ML20154D981

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1988
ML20154D981
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 04/30/1988
From: Deelsnyder L, Robey R
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
0027H-0061Z, 27H-61Z, RAR-88-20, NUDOCS 8805200048
Download: ML20154D981 (20)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ . _ ___ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

e f .' .

QUAD-CITIES NUCLEAR POWER STATION UNI.4 1 AND 2 MONTHLY PERFORMANCE REPORT APRIL, 1988 COMMONWEALTH EDISON COMPANY AND 10HA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 SL:1M 0027H/0061Z 8805200048 880430

'[(

PDR ADOCK 05000254 R DCD

P TA9LE 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 Haintenance A. Amendments to facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval 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 0027H/0061Z

l .. ..*.

'~ I . INTRODUCTION 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 Systems are General Electric Company Bolling Water Reactors. The i

Architect / Engineer was Sargent & Lundy, Incorporated, and the primary

! construction contractor was United Engineers & Constructors. The Mississippt l

River is the condenser cooling water source. The plant is subject to license l

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 One and Two, respectively were October 18, 1971, and Aprl) 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.

l This report was complied by Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.

1 0027H/0061Z

. . l

.II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One April 1-30 Unit One began operations for the month of April in Economic Generation Control (ECC). The unit remained in EGC with only minor interruptions to perform routine surveillances until April 8. At 0105, an Electro Hydraulic Control (EHC) Hi/Lo level alarm was received in the control room. An EHC oil leak was discovered on the #3 control valve and a load reduction was immediately taken. At 0140. EHC oil was added to the system. Control rods were inserted and the recirc pumps were ramped to minimum speed. At 0345, the turbine was manually tripped. At 0630, the EHC pumps were taken out-of-service. After investigations, Maintenance discovered a break in the EHC line. Repairs were made and, at 1220, the turbine was reset and the mode switch was placed in RUN. Control rod withdrawal was begun. However, the

  1. 3 control valve would not respond to input and rod withdrawal was halted.

At 1505, rods were inserted and, at 1615, the mode switch was placed in STARTUP/ HOT STANDBY. At 1800, a Group I isolation and Channel A 1/2 scram was received. At 1805, it was determined that this was a result of the Condensate Low Vacuum and Steam Valve closure relay dropping out. This is a function of the mode switch. At 1812, the mode switch was placed in REFUEL, then back to STARTUP/ HOT STANDBY, and the relay then picked up. More repairs were performed on the EHC system on April 9. At 1435, on April 10, the turbine began to roll and, at 1533, the generator was synchronized to the grid.

A power ascent was begun using control rods and recire pumps. 780 MWe was reached at 2240. Control rod pattern adjustments were made and full load was achieved at 0740 on April 11. More rod pattern adjustments were made on April 11 and 12, and routine surveillances were performed. At 1112, the unit was placed in ECC. From April 13 to April 30, unit load was maintained near full power or the unit operated in Economic Generation Control with brief interruptions to perform routine surveillances. .

I B. Unit Two April 1-30 Unit Two began the month of April operating in Economic Generation Control (ECC). Unit load was maintained near full power or the unit operated in EGC with brief interruptions to perform routine surveillances until April 10.

At 0045, Unit Two was taken off of EGC and primary containment was deinerted to begin the Unit Two End of Cycle Nine Refueling Outage. At 1323, the turbine was tripped and at 1653, the reactor scram was completed. Normal refueling activities occurred thru the remainder of the month. The reactor head and steam dryer were removed on April 13 and the mode switch was locked in REFUEL on April 14. The core was unloaded on April 16 thru April 18. The vessel was drained on April 21 and decontamination of the recirc loops was begun on April 22 and continued thru the end of the month.

0027H/0061Z l

I

III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Techaical Specifications for the reporting period.

B. Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C. Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D. Corrective Maintenance of Safety Related Equipment

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

l l

J i

i 0027H/00612 i

j j UNIT 1 MAINTENANCE

SUMMARY

f I There were no Deviation Reports or' License Events Report associated with the f Safety Related Work Request Log this month.  !

