ML20080T642
| ML20080T642 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/31/1984 |
| From: | Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC |
| References | |
| NUDOCS 8403020002 | |
| Download: ML20080T642 (30) | |
Text
-:
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1 TENNESSEE VALLEY AUTHORITY {
4 DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT I
1 MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY C9MMISSION JANUARY 1, 1984 - JANUARY 31, 1984 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT-2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 Submitted By: _
Power Plant Superintendent i
8403020002 840131 PDR ADOCK 05000327 i R PDR
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TABLE OF CONTENTS i i
l
- Operations Summary . . . . . . . . . . . . . . . . . . . . . . . I Significant Operational Events . . . . . . . . . . . . . . . . . 1-3 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . . 4
- Reports
- Licensee Events-. . . . . . . . . . . . . . . . . . . . . . 4 Diesel Generator Failure Reports . . . . . . . . . . . . . 5 Special Reports.. . . . . . . . . . . . . . . . . . . . . . 5 Offsite Dose Calculation Manual Changes . . . . . . . . . . . . 5
.. Operating Data Unit I- . . . . . . . . . . . . . . . . . . . . . . . . . . 6-8 Unit-2 . . . . . . . . . . . . . . . . . . . . . . . . . . 9-11
' Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . 12-27 9
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I f say Oparations Summary
_ ~ ,
January, 1984 1The following summary describes the 'significant operational activities ;
- for.the month of_ January.
In support of this summary, a chronological log 6
- of significant events is included in this report.
Unit-1 LUnit~1 was: critical for 535.4' hours,, produced 454,340 MWH (gross), resulting
- in an average hourly gross load of 943,043 kW during the month. There are 2.8 '
' fullLpower days' estimated remaining until the.end of cycle 2 fuel. Cycle 3
_ refueling / modification outage is scheduled to begin February 24, 1984.
There:were 3Ereactor. scrams, 2 manual shutdowns and no power reductions during January.
-Unit 2 Unit 2.was critical ~for-744 hours, produced 881,480 MWH (gross),
. resulting in an. average hourly gross' load of 1,184,785 kW during the month.
-Th re are 194.6 full power' days estimated remaining until the end of cycle 2
'o fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached-September 16, 1984. The;capacit.y factor for the month was 100.15 percent.
'The.high~ capacity factor is due to: lower than designed condenser circulating water temperatures and exceeding expected generator loads.
There were no reactor scrams, no manual shutdowns, or power reductions
-during January.
Significant Operational Events
-Unit 1 Date -Time Event 101/01/84f 0001- _ Reactor was in mode 4 in preparation to return the unit to service as the result of the outage caused by the generator stator bar iron shorting on November 24, 1983.
.01/04/84 .1730 The reactor entered mode 3.
2
.x, 01/06/84. 0034 The reactor was taken critical.
0215 The reactor entered mode 1.
n 0445 The generator was tied on-line.
-1115 The reactor obtained 30% power and held due to steam generator chemistry requirements.
01/08/84 1835 Began power ascension.
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i Significant Operational Events (Centinued)
Unit 1.
(Continued) 01/09'/84 0627- Reactor at 44% power. Began reducing power to 32% because the cold leg accumulator levels were not in' specification.
0739 Manually tripped the generator.
0745 The reactor entered mode 3 with s - all rods inuerted.
1706 The reactor was taken critical.
01/10/84 0042 Began power ascension.
0141 The unit was tied on-line.
0159 The turbine tripped on a #4 steam generator Hi-Hi level.
0204 The reactor tripped on a #2 steam generator Lo-Lo level.
. 1223 The reactor was taken critical.
1354 1he reactor entered mode 1.
~1556 Tied the unit on-line. The reactor at 12% power.
1610 The turbine tripped on a #3 steam generator Hi-Hi level. Began reducing reactor power.
1612 .The reactor tripped on a_#4 steam generator Lo-Lo level.
01/12/84 2027 The reactor was taken critical.
-01/13/84 0821 The reactor entered mode 1.
-1144 Tied the unit on-line.
1411 The reactor was at 32% power, producing 330 MWe and holding d e to st;eam generator chemistry
^ -
requirements.
~
(01/14/84 0210 Bcgan power ascension.
0330 Holding reactor power at 40%.
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<e IS Significant Operational Events 9 ' . '(Continued)
Unit l' (Continued)
(01/14/84- 0620 Began power ascension.
01/16/84 0500 The reactor obtained 100% power.
-01/29/84 1153 Began reducing reactor power for a manual shutdown due to the unidenti-fiable leakage exceeding its limits.
