ML20206M793
| ML20206M793 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 03/31/1987 |
| From: | Robey R, Schmidt K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| RAR-87-17, NUDOCS 8704200189 | |
| Download: ML20206M793 (25) | |
Text
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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFARMANCE REPORT MARCH, 1987 COMMONNEALTH EDISON COMPANY AND I
IONA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 R
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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.
Control Rod Drive Scram Timing Data VII.
Refueling Information VIII.
Glossary i
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F I.
INTRODUCTION i
Quad-Cities Nuclear Power Station is composed of two Bolling Hater Reactors, each with a Maximum Dependable Capacity of 769 MHe 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 Hater Reactors.
The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors.
The Mississippi i
River is the condenser cooling water source.
The plant is subject to license i
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-4 February 18, 1973 for Unit One and March 10, 1973 for Unit Two.
l This report was compiled by Becky Brown and Kurt Schmidt, telephone number 309-654-2241, extensions 2240 and 2147.
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II.
SUMMARY
OF OPERATING EXPERIENCE A.
Unit 1 March 1-15 The month of March was begun by going off of EGC and dropping load from 780 to 740 MWe for turbine surveillance.
Following surveillance, at 0200 load was raised from 740 to 770 MWe at 0210 and then at 5 MWe per hour until 0614 when the unit was placed in EGC.
At 1045, EGC was shut off and the unit brought to full load (828 MWe) by 1430.
On March 2 at 0400 a load drop was begun for relief valve surveillance. At 0645, 437 MWe reached and held until the surveillance was complete and at 0750 load ascent was begun from 430 MWe.
Full power was reached the next day, March 3, at 0245 and held until 0300 on March 4 when high main condenser back pressure required a temporary load reduction.
At 0315 the back pressure was corrected and the unit returned to full load by 0335. At 1348 load was reduced temporarily from 824 to 790 MWe in order to reposition control rods.
The unit was brought to full load at 1422 and remained until 0220 the next morning, March 5, when the unit was placed in EGC.
On March 6, EGC was shut off from 0342 to 0450 for HPCI testing. On March 8, EGC was shut off from 0035 to 0155 for Turbine Generator Surveillances. The unit was taken off of EGC at 0510 on March 9 and run up to full load by 0925.
Full load was held until 0200 on March 11 when load was reduced to 800 MWe for EGC.
EGC was run from 0309 to 0550 and the unit subsequently returned to full load by 0623.
It ran at full load until 0120 on March 12 when it was placed in EGC.
ECC ran until 0710 and the unit was back at full power by 0725. On Friday the 13th of March a load reduction was started at 0038 and the unit placed in EGC at 0055. The unit came out of EGC at 0712 and was ran up to full load and held until 1800 when power reduction was began for a planned shutdown. The unit was at 100 MWe at 2345 and at 0005 the Generator was taken off line. At 0040 on March 14, the mode switch was placed in shutdown. Cold shutdown was reached at 0540.
On March 15, the reactor startup was begun at 1740 and the reactor reached criticality at 1948 with a temperature of 252 and a 75 second period.
March 16-31 March 16 was begun with a unit startup in progress. The generator came on line at 0420 and the rest of the day was spent increasing load.
On March 17 at 0320, load was reduced from 755 to 700 and eventually to 640 MWe to facilitate rod maneuvering.
Power ascent was resumed at 0505 and continued until 1102 when a Reactor Scram occurred due to mois-ture separator high level. At 1740 the reactor was in cold shutdown.
Reactor startup was commenced on March 18 at 0244.
Criticality was reached at 0620 with a temperature of 273 F and a 92 second period. At 1250 the turbine was rolled and at 1313 the generator went on line with an initial load of 120 MWe.
Power ascent was performed until 1725 when i
0027H/0061Z i
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r March 16-31 (continued) scram timing was begun. At 0327 on March 19 scram timing was. complete and power ascent resumed. Load was held at 655 MWe for control rod maneuvering from 1045 until 1401 after which power ascent continued.
