ML20212G647
| ML20212G647 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/31/1986 |
| From: | Kronich C, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| RAR-87-1, NUDOCS 8701210107 | |
| Download: ML20212G647 (23) | |
Text
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9 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER, 1986 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND OPR-30 i
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87012101 7 861231
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-c TABLE OF CONTENTS I.
Introduction II.
C. 71ry 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 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
5 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 Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.
The Mississippi River is the condenser cooling water source. 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 One and Two, respectively were October 18, 1971, and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
This report was compiled by Becky Brown and Carol Kronich, telephone number 309-654-2241, extensions 2240 and 2157.
1 0027H/00612
II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit 1 December 1-15 Unit 1 began the month of December on Economic Generation Control (EGC).
At 0045, on December 1, the unit was taken off of EGC and load was dropped to 740 MWe for surveillances. Load was then increased to 760 MWe and the unit was returned to EGC operation at 0430. At 1250 the unit was taken off of EGC and load was increased to full power. On December 2, at 0440, the unit was returned to EGC operation. At 1020 the unit was taken off of EGC and load was increased to full power. At 2225 the unit returned to EGC operation.
On December 3, at 0350, the unit was taken off of EGC to perform surveillancen and was returned at 0435. At 1117 the unit was taken off of EGC and ioad was increased to full power. On December 4 the unit was placed in EGC operation at 0250. At 0852 the unit was taken off of EGC and load was increased to full power.
On December 5, at 1800, a unit shutdown commenced to repair Environmental Qualification splices. The Generator was taken off line at 0228 on December 6, and the unit was manually scrammed at 0229. The unit remained shutdown until December 9, at 1020 when the unit went critical. At 1733 the Reactor scrammed due to low condenser vacuum. The unit went critical at 2112.
The Generator was placed on line on December 10, at 0313. A normal unit startup followed.
Full power was reached on December 12, at 2300. On December 14, at 0231, the unit was placed in EGC operation. At 2340 the unit was taken off of EGC to perform Turbine surveillances.
On December 15 the unit was placed on EGC at 0120. At 0827 the unit was taken off of EGC to perform surveillances, and returned at 0925. At 1510 the unit was taken off of EGC and load was increased to full power.
December 16-31 Load was held at full power until December 17, at 2125, when load was dropped to 475 MWe for a flow drop test.
Load was then increased to full power. On December 19, at 0920, the unit was placed in EGC operation. At 1310 the unit was taken off of EGC and load was increased to full power.
On December 20, at 1800, load was dropped to 780 MWe for a control rod pattern adjustment. At 1910 load was increased towards full power. Load was held at full power until December 24, at 1646, when the unit was placed in EGC operation. On December 26, at 0859, the unit was taken off of EGC and load was increased to maximum power. At 0005, on December 27, the unit returned to EGC operation. On December 28, at 0020, the unit was taken out of EGC and load was dropped to 550 MWe for MSIV surveillances. At 0245 load began an increase towards full power. At 1505 a GSEP Unusual Event was declared due to continuous high Drywell sump levels.
Load began a drop to 120 MWe.
The GSEP event was terminated at 2330. Load began an increase towards full power at 0245 on December 29.
The unit reached 833 MWe on December 31, at 1510, and held at full load for the remainder of December, 1986.
0027H/0061Z
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B.
Unit'2 December 1-31 Unit 2 remained shutdown for the entire month of December for the End of Cycle Eight Refueling and Maintenance Outage.
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O 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' Technical 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.
i D.
Corrective Maintenance of Safety Related Equipment 3
The following represents a-tabular summary.of the major safety related maintenance performed on Units 1 and 2.
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 Repetition.
4 0027H/0061Z
UNIT 1
MAINTENANCE SUWARY CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO ysER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REFETITION Q53127 Replaced shunt There was no This problem is currently As PVC wiring is not wire on Electro-malfunction; under investigation and acceptable under the matic Relief the valve was is being tracked by Form current EQ program in valve solenoid still operable.
A (Equipment Qualifica-this application, the valve 1-203-3B tion Variation Form),
shunt wires on the potential EQ discrepancy, Dresser Electromatic by our downtown solenoid actuators engineering staff.
(1-203-3B, C, D) were replaced by acceptable wiring.
Q53128 Replaced shunt There was no This problem is currently As PVC wiring is not wire on Electro-malfunction; under investigation and acceptable under the matic Relief the valve was is being tracked by Form current EQ program in valve solenoid still operable.