1554 Turbine taken off-line.
g 1603 The reactor entered mode 3.
01/30/84 1400 .The reactor was taken critical.
tg 1930 The turbine tripped on a #4 steam generator Hi-Hi level (unit was not on-line).'
1933 The reactor tripped on a #3 steam generator Lo-Lo level.
01/31/84- 0247 The reactor was taken critical.
0$22 The turbine tripped due to a volts /
hertz relay problem. (The unit was not on-line).
_ ,. 0549 Tied the unit on-line.
0600' . Reactor obtained 30% power and held -
for steam generator chemistry.
2400 The reactor was in mode 1 at 30%.
power, producing 330 MWe and is
- holding for steam generator chemi=try
~
, ,g requirements.
Unit 2
' Unit 2 maintained 100% reactor power for the entire month resulting in a
_ record; gross generation of 881,480 MWH and a 100.15% capacity factor.
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' Fuel-Performance Unit 1 The core average fuel exposure accumulated during January was 647.17 MWD /MTU with'the total accumulated core average fuel exposure of 11059.99
. MWD /MTU.
On January' 17-18, 1984, 13 fuel assemblies (cycle 3) had the incorrect ANSI letter engraved. The initial receipt of these bundles had LMO... engraved and'should have been LMQ... Westinghouse representatives performed the work via All work was closely monitored by plant engineering
~
plant instruction SMI-1-79-1.
representatives, Operations SRO, Health Physics and Field Quality Engineering.
~All work was satisfsetorily completed.
Unit 2-
~The core avera'ge '"el exposure accumulated during January was 1192.63 MWD /MTU with the total accumulated core average fuel exposure of 3479.42 MWD /MTU.
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 Reports (LER's) were sent during January p w, 1984, to the Assistant Director of Nuclear Power (Operations) for reporting to .the Nuclear Regulatory Commission.
~LER DATE TIME UNIT MODE DESCRIPTION OF EVENT SQR050328/83181 12/23/83 1 5 ^The 120 volt'AC vital inverter a .2 1 I was taken out-of-service for r MI-10.6 and,was not returned to
-service within 24 houra.
lSQR050327/83186 12/09/83- 1 5 Diesel generator IA-A tripped due to
, 2 1 high crankcase pressure during routine surveillance testing.
SQR050327/83187 12/31/83 1 4 ERCW Header A liquid rad monitors
> 2- 1- 0-RM-90-133 and_-140 were declared
, inoperable when the sample pump motors failed.
SQR050328/83188 12/21/83 1 5- While reducing load for SI-7, diesel 2 1 generator IA-A dropped from 4 MWe to y4 instantly.
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t Licensee Events and Special Reports (Continued)
LER< DATE . TIME UNIT MODE DESCRIPTION OF EVEN1'
'SQR050328/83189 12/02/83 2 1 Feedwater flow channel 2-FT-3-90 was declared inoperable due to frozen sense line. A similar event occured on the RWST J 1evel transmitter 2-LT-63-51.
SQR050328/83190 12/11/83 2 1 The RCS subcooling margin monitor was declared inoperable cra to the loss of the P250 computer.
lSQRO50328/83191 12/27/83 2 1 Rod position indicator for rod C-11 in shutdown bank C was declared inoperable due to erratic behavior.
SQR050327/184001 01/02/84- 1 4 Containment vent isolations were
, actuated due to spurious spikes in 1-RM-90-112. This LER combines 5 separate but similar incidents.
r L
Diesel Generator-Failure Reports There~were no diesel _ generator failure reports transmitted during the
'Special Reports Special. Report.83 Fire barrier non-functional for a period in excess of seven days - was transmitted on December 6,1983.
Offsite Dose Calculation Manual Changes
. r There~were no changes to the Sequoyah Nuclear Plant ODCM during the e -month..
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OPERATING DATA REPORT DOCKET NO. 50-327 DATE FEBRUARY 3 1984 COMPLETED BY M. G. EDDINGS U TELEPHONE (615) 870-6248
. OPERATING STATUS'
- 1. UNIT NAME: .SEQUO'YAH NUCLEAR PLANT, UNIT 1 NU1ES:
- 2. REPORT PERIOD: JANUARY 1984
- 3. ? LICENSED THERMAL POWER (MWT): 3411.0
'4,1 NAMEPLATE RATING (GROSS'MWE): 1220.6 15.) DESIGN ELECTRICAL RATING (NET MWE):. 1148.0 6.' MAXIMUM DEPENDABLE CAPACITY'(GROSS MWE):- 1183.0
.7., MAXIMUM DEPENDABLE CAPACITY 1(NET MWE): 4148.0 L8. 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:_-_-_---_----__._--_-__-
a------_-----------------------------------------------
-THIS' MONTH YR.-TO-DATE CUMULATIVE 11.fHOURS IN REPORTING PERIOD. . .
