ML20083G837
| ML20083G837 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/30/1983 |
| From: | Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8401120257 | |
| Download: ML20083G837 (24) | |
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TENNESSEE-VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT P
MONTHLY OPERATING REPORT TO THE NUCLEAR REGULATORY COMMISSION NOVEMBER 1, 1983 - NOVEMBER 30, 1983 UNIT 1 DOCKET NUMBER 50-327
. LICENSE NUMBER DPR-77 UNIT 2 -
DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 a
Submitted By:
Power Plant Superintendent 8401120257 831130 PDR ADOCK 05000327 R PDR
TABLE OF CONTENTS Operations Summary . . . .. . . . . . . . . . . ... . . . . .1 Significant Operational Events . . . . . . . . . . . . . . . . . 1-4 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . .5 Licensee Events and Special Reports . .. . . . . . . . . . . . 5-7 Offsite Dose Calculation Manual Changes . . . . . . . . . . . .7 Operating Data Unit 1 ... .. . .. . . . . . . . . . . . . . . . . . . 8-10
-Unit 2 ... . . . ... . . . . . . . . . . . . . . . . . 11-13 Plant Maintenance Summary . . . . . . . . . . . . . . . . . . . 14-21 l .-
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Opar2tien2 Summ9ry November, 1983 The following summary describes the significant operational activities for the month of November. In support of this summary, a chronological log of signiffcant events is included in this report.
Unit 1 Unit I was critical for 567.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, produced 658,150 MWH (gross),
resulting in ac average hourly gross load of 1,160,554 kW during the month.
There are 19.6 full power days estimated remaining until the end of cycle 2_ fuel. With a capacity factor of 85 percent, the target EOC exposure would be reached January 19, 1984. The capacity factor for the month was 77.3 percent. Cycle 3 refueling / modification outage is scheduled to begin February 10, 1984.
There was one reactor scram and no manual shutdowns, or pawer reductions during November.
Unit 2 Unit 2 was critical for 521.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, produced 461,260 MWH (gross),
resulting in an average hourly gross load of 903,693 kW during the month.
There are 256.6 full power days estimated remaining until the end of cycle 2 fuel. With a capacity factor of 85 percent, the target E0C exposure would be reached September 27, 1984. The capacity factor for the month was 54.2 percent.
There were two reactor scrams (unit not on-line), two manual shutdowns, and two power reductions during November.
Significant Operational Events Unit 1 Date Time Event 11/01/83 0001 Reactor in mode 1 at 100% power producing 1160 MWe.
11/24/83 1503 The reactor tripped after the turbogenerator tripped when an electrical fault alarm was received on the main generator.
11/25/83 1537 The reattor entered mode 4.
11/28/83 0958 The reactor entered mode 5.
11/30/83 2359 The reactor is in mode 5. The investigation cantinues to determine the cause of the electrical fault in the main generator.
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Significtnt Op; rational Events t
(Continued)
Unit 2 Date Time Event 11/01/83 0001 The reactor was in mode 1 at 100% power producing 1185 MWe.
2230 Began load reduction due to high vibrations on reactor coolant pump #1.
11/02/83 0128 Unit taken off-line.
0147 Reactor entered mode 3.
1042 Reactor entered mode 4.
11/03/83 0038 Reactor entered mode 5.
11/06/83 0926 Began unit heat-up.
11/07/83 0424 Reactor entered mode 4.
1137 Reactor entered mode 3.
11/09/83 1237 Reactor taken critical.
1330 Reactor entered mode 1. The unit is not tied on-line.
1335 Reactor power held at 9% due to steam generator chemistry.
1551 Unit tied on-line. Increasing power to 30%.
1910 Holding reactor power at 30%,
producing 280 MWe due to steam generator chemistry.
11/13/83 1628 Began power ascension.
2200 Held reactor power at 75% while placing the cooling towers in service.
11/14/83 0400 Began power ascension.
0930 Held reactor power at 87% while adjusting feedwater controls.
1000 Began power ascension 1430 Reactor at 100% power producing 1183 MWe.
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Significant Operational Evrnts (Continued)
Unit 2 t;
, Date Time Event
-11/15/83 0743 Began reducing load due to control oil problems on both main feed pumps.
0752 Held load at 96% due to control oil problems on the MFP's.
0827 Began power ascension.
0900- Reactor at 100% power producing
.1186 LWe.
