ML20082S839
| ML20082S839 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/1983 |
| From: | Dupree D, Eddings M, Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8312150027 | |
| Download: ML20082S839 (21) | |
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TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER
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- SEQUOYAH NUCLEAR PLANT ., ,
MONTHLY OPERATING REPORT TO THE j NUCLEAR REGULATORY COMMISSION OCTOBER 1, 1983 - OCTOBER 31, 1983 l
UNIT 1 DOCKET AUMBER 50-327 LICENSE NUMBER DPR-77 l
UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l-i l
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. Submitted By:
l- Power Plant Superint_endent 8312150027 831031 PDR ADOCK 05000327 R pm
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TABLE OF CONTEhTS -,
t Operations Summary . . . . . . . . . . . . . . . . . ... . .1 Significant Operational Events . . ... ... .. . . .. . . . 1-4 PORV's and Safety Valves Summary . . . . . . . . . . . . . . . 4 Licensee Events and Special Reports . . ... .. . . .. . . . 5-6 -
Offsite Dose Calculation Manual Changes .. . .. . . .. . . .6 Operating Data Unit 1 . . . . . . . . . . . . . . . . . . . . . . . . . 7-9 Unit 2 .......... ... . . . . .. ., .. . . 10-12 Plant Maintenance Summary ... . . . . . . . .. . . .. . . 13-18 0
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. Op;retien3 Summary October, 1983 The following summary describes the significant operational activities for the month of October. In support of this summary, a chronological log of significant events is included in this report.
Unit 1
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Unit I was critical for 745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, produced 861,990 MWH (gross),
resulting in an average hourly gross load of 1,157,034 kW during the month.
There are 43.2 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 December 22, 1983. The capacity factor for the month was 97.8 percent. Cycle 3 refueling / modification outage is scheduled to begin January 2,1984.
There were no reactor scrams, or no manual shutdowns, and there was one power reduction during October.
Unit 2 Unit 2 was critical for 456.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, produced 309,380 MWH (gross),
resulting in an average hourly gross load of 820,129 kW during the month.
There are 273.4 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 October 6, 1984. The capacity factor for the month was 35.5 percent.
There were no reactor scrams, one manual shutdowns, and no power reductions during October.
Significant Operational Events Unit 1 Date Time Event
- 10/01/83 0001 Reactor in mode 1 at 100% power producing 1160 MWe.
10/26/83 1025 Began reducing power for an Incore/
Excore calibration.
1530 The reactor holding 85% power producing 1000 MWe for incoretexcore calibration.
10/28/83 0153 Began power ascension.
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,' Signifiernt Oparctienal Ev:nts Unit 1 (Continued) .
Date Time Event 10/28/83 1345 The reactor obtained 100% power and producing 1162 MWe.,
4 10/31/83 2359 The reactor was in mode 1 at 100% power and producing 1160 MWe.
Unit 2 10/01/83 0001 The reactor was in mode 5. The refueling / modification clean up was in progress preparing to return the unit to service.
10/05/83 2137 The reactor entered mode 4.
10/07/83 1154 The reactor entered mode 3.
10/09/83 1240 The reactor was in mode 3 at full temperature and pressure and pulling control rods when rod K-8 in Bank A wouldn't move. A short to. ground was found in the lift coil.
-10/10/83 0245 Began cooling down to repair control rod K-8 lift coil.
0758 The reactor entered mode 4.
1200 The reactor entered mode 5.
10/11/83 1516 The reactor entered mode 4.
2028 The Reactor entered mode 3.
10/12/83 2235 The reactor entered mode 2.
2350 The reactor was taken critical.
10/15/83 1309 The reactor entered mode 1.
1416 The unit was tied on-line.
2200 The reactor was at 3D% power producing 235 MWe and holding _for steam generator chemistry clean-up.
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Significent Operatienel Evznts (Continued)
Unit 2 Date Time Event 10/16/83 1105 Began power reduction for the turbine
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overspeed test.
1122 The unit was taken off-line.
1404 The turbine testing completed.
10/17/83 0452 The unit was tied on-line.
0600 The reactor was at 30% power producing 258 MWe and holding for steam generator chemistry. .
10/19/83 1114 Began power ascension.
1405 Held reactor power at 36% (325 MWe).
2156 Began power ascension.
10/20/83 0620 Stopped the power ascension at 49%
reactor power (500 MWe) due to chemistry.