744.00 744.00 22681.00
.12. NUMBER OF. HOURS REACTOR WAS CRITICAL' 535.40 535.40 14976.96
- 13. REACTOR RESERVE-SHUTDOWN HOURS 0.00 0.00 0.00 14.(HOURS GENERATOR ON-LINE 481.80 481.80 14594.95 15L UNIT ~ RESERVE SHUTDOWN HOURS- 0.00 0.00 0.00
,16.fGROSS. THERMAL ENERGY GENERATED (MWH) 1375823.08 1375823.08 46867673.38
- 17. GROSS ELECTRICAL ENERGY GEN.-(MWH) 454340.00 454340.00 15833476.00-
.18.iNET ELECTRICAL 1 ENERGY GENERATED (MWH) 434623.00 434623.00 15211551.00
- 19. UNIT SERVICE FACTOR 64.76 61.76 64.35 20.? UNIT AVAILABILITY ~ FACTOR 64.'76 64.76- 64.35
- 21. UNIT CAPACITY FACTOR (USING -MDC NET) 50.89 50.89 58.42 220. UNIT CAPACITY FACTOR (USING DER. NET) 50.89- 50.89 53.42
,23.' UNIT FORCED OUTAGE' RATE ~ . .
35.24 35.24 18.67
- 24.' SHUTDOWNS SCHEDULED OVed NEXT 6' MONTHS (TY E, AND DURATION OF EACH):
p_fy3}ing3gd i_f_ iga p i_oyp_o,y,t agg_t_o_ pgg,in_fgy_u_ayy _2 p, 19,g1 AT E ,4 for 54 days.__
- 25. dFl SHUTDOWN AT END.0F' REPORT. PERI'OD, ESTIMATED DATE OF STARTUP:
- c - -.; - - - _ - - _ - - _ _ - - _ - - _ - _ - - - - - _ _ - - -_ _ . -_----_____ _---_---
~
NOTE THAT?THEETHE YR.:-TO-DATE AND
. CUMULATIVE VALUESyHAVE BEEN' UPDATED.
~
AVERAGE DAILY UNIT POWER LEVr; DOCKET NO. 50-327 UNIT 'Seonovah One DATE February 3, 1984 COMPLETED BY M. Eddings TELEPHONE (615)870-6248 MONTH ~ JANUARY e
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEWL (MWe-Net) ,
(MWe-Net) ,
1 0 17 . 1132 2 0 18 1132 3 0 19 1134
~
4 0 20 1135 5 'O 21
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6 211 22 113_b 7- 303 23 1660 8 351 24 1133 9 401 25 1134 10 0.- 26 1128 11 0 27 1136 12 ~0 28 1130 13 971 , 29 1010 14 590 ~30 'I74.5 15 971- 31 227 ,
16 1131
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~ .-
INSTRUCTIONS .
'On this format, . list the average daily unit power level in MWe-Net for each day in
,the-reporting month. Compute to the nearest whole megawatt.
(9/77)
~
4
~ UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.30-327 UNIT NAME- Sequovah one
^
DATE February 3. 1984 COMPLETED BY M. G. Eddings REPORT MONTH JANUARY TELEPHONE (615)870-6248 _,
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- gg No.
- "e e if t Licensee y Cause & Corrective
.Date 8, t$ 8 yt2 Event- $% 8% Action to , ,
. 'g gj g- 5g* Report ! t*g 8, ] - Prevent Recurrence E?
- ld5 N" .8
- R' E
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c 26 831124 F 124.75 A. 3 Generator outage continuation.
l' 840109 F 18.0 A 1 Cold leg accumulator level out of technical specification limits.
, 2 840110 F 13.95 A 3 Steam flow-feedwater flow mismatch during y
start-up.
3 840110 F 67.6 A 3 Steam flow-feedwater flow mismatch during start-up.
4 840129 F 37.9 A 1 Leak on pressurizer root valve.
1 2 ~3 4 F: Forced Reason: Method: Exhibit G-Instructions
'S : Scheduled A-Equipment Failure (Explain) 1-Mar. .1 for Preparation of Data B-Maintensace or Test 2-Manual Scraca. 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
- 0utage was started in 1983.