1057 Began load reduction due to control oil problems on the MFP's.
1119 The reactor was at 85% power and holding. This was the maximum power the MFP's could handle.
1121 The MFP's oil strainers were found clogged.
1155- Began load reduction.
1250' Held reactor at 48% to work on the MFP's oil strainers.
11/16/83 0525 Began power ascension.
1400 The reactor obtained 100% power producing 1183 MWe.
11/18/83- 1800 Began reducing load due to high 4 vibrations on reactor coolant pumps #1 and #4.
n 2113 Unit taken off-line.
11/18/83 2140 Reactor entered mode 3.
L 11/19/83 1142 Reactor taken critical 1330 Reactor entered mode 1 (unit not on line).
1456 The reactor was at 20% power and the unit not tied on-line when the reactor tripped due to feedwater/
- steam flow mismatch during startup.
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s i Significent Operstienal Evcnts (Continued)
Unit _ 2_
Date Time Event 1720 Reactor taken critical.
1920 The reactor was at 11% power and the unit was not on-line when the reactor tripped due to feedwater/ steam flow mismatch during start-up.
2245 Reactor taken critical.
11/20/83 003a The unit tied on-line.
0055 Reactor holding power at 30% due to secundary water cher.istry.
2027 Began power ascension.
11/21/83 1400 Reactor power 100% power producing 1181 MWe.
0855 Began load reduction due to injection water problems on the MFP's.
1400 Held reactor power at 50% for maintenance on MFP's.
11/26/83 0630 Began power ascension.
1120 Reactor at 100% power producing 1183 MWe.
11/30/83 2359 Reactor at 100% power producing 1183 MWe.
Fuel Performance Unit 1 The core average fuel exposure accumulated during November was 907.79 MWD /MTU with the total accumulated core average fuel exposure of 10412.82 MWD /MTU.
The first fuel shipment (cycle 3) arrived on November 9. A total of 48 fuel bundles were satisfactorily inspected, processed and stored in the new fuel storage vault. Twelve fuel bundles received on the first shipment have incorrect ANSI numbers. It is planned that two Westinghouse representative from Columbia, S.C.
will be on-site on or about the first of January to correct the discrepancy.
Unit 2 The core average fuel exposure accumulated during November was 647.21 MWD /MTU with the total accumulated core average fuel exposure of 1094.10 MWD /MTU.
i- PORV'S cnd Stftty Valres Summary No PORV's or safety valves were challenged during the month.
Licensee Events and Special Reporti The following Licensee Event Reports (LER's) were sent during November 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
Unit 1 LER SUBJECT SQR0-50-3?.7/83135 During recalibration of unit 2 reactor trip instrumentation for overtemperature delta T, it was found that the calibration procedure contained incorrect valves. A review of unit l's calibration data indicated that all four unit 1 overtemperature delta T cF7nnels setpoints were less conservative than Tech Spec allowable limits.
SQRO-50-327/83138 Containment isolation valve 1-FCV-43-64 was discovered leaking.
SQRO-50-327/83139 Primary containment internal pressure exceeded
+.3 psig relative to the annulus. Maximum pressure reached approximately .415 psig and occured while purging containment. It was discovered that exhaust fan suction damper 1-FCV-30-61 was not opened when i the system was lined-up.
SQRO-50-327/83142 On October 7, 1983, with unit 1 in mode 1 and unit 2 in mode 3, during a review of modifications involving safety related snubbers, it was discovered that the plant procedure listing snubbers did not agree in number with table 4.7.9A of LCO 3.7.9.
SQR0-50-327/83143 During a review of SI's it was discovered that "H" WGDT had a high oxygen concentration of 2.2%
on October 6, 1983 and "A" WGDT had a high oxgyen concentration of 2.3% on October 22, 1983.
SQRO-50-327/83150 On October 25, 1983 one channel of the reactor l coolant pump underfrequency trip system was declared inoperable due to failure to meet surveillance requirements.
SQRO-50-327/83152 Reactor coolant drain tank nitrogen supply line containment isolaticn valve 1-FCV-77-20 was found inoperable during surveillance testing on October 28, 1983.
SQRO-50-327/83154 "J" WGDT had a high oxygen concentration of 3.5% and "H" WGDT had a high oxygen concentration of 2.35% on November 6, 1983.
