ML20210V423
| ML20210V423 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/31/1987 |
| From: | Robey R, Schmidt K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| RAR-87-7, NUDOCS 8702190016 | |
| Download: ML20210V423 (24) | |
Text
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JANUARY, 1987 COMMONWEALTH EDISON COMPANY I
AND
(
IONA-ILLINOIS GAS & ELECTRIC COMPANY 2
NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 t
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I 8702190016 870131 PDR ADOCK 05000254 R
PDR 0027H/00612 Ec34
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l TABLE OF CONTENTS I.
Introduction II.
SummaryofOperatingExperience A.
Unit One e
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 Sclam Timing Data VII.
Refueling Information VIII.
Glossary I
0027H/0061Z
I.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of 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 Boiling 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 critica11tles 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 Kurt ":hmidt, telephone number 309-654-2241,. extensions 2240 and 2147.
0027H/0061Z
II.
SUMHARY OF OPERATING EXPERIENCE A.
Unit 1 January 1-15 Unit 1 began the month of January holding full load. At 2136 on January 1 the unit was placed in EGC and remained in EGC until 1122 on January 2 when it was taken off for HPCI surveillances. The unit was placed back in EGC at 2130 on January 2 when load was reduced to 700 MWe for Turbine surveillances. At 0830, on January 3, a power ramp-down was begun from 700 to 300 MWe because of a control valve failure.
Power reduction was stopped at 392 MWe at 1145. Power was held at 392 MWe until 1245 when a power ascension was performed until 700 MWe was reached at 1530 on January 3.
On January 4, at 0030, the power ascension was resumed until 1910 when full power was achieved. The unit was held at full power January 5, 6, and 7.
At 0015, on January 8, power was reduced to 800 MWe for weekly Turbine surveillances. Following Turbine surveillances, at 0145, the unit was restored to full power and remained until 1838 on January 8 when the unit was placed in EGC.
The unit stayed on EGC until
- ?l5 on January 9.
The unit was run at full power until 0125, January
- 19. when it was placed back in EGC.
At 1643 EGC was tripped and the unit returned to full power. At 2309, January 10, load was reduced to 805 MWe for weekly Turbine surveillances, and subsequently placed in ECC at 0152 on January 11.
EGC was tripped at 0656 on January 12, and the unit brought to full power. Full power was held until 2023 on January 14 when the unit was placed in EGC.
At 0710, on January 15, the unit was taken off EGC and run at full power until 2350.
It was then placed back in ECC, January 16-31 On January 16 Unit 1 started in EGC.
The unit was taken out of EGC at 0625 and ran at full power until 1245 on January 17 when it was returned to EGC.
The unit was taken out of EGC for surveillances from 0045 to 0255 on January 18.
On January 19, at 0820, the unit was taken out of EGC and run to full power. At 0255, January 20, the unit was placed in ECC.
EGC was tripped for a test from 0920 to 0923. The unit was taken out of EGC from 1717 until 1756 on January 20.
On January 21 EGC was tripped from 0315 to 0326 for surveillances. At 0725 the unit was taken out of EGC and run at full power until 0055 on January 22 when it was placed back in EGC.
On January 22, at 0658, the unit was taken out of EGC and run to full power.
Full power was held on January 23 and 24, until 0855 on January 25 when the unit was placed back in EGC.
At 0823, on January 26, the unit was taken out of EGC and run to full load which was held until 0023 on January 31 when the unit was placed back in EGC.
At 1120 the unit was taken out of EGC and full load held until 2310 when a load drop to 700 MWe was begun for surveillances.
B.
Unit 2 January 1-31 Unit 2 continued shutdown for the End of Cycle Eight Refueling and Maintenance Outage through January 21.
At 1440, on January 21, Reactor startup was commenced. The Reactor reached criticality at 1710. The Unit 2 Generator was closed to the grid at 1130 on January 22.
At 1500 the unit was powered down to below 100 MWe to prepare for Turbine Generator overspeed tests.
These tests were started at 1638 and completed at 1745. The unit was subsequently run to 25 percent power for rod scram timing. At 0923, on January 23, the rod scram timing was stopped and at 0948 a Reactor shutdown was commenced because of condenser tube leaks.