0730 Began power ascension.
1155 Power ascension stopped at 53%
reactor power (531 MWe) for maintenance on MFPT-B.
, 1240 The reactor was at 50% power producing l
510 MWe. Work continued on the MFPT-B controller.
10/21/83 0300 MFPT-B returned to service and MFPT-A removed from service for maintenance l on the controller.
l l 1403 The reactor was held at 55% power, producing 626 MWe while work continued on both MFPT's.
10/22/83 0200 Began power ascension.
! 0600 The reactor was held at 63% power, producing 720 MWe, for chemistry.
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Significent Optrctienn1 EvInts (Continued)
Unit 2 Date Time Event 0900 Began power ascengipn.
i 1615 The reactor at 75% power and producing 871 MWe and holding for start-up testing.
10/24/83 1615 Began power ascension.
10/25/83 1415 The reactor obtained 100% power and producing 1150 MWe.
10/31/83 2359 The reactor was in mode I at 100% power producing 1185 MWe.
Fuel Performance Unit 1 The core average fuel exposure accumulated during October was 1184.22 MWD /MTU with the total accumulated core average fuel exposure of 9505.03 MWD /MTU.
Unit 2 The core average fuel exposure accumulated during October was 446.89 MWD /MTU with the total accumulated core average fuel exposure of 446.89 MWD /MTU.
After a 88-day scheduled outage, initial criticality occured on October 12, 1983. Low power physics testing commenced on October 12 and the reactor achieved 100% power on October 25, The unit was returned to commercial status (generator synchronization) on October 16.
PORV'S and Safety Valves Summary No PORV's or safety valves were challenged during the month.
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Licensee Events and Special Reports The fellowing Licensee Event Reports (LER's) were sent during October 19*9. t> the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
- Unit 1 LER SUBJECT L
SQRO-50-327/83116 The RCS subcooling margin monitor was declared inoperable due to loss of the P-250 Computer.
SQRO-50-327/83117 The monthly surveillance on the Power Range of the incore/excore channel was not performed.
SQRO-50-327/83123 ABGTS Train A was declared inoperable when 1-FCV-30-149 failed to open.
SQRO-50-327/83125 Condenser vacuum exhaust flow rate monitor 2-FT-2-257 was declared inoperable.
SQRO-50-327/83126 Ice build up was found on the intermediate ice condenser doors.
SQR0-50-327/83128 Radiation monitor 1-RM-90-106B was declared inoperable when it failed to meet surveillance requirements. .
Unit 2 LER SUBJECT SQR0-50-328/83122 Diesel generator 2A-A failed to maintain load during testing.
SQRO-50-328/83124 Condenser vacuum exhaust flow rate monitor
/83131 2-FT-2-257 was declared inoperable.
SQRO-50-328/83127 The PRZ safety valves failed to meet the lift setpoint limits.
SQR0-50-328/83129 Two MSIV's 2-FCV-1-22 & -29 would not close due to dried out packing.
SQRO-50-328/83130 containment Sump Level Channel 2-LT-63-177 failed to meet the surveillance requirements.
SQRO-50-328/83132 Steam generator blow down radiation monitor 2-RM-90-120/121 failed to maintain adequate flow.
SQR0-50-328/83133 AFW pump 2A-A was declared inoperable when 2-LCV-3-156 failed to open.
9 Licensee Events and Special Reports (Continued)
Unit 2 LER SUBJECT SQRO-50-328/83136 Diesel generator 2B-B was declar,ed inoperable due to the loss of the 125V DC battery bank, i
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SQRO-50-328/83137 Diesel generator 2B-B was declared inoperable due to water in the lube oil.
Special Reports There were no special reports transmitted during the month of October.
l Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during the month.
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- i OPERATING DATA REPORT -
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DOCKET NO. 50-327 -
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DATE November 15, 1983
-COMPLETED BY M. Eddines
- . TELEPHONE (615) 870-6243 OPERATING STATUS
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- 1. Unit Name: SEQUOYAH ONE' Notes
- 2. Reporting Period: October -1983 -
- 3. ' Licensed Thermal Power (HWt): 3411 -
4.' Nameplate Rating (Gross HWe): 1220.6 .
1 5. Design Electrical Rating (Net NWe): 1148 . .