On' March 20 at 1540 load was reduced from 700 to 650 MWe because of problems with the 1D3 heater. Power ascent was begun at 1714 and con-tinued until 0305 on March 21.
Load was held at 775 MWe until 1215 when it was dropped to 650 for rod maneuvering. A load increase was begun and continued until 2100 when power was again reduced for rod maneuvers from 815 to 600 MWe where it was held from 2320 until 0000 on March 22 when a 5 MWe/hr ascent was begun.
Full load was reached on March 24 at 0005 and held until 1400 on March 26 when power was reduced for EGC.
The unit went into EGC at 1425. At 2210 EGC tripped due to an input failure and was placed back in EGC at 2235. The unit ran in EGC until March 29.
EGC was shut off from 0007 until 0118 for turbine surveillance. At 2320 EGC tripped for unknown reasons and following required surveillance, EGC was reset at 2325.
EGC was shut off at 0750 on March 30.
At 0920 a leak on the 1A Reactor Feed pump seal water line flex hose forced a rapid power reduction and at 1050, 308 MWe was reached and held until 1600 when power ascent was begun.
Full load was reached at 1510 on March 31 and held for the remainder of the day.
B.
Unit 2 March 1-15 The month of March was begun with the unit operating in ECC.
EGC was shut off on March 2 from 0005 to 0009 for MSIV surveillance. At 0632 EGC was shut off and the unit run up to full power 825 MWe by 0645.
Full load was held until March 5.
At 0111 the unit was placed in EGC.
EGC was shut off on March 6 from 1023 to 1100 and on March 7 from 0040 to 0055 for surveillances. On March 8 at 1650, EGC tripped off due to a problem with the turbine control oil pressure regulators. A load increase was started following a test of the control oil system.
Full load was reached at 2140.
Full load was held for the next two weeks until March 21.
March 16-31 Full load was held from March 8 to March 21.
At 0143 a Reactor Scram occurred caused by the trip of a main transformer sudden pressure relay.
A reactor startup was commenced at 2148.
The reactor became critical at 0130 on March 22, the temperature was 264 and the period 61 seconds.
The turbine was rolled at 1120 and the generator went on line at 1150.
The remainder of the day was spent increasing load. On March 23 at 0145 load was first held at 750 and then dropped to 685 MWe due to a problem in the 2B3 heater.
Load was held from 0230 until 1800 first to correct the heater problem and then to perform rod maneuvers.
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March 16-31 (continued)
At 1801 more heater problems require load' reduction and at 1813 a problem with recire flow mismetch required the recire pumps be placed in indi-vidual manual control.
Over the next four hours, numerous power varia-tions were required to correct these problems and at 2220 a load of 818 MWe was established with load going up 5 MWe/ hour to full. On March 24 at 0155 full load was reached. At 1530 a load reduction was started in order to test relief valves.
550 MWe was held from 1735 until 1930 when a power ascent was begun.
Full load was reached on March 25 at 0710. At 0850 load was dropped for EGC which went on at 0912. On March 26 EGC tripped off at 0014 and was returned at 0024 following required 4
surveillances.
EGC was shut off from 0140 to 0255 for turbine generator i
surveillance and again from 0812 to 0901 for rod maneuvering. EGC was turned off and a load increase started at 1535.
Full. load was reached at 1550 and held until 1900 when it was dropped to return to EGC at 1915.
On March 27 ECC was shut off for a turbine surveillance at 2340 and returned at 0102 on March 28.
On March 30 from 0054 to 0103 EGC was off for MS1V surveillance.
EGC was shut off at 0745 on March 30 and the unit taken to full load by 0800.
It finished the month holding full load.