Licensee Events and Special Reports (Continued)
Unit 1 SUBJECT LER 1-FT-3-103A loop 4 FW flow transmitter was delcared SQR0-50-327/83155 inoperable on November 4, 1983 when the test on line isolation valve pulled loose from the line while instrument mechanics were connecting test equipment.
UHI level switch 1-LS-87-23 was declared inoperable SQRO-50-327/83156 on November 1, 1983 when it failed to meet surveillance requirements.
The reactor coolant system subcooling margin SQRO-50-327/83158 monitor for accident monitoring instrumentation was declared inoperable on November 8, 1983 due to the failure of the plant process computer.
"D" WGDT had a high oxygen concentration of 2.3%
SQR0-50-327/83159 on November 10, 1983. "A" WGDT had a high oxygen concentration of 2.1% on November 11, 1983.
Unit 2 SUBJECT LER Containment sump level channels 2-LT-63-176, -177, SQRO-50-328/83140 and -178 were found out of calibration during the performance of SI-202 on October 3,1983.
Steam header pressure channel 2-PS-1-9 was found SQRO-50-328/83141 out of calibration.
During the performance of the 18-month calibration of SQRO-50-328/83144 the reactor trip system instrumentation, RCS flow channel 2-FT-68-6B and time power range flux tilt overtemperature bistable were found out of tolerance.
Steam generator level channels 3-LT-3-39 and -107 SQRO-50-328/83145 were found cut of tolerance.
SQRO-50-328/83146 Pressurizer level channels 2-LT-66-320 and -335 were found out of calibration on October 12, 1983.
Steam generator level channel 2-LT-3-106 failed to SQRO-50-328/83147 meet surveillance requirement on October 9,1983 and was declared inoperable.
SQRO-50-328/83148 The condenser vacuum exhaust flow rate monitor failed high and was declared inoperable on October 22, 1983.
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Lftenste Ev:nts and Sp;cisl Reporta (Continued)
Unit 2 I.lR SUBJECT SQRO-50-328/83149 On November 9, 1983 pressurizer PORV 2-FCV-68-340 was found leaking through.
SQRO-50-328/83153 On October 31, 1983 engineering personnel found the outer door of the upper personned airlock not fully closed.
SQR0-50-328/83157 During the review of response time testing of the RCS flow loop temperature channels, on November 2, 1983, it was found that protection channel I 2-TE-68-2A and -14A for delta T/Tavg were not completed within the required time frams.
SQRO-50-328/83160 The turbine driven AFW pump failed to obtain 880 gpm minimum flowrate during the performance of SI-166.32 on November 2, 1983.
SQRO-50-328/83161 The rod bottom light did not come on at shutdown for control rod H-10 on November 2, 1983 and was declared inoperable.
Special Reports There were no special reports transmitted during the month of November.
Offsite Dose Calculation hanual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during the month.
a
OPERATING DATA REPORT DOCKET NO. 50-327 DATE DECEMBER 7 1983 COMPLETED BY M. G. EODINGS TELEPHONE (615) 970-6248 OPERATING STATUS
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:
- 2. REPORT PERIOD: NOVEMBER 1 - 30 1983
- 3. LICENSED THERMAL POWER (MWT): 3411.0 G. NAMEPLATE RATING (GROSS MWE): 1220.6
- 3. 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 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 ------_--------_---_-__
._= = - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
lHIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 720.00 8016.00 21193.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 567.05 6905.86 14441.56
- 13. REACTOR RESERVE SHUTDOWN HOURS O.00 0.00 0.00 14 HOURS GENERATOR ON-LINE 567.05 6793.65 14113.15
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) .
1929870.12 22209108.30 45491850.30
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 658150.00 7621600.00 15379136.00
- 18. J4ET ELECTRICAL. ENERGY GENERATED (MWH) 632305.00 7340924.00 14776928.00 19.-UNIT SERVICE FACTOR _ 78.76 84.75 66.59 66.59
, . 20. UNIT AVAILABILITY FACTOR 78.76 84.75 2Y. UNIT-CAPACITY FACTOR (USING MDC NET) 76.50 79.77 60.74
- 22. UNIT' CAPACITY FACTOR (USING DER NET) 76.50 79.77 60.74
, 23. UNIT FORCED OUTAGE RATE 21.24 10.04 14.24
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
te_b.TSa rY_19 %_ _Cygle_,2_ geb eJigg,,pp_ _qays . _ _____________________________
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r 25. 5F SHbkbbWh kk hhb bF RdPORT PERIOD, EETI~kTUb~UATE M bF b5kRTUP5 De cembe r 2 8.t_1_9,8,3_ _____ _ _ _ __
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327 UNIT NAME Sequoyah One .
