_
m_. _=-_____-__-____-- ____________-______________- THIS MONTH YR.-TO-DATE CUMULATIVE
.11.fHOURS IN REPORTING. PERIOD. 744.00 3647.00 25584.00 L12J NUMBER OF HOURS REACTOR WAS CRITICAL 259.10 1360.90 15002.46
- 13. REACTOR. RESERVE SHUTDOWN HOURS. 0.00 0.00 0.00 14.HHOURS GENERATOR ON-LINE 254.40 1254.50 15367.65 15.~" UNIT' RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS' THERMAL-ENERGY GENERATED (MWH) 565213.61 3480443.28 48972293.58
;17., GROSS ELECTRICAL ENERGY. GEN. (MWH) 172230.00 1139920.00 16519.056.00 118. NET. ELECTRICAL ENERGY GENERATED (MWH) 160030.00 1082181.00 15359109.00
- 19.: UNIT SERVICE FACTOR 34.19 34.40 60.07 E201 UNITJAVAILABILITY FACTOR.
' ~ 34.19 34.40 60.07
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 18.74 25.85 54.00
'22. UNIT ~ CAPACITY FACTOR (USING DER NET) 18.74 25.GS. 54.00 E23W. UNIT FORCED OUTAGE RATE 65.75 45.11 21.14 24'. SHUTDOWNS-SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH): . 25. IF'GHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
NOTE THAT THE THE YR.-TO-DTTE AND CUMULATIVEoVALUES HAVE BEEN UPDATED.
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( - - - - UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME ' Sequoyah One
'DATE June 4. 1984 COMPLETED BY M. G.-Eddings REPORT MONTH MAY TELEPHONE' (615) 870-6249 q r .
- 57 "e Eb Licensee % Cause & Corrective-No. .Date y, O's. @ ]O5 Event $1 E$ Action to
@ 2S 2 5p" Report . !' Mi 8. 3 Prevent Recurrence
.-- + 5* l@$ NU @G g o' 7 840419 F 234.5 A 4 . Thimble guide tube leak at seal table.
Loop #2 Lo-Lo generator level.
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8 840510 F 19.7 .A 3 f -9 840521 S 1.2 B 9 Turbine overspeed trip test. 10 840521 F 234.2 A 3 Generator electrical trouble, first out. t 1 2 3 4 - F: Forced Reason: . Method: Exhibit G-Instructions 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 G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source
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4 .t f a AVERAGE DAILY UNIT POWER LEVEL l DOCKET NO. 50-327 UNIT secunyah One DATE June 4, 1984 COMPLETED BY M. Eddings TELEPHONE (615) 870-6248 1 MONTH MAY, 1984
-- f DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
-(MWe-Net) (MWe-Net)
I N/A 17 - 834.2 2 N/A 18 858.2 3 N/A 19 997.2
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4 N/A 20 1002.5
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5 'N/A 21 99'T.5
'I 6 N/A 22 ~ N/A
7 N/A 23 N/A 8 N/A - 24 N/A
'9 N/A 25 N/A 10 239.5 26 N/A 11 244.1 27 N/A 12 263.3 28 N/A 13 221.3 29 N/A 14 249.0 30 N/A
. 15 533.2 31 63.3 .
16 801.5 l-
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INSTRUCTIONS .
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On this format, . list' the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
. . (9/77)
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OPERATING DATA REPORT DOCKET NO. 50-328 L DATE JUNE 11,1984 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6248 OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 22 REPORT PERIOD: MAY 1 THRU 31,1934
- 3. LICENSED THERMAL POWER (MWT): 3411.0
% NAMEPLATE RATING (GROSS MWE): 1220.6 S. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 1133.0
- 7. MAXIMUM DEPENDADLE CAPACITY (NET MWE): 1148.0
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:__-_-____--_
- 9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):_------_.
- 10. REASONS FOR RESTRICTIONS,IF ANY:...___--_-_-__-----------
THIS MONTH YR.-TO-DATE CUMULATIVE !11. HOURS IN REPORTING PERIOD 744.00 3647.00 17544.00 il2. NUMBER OF HOURS REACTOR WAS CRITICAL 723.60 3571.40 13932.47
'156 REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 .14. HOURS OENERATOR ON-LINE 714.00 3552.60 13706.92
' 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 L16. GROSS THERMAL ENERGY GENERATED (MWH) 2287795.06 11885954.99 44304022.80
- 17. . GROSS ELECTRICAL ENERGY GEN. (MWH) 779390.00 4100910.00 15132850.00 18; NET ELECTRICAL ENERGY GENERATED (MWH) 748394.00 3951797.00 14569534.60
- 19. UNIT SERVICE FACTOR 95.97 97.41 78.10 20L UNIT AVAILABILITY FACTOR 95.97 97.41 78.13
-21. UNIT CAPACITY FACTOR (USING MDC NET) 87.62 94.39 72.34
- 22. UNIT JAPACITY FACTOR (USING DER NET) 87.62 94.39 72.34
- 23. UNIT FORCED OUTAGE RATE 4.03 2.59 7.62 J24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
_Repeligg[M, o_difiqa,tio_q,,_ Cyq1_e_,2_@_e_1_- september _3,_118L ._aPProximaI;ely_.51_dayh__ 25: IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: t NOTE THAT THE 1HE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED. UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 UNIT NAME Sequoyah Two DATE . June 11. 1984 '! COMPLETED BY D. c. Dupree REPORT MONTH MAY TELEPHONE (615) 870-6248
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- E7 "c C pt Licensee Cause.& Corrective Mo. Date E O$ 8 '825 Event 5% E*e Action to
@ 2$ @ f"* Report d M] 2, j -
Prevent Recurrence 5~ ??5s ?d " $* u 2 840518 F 0 B 5 , Drop load. to add oil to #3 R.C.P. 3 840519 F 30.0 G 3 U. O. ~ tripped oil ptimp on "A" M.F.P.T. while .