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III. PLANT OR PROCEDilRE CHANGES. TESTS, EXPERIMENTS, AND SAFETY
.i 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.
i 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
,l for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment i
The following represents a tabular summary of the major safety related maintenance performed on Units 1 and 2 during j
the reporting period. This summary includes the.following:
J Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
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J UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST No.: Q55428 LER NUMBER: N/A COMPONENT: System 300 - Replaced accumulator at Hydraulic Control Unit 1-306-38-27.
j CAUSE OF MALFUNCTION:
The cause of this malfunction was due to a seal leak between the nitrogen and water side of the accumulator.for Hydraulic Control Unit 1-306-38-27 on Unit Two.
RESULTS & EFFECTS ON SAFE OPERATION: There was no effect on safe operation as the Station's Technical Specifications allow one accumulator in a nine rod array to be inoperable.
4 ACTION TAKEN TO PREVENT REPETITION: The action taken was to replace the accumulator. This accumulator will be rebuilt under W.R. Q55512.. As this malfunction occurs under normal wear no further action is necessary.
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UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST'NO.: Q53215 LER NUMBER: 86-017 COMPONENT: System 0201 - Repair leak on weld 02K-S3 for line 2-0201K-12" A.
CAUSE OF MALFUNCTION: The cracks found at welds 02K-S3, 02K-S4, 02C-S3, and 02BS-F2 are considered to be caused by intergranular stress corrosion cracking.
RESULTS & EFFECTS ON SAFE OPERATION: Crack indications of this type tend to propagate at a slow rate.
Therefore, a 100 percent through-wall crack would be easily detected by leakage monitoring systems before a complete failure would occur. No leakage was detected prior to the current refuel outage.
ACTION TAKEN TO PREVENT REPETITION: These welds were repaired with a " full structural" design overlay. These welds were found acceptable and a hydro-static test confirmed them to be watertight.
WORK REQUEST NO.:
Q53216 LER NUMBER: 86-017 COMPONENT: System 0201 - Rebuilt weld overlay on "K" Jet Pump Riser (weld
- 02K-S3).
CAUSE OF MALFUNCTION:
The cracks found at welds 02K-S3, 02K-S4, 02C-S3, and 02BS-F2 are considered to be caused by intergranular stress corrosion cracking.
RESULTS & EFFECTS ON SAFE OPERATION: Crack indications of this type tend to propagate at a slow rate. Therefore, a 100 percent through-wall crack would be easily detected by leakage monitoring systems before a complete failure would occur. No leakage was detected prior to the current refuel outage.
ACTION TAKEN TO PREVENT REPETITION: These welds were repaired with a " full structural" design overlay. These welds were found acceptable and a hydro-static test confirmed them to be watertight.
WORK REQUEST NO.:
Q53217 LER NUMBER: 86-017 COMPONENT: System 0201 - Repair leak on weld 02K-S3 for line 2-0201K-12"A.
CAUSE OF MALFUNCTION: The cracks found at welds 02K-S3, 02K-S4, 02C-S3, and 02BS-F2 are considered to be caused by intergranular stress corrosion cracking.
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UNIT 2 MAINTENANCE
SUMMARY
WGRK REQUEST No.: Q53217 (cont.')
RESULTS & EFFECTS ON SAFE OPERATION: Crack indications of this type tend to propagate at a slow rate.
Therefore, a 100 percent through-wall crack would be easily detected by leakage monitoring systems before a complete failure would occur.
No leakage was detected prior to the current rfuel outage.
ACTION TAKEN TO PREVENT REPETITION: These welds are repaired with a " full structural" design overlay. These welds were found acceptable and a hydro-static test confirmed them to be watertight.
WORK REQUEST NO.:
QS3525 LER NUMBER:
86-017 COMPONENT: System 0201 - Repair leak on weld 02K-S3 for line 2-0201K-12"A.
CAUSE OF MALFUNCTION: The cracks found at welds 02K-S3, 02K-S4, 02C-S3, and 02BS-F2 are considered to be caused by intergranular stress corrosion cracking.
