ML20079M951
| ML20079M951 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/31/1983 |
| From: | Dupree D, Eddings M, Mason C TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| NUDOCS 8401270481 | |
| Download: ML20079M951 (26) | |
Text
_ __
... o TENNESSEE VALLEY AUTHORITY DIVISION OF NUCLEAR POWER SEQUOYAH NUCLEAR PLANT MONTHLY OPERATING REPORT TO THE l NUCLEAR REGULATORY COMMISSION DECEMBER 1, 1983 - DECEMBER 31, 1983 UNIT 1 DOCKET NUMBER 50-327 LICENSE NUMBER DPR-77 UNIT 2 DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79 l
Submitted By:
Power Plant Superintendent 8401270481 831231 PDR R
ADOCK 05000327 PDR
s i
l TABLE OF CONTENTS Operations' Summary . . . . . . . . ........ . . . . . . .1 1
Significant Operational Events . .......... . . . .. . 1-2 l PORV's and Safety Valves Sumnary . .............. 2 Licensee Events and Special Reports . .. . . ... . . . .. . 2-5 Offsite Dose Calculation Manual Changes .. . . .. . .. .. .5 Operating Data Unit 1 . . . . . .. . .... . . . . . ... . . . . . . 6-8 Unit 2 . . . . . . . . ......... . . . . . . . . . 9-11 Plant Maintenance Summary . . . ...... . . .. . . . . . . 12-23
Operetiona Summary December, 1983 The following summary describes the significant operational activities for the month of December. In support of this summary, a chronological log of.significant events is included in this report.
Unit 1 Unit I remained in the forced outage due to the generator stator bar iron shorting on November 24, 1983. 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 28, 1984. Cycle 3 refueling / modification outage is scheduled to begin February 10, 1984.
Unit 2 Unit 2 was critical for 744 hours0.00861 days <br />0.207 hours <br />0.00123 weeks <br />2.83092e-4 months <br />, produced 879,960 MWH (gross),
resulting in an average hourly gross load of 1,182,742 kW during the month.
There are 225.1 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 September 21, 1984. The capacity factor for the month was 99.98 percent.
There were no reactor scrams, no manual shutdowns, or power reductions during December.
Significant Operational Events Unit 1 Date Time Event 12/01/83 0001 React or was in mode 5 for repairs to the generator. The stator bar iron shorted on November 24, 1983.
12/25/83 0510 Reactor entered mode 4. Remained on RHR and maintained RCS at 205*F.
12/31/83 2359 Reactor in mode 4, RCS at 205*F.
Unit 2 12/01/83 0001 Reactor was in mode 1 at 100% power producing 1183 MWe.
12/31/83 2359 The reactor is still in mode 1 at 100% power and producing 1183 MWe.
The Unit produced a record 879,960 MWh's (gross) during the month resulting in a capacity factor of 99.98%.
I
r e,
- Fuel Performance Unit 1 The core averaga fuel exposure accumulated during December was 0 MWD /MTU with the total accumulated core average fuel exposure of 10412.82 MWD /MTU.
The remaining two fuel shipments (cycle 3) were received on December 12 and 14. This completes the cycle 3 fuel shipment. A total of 72 fuel assemblies have been received, inspected and stored in the new fuel storage vault.
The following list is an abbreviated summary of the discrepancies observed during the past six shipment of fuel:
- 1. 12 fuel assemblies (E07, E08, E09, E18, E19, E26, E28, E30, E32, E33, E36, and E37) have incorrect ANSI identification on each bundle. The Q.C. Release forms reflect the same error. Fuel assembly,-E47, also has the wrong ANSI identification; however, the Q.C. Release form reflects the correct ANSI number.
- 2. Two fuel assemblies, E05 and E21, do not meet rod plane specifi-cations, as reflected on Q. C. Release forms.
- 3. Fuel assembly E15, the S-hole on top nozzle measures oversize, as reflected on the Q. C. Release form.
Unit 2 The core average fuel exposure accumulated during December was 1192.69 MWD /MTU with the total accumulated core average fuel exposure of 2286.79 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 December 1983, to the Assistant Director of Nuclear Power (Operations) for reporting to the Nuclear Regulatory Commission.
LER DATE TIME UNIT MODE DESCRIPTION OF EVENT SQRO-50-328/83151 11/07/83 1730 2 3 During unit heat-up and pressur-ization it was noted that the UHI isolation valves were not opened prior to the RCS exceeding 1900 psig.
Licensco Evrnta and Special R ports (Continued)
LER DATE TIME UNIT MODE DESCRIPTION OF EVENT SQRO-50-327/83162 12/01/83 1425 1 5 The Emergency Centrol Room {
Ventilation system was declared i inoperable as the result of a review of SQNP-WP8314. It was determined that nonseismic hangers l were installed on the high pressure fire protection system above the control roem chiller package control I panels.