DATE December 8. 1983 COMPLETED BY M. G. Eddines REPORT MONTH NOVEMBER. 1983 TELEPHONE (615)870--6248 m !
u u g* cm n tw3 . Licensee ,
g, g, Cause & Corrective U"
"o .S S $ y .5 g Event S.g g.g Action to f, %@ g j"y Report # gg o. Prevent Recurrence
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a M5 & %3 m $g
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26 831124 F 152.95 A 3 Reactor / Turbine Trip Electrical Fault Alarm
- \ On Main Generator.
J f
J f
J 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
AVERAGE DAILY UNIT POWER LEVEL -
+
DOCKET NO. 50-327 UNIT One DATE December 8, 1983 COMPLETED BY M. Eddings TELEPHONE (615)870-6248 MONTH NOVEMBER, 1983,
-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) ,
(MWe-Net) ,
1 1118 17 -
1133 2 1115 18 1133 3 1106 19 113o 4 1110 20 1133 7
5 '1112 21 1158: l 6 1113 22 1129 D 7 11'14 23 112'8 8 -946 24 705 9 1109 25 0 10 946 26 0
, 11 11'30 27 0 12 1129 28 0
( '
13 1132 29 0 14 1131 '30 0 l 15 1083 31 .
16 1130 w
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[ INSTRUCTIONS .
l-l On this format,'. list the average daily unit power level in MWe-Net for each day in j .the reporting month. Compute to the nearest whole megawatt.
(9/77) l
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OPERATING DATA REPORT DOCKET NO. 50-328 DATE DECEMBER 7,1983 COMPLETED BY D.C.DUPREE TELEPHONE (615)870-6543
-OPERATING STATUS
'1. UNIT'NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORTlPERIOD: NOVEMBER 1-30,1983
- 3. LICENSED' THERMAL POWER (MWT): .3411.0
'4., NAMEPLATE RATING-(GROS 3 MWE): .1220.6 5.' DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDABLE Ci;PACITY . (GROSS MWE): 1183.0 7.-. MAXIMUM DEPIENDABLE 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):--------
l'O.-REASONS FOR RESTRICTIONS,IF ANY ----- --- ----__. -
_ == --- _ - - - - - --
=_ -- - -- ---------------
THIS MONTH YR.-TO-DATE CUMULATIVE 11.-~ HOURS ~IN REPORTING' PERIOD' ~ 720.00 8016.00 13153.00 '
=12..LNUMBER OF HOURS REACTOR WAS CRITICAL 521.40 5728.37 9617.07 '
- 13. REACTOR' RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 14.' HOURS OENERATOR ON-LINE 510.42 5603.57 9410.32
'15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY. GENERATED (MWH) .1375955.46 17-727818.69 29882409.49
.17. GROSS ELECTRICAL ENERGY GEN. (MWH) 461260.00 6070130.00 10151980.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 440100.00 5839885.00 9766175.60 19., UNIT SERVICE FACTOR 70.199 69.90 71.55
- 20. UNIT' AVAILABILITY FACTOR 70.89 69.90 71.55
- 21. UNIT' CAPACITY FACTOR (USING MUC NET) 53.24 63.46 64.68
'22.. UNIT CAPAOITY FACTOR (USING DER NET) 53.24 63.46 64.68
- 23. UNIT FORCED OUTAGE RATE. 29.11 4.50 9.92
.24. SHUTDOWN 3 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
- 25.'IFESHUTDOWN AT END OF REPU~RT PERIbbI ESTIMATED b Tb UF STbRTUPI 1 NOTE THAT-THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
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. UNIT SHUTDOWNS AND POWER REDUCTIONS- DOCKET NO. 50-3'28 ~
. UNIT NAME Seanovah Two-
. ~> ATE ner =her 8. 1983
. COMPLETED BY n. c. nuoree
] REPORT MONTH : NOVEMBER. 1983- TELEPHONE.- (615)870-6543
% O gg-
- 4 e_ c p tj -Licensee p. Cause & Corrective-Wo. Date ~ 8.- t$ 8 ?Og Event ,$$ ET Action to p 2e _ 2_ 5y* Report ! .g i 8, *8 Prevent Recurrence g-- x pgg go. gc t
g U-15 831102 F 182.38 ,B 1 High Vibration on #1 R.C.P.
l 1
16 831115 F -0 B '5
. Maintenance on the Control-Oil System-(Main Feed, Pumps).