"B" M.F.P.T, was out of service.
.L 'P 9 1 2 3 4 - F: Forced Reason: Method: Exhibit G-Instructions 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 G-Operational Error (Explain) 9-Other 5 (9/77) H-Other (Explain) Exhibit I-Same Source
L 0 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT .Sequoyah Two DATE June 11, 1984 COMPLETED BY D. C. Dupree ! TELEPHONE (615) 870-6248 ; MONTH May, 1984 l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net)
- 1. 1136.0 17 . 1121.8 2 1131.0 18 1122.0 3 1130.0 19 269.0 4 - 1129.0 20 68.0 ,
l 5 1129.0 21 7 295,.,0 6- '1126.0 22 360.B' 7 1125.0 23 1085.0 8- 1126.0 24 1131.0 9 1126.0 25 1131.0- ~10 1125.0 26 '1131.0 11 ~ 1122.0 27 1130.0 12 1119.0 28 1133.0 13 '1120.0 29 '1131.0 14 1119.1 30 1132.0 15 1119.0 31- 1131.0 , 16 1118.0 INSTRUCTIONS. .
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On' th'is _ format, . list the everage daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.
. . (9/77)
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Plsnt Maintensnca Summary The following significant maintenance items were completed during the month of May 1984: Mechanical Maintenance
- 1. Completed work on the D-12 thimble failure in the unit #1 incore instrument room seal table.
- 2. Replaced the bad oil seal, gear reducer,- and motor seals on the unit #1 MFPT "1B" turning gear.
- 3. Repaired the solenoid valves on 1-FCV-63-41 and -42.
- 4. "1C" cooling tower lift pump was reported to have no bearing lube water flow. _ We blew out the bearing lube water lines to establish
-good flow and the instrument section repaired a flowmeter.
- 5. ' Rebuilt the "2A-A" boric acid transfer pump, replacing the bearing, shaft, and seals.
- 6. In'talled s drain papers in the unit.#2 lower ice condenser after the lower inlet doors were blown open and remained open for 2 to~3 hours.
- 7. Made repairs to the unit #1 main generator. Sent the rotor and bearing (#11) to Muscle Shoals to be remachined. Shipped the permanent magnet generator (PMG) to Westinghouse to replace the magnets and have it magnetized. After reinstalling-the rotor,
#11 bearing, and the coupling, bolt #17 in the coupling galled.
Repulled the rotor and stator and replaced the galled bolt.
- 8. Replaced a broken Masonellan Camflex operator on 1-FCV-3-329A with a spare operator borrowed from unit #2.
-9. Installed Jimmy plates over door latches on eight doors in the
. control and auxiliary buildings per NRC requirements.
- 10. Repaired relief valve 1-VLV-67-582D which was broken at the nipple on the upper containment cooler "D".
- 11. Rebuilt.the "2B-B" high pressure fire protection pump replacing the coupling and shaft which were found to be broken.
- 12. Furmanited Non-CSSC valves on systems #1, 3, and 6 (both units) and manways #19 and 23 on the MSR piping on unit #2. Furmanited CSSC valves 2-VLV-3-361A and 2-VLV-1-150.
- 13. . Performed section XI maintenance on 1-FCV-1-182 by replacing the Bonnet gasket.
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Plant Maintenance Stsnaary? Electrical Mainteriance
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DATE. CtWOENT. . . . . .FAILLME DESCRIPTIIDE...... CAUSE OF FAILlRE......... - ' CORRECTIVE ACTION P" ...'
.. l . o f.4 PRONi....