At 1300 the Generator was taken off line, and at 1323 the unit was manually scrammed. At 1825 the unit was in Cold Shutdown.
It remained shutdown on January 24 and until 1928 on January 25 when Reactor startup was begun.
At 2052 on January 25 the Reactor was critical.
The Generator was placed on line at 0925 on January 26.
A power ascent was begun at 0950 and stopped at 175 MWe at 1155.
Power was held until January 27, at 2100.
Power was raised to 250 MWe at 2205 and held until 2325 when ascent was begun to 400 MWe.
Power was held at 400 MWe from 0110 to 1000, January 28.
Power was increased to 550 MWe and held for a T.I.P. trace from 1040 January 28 to 1653 January 29.
Power was increased to 700 MWe and held from 2000 to 2340 on January 29.
Power was increased to 775 MWe and held for an APRM calibration from 0215 to 0925 on January 30.
Ascent to full power was resumed but then stopped at 1040 and 818 MWe due to condenser back-pressure problems. At 1355 a load reduction was started because of the back-pressure. At 1420, and 590 MWe, the load was held until 2225 when an ascent to full power was begun. On January 31, at 0440, the power
(
ascent was stopped at 725 MWe and load reduction begun, again due to condenser back-pressure. At 0600, on January 13, load reached 600 MWe and was held at this level for the remainder of tb-ay.
III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE I
A.
Amendments to Facility License or Technical Specifications l
Technical Specification Amendment No. 93 to Facility Operating License No. DPR-30 was issued on December 30, 1986. This Amendment modifies the Technical Specifications to reflect the modificctions mode to the Standby Liquid Control System for compliance with the requirements established in 10 CFR 50.62.
Technical Specification Amendments 98 and 94 were issued on January 6, 1987, to Facility Operating Licenses DPR-29 and DPR-30.
This amendment will modify the LPCI pump flow surveillance test requirements to support facility modifications for resolution of a single failure concern identified in i
Inspection and Enforcement Bulletin (I.E.B.) 86-01.
Technical Specification Amendment No. 95 was issued on January 16, 1987, to Facility Operating License DPR-30.
This l
Amendment reflects Cycle 9 reload fuel and transient analyses.
In addition, the Amendment removes the provisions for single loop operation as a license condition and incorporates a similar provision into the body of the Technical Specifications.
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 maintensnce 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.
UNIT 1
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QS3549 Replaced diodes The cause of the When the RBM 7 & 8 were The corrective action was on input relay defective LPRM declared inoperable, a to replace like-for-like cards for RBM cards was rod block was established diodes on the input cards.
7 & 8 (System attributed to to prevent inadvertent As this is an isolated 756) the end of life control rod withdrawal.
case, no further corrective failure of Control rods could still action is deemed necessary.
several diodes.
he inserted to a safe position using the
' EMERGENCY IN' control switch. Therefore, safety implications were minimal.
Q53811 86-37 Taped E.Q.
The root cause of Due to the information The corrective action taken Penetration the failure of the obtained, Unit I was was to tape over the E.Q.
butt splices butt splices used immediately shutdown and butt splices that were in-(System 100) in G.E. Penetra-Unit 2 was in a refueling side the containment of both tion Assemblies outage. The valves involved units. The electrical was that the were operating properly penetrations containing E.Q.
nylon insulation before shutdown was splices are inspected every was degraded commenced.
refueling outage and a major during testing at inspection of all E.Q.
Wyle Labs.
penetration splices is per-formed every sixth refueling outage.
QS3824 Unit 1 Diesel The cause of the All of the low pressure The airstart magnet valve Generator -
Diesel Generator's core cooling & all loops MVST was examined by no problem inability to start of the containment cooling Electrical Maintenance and no found (System is unknown.
mode of the RHR System problem found. No further 6600) along with the 1/2 Diesel corrective action is considered Generatot were available necessary at this time.
during the 11 minutes the Unit 1 Diesel Generator was inoperable. Therefore, safet'y implications were minimal.
0027H/0061Z
UNIT 1
MAINTENANCE StAAAARY CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUlEER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q53990 No problems The cause of the IB Safety implications were The Electrical Maintenance found (System RHR Service Water minimal because the 'B' Department investigated 5700)
Pump Room Cooler loop of the containment the failure, but could fans failing to cooling mode of the RHR find no problem. The start could not System and the Unit 1 control switch for the IB be determined.