SQRO-50-328/83163 11/11/83 2245 2 1 Rod position indicator for rod M-2 on shutdown bank "A" was declared inoperable due to erratic readings.
SQRO-50-327/83164 11/14/83 1303 1 1 The turbine building liquid effluent line radiation monitor was declared inoperable because it was unable to clear a false hi-rad alarm.
SQRO-50-328/83165 11/15/83 -
2 5 During the review of SI-112 it was found that the pressurizer safety valve 2-VLV-68-563 failed to meet its seal leakage acceptance criteria and the lift setpoints could not be verified.
SQRO-50-328/83166 11/15/83 -
2 1 Primary Containment internal 11/19/83 0005 2 3 pressure relative to the annulus increased above 0.3 psig.
SQRO-50-327/83167 11/15/83 -
1 1 'E' WGDT had a high oxygen concentration of 2.7%.
SQRO-50-327/83168 11/18/83 0845 1 1 1A-A diesel generator was declared inoperable when it failed to start I
during the performance of SI-7.1.
SQRO-50-327/83169 11/17/83 1710 1 1 Steam generator blowdown floti rate j monitor .1 TE-15-25 was declared i inoperable whc the recorder pen l stopped inkir.
SQRO-50-328/83170 11/18/83 1100 2 1 2-FCV-63-84 was declared inoperable when it was found in the throttle position.
SQRO-50-328/83171 12/06/83 2109 2 1 Diesel generator IA-A was declared inoperable when the remote speed control failed to operate properly.
e
.. e*
'Licentes Events and Special Reports (Continued)
LLER DATE TIME UNIT MODE DESCRIPTION OF EVENT
- _SQRO-50-328/83172 - 11/30/83 0530 2 1 Steam generator blowdown containment isolation valve 2-FCV-1-182 failed to
, close on demand.
SQRO-50-327/83173' :
11/21/83 1000 1 l' Diesel generator 2B-B declared 2 1 inoperable when it failed to reach rated voltage and speed during the performance of SI-7.1.
4 --
SQRO-50-327/83174 11/21/83 1220 1 1 The engineered sa'. guard feature
'for steam line pressure function
-was declared inoperable due to a logic error for the low steam ;
pressure safety injection signal. l DQRO-50-327/83175 11/29/83 0900 l' 5 During the review of SI-70 it was-found that'one RWST level channel 1-LT-63-50 was out of TS tolerance.
SQRO-50-327/83176 11/24/83 1925 1 3 Steam generator flow transmitter 1-FT-1-28A was declared inoperable due to reading high.
SQRO-50-327/83177 11/22/83 0940 - 1 1 Diesel generator 2A-A was declared 2 1 inoperable due to failing to trip
, on demand during ralay testing. ,
SQRO-50-327/83178 12/06/83 0815 1 5 'G' WGDT had an oxygen concentration of 2.2% exceeding the 2% limit.
SQRO-50-328/83179 12/03/83 -
2 1 2B'-B Centrifugal Charging Pump failed to start during the performance of SI-699.2.
[ SQRO-50-327/83180 12/06/83 -
1 5 Several motor-operated valves
- thermal overload devices failed the trip check test during the performance of SI-251.1.
- SQR0-50-327/83182 12/06/83 -
1 5 ERCW pump JA time delay relay ST-1A failed SI-220.1.
SQRO-50-327/83183 12/02/83 0430 1 5 The turbine driven AFW pump steam supply valve 1-FCV-1-18 failed to meet the stroke time surveillance requirements.
O SQRO-50-328/83184 12/12/83 1142 2 1 The lower containment personnel !
airlock outer door failed to close.
! 4
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- Licensee Events and Special Reports (Continued)
LER DATE TIME UNIT MODE DESCRIPTION OF EVENT SQRO-50-328/83185 12/07/83 1622 2 1 Glycol containment isolation valve 2-FCV-61-97 would not clear it's open limit switch.
Special Reports There were no special reports transmitted during the month of December.
Offsite Dose Calculation Manual Changes There were no changes to the Sequoyah Nuclear Plant ODCM during the month.
