ML20042A740
| ML20042A740 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/03/1981 |
| From: | Tubbs R COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20042A735 | List: |
| References | |
| NUDOCS 8203230731 | |
| Download: ML20042A740 (21) | |
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY 1981 COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 okohhhj4 DO PDR
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TABLE OF CONTENTS j
l 1.
Introduction 11.
S0mmary of Operating Experience ~
A.
Unit One B.
Unit Two i
lil. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.
Amendments to Facility License or Technical Specifications 1
B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approvai D.
Corrective Maintenance of Safety Related Equipnent IV.
Licensee Event Reports V.
Data Tabulations A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
Unique Reporting Requirements A.
Main Steam Relief Valve Operations B.
Control Rod Drive Scram Timing Data.
Vll.
Refueling information Vill.
Glossary I
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1.
INTRODUCTION Quad-Cities Nuclear Power' Station is composed of two Boiling Water React 6rs, each with a Maximum Dependable Capacity of 769 MWe net, located
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in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison Company and towa-lllinois Gas & Electric Company.
The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors.
The Architect / Engineer was Sargent & Lundy, Incorporated and the primary construction contractor was United Engineers & Constructors.
The con-denser cooling method is a closed-cycle spray canal, and the Mississippi River is the condenser cooling water,souce.
The plant is subject to license numbers DPR-29 and DPR-30, issued October 1,1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor criticalities for Units 1 and 2, respectively, were
.1 October 18, 1971, and April 26, 1972.
Commercial generation of power began on February 18, 1973, for Unit I and March 10, 1973, for Unit 2.
This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 245 and 174.
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11.
SUMMARY
OF OPERATING EXPERIENCE l
A.
UNIT ONE July 1-6:
Unit One began the reporting period holding load at 793 MWe.
Load was held until the isolation of the "D" heaters forced a reduction to below the corresponding limiting load.
The heaters were isolated when the Moisture Separator Drain Tank (MSDT) normal drain was closed due to the air supply to the air operated isolation valve being closed.
On July 3, while load was being reduced to 450 MWe to reset the MSDT emergency drains, an alarm for the B Recirculation Pump motor lube oil was received. The Drywell was de-inerted and an entry was made to add oil.
Load was increased, starting at 0630, throughout the remainder of the day.
On July 4 and 6, load was reduced at the request of the Load Dispatcher due to minimum load conditions with load being increased through July 5 July 7-9:
On July 7, at 0635, the Reactor scrammed on Reactor Vessel Low Water Level.
The low level scram was initiated by a condensate pump trip and the standby pump not auto-starting.
The Unit was put back on line at 1854 and load was increased at various rates.
On July 8, load was held at 550 MWe due to high suppression chamber temperature.
July 10-18: On July 10, load was reduced for minimum load conditions for approximately five hours.
Load was returned to 600 MWe at 0900.
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On July 11 and 12 load was reduced to 400 MWe to enable operation using the Mississippi River for 100 percent cooling in an effort to reduce suppression chamber temperature.
On July 13, load was brought up to 600 MWe, with load still limited by suppression chamber temperature.
Load remair.ed at this level except for a two and one half hour drop to 500 MWe on July 15 July 19-24: The B Recirculation Pump motor lube oil alarm was received again.
Load was reduced to 400 MWe, the Drywell de-inerted, and an entry was made.
Oil was added to the motor.
Load was returned to 600 MWe on July 20 and remained at that level until July 23 when it was increased to 700 MWe.
July 25-28:
Load was reduced, once again, in an effort to lower suppression chamber temperature. While holding load at 400 MWe, the endeavor was successful.
Later, on July 25, the control rod pattern was adjusted by the Nuclear Engineer.
Load was held until 0430 on July 27 when it was increased to 600 MWe at 50 MWe/ hour.
The rate was then decreased to 5 MWe/ hour and was continued through July 28.
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OPERATING DATA REPORT DOCKET NO._
50-265 UNIT T U_O DATEAugust 3 1985
-m COMPLETED BYRobert C Tubbn TELEPHONE 309-654-2241X174 OPERATING STATUS 0000 070181 1.
Reporting period:2400 073181 Gross hours in report.ina period:
744 2.
Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
This Month Yr,to Date Cumulotive 5.
