ML20206A933
| ML20206A933 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/31/1988 |
| From: | Deelsnyder L, Robey R COMMONWEALTH EDISON CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| RAR-88-57, NUDOCS 8811150297 | |
| Download: ML20206A933 (23) | |
Text
n.
e Commonwealth Edison ouad Cities Nuclear Power Station 22710 206 Avenue North Cordova. Il bis 61242 Telephone 309/654 2241 RAR-88-57 October 27, 1988 Director of Nuclear Reactor Regulations U. S. Nuclear Regulatory Commission Mail Station PI-137 Washington, D. C.
20555 Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Power Station, Units One and TW, during the month of October, 1988.
Respectfully, COMMONHEAl.TH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION
/
J R. A. Robey Services St'perintendent RAR/vmk Enclosure
$6
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0027H/0061Z 8811150297 esto31 PDR ADOCK 05000254 R
QUAO-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY FERFORMANCE REPORT OCTOBER, 1988 COMMONHEALTH EDISON COMPANY AND IONA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 1
[@
0027H/0061Z
TABLE OF CONTENTS-I.
Introduction II.
Summary of Operating Experience A.
Unit One B.
Unit Two III.
Plant or Prdcedure 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 0.
Corrective Maintenance of Safety Related Equipment IV, licensee Event Reports V.
Data Tabulations A.
0perating 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 r
0027H/0061Z
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I.
INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Bolling 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 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 complied by Verna Koselka and Lynne Deelsnyder, telephone number 309-654-2241, extensions 2240 and 2185.
4 0027H/0061Z t
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II.
SUMMARY
OF GPERATING EXPERIENCE A.
Unit One Unit One began the month of October operating in Economic Generation Control (EGC). The unit remained in EGC or operated near full power until October 11 with minor interruptions to perform weekly surveillances.
At 0102 hours0.00118 days <br />0.0283 hours <br />1.686508e-4 weeks <br />3.8811e-5 months <br />, the unit was taken out of EGC and a power reduction to 550 MWe was taken at the request of the Chicago Load Dispatcher.
Power levels were held conctant until 0615 when an ascent to full power was taken per the Load Dispatcher.
At 0750, full load was achieved and held until 2130, when a load reduction was taken in pruparation for 1B Main Steam Drain Tank Emergency Drain Valve repairs. On October 12, at 0336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />, 335 MWe was reachea. Power levels were held constant while work was done on the IB MSDT Emergency Drain Valve. At 2100, a power ascent was begun.
On October 13, at 0350, load increase was stopped due to several LFRM's being high. The Load Dispatcher was notified and power levels were held constant until 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> when a load increase was taken to full power with recirculation pumps. On October 14, power levels were adjusted and the unit was placed in ECC.
Unit One remained in ECC until October 17, when EGC was tripped and "B" channel half scram was inserted due to a IB Main Steam Line Radi-ation Monitors failure. The Radiation Monitor was taken out-of-service resulting in a 1/2 Group I Isolation.
Repairs were made and the monitor was declared operable at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />. A load increase was taken to 774 MWe and on October 18, at 0113, the unit was placed in EGC.
At 0755, the unit was taken off of EGC and an ascent to full load was taken. At 0815, 815 MWe was reached and power icvels were held constant through Occober 21, while Traversing In-Core Probe sets (TIP's) were performed. On October 20. TIP's were completed, but a computer failure resulted in full power being maintained until October 21, at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />, when the computer was repaired. At 2255, power levels were adjusted in preparation for ECC operation.
From October 21 to 28 the unit remained in EGC or operated near full power. On October 28, at 1105, the unit was taken out of EGC due to recirculation motor generator set speed oscillations. The unit was ramped to full load and remained at constant power levels thru the remainder of the month, being unavailable for ECC operation due to recirculation pump speed oscillations.
B.
Unit Two Unit Two began the month of October operating in Economic Generation Control (EGC). The unit remained in ECC or operated near full power until October 5.
At 2320, the unit was taken out of EGC due to 2D3 heater emergency drain valve problems. The valve was discovered to be stuck closed, and a power reduction was taken with recirculation pumps.
On October 6 at 1830, the 2D3 heater alarm was cleared and at 1930 the unit was placed in EGC.
At t
I
2350, EGC was tripped due to another alarm received on the 203 heater level after the 2D3 drain valve was closed. The alarm was reset and the unit was placed back in EGC.
