ML20237G809
| ML20237G809 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 07/31/1987 |
| From: | Robey R, Schmidt K COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RAR-87-35, NUDOCS 8708240241 | |
| Download: ML20237G809 (24) | |
Text
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1 QUAD-CITIES NUCLEAR POWER STATION I
UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JULY, 1987 COMMONWEALTH EDISON COMPANY AND 10HA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE N05. DPR-29 AND DPR-30 8708240241 070731 PDR ADOCK OfiOOO254 R
PDR Y
0027H/00612 f
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TABLE OF CONTENTS I.
Introduction II.
Summary of Operating Experience A.
Unit One i
B.
Unit Two III.
Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A.
Amendments to facility License or Technical Specifications l
B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approval l
D.
Corrective Maintenance of Safety Related Equipment IV.
Licensee Event Reports V.
Data Tabulations A.
Operating Data Report B.
Average Daily Unit Power Lc'iol 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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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 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 Kurt Schmidt, telephone number 309-654-2241, extensions 2240 and 2147.
i 0027H/00612 l
r II.
SUMMARY
OF OPERATING EXPERIENCE A
Unit 1 July 1-15 Unit One began the month of June operating in EGC, and continued with only brief interruptions until 0200 on July 4.
At that time, the unit was taken out of EGC and a load reduction commenced to allow for a control rod pattern L
adjustment. A minimum power of 460 MWe was reached at 0710 and upon completion I
of the control rod moves, a slow power ascent was begun at 0755. The power ascent continued until July 6 at 0750 when another slight rod adjustment was required. The ascent resumed at 0800 and continued until 2330 when a power reduction was begun from 760 MWe to facilitate a drywell entry. A minimum power of 350 MWe was attained at 0205 on July 7.
A drywell entry was made at 0245 to add oil to the A recire pump upper bearing. Upon completion of the work, a power ascent was begun at 0530.
600 MWe was attained at 0610, and the ascent was slowed to 5 MWe per hour.
Full load was reached at 1903 on July 8 and held until 0006 on July 10.
Power was reduced, and the unit placed in EGC at 0052. The unit was taken out of EGC at 0633 with a sub-sequent slow ascent to full power.
Power was reduced at 0215 on July 11 and the unit placed in EGC at 0244. The unit was operated in EGC until 0255 on July 12.
Following a weekly turbine test the unit was placed back in EGC at 0420 and operated until 1615 when EGC was turned off to prepare for j
a change of the Recire Motor Generator (MG) set oil coolers.
Following control l
rod position adjustments to reduce the flow control line, a slow power ascent was begun at 2030.
Full power was reached at 1230 on July 13 and held until 0140 on July 14.
Power was reduced at the request of the Load Dispatcher (LD) to a minimum of 600 MWe at 0355. This power level was held until 0530, followed by an ascent to full power.
Full power was reached at 0005 on July 15 and held until 1605 when it was reduced for EGC. The unit was placed in EGC at 1700 and operated in EGC for the mainder of the day.
July 16-31 Unit One began July 16 operating in EGC.
EGC was off for a turbine bypass valve test from 0937 until 1005 on July 16.
On July 17, EGC was tripped at 0840 to prepare for reversal of main condenser cire water flow. Following the reversal, the unit was increased to full power which it held from 1140 until 0120 on July 18.
Power was reduced and the unit placed in EGC at 0145.
EGC was off for a Reactor Feed Pump (RFP) change from 0316 until 0346 and on July 19 from 0000 until 0115 for turbine generator tests. At 0552 on July 19, EGC was turned off and load was reduced to 600 MWe at the request of the LD.
At 0650, a power ascent was begun.
Full load was reached at 2100 and held until 0025 on July 21.
Power was reduced and the unit placed in EGC at 0030. At 0826, EGC was turned off and the unit raised to full load by 0850.
At 1350, power had to be rapidly reduced due to a loss of vacuum.
From 1352 until 1430 load was held at 538 MWe.
