ML20128C373
| ML20128C373 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 04/30/1985 |
| From: | Kronich C, Tamlyn T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 0027H, 0061Z, 27H, 61Z, TKT-85-21, NUDOCS 8505280276 | |
| Download: ML20128C373 (23) | |
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- QUAD-CITldS~ NUCLEAR POWER STATION UNITS'1 AND 2 MONTHLY PERFORMANCE REPORT APRIL 1985 COMMONWEALTH EDISON COMPANY AND
'ICWA-ILLIN0IS. GAS & ELECTRIC COMPANY NRC DOCKET NOS. S0-254 AND'50-255 i
' LICENSE NOS. DPR-29 AND DPR-30
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. TABLE OF CONTENTS 5,.
VI.
~ Introduction.
iII.
- Summary _ of Operating Experience -
~
A.
Unit 0ne
- B. Uni t: Two
- III.
Plant'or Procedure Changes, Tests,' Experiments, and Safety Related Maintenance A. - Amendments;ro facility > License or Technical Specifications B.
Facilityfor Procedure Changes-Requiring _NRC Approval C.
Tests and Experiments Requiring NRC Approval-
-0.
Corrective Maintenance;of Safety'Related Equipment lIV.
~ Licensee Event Reports
'Ni Data. Tabulations i
.A.
_ Operating Data Report 8.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions
- VI.
Unique _ Reporting' Requirements Main ~ Steam-Relief. Valve. Operations A.~
B.
Control Rod Drive Scram Timing Data
.VII.
' Refueling Information MVIII.
Glossary 4
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INTRODUCTION
' Quad-Cities Nuclear Power StationLis composedlof two Boiling 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 Bol. ling Water. Reactors.
The
, Architect / Engineer-was Sargent & Lundy,-Incorporated, and.the primary
~ construction contractor was~ United Engineers &1 Constructors.
The Mississippi-River ls-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,
- rsspectively; pursuant:to.0ccket Numbers 50-254 and 50-265.
The date of Linitial' Reactor criticalities-for Units One and Two, respectively were October cl8,-1971, and April
.6, 1972. Commercial generationlof power' began on 2
~
LFebruary ~ 18,-1973 for Unit One and March 10,.1973.for Unit Two.
This report was compiled'by-Becky Brown and Dave Kimler, telephone number n'
309-654-2241, extensions 1.27 and 192.
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-II.
SUMMARY
.0F OPERATING EXPERIENCE ~
A.
Unit One i April 1-30: Unit One began the month holding load at full power.
- On' April 6, at- 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, load was dropped to 650 MWe for a Control Rod. Pattern adjustment. At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> the unit began a normal load
.. increase to full power. On April 13, at 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, load was dropped
. to 70015ha for weekly Turbine tests. -_ At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> load was increased.
. to 760 !!We, and the unit.was placed on~ Economic Generation Control (EGC).. At 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br /> load was dropped to 700 MUc for a Control Rod Pattern adjustment. yAt 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> the unit began a normal load increase to full power. _On April 17, at 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, load _was dropped to 700 IfWe.for monthly. Turbine tests. At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> -load.was
.' increased to. 740 MWe and the unit was placed on Economic Generation
' Control.(EGC).
B.- Unit'Two April 1-30: -Unit Two remains shut down for the End of Cycle Seven Refueling and Maintenance Outage for the entire month of April.
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s 0027H' 100612;
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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.
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, LER Numbers, Components, Cause of lialfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
1 0027H 100512 i
UNIT 1
MAINTENANCE'
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCT10N SAFE OPERAT10N PREVENT REPETIT10N Q34172 Rebuilt Spare CRD NA NA Replaced tube & flange 110LD Card #84-241 Serial No. A4623; S/H 6435 Rejected scrap tube Q40200 Adjusted Pressure Flow switch out 14 Valve will not auto-Adjusted low flow Switch on 1-2301-of adjustment, open when 13 Valve setpoint of flow 14 Valve to !!ake open. 14 Valve vould switch.
Valve Operate work with Control Correctly Suitch;.HPCI operable.
Q40201 1-2301-48 Valve 48 Valve vould not Occurred during Valve later stroked shut with control testing; HPCI
- normally, switch, available.
Q40203 85-01 HPCI Reset &
Solenoid coils had Would not trip or Repaired contacts Trip Pushbuttons broken contacts in reset from_ Control SV-8 and SV-12.
SV-8 & SV-12,
- Room, probably due to Turbine vibration.
Q40419 1/2-7503A Lugs of 2 phases The heater breaker Separated the lugs, Standby Gas touched in the tripped while running
' checked resistance Treatment IIeater heater junction
- heater, phase-to-phase. All 3 box.
phases satisfactory.