4 i
f 17 831118 F 27.20 B 1 High Vibration on #1 & #4 R.C.P.
1 4
l F8 831125 F 0 B 5 Repaired the Injection Water Supply Line 1
to "B" M.F.P.
q i
i i 1 2 3 4
- F
- Forced Reason: Method:
S: Scheduled Exhibit G-Instructions 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-3 D-Regulatory Restriction 4-Cont. of Existing 0161) j E-Operator Training & License Examination Outage
, F-Administrative 5-Reduction j G-Operational Error (Explain) 9-Other 5 j
(9/77) H-Other (Explain) Exhibit I-Same Source i
, . . - . . , . . . =- . , = .
s o AVERAGE DAILY UNIT POWER LEVEL DOCKET No.53-328' UNIT T so DATE Dacember 8, 1983 COMPLETED BY- D. C. Dupree TELEPHONE -(615)870-6543 4
MONTH NOVEMBER, 1983 DAY AVERAGE DAILY POWER H VEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)
I '~ 1125 17 1N7 -
2 0 18 , 957
- 3 -0 19 0 4 0 20 275 0 I 5 21 10f23 6 0 22 11'52P 7 0 23 1151 8 0 24 1150
-9 -
'73 25 882 10 280 26 970 11 141 27 1149 12 251 28 1144 13 250 29 1145 14 1040 30 1147 15 839 31 .
16 903
~ .
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)
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Plant Heintenance Summary
-_The following significant maintenance items were completed during the
' month of November 1983:
MECHANICAL MAINTENANCE
- 1. _ Replace'd condenser vacuum pump IB.
- 2. " Plugged B spent fuel. pit heat exchanger.
- 4. Realigned number I reactor coolant pump (unit 2).
- 5. . Furmanite repaired the unit 2 number 3 thermal barrier test flange.
- 6. Balanced'the unit 2 reactor, coolant pumps number 1 and 4.
,7 . . Cleaned the-control oil-tanks and orifices on unit 2 MFPT's.
- 8. Removed the bladder from the monitor tank.
. 9. Repaired the_ unit I steam dump valves.
- 10. ' Began inspecting the MSR's on unit'1.
- 11. - Began the ice basket servicing on unit 1.
~
- 12. - Repaired the steam leaks on unit 1 NFPT's.
- 13. Inspected and'reprired both units fuel transfer wafer valves and the unit I upender.
- 14. Replaced some HP heater valves-using freeze plugs for isolation.
Electrical Maintenance
- 1. Checked the oil levels on unit I reactor coolant pump motors. Added oil to the 1, 2, & 4 motor lower bearings.
p
- 2. Completed the walkdown inspection of the E-Field wiring and made necessary repairs.
I
- 3 .~ - Returned the intertie transformer bank to its original configuration after
- repairs to-all-tap changers and diverter switches.
- 4. Repaired the heat trace on various boric acid lines to allow better ;
- operation of the equipment.
- 5. Replaced defective cells on IB-B and 2B-B D.G. battery banks due te low specific gravity.
L6. ~ Adjusted the unit 1 pressurizer heater group contro11s to allow for more efficient operation.
[ 7. Located the grounded bar in the unit 1 generator stator.
f y.- v - - . 9 ,.. ,,..y.-.. . ,, m. + , .,- --r,- -,--,,..,-%--,,-,,v,..---.-- ~ - -.-w ., , .m.-m.w. -,c,_,... m ,w-,~. ,- , , , , - . . ,
Plent Msintenance Summary (Continued)
Instrument Maintenance
- Unit 1-
- 1. Performed monthly testing of the unit 1 and 2 UHI accumulator level swithces. All_ switches were found within Tech Spec tolerance and three were found within desired tolerance. Two switches on unit 2 were found
~ with wiring errors. -This was reported by SQRO-50-327/83151.