O & 18 1-ffrRS-082-1A/ - CECK LLBE DIL PREVENTATIVE 11AINTEMA6CE INSPECTED PRIf1AltY LEADS NOE 2 CIRCIA.ATING PLN CONTROL AND NAS GOOD CLEARANCE TRNRIFIBM!R PRIMARY LEADS , FOR GotB CLFARAICE , 05-03 1-PJV-001-0022 REfWUE GROLDO ON VITAL ROOF LEANED MO WATER CLEMED WATER'00T 0F . . H0tE
~ ~ BATTERY BOARO 144 AfD ORIp?ED IMTG JLACTION BOX JUNCTION BOX 2042
, 86 I ,
- 05-05 1-LED-095-SC
- H TEf50tARY CABLE WAS IM D M5 CABLE C0telECTOR WAS REPLACED CRDM H5 CABLE IN NOE 5 LMTIL ORIGINAL CABLE FLA L OF 80 RATED WATER PLACE OF TEPPORARY CAME l COLLD BE REPAIRED AlO CAUSIfC CABLE TO GR0lae -
REIDETALLED M O NAVE RESISTANCE IN - COIL
- 05-06 0-1CV-67-019/ YALVE WILL NOT OPEN ALL DIRTL .
CLEAED VALVE NONE .! i TE WAY 3 05-06 1-FSV-313-0223 REMOYE GROLDO ON VITAL WATER INTRUSION CLEAE0 TERMINAL STRIP NOE 84TTERY 80ARO 1 FUSE D3 AND REPLACED DIODE
- CLEANED LIMIT SWITCH AfC l, VALVE
!U ! ' 05-08 1-FD-31C-0904 BLOLM FUSE LIDBC ACTIVATED PYROTRONICS REPLACED LINKS NOE l PAIEL 05-08 1-FD-313-0905 REPLACE FUBABLE lib 8(S . ACTIVATED BY PYROTRONICS REPLACED FUSA8LE LI>t(S NONE i PAIEL i ! 05-09 2-fRR8-002-2A/ CECK LLBE OIL - PREVENTATIVE f1AINTENANCE INSPECTED PRIMARY LEADS . NONE
- 3 CIRCLLATING PLW CONTROL - HAD GOOD CLEARANCE.
j TRANSFERfER PRIf1ARY LEADS FOR GOOD CLEARANCE f ! 05-09 2-fRRB-082-2A/ CECK LLBE DIL PREVDITATIVE f1AINTENANCE INSPECTED PRIf1ARY LEADS. NOE ! 2 CIRCIA.ATIls PLN CONTROL NAS GOOD CLEARANCE i TRANSFORfER PRIMARY LEADS
- FOR GOOD CLEARANCE
! 05-09 1-ffTRB-002-1A/ . CECK LLBE OIL PREVENTATIVE f1AINTENANCE INSPECTED PRIf1ARY LEADS NONE 3 CIRCLLATING PtN CONTROL MO FOUFO GOOD CLEARANE TRANSFORfER PRIf1ARY LEADS ! FOR GOOD CLEARMEE l
Plant' Maintenance Sunanary
~
. . Electrical Maintenance Page 2 of 4 DATE. CorPOENT..... . FAILLRE DESCRIPTION...... CAUSE CF FAILURE. . . . . . . . . - CORRECTIVE ACTION........ PRON....
05-10 2-HICK-234-223 CECK #1AIN DRAIN LIE FAIA.TY TEMERTURE REPLACED TEMERTLRE ' HONE P TEWERTLRE CMTRS.LER MO ~ CNTROLLIR CONTROLLER FUSES (DI CIRCUIT 1 223 P.R. , 05-10 0-BATB-250-QVJ OXIDATION ON BATTERIES PREVENTIVE 11AINTANCE CLEANED OXIDATION FRON HONE BATTERIES 05-10 1-11TRB-082-1B/ CECK LUBE DIL PREVENTATIVE 11AINTENANCE INSPECTED PRIf1ARY LEADS. HOE 2 CIRCIA.ATING PtFF CONTROL HAD C000 CLEARANCE TRANSFORER PRIl1ARY LFADS FOR GOOD CLEARANCE 05-10 2-f1TRB-002-028 CECK LUBE OIL - PREVENTATI4E t1AINTENANCE INSPECTED CONTROL HOE 3 CIRCULATING Plfp CONTROL TRANSFORTER PRIl1ARY TRANSFORfER PRIMARY LEADS LEADS, HAD GOOD CLEARNCE t FOR GOOD CLEARANCE I 05-11 0-iMTB-250-09X CLEAN OXIDATION ON PREVENTATIVE f1AINTENANCE CLEAED BATTERIES NONE T BA1TERIES 12,19,3,9 N O l, % i 705-11 0-BATB-250-0GW CLEAN OXIDATION OFF PREVENTATIVE f1AINTEANCE CLEANED BATTERIES NOE T BATTERIES 2,10 NO 42 I 05-11 0-BATB-250-03Y CLEAN OXIDATION OFF PREVENTATIVE 11AINTENANCE CLEMED BATTERIES HDE T BATTERIES 3,4,8,16,31,41,45 NO 58 05-23 1-fWOP-001 ISOLATION VALVE STEAM TORGUE SWITCH OUT OF ADJUSTED TORQUE SUITCH 1-84-187 i B FLOW TO AUX. FW NOT. ADJUSTrB4T PER ril 11.2 OPERATIONS WORKING PROPERLY STROKED VALVE DErtSTRATED OPERABILITY OF VALLE RETURED TO SERVICE , 05-23 1-FEV-062-0085 CHARGING FLOW RCS CONTROL ACTUATOR art 1 WAS LOOSE ON ADJUSTED ACTUATOR arf 1 #O N0tE POSITION SWITCH LIl1IT SHAFT PREVENTING LIf1ITS CECKED FOR PROPER i LIGHTS lERE LOT SHOWING FR0ft FW(ING UP OPERATION ACTUAL VALVE POSITION 05-23 0-1.S-032-90-9 AUX AIR COWRESSOR B-B DIAtING t1AINTANCE OF OTER REPLACED DIL LEVEL SWITCH NONE LOW OIL LEVEL SWITCH EGUIPl1ENT THIS SWITCH WAS
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i: a Plant Maintensnce Summary
- (Continued)
Instrument Maintenance
- 1. lDuring monthly testing of UHI level switches, we found all switches to be within. Technical Specification Tolerance and only two switches on unit 1-out.of the desired tolerance of 2" H 0. We have now 2
. prepared a DCR;to replace these switches due to the unreliability that
,has been experienced.