Q40441 1-1001-4B Breaker Unknown.
Itaintenance checked Tripped with breaker; operated Valve in CLOSED normally.
position; did not open
UNIT 1
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION.TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT' REPETITION Q40683 1/2 Emergency Broken snap ring Breaker auto-trips Replaced snap ring.
Diesel Generator in cubicle linkage.
immediately when Cleaned secondary to Bus 13-1 closing breaker.
disconnect switches.
Worked 0.K. in TEST position; Unit 1 Diesel Generator operable.
Q40764 85-06 901-10 Surmised to be Failed downscale.
Modification 4-1/2-1A Fuel Pool
" electrical IB monitor verified 85-14 installed a Radiation noise inter-
- operable, capacitor to increase Monitor
- ferences, response time constant.
Q40768 85-05 1-1701-16A Surmised to be Spurious trip.
Modification 4-1/2-LA Fuel Pool
" electrical 85-14 installed a Radiation noise" inter-capacitor to increase Monitor ferences.
response time constant.
Q40769 85-05 1-1701-16B Surmised to be Spurious trip.
Modification 4-1/2-1B Fuel Pool
" electrical 85-14 installed a Radiation noise" inter-capacitor to increase Monitor
- ferences, response time constant.
Q40866 85-12 1-1743A Surmised to be Spiking high.
Modification 4-1/2-1A Fuel Pool
" electrical 85-14 installed a Radiation noise" inter-capacitor to increase Monitor ferences.
response time constant.
Q41456 1-5745C Dirty auxiliary Circuit would not Circuit breaker auxiliary Middle RIIR suitch in the close, so the fan switch was cleaned and Service Water pump circuit would not start. RHR breaker returned to Vault Room Cooler breaker.
System was operable.
service.
Fan
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UNIT 2
MAINTENANCE
SUMMARY
4
.CAUSEo RESULTS & EFFECTS W.R.
LER OF
.ON
.ACTIONiTAKEN TO
' NUMBER NUMBER COMPONENT.
MALFUNCTION SAFE OPERATION PREVENT REPETITION Q40142 85-02 Replaced, Torque.
'The support arm.
Declared GSEP Unusual
. Failed torque switch -
Switch on Valve which holds'"0 PEN"'
Event and began replaced:like-for-like.
2-2301-8 in Unit finger contact was shutting down Unit 2.
Valve successfully:
Two MSIV Room broken. Valve stroked,three times.'
travel then. limited.
Q40295 Replaced Solenoid.
Cyclic fatigue..
Bad seals prevented.
Solenoid valve. replaced Valve & Tubing on deteriorated seals air from operating AO-like-for-like..
A0 2-1601-20B on solenoid valve 2-1601-20B. 20A Valve Valve SO 2-1601-50B was operable.'
Q40425 85-05 Unit Tuo MSIV -
Failed limit switch 2B MSIV isolation valve Replaced limit switch Isolation Valve did not.stop valve' went full closed.
like-for-like. 2B MSIV Limit Suitch at 10% closed Increased pressure isolation. valve Replaced.
- position, caused full Reactor functionally. tested'
- scram, satisfactorily..
Q40495 2-1001-36B Cyclic fatigue.of Valve breaker tripped Breaker replaced like--
Valve Breaker-
' breaker spring.
with valve in mid-for-like, and' valve.
Breaker tripped stroke position. All successfully stroked at high starting-other containment.
three times.
current.
systems available.
Q40568 E-Z liigh Density Cells.A-1 and A-16 Fuel Rack Cells blanked off.
A-1 and A-16 Q40639 2-1001-36A Valve Auxiliary' contacts-While testing, ther The auxiliary contacts Breaker.
' associated with M0'2-1001-36A would for both OPEN and'CLOSE OPEN position in not open'.,'B' Loop-of-con'tactors replaced breaker were Containment Cooling;
_like-for-like, binding, preventing available. 36A Valve proper operation of. could have.been manually
-OPEN contactor.
opened if needed.
UNIT 2
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF
'ON ACTION.TAKEN T0 NUMBER NUMBER COMPONENT-MALFUNCTION SAFE-0PERATION PREVENT REPETITION-Q41409 2-1001-18A RHR Spring tension While running valve
. Adjusted' spring tension' Minimum Flow out of adjustment for Environmental on contacts 7 & 7C and Bypass Valve on Limitorque Qualification.
on' contacts 8 &.8C.
operator.
- inspection, valve:
opened but no light-indication. Once full open, valve would not
.close.
