ML20092C093

Monthly Operating Repts for Jan 1992 for Quad Cities Nuclear Station Units 1 & 2

ML20092C093
Person / Time
Site:	Quad Cities
Issue date:	01/31/1992
From:	Michael Benson, Tietz G COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GCT-92-005, GCT-92-5, NUDOCS 9202110266
Download: ML20092C093 (21)

Text

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i Commonwealth Edison Quad Cities NucleCf Power Station .

22710 206 Avenue North

. Cordova. Illinois 61242 Telephone 309/654-2241 GCT-92-005

.s I february 3, 1992 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555

SUBJECT:

- Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report NRC_Docke_LHm 50-254 and 50:255 Enclosed for your-_information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and Two, during the month of January 1992.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION Q (?. f G. C. Tietz Technical Superintendent GCT/CALS/dak

. Enclosure cc: A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector I

n.

9202110266 920131 PDR ADOCK 05000254 g) f '

6 R .__

PDR

t QUAD-CITIE~, NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JANUARY 1992 COHHONHEALTH EDISON COMPANY AND IONA-ILLIN0IS GAS & ELECTRIC COMPANY

~NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30

1. ,4

l TABLE OF CONTENTS I. Introduction II. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to facility License or Technical Specifications

, B. Facility or Procedure Changes Requiring NRC Approval l

C. Tests and Experiments Requiring NRC Approval D. Corrective Maintenance of Safety Related Equipment 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 VII.- Refueling Information VIII. Glossary TS 14

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1. - -IXIR000CIl0N

-Quad-Cities-Nuclear. Power Station is composed of two Bolling Water Reactors, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois. The Station is jointly owned by Commonwealth Edison

~

Company and Iowa-Illinois Gas & Electric Company. The Nuclear Steam Supply-5ystems are General-Electric Company Bolling Water Reactors. The 1 Architect / Engineer was Sargent & Lundy, Incorporated, and the primary .

construction ~ contractor was United Engineers & Constructors. The Mississippi River islthe condenser cooling water source. The plant is subject to license numbers.DPR-29 andzDPR-30, issued October.1, 1971, and March 21, 1972,

-respectively; pur'suantito Docket-Numbers 50-254 and 50-265. The date of Initial Reactor criticalities for Units 0ne and Two, respectively were October 18,11971, and April 26,:1972. Commercial' generation'of power-began on

. February 18, 1973 for Unit One and March 10, 19731for-unit Two.

This report was compiled.by Scott Hoodruff and Debra Kelley, telephone

number:309-654-2241, extensions /2936 and 2240.

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1 II..= SVitML0f_0EEBAUNGlXEERIENCE A. Uni.L0nt .

On 1/02/92 Unit One was brought down to 700 MWe for turbine testing. ,

The Chicago Load Dispatch ordered a reduction to 615 MHe for.the early '

morning of 1/03/92.: On-1/22/92 the Automatic Depressur12ation System

-(ADS) was declared inoperative due to possible discrepancies with the

-59" setpoint for-Emergency Core Cooling System (ECCS). A GSEP Unusual Event was entered and an orderly _ shutdown was began. At 19:10 hours. ,

the Unusual-Event was terminated. because engineering had determined that the s_cenario originally analyzed did not apply. The Load had.been

-reduced to 450 MHe. Unit One was-returned to full power and remained at_ full'_ power for the rest of the month.

B. -Unit Two [

Q2R11 st'artei on:.1/01/92 and is scheduled to end on 3/11/92~. The unit was brought =downLto 205 MWe, the turbine was tripped manually to produce an automatic SCRAM at 00:15 hours.

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- y .- , y d-* ** T T "" e ---Ae. m - - - - -y- p

III. 11AtiLOR_ERQCEDURLCHANGES.._11SLS mEXEERIMENIX.

AND_SAEEILRELAIEDJalHIENANCE Amendments _tolatility Lltense or TitthnicaLSpitc11Lcations

_A.

There were no Amendments to the Facility License or Technical Specifications for the reporting period, B. ELC111ty or PEQttdure_Cb1Dge.s_RequiringJfRC_ Approval There were no facility or Procedure changes requiring NRC approval for the reporting period.

C. Itsis_and_Expe timentLReguirin9_NRCJsproy al There were no Tests or Experiments requiring NRC approval for th6 reporting period.

Carr(C_tive _ Mai ntca&RCt._Df_.iale.ty_Relatad_Egulpment D.