A (Equipment Qualifica-this application, the valve 1-203-3C tion Variation Form),
shunt wires on the potential EQ discrepancy, Dresser Electromatic by our downtown solenoid actuators engineering staff.
(1-203-3B, C, D) were replaced by acceptable wiring.
Q53129 Replaced shunt There was no This problem is currently As PVC wiring is not wire on Electro-malfunction; under investigation and acceptable under the matic Relief the valve was is being tracked by Form current EQ program in valve solenoid still operable.
A (Equipment Qualifica-this application, the valve 1-203-3D tion Variation Form),
shunt wires on the potential EQ discrepancy, Dresser Electromatic by our downtown solenoid actuators engineering staff.
(1-203-3B, C, D) were replaced by acceptable wiring.
0027H/0061Z
UNIT 1
MAINTENANCE StANARY CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NU EER NUnEER COMPONENT MALFUNCT10N SAFE OPERATION PREVENT REPETITION Q53275 86-33 Modified Control Control Room Safety implications, Modification 4-1-86-36 Room Panels to Panels 901-2, were minimal as both was initiated to bring Meet Seismic 10, 11, 19, 20 units were in Cold the Control Room Panel Requirements and 912-2, 8 Shutdown and remained anchorages within FSAR were not so until work needed seismic requirements and anchored as to meet FSAR require-work was conpleted under required due to ments was completed.
Work Request Q53275.
improper in-stallation.
Q53324 IRM 16 Detector Cause of mal-Safety implications IRM 16 will be replaced
{
Will be Re-function of IRM were minimal because as under Work Request Q52017 placed Under 16 & 17 was due soon as it was known and the connectors were 4
Work Request to IRM 16 being that IRM 17 along with remade on the butt splice Q52017 a bad detector 16 was not functioning cable ends for IRM 17 and IRM 17 properly a one-half under Work Request Q53325.
having bad cable scram was initiated.
ends.
Q53325 Remade Connectors See Work Request See Work Request Q53324.
See Work Request Q53324.
on Butt Splice Q53324.
Cable Ends for IRM 17.
Q53340 86-34 Repacked HPCI The old packing Safety implications The old packing was re-Steam Supply in the 1-2301-5 were minimal as the moved and replaced like-Valve 1-2301-5 HPCI valve failed LPCI mode of RHR, both for-like with 17 rings of due to normal Core Spray subsystems, new packing. Valve 1-2301-r J
to service.
0027H/0061Z
UNIT 2
MAINTENANCE SUWARY O
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUWER NUWER COMPONENT MALFUNCTION SAFE OPERAT10N PREVENT REPETlT10N Q52637 Installed new Valve 2-1001-36B Safety implications were The auxiliary contacts Auxiliary Con-failed due to the minimal as the
'A' loop-were replaced like-for-like tacts on the binding of the of containment cooling, with new, and testing of Open & Closed auxiliary contacts both Core Spray sub-the valve was performed Contactors on which mechanically systems, and both Diesel satisfactorily.
G.E. has 2-1001-36B prevented the Generators were operable, been asked for assistance Valve close contactor to prevent recurrence of from picking up.
sticking auxiliary contacts.
The binding was caused by the auxiliary con-tacts not operating smoothly.
0027H/0061Z
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.S.I. and 6.6.B.2. of the Technical Specifications.
Unit 1 Licensee Event Report Number Date Title of Occurrence 86-36 12-4-86 Lost Samples for Particulate Analysis 86-37 12-5-86 Environmental Qualification Problem.-
Drywell Butt Splice Failure 86-38 12-9-86 Reactor Scram - Low Condenser Vacuum Unit 2 Licensee Event Report Number Date Title of Occurrence 86-20 12-11-86 Auto Start of Standby Gas Treatment System 86-21 12-19 ESF Actuation on Loss of Bus 28 f
0027H/0061Z
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/0061Z
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' OPERATING' DATA REPORT DOCKET NO.
50-254 j
i l
UNIT _.
ONE DATEJANUARY 5 1987 COMPLETED BYC_AROL L KRONICH q
TELEPHONE (309) 654-2241 OPERATING STATUS l
0000 120186 l
- 1. Reporting period 2400~123186 Gross hours-in' reporting period 744 2.-Currently authorized power level (MWt): 2511 Max. Depend capacity
-(HWa-Net): 769* Design' electrical rating (MWe-Net): 789
- 3. Power. level to.which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if~ony):
lhls Month Yr.to Date Cumulative 5.
Number'of hours reactor was critical 660.5 6151.3
__10P812.7 6.
Reactor reserve shutdown hours 0.0 0.0 3421.9
- 7. Hours generator on line 647.3 6037.1 99316.5 8.