The vacuum problem 0027H/0061Z 1
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I l-was corrected and the unit raised to full load by 2230.
Full load was held until 2150 on July 22 when it was reduced-and the unit placed in EGC at 2205.
On July 23 at 0921, the unit was taken out of EGC and raised to full load by 0930.
Full load was held until 0345 on July 24.
The unit was operated in EGC from 0355 until 0850 and returned to full load by 0905. At 0240 on July 25, power was reduced and the unit placed in EGC at 0255. 'There was an EGC trip at 1215 due to a reserve emergency.
Load was raised to 770 MWe I
by 1315 and held until 2330. At that time, a load reduction was begun to.
1 facilitate a control rod pattern adjustment. Load was held at 500 MWe during the control rod movements from 0130 until 0240 on July 26.
A slow power ascent was begun and the unit achieved full load at 1700 on July 28.
Full load was held until 1550 on July 29 when it was reduced slightly to allow for control rod withdrawal. At 1558 a lightning strike on line LO403 caused circuit breakers OCB 7-8 and 8-9 in the 345 KV switchyard to open, and also caused numerous alarms in the control room, as well as an isolation of the control room ventilation (See LER 87-014).
There was no apparent damage.
At 1700, a power increase was begun and the unit reached full load at 2000-which it held until 0045 on July 31.
Load was reduced to 716 MWe to avoid backpressure problems while reversing cire water flow in the main condenser.
Following the flow reversal, load was raised to 780 MWe at 0450 and held for the rest of the day. At 0526 a power supply failure caused an isolation of the reactor building vents and an auto start of the standby gas treatment system-(see LER 87-015).
B.
Unit 2' July 1-15 Unit Two began the month holding full load. At 0100, a rapid load reduction was started for Special Test (ST) 2-71.
This is a test of the units ability to load follow while using barrier fuel. Minimum power (420 MWe) was ranched at 0257 and held until 0525. A rapid power ascent returned the unit to full load by 0730 which it held until July 2 at 0025 when ST 2-71 was repeated.
Full load was reached at 0730 and held until 0000 on July 3 when ST 2-71 was performed again.
Full load was reached at 0803 and held until 0105 on July 4 when~the fourth and final performance of ST 2-71 was commenced.
Full load was reached at 0930 and held until 0045 on July 5.
Load was again rapidly reduced, this time at the request of the Load Dispatcher (LD). Minimum load, 406 MWe was reached at 0245 and held until 0845.
Power was increased and the unit reached full load at 1110.
Full load was held until-1235 on July 6 when' power was reduced slightly with recircs to allow for a control rod with-draway.
Full power was restored at 1254 and held until 1510 on July 7 when power was reduced to help restore deteriorating condenser vacuum.
Power was held at 730 MWe from 1520 until 1800.
Power was increased and the unit reached full load by 1915 which it held until 0113 on July 9 when the unit
_ _ _ _ _ _ _ - = _ _
I was placed in EGC.
The unit was operated in EGC until 0831 when EGC was tripped and the unit raised to full load by 0925. Full load was held until l
0025 on July 10 when pow r was reduced and the unit placed in EGC at 0155.
(
At 0240 the unit was taken out of EGC and a load reduction initiated at the request of the LD.
600 MWe was reached at 0340 and held until 0610, Power l
was increased, and the unit reached-full load at 0740.
Full load was held
)
until 0039 on July 12 when power was reduced for EGC operation beginning
]
at 0102 and continuing until 0255 on July 13.
Power was again reduced per j
the LD's request to a minimum of 600 MWe from 0355 until 0530 and then 1
returned to full load by 0715. At 0615, power was reduced for EGC which l
was operated from 1710 until 2305. Power was reduced to 620 MWe in preparation for reversing main condenser circ water flow.
At 0030 on July 14, a further load reduction was initiated at the request of the LD.
Power was held at 510 MWe until 0540 when a power ascent was begun. The ascent paused twice because of minor process computer malfunctions.