RESULTS & EFFECTS ON SAFE OPERATION:
Crack indications of this type tend to propagate at a slow rate. Therefore, a 100 percent through-wall crack would be easily detected by leakage monitoring systems before a complete failure would occur. No leakage was detected prior to the current refuel outage.
ACTION TAKEN TO PREVENT REPETITION: These welds were repaired with a " full structural" design overlay.
These welds were found acceptable and a hydro-static test confirmed them to be watertight.
WORK REQUEST NO.:
Q53621 LER NUMBER:
86-017 COMPONENT: System 0201 - Repair leak on weld 02K-S3 for line 2-0201K-12"A.
CAUSE OF MALFUNCTION: The cracks found at welds 02K-S3, 02K-S4, 02C-S3, and 02BS-F2 are considereo to be caused by intergranular stress corrosion cracking.
RESULTS & EFFECTS ON SAFE OPERATION: Crack indications of this type tend to propagate at a slow rate. Therefore, a 100 percent through-wall crack would be easily detected by leakage monitoring systems before a complete failure would occur. No leakage was detected prior to the current refuel outage.
ACTION TAKEN TO PREVENT REPETITION: These welds were repaired with a " full structural" design overlay. These welds were found acceptable and a hydro-static test confirmed them to be watertight.
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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.l. and 6.6.B.2. of the Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title of Occurrence 87-04 3-2-87 HPCI Inoperable --
Suction Valve Closure Failure 87-05 3-17-87 Turbine Trip and Reactor Scram due to Moisture Separator High Level UNIT 2 Licensee Event Report Number Date Title of Occurrence 87-05 3-21-87 Generator / Turbine Trip (SPR) Caused Reactor Scram 87-06 3-24-87 HPCI Inoperable -- After Monthly Testing
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V.
DATA TABULATIONS
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The following data tabulations are presented in'this report:
A.
Operating Data Report 8.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 6
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0027H/0061Z
i' OPERATING DATA REPORT DOCKET NO..
50-254 UNIT ONE DATEMARCH 6'1987 COMPLETED BYK,A._SCHMI_DT TELEPHONE 309 654-2241 OPERATING STATUS 0000 030187 1.
Reporting period 2400 033187_ Gross hours in reporting period:
744 2.
Currentiv authorized power level (MWt): 2511 Max. Depend copocity (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):
1his Month Yr.to Date Cumulative 5.
Number of hours reactor was critical 681.6 2097.6 104910.3 6.
Reactor reserve shutdown hours 0.0 0.0 342_i.9 7.
Hours generator on line 615.6 1081.6
..12.1398.1 8.
Unit reserve shutdown hours.
0.0 0.0 909.2 9.
Gross thernal energy generated (MWH) 1516608 4972752 214030570 i
- 10. Gross electrical energy generated (MWH) 499240 1649098 69402482 ii. Net electrical energy generated (MWH) 477230 1576903 65024105
- 12. Reactor service factor 91.6 97.1 80.4
- 13. Reactor ovallobility factor 91.6
__97.1 93.0
- 14. Unit service factor 89.5 96.4 77.7_
- 15. Unit ovellability factor 89 5 96.4 78.4 2
- 16. Unit capacity factor (Using MDC) 83.4 94.9 64.8
- 17. Unit capacity factor (Using Des.MWe) 81.3 92.5 63.1
- 18. Unit forced outage rate 3.8 1.2 5.6
- 19. Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):
- 20. If shutdown at end of report period,estinated date of startup N/A
$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT i
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OPERATING DATA REPORT DOCKET NO._.
50-26E_
UNIT TWO DATEMARCH 6 1987_
COMPLETED BYK.A. SCHMIDT TELEPHONE 309 654-2241 OPERATING STATUS 0000 030187 1.
Reporting period:2400 033187 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.
Newber of hours reactor was critical 720.2 1532.7 99248.4 6.
Reactor reserve shutdown hours 0.0 0.0 2985.8 7,
Hours generator on line 709.9 1479.7 96178.8 8.
Unit reserve shutdown hours.
