ML20147H113
| ML20147H113 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/31/1987 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RAR-87-58, NUDOCS 8801220234 | |
| Download: ML20147H113 (23) | |
Text
./
,. j # ' !.. '..
e QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER, 1987 COMMONHEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 l
l l
~880'1220234 871231 PDR ADOCK 05000254 R
DCD d
4 0027H/00612 l1 l.
i TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two III.
Plant or Procedure Changes, Tests,_ Experiments, and Safety Related Maintenance A.
Amendments to Facility License or Technical Specifications B.
Facility or Procedure Changes Requiring NRC Approval 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.
Contiol Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary 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 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 OPR-30, issued October 1, 1971, and March 21, 1972, respectivel,, 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 Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
0027H/0061Z
~
II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit One December 1-15 Unit One began the month still in a refueling outage.
From December 1-4 normal outage testing and surveillances were performed. On December 5 at 0245 the Integrated Leak Rate Test began. The test was completed at 0830 on December 6.
On December 7 at 1315 control rod scram timing was resumed and continued until 0138 on the following day, December 8.
Normal outage testing and surveillances continued through December 11 when, at 1149, control rod timing was resumed until the main turbine was placed on the turning gear.
December 16-31
-From December 16-18 the month continued with more outage testing. On December.18 at 0737 the 1A and IB circulating water pumps were turned on.
At 1700 the main turbine was taken off the turning gear. On December 19 at 0545 the B Core Spray header was filled and normal outage work continued until December 22 when, at 1230, the main generator was filled with hydrogen to begin Startup. At 1617 the main turbine was placed on the turning gear.
At 1640 the mode switch was placed in refuel, then to startup at 1735.
At 1806, withdrawal of control rods was begun and at 2200 the Unit 1 Reactor achieved critica111ty.
The head vents were closed at 2228. On December 23, power was held constant while other control rod drives were vented. At 0440 the IB Reactor Feed Pump was turned on and at 0805 the mode switch was placed in RUN. At 0855 Average Power Range Monitor (APRM) gains were set to 13%.
The' generator was synchronized to the grid at 1725,'but at 1750 the main turbine was tripped due to high vibrations. The main turbine was placed back on the turning gear. The turbine began rolling at 0040 on December 24 and the unit went on line at 0120 at 10 MWe initial load and increasing approximately 3 MWe/ min.
At 0145 the unit reached 90 MWe; load was reduced at 0225 si per Shift Engineer due to high vibrations on the turbine, and the unit ecme off line at 0232.
The turbine was tripped at 0355. At 0440 the main tucbine was placed back on the turning gear and at 0750 the turbine began to rol..
The main generator was synchronized to the grid at 1310.
At 1330 control rods were withdrawn to increase power to 180 MWe, Load was held at 156 MWt to adjust APRM gains.
On December 26 at 1010 hot scram timing began anc was completed at 0625 on December 27.
At 1105 the Turbine Overspeed Trip Test was performed, but after reaching 1400 RPM's, the turbine began decelerating and subsequently was tripped.
The turbine was reset at 1510 and placed in the turning gear. At 1805 turbine was brought up to 1370 rpm and control valves closed, turbine was manually tripped.
Turbine problem investigation and repair work continued until December 29 at 1703 when the turbine was synchronized to the generator.
Turbine ran until 2040 when it was tripped for overspeed test.
Then at 2210 the turbine was synchronized to the generator and load increase was begun using control rod withdrawal and recirc system.
Startup testing was performed through December 31.
0027H/0061Z
. +.,
- - _ ~.
a B.
Unit'Two December 1-15 Unit Two began the month of December on EGC and operated in EGC with minor interruptions for normal testing.until December 10 when at 0117 the reactor scrammed on a turbine / generator load mismatch. At 0252 the main turbine was placed on the turning gear and at 0345'the mode switch was placed in startup and rod moves were begun to increase power.
The reactor achieved criticallity at 1141, control rod moves continued and the mode switch was placed'in run at 2220. On December 11 at 0031 the main generator was synchronized to the grid. The initial load was 120 MWe and a power ascent was begun with control rods and recirc pumps.
Full power was reached on December 12 at 1110 (818 MWe), but was decreased at 1118 with recirc pumps to 800 MWe because of high MFLD readings.
At 1359 control rods were inserted because of high LPRM readings.
Power was held constant.