Full load was achieved at 2100 and held until 1611 on July 15, when power was reduced for EGC. The unit was placed in EGC at 1640 and operated in EGC for the remainder of the day.
July 16-31 Unit Two began July 16 operating in EGC. At 0155 the unit was taken out of EGC and power reduced at the LD's request.
600 MWe was held from 0255 until 0545. The unit was returned to full power by 1445, and held full power until 0015 on July 17, when load was again reduced per LD request.
The load reduction was stopped at 0120 because of problems with the reactor water level controller.
Load was held at 700 MWe from 0140 until 0625.
The unit was increased to full load by 1020.
Full load was held until 1034 on July 18.
At that time, load was reduced slightly to allow control rod with-draway and the unit was restored to full power at 1135.
Full load was held until 1510 on July 19, when it was reduced slightly to help improve condenser backpressure. The backpressure improved, full load was restored at 1720 and held until July 21.
At 0110, a load reduction was begun to allow condenser flow reversal. The load reduction was stopped at LD's request. At 0205 power was held at 710 MWe.
At 0230 the load reduction resumed and from 0330 until 0520 load was held at 600 MWe.
Power was raised slowly, and the unit returned to full load at 1615.
Full load was held until 2145 on July 22 i
i when it was reduced for ECC.
EGC was operated with only brief interruptions from 2203 until 0930 on July 23.
The unit was increased to full load by 1120 and held load until 2220 on July 24, when a power reduction was initiated in order to test electromatic relief valves.
Power reached its minimum of 500 MWe at 2347 and was held during the testing until 0305 on July 25.
Power ascent was begun, but then halted at 0545. At 1040, power was reduced by 50 MWe due to a high reading from a Local Power Range Monitor (LPRM). Power was held at 725 MWe from 1043 until 1800 when a slow power ascent was begun.
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On July 26 control rod withdrawals at 0305 and 0340 raised power to 772 and
' 782 We, respectively.
The power ascent was resumed at 0345 and the unit s
reached full load at 0400.
Full load was held until 2300 when a load reduction was started at the request of the LD.
Load was first reduced to 695 We at 2340 and beginning at 0025 on July 27 was further reduced to 600 W e, which was held from 0110 until 0545.
Power was raised slowly and the unit I
returned to full load at 1402. Full load was held until 0245 on July 28 when power was reduced to 700 We to allow condenser flow reversal.
The i
unit was returned to full load by 0445 and held load until 0115 on July 29.
Power was reduced, and the unit operated in EGC from 0148 until 0930.
The i
unit was returned to full load by 1000. At 1558, a lightning strike caused two breakers in'the 345 KV switchyard to trip, but caused no apparent damage.
At 0130 on July 30, power was reduced and the unit placed in EGC at 0145.
At 0410, EGC auto tripped because of recirc system flow instabilities. The problem was corrected and the unit returned to full load by 0715.
Full load 4
was held until 0045 on July 31.
At that time, power was reduced to help improve condenser backpressure. The condenser backpressure improved and at 0200 a power ascent was begun.
Full load was achieved at 0240 and held for the remainder of the day.
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i III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications 1
i 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 i
i 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, i
0027H/0061Z
1' UNIT 1 MAINTENANCE
SUMMARY
WORK REQUEST NO.:
Q54453 LER NUMBER: '87-001 COMPONENT:
System 6600 - Corrected wiring per print on the 1/2 Diesel Generator, 1/2-6601.
CAUSE OF MALFUNCTION: The failure of the 1/2 Diesel Generator (1/2-6601) to auto-start during Core Spray logic testing was due to a design error in the electrical wiring drawing.
RESULTS & EFFECTS ON SAFE OPERATION: As the failure was in the auto-start function it could still be started manually and the Unit Two Diesel Generator was available as an emergency power supply.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to isolate the ground and replace the fuse in the auto-start circuit. The wiring i
was then corrected and successfully tested. Also, a final field walkdown has been added to the modification program which will detect this type of error.