OPERATING DATA REPORT '
DOCKET NO. 50-328 DATE FEBRUARY 3, 1984 COMPLETED DY U.C.DUPREE TELEPHONE (615)870-6?48 OPERATING STATUS 1.. UNIT NAME: SEQUOYAH NUCLEAR' PLAN 1,. UNIT 2 NOTES:
- 2. REPORT PERIOD: JANUARY 1 - 31, 1984
- 3. LICENSED THERMAL POWER (MWT): 3411.0
- 4. NAMEPLATE RATINO (GROSS MWE): 1220.6 .
.5.. DESIGN ELECTRICAL RATING (NET MWE): - 1148.0 6.-MAXIMUM DEPENDADLE CAPACITY (OROSS MWE): 1183.0
' 7. MAXIMUM DEPENDABLE-CAPACITY (NET MWE): 1148.O' 8.'.IF CHANGES' OCCUR IN CAPACITY RATINGS (ITEMS NUMfWRS 3 THROUGH '7)SINCE LAST REPORT, GIVE REASONS:_.--__.._____
- - - - - - _ - - - - - - - - - - - - - - - . ....-.m _---..------------- :_.------
9.. POWER LEVEL'TO WHICH RESTRICTED,IF ANY(NET MWE):-_---_-_
10.: REASONS FOR RESTRICTIONS.IF ANY:- .-_---_--_..---____--- .
THIS MONTH YR.-TO-DATE CUMULATIVE
,1 1. HOURS IN REPORTING PERIOD -744.00 744.00 14641.00 12.iNUMBER OF: HOURS REACTOR WAS CRITICAL ~ 744.00 744.00 11105.07
- 13.' REACTOR RESERVE SHUTDOWN HOURS 'O.00 0.00 0.00 19 <4. HOURS GENERATOR CN-LINE' 744.00 744.00 10898.32
- 15. UNIT _ RESERVE SHUTDOWN HOURS' O.OO O.00 0.00
~ 16. GROSS' THERMAL ENERGY GENERATED (MWH) 2535536.63 2535536.63 34953604.44
- 17. GROSS ELECTRICAL ENERGY GEN. . (MWH) 881480.00 881480.00 11913420.00 18 6 NET ELECTRICAL ENERGY-GENERATED (MWH) 849762.00 849762.00 11467499.60
- 19. . UNIT SERVICE FACTOR ~ '100.00 100.00 74.44 20.. UNIT AVAILABILITY FACTOR 100.00 100.00 74.44
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 99.49 99.49 68.23
- 22. UNIT CAPACITYJFACTOR(USING DER NET) 99.49 99.49 68.23
- 23. UNIT FORCED OUTAGE RATE' O.OO O.00 0. <68
-2G. SHUTDOWNS GCHEDULED OVER NEXT'6 MONfHS (TYPE, DATE, AND DURATION OF EACH):'
25 1IF' SHUT DOWN , AT END OF REPQRT PERIOD, ESTIMATED DATE OF STARTUP:
' NOTE THAT THE'THE'YR M10-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED. ,
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e AVERAGE DAILY UNIT POWER LEVEL
, - DOCKET No. 50-328
, UNIT Sequoyab Two DATE February 3, 1984
. COMPLETED BY D. C. Dupree TELEPHONE (615)870-6248
. MONTH January:
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P0k'CR LEVEL
'(MWe-Net) (HWe-Net)
! -I' 1143 17 11'46 .
~
2 1148 18 1146 ,
3- 1146 . 19 1147 4 1149 20 1145 7
.5.
1151 21 1r'45 1 i f4N'
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6 1149 22 _ _ _ _
1144
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7 - 11'48 - 23 l l8 1147 24 1146 9 1144 . . 25 1146
, 10 1144- 26 1144 11 '1145 27 1146
- 12 -1146 28 1143
- 13 1148 29 1147 14 - 1146 30 1145.
. 15. -1147 -
31 1145 . .
16 1143 .
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INSTRUCTIONS
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F l Pltnt Maintentnce- Summary The following significant maintenance items were completed during the month of January 1984:
Mechanical Maintenance
- 1. -Unplugged the boric acid recirculation line (BAT to BIT) on unit 1.
- 2. Repaired'and hydrostatically tested "B" boric acid evaporator concentrates piping.
- 3. Straightened the fuel transfer system track on the unit I side.
.4. Removed the mixed bed demineralizer tank 2A for repairs or replacement.
- 5. IB purge ~ air exhaust charcoal filters were changed out.
- 6. ~ Changed the hydralic pump out due to a leaking seal oa motor driven AFWP pressure control valve 2-PCV-3-132.