- 2. . Started working the' refueling outage surveillance- tests and response time testing when unit 1 tripped due to the generator fault.
3 '. Steam flow transmitter.FT-1-28B failed high when unit 1 tripped. Inspection of transmitter revealed that apparently oil had leaked from the torque tube. We immediately shipped the transmitter to Barton for repair.
[ 4. Reprogrammed the P-250 computer to correct the totalized feedwater flow rate input due to nozzle fouling to increase the accuracy of the calculated value of reactor. thermal power.
- 5. ' Replaced a universal logic card in Train B of SSPS which was found bad during monthly functional testing.
Unit 2
- 1. Replaced the circuit board in PRT level transmitter.
- 2. Response time tested 12 narrow range RTDs on the Reactor Coolant System.
- 3. Change out the control oil, cleaned the orfices, and calibrated the EH converter on A and B MFPT controls during the forced outage.
4; RPI channels M2 and B10 were erratic indicating high resistance in the connectors. Reliable contact was achieved by applying voltage to the
' field cable and connectors.
- 5. Checked the stroke and response of' loops 2, 3, and 4 feedwater reg valves.
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' INSTRUMENT MAINTENANCE
SUMMARY
FOR THE MONTH OF NOVEMBER 1983
-Page 1 of-2 EFFECT ON-SAFE NATURE OF' OPERATION OF CAUSE OF RESULTS OF ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION ~ MALFUNCTION PRECLUDE RECURRENCE' _
11/17 92 U-2 Recal Hi Lvl- Recal For New Core None Recal XX-92-5020 Trip & Rod Stop_ Safe Operation. New Data From Bistables. Nuc Engr.
11/17 92 U-2 Recal Hi Lvl Recal For New Data None Recal XX-92-5026 ' Trip & Rod Stop Safe Operation. From Nuc Engr.
.Bistables.
11/17 68 2-LT-68-312C Check out level None Out of Cal. None Recal Xmtr.
i 11/17 99 2-SSPS-99-K615 Relay energized Bad relay None Replaced Relay'& check:-
E but didn't latch. per SI-26.2B.
i 11/17 99 2-SSPS-99-K615 Relay didn't- Bad relay None Replaced Relay & check latch. per SI-26.2B.
11/17 63 2-LI-63-109 Channel fails None Strain gage None Replaced Strain Gage &
out the top. bad in xmtr. recalled xmtr.
11/17 90 1-RM-90-106B Will not initiate None Relay out of None Reinstalled Relay & Ran contet. Vent isol. socket. SI-82.
11/17 68 2-LT-68-300 Suspect Inl xmtr Bad circuit None Replaced circuit board &
has failed. board. recalled xatr.
INSTRUMENT' MAINTENANCE-
SUMMARY
FOR THE MONTH OF NOVEMBER 1983 Page 2 of 2 EFFECT ON SAFE
- NATURE OF OPERATION'0F CAUSE OF RESULTS OF ACTION TAKEN TO DATE SYSTEM COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE 11/17 82 0-PS-82-271 Will not None- Dirty Low Diesel Cleaned contact, recal.
maintain 250- contacts- starting 300 psi pressure. calibration. press.
4 11/17 3 1-FT-3-103A Fittings None PM on Vlv blew off Tightened fittings &
(verified fittings. & burned IM. verified installation.
installation).
s 11/17 3 1-FT-3-48 Verify valve & None PM on Vlv blew off Tightened-fittings &
fitting fittings. & burned IM. verified installation.
ins ta llation) .
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7 11/17 3 1-FE-3-48 Verify proper None PM on valve Vlv blew off Tightened fittings &
installation of & fittings & burned IM. verified installation.
valves. installation.
11/17 3 1-FE-3-90 Verify proper None PM on valve Vlv blew off Tightened fittings &
installation or & fittings & burned IM. verified installation.
valves. installation.
11/17 68 2-PT-68-323 Check Cal of None Out of None Recal xmtr.
xmtr. calibration i
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' Plant Maintenance Summary n
(Continued)
Field Services Group J1. ;ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2)
Conduit and~ cable installation is complete in the unit 1 annulus and'inside-the unit 1 primary containment for the post accident sampling ' system. Work sis continuing to install cable in the unit 2 annulus. Cable is being pulled 1for the PASF' lighting and is nearing' completion. Work continued on the installation of duct for the HVAC systems serving the PASF. Installation of PASF area conduit and electrical components as well as sample tubing
-outsideJcontainment. continues. Rework'of the staircase leading from the
- PASF area continued; Prefabrication of hangers has begun for the PASF
~ area breathing station air system.