WORK REQUEST No.: Q54458 LER NUMBER: N/A COMPONENT:
System 0020 - Grouted unsealed penetration.
CAUSE OF MALFUNCTION: The cause for the unsealed penetration could not be determined.
RESULTS & EFFECTS ON SAFE OPERATION: The unsealed penetration was located on the ground floor east side reactor building to outside interlock. A differential pressure was maintained between the outside and reactor building causing all leakage to be into the reactor building.
This would have prevented any potential release of radioactive material from the reactor building.
ACTION TAKEN TO PREVENT REPETITION: The immediate corrective action was to chain and lock the two doors to the reactor building which are part of this interlock.
The penetration was sealed the day after discovery.
_________-____________a
UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST No.:
Q55167 LER NUMBER: N/A CGMPONENT:
System 500 - Installed new limit switch for 2-203-1D MSIV.
CAUSE OF MALFUNCTION: The cause for the failure of the 2-203-1D MSIV Limit Switch was due to moisture from condensation.
RESULTS & EFFECTS ON SAFE OPERATION:
Since all eight MSIV's were operable, the requirements of Technical Specification 3.7/4.7.D were satisfied. Therefore, safety implications were minimal.
ACTION TAKENTO PREVENT REPETITION: The limit switch was replaced like-for-like and to prevent further moisture problems, the wiring connectors threaded connections were sealed with pipe / thread sealant.
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4 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 6.6.8.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1 l
Licensee Event Report Number Date Title of Occurrence 87-014 7-29-87 Control Room Ventilation Isolation Due to Lightning Strike 87-015 7-31-87 Loss of IB Rx Bldg Vent Rad Monitor Refuel Floor Power Supply UNIT 2 There were no Licensee Event Reports for Unit 2 for the month of July.
0027H/0061Z 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 l
)
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'O, DDCKET NO. _
5 0 - 2 b 1 __,,._,,
UNIT ONE O
DATE.07 AUGUST 1987 Q
COMPLETED BYK.d. SCHMIDJ TELEPHONE 109-654-gl4j O
MONTH
_.,,,,_ _,J u ly 1987 Q
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)-
(MWe-Net)
'O-1-
'96 '
7-75 5 2.
._649.8 18, 7 21,._9 _
.O-3.
730.4 19, 711.5 Q.:
4.
_518.9 2 ().
753 $.
5.
597.3 2i.
7 i 9_. E.,,,
O 6.
77J.2 22.
.y 741 6 2
.Q' 7.
479.6 23.
728 7 2
8.
~ 73920 24.
,248.3
- 9. :
753.7 25.
710 5_
2
.O 18-756 1 26- --
52 -7 7.*29.7 27, 634.0 ti.
'O 12.
706.8 20.
758.0
.Q 13.
764.5 29.
774.5_
14.
714.2 30, 773.5
- o 764.4 15, 762.2 31, _ _,
O 16-778 INSTRUCTIONS On this forn, list the overcge daily unit power level in MWe-Net for enth doy in the reporting nonth, Compete to the ed.
ntorest whole negawatt.
These figures will be used to plot a graph for each reporting nonth. Note that when noxinun dependable capacity is used for the net electrical rating of the unit,there may be occasions when the daily overage power level excetas the
'n 100% line (or the restricted power level line).In such cases,the overage dolly vnit power output sheet should be U
footnoted to explain the apparent anonaly O
O-
n-V.
APPENDIX B Q
AVERACE DAILY UNIT POWER LEVEL l
.Q; DOCKET NO..
50-265 U N I T,, _..
_,TJ 0,,
'O D ATE 07JQGUST 147,87 l
-O C ""'ETE BYK, A. sc!itLI.D.I.
l T ELEP HONE 3 0 9_-654-22_4.i_
..O 1
MONTH Julv 1987 i
Q-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) i 1
Q i.
697.1 17, 720 3 1
2.