Diesel Generator were RHR Service Water Pump was determined to be operable.
then exercised and the four cooler fans started as designed. There have been no reoccurrences and no further corrective action is deemed necessary at this time.
)
't 4
0027H/0061Z
UNIT 2
MAINTENANCE
SUMMARY
CAUSE RESULTS & EFFECTS W.R.
LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q52872 86-14 A0-8801C -
This work was Actual leakage would Corrective action &
Cleaned valve necessary due to 1e less than tested, as action to prevent
& lapped seat excessive leakage testing is conservative, repetition will be de-(System 8800) during Local Leak Also, Secondary Contain-lineated in a supplemental Rate Testing. The ment & Standby Gas report to this LER (86-14).
cause is being Treatment Systems would investigated &
be available.
will be de-lineated in a supplemental report.
Q53154 86-14 2-220-62A -
See Q52872 See QS2872 See Q52872 Repaired Feedwater Check Valve (System 220)
Q53821 2-590-108B -
The cause of the The 590-108B relay is The 590-108B relay contacts Replaced relay malfunction of the used to actuate the back-were replaced like-for-like coil & aux 3-4 auxiliary up scram valve, 2-302-
& successfully tested. This contacts contacts on the 19B. As the 3-4 contacts is considered an isolated (Systea 590) 590-108B relay of the 108B are wired in incident and no further was the slight parallel with the 108F, corrective action is burning & carbon 2-302-19B would still necessary build-up on the have worked. Therefore, contacts which safety implications are prevented circuit minimal.
continuity.
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 Las set forth in sections 6.6.B.1. and 6.6.B.2. of the Technical Specifications.
Unit 1 Licensee Event Report Number Date Title of Occurrence 87-01 1-5-87 Reactor Water Clean-4_
up System Isolation 87-02 1-7-87 Missed Hourly Fire Watch Unit 2 Licensee Event Report Number Date Title of Occurrence 87-01 1-3-87 Failure of 1/2 Diesel Generator to Auto-Start During Logic Testing 87-02 1-22-87 RCIC Inoperable 1-26-87 87-03 1-27-87 HPCI Inoperable 87-04 1-27-87 Failure of RCIC to 4
Fast Start, Less Than 30 Seconds i
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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/0061Z
1 OPERATING DATA REPORT DOCKET NO.
50-254
- UNIT, ONE D A T E F E B_Ilt) A R Y 6 19_87 COMPLETED BYK_URT_ A SCHMI_DT TELEPHONE 3_09 654-2241 OPERATING STATUS 0000 010187 1.
Reporting period:2400 013187 Gross hours in reporting period:
744 2.
Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
This Month Yr to Date Cunulutive 5.
Number of hours reactor was critical 744.0 744.0 103556.7 6.
Reactor reserve shutdown hours 0.0 0.0 3421.9 7.
Hours generator on line 744.0 744,0 100060.5 8.
Unit reserve shutdown hours.
0.0 0.0 909.2 7.
Gross thernal energy generated (MWH) 180_8816_
1808816
_2i_0.866634_
- 10. Gross electrical energy generated (MWH) 604117 6.04117 68357_501 ii. Net electrical energy generated (MWH) 576938 576938 64024140
- 12. Reactor service factor 100.0 100.0 80.2
- 13. Reactor avo11obility factor 100.0 100.0 82.9
- 14. Unit service factor 100.0
_iOO,n 77.5
- 15. Unit avo11ob111ty factor 100.0
, _ _ _ 100.0 78.2
- 16. Unit capacity factor (Using MDC) 100.8 100.8 64.5
- 17. Unit capacity factor (Using Des.MWe) 98.3 98.3 62.9
- 18. Unit forced outoge rate 0.0 0.0 5.7
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
- 20. If shutdown at cnd of report period,estincted date of startup __,NA_________
$UN0FFICIAL COMPANT NUMBERS ARE USED IN THIS REPORT
OPERATING DATA REPORT DOCKET NO.