- 2. The:No. 3 Heater Drain. Tank Level Control Valves 1 and 2, LCV-6-106A
& B,- were set for split- range operation instead of. the parallel operation they had.previously been set to. . This improved the
-stability of the No. 3 Heater Drain Tank flow and therefore helped
, .to. improve the feedwater' flow and steam generator level control.
UNIT 1
- 1. Completed ' the NIS power range calibrations required as a result of startup testing. for the new core.
' 2. Completed all required initial calibrations for the reactor vessel
' level indication system. Returned to service ~on May 29, 1984.
~
- 3. During the. month there were two.(2)' failures of the containment sump' level transmitters as follows:
- a. 1-LT-63-179 failed on May 10, reading. greater than 6 percent de'viation during performance of SI-2. Mechanics found the 3 output to be approximately 6 percent high over full range.
-Transmitter was recalibrate'd and returned to service. No
,. " top.'off" was performed. (MR #A282500,-PRO #1-84-188) ts -
'(Curtis Lagasse)
. uc :b. .1-LT-63-179 failed on May 21, reading low approximately 2 percent. Mechanics found the output of the transmitter to be
-approximately 0.7 mA low over entire range. Transmitter was recalibrated by exercising.the " span" and "zero" adjustments and returned to service. Possible oxide buildup on the "zero" and " span" pots. No ' " top of f" was performed.
, (MR #A283141,
= PRO #1-84-198) (R. G. Lewis).
- 4. .During'the-month ~there-were four (4) ABI's attributed to spurious
-r -signals. lOne=(1) on'the RM-90-101-monitor during a transfer of'
. voltage on the same power supply and the other three (3) from the
~
i
~~
high-background levels of the' spent fuel pit. There was.one + combination ABI~and CVI on unit 1-during the loss of a vital inverter when-the reactor ~ tripped.
' ~
i
' Additional modifications'are being requested by CATEGORY D FCR 2406
- to operate with a upper-leve1~discrimator set below the max preamplifier pulse height.
-1 4 E I._m
^
'Plent Maintentnca Summ ry (Continued)
' Instrument Maintenance
'UNITc2^
1.- -Rod position indicator H-6 was erratic and indicating a high resistance in'the connector. Repair was achieved by applying voltage to the field cable and connector. (2. Replaced the.MOOG Servo valve on_the turbine throttle valve No. 3 t, cand verified correct stroke. 4
, .3. . Completed the. modification to the square root converters on safety related flow loops to install a voltage regulation circuit.
- 4. The Terry-Turb'ine. tripped on turbine overspeed during a SI performance. A problem was found with SC-46-57 and FIC-46-57.