.. .- OPERATING DATA REPORT DOCKET NO. 50-327 DA1E JANUARY 6,1984 COMPLETED DY M G EDDINGS TELEPHONE (615)8706248 OPERATING STATUS
- 1. UNIT NAMES SEQUOYAH NUCLEAR PLANT, UNIT 1 NOTES:
2.-REPORT PERIOD: DECEMBER 1983
- 3. LICENSED THERMAL POWER (MWT): 3411.0
- 4. NAMEPLATE RATING (GROSS MWE): 1220.6
- 5. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDADLE CAPACITY (GROSS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROllGH 7)SINCE LAST REPORT, GIVE REASONS ____________ '
_ _ _ _ _ _ _ _ _ =. _=___________ - = = _ _ _ _
- 9. POWER LEVEL TO WHICH RESTRICTED,IF ANY(NET MWE):____-___
- 10. REASONS FOR RESTRICTIONS IF ANY:___-___________-____--_
___=- -_-______ -
_-- _ __________-- =__-_--_----_--______-____-____
THIS MONTH YR.-TO-DATE CUMULA11VE
- 11. HOURS IN REPORTINO PERIOD 744.00 8760.00 21937.00
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL O.00 6905.86 14441.56
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 14. HOURS GENERATOR ON-LINE O.00 6793.65 14113.15
.15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00 f6. GRO9S THERMAL ENERGY GENERATED (MWH) 0.00 22209108.30 45491850.30
- 17. GRO,3 ELECTRICAL ENERGY GEN. (MWH) 0.00 7621600.00 16379136.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 0.00 7340924.00 14776928.00
- 19. UNIT SERVICE FACTOR O.00 77.55 64.33
- 20. UNIT AVAILABILITY FACTOR O.00 77.55 64.33
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.00 73.00 58.68
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.00 73.00 58.68 I
- 23. UNIT FORCED OUTAGE RALE 100.00 18.11 17.95
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DALE, AND DURATION OF EACH):
Ecfuellughtodifi cation _Jehruary_LL_19Ft._M_ days __ _-________________-_______
- 25. IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP imum11_6u19%4_.__-__________--------_______-_____________-_____--_-
NOTE THAT THE YR.-TO-DATE AND CUMULATIVE VALUES ARE NOT UPDATED.
__ _m 3
AVERAGE DAILY UNIT POWER LEVEL DOCKET No. . _ _
50-327 UNIT one DATE January 9, 1984 COMPLETED BY M. Eddituts TELEPHONE (615) 870-6248 MONTH DECEMBER, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) ,
1 0 17 -
0 2 0- 18 0 3 0- 19 0 4 0 20 0
~
5 'O 21 05-6 ~~ 0 22 0' ?
7 0' 23 0-8 0 24 0 9 0 25 0 10 0- 26 0 11 o 27 0 12 0 28 0
~
13 0 29 0 14 0 '30 0 15 'O 31 0 ,
16 0 ,
~
INSTRUCTIONS .
On this format,. list the average daily unit power level in HWe-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- seanovah one .
DATE Januarv 9. 1984 COMPLETED BY M. Eddines REPORT MONTH DECEMBER. 1983 TELEPHONE (615) 870-6248 I
4 w
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, - gg % ep" Licensee y Cause & Corrective
- 20. Date t $i Event:
[
p 2j 2,jt@
5y* Report !8 5%
g'g 8%
g]
Action to Prevent Recurrence
~
E" E$5 N* .5 u
g -
26 831124 F [44 A 3 Reactor / Turbine Trip, Electrical Fault Alarm on Main Generator. Electrical Short on 4
i i
_; 1 2 '3 4
- F
- Forced Reason: Method: Exhibit G-Instructions l ~S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-C.ont. of Existing 0161)
E-Operator Training & License Examination Outage F-Administrative 5-Reduction G-Operational Error (Explain) 9-Other 5 4
(9/77) H-0ther (Explain) Exhibit I-Same Source ~
- - OPERATING DATA REPORT DOCKET NO. 50-328 DATE JANUARY 6 1984 COMPLETED BY D C DUPREE TELEPHONE (615) 870-6248 OPERATING STATUS l
- 1. UNIT NAME: SEQUOYAH NUCLEAR PLANT, UNIT 2 NOTES:
- 2. REPORT PERIOD DECEMBER 1-31 1983
- 3. LICENSED THERMAL POWER (MWT): 3411.0 C. NAMEPLATE RATING (GROSS MWE): 1220.6 l S. DESIGN ELECTRICAL RATING (NET MWE): 1148.0
- 6. MAXIMUM DEPENDABLE CAPACITY (GROdS MWE): 1183.0
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWE): 1148.0 C. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBERS 3 THROUGH 7)SINCE LAST REPORT, GIVE REASONS:--------____
9 POWER LEVEL TO WHICH RESTRICTED IF ANY(NET MWE):------__
. ------------------------------=_ = = - - - - - - - . . - -
- 10. REASONS FOR RESTRICTIONS,IF ANY:_.._----.._--_-----_-__-..