50-265 UNIT __
TWO DATEFEBRUARY 6 i?87 COMPLETED BYKURT h SClidIDT TELEPHONE 3_09 654-224.1 OPERATING STATUS 0000 010187 1.
Reporting period 2400 01310Z Gross hours in reporting period:
744 2.
Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 3.
Power level to which restricted (if any)(MWe-Net): NA 4.
Reasons for restriction (if any):
This Month Yr.to Date Cumulative 5.
Number of hours reactor was critical 191.4_
191.4 97907 1 6.
Reactor reserve shutdoun hours 0.0 0.0 2985.8 7.
Hours generator on line 150.9 158.9 94858.0 8.
Unit reserve shutdown hours.
0.0 0.0 702.9 9.
Gross thermal energy generated (MWH) 206093
_206093
_2_01545792
- 10. Gross electrical energy generated (MWH) 66250 66250 64425542 ii. Net electrical energy generated (MWH) 60146 60146 60657183
- 12. Reactor service factor 25.7 25.7 76.4
- 13. Reactor avo11obility factor
_ J 5, '7
___25.7 78.7
- 14. Unit service factor 21.4 21.4, 74.0
- 15. Unit availability factor 21.4-21,.4 74
- 16. Unit capacity factor (Using MDC) 10.5 10.5 61.5
- 17. Unit capacity factor (Using Des.MWe) 10.2 10.2 60.0
- 18. Unit forced outage rote 30.1 30.1 7.7
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
- 20. If shutdown at enn of report period,estincted dote o f s t or t u p ___ _NA_________
$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT
l APPENDIX B AVERAGE DAILY UNIT POWER' LEVEL DOCKET NO.
50-254 UNIT _
ONE DATEEEBRUARY'6 1987 COMPLETED BYKURT A SC_HMIDT TELEPHONE 309 654-2241
-MONTH Januarv 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE: DAILY POWER LEVEL
-(MWe-Net)
(MWe-Net)
.i.
789.0 17.
780.0 2.
733.9 18.
773.8 3.
611.4 19, 765.2
. 4 '.
766.4 20.
780.7 5.
783.5 21.
784.5 6.
792.9 22.
770._0 7.
799.5 23.
793.6 8.
788.3 24.
795s9 9.
773'8 25, 759.6 10.
770.7 26.
789.0
' ii.
769.5 2h.
795._2 12, 790.5 28.
790.4 P
13, 792.6
- 29. _
793.5 14.
788.7 30, 795.__i Ji5.
787.4 31, 775.4 16.
782.0 INSTRUCTIONS-neerest uhele, list the oeerege dolly enit power level in mie-Net for each day in the reporting nenth. Compete to the On this fern acgovett.
These figures ull! he : sed to plot a graph for each reporting nenth. Note that when notinen dependable capacity is used for the net electrical rating of the unit,there nay be occasions when the daily overage peuer leeel exceeds the 199111ne (or the restricted power level line).In such cases,the neerage dolly unit power setput sheet sheeld be fests.sted to exphin the opperent enenely
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APPENDIX D p
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-26.5 UNIT _
TWO DATEEEBRJUAR.Y 6 1987_
COMPLETED BYKURT A SCHM_I_DT TELEPHONE 309 654-2241 Junypt.v 1907 MONTH r
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
-4.i 17.
-9.6 2.
-4.2 18.
-0 t.'7 3.
-4.0
- 19. __
-7.6 4.
-4.1 20.
-4.0 5.
-4.0 21.
-14.2 6.
-3.0
- 22. _
52.0_ __
7.
-4.3 23.
6.h8 8.
-4.3 24.
-7.5
~9.
-4.3 25.
-0.3 10.
-4.i 26.
75.2 11.
-4.0 27.
151.5 12.
-4.6 28.
447.3_.
13.
3 29.
557 4 14.
-7.7 30.
658.7 15.
.2 31.
585.__0._
16.
-7.3 INSTRUCTIONG On this forn list the overage daily snit power level in mie-Net for each day in the reporting month. Compete to the e
- neerest whole negewett.