- 6. Haximum Dependable Capacity (Gross NWe)
- 1183 '
- 7. Maximum Dependable Capacity (New HWe): 1148 -
- 8. If Changes occur in capacity Ratings (Items Number 3 Through 7) Since Last T g , Report, Give Reasons: '
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1 i 9. Power Level To Which Restricted, I,f Any (New HWe):
- 10. Reasons For Restrictions, If Any: - '
s This Month Yr-to-Date Cumulative -
- 11. Nours in Reporting Period 745 7296 20,473-
, 12. Number of Hours Reactor Was~ Critical 745 6338.81 13,877]OI '
.. 13. Reactor. Reserve Shutdown Hours 0 0 0 ;
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- 14. . Hours Generator.On-Line 745 6226.6 13,546.1 l
- 15. Unit Reserve Shutdown Hours 0 0 0 ,
- 16. Gross Thermal Energy Generated (HWH) 2.517.539.03 20,279,238.18 43,561,980.18
- 17. Gross Electrical Energy Generat'ed (HWH) 861,990 6,963,450 14,720,950
- 18. Net Electrical Energy Generated (HWH) 830.283 6,708,619 14,144,623
- 19. Unit Service Factor ' ,
i 100 85.3 . 66. Z -
- 20. ~ Unit Availability Factor
., 100 85.3 eb.z 21 Unit Capacity Factor (Using HDC Net) 97.1 80.1 bU.z 22.3 , Unit Capacity Factor (Using DER Net) 97.1 80.1 '60.2 7
- 23. Unit Forced Outage Rate 0 8.9 13.9 24.- Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
Refueline/ modification outage, 1/03/84. .
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- 25. .If Shut Down At End of Report Period, Estimsted Date of Startup:^
- 26. Units In Test Status (Prior to Commercial Operation):
L Forecast Achieved 4_ INITIAL CRITICALITY -
- 07/04/80 07/05/80 INITIAL ELECTRICITY - -
08/21/80 07/22/80
, CONMERCIAL OPERATION 07/01/81 07/01/81 a- - . - . .- :-
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- (g/77) .. -
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-327 UNIT ONE DATE october, 1983 COMPLETED BY M. Eddings TELEPHONE /A1o A7n-676R MONTH nr.pnnen DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1111 17 1118 2 1in7 18 1120 3 1110 19 1121 4 1112 20 1118 5 1104 21 1119 -
6 1107 22 1122 7 1111 23 1125 8 1113 24 1125 9 1113 25 1125 10' 1115 26 1045 11 1111 27 957 12 1114 28 1058 13 1116 29 1120 14 1109 30 1118 15 1115 31 1117 16 1118 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)
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-327
- UNIT NAME SEOUOYAH ONE
- DATE November 15. 1983 COMPLETED BY M. Eddings REPORT MONTH OCTOBER TELEPHONE * (615) 870-6248
% a Cn N Licensee g. gm Cause & Corrective yo. Date 00
~, S "- @ .e J g Event 3.g g.g Action to R y8 g ,8 ij y Report # gg o. Prevent Recurrence H
j5 a tam g
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No Shutdowns or Power Reductions during month.
.h I 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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8 OPERATING DATA REPORT
, DOCKET NO. so_us ~
DATE wnu ur i t, _ 1983 '
COMPLETED BY David C. Dupree
. TELEPHONE (615) 870-6543 OPERATING STATUS l
- 1. Unit Name: SEQUOYAH TWO' Note [s
- 2. Reporting Period: OCTOBER, 1983 .
- 3. Licensed Thermal Power (HWt): 3411 *
, 4. Nameplate Rating (Gross MWe): 1920.6 -
- 5. Design Electrical Rating (Net MWe): 1148 .. -
. 6. Maximum Dependable Capacity (Gross MWe):1183 -
. 7. Maximum Dependable Capacity (New MWe): 1148 -
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: '
Items "6" and "7" were chenged base on the Turbine Acceptance Test. .
- 9. Power Level To Which Restricted, I,f Any (New HWe):
- 10. Reasons For Restrictions,, If Any: -
This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 12.