===- ==--------------------------------- ...--------
THIS MONTH YR.-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744.00 8760.00 13897.00 1:2. NUMBER OF HOURS REACTOR WAS CRITICAL 744.00 6472.37 10361.07
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 10. HOURS GENERATOR ON-LINE 744.00 6347.57 10154.32
- 15. UNIT RESERVE SHUTDOWN HOURS 0.00 0.00 0.00
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 2535658.32 20263477.01 32418067.81
- 17. GROSS ELECTRICAL ENERGY GEN. (MWH) 879960.00 6950090.00 11031940.00
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 851562.00 6691447.00 10617737.60
~19. UNIT SERVICE FACTOR 100.00 72.46 73.07
- 20. UNIT AVAILABILITY FACTOR 100.00 72.46 73.07
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 99.70 66.54 66.55
- 22. UNIT CAPACITY FACTOR (USING DER NET) 99.70 66.54 66.55
- 23. UNIT FORCED OUTAGE RATE O.00 4.00 9.26
- 20. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):
. :25. IF SHUTCOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
_ =--- -----------------------------------------------
NOTE THAT THE THE YR.-TO-DATE AND CUMULATIVE VALUES HAVE BEEN UPDATED.
i
, e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-328 UNIT Seonovah Two DATE Januarv 5. 1984 COMPLETED BY D. C. Dupree TELEPHONE (615) 870-654?
MONTH DECEMBER, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (hWe-Net) 1 1145 17 1147 .
2 1144 gg 1145 3 1145 . 19 1145 4 1144 20 1144 1
5 1144 21 1*i;45 j
~
6 1143 22 114Y 7 1143 23 1145 8 1142 24 1146 9 1143 25 1146 10 1140 26 1150 11 1141 27 1144 12 1154 28 1149 13 1144 29 1148 14 )144 30 1147 15 1145 31 1148 ,
16 1145
~ -
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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~
~
UNIT' SHUTDOWNS AND POWER REDUCTIONS' DOCKET NO. 50-328 UNIT NAME % ,, , m..w r,.m .
DATE ' Jariua'r y 5, 1984 C0iiPLETED BY D.'C. Duoree d REPORT MONTH DECEMBER, 1983 TELEPHONE (615) 870-6543
~ .
r u o 8g "a c . E tj Licensee y Cause & Corrective No. Date 8, Oy 8 '8 0 @ Event $% 8% Action to R 2e 2 5y" Report # M'g 8.] Prevent Recurrence 8" $55 N"
- 8' 8
None 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 4
I J
r Plcnt Maintenance Summ:ry The following significant maintenance . vere-completed during the month of December 1983:
Mechanical Maintenance
- 1. Serviced the unit 1 ice condenser baskets by thermal drilling, filling the thermal holes with ice and weighing.
- 2. Inspected 2 of the main steam check valves and repacked all four of the valves on unit 1.
- 3. Performed SI-138 on unit I containment spray headers.
- 4. Repaired the coupling and leaks on 1A-A containment spray pump.
- 5. Installed flexitallic gaskets in auxiliary feedwater check valves 1-VLV-3-S !1 & 922.
- 7. Repaired the flange leak on 1-FCV-62-70 valve.
- 8. Modified 1-RM-90-99, condenser vacuum exhaust radiation monitor.
Electrical Maintenance
- 1. Diesel generator IA-A would not load. A screw on the lever that makes up the 'A' finger on the emergency supply breaker 1912 for the 6.9hV shutdown board 1A-A fell out. The screw was replaced.
- 2. Upper ccncainment exhaust valve limit switch 1-ZS-030-0052 required adjustment due to incorrect status light indications. An electro-chemical reaction causing a galvanic coating on the terminal lugs created a high resistance between the lugs and screw terminals. The terminal lugs were replaced and the terminal strip replaced.
- 3. The drive motor for diesel generator 1A-A speed control pot had an open wind?c - The motor was replaced.
- 4. UHI valve 1-FCV-087-0022 close limit switch would not turn out the open (red) light. The contacts on the limit switch were found dirty and were cleaned.
- 5. Steam generator #2 blowdown isolation valve 2-FCV-001-0182B required its limits switches to be adjusted when the limit switch arm slipped due to abnormal temperature changes.
- 6. Removed a 45 volt negative ground on vital battery board 0-BDG-250-KH-T.
The ground was found on breaker 210, fuse column A, circuit 16 (2-TCO-30-94).
- 7. Per Westinghouse Technical Bulletin NSB-TB-83-02, checked the AT8 undervoltage devices for missing lockwashers. All the breakers had the required washers.
i
y Plent M:inteninca Summtry (Continued)
Electrical Maintenance
- 8. 1-FCV-63-93 would not close on demand due to dirty closing coil contacts.
- 9. CRDM (CA) shroud suction damper 1-TCO-030-0081-B showed both red and green lights when the damper was closed due to loose linkages.
- 10. Ice machine C would not operate because control transformer (0-MTRB-061-0085) burned up due to high supply voltage. The transformer was replaced.