These figeres will be used te plot a graph for each reporting nenth. Note that when nominen dependable capacity is 1991 line (or the restricted power level line),there nay be occasiens when the daily overage power level exceeds the
- j used for the net electrical rating of the enit
.In seth cases,the overage delly snit power setpet sheet sheeld be feetnoted to esplein the opperent enenely ii i
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M M
M M
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P"t ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-254 August 1982 UNIT NAME Quad-Cities Unit 1 COMPLETED BY Kurt Schmidt DATE February 9, 1987 REPORT MONTil JANUARY 1987 TEI.EPil0NE 309-654-2241 N
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NO.
DATE (IlOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS oQ 87-1 870102 S
0.0 B
5 HA TURBIN Reduced load to 700 MWe for Turbine surveillances 87-2 870103 F
0.0 A
5 llA VALVEX Reduced load to 392 MWe due to Turbine Control Valve failure APPROVED AUG 1 G 1982 (final)
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M M
M M
M M
M M
M M
M M
ID/5A APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY Kurt Schmidt DATE February 9, 1987 REPORT HONTil JANUARY 1987 TELEPil0NE 309-654-2241 I
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5 a5W Wm Q
LICENSEE g,
DURATION EVENT o"
"g u
NO.
DATE (HOURS) o REPORT NO.
CORRECTIVE ACTIONS / COMMENTS A
87-1 870122 S
1:15 B
5 HA TURBIN Reduced load for Turbine overspeed tests 87-2 870123 F
68:25 A
2 HC HTEXCH Unit shutdown due to condenser tube leaks 87-3 870130 F
0:00 11 5
HC HTEXCH Reduced load due to condenser back pressure problems i
87-4 870131 F
0:00 H
5 HC HTEXCH Reduced load due to condenser back pressure problems APPROVED AUG 1 G 1982 (final) ygg3g
~
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 Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.
Unit: Twc Date: January 22, 1987 Valvea Actuated No. & Type of Actuation 2-203-3A 1 Manual 2-203-3B 1 Manual 2-203-3C 1 Manual 2-203-3D 1 Manual 2-203-3E 1 Manual Plant Conditions: Reactor Pressure - 923 PSIG Description of Events: Surveillance Technical Specification 4.5.D.l.a B.
Control Rod Drive Scram Timing Data for Units One and Two The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifica-tions 4.3.C.1 and 4.3.C.2.
The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with Reactor pressure greater than 800 PSIG.
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VII.
REFUELING INFORMATION 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.
l 0027H/0061Z
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 l
INFORMATION REQUEST 1.
Unit:
01 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 Itcensing 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 assemblies, 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:
Licensed storage capacity for spent fuel:
3657 a.
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 WPPROVED APlR 2 01978 Q.C.O.S.R.
qTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
Q2 Reload:
8 Cycle:
9 2.
Scheduled date for next refueling shutdown:
3-14-88 3
Scheduled date for restart following refueling:
5-22-88 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:
DECEMBER 14, 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 AT PRESENT TIME, 7
The number of fuel assemblies.
a.
Number of assemblies 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 licen' sed storage capacity that has been requested or is planned i
in number of fuel assemblies:
a.
Licensed storage capacity for spent fuel:
3897 b.
Planned increase in licensed storage:
0 i
l 9.
The projected date of the last refueling that can be discharged to the j
spent fuel pool assuming the present licensed capacity: 2008 WPPROVED l APR 2 01978 j
Q.C.O.S.R.
l L
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 Tran:ient Without Scram BHR Boiling Water Redctor CRD Control Rod Drive EHC Electro-Hydraulic Control System EOF Emergency Operations Facility GSEP Generating Stations Emergency Plan HEPA High-Efficiency Particulate Filter HPCI High Pressure Coolant Injection System HRSS High Radiation Sampling System IPCLRT Integrated Primary Containment Leak Rate Test IRM Intermediate Range Monitor ISI Inserv'ce 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 Primary Containment Isolation PCI PCIOMR Preconottioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Water System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RHM Rod Worth Minimizer SBGTS Standby Gas Treatment System Standby Liquid Control SBLC SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCW Turbine Building Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H/00612
O Commonwealth Edison
~
ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 309/654-2241 RAR-87-7 February 2, 1987 Director, Office of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: 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 January, 1987.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R. A. Robey Services Superintendent bb Enclosure g \\\\
0027H/0061Z r s