Electrical Maintenance
-1. .RCS cold-leg charging flow valve 1-FCV-62-85 valve position indicating lights were showing incorrect valve position. The investigation found that the actuator. arm on the valve stem would not allow the limit switch to close. The actuator arm was tightened and proper valve
. operation was obtained.
2.. 1-LCV-62-118 was operating abnormally. The investigation found the solenoid valve-internals dirty and preventing proper seating. The
.6olenoid' valve was replaced and the valve checked for proper operation.
~
- 13. A ground was indicated on the 125V vital battery board 3. The investigation found a wire connected to the control relay for
,2-FSV-77-128 was touching the cabinet. The wire was relocated and the alarm' cleared.
- 4. Containment spray header IA isolation valve 1-FCV-72-39 would not close -due to a tripped thermal overload. The breaker was reset and the valve checked for proper operation.
4
- 5. A 127V DC ground.was indicated on the 15V DC vital battery board 4. The around was - found on breaker 210 and 217 supply to 2-FSV-1-25 and
~
12-FSV-30-94.
- 6. 1-FCV-67-130 would not close on a containment isolation signal due
~
to a burned out motor. -The motor was replaced, valve adjusted and c the' valve checked ~for proper. operation.
- 7. ;The open limit switch indicating light for 2-FLV-62-73 did not indicate properly due to a loose actuator arm. The actuator arm was' tightened.
- 8. During surveillance . testing on 1-GENB-062-1A-A, an intermitter governor
~1oad/ speed problem was found due to a loose connection.
t.
[6 0; 5 -
Plant Mzintentnce Summary (Continued) m
- c Electrical Maintenance
- 9. During inservicefinspection, the steam supply valve to AFW turbine 1-FCV-1-16 would'not operate due to frozen gears in the limitorque gear switch box causing the control' fuses to blow. The gear switch box 1was' replaced.
'10. .1-FCV-3-100 would~not open because.the contacts would not make-up.
The-contacts were. cleaned and the valve operated to insure the failure was corrected.
11 During surveillance. testing of diesel generator.1A-A, battery cells
-55, 56,fand 57 failed to meet the specific gravity acceptance criteria. The cells were replaced.
- 12. Condensate demineralizer effluent monitor 0-RM-90-225 was found with its motor burned out. The motor was replaced.
'13.
'ERCW liquid monitor 0-RM-90-133 would trip every time it was manually started due.-to the motor being burned out. The motor was replaced.
J14. Pressurizer backup heater-group B-B would not operate as demanded. The heater group was. staying on at all- times. 2ne trip coil had burned out
.on the 69 kV switch. gear causing excessive current to be drawn on the
>- ' normally. closed contacts' arcing them together' thereby preventing the
. ' breaker from tripping. 'The contact block was replaced in the relay.
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1
- 15. IB-B pressurizer backup heater was blowing fuses in its control circuit.
A-short'was found on the trip coil and the interconnecting wire was ,
found burned due to overheating. The. trip coil and breaker wire were replaced.
- 16. > A blown control fuse was 'found in 'the control circuit ' for ERCW
, strainer 1A-A. The fuse was replaced.
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- 17. The_ trip-coil and a toggle-link pin'was found broken in the circuit Efor 'the pressurizer backup heater IB-B. The trip coil and toggle
-link pin were replaced.
~
'18.- :AFW valve 1-FCV-3.156 position ~ lights were not indicating proper valve position. The valve stem didn't have the proper: lubrication
-preventing the' limit switches ~from making up. The stem was lubricated
. and' limit switches adjusted.
'-19 . Ice condenser air handling unit IB would not defrost when placed in
.x imanual defrost. The high limit switch was tripped preventing the-
' defrost heater from working. . The limit switch-thermostat was reset and checked for proper operation.
L .
'2:0. 'An alarm indicated low RHR pump flow was received when the actual flow rate was normal. The' investigation-found the RHR pump run relay
- ihoperable. The spring on'the 'on contact' had slipped out of place causing the contact to be maintained in the closed position. The spring was replaced and checked for proper operation.
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I Plant Maintenance Summary
.(Continued)
I f Instrument Maintenance r
~
Uniti1.
SE .1; Installed'a fluid componenets flow transmitter in the condenser vacuum L;
. pump. exhaust for testing.: The transmitter has been sent off site for reranging. Testing-will continue when the switch is returned.
- 2. 'UHI' level switch les were' tested. -One switch on unit I was outside T. S.
t' ole rance. :This was the first T.S. out of tolerance in nine months. The cause was attributed to the switch being bumped when a scaffold was erected.