'. 745 7296 12,433 -
Number of Hours Reactor Was Critical 456.2 5206.97 9093.0/_
.. 13. Reactor Reserve Shutdown Hours 0 0 0
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. 14. . Hours Generator,0n-Line 377.2 5093.15 8,899.9
~ 15. Unit Reserve Shutdown Nours 0 0 0
- 16. Gross Thermal Energy Generated (MWH) 950.093.8 16.351,863.23 28,506,454.03
- 17. Gross Electrical Energy Generat'ed (MWH) 309.380 5,608,870 9,690,720
- 18. Net Electrical Energy Generated (MWH) 286.728 5.399,785 9,326,075
< 19. Unit Service Factor -
50.63 69.81 71.58 -
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- 20. Unit Ava'ilability Factor '
50.63 69.81 71.58
- 21. Unit Capacity Factor (Using MDC Net) 33.52 64.47 65.34
- 22. , Unit Capacity Factor (Using DER Net) 32.53' 62.56 63.41
- 23. Unit Forced Outage Rate 0.0 1.06 5.30
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
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- 25. If Shut Down At End Of Report Period, Estimated Date of Startup:_
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY -
j . INITIAL ELECTRICITY - -
COMMERCIAL OPERATION .-
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AVERAGE DAILY UNIT POWER LEVEL
' DOCKET NO. 50-328
- UNIT TWO
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DATE October 18, 1983 f COMPLETED BY D. C. Dupree TELEPHONE (615) 870-6543 MONTH OCTOBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net) (MWe-Net) 1 Down Fog Outage 17 236 2 18 233 3 19 236 4 20 476 5 21 563 .
6 22 748 7 23 844 8 24 860 9 25 1071 10 26 1134
_.11 27 1137 12 28 iian 13 29 1137 14 ss r' 30 1131 15 62 31 1138 16 113 INSTRUCTIONS On this format, list wte av.:,ge daily unit power level in MWe-Net for each day in the reporting month, compute to the nearest whole megawatt.
(9/77) f
UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-328 .
UNIT NAME SEQUOYAH TWO DATE November 14. 1983 COMPLETED BY D, C. Dupree i REPORT MONTH OCTOBER 1983 TELEPHONE DIS) 870-6543 f
% u No.
en n I cc 3 ' Licensee g g, Cause & Corrective Date
% S 5 .e j g Event o.g gg Action to R y8 g ,8 u y Report # gg gg Prevent Recurrence Y5 o
5 NE O
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13 830719 S 350.27 C 4 Refueling / Modification Outage continues.
14 831016 S 17.50 B 9 Turbine Overspeed Test. Reactor power remained at 30%.
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Method: Exhibit G-Instructions F: Forced S: Scheduled
' sReason:
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
Plant Maintenance Summary The following significant maintenance items were completed during the month of October 1983: -
MECHANICAL MAINTENANCE
- 1. Changed out the Lube Oil Cooler on Diesel Generator 2Bl.' '
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' 2. Furmanited 1-FE-3-163 and 2-VLV-3-526
- 3. Replaced the bellow assembly on 1-FCV-43-64.
- 5. Replaced the drain lines on 2AA and 2BB Centrifugal charging pumps.
- 6. Balanced Unit 2 Reactor Coolant Pumps. .
Electrical Maintenance
- 1. Replaced a bad exciation transformer on diesel generator 2A-A.
- 2. Replaced a CRDM motor (unit 2) due to an open motor winding.
- 3. 2-FCV-90-109 did not close on a phase A signal. Replaced the solid state protection relay latch.
- 4. Inspected the reactor trip keypass breakers, per W vender request.
- 5. Performed a surveillance instruction on the vital battery banks and charger performance test.
- 6. The aux. feed water 2B-B pump (unit 2) failed to start with both main feed pumps tripped. Replaced a defective relay and returned the pump to service.
- 7. The acceptance criteria was not meet on the diesel generator battery system during inspection and surveillance instruction testing on 2A-A and 2B-B.
Replaced cells 4, 5, & 6 on 2A-A and 28, 29, 30 on 2B-B.
Instrument Maintenance Unit 1
- 1. Recalibrated the overtemperature A I flux penalty modules after discovery of a calibration error. This was reported by SQRO-50-327/83135.
- 2. Performed monthly testing of UHI accumulator level switches. Three switches were found within tolerance. One switch was found inoperable.
This was the first time in 5 months that a switch has been found out-of-tolerance. The prototype static-o-ring switch was found within tolerance for the second consecutive month.
n 2 -u + , a Plant Maintenance Summary (Continued)
Instrument Maintenance
- Unit 2
" 1. Recalibrated NIS power and intermediate range channels fo'r new detector 4
currents for startup after the refueling outage.