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-IV.
LICENSEE EVENT REPORTS TheLfo11owing is a~ tabular summary offall licensee event reports for.
Quad-C! ties _' Units One and Two occurring during the reporting period, pursuant (to;the reportable occurrence reporting requirements as set forth in sections
~
6.6.8.l. and 6.6.B.2. of the Technical Specifications.
UNIT ONE Licensee Event Report Number-Date Title of Occurrence 85-14~
4-3-85 1A Fuel Pool Radiation Monitor Spiked High UNIT TWO 85-10 3-28-85 Reactor Scram Due to
-Radiography Test and Late NRC Notification l
0027H.-
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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
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OPERATING DATA REPORT j
-1 DOCKET NO.
50-254
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UNIT ONE D
DATEMov 3 1985
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1 COMPLETED BYCAROL KRONICH'
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TELEPHONE 309-654-2241xi93 OPERATING STATUS l
0000 040185 l
- 1. Reporting period:2400 043085 Gross-hours-in reporting period 719
- 2. Currently authorized power level-(MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical' rating (MWe-Net): 789
--3.- P owe r level-to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative 5,
Number of hours reactor was critical 719.0 2879.0 91201 5
'6, Reactor reserve shutdown hours 0.0 0.0 3421.9
- 7. Hours generator on line 719.0 2853.7 87889.0 8.
Unit reserve shutdown hours.
0.0 0.0 909.2
'.9. G'ross thernal_ energy generated (11WH)
-1728856 6717756 182464146
- 1. 0.. Gross electrical energy generated (MWH) 567765 2218890 58996341 11.- Net electrical energy generated (MWH) 544301 2126874 55082576
- 12. Recctor' service factor 100.0 100.0 80.2
- 13. Reactor ovallobility factor 100.0 100.0 83.2
- 14. Unit' service-factor 100.0 99.1 77.3
- 15. Unit ovallobility factor 100.0 99.i 78,i
- 16. Unit capacity factor (Using MDC) 98.4 96.1 63.0
- 17.. ' Un i t capacity factor (Using Des.MWe) 95.9 93.6 61.4
- 18. Unit forced outage rate 0.0
.9 5.9
-19.
Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
'20.
If shutdown at end of report period,estincted date of stortup NA
-*The MDC nay be lower then 769 MWe during periods of high anbient temperature due 7e the thernal perfaracnce of the spray caul.
- UNDFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT
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OPERATING DATA REPORT DOCKET NO.-
50-265-UNIT TWO DATEMov 3 1985 COMPLETED BYCAROL KRONICH TELEPHONE 309-654-2241x193
- OPERATING STATUS-0000 040185 1.
Reporting period 2400 043085 Gross hours in reporting period:
719
2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net):'769* Design. electrical roting ( MWe-Ne t )': 789
- 3. Power -level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if~ony):
This Month Yr,to Date Cunulotive a
.- 5. Number of hours reactor was critical 0.0 1630.8 86536.8 6.
Reactor reserve' shutdown hours 0.0 0.0 2985.8
- 7. - Hours generator on line 0.0 1608.7 83657.8 8.
Unit reserve' shutdown hours.
0.0 0.0 702.9 9.rGross thernal energy generated (MWH) 0 3722622 175241689
'10.-Gross electrical energy generated (MWH) 0 1217469 55870880
- Li. N'et electrical energy generated (MWH)
-1122 1164766' 52482'751
- 12. Reactor service factor-0.0 56.6
-76.7
- 13. Reactor ovallobility factor 0.0 56.6 79.4
- 14. Unit service factor 0.0 55.9 74.2 115. Unit ovo11obility factor 0. _0 55.9 74.8
.1'6', ;Un i t copocity factor (using MDC)
.2 52.6 60.5
- 17. Unit capacityffector (Using Des.MWe)
.2 51.3 59.0
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11 8. Unit forced outoge rate 0.0 10.6 8.4
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each ) :
-20.
If shutdown at end of report period,estinated date o f s t ar t u p
___5-30 _85____
- The PDC nay be lower then 769 MWe during periods of high entient teaperature du s
to-the thernal perfars=ct of the spray cual.
$UN0FFICIAL CDP.PANY NUMBERS ARE USED IN THIS REPORT t
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- APPENDIX ' B AVERAGE DAILY UNIT POWER LEVEL-DOCKET NO.
50-254 UNIT ONE DATEMay 3 1985
' COMPLETED BYCAROL KRONICH TELEPHONE 309-654-224ix193 MONTH Aor11 i985
. DAY. AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
-(MWe-Net)
(MWe-Net)-
e 1.