On October 7, at 0515, the 2D3 heater alarm was again received. The alarm could not be reset and the extraction valve was kept closed per the Shift Engineer with generator output limited to 95%.
At 0800, power level adjustments were made and at 0835, the unit was placed in EGC.
The unit remained in ECC uith =iner interruptions until October 10, when the 2D3 heater high level alarm was again received and the unit was taken off of ECC.
All heater drain valves were returned to normal and the alarm was cleared.
The unit was placed back in EGC at 0147.
The unit remained in EGC or was operated near full power with normal operational activities until October 15.
At 0042, the unit received an instruuent air low pressure alarm due to an inadvertant isolation of the backup air aupply during the Unit 2 instrument air compressor return-to-service. During the return-to-service of the Unit 2 instrument air compressor and dryer, the dryer bypass valve was shut.
The dryer inlet and outlet valves were immediately opened, but the dryer continually blew down so the dryer inlet and outlet valves were closed. This isolated service air to the Instrument Air System.
At 0047, the reactor was manually scrammed upon receiving indication of at least one control rod drift and at least one control rod scram.
The closed dryer bypass valve was discovered and opened. This immediately restored the pressure in the Instrument Air System and a normal scram recovery was completed. At 0247, the mode switch was placed in Startup and control rods were withdrawn for startup. At 0854, the reactor was made critical and at 1235 the mode switch was placed in RUN. The generator was synchronized to the grid at 1348. An ascent to full power was begun with control rods and recirculation pumps. On October 16, at 2100, full power was achieved. On October 17, at 0010, a power reduction to 750 MWe was taken to perform Reactor Core Isolation Cooling Monthly surveillance and Average Power Range Monitor Balance Test.
All surveillances were completed at 0400 and an ascent to full load was taken. At 0540, 823 MWe was reached. On October 18, at 0100, power '.evel adjustments were made and the unit was placed in F1C.
At 0750, the unit was taken off of EGC and a power increase to fur.oad was taken. At 0815, full power was achieved. At 1705, a 2A2 Flash Tank High Level alarm was received in the conttal room and several heater level control valves tripped within a five-minute period. The recirculation pumps were ran down to 70% and control rod H-8 was inserted to position 00.
The unit's power level was reduced to 700 MWe.
At 1835, the unit was ramped to full power.
On October 19, power levels were adjusted and at 0445 the unit was placed in EGC. At 0910, the unit was taken off of EGC and a power reduction to 650 MWe was taken while the 2B feedwater regulating valve was taken out-of-service for maintenance.
At 1910, the valve was returned to service and load was increased to full power.
Power levels were held constant until October 22 when, at 0245, a half-scram on the "B" channel was taken due to the failure of the #4 turbine control valve while performing control valve fast closure scram surveillance. At 0300, a power reduction was taken with recirculation pumps and control rods to 45% rated steam flow so the "B" channel half-scram could be reset. At 0525, the Turbine Pressure Generator Load Reject Steam valve bypass alarm was received and another power reduction to 330 MWe was taken.
Power levels were held constant while alarms were cleared and surveillances were completed.
On Occober 23,
P an ascent to full power was taken and achieved at 1245. On October 24, power levels were adjusted and at 1733 the unit was placed in EGC. The unit remained in ECC until October 25, when at 1601, the unit was taken off of EGC a,nd a load increase to full power was taken at the request of the Chicago Load Dispatcher. At 2254, power levels were adjusted and th-unit was placed in EGC.
The unit remained in EGC until October 26.
At 0650, an EGC emergency trip was received. At 0700, a load increase to full power was taken.
Power levels were held constant while the weekly turbine / generator tests were completed. At 0304, power levels were adjusted and the unit was placed in EGC.
For the remainder of the month, the unit operated in EGC or was maintained near full power.
=.
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III. PLANT OR PROCEDURE CHANGES. TESTS. EXPERIMENTS. AND SAFETY RELATED MAINTENANCE i
A.
Amendments to Facility License or Technical Specifications j
There were no Amendments to the Facility License or Technical
)
Specifications for the reporting period.
B.
Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.
C.
Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.
D.
Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period. This summary includes the following:
Work Request Numbers, Licensee Event Report Numbers, Components. Cause of lialfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.
0027H/0061Z l
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UNIT 1 MAINTENANCE
SUMMARY
There were no Deviation Reports or License Events Report associated with the Safety Related *4ork Request Log this month.