- 22. ECN 5743--Pressurizer Enclosure Access-Platform (Units 1 and 2)
Work is underway on the unit 1 platform during the current forced outage.
- 3. ECN 5370--Replacement of Class IE Electrical Motors Speed readings were obtained on various motors to be replaced in the plant.
- 4. <ECN 5106--Reactor Pressure Vessel Level Indication System Effort is underway to begin tubing hanger installation inside the primary containment during the present unit 1 forced outage. Conduit installation inside the unit 1 primary containment is to begin during the unit 1 forced outage as well. 'The majority of conduit and cable work outside of containment has been completed. No work has begun in the main control panels.
- 5. ECN 5009--ERCW Piping Changeout (Units 1 and 2)
- Work was completed to changeout ERCW piping serving the IA1, IA2 and 1A3 penetration room coolers. A portion of the ERCW piping, serving the 1A pipe. chase-cooler.was replaced. Prefabrication of stainless steel piping h began this month for replacement of ERCW piping serving the unit I spent fuel pit pump and thermal barrier booster pump area space cooler. Work has begun during the current unit I forced outage to change out ERCW pipe l- serving' the safety injection system pump 1B oil cooler and room cooler as well as for the centrifugal charging pump 1A oil cooler and room cooler.
- 6. ECN~5645--Steam Generator Blowdown (SGBD) System (Units 1 and 2)
Nonoutage mechanical. work is continuing for both units as work concentrated on installing unit 1 instrument panels, tubing, and hangers. Prefabrication
- of piping for. unit 2 heat exchanger tie-ins and miscellaneous unit I hanger and insulation work continued. Work began to repair the unit 1
- . . isolation valve 1-VLV-15-868 serving ventilation piping on the unit SGBD pump casings. Unit I conduit installation has begun as well.
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a i e q Plsat Maintentnca Summary (Continued)
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Field Services.(continued)
.7. - ECN 5198--Technical Support.Cneter' (TSC) (Units 1 and 2)
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- The_ hardware portion of the' site acceptance test is complete. Work is now complete t'o install the TSC: power distribution equipment and associated conduit on elevation 669 in the control building. The unit 1 SMS cabinet modification is complete. Installation of the TSC power and 1
manufacturer output cables lack only obtaining-_the final configuration of cables which are routed to the'old.TSC area. Installation of TSC conduit
'is continuing throughout the control building. Installation of conduit serving-the unit I-main steam blowdown valves is complete. Layout of conduit H
routing inside the' unit 1 primary containment has begun during the present
~ forced outage as well as conduit installation in the unit I valve rooms.
8 .~ ECN 5847--Plant Fire Dampers-(Units 1 and 2)
J All of the 89 plant fire. dampers have been modified. Eight of the 15 plant fire. dampers to be' replaced on this ECN have been completed.
-9. 'ECN 5647--! bin-Feed Pump Turbine (MFPT) Condenser Air Removal Piping
'(Units-I and 2)
' Prefabrication fof pipe and pipe supports is continuing for unit 1. The unit.1 piping'is scheduled to be replaced during the current' unit 1 forced
- outage.
- 10. 'ECN 6695--Water Treatment System Neutralization Work was completed this month to install control air tubing for the system.
All mechanical work is complete for this ECN.
f 11. ECN 5237--Laundry Facility-I Field work continued this month on the laundry facility to install HVAC ductwork. Work continued this month to install the new chiller package n in the service building on clevation 706. Installation of conduit to the exhaust and supply fans is in progress on elevation 718. Cables are being pulled for~the_ fire protection equipment.
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- 12. ECN 5644--Hotwell Makeup /Dumpback Piping l_
The-piping is now being installed during the current forced outage from CST."A pipe isolation valve to the condenser hotwell for unit 1. This piping is being tied into the condenser in order to make this operational by the end of the current unit 1 forced outage. Piping has been installed but-has not yet tied-in on unit 2. Heat trace was placed on outdoor piping serving CST "A" this month.