793.2 17, 733.0 2.
790.6 18, 759.5
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3.
794.3 19.
722.i 4,
805.5 20.
725.6 5.
764.1 21.
720.7 6.
667.2 22, 742,0 7.
780.1 23.
766.1 8.
785.5
-24.
773.5 9.
791.0 25, 740.3 10, 800.1 26.
748.9 ii.-
739.3 27.
745.3 12, 783.5 28, 718.3 13.
745.4 29.
750.0
- 14.
775.0-30.
744,i
'i5, 739,i 16.
736.7 INSTRUCTIONS nearest whole, list the average daily unit power level in MWe-Het for each day in the reporting nonth. Compete to the On this forn negawatt.
These figures will be used to plot a graph for each reporting nonth. Note that when notinen dependable capstity is used for the net electrical rating of the unit there may be occaslins when the daily average power level exceeds the
'1881 line (or the restricted power level line),.In sich cases,the average daily snit power estput sheet shoold be festnoted to explain the apparent anonaly
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APPENDIX B' AVERAGE DAILY UNIT POWER LEVEL
- DOCKET NO.
50-265 UNIT TWO DATEMov 3 1985 COMPLETED BYCAROL-KRONICH TELEPHONE 309-654-2241x193 i
MONTH Apr ll-1985 DAY AVERAGE' DAILY POWER LEVEL DAY AVERAGE DAILY POWER. LEVEL
( MWe--Ne t )
(MWe-Net)
- 1.-
-2,6-17.
-i.8 2.-
-2.4 18.
-2.2 3.
-2,1 19.
-2.2
'4.-
-2,i 20.
-2,2 5.
-i.7 21.
-2,3
~6.
-1,6-22.
-2,2 7.
-1.5 23.
-2,1 8.
-1.5 24.
-2.0 9.
-1,6 25.
-2,i 10.
-1,5 26.
-2.3 11.
-1,7 27.
-2,2 12.
-1,6 28.
-2,i 13.
-1,7 29.
-2.2 14.
-1,7 30.
-9,8 15.
-1,7 16.
-1.8 INSTRUCTIONS On this fern, list the average daily unit power level in PWe-Net for each day in the reporting nonth.Compite to the necrest whole negawatt.
These figures will be used to plot a graph for each reparting nenth. Note that when notinen dependable capacitt is
- used for the met electrical rating of the unit,In such cases,the average daily snit power entput sheet should bet 1981 line (or the restricted power level line).
festnoted to explain the apparent onently L
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ID/SA APPENDIX D QTP 300-S13 UNIT SliUTDOWNS AND POWER REDUCTIONS Revision 6
-DOCKET NO.
50-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY C Kronich Ilay 6, 1985 APRIL 1985 REPORT HONTil TELEP110NE 309-654-2241 DATE 5.
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DURATION M
EVENT o"
NO.
DATE (1100RS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS-ca 85-23 850406 S
0.0 11 5
RB CONROD Reduced load to 650 MWe for Control Rod Pattern Adjustment 85-24 850413 S
0.0 B
5 IIA TURBIN Reduced load to 700 MWe for weekly Turbine tests 85 -25 850413 S
0.0 11 5
RB CONROD Reduced load to 700 MWe for Contro'l Rod Pattern Adjustment 85-26 850417 S
0.0 B
5 liA TURBIN Reduced load to 700 MWe for monthly i
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Turbine tests I
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- VI. UNIQUE REPORTING REQUIREMENTS The-following.
- ltems-are included l'n thisLreport based on prior commitments to the: commission:
A.
MAIN STEAM' RELIEF VALVE 0PERATIONS'
~There were no Main Steam Reitef-Valve Operations for the reporting period.
.B.
LCONTROL ROD ORIVE 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.
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i VII.
REFUELING INFORMATION-
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-The following)information'about future reloads at Quad-Cities Station was-3 requested _in a January-26, 1978, licensing memorandum-(78-24) from D. E.
- >0'.Brien to' C. ~ Reed, et al., ti tled- "Dresden, Quad-Ci ties, and --Zion Station--NRC Request' for Refueling Informatio'n"," dated-JanuaryL18,-1978.
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9 Q'
i QTP 300-S32 I
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Rsvision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST' C,,
o 1.
Unit:
Q1 Reload:
7 Cycle:
8 2.
Scheduled date for next refueling shutdown:
1-2-86
=3 Scheduled date for restart following refueling:
4-2-86 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
'NOT AS YET DETERMINED.