699.2 i8.
776.,8 0
3.
667.0_
19.
756.fi Q
4.
661.4 20.
76.5.4 5~
624.3 21.
716.,,5._
O-6.
762.1 22.
7.,4L.0 _,_,_,.
Q.
7.
756.0 23.
737.5 8
768.3
- 24. _
75!6 2._.,
9.
742.3 25, 652 4 238 3 26-O 1
745 D ii.
754c2 27.
6 9, 2,.,3
- o; 12.
7g6.4 28.
7 6 5,. i_
O 13-727 6 29-729 0 14.
7,10.i 30.
751.]
O i5.
726.3 3i.
7 4 B.. 0. _ _
O' 16-724<2 INSTRUCTIONS On this forn, list the overage dolly unit power level in MWe-Net for each day in the reporting month Compute to the O-nearest whole negowatt.
These figures will be used to plot a graph for each reporting nonth. Nate that when noxinen dependable copocity is used for the net elettrical rating of the pnit,there noy be occasions when the daily overage power level exceeds the 100% line (or the restricted power level hne).In such cases,the overage daily unit power ostput sheet should be O
feetnoted to enplain the apparent anonolv O
O
Q OPERATING DATA REPORT DOCKET N0'._
- 51,R_54
.es
>V
- UNIT, ONE O
DATE0E AUGUST 1987 COMPLETED BYK,A. SCliMJRT TELEPHONE 309-654-224j
!O.
PERATING STATUS 1.
Reporting periodigdOO 0 7,,,3,jlZ, Gr o s s h o u r s in r e p o r t i n g p e r i o d i _7_4_4_,__,,,
O
~2.-Currently authorized power level (MWt) 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 O-
- 3. Power 1cvel to which restricted (if any)(MWe-Net): NA O ""aSa"5 for
"*5'rl'*1a" (if ""v)'
1his Month Yr,to Date CumulotIve O
5.
Number of hours reactor was critical
_744,0 5024,,A _,,_107837L1 O'
6.
Reuctor reserve shutdown hours 0.0
,,,,_0. 0 3421.<?
7.
Hours generator on line 744 0 5008.6 104325.1 2
O 8.
Unit reserve shutdown hours.
0.0 0.0 909.2 Q
9.
Gross thermal energy generated (MWH) 17j!28,JJ.
_ijf 69185
,_R29127003
- 10. Gross electrical energy generated (MWH) 55 Jig],3,_
3894453
_ 71647837 O
- 11. Het electrical energy generated (MWH) 5R5875 3Z23323
_671705R5, 12- """ r 5"""I'*
f"
r 1"
98 8 8
8 O
- 13. Reactor avn11ob111ty factor 100.0
,,, 2 8. 8
,,,,, 8 3. 4 0
- 14. Unit service factor 100.0 98.5 78.2
.Q
- 15. Unit availability factor
,10 0. Q, 98x5 7 8,,,2.,
- 16. Unit capacity factor (Using MDC) 91.9 95,,,3R.
65.5 O
- 17. Unit capacity factor (Us.ing Des.MWe) 8'?. 6 92.8 63.8 O.
- 18. unit forced outage rate 0.0
.5 5.s q
- 19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of each)i O
- 20. If shutdown at end of report perjod,estincted date of startup
'O
$UN0ff1CIAL COMPANY NUMBERS ARE USED IN THIS REPORT O
(;
}
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lQ OPERATING DATA. REPORT DOCKET NO.
50-RA5
'O
- UNIT, TWO O'-
DATE07 AU,. GUST 1987 COMPLETED DYB_,.A, SCHMIJ)T
-'O -
TELEP HONE 3,,0 7,-h54-224 %
l O
PERATING STATUS 0000 070187
- 1. Rep or t ing p er i od s p40 0.92.3,,187 Gross hours in reporting periodi.,714 0
~2.
Currently authorized power level (MWt): 2511 Max. Depend capacity
.O.