. UNIT 2 MAINTENANCE

SUMMARY

t s

WORK REQUEST No.: Q52708 LER NUMBER: 86-13 ,

i  ;

COMPONENT: System 200 - Repaired valve A0-2-203-2D after failing LLRT by res)ating valve body and machining disc.  !

CAUSE OF MALFUNCTION: The cause of valve A0-2-203-2D to fail the Local Leak I Rate Test was deter 51ned to be normal wear and erosion of valve internals.

l RESULTS & EFFECTS ON SAFE OPERATION: Safety implications were minimal as the I

' i inboard valve. A0-2-203-ID, was within acceptable limits.

f ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to t reseat the valve body and also to lap the valve seat and pilot seat. A new f valve seat lapping machine used to repair this valve is anticipated to isprove l future MSIV performance.  !

l l

. t i

t

i

! t i  !

I b

I

- i i

I t

1 I I

i 1  !

i i i l

e

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 6.6.8.1. and 6.6.8.2. of the Technical Specifications.

UNIT 1 Licensee Event Report Number Date Title of Occurrence 88-008 4-8-88 Group I Isolation in Startup/ Hot Standby.

UNIT 2 88-006 4-4-88 Flued Head Anchors Don't Meet Design Requirements.88-007 4-13-88 Leak Rate From All Valves

& Penetration - > T. S. Limit .

L l

I I

0027H/00612 l

V. DATA TABULATIONS The following data tabulations are presented in this report:

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Power Reductions 0027H/00612

APPENDIX C OPER ATING DATA REPOR7 00CKET NO. 50-294 UNIT ONE OATg May 5, 1988 COMPLETE 0 llY lxnne neelanyder TELEPHONE 309-654-2241 MATM STAM 0000 040188 I9 t, RePORTINe ptR100: 2400 043088 Gross HOURa lN REPORTINO PERICO:

4. CURRsNTLY AUTwCRizto power LavtL(WWO: 251I gax, og f a,0. CAP ACITY (MPW8sde 769 08864N SLICTRICAL RATING (MYerNeu: 780 N/A
3. POW 9M LEYtL TO WHICH R88TRICTED (IP ANYI (% Net):
4. REASONS POR RESTRICTION (IP ANYtt THIS MONTH VR TO DATE CVWUL.tflVE 714.0 2403,0 _ 111967,3 S. NUMSOR OS HOURS REACTOR WA4 CRITICAL . . . . . . . . . . . . . . .

00 00 3021 9

8. R EACTOR RESERVE SMUT 00WN HOURS . . . . . . . . . . . . . . . . . . .

659.2 2836.3 108294.5

7. HOURO GG N E R ATOR ON LING . . . . . . . . . . . . . . . . . . . . . . . . . .

0.0 0.0 909,2

8. UNIT R SSORVE SMVTOOWN HOURS . . . . . . . . . . . . . . . . . . . . . .

1576514 6769569_ 230110126

! 5. GRoet THERMAL ENERGY CINER ATED (WWMI ..............

510823 2210059 74633561

10. GROSS ELECTRICAL ENERGY CENam AT :D (WWM1. . . . . . . . . . . . .

496046 ?11?A8; 70n i 593

.v. NET fLICTRICAL ENERGY CINER Af t0 (WWMI . . . . . . . . . . . . . .

100.0 100.0 80.0

12. ' t ACT OR $ t R v lC E P ACTOR . . . . . . . . . . . . . . . . . . . . . . . , . .

l 100.0 100.0 8 ? , _4

13. R E ACTOR A 6' AILA 8t LITY P ACTOR . . . . . . . . . . . . . . . . . . . . . .

41 7 97 7 77 5

14. U NIT S E RVIC E P ACT OR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

91.7 97.7 78.0

15. UNIT AV AI LAtll.l TY P ACTOR . . . . . . . . . . . . . . . . . . . . . . . . . .

00*I -

94.6 65.0 it. U NIT CAP ACITY P ACTOR tUM MOC1 . . . . . . . . . . . . . . . . . . . . .

85.8 92.2 61.4

17. UNIT CAP ACITY P ACTOR luwg 0 sop WWol . . . . . . . . . . . . . . . . .

8*3 23 53

18. UNIT PORCID OUTAGE RAf t . . . . . . . . . . . . . . . . .

4

19. SHUT 00WM8 SCHG0VL80 Qvim NEXT 4 WONTHS (TYPt. DATE. AND DURATION OF I ACHit
20. IP SMUT DOWN AT END GP REPORT PERICO. ESTIMAf t0 DATE OP ETARTUP.