- 2. Replaced the high voltage power supply for NIS intermediate range channel N-36.
- 3. Added Silicon oil to " top off" the fill system for containment. sump level transmitter 2LT-63-177. This is the third channel on Unit 2 requiring refill in the last two months. One channel on Unit I was refilled last month.
- 4. Performed maintenance and calibration on the speed governor and E-H converter for U2 "A" MFPT controls. Performed calibrations on same for "B" MFPT during startup.
- 5. Replaced a sampling resistor in power cabinet for bank C shutdown control rods.
- 6. Replaced slave relay K 615 in Train A SSPS and the latch mechanism on slave relay K 622 in Train B SSPS.
- 7. Condenser vacuum exhaust flow monitoring channel F-2-257 was declared inoperable twice this month resulting in LERs. The frequency of
'L SI-189.1,-which removes condensate from the sense line, was increased to daily performances. DCR-2023 has been submitted for evaluation by ENDES to resolve this problem.
Field Services Group i
- 1. Critical Path Critical path consisted of several sequential items this month of which FSG was responsible for SI-111, "Setpoint Testing for MSSVs".
- 2. Primary Containment Snubber inspection and repair in accordance with SI-162 was completed for snubbers located inside containment. Final containment cleanup and
- . inspection for entry into mode 4 were conducted.
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Plant Maintenance Summary (Continued)
Field Services-(Continued)
- 3. Balance of Plant / Valves Extensive work was accomplished inside containment this. month during
- the unit 2 cycle 1 refueling outage to repair a control air system pipe.
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Preparation has begun to install additional cable trays in the turbine building. Cable tray covers that have been removed are being replaced throughout the plant.
Repair of spare pressurizer safety valves was performed this month in anticipation of changeout of one or more of the unit 2 valves which are currently suspected to be leaking.
- 4. ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2) -
Work is underway to complete conduit installation in the unit I annulus and was completed in the unit 2 annulus. Work has begun to install cable in the unit 2 annulus. Work continued on the installation of duct for the HVAC systems serving the PASF. The equipment pads have been set and
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equipment installed. Installation of PASF area conduit and sample tube continues. Work has begun to rework the stair case leading from the'PASF area. Tubing inside unit 2 containment was installed during the unit 2
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cycle 1 refueling outage in October.
- Removal of the old unit 2 system and restoration of both units containment lights in the old system electrical sockets were completed.
- 6. ENC 5009--ERCW Piping Changeout (Units 1 and 2) l ERCW piping serving the auxiliary air compressor "B" was changed out in order to install stainless steel piping this month. Work is underway to changeout the unit 1 "A" train penetration room and pipe chase cooler piping. Work was completed to changeout the ERCW return piping serving the centrifugal charging pump 2A room cooler and oil cooler.
Nonoutage mechanical work is continuing for both units. No electrical -
work has started yet.
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The TSC computer systems have been energized and the site acceptance test is underway. Hardware checkout will be completed by November 7 and software checkout by November 21. Conduit and cable pulls are continuing
(, in the control building (elevations 685 and 669) and turbine building and is 90 percent complete. Fire protection piping for the TSC was completed this month.
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. Plent Maintentnce Summary (Continued)
Field Services (continued) .
- 9. ECN 5642--Add N2 Regulating Station To Supply N2 To Deaeration Distribution System Inside Condensate Storage Tanks /and To Steam Generators (Units 1 and 2)
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Work is complete inside both tanks on installation of the'N2sparger 4 and associated piping. Final pipe tie-in outside the tank is now complete. The tank vent piping has been installed as well as the tank pressure switch. Some minor work remains on the high pressure portion of the system and modification of the valve cabinets.
- 10. ECN 2773,2775,2779,2923--Post Accident Radiation Monitoring-(Unit 2)
Instrument calibration and post-modification testing were completed as well as installation of a lead enclosure around the unit 2 reactor building exhaust stack radiation detector 1 coated on elevation 734 in the auxiliary building.
Of the 89 plant fire dampers, 86 have been modified. Work also remains on this ECN to change out.15 plant fire dampers.
- 12. ECN 5647--Main Feed Pump Turbine (MFPT) Condenser Air Removal Piping (Units 1 and 2)
Prefabrication of pipe and pipe supports is underway for unit 1.