Number of hours reactor was critical 744.0 4991.6 63824.4 ~ '
6.
Reactor reserve shutdown hours 0.0 0.0 2985.8 7.
Hours generator on line 744.0 4965.8 61247.0 B.
Unit reserve shutdown hours.
0.__0 0.0 702.9 9.
Gross thernal energy generated (MWH) 1369866 11027203 126227611
- 10. Gross electrical energy generated (MWH) 420673 3485473 40207024
- 11. Het electrical energy generated (MWH) 397704 3307082 37664034
- 12. Reactor service factor 100.0 98.1 79.8
- 13. Reactor ovallobility factor 100,0 98.1 83.6
- 14. Unit service factor 100.0 97.6 76 4
- 1. E. Unit uvoilobility factor 100.0 97.6 77.5 L6. Unit capacity factor (Using MDC) 69.5 84.5 65.3
- 1. 7. Unit capacity factor (Using Des.MWe) 67.8 82.4 59.7
- 10. Unit forced outoae rate 0.0 1.0 8.5
- 19. Shu tdowns sched uled over next 6 Months (Type,Date,and Dorotion of each ) :
NA
- 20. If shutdown at end of report period,estinated date of startup ____________
- The MC ncy be lower than 769 M'.'e dtring periods of high cmbiant ter.perature due to the thernal perfarnance of the spro; canal.
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OPEPATING DATA REPOR'I DOCKET NO.
50-254 UNIT ONE LATEAunust 3 1Y1:1 C0tiPLETED BYR ober t f'
Tubbn TELEPHONE 309-654.-22412174 OPERATING STATLIS 0000 070181 1.
Reporting period:2400 073181 Gross hours in reporting period:
744 2.
Currently authorized power level (MWt)- 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 3.
Power level to which restricted (if any)(Mue-Net): NA 4.
Reasons for restriction ( i f' ony):
This Month Yr to Date Cumulative 5.
Number of hours reactor was critical 726.9 4057.6 65563.9~~
5 6.
Reactor reserve shutdown hours 0.0 0,0 34?i.9 7.
Hours generator on line 671.2 4739.0 62622.8 0.
Unit reserve shutdown hours.
0.0 0.0 909.2 9.
Gross thermal energy generated (MWH) 1262778 10723566 126965654
- 10. Gross electrical energy generated (MWH) 399120 3499121 40878036 ti. Net electrical energy generated (MWH) 366422 3253750 3011.1029
- 12. Reactor service factor 97.7 95.5 81.1
- 13. Reactor ovallobility factor 97.7 95.5 G5J
- 14. Unit servire factor 90.2 93.2 77.4
- 15. Unit availabil. tty factor 90.2 93.2 78.6
- 16. Unit capacity factor (Using MDC) 64.0 83.2 61.3
- 17. Unit copocity factor (Using Des.MWe) 62.4 81.1 59.7
- 18. Unit forced outoge rate 9.8 2.8 7.4 g
- 19. Shutdowns scheduled over next 6 nonths (Type, Dote,and Duration of each):
NA
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- 20. If shutdown at end of report period,estinated date of startup _____________
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- The RC ncy be Icaer then 769 M'*'e durin; perieds of high cr.bioni terperetcre due to the thermi perf6rence of the sprey com!1.
V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report
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B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions
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IV.
LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.
UNIT ONE Licensee Event Report Number Date Ti tle of Occurrence 81-13/03L 7-17-81 Drywell High Pressure Switch Setpoint Drift 81-14/03L 7-23-81 Torus to Reactor Building Vacuum Breaker inoperable l
Solenoid 8-15/03L 7-24-81 Turbine First Stage Low f
Pressure / Scram Bypass Switch Setpoint Drift UNIT TWO h
81-11/03L 6-8-81 Failure to Demonstrate Unit Two Diesel Generator Operabi l i ty 81-13/03L 7-15-81 Reactor High Pressure /
l Automatic Blowdown i
Pressure Switch Setpoint Drift l
81-14/03L 7-24-81 Torus Vacuum Breaker l
Pressure Switch Setpoint Drift 1
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UNIT TWO MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LLR OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13338 2-5746A, 2A RHR Fan was making The cooling unit was Replaced belts and Room Air Unit excessive. noise still operable.
RHR operated fan.
fromwornlV-belts.
pumps were still ope rab l e.