PQRECAST ACHitVED

21. UNITS IN TEST STATUS (PRIOR TO COMMERClaL OPERATIONl:

INITI AL CRITICALITY INITI AL EL ECTRICITY COMutRCIAL OPSRAT6080

} .\ E*I

APPENOlX C OPERATING OATA REPORT 00CKET NO. 50-265 UNIT M OATE .111 5. 1988 COMPLETED BY Lynne Deelsnyder ,

TELEPHONg 309-654-2241 l

OPER ATING 8TATUS 0000 040188

?400 043088 219 GROSS HOUR $ IN R$ PORTING PSRICO:

1. R8 PORTING PGRICO:

25II M AX. OEPS NO. CAPACITY (MWee Nett: 769

3. CURRENTLY AUTHORI2ED POWER LEVEL (MWO:

OESIGN ELECTR6 CAL RATING (MWe>Ned 789 N/A _

3. POWSR L8 VEL TO WM6CH RESTRICTED (IP ANY) (MWeNed:
4. REASONE POR RS$TRICTl088 (IP ANYli THIS MONTW YR TO DATE CUMULATIVE 228*9 2I89 8 -

l

-_06946.9_

S. NUMOGM OF HCiJAG REACTOR WsAS CRITICAL . . . . . . . . . . . . . . .

0.0 0.0 ,,,,,, 2 9 A s , g_

8. REACTOR RSSSRVE SMUTOOWN HOURS . . . . . . . . . . . . . . . . . . .

228.4 2261.9 103797.2  !

7. HOUR 8 GE NE R ATOR 0N LINE . . . . . . . . . . . . . . . . . . . . . . . . . .

0.0 0.0 702.9

8. UNIT R SSERVE SMUT 00WN MouRs . . . . . . . . . . . . . . . . . . . . . .

490072 5138743 222509310 ,

9. GROSS THERMAL ENERGY GENERATED IWWHI ..............

4 162610 1669730 71227514

10. GR088 ELECTRICAL ENERGY GENER ATED (MYpd . . . . . . . . . . . . .

154454 1599345 67159370

11. NET ftICTP.lCAL ENERGY GENER ATIO (MWM) ..............

31.8 78.9 76,o

12. ' E ACT O R SE Rv lC E P ACTOR . . . . . . . . . . . . . . . . . . . , . . . . . . .

f 78.9 79.0 31.8

13. R E ACTOR AV AILA SI LITY P ACTOR . . . . . . . . . . . . . . . . . . . .

31.8 77.9 74.6 1

14. U NIT S E RVIC E P ACT OR . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

' 31.8 77 o ' 7s.1 '

l 15. UNIT AV AILA slLI TY P ACTON . . . . . . . . . . . . . . . . . . . . . . . . . .

27.9 71.6 62.8 it. UNIT CAPACITY F ACTOR (Uelag MOC1 . . . . . . . . . . . . . . . . . . . . .

17. UNIT CAP ACITY P ACTOR tumg 0eme MWel . . . . . . . . . . . . . . . . .

Md

' O.0 6.2 a.1

18. UNIT PORCE0 0UTA48 RATE . . . . . . . . . . . . . . . . . . ......

! 19. SHUT 00*kS SCH400LA0 0VER NEX' S MONTHS LTYPE. 0 ATE. AN0 0VRAT10N OP EACHl: ,

i 20. IP SMUT 00*N AT ENO CP REPORT PERICO. EETIM ATf D DATE OP STARTUP.