- 11. Control Building Pressurization fan B breaker (0-MTRB-061-0015-B) on C and A vent board would not operate because the trip coil burned up due to the high plant supply voltage. The coil was replaced.
- 12. The fan motor failed on the 120V vital inverter 2-1 (2-INVB-250-QM-T).
The motor was replaced.
- 13. Removed a jumper on the level switch (0-LS-077-133' J 1B) for the auxiliary building sump pump B.
- 14. Reactor building glycol inlet supply valve open limit switch l (2-ZS-061-0097-B) had a loose bolt on the mounting bracket causing both the red and green light to remain on when the valve was closed.
The bolt was tightened.
- 15. The closed limit switch on steam generator loop A warning valve 0-FCV-001-0150-B was not making up due to a loose nut on the adjustment arm of limit switch ZS-1-150. The limit switch was adjusted and the nut tightened.
- 16. A visual alarm indicated that the CVCS diversion flow valve (1-LCV-062-0118-A) zone switches were not in their correct position.
The operating lever had slipped on the valve shaft. The lever was adj usted.
! and would not allow the limit switch to complete the interlock circuit to keep the valve open. The actuator was adjusted for proper operation.
- 18. Steam generator pump motor 1-MTRB-015-0003 tripped on thermal overload due to an undersized motor. The motor was replaced.
- 19. 1-FCV-067-0139-A failed to close on a phase B isolation signal due to a burned 007 motor. The motor was replaced.
- 20. The auxiliary building general exhaust fan breaker was found with a broken roller arm. The roller arm was replaced.
- 21. The steam supply valve to the axuiliary feedwater pump 1-FCV-1-18 was found jammed in the closed position. Dried grease in the gear case caused the limit gear 1-ZS-1-18 to strip. The gear driven limit switches were replaced.
t
l Plant Msintentnce Sunua:ry l l
(Continued) i Instrument Maintenance Unit 1 During the unit.1 forced out' age the following items were completed:
=-
- 1. Nine Tech Spe: and Compliance Required Refueling Outage SI'c and threc l
- Non Tech Spec Refueling SI's. '
- 2. Eleven Response Time Test on steam flow, steam pressure, and containment pressure channels.
- 3. Replaced /upv,raded red insertion limit recorder.
- 4. Replaced 3 seismic monitors located in the annulus and containment.
- 5. Inverted the instrument bellows on the V.C.-7. UHI surge tank and pressurizer relief tank.
- 6. Added'o'11 to " top off" containment sump transmitter 1-LT-63-176.
l
-8. Stroked and verified operation of steam dump valves and feedwater reg valves. ,
- 9. Replaced the under voltage P.C. board in Train B SSPS.
'10. Received and installed a new Barton transmitter for steam flow, 1-FT-128A. The old transmitter was. returned because of torque tube oil leaks.
- 11. l Inspected all .Barton transmitters for possible torque tube oil leaks.
-Four transmitters of the 26 inspected had evidence of leaking oil.
These~will be returned to Barton for inspection and repair during the February refueling outage.
- 12. Installed modification kits in Foxboro power supplies for ESF instrument channels.
- 13. Replaced two defective temperature elements for main generator H2 gas indication'during the generator repair.
- 14. -Replaced control oil, cleaned orifices and calibrated speed controls on 1A and IB MFPT.
- 15. Calibration of UHI level switches found all within Tech Spec tolerance.
- 16. Completed an inspection of instruments inside the crane wall for .
possible water damage from the inadvertent R.H.R. spray actuation.
l kl . .
l l
l Plant Maintenance Snamary l (Continued)
Instrument Maintenance
' Unit 2 fi . Removed from service and awaiting parts for pocket sump transmitter
_ 2-LT-77-410.
- 2. . Replaced Beckman controller for auxiliary feedwater system 2-LCV-3-175.
- 3. Performed response time test on 4 reactor coolant system narrow range ETDs.
- 4. Monthly calibration of UHI level switches were all found within Tech Spec tolerance.
General
' Added insulation and increased the surveillance of haat trace circuits to improve freeze protection of feedwater and RWST instrument sense lines for both units.
INSTRUMENT MAINTENANCE
SUMMARY
FOR THE MONTH OF DECEMBER 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 12/07 90 0-RM-90-212 Replace Relay None Bad Relay None Replaced Relay 12/07 3 1-PT-3-132A Recal Xmtr None Zero Shift None Recal 12/07 3 1-LT-3-164 Replace Resistor None Bad Resistor None Replace Resistor & Ver. Cal.
I 12/01 68 1-TI-68-43C TI off Scale Hi None TM-68-43 None Recal 1-TM-68-43C cont. of cal.
1 T
12/01 18 0-PS-18-81 Xmtr leaking None Bad Switch None Replace Press. Srv.