UNIT 2 MAINTENANCE
SUMMARY
WORK REQUEST NO.:
Q66105 LER NUMBER:
87-019 COMPONENT:
System 1000 - Reset spring can support on line 2-1024B-20".
CAUSE OF MALFUNCTION: Piping configuration verification program identified piping support did not comply with Final Safety Analysis Report.
RESULTS & EFFECTS ON SAFE OPERATION:
Safety effects were minimal. Line was demonstrated operable.
ACTION TAKEN TO PREVENT REPETITION: Modification testing program now requires dimensional verification involving installation of supports.
IV.
LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-ities Units One and Two occurr;ng during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.3.1. and 6.6.B.2. of the Technical Specifications.
UNIT 1 Licensee Event Report Number Date Title of Occurrence 88-015 10-14-88 Missed fire valve surveillance in 1987 UNIT 2 88-026 10-15-88 Manual scram on loss of instrument air 0027H/0061Z
V.
DATA TABULATIONS 1
l 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
- Revisions made to Operating Data Report for Unit Two in September, 1988.
I I
l 0027H/0061Z
APPENOlX C 1
l OPERATING DATA REPORT DCCKET NO.
50-254 f
UNIT One OATE November 4, 1988_
j COMPLETED gy Lvnne Deelsnyder l
309-654-2241 72LEPHONE
+
OPtM ATING STATUS 0000 100188 745 2400 103188 GRoEE HOUR? IN REPORTING PERICO:
- 1. M8POMTIP'O PERICO:
2511 M AX. 0EPE NO. CAPACITY (MWeNed: 769
- 2. CURRENTLY AUTHOR 12EO POWtR LEVEL (WWOr DESIGN ELECTRICAL RATING (MWpNedt _ _ 789 N/A
- 3. POWER LEVELTO WHH",H RESTRICTED (IP ANY)(WWpNed:
- 4. REAEONS POM RESTRICTION (IP ANY):
THIS MONTH YR TO DAT8 CUMULATIV8 745.0 7071.2 116135,5_
- 5. NUMGEM OP HOURE REACTOM WA8 CRITICAL...............
0,0 0,0 3421,9_
- 4. R EACTOR RESERV E SHUTD0ffN HOURS...................
745.0 6817.2 112275.4
- 7. HOURS CE N ER ATO R ON Ll H 8..........................
0.0 0.0 909.2 E. UNif R ES ER V E SHUTOCWN HOURS,......................
- 9. GROSS THERMAL ENERGY QENER ATED (MWH1..............I742587 15227297 23856R054 566517 4913306_
77316ROR
- 10. GRCS$ ELECTRICAL ENERGY GENER ATED (MWHI.............
- 11. NET ELECTRICAL ENERGY GENERATED (MWM),...,...,..,. 541828 4684663_
72587952 100.0 96.6 80.4 12 r E ACTO R SE RVIC E P ACTOM.......................
100.0 96.6 R2 R_
- 13. R E ACTO R AV Alu st LITY P ACTOM.......................
100.0 93.1 77.7
100.0 93.1 7R.4
- 15. U Nif AV AILAllLITY P ACTOM..........................
65.4 94.6 R3.2
- 18. UNIT CAPACITY P ACTOR (VeinE MDC) 92.2 _
81.1 A3.7
- 17. UNIT CAPACITY P ACTOR (Uww Demen MWel..
0.0 4.7 5.4
- 14. U NI T P O RC E D OUT AG E RAT E..........................
- 15. SHUTOOWNS SCHEDULED QVER NEXT E MONTHS ITYP.' OATE. AND OURATION CP E ACMI:
- 20. IP SHUT DOWN AT END OP REPORT PERIOD. EsTIM ATED D ATE OP $*1.*.T','P:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPE R ATIONi; PORECAST ACHIEVED INifl AL CRITICALITY INITI AL ELECTRICITY COMMERCl AL OPERATION l.16 9
a APPENDIX C OPERATING DATA REPORT DOCKET NO.
50-265 UNIT Tw OATE November 4, 1988 COMPLETED BY tvnne Deelsnyder l
TELEPHONg 309-654-2241 OPERATING $7ATUS 0000 100188
- 1. R8m0RTINO PERico:
CR088 HOUR 81N REPORTINO PSRl00: 745 2400 103188 769
- 2. CURRGNTLY AUTHORIZID POWSR LEVEL (Wwd 2 5 I I M AX. QSPS NO. CAPACITY (WWee Mod.