Unit reserve shutdown hours.
0.0 0.0 909 g t
- 9. Gross thernal energy generated (MWH) 1496070 14092661 20905781g
- 10. Gross electrical energy generated (MWH) 496033 4634013
,_h2753384 ii. Net electrical energy generated (MWH) 473822 4420669
_ 63447202
- 12. Reactor service factor 88.8 70.g 80.1
~ i3. Reactor avo11oh111ty factor
_ 8 8. 8_
70.2 82.Q i
- 14. Unit service factor 87.0 68.9 77.4 i
- 15. Unit availability factor 87,0_
68.9.
78,1
- 16. Unit capacity factor (Using MDC) 02.8_
65.6 61 3
- 17. Unit capacity factor (Using Des.MWe) gol
..,_6 4,_,,3, 62.7
' 1 81 Unit forced outoge rate
.13.0 3,i 5.7
- 19. Shutdowns scheduled over next 6 nonths (Type, Dote,and Duration of each):
NA
- 20. If shutdown at end of report period,estinated date of startup 8WOFFICIAL COMPANY MUMBERS ARE USED IN THIS REPORT
OPERATING DATA REPORT DOCKET NO.
50-265 UNIT _
TWO DATEsTANUARY 5 1987 COMPLETED BYC6.ROL L KRONICH TELEPH3NEL309) 654-2241 OPERATING STATUS 0000 120106
)
'i. Reporting period 2400 123106 Gross hours in reporting period:
744 l
2.' Currently authorized power level (MWt): 2511 Max Depend capotAty (MW2-Net): 769* Design electrical rating (MWe-Net): 789
- 3. Power level to which restricted (if any)(HWe-Net): NA
-4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative
- 5. Number of hours reactor was critical 0_, 0 6448,1 _
97715.7
- 6. Reactor reserve shutdown hours 0.0 0.0 2985_8
- 7. Hours generator on line 0.0 6401.5 94699,i_
0.
Unit reserve shutdown hours.
0 0 0.0 J.0 2, 9_
1 9.
Gross. thermal energy generated (MWH) 0 15R30676
_RQt339629
- 10. Gross electrical energy generated (MWH) 0
__.AZ42510_
643592ER ii. Net electrical energy generated (MWH)
_-2012
__3ZR2778 60597037
- 12. Reactor service factor O t1 73.6 76.7
~13. Reactor avo11ob111ty factor
_Q20 73.6 79.0
- 14. Unit service factor 0.0
__73.1 74.3
.15. Unit avo11ob111ty factor 0.0 73.i_
74.9
- 16. Unit capacity factor (Using MDC)
.5 70.1 61,R
- 17. Unit capacity factor (Using Des.MWe)
__.5 30.3 60 4
- 18. Unit forced outoge' rate O u0
.7 7.7_
,19. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each):
NA
- 20. If shutdown at end of report period, estimated date of startup SUNIFFICIN. COMPMY NURKRS ME UED IN THIS RE. PORT
T-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.__
50-254 UNIT ONE DATEJANUARY 5 1987 COMPLETED BYCAROL L KRONICH TELEPHONE 1109) 654-2241 MONTH De c e mb e r-1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
763.3 17.
796.4 2.
786.6
- 18. __
783.0 3.
763.9 19, 782.1 4.
795.4 20, 795.0 5.
701.6 21.
785.0,_
6.
-4.0 22.
802.7 7.
-10.8 23, 790.5 8.
-10.7 24.
792 3 9.
-17.9 25.
747.1 10, 294.9 26.
773.6 ii.
675,0 27.
760.0 12.
775.5 28, 544.2 13.
700.6 29.
460.5 14.
758.8 30.
704,_1 15.
774.1
- 31. __ _
78.id 16.
781.5 INSTRUCTIONS On this forn, list the everage daily enit powr level in Mk-Net for each day in the reporting nenth. Compete to the neerest whole negewett.
These figeres will be used to plot a graph for each reporting nenth. Note that when notinen dependeble copecity is esed for the net electrical rating of the unit there may be occasions when the dolly everage pour level exceeds the 1881 line (or the restricted powr level line),In such cases,the average delly unit powr estpet sheet shes!d be festeeted to esplein the opperent onenely
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APPENDIX D j
. AVERAGE DAILY UNIT POWER LEVEL j
J DOCKET NO.
50-26.5 UNIT _
TWO DATEJANUARY 5 i_9_07 COMPLETED BYp_A_ROL L KRONICH TELEPHONEL309) 654-2241 MONTH December 1906 l
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.-
~2.8
'i7.