December 16-31 Normal plant operations continued through the remainder of the month with small power reductions and increases as per requested through the load dispatcher. The unit operated in EGC for 353.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for the month of December. Normal surveillance testing was performed during the month.
1 1
n.-
e III.
PLANT OR PROCEDURE CHANGES,' TESTS. EXPERIMENTS, AND SAFETY-RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications Technical Specification Amendment No. 103 was issued on December 17 to facility operating license DPR 29.
This Tech Spec amendment included revisions to plant operating limits, operating domains and surveillance requirements to reflect the new fuel type being utilized for this cycle.
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 Repetition.
0027H/0061Z I
l UNIT 1 MAINTENANCE
SUMMARY
~
WORK REQUEST NO.: -Q53539 LER NUMBER:: N/A
. COMPONENT:
System 1000 - Journal bearing for 1A RHR S.W.
(1-1001-65A) sent to G.E. for repairs.
CAUSE OF MALFUNCTION: The cause for the failed motor bearing on the 1A Residual
-Heat Removal Service Water (RHRSW) pump (1-1001-65A) was determined to be'the result' of loose journal bolts.
The bolts loosened with. vibration allowing bearing oil to leak out, eventually causing its failure.
RESULTS-& EFFECTS ON SAFE OPERATION:
There were no results or effects on safe operation as all other active components required by Technical Specification 3.5 B.2 were proven operable.
' ACTION TAKEN TO PREVENT REPETITION:
The journal bearing was removed and sent to General Electric.for repair.
It was einstalled and operability and vibrational testing were found acceptable. As this :s an isolated incident, no further corrective action is necessary.
WORK REQUEST NO.:
Q57667 LER NUMBER: N/A C0HPONENT:
System 9400 - Resoldered corroded wire on Control Room Vent CL Monitor, 1/2-9400-103.
CAUSE OF MALFUNCTION:.The cause of the malfunction of the chlorine monitor portion of the control room toxic gas analyzer (1/2-9400-103) was a corroded solder. joint.
RESULTS & EFFECTS ON SAFE OPERATION: As the control room ventilation was manually placed in the 100 percent recirculation mode as soon as the analyzers were noted to be functioning improperly, preventing any potential intake of toxic gases from outside, safety consequences were minimal.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to disassemble the chlorine monitor cell and resolder the failed connection. The cell was refilled with electrolyte solution and tested successfully.
The control room ventilation was then returned to its normal circulation mode.
i
UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST NO.: Q57585 LER NUMBER: N/A COMPONENT:
System 1000 - No problems found with valve 2-1001-16B.
CAUSE OF MALFUNCTION:
Failure of the 2-1001-16B to reopen after being closed for its Monthly Operability Surveillance is unknown.
RESULTS & EFFECTS ON SAFE OPERATION: There were no results or effects on safe operation as all other safety systems required by Technical Specification 3.5.B.3 were operable.
ACTION TAKEN TO PREVENT REPETITION: During investigation of valve 2-1001-16B by the Electrical Maintenance Department it worked flawlessly. After two more subsequent attempts, six altogether, no further problems were observed. As this is an isolated incident no further corrective action is deemed necessary at this
- time, e
t 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.B.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title of Occurrence 87-027 12-1-87 Control Room Vent Isolation (ESF) False Signal - Control Room HVAC Isolation While OJT 87-028 12-2-87 Missing, Damaged Fire _ Seals -
Open Penetration in U2 Cable Tunnel 87-029 12-7-87 B13-1 2nd Level UV Timer Out of Tolerance 87-030 12-19-87 U-1 ATWS Hangers Do Not Meet Design Specifications87-031 12-23-87 2301-14 Failure (would not open with 3 valve open)87-032 12-23-87 RCIC Inoperable (failed to inspect during test)87-033 12-26-87 Inadvertent Rod Scram - During Hot Scram Timing UNIT 2 87-020 12-10-87 Reactor Scram - T/G Load Mismatch 87-021 12-30-87 SBCS Valve Breaker Failed 0027H/0061Z
- r -
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
APPENDlX C OPERATING D ATA REPORT 00CKET NO.
50-254 UNIT ONE DATE JANUARY 8.