The following represents a tabular summary of the rnajor safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following: Hork Request Numbers, Licensee Event Report Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT 1 MAINTENANCE SUPG4ARY

i. HORK RE00EST -SYSTEM 'EID DESCRIPTION- HORK PERFORMED -

Inspect and repair _ breaker for U1_ As Found: Aux.-switch operator was_ twisted and-Q97001 .6700 i

'4 KV breakers number'39. bent.

i

.AsL Left

. Straightened aux. switch operator.

, Adjusted to 14-1/2" from floor.to top of. roller- [

when breaker is charged and closed._; Tested [

. electrically worked fine.

j Q97582' 5209'- Repair union on fuel _line .As Found: External condition of union' elbow upstream of-motor driven fuel indicated the repeat. disassembly, and reassembly j pump which leaks when diesel runs. with pipe wrenches.. The union was disassembled:  ;

. appearing to be significant1y' tight however the .. [

union seats have some slight cuts in them and:1t'

' appear they.have been cleaned up before.  :

As left: . Disassembled union, cleaned matingL .i surfaces, polished with emery clothi. applied (

pcreatex thread sealant to seating areas. [

Q96776 8300 Investigate _why no ground was As Found: Ground was found in 2-203-2D MSIV limit  !

found on hard positive ground; switch. _

! +125 V, -5V battery volt of 130V. As left: With support of OAD, checked panel 1A i cubicle A02 on circuit 11. Checked relay house-  !

for moisture, but it was dry. Control room 902-3 .

-panel was then cleared of ground indication. It f was determined that probable cause of the .L indication was due to a moisture in limit switch i probably due to a steam leak. ,

l 089251 0263 Investigate.and repair pressure As Found: Computer point C211 reads +7.554 psi; t indicators 2-263-1558, digital indicator reads +9 psi; recorder reads i L 2-263-153B, 2-263-158, 2-263-115, +5 psi. . 'l l which read 10 psi. higiner than all As Left: Calibrated 2-263-155B, 2-263-153B, l l other_ pressure indications. _2-263-158, 2-263-115. Found digital indicator-  ;

2-263-115 out of tolerance. This indicator was i zeroed and spanned until a good indication was 't received.

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UNIT 2 MAINTENANCE

SUMMARY

EID DESCRIPTION HORK PERFORMED HORK RE00ESI. SYSTEM Q97353 5741 Repair U2 reactor building supply As Found: Two check valves removed from line damper failed test. piping had white powdery substance probably due to mositure and teflon tape.

As left: Removed piping and labeled all schematic piping; cleaned out pipes, changed out check valves, replaced piping back in place.

Repair or replace reactor As Found: Exterior looked OK and flows go in the 097386 5741 building vents fail safe check right direction, valve. As Left: Installed new check valves to replace previous check valves.

Repair and replace U2 fall safe As Found: Valve exterior looked OK and flow goes Q97384 5742 check valve on reactor building in the right direction.

As left: Installed new check valves to replace vents.

previous check valves.

Repair and replace U2 fall safe As Found: Valve exterior was painted and flow 5742 Q97385 check valve on reactor building goes in the right direction.

vents. As left: Installed new check valves and replaced the pipe to tubing connectors.

8294 Replace breaker and wire and As Found: Breaker terminal was bad with some Q97363 appears to be no. 8, which showed wires showing signs of overheating.

signs of overheating. As left: Removed old breakers, installed new breaker.

Investigate 1/2 A SBGT fan As Found: Common adjustable setting set at "LO".

097492 8294 breaker MCC 29-4 A4 which tripped. As Left: Settings were checked with the breaker test set, The rew adjustable common setting is "4". Installed breaker in it's cubicle.

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IV. LICENSELEVElfLREEORIS The following.is a tabular summary of all licensee event reports for Quad-Cities Units Or., and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the Technical Specifications.

UNIL1 Licensee Event ReporLNumber Ditta Ilile_.oL0cturrence 92-001 01-06-92 RHCU isolation on non-regen Hx outlet Hi Temp.

UN11_2 92-001 01-01-92 U-2 Reactor scram during turbine trio test for a Group I isolation.92-002 01-03-92 LLRT leakage limits exceeded.92-003 01-06-92 R.B. Vent isolation and SBGT start.92-004 01-16-92 Inadvertent closure of the U-2 Reactor Building isolation damper.92-005 01-25-92 SBGT initiation and Reactor Building vent l 1 solation from fuel pool monitor switch

! falling out of the panel.