. Anothar switch on unit I was within T.S. tolerance but outside desired tolerance. -All other unit I and 2 switches, including the custom component 4 Ltest switch, were within the desired tolerance.
-3. . The turbine driven auxiliary feedpump failed to come to the desired speed during testing. 1The control gain wss adjusted. for proper operation.
- 4. fCleaned and calibrated instruments associated with the generator seal oil and
~ -
JH2 Purity systems. This was in response to excessive oil in the generator.
>5'. Continued preparation fo work-plans and work on unit I refueling outage surveillance requirements that do not require the unit to be shut down.
Unit 2
-a- . 1. ; Replaced Hoog control valve on 2-PCV-3-132. The train B motor driven auxiliary ~feedwater pump pressure control failed to control properly when tested.
- 2. Containment. sump level transmitter 2-LT-63-176 drifted high due to partial loss of oil fill.- Topped-off' oil fill, verified calibration:and returned to service.'
Unit 0;
^
- - 21 '.- 0RNL was on-site to collect quarterly. data for their reactor on line
- analyser. study. This is the last' scheduled test in their study.
~
2; , Improvements were made in several areas on radiation monitoring to prevent
. excessive auxiliary'and control building isolations.
- 3. ' Instruction revisions were completed to ensure containment boundary
- isolation drain valves ~are closed and locked. A category D'FCR.has
'been written,to remove.the drain valves.
. c a .
lt - 4. . Instruction' revisions were. completed for improving second person verification
, Lof instrument' maintenance work. This was in response to an NRC finding.
.+4.-
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. . INSTRUMENT MAINTENANCE
SUMMARY
f
.FOR THE MONTH OF JANUARY 1984. i
~' '
'Page l'of.7f
~
EFFECT ON SAFE NATURE 0F- OPERATION OF.. CAUSE OF RESULTS OF- ACTION TAKEN TO THE REACTOR MALFUNCTION- MALFUNCTION PRECLUDE RECURRENCE DATE SYSTEM- COMPONENT MAINTENANCE 12/23' 65L 1-PDT-65-90 Chk Cal on'Xmtr- None ~ Sense Lines 'None -
Call-xatr & clea'n lines.-
filled.with' - A-027615
[ foam.
12/23' 65 HPDT-65-97 'Chk' Cal on~xatr. 'None- Sense lines- None- Cal xatr & clean lines-filled with'. A-027614.
i foam.
i l
'12/28 68 1-LI-68-335A Lvl going up & 'None' Unknown None ,
Verified. Cal A-247894.
Gi down.
12/28 92 1-XE-92-5004' Moving ca'ble None Dirty None Cleaned A-237225 connector.
causes meter to connector.
fluctuate.
1/12- 68 2-TS-68-444S Adj pots erratic 'None -Pots bad None Replaced pots A-100200 1/4 3 2-FF-3-48A Verify xmtr cal None Xs.Lr out of None Recal A-112686 Cal.
1/5 3 2-FF-3-103A Verify-xmtr cal. None Xmtr out of None Recal A-112688 Cal 1/6 3 1-FF-3-103B ' Don't-ind. None Bad spsule None Replace capsule A-243116.
properly.
' ' ' " ' ' ' ' ' ' ~
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- INSTRUMENT MAINTENANCE-SUMMAP.YI '
'FOR THE'HONTH OF-' JANUARY 1984.
3 ,
-Page'2 of'7 EFFECT ON SAFE' NATURE OF' '
OPERATION OF- CAUSE OF- RESULTS'OF- ~ ACTION TAKEN TO-DATE SYSTEM- COMPONENT -~ MAINTENANCE- THE' REACTOR ~ MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE
- .1/6 ' 3. 1-FI-3-48B FI'not' working'. None- Xatr out of 'None ~Recal A-243119 Cal 1/8' '3
- 1-FI-3-90B :FI erratic- -None Xmtr out of None Recal A-243147 ind lo; cal.
.1/14 .3- 2-FCV-3-175 V1v strokes slow. Not.e - V1v stem- None -Tube viv stem - Adj air binding supply . press A-242887-~
1, -press.
7 12/15 3 1-LCV-3-174 V1v won't oper'. .None Unknown None. Verified proper operation
~
A-250529.
1/3 68 2-TI-63-309 Reads < ambient None Unknown None Verified Cal A-248247 1/3 3 2-FT-3-90B Verify Cal None Cal -None Recal A-112683 1/3 3 2-FT-3-103B Verify Cal None Cal' None Recal A-112684 12/24 63 2-LI-63-41 Lvl ind - Hi None Frozen sense None Reinsulate & Thaw sense i
lines. lines A-236251.