Q13322 2B-5741, Reactor Faulty co.il in the Reactor Building Changed coil on solenoid Building Vent solenoid valve.
ventilation isolation valve.
Isolation Valve valve would not ope ra te.
In-line valve was operable.
Q12855 1/2-7541-6A, Loose fittings were Not controlling flow Found loose fitting on Flow Controller leaking air to the p rope r l y.
SBGT train outlet of controller.
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'A' SBGT flow control valve. was operable.
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UNIT ONE MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q13561 81-14/03L l-1601-20B Torus Faulty solenoid The air operated Installed new solenoid Vacuum Breaker valve on air vacuum break.er valve on ai r operator.
operator.
would not open.
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PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications
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On June 25, 1981, Amendments 72 and 65 were issued to DPR-29 and DPR-30 respectively. These Amendments consist of changes
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in the Technical Specifications for each of the two units which change the definition of operable to:
A system, subsystem, train, component or device shall be operable when it is capable of performing its specified function (s).
Implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal and emergency electrical power sources, cooling or seat water, lubrication or other auxiliary equipment that are requi red for the system, subsystem, train, component or device to perform its function (s) are also capable of performing thei r related support function (s).
Also, a new section, 3.0/4.0 Limiting Conditions for Operations (General), was added which defines corrective action to be taken if a system, subsystem, train, component or device is inoperable beyond the scope of a specific Limiting Condition for Operation.
.L On July 9, 1981, Amendments 73 and 66 were issued to DPR-29 and DPR-30 respectively. These Amendments consist of changes in the License for each of the two units which adds a section allowing power operation with one recirculation loop out of service provided eight specific criteria, as listed in the License, are satis fied.
B.
Facili ty or Procedure Changes Requi ring NRC Approval There were no Facility or Procedure Changes Requi ring NRC approval for the reporting period.
C.
Tests and Experiments Requiring NRC Approval There were no Tests and Experiments Requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related i.uintenance performed on Unit One and Unit Two during the reporting period.
The headings indicated in this summary include:
Work Request Numbers, LER Numbers, Components, Cause of Mal-functions, Results and Effects on Safe Operation, and Action
, Taken to Prevent Repetition
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July 29-31: The load increase was being c antinued until a Steam Jet Air Ejector High Flow alarm was received at 0507 condenser vacuum started to drop, and load was reduced to 357 MWe.
At 0535, the Reactor scrammed on low condenser vacuum.
The Reactor was brought critical at
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1459 and a search to find the source of inleakage was started.
A Helium Mas's Spectrometer was brought in to aid in the search on July 30.
On July 31, the standby SJAE was put on and the Unit was put on line at
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1805, to improve the leak detection capabilities.
Load was held at 250 MWe while the search continued, and ended the reporting period in that condition.
B, UNIT TWO July 1-10:
Load was held at the maximum attainable with the exception of drops on July 4, 5, 6, and 10 due to minimum load conditions.
July 11-12:
Over this weekend, load was reduced to 400 MWe to aid in cooling the suppression chamber.
July 13-24:
In this twelve day period, load was held at 600 MWe.
This limitation was imposed by the suppression chamber temperature.
Load was reduced briefly on July 15 by the Shif t Engineer to try and cool the suppression chamber, and on July 22, 23, and 24 due to minimum load conditions.
July 25-26:
Over this weekend, load was reduced again to cool the suppression chamber.
July 27-31:
On July 27, load was brought back up to maximuni, which was about 600 MWe, due to fuel depletions On July 28 and 29, load was reduced due to minimum load conditions.
Load was held at the maximum attainable and the Unit ended the reporting period holding a load of 592 MWe.
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APPENDIX 0 QTP 300-S13 50-265 UNIT StiUTDOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.
March 1978 quad-Cities Unit Two DATE
~Auoust 3.
1981 REPORT MONTH JULY 1981 TELEPHONE 309-654-2241, extension 174 5
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gg5 LICENSEE pg gg po DURATION $
p3 EVENT
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(HOURS) y5g REPORT NO.
NO.
DATE u-8 CORRECTIVE ACTIONS / COMMENTS R
81-14 810711 S
0.0 F
5 SA ZZZZZZ Load reduction to allow full river operation to reduce the suppression pool temperature.
81-15 810725 S
0.0
'F 5
SA ZZZZZZ Load reduction to allow full river operation to reduce the suppression poo) temperature.