Replaced the dropping resistor and returned the turbine to service. Plant Maintenance Summary Instrument Maintenance Page 1 of 5 INSTRLFENT MAINTEMAKE IDfTtLY RffMRY 06-06-84 - PAGE 1 i UE' tgt.CIWp U FLDC SYS annasun DATE. . . . DESCRIPTIEM. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTI(M. . . .. . . . . . . . . . . . . . . . . . . A097553 2 FI 003 6 05/25/94 2fI-40@-6,IDOICATING If9R0PERLY. LPON INWSTIGATION TE FLOW TRANSMITTER t WAS FOUpc OUT OF CALBRATION DE TO j NATIRAL ORIFT. TE DOICATOR WAS ' - 4 RECALIBRATED AIC RETtRDED TO SERVICE. ! A110942 ,1 FCV 003 AS 05/25/941-fCV-405-41, UALVE DOESN'T RESP 0lO PROPOLY AT PACKING TOO TIGHT ON YALVE STErL 4 30E LGAD A00 WILL 90 GO IN AUTO. ADalSTED PACKING CLENED PILOT YALVE ON i POSITIGER REPLACED AIR StPPLY i oma ATOR, S RESTORED UALVE. A233327 1 FT 063 914 06/01/841-fT-063-91A,1-FT-43-914, REPLACE TUSE FITTINGS, LPON INVESTIGATION TE TLBIIC FITTIBCS 1 VENT PLUES AfD itBIls AS REGIRED TO ELIMINATE ERE FOLSO LOOSE DLE TO CYCLIC FATIGE. i LEANS TE FITTItCS WERE TIGNTEED ABC j TRAMBnITTER WAS LEFT IN SERVICE. A238091 1 PCV 001 5 05/03/841-fCV-401-5,91TN 151-6 IN AUTO A!G 1-f!C-1-6A TE GASNET ON TE POSITIOER WAS FOUle j IN AU10. TIE POSITIEM DOICATIlE LIGHTS StelED BAD DE TO CYCLIC FATIGLE CAUSIIC _TE j i RED Ale GREEN (CBI TEIR 0L40. ul#RDu AIR LEAK. REPLACED 1E GASNET, ADJUSTED I M TE CLNtRENT TO PRES 8UtE CONYERTER Ale RETINtED TO SDtVICE. A238242 0 02R 043 5000 05/07/84 0-03-043-5000,02 ANALYZDt SIEWING ( 01, THERE IlOICATOR LAMPS BAD & OUT OF ADJUSTFENT. SIGR.D BE .XRE KDG EF A READDC. INESTIGATE READalSTED & REPLACED LArpS. ! AfD REPAIR. ; i A245631 1 PCV 001 12 05/04/841-fCV-001-12,UALVE POSITISElt IS LEAMDC AIR, TE GASMET ON TE POSITIONER WAS FOLDO l BAD GASNET (M REG. l#ERE AIR cores IN. al#RDu TO BE BAD DUE TD CYCLIC FATIGLE. l REPLACED TE GASKET #6 RETURED TO SERVICE. A2 U061 1 L1:V 003 171 05/10/841-{.CV-403-171 TO LO(P #4 S/G DOES TOT CONTROL AT TE SET POINT DIAL WAS OUT OF SETPOINT, CONTIPRES TO FEED S/G AFTDt LEVEL IN CALIBRATION DUE TO DRIFT. RECALIBRATED
- S/G DCREAEES PAST SETPOINT. IIMSTIGATE AND TE SET POINT DIAL, WRIFIED PROPER j
! REPAIR. OPERATI0li AIG RETLNt>ED TO SERVICE. I A2W614 2 FT 003 48A 05/17/84 2fT-003-6,PERFIRM CHAl#EL CALIBRATION ON TE TE TRANSMITTER WAS FOUle OUT OF F-3-414 LOOP. CALIBRATION DE TO HATURAL DRIFT. RECALI8 RATED TE TRAlerlITTER, VERIFIED i j CALIBRATION OF THE CUtRENT TO CLNtRENT I fEIllA.E VERIFIED OPERATION AIG RETURED TO SERVICE. .
- A2&615 2 FT 003 90A 05/17/84 2-FT-003-904,PEltFtutti CHAl#EL CALIBRATION ON TE A PROBLEM UAS REPORTED WITH THIS LOOP. I F-3-90 LOOP. A C0f9LETE LOOP CECK WAS MADE AlO NO PROBLEM UAS FOUPO.
. A2W616 2 003 age 05/18/94 2--003-4BS. PERFORM CALIBRATION OF TE U2 F-3-488 UP0H INVESTIGATION TE FLOW TRANSMITTER FEEDUATER FLOW Lotp. WAS FDL40 OUT OF CALBRATION DLE TO l
- HATuRAL DRIFT. T>E mANSnma uAS l RECALIBRATED Ale RETUtlED TO SERVICE.