1988 LYNNE DEELSNYDER COMPLETED BY TELEPHONE (309)-654-2241 l
OPERATING STATUS 0000 120187 744 2400 123187 GROSS HOUR $ 1N REPORTING PERIOD:
- 1. REPORTING PERIOD:
2511 MAX. DEPEND. CAPACITY (MWe-Neth 769
- 2. CURRENTLY AUTHORIZED POWER LEVEL (Mg:9 DESIGN ELECTRICAL RATING (MWe Noth N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IP ANY) (MWtNeth
- 4. REASONS FOR RESTRICTION (IF ANYh THIS MONTH YR TO DATE CUMULATIVE 218.0 6251.6 109064.3_
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL..,...........
0.0 3421.9 0.0
- 6. R EACTOR R ESERVE SHUTOOWN HOURS.................
125.0 6141.7 105458.2
- 7. HOUR $ GENERATOH ON LINE........................
0.0 0.0 909.2
- 8. UNIT RESERVE SHUTDOWN HOURS..................
14241357 223299175
............ 69025
- 9. GROSS THERMAL ENERGY GENERATED (MWH) 30467 4670118 7242350_2
- 10. GROSS ELECTRICAL ENERGY GENER ATED (MWH)...........
4456087 67903289
............. 25806
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 29.3 71.4 79.6
- 12. 8"EACTOR SERVICE F ACTCR........................
29.3 71.4 82.1
- 13. REACTOR AV AILABILITY F ACTOR,....................
16.8 70.1 76.9
- 14. UNIT SERVICE F ACTOR................,.......
16.8 70.1 77.6_
- 15. UNIT AV AILABILITY F ACTOR..........................
4.5 66.1 64.4
- 16. UNIT CAPACITY FACTOR (Uslog MDCI...,.
4.4 64.5 62.8
- 17. UNIT CAPACITY F ACTOR (Using Design MWe)..............,.
12.7 0.6 5.4
- 18. UNIT FORCEO OUTAGE RATE..............
- 19. SHUTOOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE, AND OURATION OF EACHh
- 20. IF SHUT DOWN AT END OF REPORT PERIOD. ESTIMATED OATE OF STARTUP:
FORECAST ACHIEVEC 21, UNITS IN TEST ST ATUS (PRIOR TO COMMERCf AL OPERATIONh INITI AL CRITIC ALITY INIfl AL ELECTRICITY COMMERCI AL OPERATION 1.16 9
5 APPENDIX C OPERATING DATA REPORT DOCKET NO.
50-265 UNIT N
DATE JANUARY 8, 1988 LYNNE DEELSNYDER COMPLETED BY TELEPHONE _ (309)-654-2241 l
OPERATING STATUS 0000 120187 744 2400 123187 GROSS HOURS IN REPORTING PERIOO:
- 1. REPORTING PERIOD:
2511 MAX. DEPEND. CAPACITY (MWe Neti: 769
- 2. CURRENTLY AUTHORIZED POWER LEVEL (Mg:Y DESIGN ELECTRICAL RATING (MWeNet);
N/A
- 3. POWER LEVEL TO WHICH RESTRICTED (IF ANY) (MWe Net):
- 4. REASONS FOR RESTRICTION (IF ANYh THl3 MONTH YR TO D ATE CUMULATIVE
,. 731.6 6941.4 104657.I
- 5. NUMBER OF HOURS REACTOR WAS CRITICAL,..........
0.0 0.0 7985.8
- 6. R EACTOR RESERVE SHUTDOWN HOURS...................
............... 720.8 6816.?
101515.1
- 7. HOURS GENERATOR ON LINE......
O.O O.0 707 4
- 8. UNIT RESERVE SHUTDOWN HOURS 16030868 217370567
............. 1703136
- 9. GROSS THERMAL ENERGY GENER ATED (MWH) 553721 5198492 69557784
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWH).......
528551 4962988 65560025.
- 11. NET ELECTRICAL ENERGY GENERATED (MWH) 98.6 79,2 76.8
- 12. c EACTOR SERVICE F ACTOR.................
98.6 79.2 79.0
- 13. REACTOR AVAILABILITY F ACTOR.......
96.9 78.0 74.5
- 14. UNIT SERVICE FACTOR,.........................
96.9 78.0 75.0
- 15. UNIT AVAILABILITY F ACTOR.............
92.4 73.4 __.
62,6
- 16. UNIT CAPACITY F ACTOR (Using MDC).....................
90,1 71.8 61.0
- 17. UNIT CAPACITY F ACTOR (Uting Design MWel......