P
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5
. Scheduled date(s) for submitting proposed IIcensing action and supporting Information:
b DECDIBER 19, 1985; IF LICENSING ACTION REQUIRED.
s 6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewe:t design or performance analysis 4
methods, significant changes in fuel design, new operating procedures:
NONE PLANNED AT PRESENT TIME.
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7 The number of fuel assemblies.
)'
a.
Number of assemblies in core:
724 h
b.
Number of assemblies in spent fuel pool:
2340 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:
-1 a.
Licensed storage capacity for spent fuel:
3657 l
b.
Planned increase in IIcensed storage:
O h
9 The projected date of the last refueling that can be discharged to the 7
spent fuel pool assuming the present licensed capacity: 2003
(,
WPPROVED v APR 2 01978 3.,
Q.C.O.S.R.
?s.L
F QTP 300-S32 i
~
Rsvision 1
}
QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST
(:, _
o 1.
Unit:
-Q2 Reload:
7 Cycle:
8 2.
Scheduled date for next refueling shutdown:
3-16-85 (Actual) i 3.
Scheduled date for restart following refueling:
5-30-85 P
4.
Will refueling'or resumption of operation thereafter require a technical specification change or other license amendment:
Yes.. A routine MAPLHGR amendment has been submit'ted as a preparatory change to allow a 10 CFR~50.59 review.
5 Scheduled date(s) for submitting proposed licensing action and supporting Information:
Not Applicable.
^
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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;:
5 None planned at present time.
2
{
7 The number of fuel assemblies.
a.
Number of assemblies in core:
724
- r..
(
b.
Number of assemblies in spent fuel pool:
176 8.
The present IIcensed 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 IIcensed storage:
0 9
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 WPPROVED v APR 2.01978 f..
Q.C.O.S.R.
{ _. g....
- g
~
i
~
.y i
b 4
if VIII. GLOSSARY fk
-Theafollowing, abbreviations which may have.been_used in the Monthly-Report, are-defined'below:
-ACAD/ CAM
' Atmospheric Cont'ainment Atmospheric-Dilution / Containment AtmosphericLMonitoring American National Standards Institute ANSI-
-e APRM Average' Power Rangt Monitor ATHS
- 1 Anticipated Transient Hithout Scram BWR:
Boiling' Water (Reactor-CRD Control Rod Drive LElectro-Hydraulic' Control System
'EHC-EOF:
l Emergency Operations Facility GSEP.
- Generating' Stations Emergency Plan-L HEPA 2High-Efficiency Particulate Filter' High Pressure Coolant Injection System HPCI L
HRSS '
.High Radiation Sampling System F
- IPCLRT.
Integrated Primary Containment Leak Rate' Test
. IRM t-(Intermediate Range Monitor
- ISI.
. Inservice Inspection-LER;
' Licensee Event Report LLRT:
J Local Leak. Rate Test Low' Pressure Coolant Injection Mode of RHRS fLPCI.
=-
l;
'LPRM-..
Maximum Average Planar Linear Heat Generation Rate Local Power Range Monitor L.
MAPLHGR' -
.MCPR-Minimum Critical Power Ratio
.MFLCPR~
- 1 Maximum Fraction Limiting Critical Power Ratio
~
-MPC-LMaximum Permissible Concentration-MSIV-Main-Steam Isolation Valve
- Nationa1> Institute for Occupaticnal Safety and Health
- LNIOSH PCI Pr_imary Containment Isolation i
PCIOMR
. Preconditioning Interim Operating Management Recommendations i
RBCCH ReactorfBuilding Closed Cooling Water System F
'RBM-Rod Block. Monitor m
- Reactor Core Isolation Cooling System l'
~
Residual Heat Removal System
-RHRS.
E
.RPS-
_ Reactor Protection System RWM-Rod Worth' Minimizer SBGTS
.- - Standby, Liquid Cont cl SBLC-i SDC Shutdown Cooling Mode of RHRS e
SDV c-s
-Scram Discharge-Volume
?SRM-(Source-Range Monitor
- 5-
-TBCCWL
- iTurbine' Building Closed Cooling Water System 1TIP
' -?
Traversing Incore Probe-1TSC-
i 10027H 00612
,e
. u-
Commonwealth Edison cuad Citi:s Nucleir Power Stati:n 22710 206 Avenue North Cordova, lilinois 61242 Telephone 309/654-2241 TKT-85-21 May 1, 1985 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Document Control Desk Gentlemen:
Enclosed for your information is the Monthly Performance Report covering the operaticn of Quad-Cities Nuclear Power Station, Units One and Two, during the month of Acril 1985.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION C
T. K. Tamlyn Services Superintendent bb Enclosure
((1h cc:N s:
il/
.