- 13. ECN 5608--Pressurizer Manway (Units 1 and 2)
The manway cover was installed and leak tested prior to mode 4 entry.
Prefabrication of pipe and pipe supports has not begun for unit 1.
The unit 2 loop seal drain piping is valved out of service.
Cable terminations and functional testing were completed. The unit I portion of this ECN remains to be done.
- 16. ECN 5743--Improved Access to Pressurizer and Steam Generators (Unita 1 and 2)
Substantial work remains for unit 1 but will not start until the unit 1 outage. .
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Plant Maintentnce-Summery (Continued)
Field Services (continued)
,17. ECN2777-_3eactorPressureVesselHeadVent(Unit 2)
One valve was replaced when it failed during functional, testing. . The
- I/I' converter nonconformances have been cleared. Diode nonconformances t.
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have been cleared. The post-modification valve leakage test data was-evaluated and found acceptable. This job is field complete.
.(Unit 0)
Thermal overload portection device functional testing was completed on all motors replaced during the unit 2 outage.
- 19. ECN 5106--Reactor Pressure Vessel Level Indicatio.n System .
No mechanical field work was done this period. Mechanical engineering work is continuing. Electrical field work has started. Wiring junction boxes and terminating field cables at local panels and junction boxes is underway outside of the primary containment. Conduit and cable installation
.outside of containment is nearing completion. Electrical engineering work is continuing.
- 20. ECN 5596--Water Treatment System Neutralization Work was completed this month to install the remaining pipe hangers.
Work is underway to install control air tubing for the system.
- 21. ECN 5237--Laundry Facility Field work resumed this month on the laundry facility to install HVAC ductwork. Preparation is underway to install the new chiller package in the service building on elevation 706.
- 22. ECN 5202--Sth Diesel Generator Interface Work Work is underway to complete installation of annunciation cables in the auxiliary and control buildings.
- 23. L1902--Add Isolation Valve and Trap to Pipe Serving Main Feedpump Turbine Drain Tank This work was accomplished for unit 2. The unit I work remains to be done.
- 24. ECN 5664--Wells Fargo Tamper Indication ~
Prefabrication of electrical component assemblies to be installed for this modification is in progress as well as checkout of existing cables.
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Plant Maintenance Summary (Continued)
Field Services (continued)
- 25. ECN 5555--HPFP Deluge Valve Pressure Switch Supports
- Installation of the hangers for the switches is complete ,except for two
- remaining hangers.
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~26. LDCR1883--Liquid N System Suppoort Facilities 3
An access platform was built but Equipment installation is complete.
still lacks handrails.
- 27. LDCR1321--Install Turbine Building Safety Cables This work was completed this month. .
System Hangers
- 28. ECN 2456--Install H7 This work is now 20-percent complete.
29 ECN 2974--Complete Response Time Cables-Unit 2 Refueling Water Storage Tank (RWST)
This work is 40-percent complete.
- 30. ECN 5420--Essential Air Compressor Relay Replacement Work to replace the relays is 35-percent complete.
- 31. ECN 5495--Field Services Building Electrical Work Work is continuing to complete the building electrically as material and manpower allow.
- 32. Planning and Scheduling Planning, scheduling, and monitoring the status of the unit 2 cycle I refueling outage work was completed by the FSG planners with supportThe Project 2 from the central office Planning and Scheduling Group.
computer schedules.
program continues to be used for the outage and nonou unit 2 cycle 1 refueling outage and the unit 1 cycle 2 refueling outage is continuing as well as assistance to the central office planning section for planning of the unit 1 cycle 2 refueling outage.
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8 s TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 .
-November 15, 1983 -*
1 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the October 1983 Monthly Operating Report to the NRC for Sequoyah
- Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY C. C. Mason YhA 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) i Suie 3100 l Atlanta, GA 30303 (1 copy) INPO Records Center Suite 1500 f Director, Office of Inspection 1100 Circle 75 Parkway and Enforcement Atlanta, GA 30339 Nuclear Regulatory Commission l Washington, DC 20555 (10 copies)
Mr. A. Rubio, Director
, Electric Power Research Institute l P. O. Box 10412 .,-
l Palo Alto, CA 94304 (1 copy) U Mr. R. C. Goodspeed ] k MFC 461
(
Westinghouse Electric Corporation -
P. O. Box 355 Pittsburgh, PA 15230 (1 ocpy) i l
l . An Equal Opportunity Employer
. .-