Fuel Oil 12/01 68 2-FP-68-29A Test PT resistor None Bad Resistor None Replace Resistor & Ver Cal.
out of tolerance.
12/02 43 2-H2AN-43-200 Lo Flo Alm None Reagent Air None PRO-2-83-143 won't clear Press Lo adjusted pressure.
12/03 62 2-PS-62-24'. Pump wouldn't None Bad Micro None LCO 3.1.2.4 & 3.5.2 start in man. switch replaced switch.
12/12 3 1-LM-3-148A Repair Iv1. None Bad None Replaced Transdu. er & Recal.
modifier Transducer i
l l
d INSTRUMENT MAINTENANCE
SUMMARY
FOR THE MONTH OF DECEMBER 1983 Page 2 of 2 EFFECT ON SAFE .
l NATURE OF OPERATION OF CAUSE OF .RESULTS OF ACTION TAKEN TO' -l DATE SYSTEM -COMPONENT MAINTENANCE THE REACTOR MALFUNCTION MALFUNCTION PRECLUDE RECURRENCE ]
12/05 92 2-X1-92-5005B Meter drifts None Bad None Cleaned Connections &
Connection Replaced 63 1-LT-63-176 Xmtr out of None Out of Cal None Recal Xmtr, updated cards tolerance 12/15 1 LTM-1-73E Mod out of None Out of Cal. None Balance Xformers & adj Lo tolerance limit circuit & recal.
I C' 12/19 1 1-PIC-1-31 Cont. won't None Reg Press None Adj press to 30 psig, Recal.
open viv. Lo 12/13 3 1-LM-3-156A Mod won't cal. None Force motor None Realign & Recal misaligned.
12/23 3 2-LCV-3-175 Vlv won't fully None Bad Cnt1r None Changed Cntlr open.
12/22 99 1-SSPS-99-B Replace UVBd None Bad UVBd None Replaced UV Board 12/23 3 2-LCV-3-148 Vlv wont fully None Cont out of None Field tuned contir.
open. adj.
., . . - . . -- - _- - - _ _ . . . - ~. .
L Plant Maintenance Summary (Continued)
Field Services Group t
- 1. ECNs 2780/5200--Post-Accident Sampling Facility (Units 1 and 2)
During the current unit I forced outage, work began to. remove the RHR sump sample tubing.. This work will be finished during the unit I cycle 2 outage.
The installation of _ cable was completed in the unit.2 annt'.lus. Conduit and cable pulling in the unit' I reactor building for the primary containment solenoid valves _was completed this monti Cable pulling and terminations at_ receptacles and lights was completed.
Work continued on:the installation'of duct for the HVAC systems serving the PASF. -Installation of PASF area conduit and electrical componenets as well as sample tubing outside containment continues. Rework of the staircase leading from the PASF area continued. Installation of piping
.and hangers is underway for the PASF area breathing station air system.
- 2. '5CN 5009--ERCW Piping Changeout'(Units 1 and 2)
Prefabrication of stainless ~ steel piping continued this month for replacement of ERCW piping serving the unit I spent fuel pit pump and thermal barrier booster pump area space cooler. Work was completed during the current unit 1
. forced outage to change out- ERCW piping 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.
- 3. ECN 5645--Steam Generator Blowdown (SGBD) System (Units 1 and 21 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 is continuing. The unit 1 SGBD pipe hangers are.now installed. The unit 1 SGBD piping insulation is being installed at present. Repair to the unit 1 isolation valve
,1-VLV-15-868 serving the first stage SGBD heat exchanger was completed during the current unit 1 forced outage. Installation of ventilation piping on the unit 1 SGBD pump casings was also completed during the current unit 1 forced outage. Unit _1 conduit installation is nearing completion but is currently in hold until the remainder of the solenoid valves are installed.
Installation of the TSC power and 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 i control building. Conduit installation in the unit 1 valve room was I completed as well as cable pulling in the rooms. Conduit and cable I installation for the main steam blowdown valves was completed during the outage. l l
.5. ECN 5847--Plant Fire Dampers (Units 1 and 2) l Work continued this month to replace the 15 plant fire dampers.
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Plant Maintenance Summary (Continued)
Field Services (continued)
- 6. ECN 5647--Main Feed Pump Turbine (MFPT) Condenser Air Removal Piping (Units 1 and 2)
The unit 1 piping was replaced during the current unit 1 forced outage.
All field work is complete for this ECN.
7.