0.0 0.0 702.9 9.
Gross thernal energy generated (MWH) 1725680 3399677 204739376
- 10. Gioss electrical energy generated (MWH) 564078 1110820 65470112
- 11. Net electrical energy generated (MWH) 540095 1060690 61657727
- 12. Reactor service factor 96.8 71.0 76.6
- 13. Reactor availability factor 96.8 71.0 78.9
- 14. Unit service factor 95.4
. 68.5 74.2
- 15. Unit ovallobility factor 95.4 68.5 74.8
- 16. Unit capacity factor (Using MDC) 94.4 63.9 61.9
- 17. Unit copocity factor (Using Des.MWe) 92.0 62.2 60.3
- 18. Unit forced outoge rote it6 10.0 7.7
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each):
- 20. If shutdown at end of report period, estimated date o f s t a r t u p __ _ N]A___ __ __
$UN0FFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT
l APPENDIX B AVERAGE DAILY UNIT POWER LEVEL l
l DOCKET NO.
50-254 UNIT,_
ONE DATEMARCH 6 1907 COMPLETED BY!(.A. SQ.HMIDT l
TELEPHONE 309 654-2241 MONTH March 1987 DAY AVERAC Q AI g DWER LEVEL DAY AVERAG g I OWER LEVEL i.
766.7 17, 306.7 2.
696.4 18.
113.6 3.
783.8 19, 531 3 4.
798.2 20.
672 4_
3 5.
764.3 21, 730.4 6.
748.i 22, 631.9 7.
765.9 23.
729.i 8.
739.5 24.
784,1 9.
790.3 25.
783.4 10.
782.4 26.
782 J ii.
789.2 27, 738,i 12.
793.1 28.
749.1 13.
670.2 29, 733.0_
14.
-9.2 30, 575.J 15.
-8.7 31, 746.8 16.
408.5 INSTRUCTIONS On this fern, list the overage daily unit power level in MWe-Net for each day in the reporting nenth.Cenpite to the nearest whole neaawatt.
These figures will be used to plot a graph for each reporting nenth. Note that when noxinen depend d le capacity is used for the net electrical rating of the unit,there nay be occasions when the daily overage power level exceeds the 1003 line (or the restricted power level line).In such cases,the overage daily onit power estpst sheet sheeld be festnoted to explair the apparent onenoly
APPENDIX B AVERAGE DAILY UNIT POWER LEVEL i
DOCKET NO.
50-265 UNIT __
T W O_ _ _
DATEMARCH 6 1987 COMPLETED BYl<.A. SCHMIDT TELEPHONE 309 654-2241 MONTH Mrarch 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1.
764.1 17.
793 3 2
2.
764.4 18, 709,8 3.
780.8 19, 778.7 4.
791.7 20.
788.0 5.
757.0 21.
43.9 6.
748.5 22, 161.4 7.
764.9 23.
680_.._2 8.
748.5 24.
727.3 9.
788.8 25.
765,0 10, 780.3 26.
759.9 11.
790 7 27, 738.0 12.
790.I 28, 757.4 13, 790.6 29.
739 i 14.
790.6 30, 777.6 15, 790.0 31, 785.4 16.
781.6 INSTRUCTIONS On this fern, list the average daily init power level in MWe-Net for each day in the reporting nenth. Compete to the n @ es? whole negawatt.
These figures will be used to plot a graph for each reporting nenth. Note that when narinen dependable capacity is used for the net electric 11 rating of the snit,there nap be occasions when the daily overage power level exceeds the ill% line (or the restricted power level line).In such cases,the overage daily unit power evtput sheet should be festnoted to explain the apparent onenaly l
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ID/5A APPENDIX D QTP 300-S13 UNIT SHUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO.
050-254 August 1982 l
UNIT NAME Quad-Cities Unit 1 COMPLETED BY K. Schmidt DATE April 9, 1987 REPORT HONTH MARCH 1987 TELEPHONE 309-654-2241 m
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NO.