21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATIONI:

PORECAST ACHitVED l

INITI AL CRITICALITY INITI AL ELECTR'C17Y

(

COMMERCIAL OPSRAT1080 ___

i l t

(

I i

t i ,_ - __ . __- - __. -_ _ .---- - - _ _ - _ _ . .- - - ___

I APPENDIX B AVERAGE DAILY UNIT POWER IEVEL DOCKET NO. 50-?;4 UNIT ONE DATE May 2, 1988 COMPLETED BY 1.vnne neelsnyder TELEPHONE '09-654-2241 F

MONTH m" DAY AVERAGE DAILY MWER LEVEL DAY AVERAGE DAILY POWER IEVEL (MWHet) (MWe Net) g 658 gy 732 g 739 gg 760 737 1, 770 3

4 7%1 3 737 g 762 gg 754 857 811

, 22 y 662 23 67s ,

52 24 738 8

4 g -16 3 7?7

- IA3 M 726 l 10 gg 777 27 761 761 g 759 12

gg 747 y 750 76 756 14 30 730 gg 15 16 734 INSTRUCTIONS On this form, list the averap datly urtit power level in MWeNet for each day in the reporting month. Compute to the neaisst whole megawatt.

These figures will be und to plot a gr4;h for ca h reporting month Note that v hen manamum dependable capacity is 4 uad for the net etestncel rating et the unit, there may be oscasios , wheri the daily average power level exceeds the 100J hee (or the rntn.ted power Icsel Imet in such cases, the a erage 4.uly unit power output sheet should be I foutnoted to esplam the apparent anomaly.

l.l H 4

4

APPENDIX B AVERAGE DAILY UNfT POWER LEVEL

. i l

DOCKETNO. sn-?ss l UNIT Two DATE Mav 2- 198R _

COMPLETED BY f vnne neet anvder TELEPHONE _109-6s4-2241 MQ g APRTI.

DAY AVERAGE DAILY NWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe het) (MWe Net) g 707 gy -7 2

694 gg -7 3

689 gg -6 4

712 at -7 692 21

-6 5

g 711 -4 22 y 706 23

-2 g M7 24

-I g 738 g -1 gg 126 -1 26 gg -11 27

-2 12

-10 g -?

13

-9 29 -I 14

-10 g -2 18

-7 31 16

-8 I INSTRUCTIONS On this form, list the awrap daily unit power level tn MWeNet for each day in the reportmg rnonth. Compute to the healsst whole mC$awatt. '

, These figures will be used to plut a paph for ca h reporung month Nute that when m424 mum dependable capacity 8 4

uwd f or the net ettetncal ratmg ut the unit there may be osemons wheti the daily aversy power level exceeds the 1003 Imc for the rntchted power Icsel 'tnc). In such cases, the average daly umt power output shaet should be foutnoted to caplam the apprent anomaly.

llM is

I I

-l ID/$A APPENDIX D QTP 300-S13 ~

UNIT $NUfDOWNS AND POWER REDUCTIONS Revision 6 DOCKET No. 50-254 August 1982 UNIT MAPE JUAD CITIES l' NIT ONE CONPLETED BT Lynne Deelsnyaer DATE __ May 3, 1988 REPORT MONTR APEIL. 17R8 TELEPHONE 309-654-2241 A 5 w" 5 $EU go hw g5 2 3 LICENSEz 8 gg No. DATE w DURATION 3 "

EVENT UU $o (HOURS) REPORT NO. CORRECTIVE ACTIONS /CorWENTS 88-3 880408 F $9.8 A 9 HE PIPEXX Manually Tripped Turbine Due to EllC Line Oil Leak - Unit Remained in Startup.IHot Standby APPROVED AUG161982 (ff==1) yc.o3g

i .

ID/5A APPENDI% D QTP 300-S33 UNIT $NUTDOWIIS AND POWR REDUCTIONS Revisfee 6 DOCKET NO. 50-265 ~

August 1982 12flT NAfE Ol'AD CITIES UNIT TWO COMPIITED BY Lynne DeelsnYder DATE May 3. 1988 REPORT MONTM APRIL. 1988 TEIIPIIONE 309-654-224I w 5

. a oSU go o g5 s, DURAT100f gi uCE Su EVElfT

-8

$o 8

u No. DATE (NOURS) REPORT NO. "

ColtRECTIVE ACTIO0lS/C0f9ElfTS 88-5 880410 S 490.6 C 1 RC FUEL} X End of Cycle Nine Refuelinct Outage APPROVED

, , AUG161982 (final) ygo3g

P VI. UNIQUE REPORTING REQUIREMENTS

'The following items are included in this report based on prior commitments to the commission:

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 was no Control Rod Drive Scram Tining Data for Units One and Two for the reporting period.

l l

l l

l 0027H/0061Z

i 9

VII. REFUELING INFORMATION l

The following information about future reloads at Quad-Cities Station was  ;

requested in a January 26. 1978, licensing memorandum (78-24) from 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.