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T APPENDlX D QTP 300-513 50-254 UN!T SHUTOOWNS AND POWER REDUCTIONS Revision 5 DOCKET NO.
March 1978 u - iis n One UNIT:NAME COMPLETED BY R C Tubbs DATE
' August 3, 1981 REPORT MONTH JULY 1981 TELEPHONE 309-654-2241, extension 174 m
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@g6 LICENSEE pg gg po DURATION $
53
- EVENT g8 g: 8 (HOURS)
NO.
DATE u.
gj g g REPORT NO.
8 CORRECTIVE ACTIONS / COMMENTS R
J 81-13 810703 F
0.0 A
5 CB MOTORX Load reduction to add oil to B Recirculation Pump Motor lower bearing.
81-14 810707 F
12.3
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HH P UttPXX Reactor scram on low vessel water level, caused by standby condensate pump not starting when required.
81-15 810711 S
0.0 F
5 SA ZZZZZZ Load reduction to allow full river operation to reduce the suppression pool temperature.
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81-16 8107.19 F
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5 CB ~
MOTORX Load reductidn to add oil to B Recirculation l
Pomp Motor lower bearing.
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81-17 810725 5
0.0 F
5 SA ZZZZZZ Load reduction'to allow full. river operation to reduce the' suppression pool temperature.
81-18 810729 F
'60.5 A
3 HD ZZZZZZ Reac. tor scram on low condenser vacuum caused by g' land steam loop seal going dry.
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APPENDIX D AVERAGE DAILY UrJIT POWER L.E. VEL DOCKET tJ 0.
5h-265 Ul'IT Ty0 DATEAvoust 3 1981.
COMPLETED BYRobert C T ithbn TELEPHONE 309-654-2241Xi"/4 HONTH July 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
613.3 17.
558.0 2,
621.4 10, 564.0 3.
592.8 19, 571.8 4.
537.4 20, 553.7 5.
581.6 21.
562.4 m
6.
530.8
- 22. _
536.5 7.
589.0 23.
551.5 B.
591.6 24, 547.6 9.
587.3 25, 379.9 10, 531.7
- 26..
369.1 11.
381.5 27, 507.0 12.
365.5 28, 524.6 13, 524.5 29, 518.5 14, 547.6 30, 566.9 15, 533.4 31, 566.6 16, 563.7 INSTRUCTIONS i
On this fern, list tte overage dcily snit power level in N't;&t fer ecch day in the reporting ncnth.Cer.pute to the neerest whole neanctt.
8, These flavres will he used to plot a croch fer ectt repertina. enth. Note thct.hp r.ciinum deterdcble test:ity is use6 for'the net electrical reting of'th'e Unit there may be 6ccasions when the d211y evert:!e pcwer letiel oceeQs the 16B8 line (or the restricted power level line),In such cases,the average daily snit power ictret sheet shov:1 be festnoted to explain the cpptrent ciently
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APPENDlX D AVERAGE DAILY UNIT P O UE P.
LFUEL DOCKET NO.
E O -tE4 UNIT ONE D AT E A.qqts t 3 1901
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COMPLETED BYRobert C Tubbs TELEPHONE 309-654-2241Xi74 MONTH July 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
( MW e-Ne. t )
(MWe-Net) 1.
740.6 17, 549.5 2.
729.7 18, 555.7 3.
549.1 19, 501.4 4.
549.0 20.
617.3 5.
680.7 21.
468.9 3
6.
642.4 22.
553.0 7.
218.4 23.
590.8 0,
505.7 24.
645.7 9.
537.6 25, 388.2 10, 506.0 26, 422.0 11.
396.4 27.
550.3 1
12.
424.3 28, 666.2 l
l 13.
524.0 29.
135.9 l
- 1. 4.
543.0 30.
-39.0 15.
534.2 31, 22.5 16.
558.3 INSTRUCTIONS On this forn, list the cieregt daily unit power level in MWe-Net for each day in the reporting nonth.Ctepute to the necres? 6 hole neco att.,
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These figstes will be c5ed to plot a grach for ench reportinc ncnth. Note thet wheky overage pcwar levekc:: cit!s the eatinum depend 2ble is LJ vsed fcr the net electrical rating of the Unit tbtre may te bccasant,s when the dol excee i
iC0I line (or tre restricted power level line),.In such cases,the average daily init power output sheet shculd be footnoted to explain the cpacrent onen21y
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VI.