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V. DATA _ TABU 1AllDNS The following data tabulationt are presented in this report:

A. _ Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions l-79 14

APPENDIX C

. OPERATING DATA REPORT DOCKET NO $0-Z$4 VN!T Qne DATE ItbFWATJ_L 139Z_

COMPLETED BY Matt _ Den &On TELEPHONE 1309)Jhi-22.41 OPERATING STATUS 0000 010192

1. REPORTING PERIOD: 2400 013192_ GROSS HOURS IN REPORTING PERIOD: 244

2. CURRENTLY AUTHOR! LED POWER LEVEL (HWt): Z$11 HAX, DEPEND. CAPACITY: 269 DESIGN ELECTRICAL RATING (HWe-Net): 289

3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (HWe-Net): N/A

4. REAS(NS FOR RESTRICTION (If ANY):

THIS HONTH YR TO DATE CUMULATIVE

5. NUMBER OF HOURS REACTOR WAS CRI11 CAL . . . . . . . . . . . 744 Q. 7442R_ __J322iltl

6. REACTOR RESERVE SHUTDOWN HOURS .................. 0.Q_ 0,A. 341119

7. HOURS GENERATOR DN LINE.......................... 744 E_ 74d10._ 132915tl

8. UNIT. RESERVE SHUTDOWN HOURS ..................... 0,D_ .0,Q_ 90112

9. GROSS THERMAL ENERGY GENERATED ( HWH) . . . . . . . . . . . . . ]B4E90946. _164590220 2a591Z93316

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... J03425,0._ __603475,Q 9262]SILD

11. NET ELECTRICAL ENERGY GENERATED (HWH)............ ._$24H1LQ_ J9_401610_ 87304434,0

12. REACTOR SERVICE FACT 0R........................... 1004Q. ' 109,Q_ 9440

13. REACTOR AVAILABILITY FACT 0R...................... 100,R_ ____J00.0 96,3

14. UNIT SERVICE FACTOR ............................. 10QiQ_ 10),Q_ 91,1

15. UNIT AVAILABILITY FACTOR ........................ 10010_ 100,0_ 191.1

16. UNIT CAPACITY FACTOR (Using HDC) ................ 100,0_ ____] D Q2 0_ 77 0

17. UNIT CAPACITY FACTOR (Using Design HWe) ......... 1002A_ 1001Q_ 75,8

18. l#4tT FORCED OUTAGE RATE ......................... 0.0 0.Q_ - $21

19. SHUTDOWNS SCHE 00 LED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH):

' 20.LIF SHUTDOWN AT LMD OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

21. UNITS IN TEST STiTUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY-COMMERCIAL OPERATION in u 1.16-9 r.

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APPENulX C OPERATING DATA REPORT DOCKET NO $0-20 UNIT lyo DALE labtuREy b!29L._

C0ttPLETED BY litiLBeatan iELEPHONE DQ2LM4-2241 1

OPERATING $TATUS~

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0000 010192

1. REPORTING PERIOD: _g4Q0 013191_, GROSS HOURS IN REPORTING PERIOD: 1.44 1

2. CURREN1LY AUTHORIZED POWER LEVEL (HWt): 2511 HAX. DEPEND. CAPACITY: 169 DESIGN ELECTR! CAL RATING (HWe-Net): 2B9 -

=3. POWER LEVEL TO WHICH RE$TRICTED (IF ANY) (HWe-Net): N/A

4. REASONS FOR RESTRICTION (IF ANY):

THIS HONTH YR TO DATE CUHULATIVE

5. NUNDER OF HOURS REACTOR WAS CRITICAL ............ 0.3 Q.3. 133403J l I

6. REACTOR RESERVE SHUTDOWN HOURS .................. DJ_ 0.Q. _Z9E6 l l

7. HOUR S GEIFRATOR ON LINE . . . . . . . . . . . . . . . . . . . . . . . . . 0.3_ 0.3 129864,8

8. UNIT RESERVE $HUTDOWN HOURS ..................... 0.0 0.0 702J

9. GROSS THERHAL ENERGY GENERATED (HWH)............. 00_

1 0J.. 2000HJDSLD

10. GROSS ELECTRICAL ENERGY GENERATED (HWH).......... ___504Q 50.0 _A934911.9,Q

11. NET ELECTRICAL ENERGY GENERATED (HWH) . . . . . . . . . . . . -0.0_ 0Q 2 ._051111 E 0

12. REACTOR SERVICE FACT 0R........................... 0.0 0.,D_. 73J

15. REACTOR AVAILABILITY FACT 0R...................... 0.0 00_ 75J

14. UNIT SERVICE FACTOR ............................. 0.0 0.0 71J l 15. UNIT AVAILADILITY FACTOR ........................ 0.0 0.0- 7222