I I

e I

I l

h I

0027H/00612 l

i

QTP 300 5)2 Revision i QUAD CITit$ REFutLING March 1978 INFORMATION Rtqut$T

1. Unit: 01 ,

Reload: o Cycle: to

2. Scheduled date for next refueling shutdown: 4 3;.g9
3. Scheduled date for restart following refueling: 9 17-89
4. Will refueling or resweption of operation thereaf ter require a technical specification change or other license amendment:

NOT AS YET DETERMINED.

5.

scheduled date(s) for submitting proposed IIcansing action and supporting In forma tion:

MARCH 24 1989 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. Nuaber of assemblies in core: 724
b. Nu-ber of assemblies in spent fuel pool: 1773 8.

The present licensed spent fuel pool storage capacity and the size of any ine,rease in licensed storage capacity t9at has teen reswested or is planned in number of fuel asse-clles:

a. Licensed storage capacity for spent fuel: 3657
b. Planned increase in licensed storage; o 9

The projected date of the last refueling that can be disenarged to the spent fuel pool assuming the present licensed capacity: 2008 AL P P R C) V E C) 1-APR 2 01973 l

Q. C. O. S. R.

I

qTP 300-532 Revision 1 QUAD-CITIES REFUELING INFORMATION REQUEST March 1978

i. Unit: 02 Reload: 8 Cycle: 9
2. Scheduled date for next refueling shutdown:

4-9-88

3. Scheduled date for restart following refueling: 6-18-88 4.

Will refueling or resumption of operation thereaf ter regulce a technical -

specification change or other license amendment:

YES. TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLGR CURVE CHANGE TO MCPR LIMIT AND OPERATION AT INCREASED CORE FLOW / FINAL FEEDWA 5.

Scheduled in forma t ion:date(s) for submitting proposed licensing action and supporting March 4, 1988

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

FIRST RELOAD OF GENERAL ELECTRIC, GE8E FUE.

LIMIT OF 14.4 KW/FT. .ITH 4 WATER-RODS AND LHGR

7. The number of fuel assemblies, a.

Number of assemblies in cora:

724_

b. Number of assemblies in spent fuel pool:

1311

3. The present licensed scent increase in licensed storage capacity that has be cfuel pool storage capacity an requested or is planned in number of fuel assemblies:

l a. Licensed storage capacity for spent fuel:

3897

b. 01anned increase in licensed storage:

0 l

9 I The projected date of :ne last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 Al P P R () V E [>

i APR 2 01978 Q.c.o.S.R.

,{

u -. . . - - _- - -

h.,,.!

9 VIII. GLOSSARY The following abbreviations which may have been used-in the Monthly Report, are defined below:

ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor

  • ATHS -

Anticipated Transient Hithout Scram BHR - Boiling Water Reactor CRD -

Control Rod Drive EHC - Electro-Hydraulic Control System E0F -

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 Range Monitor 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 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 PCIOMR - Preconditioning Interim Operating Management Recommendations RBCCH - Reactor Building Closed Cooling 4ter System RBH -

Rod Block Monitor RCIC - Reactor Core Isolation Cooling System RHRS - Residual Hedt Removal System RPS - Reactor Protection System RHH -

Rod Horth Minimizer SBGTS - Standby Gas Treatment System SBLC - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monttor TBCCH - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center 0027H/0061Z

s, ouad Cities fluclear Power Station O Commonwealth Edison 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241

-RAR-88-20 April 29, 1988 U.S. NRC Office of Nuclear Reactor Regulation Washington, D. C. 20555 Attn: Document Control Desk 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 April, 1988.

Respectfully, COMMONHEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R. A. ?dy R. A. Robey Services Superirtendent yk Enclosure 0027H/00612 l

1

-

Retrieved from "https://kanterella.com/w/index.php?title=ML20154D981&oldid=2955234"