12/25 3 2-FI-3-90A Failed Hi None Frozen sense None Replaced Fuse & Thawed lines
! lines blown A-236271 l fuse.
s yo .5
'~
7 INSTRUMENT' MAINTENANCE'
SUMMARY
- FOR THE MONTH OF JANUARY 1984.
~
Page '3 of 7.
. EFFECT ON SAFE NATURE OF OPERATION OF- CAUSE.OF 'RESULTS OF A'CTION TAKFJ TO DATE SYSTEM C6rfPONENT ~ MAINTENANCE THE REACTOR MALFUNCTION -MALFUNCTION PRECLUDE RECURREACE 12/31 30 2-FCV-30-56 Lo flo None 'Unknowa- None No problem found A-236294.
1/5 3 2-FT-3-90A Verify Cal- None Out of Cal Ncne Recal A-112687 Unknown.
1/4 46 1-PCV-46-132 .Vlv won't operate'None' Bad Moog v1v. Needed to Replaced Moog valve chg modes.
1 Y 1/5 32 0-PS-32-88 Compressor. None Possible Degraded- MR to Mech Maint to correct Cycles' Water Leak Operation A-251214 12/23 65 1-PDT-65-80 Difference in None Calibration None Recal A-109825 Flow 12/22 65 1-PDIC-65-82 Controls erratic None Xmt: Cal None Recal Xmte - A-100826 1/21 90 1-RM-90-106 Inst Malf. None Loose screw None Tighten screw A-236493 1/20 90 1-RM-90-101 Spiking None Bad pmp None Switched to good pump A-243564 1/20 3 2-LCV-3-172 Vlv won't open None Blown fuse None Replaced fuse A-250316 1/20 3 2-LCV-3-175 Vlv won't open None Blown Fuse None -Replaced Fuse A-250317
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.'INSTRUMEN1 MAINTENANCEt
SUMMARY
<FOR THE MONTH.0F JANUARY 1984'. -
4
~
, , _ Page 4 ' of 7 '
EFFECT ON SAFE; NATUP.E OF - OPERATION OF CAUSE-0F RESULTS OF' eACTION TAKEN TO.
DATE SYSTEM' COMPONENT - MAINTENANCE- THE REACTOR MALFUNCTION- MALFUNCTION- PRECLUDE-RECURRENCE-1/20 68 1-TI-68-258 Ind reads Hi- None Modifier out' None Recal. modifier.A-243097, ~
of Cal' w
1/25 63 0-FIS-63-43' Init'ial Cal None Init Cal; None Verify Cal - A097935 1/20' 68 2-TS-68-317 Alm should not .None . Low temp in None .Recal R/I &~TS, but temp be in- system lo. A-250462.
, 1/28 90 0-RM-90-122 Backgound'- Hi None. -Bowl contam- None Clean Bowl - A103028-g inated.
i 1/31 63 2-LI-63-176 Shows 5% (w) no None. Loss of leg & None Back fill leg & recal sump lv1. Cal drift A-250464 1/24 3 1-LCV-3-154 Verify vlv for None Limit switch Noae Recal limit switch (Elec) consistent oper. out of cal. A-231906 1/30 68 1-XX-68 Isolate PZR instr None Verify root None Verified root vlv - A-242829 so root vlv can vlv o1+ ration, be operated.
1/30 90 1-RM-90-112B Change S.P. None- S.P. change None Chang SP - A-103035 1/30 90 1-RM-90-106B Change S.P. None S.P. change None Change SP A-103036.
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=
n I INSTRIMENT MAINTENANCE
SUMMARY
'FOR THE. MONTH.0F' JANUARY 1984'
'Page;5-of;7 ,
x
-EFFECT ON SAFE- -
-NATURE OF OPERATION OF CAUSE.OF RESULTS OF ACTION-'TAKEN TO"
'DATE' SYSTEM COMPONENT MAINTENANCE THE REACTOR = MALFUNCTION' MALFUNCTION: ' PRECLUDE RECURRENCE -,
1/9 f82 '0-PS-82-232 Pressure switch None: Bad switch: -None- Replaced switch performed sticks after- IMI-134. A-2477SI:
-engine starts.
1/7 3 1-FI-3-90A Repair / remove- None Air in sense None Removed bistablen, bled from service lines transmitter, verified per per TI-67. other xatr. A-243127 1/7 3 1-FI-3-103A . Remove from ser- None Pen dragging None- Verified cal per deta card, i 'vice per TI-67, due to static A-243126 G repair.C place
' back in service.