I -,,_._ --~___ _, _ _, . _ _ . . _ _ _ . _ _ , _ _ _ . . _ _ _ . _ _ _ . . . . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Plant Maintenance Summary
, Instrument Maintenance Page 2 of 5 ! INSTRLFENT MAINTEMMCE lENTM.Y SLM1ARY 06-06-84 PAGE 2
'. CG9 j ret.COM U FUNC SYS ADDRESS. DATE. . . . DESCR IPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . . $ A247622 2 FI 003 48A 05/24/84 2-FI-403-4BA,IleICATDR READING HIGH0t THAN "B" INDICATOR OUT OF CAL 1BitATION. I CHM 8EL VERIFY CAL. .RECALIBRATED FI-3-eA, A281530 2 FI 003 358 05/20/94 2-FI-003-350 De!CATtR READ 6 LOW PER CH49 EEL TE FLOW TRANSMITTER WAS FIR 3e OUT OF DECK TRIP ASSOCIATED BISTABLES PER INSTRUCTION CALIBRATION CAUSIls 16E FAILLNtE. (TI-67h INWESTIGATE Ale REPAIR AS REGUIRED AfG RECALIBRATED TE TRADEMITTER, OLED D0 lad i RETLRN TO DERMAL. TE ASSOCIATED SOGE LDES Afe RETLRIED l TU SERVICE. I A281543 2 PT 003 1 05/30/84 2-PT-003-1,PT FAILID HIGH CAUSIls FEED PUW TO WATER HAD CONDENSED BtTO .AACTION BOX AT j BACK DOL 44 IN AUTO - INVESTIGATE & REPAIR TRANSMITTER FROM A 81EAM LEAK OUDtEAD. l DRIED OUT .ASCTION BOX, REPLACED TEST l BLOCK, & RECALIBRATED TRANBMITTER. A281544 2 PI 001 33 05/30/84 2-9I-001-33,DGICATGt READING HIGH TRANSMITTER DUT OF C4.. RECAL l TRANSMITTER-A281646 1 FI 003 163 05/31/841-fI-003-163,FI SHOWS 40 GPM WITH A AFM PUN OFF FT-3-163 OUT OF CAL. RECAL. FT-3-163. A281647 1 FI 003 155 05/31/841-FI-403-155, FLOW IldDICATINt SHOWS 90 GPM WITH A T E FLOW TRANSMITTER WAS FOUlO OUT OF AFU PLFF OFF CALIBRATION DUE TO SETPOINT DRIFT. i RECALIBRATED TE TRAMiMITTER, BACK M' FILLED TE SENSE LIlES AfC RETLNtlED TD SERVICE.
- A281752 1 15 068 331 05/16/841-TS-068-331,RECALIBRATE TO IIS M)RMAL SETPOINT TE SWITCH WAS OUT OF CALIBRATION TO j OF 140 DEGREES F. TE SETPOINT WAS CHADEED PER 210F WHICH WAS BRIICING IN TE ALARtl IN
] TACF 1-84-062-68, tR A281755 WILL CLEAR TACF. TE CONTROL ROOM DUE TO CALIBRATION l DRIFT. RECALIBRATED TE SWITCH TO 140F . Als RETURIED TO SEltVICE. l A281753 1 TS 068 330 05/16/841-TS-068-330,RECALIBRATE 10 IIS letMAL SETPOINT TNE SWITCH WAS OUT OF CALIBRATION TO - l OF 140 DEGREES F. TE SETPOINT WAS CHADEED PER 210F WHICH WAS BRIICDC IN TE ALARfl IN ,, ) TACF 1-84-062-68. FNt A281755 WILL CLEAR TACF. TE CONTROL ROOM DLE TO CALIBRATION f DRIFT. REEALIBRATED TE SWITCH TD 140F { I' ate RETURNED TO SERVICE. A281754 1 15 068 329 05/16/841-TS-068-329,RECALIBRATE TO Il letl14L SETPOINT TE SWITCH WAS OUT OF CALIBRATION TO ! 0F 140 DEGREES F. TE SETPOINT WAS CHAICED PER 210F WHICN MAS BRDCDC IN TE ALARM IN l TACF 1-84-062-68. f5t A281755 WILL CLEAR TACF. THE CONTROL ROOM DUE TO CALIBRATION ! DRIFT. RECALIBRATED TE SWITCH TO 140F l AFD RETURED TO SERVEE. A281755 1 15 068 378 05/16/84 1-TS-068-328,RECALIBRATE TO IIS DORnAL SETPOINT TE SWITDI WAS OUT OF CALIBRATION TO OF 140 DEGREES F. CLEM TACF 1-84-062-68 UEN 210F WHICH WAS BRINGDC TE ALARM IN TE : y 4 fft'S A281755, A281752, A281753, Ale A281754 ARE CONTROL ROOM DLE TO CRLIBRATION DRIFT. CIFFLETED. RECALIBRATED TE SWIlCH TO 140F AfD 4 RETURED TO SERVICE. A282045 1 FM 003 488 05/31/841-FFt-003-488, LOOP 2 FW FLOW CONVERTER, LOW IT WAS FOUIC THAT TE COIL AIO REED i SIGNAL CUTtFF CIRCUIT IS STICKING. nWRDu SWITCES lERE BAD CAISIls TtE FAIListE.
Plant' Maintenance Summary Instrument Maintenance Page 3 of 5 INSTRtfENT FIAINTEMMCE femLY SLN1ARY 06-06-84 PAGE 3 CG9 rm. Corp U Ft9C SYS ADDRESS. DATE. . . . DESCR IP TION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . . . TE REE0 SWITCES NO COIL LERE REPLACED, PROPER OPERATION WAS VERIFIED
, RECALIBRATED AIC TE PRDIFIER WAS
.. RETIRED TO SERVICE.