769* Design electrical roting (MWe-Net): "709
)
(MWe-Net)1 3.
Power level to which restricted (if any)(MWe-Net): NA LO 4.
Reasons for restriction (if any):
lhls Month Yr.to Date Cumulative.
O 5'.
Number of hours reactor was criticul 744',0 4459.7-,_1Q1125,4 0
6.
Reactor reserve shutdown hours
_{ld),
LO,,
2985,0
.7.
Hours generator on line 744jl.,
4406.7 99115 8
'0 1
O.
Unit reserve shutdown hours.
0,0 0.0 70 gd,
.Q-
-- 9. Gross thermal energy generated (MWil) i?8ASA,1 10476574
_R11816273:
- 10. Gross electrical energy generated (MWH)
_,,_,,,,,,,5 6,h ;3 7 9 33WL3.,,3_.2,
,,,_ 6 7 7 3 9 6 2 4 1
O ii. Net electrical energy generated (MWH) 5,,,4.jlf.R.9,_
_,,,,,. 3 2 3,2 6 6 1.
_.63829698-i Reactor service factor 100.0 87,'l 77,1 O
- 13. Peactor ovallobility factor iA 0,0 87,7 72,,td t
O-
- 14. Unit service factor 100.0 86.6 74.0
'O
- 15. Un.t t avoitability factor 100,0 86.6 75.3
.16. Unit capacity factor (Using MDC) 9 4, h.,
82.6 62.6 0
- 17. Unit capacity factor (Using Des.MWe)
,12,2
_ 80.5 61,0 Q
- 18. Unit forced outage rate
_,,,,,0 1 3.6 7,5.
t
- 19. Shutdowns scheduled over next 6 monthy (Type, Dote,and Duration of each):
l
- 20. If shutdown at end of report period, estimated dote of startup
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l VI.
UNIOUE 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:
Two Date: July 25, 1987 Valves 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 - 1002 psig Description of Events:
Surveillance Technical Specification 4.5.D.l.b B.
Control Rod Drive Scram Timing Data for Units One and Two There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
0027H/0061Z
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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.
0027H/0061Z
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 l
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 (MAPHLCR 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 design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
FIRST RELOAD OF GENERAL ELECTRIC, CE8E FUEL WITH 4 WATER-RODS AND LHGR LIMIT OF 14.4 KW/FT.
A 7
The number of fuel assemblies.
i a.
Number of assemblies in core:
724 b.
Number of assemblies in spent fuel pool:
1573 8.
The present Ilcensed 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 4PPROVED APR 2 0'1978 Q.C.O.S.R.
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978 INFORMATION REQUEST 1.
Unit:
02 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 j
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.
I.icensed storage capacity for spent fuel:
3897 f
l 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 resent IIcensed capacity: 2008 APPROVED 1 APR 2 01978 l
Q.C.O.S.R.
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j VIII.
GLOSSARY l
The following abbreviat is which may have been used in the Monthly Report, are defined below:
I
-l ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI American National Standards Institute Average Power Range Monitor
'APRM ATHS Anticipated Transient Without Scram BWR Boiling 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 HRSS 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 National Institute for Occupational Safety and Health NIOSM PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH Reactor Building Closed Cooling Hater System RBM Rod Block Monitor i
Reactor Core Isolation Cooling System RCIC Residual Heat Removal System RHRS RPS Reactor Protection System RWM 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 Builling Closed Cooling Water System TIP Traversing Incore Probe TSC Technical Support Center 0027H/00612
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O Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North m, ; y pm1 gra Cordova, Illinois 61242 qg.y rqg; Telephone 309/654-2241
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RAR-87-35 rnt/ g August 4, 1987 U.S. Nuclear Regulatory Commission Atta: Document Control Desk Office of Nuclear Reactor Regulation Hashington, D. C.
20555 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 July, 1987.
Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION R. A. Robey Services Superintendent vk Enclosure
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0027H/0061Z AUG 171987
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