-2.6 2.
-2.9 10.
-3.3 3.
-3.0 19.
-2.6 4.
-2.5 20.
-3.3 5.
-2,3 21.
-2.0 6.
-2.5 22.
-3.8 7.
-2.8 23.
-4.1 0.
-2.9 24.
-4.0 9.
-3.3 25.
-3d 10.
-3.0 26.
-3 0 2
11.
-3.2 27.
-4.6 12.
-2.7 28.
-4.0 13.
-2.0 29.
- 4. 0 __
14.
-2,4 30.
-4.0 15.
-2.5 31.
-4.1 16.
-2.6 INSTRUCTIONS On this fern, list the overage dolly unit powr level in MWe-Net for each day in the reporting nonth Cenpete to the nearest uhele negewett.
These figeres will be used to plot a graph for each reporting nenth. Note that when no inen dependable capacity is used for the net electrical rating of the snit there ney be eccellens when the daily overage powr level exceeds the 1981 line (or the restricted powr level line),.In such cases,the overage daily snit powr estput sheet shes!d be feetnoted to explain the opperent onenely
M put F=t M
M M
M M
M M
M P*4 M
M P"9 ID/SA APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-254 August. 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C. KRONICH DATE January 2, 1987 REPORT MONTil DECEMBER 1986 TELEPil0NE 309-654-2241 5
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DURATION Eg EVENT u
o NO.
DATE (Il0URS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS u
o ca 86-37 861205 F
96.75 H
2 86-37 ZZ ZZZZZZ Unit shutdown to repair Environmental Qualification Splices 86-38 861217 S
0.0 B
5 RC ZZZZZZ Reduced load to approximately 475 MWe to perform flow drop test 86-39 861228 S
0.0 B
5 CD VALVEX Reduced load to 550 MWe for MSIV surveillances 86-40 861228 F
0.0 A
5 AA HTEXCH Commenced unit shutdown -- GSEP Unusual Event declared due to continuous high Drywell sump levels (terminated approximately 8.42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br />)
APPROVED AUG 1 G 1982 (final) ygg3g
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5 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 Timing Data for Units One and Two for the reporting period.
0027H/0061Z
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,.o' VII.
REFUELING INFORMATION The following information about future reloads at Quad-Clties 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.
0027H/0061Z
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QTP 300-532 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
Q1 Reload:
8 Cycle:
9 2.
Scheduled date for next refueling shutdown:
9-14-87 3
Scheduled date for restart following refueling:
12-7-87 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: YES. TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLGR CURVES) AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECIFICATIONS.
5.
Scheduled date(s) for submitting proposed IIconsing action and supporting Information:
AUGUST 21, 1987 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 PLANNED AT PRESENT TIME.
7 The number of fuel assembites.
t a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1683 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.
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 IIcensed capacity: 2008 XPPROVED APR 2 01978 C3.C:.c).!5.Ft.
I
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QTP 300-532 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
Q2 Reload:
7 Cycle:
8 2.
Scheduled date for next refueling shutdown:
5-30-88 3
Scheduled date for restart following refueling:
1-19-87 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:
APRIL 22, 1988 6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7 The number of fuel assembites, a.
Number of assembiles in core:
724 b.
Number of assemblies in spent fuel pool:
1198 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.
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: 2008 XPPROVED APR 2 01978 C3. c:. c). !B. R.
,a o
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 Without Scram Bolling Water Reactor BWR CRD Control Rod Drive Electro-Hydraulic Control System EHC E0F Emergency Operations Facility Generating Stations Emergency Plan GSEP HEPA High-Efficiency Particulate Filter High Pressure Coolant Injection System HPCI l
HRSS High Rad'.ation Sampling System 4
IPCLRT Integrated Primary Containment Leak Rate Test IRM 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 Maximum Fraction Limiting Critical Power Ratio MFLCPR MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI PCIOMR Preconditioning Interim Operating Management Recommendations Reactor Building Closed Cooling Hater System RBCCW RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHRS RPS Reactor Protection System RHM Rod Worth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control Shutdown Cooling Mode of RHRS SDC SDV Scram Olscharge Volume l
SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe Technical Support Center TSC I
0027H/0061Z
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l O Comm)nwealth Edison Quad Citles Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RAR-8-1 January 2, 1987 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Conmtission Washington, DC 20555 Attention Document Control Desk Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units 1 and 2, during the month of December, 1986.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R. A. Robey Services Superintendent bb Enclosure gb tll