A282092 2 TS 062 245 05/04/84 2-T9-062-245,CALISRATE TErp. SWITCH HIGH IT WAS FOLAC THAT TE SETPOINTS ON TE SETPOINT IS 175 DEEREES, IPOICATION IS 177 SWITCH LERE OUT OF TELERANCE DUE TO recemL NWRDu NATURAL DRIFT. TE 1ErpERAT15tE SWITCH WAS RECALIBRATED ABC RETtstED TO SERVICE. A282323 1 LR 003 43P002 05/18/841-LR-003-47002, GREEN PEN IS FAILED HI, REPAIR TE VALVE WHICH PERf11TTED FLOW TO TE AS REGUIRED. HIGH SIDE OF TRANSf1ITTER WAS FDLNG CLOSED CAUSING THE FAILLNtE. OPEED TE - VALVE, VERIFIED OPERATICMS #6 RETIRIED TO SERVICE. A283101 1 TI 068 319 05/14/841-TI-068-319,RCS PREZ HAS HIGH ALARf1 OH ON INVESTIGATION ON 1E TE@ERATlNtE TI-69-319 F(R LIeUID TErpERATLRE ItOICATOR. f10DIFIER HAD DRIFTED HIGH DUE TO MATtRAL h b DRIFT. RECALIBRATED TE 110DIFIER #O Y RETURED TO SERVICE. A283141 1 LI 063 179 05/23/841-LI-063-179, LEVEL ItBICA1DR FAILED LOW, REPAIR. TE TRANSf1ITTER WAS (Eli 0F CALIBRATION . DtE TO NATURAL DRIFT IAiICN CALED TE LEVEL IlOICATOR TO FAIL LOU. TE LEVEL TRANSf1ITTER WAS RECALIBRATED MO . RETURED TO SERVICE. ! A285343 1 LT 068 339 05/07/841-LT-068-339, VERIFY CALIBRATION OF 1-LT-68-339 THE LEVEL TRANSt1ITTER WAS FOUIC OUT OF PER If1I-99, CC 5. 4. RECALIBRATE #0/tR REPAIR CALIBRATION DUE TO NATURAL DRIFT. TE IF ECESSARY. LEVEL TRANG1ITTER WAS RECALIBRATED NO lf RETURifD TO SERVICE. A286504 1 PCV 001 5 05/03/841-PCV-001-5 AIR IS BLDWING FR0ft GAESET AREA 0F TE GASKET ON TE POSISTICER WAS FOLDO ; TE AIR REGtLATOR FGt TritS PORV. al@RDu BAO DUE TO CYCLIC FATIGUE CAUSING TE C OIL LEAK. REPLACED 1E GASKET, ADJUSTED b TE CURRENT TO PRESSLRE CONVERTER #6 RETIRito TO SERVICE. A286641 0 Rrl 090 118 05/04/84 0-Rit-090-118, RAD PENITOR APPEARS TO HA'd A BAD POER SLPPLY IN llP-30 F100tLE. StUtT. FAILS TO F1 ACTION. REPAIRED POWER SUPPLY. A292031 1 FCV 003 4S 05/25/841-FCV-003-48,CtECK S/G LEELS FCR LOOPS 1, 3,1 TE LOCAL REF10TE SWI1CH WAS FOUlO IN
- 4. al@RDa LOCAL POSITION AND SHXLD HAVE BEEN IN REf10TE CAUSING THE READINGS TO BE INCORRECT. PLACED SWITCH IN REr10TE POSITION #D RETURfED TO SERVICE A292035 0 Erl 090 225 05/25/84 0-RtH90-225,TE fEELLE IS READIPO HIGER THAN CONTACTS DIRTY ON REGR00t Il@UT.
TE RECORDER. CLEAED CONTACTS ON llECORDER.
Plant Maintenance Summary Instrument Maintenance Page 4 of 5 INSTRtfENT MAINTENMCE IDiTM.Y SLfmARY ; 06-06-84 PAGE 4_ Ct N .
~
Pst.CorF U FLDC SYS ADORESS. DATE. . . . DESCRIPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . CORRECTIVE ACTION. . . .. . . . . . . . . . . . . . . . . .,. A29204 1 FIS - 001 55 05/29/941-FIS-001-55,FIS 1%S FAILED HIGH DELL 0uS IN FIS PUICTutED. REPLACED BELLDUS 8 RECALIBRATED. 31 records listed. . '
* *-*s @
Q O
*1 em W
l 1
- Plant Maintenance Summary-IWTRlFENT MAINTENNI FOmLY SLN1ARY 06H W 84 PAY $ .
Cor,
~
r9t2. . . . U RAC SYS ADDRESS. DATE. . . . DESCR IPTION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . ' CORRECTIVE ACTI0N. . . . . . . . . . . .. . . . . . . . . . . , A247335 2 FT 003 414 05/09/94 2-FT-003-414,PERFIRM CALIBRATION AND TE CAUSE WAS FROM HATtRAL CA.18 RATION ~ VERIFY OUTPUT WITH ROSER 10LNT TEST DRIFT. TE TRANSMITTER WAS ECALIBRATED TRAIERITTER. Ale RETURE9 TO SERVICE. A283059 2 LCV 003 -., 164 05/11/84 2-LCV-003-164, cal #iOT GET RLL CLOSLME TE CONTRG.LER WAS FOIAC WITH A BAO - IleICATION (M LCV-3-164 l&EN SETPOINT IS flILLI VOLT TO CLRRENT CIRCUIT BOARD
- DEDtEASED TO ZERO. REPORTED TIMT AIR IS CAUSING IT nit TO GO TO ITS RLL ~
. BLOWIls e MN. REF. SI276 0UTPUT. TE CIRCUIT BOARD IMi REPAIRED, VERIFIED CALIBRATIEM ON TE CONTROLLER AfC RETURNED TO SERVICE.