DATE (IIOURS)
REPORT NO.
CORRECTIVE ACTIONS / COMMENTS sa 87-7 870314 S
52:15 B
1 ZZ ZZZZZZ Short Maintenance Outage 87-8 870317 F
26:11 A
3 87-005 HB VALVEX Turbine trip / Reactor scram due to moisture separator high level caused by drain valve malfunction 87-9 870330 F
0.0 A
4 CH PIPEXX 1A Reactor feed pump seal water line flex hose leak.
APPROVED AUG 101982 (final) y g,g g g
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 K. Schmidt COMPLETED BY A ril 9, 1987 REPORT MONTil MARCH 1987 DATE P
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2 NO.
DATE (Il0URS)
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REPORT NO.
CORRECTIVE ACTIONS / COMMENTS 87-14 870321 F
34:07 A
3 87-005 EB RELAY-D Spurious relay trip of main transformer sudden pressure relay causes generator trip / reactor scram.
4 APPROVED AUG161982 (final)
V. C. U S k '
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: One Date: March 2, 1987 Values Actuated No. & Type of Actuation 1-203-3A 1 Manual 1-203-3B 1 Manual 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E 1 Manual Plant Conditions: Reactor Pressure - 923 PSIG Description of Events: Surveillance Technical Specification 4.5.D.1.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 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 was performed with Reactor pressure greater than 800 PSIG.
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RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL ROD DRIVES, FROM 1-1-87 TO 12-31-87 AVERAGE TIME IN SECONDS AT %
MAX. TIME INSERTED FROM FULLY WITHDRAWN FOR 90%
INSERTION DESCRIPTION
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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 Ilot Scram Timing (K-5) 2-20-87 1
0.30 0.72 1.58 2.80 2.80 Unit 1 Hot Scram Timing after ilCU (K-7)
Replacement (Work Request Q55428) 3-19-87 89 0.29 0.66 1.43 2.52
~2.82 Unit 1 Ilot Scram Timing (J-11)
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0027H/0061Z i
e 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.
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QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 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 licensing action and supporting information:
AUGUST 21, 1987 6.
Important licensing considerations associated with refueling, e.g., new or different fuel desigr. or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE PLANNED AT PRESENT TIME.
l 4
7.
The number of fuel assemblies.
a.
Number of assembiles in core:
724 b.
Number of assemblies in spent fuel pool:
1573 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 licensed capacity: 2008 APPROVED 1-APR 2 01978 Q.C.O.S.R.
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QTP 300-532 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 thereaf ter 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:
1308 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 3
in number of fuel assemblies:
Licensed storage capacity for spent fuel:
3897 a.
b.
Planned increase in licensed storage:
0 J
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 4PPROVED APR 2 01978 Q.C.O.S.R.
VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined below:
ACAD/ CAM -
Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute APRM Average Power Range Monitor ATHS Anticipated Transient Hithout Scram BHR Bolling Hater 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 PcIS High Radiation Sampling System 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 MFLCPR Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration MSIV Main Steam Isolation Valve NIOSH National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Hater System RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RHM Rod Horth Minimizer SBGTS Standby Gas Treatment System SBLC Standby Liquid Control SDC Shutdown Cooling Mode of RHRS SDV Scram Discharge Volume SRM Source Range Monitor TBCCH Turbine Building Closed Cooling Hater System TIP Traversing Incore Probe TSC Technical Support Center l
0027H/0061Z t
O 22710 206 Avenue North Commonwealth Edison ouad Cities Nuclear Power Station Corcova, Illinois 61242 Telephone 309/654-2241 RAR-87-17 April 1, 1987 Director, Office of Inspection & Enforcement United States N:Jclear 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 March, 1987.
Respectfully, COMMONWEALTH EDIS0ll COMPANY 00AD-CITIES NUCLEAR POWER STATION
- f. h.
R. A. Robey Services Superintendent l
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Enclosure d
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0027H/0061Z