UNIQUE REPORTING REQUIREMENTS The following i tems are included in this report based on prior commitments to the co wission:
A.
Main Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period.
B.
Control Rod Drive Scram Timing Data for Units One and Two There were no Control Rod Drive Scram Timing Data for the reporting period.
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QTP 300-532 Revision 1 QUAD-C! TIES REFUELING Harch 1978
(.
INFORMATION REQUEST
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Unit:
1 Reload:
6 Cycle:
7 2.
Sch$duled date for next refueling shutdown:
9-12-82 (Shutdown EOC6) 3 Scheduled date for restart following refueling:
12-5-82 (Startup BOC7) 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:
No, Plan 10CFR50 59 reloads for future cycles of Quad Cities Unit 1.
The review will be conducted in August, 1982.
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Scheduled date(s) for submitting proposed licensing action and supporting information: August, 1982 for 10CFR50.59 related changes ~ 90 days prior to shutdown.
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Important licensing considerations associated with refueling, e.g., new o'r
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' different fuel design or supplier, unreviewed design or performance analysis i
methods, significant changes in fuel design, new operating procedures:
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New fuel d.csigns:
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The number of fuel assemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
820 8.
The present licensed spent fuci pool storage capacity and.he size of any increase in~IIcensed storage capacity that has been requested or is planned in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
146e Planned increase in licensed storage:
None b.
9 The projected date of the last, refueling that can be discharged to the spent' fuel pool assuming the present licensed capacity: September, 1985 9
(end of batch discharge capability) k
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APR 2 01978
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REFUELING INFORMATION 1
The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) f rom D.E. O'Brien to C. Reed, et. al. titled "Dresden, quad-Cities, and Zion Station -NRC Request for Refueling Information", dated January 18, 1978.
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I QTP 300-532 Revision 1 QUAD-C! TIES REFUELING Harch 1978 b-INFORMATION REQUEST 1.
Unit:
2 Reload:
5 Cycle:
6 2.
Scheduled date for next refueling -shutdown:
8-30-81 (Shutdown EOC5) 3 Scheduled date for restart following refueling:
12-20-81 (StartupBOCI) 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
No, Plan 10CFR50.59 Reloads l
for future cycles of quad Cities Uni t 2.
The review will be conducted by early August, 1981.
Scheduled date(s) for submitting proposed licensing action and supporting 5.
Information: Early August, 1981 for 10CFR50.59 related changes a90 days prior to shutdown.
P l
6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or perforrr.ance analysis methods, significant changes in fuel design, new operating procedures:
New Fuel Design:
1.
Barrier Fuel 2.
Control Cell Core l'
2 e
7 The number of fuct a.ssemblies.
a.
Number of assemblies in core:
724 b.
Number of assemblics in spent fuel pool:
672 8.
The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:
a.
I.icensed storage capacity for spent fuel:
1460 b.
Planned increase in licensed storage:
None 9
The projected date of the last refueling that can be discharged to the spent, fuel pool assuming the present licensed capacity:
September, 1984 cf (End of batch discharge capability)
A. ' P P R O V E D[-
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~' APR 2 01978
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Vill.
GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
l ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment l
Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATWS Anticipated Transient Without Scram BWR Boiling Water Reactor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant injection System HRSS High Radiation Sampling System IPLCRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI In-Service inspection LER Licensee Event Report LLRT Local Leak Rate Test LPCI Low Pressure Coolant injection Mode of RHRS LPRM Local Power Range Monitor a
MAPLHGR Maximum Average Planar Linear Heat Generation Rate MCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment isolation Preconditioning Interim Operating Management Recommendations PCl0MR Reactor Building Closed Cooling Water System RBCCW Rod Block Monitor RBM RCIC Reactor Core isolation Cooling System RHRS Residual Heat Removal System i
I RPS Reactor Protection System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System Standby Liquid Control SBLC SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume S R.,
Source Range Monitor TBCCW Turbine Building Closed Cooling Watcr System TIP Traveling Incore Probe TSC Technical Support Center
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