ECN 5743--Pressurizer Enclosure Access Platform (Units 1 and 2) r E All mechanical work on the unit 1 platform was completed during the current forced outage except for painting. Further lower containment -
- platform and ladder work will be done both prior to and during the unit 1 g cycle 2 refueling outage. -
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= 8. ECN 5106--Reactor Pressure Vessel Level Indication System Reactor pressure vessel level tubing hanger installation inside primary containment was worked during the present unit 1 forced outage. All tubing hangers were installed in the reactor cavity and significant
. progress was accomplished inside lower containment installing tubing
[ hacgers. Conduit installation inside unit 1 primary containment was
= conducted during the unit I forced outage with all conduit being installed L in the fan rooms and the majority of conduit inside the polar crane wall
, being installed. -
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, 9. ECN 5237--Laundry Facility I e
! Field work continued this month on the laundry facility to install HVAC -
l ductwork. Work continued this month to install the HEPA filters on the p PCDF exhaust system. Installation of conduit to the exhaust and supply
!i fans is in progress on elevation 718. Cables are being pulled for the fire protection equipment.
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- 10. ECN 5644--Hotwell Makeup /Dumpback Piping j The piping was completely installed during the current forced -
r outage from CST"A" pipe isolation valve to the condenser hotwell for R unit 1. This piping has been tied into the condenser and the system is now operational for unit 1. The piping has not yet been tied-in to the E unit 2 condenser. Heat trace was placed on outdoor piping serving CST "B" this month, f
h 11. LDCR 1902--Add Isolation Valve and Trap to Pipe Serving Main Feedpump p Turbine Drain Tank h Installation of these piping components was accomplished during the current s unit 1 forced outage. This modification is now complete.
ECN 5664--Wells Fargo Tamper Indication 12.
[ Prefabrication of electrical componenet assemblies to be installed for this modification is continuing as well as checkout of existing cables.
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Plant Maintenance Summary ;. . e .;
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y Field Services (continued) 2... ic f. - '
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i 13. ECN 5495--Field Services Building Electrical Work N.k
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? Work is centinuing to complete the building electrically as material flb .
ar.d manpower allow.
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- 14. ECN 5939--Main Feed Pump Turbine Condenser (MFPTC) [. #-
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Installation of a temporary platform is nearing completion in preparation ;7 , .p. -
1 for the feedwater heater tube bundle replacement during the unit I cycle 2 : .
.+ refueling outage. Fabrication of lifting beams is in progress for this .. Y.(1 .
J:f modification as well. .j ' ). . -
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,f. , ' 15. ECN 5560--Manhole Fire Detector T.emoval-- M'.fi.n..
r .. v g, .. e 1 Work is continuing this month to remove manhole fire detectors. t .. . . .
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'.' 16. ECN 5903--Strainers and Access Platform *\
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5-drain tanks is continuing. "?.%
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- 17. ECN 5194--Gaseous Effluent Radiation Monitoring 'Ji pl
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.? of the shield building wall for tubing installation was accomplished y.".
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- 18. ECN 5723--Condenser Sparger for Condensate System > . P-
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j The unit I sparger was replaced during the present forced outage by a (;.2: 7
> larger diameter one in a new configuration. The unit 2 sparger has not s ': > T :.
g., yet been replaced. ' f 1.;
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[ 19. ECN 6047--Reactor Coolant System Level Indication Y I. .j s .,
9 Installation of the reactor coolant system level tubing was accomplished S,h. s .9 k
- during the current unit I forced outage. The sightglass portion of this j'yj.
system will not be installed until the unit I cycle 2 refueling outage .T;f
- j. due to delays in providing the sightglass. 4.f.'
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.; . 20. ECN 5770--Condenser Vacuum Exhaust High Range Noble Gas Effluent Jkf y Radiation Monitors
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),- Work progressed for both the unit I and unit 2 portion of this ECN as ,,:..
1 conduit installation continued for each unit. .%
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- 21. ECN 6050--High Pressure Fire Protection System Modification .4 I- .E t m..:.9. .
Q Fabrication and instaliation of new pipe supports on the high pressure j!;, y 7 fire protection system serving the control building mechanical equipment Q, e room is continuing. : ;f.14
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Plsnt Maint ntnco Summ ry (Continued)
Field Services (continued)
- 22. ECN 5713--Steam Generator Upper Manway Access Platform The unit I steam generator No. 3 upper manway access platform was installed .
during the current unit 1 forced outage. l
- 23. ECN 5457--Replacement of Solenoid Valves Work was completed to change out solenoid valve parts prior to replacing existing solenoid valves. In addition, some of the primary containment l air radi !;n wonitor valves and main steam valves were replaced during the current unit 1 forced outage.
- 24. ECN 5867 Fuel Transfer System The unit I work was aborted this month when it was determined that the track and the outboard upender cage were damaged. The modification work was complete and system functional testing was underway when the damaged equipment was discovered. The unit 2 mechanical work is in progress. The unit 2 electrical work remains to be done.
0-RE-90-134/141 Installation of conduit continued this month on elevation 714 of the auxiliary building. Electrical work per ECN 5871 will follow that for ECN 5119.