3.I 17.4 8,4
- 18. UNIT FORCED OUTAGE RATE
- 19. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACHl:
- 20. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
FORECAST ACHIEVED
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPERATION):
INITI AL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPERATION 1.16-9
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
s0-2s4 UNIT ONE DATE JANIIARY 13, 1988 COMPLETED BY L DEETSNYDER TELEPHONE 309-654-2241 MONTH DECEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 1
-6 gy
-5
-2
-8 2
gg
-1I 19
-9 3
-6
~9 4
20 5
-5 21
-9 g
-6 22
-9 7
-6 23
-14 3
-6 24 53 g
-6 25 Ill
-6 I47 10 26 11
-4 27 51 12
-9 28
-16 13
-1 29 I8 F
-6 14 30 313
-5 412 15 31 16
-6 l
l l
INSTRUCTIONS l
On this form, list the average dady unit power level in MWe Net for each day in the reporting month. Compute to the neassst whole megawatt.
These figures will be used to plot a graph for cash reporting month. Note that when maximum dependable capacity is used for the net eteetncal rating ut the unit. there may be owasions when the daily average power level exceeds the 100'A line (or the rntrwted power Icsel hnc). In such cases. the average dady unit power output sheet should l>-
footnoted to explaua the apparent anomaly.
1.16 8 i
l
APPENDlX 8 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-265 UNIT Tk'O DATE mtfARY 13. 1988 COMPLETED BY L. DEELSNYDER TELEPHONE 309-654-2241 MONTH DECEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe Net) 1 750 gy 756 2
755 gg 791 705 gg 852 3
4 748 20 709 5
736 21 779 6
754 22 748 772 737 7
23 8
757 24 712 g
757 2g 694 29 723 to 24 gj 558 27 738 12 722 28 719 13 734 29 715 705 14 757 30 732 15 720 31 18 751 INSTRUCTIONS On this form, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nesisst whole megawatt.
These figures will be used to plut a graph for cash reporung month. Nute that when m43imum dependable capacity is used f or the net cleetncal rating ut the unit. there may be ucasions when the daily average power level exceeds the 100'A line (or the rntnered power level Ime). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly.
1.164 s
ID/SA APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
50-254 August 1982 UNIT NAME _ QUAD CITIES UNIT ONE COMPLETED BY L. DEELSNYDER DATE JANUARY 13, 1988 REPORT MONTH DECEMBER 1987 TELEPHONE 309-654-2241 8
m g
w" 5
$EN gm Ww g$
$ gM LICENSEE m@
w DURATION M
EVENT
$0 O
g o
NO.
DATE (HOURS)
"g REPORT NO.
u CORRECTIVE ACTIONS / COMMENTS 87-20 870912 S
545.4 C
4 RC FUELXX End of Cycle Nine Refueling Outage 87-21 871223 F
7.5 A
9 TA TG Generator Tripped Due to Turbine Vibration s
87-22 871224 F
10.6 A
9 TA TG Generator Tripped Due to Turbine Vibration s 87-23 871227 S
54.0 B
9 TA TG Turbine Tripped for Overspeed Test 87-24 871229 S
1.5 B
9 TA TG Turbine Tripped for Overspeed Test 4
APPROVED AUG161982 (final)
Q. C. O. S H
ID/SA APPENDIX D QTP 300-S13 UNIT SUUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
50-265 August 1982 UNIT NAME OUAD CITIES UNIT TWO COMPLETED BY L. DEELSNYDER DATE JANUARY 13. 1988 REPORT MONTH DECEMBER 1987 TELEPHONE 309-654-2241 5
w e
5
$EE gw
$w a
w e
M LICENSEE m@
g DURATION d
!iE g EVENT o
NO.
DATE (110URS)
"g REPORT NO.
u CORRECTIVE ACTIONS / COMMENTS 87-22 871210 F
23.2 A
3 2-87-020 TA-TB TG Reactor Scram on Turbine / Generator Load Mismatch APPROVED AUG161982 (final) y c.o s.x
- ~
~
~.
2 VI. UNIQUE REPORTING REQUIREMENTS The following items areLincluded 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 The basis for reporting this data to_the-Nuclear Regulatory Commission are specified in the surveillance requirements of' Technical Specifications 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 y'
was performed with Reactor pressure greater than 800 PSIG.