1/7 3 1-FI-3-48A' Cal-channel None- FI-3-48A None Vented xmtr per IMI-134 was' sticking removal FI & repaired.
A-251224 1/9 1 1-FI-1-21A Indicating Low None FI case None Replaced case & calibrated.
defective FI A-243148 needed cal.
1/8 90 0-RM-90-122 High back ground None Radiation in None Cleaned out detector housing monitor caus- & performed SI-206. A-243162 ing problems.
1/3 68 2-TI-68-309 Reads 68*F below None Found no None Performed IMI-68 but found ambient temp for- problem. no preblem. A-248247 PRT.
c-3 imW r,. ,
INSTRUMENT MAINTENANCE
SUMMARY
s 1
'FOR THE -MONTH OF: JANUARY 1984 -
LPagel6of'7 s ,
EFFECT ON SAFE-NATURE OF OPERATION OF 'CAUSE OF RESULTS OF' ACTION TAKEN TO DATE- SISTEM COMPONENT MAINTENANCE -THE REACTOR- : MALFUNCTION MALFUNCTION ~ PRECLUDE RECURRENCE 1/3 '30 ' '1-FT-30-242 Flow monitor- None- Xmtr was out None' Calibrated per cal' card, doesn't indicate- .of tolerance 'A-236436.
flow when fans '
are running.
1/3 -82 0-PS-82-181 Eng 2 air com- .None Set point was None Reset, verified repeatability.
pressor started off. ' ' per'IMI-134. A-232925.
.at 290 PSI.
1/2 68 1-TI-68-319- Abnormally high None Bad ziener None Repaired modifier'
& erratic diode in A-248133 L modifier.
?
1/3 3 2-FT-3-48B Verify cal. None Calibratic.n None Recalled per-IMI-99 CC8.12A.
drift A-112685.
1/11 63 2-FI-63-92C Indicating zero None Air in sense None Bled & Recalibrated.
GPM should in- lines or A-242877 dicate zero.- cal drift.
1/14 3 2-FCV-3-175 Valve isn't None Regulator ad- None Adjusted regulator &
stroking in justed low. lubricated valve stem.
required time. A-242887.
1/13 62 2-LIC-62-178 Repair malfunct- None Leg from main None Applied 800-1000 lbs. of ioning L.T.C. tank was plugged. pressure to line. A-243284.
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-INSTRUMENT MAINTENANCE
SUMMARY
.;FOR THE MONTH.OF JANUARY 1984'-
- Page'7 of.7 i..
EFFECT-ON SAFE,
. NATURE OF . OPERATION OF; 'CAUSE 0FT RESULTS OF. ACTION.TAKEN TO>
DATE SYSTEM COMPONENT- . MAINTENANCE =THE REACTOR" MALFUNCTION MALFUNCTION ~ " PRECLUDE RECURRENCE. R 1/3' i8T [1-LS-87-23' Switch found .None- Realigned "None' . Sincronized switch with.
inoperative.- switch.with- accuator; recalibrated.-
~
- accuator which A120074.
.weren'.t in' sinc.
1/18 3 1-FI-3-90A Flow indicator NoneD Flow.indi-~ NoneL Sprayed with static' kill &'
. was sticking. cator had- calibrated. A-242783 built'up a static charge.
i -1/15 62' 2-LT-62-178 ' Indicator showing None: -Air in' sense None Backfilled sense lines.
-% high level. .line. A-242923 i
.1/12 62 1-FI-62-142' ' "ihe flow indicatDNone Needle on None Unstuck needle & verified' '
or will not-show indicator was proper operator. A-243077.
flow. stuck on zero.
- 1/10 1 1-FI-1-10A Place back in None- Indicator was None Repositioned pointer &
l' service. stic hing at verified cal. A-243181 lower range.
l 1/10 1 1-FI-1-10B- Indicator shows None Static was None Thoroughly cleaned indicator.
6x108 PPH at no- holding indi- Returned to service per TI-67.
flow condition. cator up. A-243182.
1/11 3 1-FI-3-90A ' Check calibra- None Unknown None Problem resolved itself. Air tion indicator - in the sense line disipated.
is erratic. A243135
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?
TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 FEB 151984--
Nuclear Regulatory Connission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the January 1984 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.
- Very truly yours, TENNESSEE VALLEY AUTHORITY C. C. Mason Power Plant Superintendent '
Enclosure-cc (Enclosure): . .
l 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 Records Center Suite 1500 Director, Office of Inspection 1100 Circle 75 Parkway.
L and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission g 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. O. Box 355 Pittsburgh, PA.~15230 (I copy) 9 91 4
An Equal Opportunity Employer L- .