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- 26. ECN 5034--Steam Generator Access Platforms / Ladders f
A ladder,and step off paltform was installed from the elevation 679
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floor in order to provide access to the numbers 1 and 4 steam generators.
Further work will be done on this ECN during the unit I cycle 2 refueling l outage.
- 27. L1895 Turbogenerator Turning Gear Motor Local Cut-Off Switch This switch was installed for the unit I turbogenerator this month.
- 28. ECN 5410--Unit 1 Annulus Fire Protection An additional fire protection sprinkler and associated piping is to be installed in the unit annulus next month. Prefabrication of this piping is complete.
- 29. ECN 5870--Auxiliary Building to Turbine Building Drains Final pipe hangar work is all that remains for this modification. Progress was made on this work this month as only rework of one hanger remains.
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I Pltnt M:intentnca Summary (Continued)
Field Services (continued)
-30. ECN 5856--Pressurizer Loop Seal Drain Piping Prefabrication of the unit 1 pressurizer loop seal drain piping has begun.
- 31. ECN 5196--Primary Containment High Pressure Monitoring Work resumed this month on this modification with installation of conduit and cable as well as instrument panel wiring.
- 32. ECN 60364-Repull Cable For 1-FCV-77-20 Replacement of a faulty control cable for this valve required routing a new conduit. The cable has now been completely installed.
- 33. ECN 5197--Reactor Vessel Vent
-Some further work was accomplished this month on this modification as instrument mounting supports were modified in the control room panel 1-M-4.
- 34. ECN 5007--Condenser Vacuum Pumps 1A & IB Replacement The new condenser vacuum pumps 1A & IB were completely installed and are in operation. Removal of the old 1A, 1B, & IC pumps and installation of the new IC pump remain.
- 35. ECN 5277--Miscellaneous Pipe Support Repairs Pipe support 1-CH-230 for the condensate system was modified to eliminate an existing interference with adjacent equipment. Further work for this ECN will be accomplished as manp.ower allows.
- 36. LDCR 1847--Chemical Feed Supply to the Condensate Polisher Discharge Header The chemical feed supply piping (aminonia & hydrazine) was tied into the chemical feed system respective supply headers as well as into the condensate polisher discharge header during the current unit 1 forced outage. The unit 2 piping is in place but the unit 2 pipe tie-ins remain to be made during a unit 2 outage.
- 37. ECN 5429--Hydrogen Mitigation System Conduit installation began in upper containment this month for the four additional hydrogen igniters to be installed there. The junction boxes have been mounted in upper containment as well. Cable has been pullec from the distribution panel in the auxiliary building to the steel containment vessel and some cable terminations were made this month at the outboard penetrations.
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[ Plant Maintentnce Summary (Continued)
! Field' Services-(continued)
V h '38. ECN 5024--Steam Generator-Layup System Prefabrication of unit 1 piping to be installed for this new system began this month. Non outage unit 1 piping installation is scheduled to begin when sufficient piping is prefabricated. Installation of unit I conduit
' v for this new system began this month and is expected to be complete early in January.
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- 39. .ECN 600--East Valve Room Security Bars Prefabrication of the. bars' began this month. Installation of the bars over the valve room blow out panels will begin when prefabrication and mar. power allows.
- 40. LDCR 1934--Construct Paint Storage Building
.The building structural work is nearing. completion. Inctallation of
-lights, fan, fire alarms, fire protection piping, sad compressed air piping is incomplete as well as final weatherizing of the building.
- 41. ECN 5104--Moisture Separator Reheater (MSR) Housing Work resumed this' month to complete reinstallation of the housings surrounding the outdoor MSR valve compartments.
- 42. .ECN 5555--High Pressure Fire Protection Pipe Supports Work is nearing completion ~ to :nodify the high pressure fire protection support system in order to steady the deluge valve pressure switches located in the piping. The switches are located in several places in the auxiliary building.
- 43. ECN 5484--Ice Condenser Power Outlets Prefabrication of' the' unit 1 ice condenser 120 volt power conduit hangers is nearing completion. Conduit installation on the end wall is underway.
The work inside the ice condenser has not yet started and will be performed during the unit I cycle 2-refueling outage.
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2 TENNESSEE VALLEY AUTHORITY Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, Tennessee 37379 JAN 131984 Nuclear Regulatory Commission Office of Management Information and Program Control Washington, DC 20555 Gentlemen:
Enclosed is the December 1983 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):
Director, Region Il Director, Office of Management Nuclear Regulatory Commission Information and Program Control Office of inspection and Enforceraent 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 and Enforcement Atlanta, GA 01339 Nuclear Regulatory Commission Washington, DC 20555 (10 copies)
Mr. A. Rubio, Director Electric Power Kesearch 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 (1 copy)
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An Equal Opportunity Employer