0027H/0061Z
RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL R00 DRIVES, FROM 1-1-87 TO 12-31-87 1
AVERAGE TIME IN SECONDS AT %
MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%
INSERTION DESCRIPTION NUMBER S
20 50 90 Technical Specification 3.3.C.1 &
DATE OF RODS 0.375 0.900 2.00 3.5 7 sec.
3.3.C.2 (Average Scram insertion Time) 1-27-87 177 0.30 0.67 1.44 2.53 2.91 Unit 2 Hot Scram Timing (K-5) 2-20-87 1
0.30 0.72 1.58 2.80 2.80 Unit 1 Hot Scram Timing after HCU (K-7)
Replacement (Work Request Q55428) 3-19-87 89 0.29 0.66 1.43 2.52 2.82 Unit 1 Hot Scram Timing (J-II) 9-6-87 91 0.30 0.67 1.43 2.53 2.77 Unit 2 Hot Scram Timing (G-9) 11-3-87 2
0.28 0.65 1.40 2.49 2.54 Unit 2 M-7 & C-5 Hot Scram Timing (M-07) after work on accumulators (Work Requests Q60928 & Q60780) 11-4-87 3
0.31 0.67 1.43 2.51 2.64 Unit 2 M-5 & M-6 Hot Scram Timing after (M-06) work done on scram outlet valves.
(Work Requests Q61254 & Q61256). P-ll scram timed after being stuck.
12-26-87 177 0.30 0.69 1.48 2.60 3.40 U-l Hot Scram Timing (G-4) 0027H/0061Z
VII.
REFUELING INFORMATI_0N-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.
0027H/0061Z
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
Q1 Reload:
9 Cycle:
10 2.
Scheduled date for next refueling shutdown:
6-24-89 3
Scheduled date for restart following refueling:
9-17-89 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
NOT AS YET DETERMINED.
5 Scheduled date(s) for submitting proposed IIcensing action and supporting Information:
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.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1773 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 assembiles:
a.
Licensed storage capacity for spent fuel:
3657 b.
Planned increase in licensed storage:
0 9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 WPPROVED APR 2 01978 C). C:. C). S. R.
-n
,w
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING Harch 1978 INFORMATION REQUEST e
1.
Unit:
02 Reload:
8 Cycle:
9 2.
Scheduled date for next refueling shutdown:
4-9-88 3
Scheduled date for restart following refueling:
5-22-88 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:
YES. TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLGR CURVES).
CHANGE TO MCPR LIMIT AND OPERATION AT INCREASED CORE FLOW / FINAL FEEDWATER TEMP. REDUCTION.
5.
Scheduled date(s) for submitting proposed licensing action and supporting In forma ti on :
FEBRUARY 22, 1988 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:
FIRST RELOAD OF GENERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHGR LIMIT OF 14.4 KW/FT.
7 The number of fuel assemblies, a.
Number of assemblies In core:
724 b.
Number of assemblies in spent fuel pool:
1311 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:
Licensed storage capacity for spent fuel:
a.
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 WPPROVED APR 2 01978 C). C:. C). S. R.
{
3 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 BWR Boiling Water Reactor 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 Integrated Primary Containment Leak Rate Test IPCLRT 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 HCPR Minimum Critical Power Ratio MFLCPR Maximum Fraction Limiting Critical Power Ratio Maximum Permissible Concentration MPC MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health Primary Containment Isolation PCI PCIOMR Preconditioning Interim Operating Management Recommendations RBCCW 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 RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System Standby Liquid Control SBLC SOC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor Turbine Building Closed Cooling Water System TBCCW TIP Traversing Incore Probe TSC Technical Support Center 0027H/0061Z m.
.m..._
r 9
@ Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova. Idinois 61242 Telephone 309/654 2241 RAR-87-58 December 31, 1987 U.S. NRC Office of Nuclear Reactor Regulation Washington, D. C.
20555 Attn: Document Control Desk Enclosed for jour information is the Monthly Performance Report covering the operation ed Quad-Cities Nuclear Power Station, Units One and Twe, during the month of December, 1987.
Respectfully, COMMONHEALTH ELIS0N COMPANY QUAD-CITIES NUCLEAR POWER STATION 1
fS. 0 p
R. A. Robey Services Superintendent vk l
Enclosure 1
a
,- t svM',(j
?v J
fy oo2w0osu
_