- 13. L1902--Add Isolation Valve and Trap to Pipe Serving Main Feedpump j Turbine Drain Tank l
t This work was accomplished for unit 2. Preparations are being made to l install these piping components during the current unit 1 forced outage.
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' Plant M intenence Summary
-(Continued)
JField ServicesJ(continued)L
- 14. ECN-5664--Wells Fargo Tamper Indication Prefabrication- of electrical component' assemblies to be installed for this modification is continuing as well as checkout of existing cables.
- 15. LDCR 1883--Liquid N System Suppoort Facilities 2
Remaining work was completed this month on the access platform.
Field work ~was completed this month to install unit 2 RWST level transmitter-response time testing cables.
- 17. ECN 5495--Field Services-Building Electrical Work Work is-continuing'to complete the building electrically as material and manpower allow.' '
- 18. ECN 5939--Main Feed Pump Turbine Condensor (MFPTC) r Installation.of temporary platform is in progress this month in preparation for the feedwater heater tube bundle replacement during the unit I cycle 2 refueling outage.
- 19. DCR 935--Spent: Fuel Pit Bridge Crane Load Cell Work was completed this month for this DCR to replace the spent fuel pit bridge crane hoist load cell.
- 20. ECN 5560--Manhole Fire Detector Removal "w Work began this month-to remove manhole fire detectors.
- 21. -ECN 5903--Strainers and Access Platform Strainers are being installed upstream of the laundry facility and hot
' shower drain tanks. The access platform has been completely installed.
22' . ECN 5194--Gaseous Effluent Radiation Monitoring Conduit-installation has begun for this modification. Core drilling of the shield building wall for tubing installation is scheduled to bsgin 1
-during the current forced outage.
.23. ECN 5457--Replacement of Solenoid Valves Work'has resumed to change out solenoid valve parts prior to replacing existing solenoid valves. In addition, the unit I train "A" ERCW solenoid valves have.been replaced.
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_ Plent Mnintenrnce Summary
, .-(Continued)
- Field ' Services s(continued)
J24. ECN'6031--Safety Injection System Hanger Modification I A hanger wa's' installed on the operator for 2-VLV-63-615. Other hanger.
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( -documentation will be done on'this.ECN.
- 25. LECN: 5867 Fuel Transfer System .
Work' resumed at an accelerated pace as.it was decided that the unit 1.
system was tto be operational by the end of the current unit 1 forced outage.
- 26. 1ECNs 5119 & 5871--Relocate ERCW Radiation Monitors 0-RE-90-133/140 &
- 0-RE-90-134/141
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Field work has. begun to reroute some. conduit. serving these monitors that -
were installed per ECN 5119. Electrical work per ECN 5871 will follow that for ECN 5119.
. :27. ECN 5723--Condenser'Sparger for Condensate-System
. The unit.1 sparger is being~ replaced during the present forced outage by a larger diameter one which is to be installed in a new configuration.
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- 28. ECN 6047 Reactor Coolant System Level Indication Preparations are being made to install the level tubing during the current- ,
unit 1, forced outage.
129. ECN 5770--Condenser Vacuum Exhaust High Range Noble Gas Effluent Radiation Monitors-Work progressed throughout November for the unit 1 portion of this ECN as the radiation monitor was set and conduit was installed.
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- 30. ECN 6050--High Pressure Fire Protection System Modification
'An' isolation valve has been installed in the portion of this sytem serving the
- ' control building mechanical equipment room. The system pipe supports are being modified as a result of the valve installation.
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- 31. :ECN 5713--Steam Generator Upper Manway Access Platform
. Preparations are in progress to install the steam generator No. 3 upper manway access platform during the current unit I forced outage.
- 32. ECN 5034--Steam Generator Access Platforms / Ladders I Prefabrication is underway for a ladder to be installed from the elevation 679 floor in order to provide access to 1 and 4 steam generators.
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TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 l
DEC 151983 ~ l l
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Nuclear' Regulatory Commission l Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the November 1983 Monthly Operating Report to the NRC for Sequoyah Nuclear Plant.
Very truly yours, TENNESSEE VALLEY' AUTHORITY r-
. . Mason
, Power Plant Superintendent 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- Wasington, DC 20555 (2 copies)
Suie 3100 Atlanta, GA 30303 (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 J
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) 4 k An Equal Opportunity Employer