A283060 2 LCV 003 164A 05/11/84 2-LCV-403-1644,CAf80T GET FLAL ClJOSURE TE MILLIVOLT TO CURRENT CIROJIT BOARD IIGICATION ON LCV-1644 WEN SETPOINT WAS FOUlO BAD CAUSING TE CONTROLLER DECREASED TO ZERO. REPORTED THAT AIR IS NOT TO GIVE IT'S FULL DUTPUT VALUE. - BulWIIG G VLV. REF. 81276 INVESTIGATE & REPAIRED TE CIRCUIT BOARD, ERIFIED CGtRECT TO SERVICE CALIBRATION ADD RETINtED TO SERVICE. 3 records listed. i
--.--g -w,7-,,.. .m. , , , , . , . , , - , , _ . , , , , , . ,.%v , . . , , , _ - - . . . _ . _ , - - -_.,,.3,~. , , , , , - - ,
,.,.,,_,.,,,.--r--,- ,_ , . ,. . , , , . , - . , , - , - __-,_e-, -
y -. h Plant Maintenance Summary (Continued) Field Services Group
~
.l. 'ECN 2768--Reactor Pressure Vessel' Level' Indication System (RVLIS) (Unit 2)
The mechanical'wbrkplan investigation and preparation began and the
' electrical preparation is continuing. The procurenent of all electrical materials is underway.
~2. ECN 2780--Post Accident Sampling Facility-(Unit 2)
All'the mechanical' materials have been received and the electrical equipment procurement process is continuing. -The conduit work outside containment is. underway while the workplan preparation is continuing. The-following mechanical work is complete: HVAC system piping, hangers, tubing panels, and core drilling. 'The fire protection workplan is in
-the review cycle.
I 3. ECN 5198--Technical Support Center (TSC) (Unit 2)
.The modification of the status monitoring system (SMS) cabinets continued
'for the~ interface equipment. The control ~ building conduit installation
.on elevation 685 continued. Both the SMS and elevation 685 continued.
.Both the SMS and elevation 685 conduit work should be completed by mid June, the conduit in the annulus and the auxiliary instrument room is complete. The cable pulling workplan preparation is near completion.
- 14. ECN--6055 Wide Range Pressure Transmitter to the RVLIS Panel The mechanical workplan investigation and preparation is in progress.
The conduit. installation is continuing in the auxiliary building.
?S. 'ECN--519'4 Iodine Monitoring Building The electrical'workplan for unit 2 conduit is in the approval cycle.
The termination of the unit I sample room air, conditioning cable was-E completed. The mechanical workplan has been approved.
' 6 ~. Nu Reg'0588 Items
'The unit 2. vent motor replacement has begun for non outage work (ECN-5370).
No work has started on the solenoid valve replacement (ECN-5457). The workplan for the revision on the level switches was completed and the cable pull is in progress (ECN-5765). The workplan to replace the system 3 pressure switches was written and turned in for PORC review (ECN-5823). The' investigation and preparation of the electrical workplan for valve operator replacement is in progress, units 1 & 2 (ECN-5824). The workplan writing is in progress for the limit switch replacement (ECN-5881), the flow switch replacement (SCN-5883) and is complete for the temperature switch replacement on system 12 and 30 (ECN-5882). f Plant Maintenance Summary (Continued) ; Field Services Group (Continued)
- 6. Nu Reg 0588 Items (Continued)
The flow transmitter' replacement materials are on order from ENDES for , a delivery.of July 9, 1984 and the.workplan preparation is in progress . L(ECN-5884). ~The' relays for the revision of system 43 limit switches I
'have arrived for unit 1 & 2 (ECN-5898). System 3 and 7 motors are on -
order for valve operators (ECN-5970). The miscellaneous instrument replacement workplan preparation is complete and is in the review cycle (ECN-5995). Also, the mechanical and electrical workplan preparations
'are in progress for the hydrogen monitor modification (ECN-6032).
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l;- h t ( w TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379
' June 15, 1984
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Nuclear. Regulatory Commission. Office of Management Information and Program Control Washington, DC 20555 Gentlemen: Enclosed is the May 1984 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant. Very truly yours, TENNESSEE VALLEY AUTHORITY 012.Mdfu 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 -30303 (1 copy) INPO Recordo 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 Ski P. O. Box 10412-Palo Alto, CA 94304 (1 copy) Mr. R. C. Goodspeed MNC 461 , Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, PA 15230 (1 copy)
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