-16i-UNIT CAPACITY FACTOR (Using HDC) ........ ....... - 1. 0 . . -1.0 61,2

17. UNIT CAPACITY FACT 0k (Using Design HWe) ......... -1.0. -1.0 59,2

18. UNIT FORCED OUTAGE RATE ......................... 0.0 0 0_ 8,0 l.

19. SHUTDOWNS St.rtEDULED OVER NEXT 6.HONTHS (TYPE,- DATE. AND DURATION OF EACH):

'20. X SHUTDOWN AT-END OF REPORT PER100. ESTIMATED DATE OF STARTUP: 3/11/92 ..

21. UNITS IN TEST STATUS (PRIOR TO C0FNERCIAL OPERATION):

FORCCAST. ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY COHHERCIAL OPERATION l

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APPENDIX B AVERAGE DAILY. UNIT POWER LEVEL DOCKET NO 50._254 UNIT One DATE f.ebruarL 3 _lSS2 COMPLETED BY- Ma1LBenson TELEPHONE 1309L651-2241 MONTH _JanuArL1932 -)

i DAY-AVEREAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL  :

(HWe-Net) (MHe-Net)

1. _819 ._,

17, 811_ _

2. 716 18. 817 ___

3. 7f6 19. 816

4. BIS 20. 817

5. 818- 21. 817 6, 816 2 2 .~ 63 3 7.- 817 23. 817

8. _R17 24. 821

9. 818 25. 820

10. 820 26. 820 11, 818 27. 818

12. 817 2E. - 816

13. B19- 29. 818

14. 817 30. 813

15. 818 31. 815

16. 818 INSTRUCTIONS

.On this form, list the average daily unit power level in MHe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

These figures willlbe used to plot a. graph for each reporting month. Note that_when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds-the 1007. line.(or the restricted power level line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.

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4 APPENDIX.B L AVERAGE DAILY UNIT POWER LEVEL DOCKET NO 50-265_

ll UNIT. Iwo-DATE f.ibt.UArt.3 d19L,_

L COMPLETED BY MatLBeaton L TELEPHONE 13091_651-2241. . _

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HONT_H M aavarv 1992 DAY;AVEREAGE DAILY-P0HER LEVEL- DAY AVERAGE DAILY-P0HER LEVEL

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(HWe-Net) (MWe-Net)

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17.

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2. 0 18. O r

l.' 3.- 0 19. 0 L-

74.- .

-0 :20. O L, - 5; . 0 21. . 0

-0 22.

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-i 7 . - 0 23. 0

8. 0 24. 0

9. 0 25. 0

10. 0 26. 0 _

11. - 0 27. 0 --

12. - 0 28. 0 l 113 7 0- -29. L14.- 0- 30. O L 15. _ -

0 -- 31. G ,

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16.- 0  !

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LINSTRUCT' IONS . -

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i; W .On this form, list thelaverage dally unit power level'in HHe-Net for each day K 11nitheireporting month. Compute to the nearest whole megawatt.

Li These; figures willibe_used to plot a graph for.each reporting. month. . Note 1

.that when maximum dependable capacity is used for. the net electrical ; rating of D the unit, there may be occasions when the daily average power level exceeds the 100% -line (or: the restricted power level line). .In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly..

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APPENDIX D -

UNIT SNUTDOWNS AND: POWER REDUCTIONS '

- .DOCKE7 NO. .50-254L.

UNIT NAME Unit i M P ETED BY.' -

DATE February ^3, '1992: .. REPORT MONTH January 1992 TELEPHONE- '309-654-2241- - -

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LICENSEE. fu m@.

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s., DURATION M Eg EVENT $ "-

NO. :DATE REPORT NO.- CORRECTIVE ACTIOffS/COrWENTS (HOURS) g 92-01 1-22-92' F 0 D- ADS declared INOP along with all other ECCS. An Unusual Event declared. Unusual.

Event terminated when engineering.

determined that the scenario originally analyzed on.1-21-92 did not apply to.QCNPS.

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- K T E .N 2 C I T 9 O N A D U D

VI. UNIQULREEOR11NGlE0VIREMEMIS The followinglltems are included in this report based on prior commitments to the commission:

A. Main Steam _ Relief Valve _0penttoni

-There were no Main Steam Relief Valve Operations for the reporting period.

B. Control Rod Drive Scram TimingJ)tta_for_UnLti_One_and_Ivo There was no Control Rod Drive scram timing data for Units One and Two for the reporting period.

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VII, REEUELING_1Hf.0RMA110N The following information about future reloads at Quad-Cities Station was requested in a January 26, 1976, licensing memorandum (78-24) from D, E, O'Brien to C, Reed, et al., titled "Dresden Quad-Cities and Zion i Station--NRC Request for Refueling Information", dated January 18, 1978.

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QTP 300-S32 ,

Revision 2 l QUAD CITIES REFUELING October 1989 INFORMATION REQUEST l.- Unit:- 41' Reload: II Cycle:- 12

2. Scheduled-date for next refueling shutdown: 9-5-92 i

3. Scheduled date-for restart following refueling

12-5-92

4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment:

NOT AS YET DETERMINED.

-- 5 . Scheduled date(s) for submitting proposed licensing action and

-supporting information:

NOT AS'YET DETERMINED.

6. Important_ licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating

-procedures:

NONE AT PRE 6ENT TIME.

+-

7. -The number of fuel assembl!9s. .

-a.- Number of assemblies in core: 724

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b.- Number of assemblies in spent fuel pool: 1405

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8. LThepresentlicensedspentfuelpoolstoragecapacityandthesizeof' any increase in Itcensed storage capacity that has been requested or'is planned in number of fuel assemblies:

a. Licensed: storage-capacity for spent fuel: _3657

b. -Planned increase _in licensed storage: 0

9. The projected date of the last refueling that can be discharged to-the spent fuel pool assuming the present licensed capacity: 209,9, APPROVED

( '" ') i 14/0395t- -. DCT 3 01969 O.C.O.S.R..

QTP 300-532 Revision 2 ,

QUAD CITIES REFUELING October i989 INFORMATION REQUEST

1. Unit: 02 Reload: 10 Cycle: 11 __

2. Scheduled date for next refueling shutdown: 01/01/92

3. Scheduled date for restart following refueling: 03/11/92

4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: Yes, as listed below:

1. Remove Table 3.7-2

2. Modification to turbine control valve fast acting solenoid valve.

3. Modification to HPCI turbine exhaust steam line.

4. IIPCI/RCIC 24-hour shutdown action provision.

5. Scheduled date(s) for submitting proposed licensing action and information:

supporting

1. 01/15/92 ~

2. 04/18/91

3. 06/28/91

4. 12/31/91

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

7. The number of-fuel assemblies.

a. Number of assemblies in core:

3115*

b. Number of assemblies in spent fuel pool:

8. The present licensed spent fuel pool storage capacity and the si:e of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3897

b. Planned increase in licensed storage: 0

.9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2009

• 48 new fuel assemblies in new fuel vault.

APPROVED i

( '" ') OCT 3 01989 14/0395t -l-O.C.O.S.R.

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l VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defines below:

- ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Honitoring ANSI - American National Standards Institute APRM - Average Power Range Monitor ATHS - Anticipated Transient Hithout Scram BWR - Boiling Hater Reactor CRD - Control Rod Drive EHC - Electro-Hydraulle 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 IPCLRT - Integrated Primary Containment Leak Rate Test IRH - Intermediate Rsnge Monitor l ISI - Inservice Inspection LER - Licensee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode of RHRs LPRM Local Power Range Monitor HAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratto HFLCPR - Maximum Fraction Limiting Critical Power Ratio HPC - Maximum Permissible Concentration.

MSIV - Hain Steam Isolation Valve NIOSH - National Institute for Occupational Safety and Health PCI - Primary Containment Isolation PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCH- - Reactor. Building Closed Cooling Hater System-

, RBH - Rod Block Honitor RCIC - Reactor Core Isolation Cooling System-RHRS - Residual Heat Removal System RPS- - Reactor Protection System RHH - Rod North Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS

- SDV - Scram Discharge Volume SRM - Source Range Honitor TBCCW - Turbine Building Closed Cooling Water System TIP- - Traversing Incore Probe TSC - Technical' Support Center-L k

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