OR880M ELICTRICAL RATING (WWeheOr 789 N/A
.L POWSR L8V8 bio WHICH RS$TRICTIO tlP ANY)(WWpNot):
4 Rf A80N8 POR HESTRICT10N ilf AMV):
THIS WONTH YR TO DATE CVWOLATIVE 736.9 4885.7 199547,g_
S. NUW6tR OP HOURS REACf 0M WA8 CRITICAL............,..
0.0 0.0 2085.8_
- 6. R EACTOR R488RVE SNUTOCWM HOURS...................
732.0 i798.9 106334.2.
F. HOUR 8 GEN ER ATOR ON LIN E...................,,..
0.0 0.0 703.9
- 8. UNIT R ESE RV 8 SHUT 00WN HOUR 8.....................
1658040 10283292 227653859
- 9. GROS $ THERMAL ENERQY GENER ATED (WWN) 540111 3313869 72d71653
- 10. GROSS ELECTRICAL thtRGY GENER ATIO (Mmd...........
517562 3159664 68719689
- 11. NET EtECTRICAL INERGY GENERATED (WWHI......
98.9 66.7 76.3
98.9 66.7 78.4
- 13. R EACTOR AV AILA BILITY P ACTOM......................
98.3 65.6 74,1_
- 14. U Ni f S E R V I C E P A C T O R........................
98.3 65.6 74.6
- 15. UNif AV AILAtlLITY P ACTCA........,.
90.3 56.1 67.2_
- 18. UNIT CAPACITY P ACTOR IVang MOC1 88.0 54.7 60.7
- 17. UNIT CAP ACITY P ACTOR (Usee Osmen umi.................
1.7 12.6 R.6
- 18. UNIT PORCIO OUTACE RAf t.......
- 17. SHUTDOWNS SCH40VLIO QV(R Nt*T 4 MONTHS (TYPt. DAf t. AND 00 RATION OF E ACHh
- 31. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL QPERAT10Nh PCRECAST ACHI(VID INITI AL CRITIC ALIT 4 INITI AL ELICTRICITY COMMERCI AL opt RAT 1088 1.16 9 l
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AMENDIX C OPERATING DATA REPORT J
00CNET NO.
50-265 AMENDMENT UNIT Two 0A73 10-6-88 Lynne Deelsnyder COMPLETED SY l
TELEPHONg 309-654-2241 OP8 MATING STATUS 0000 090188 720
- t. R0 PORTING PERICO 2400 093088 Gross HOURS IN REPORTINO PSRICO, 769
- 2. CURRaNYtY AufwCR12EO POWem LeVILIwwin 2511 M Am. CEPENO. CMACITY (nnes.Mosh OSSIGN ELECTRICAL RATING (hRe>Nett 789 W^
- 3. Powem LtVEL TO WHICN RSSTRICTED llP ANY) thNoth
- 4. REA40NS POM RSSTRICTION (IP ANY):
THIS MONTH YF.70 OAft CUMULAftVE 720.0 4148.8 109805,9
- 5. NVWetM OP HOUR $ REACTom WA8 CRITICAL...............
0.0 0.0 2985.8
- 4. R EACTOM R S$5RV E SHUT 00WN MOURS...................
720.0 4066.9
_105602,2 7.HovR$0ENERATORON UNE..........................
0.0 0.0 702,9
- 8. UNIT R ES E R V E SHUT 00W1 HOVES......................
- 1 32,605
- 8645052 a22601561_9
- 9. GROSS THERMAL ENERQY QENER ATED (WWW) 527857 2,773758 72 3 315 t.2
505170 2642102 6A20? g
- 11. NET ELECTRICAL ENERQY GENERATED (WWH1 100.0 63.1 76.2
- 12. r E ACTO R S E RVIC E P ACTOR..................
63.1 78.3
- 13. R E ACTOR AV AILA tlLITY P ACTOM.....................
100.0 61.9,
73.9
- 14. UNif S E RVIC E P ACf 0R........................
100.0 61.9 74.4
- 15. U Ni f A V A I L A s l LI T Y P ACTOM..........................
9.2 52.3 62.1
- 18. UNIT CM ACITY P ACTOR IUM MOC1...................
88.9 50.9 60.5
- 17. UNIT CAP ACITY P ACTOR ium o s.,i ww.i...............,,
0.0 14.3 g,6
{
- 18. UNIT PO RC 8 0 0UTA4 8 RAf t..................
(
- 19. SMUTDOWh8 SCHEDULIO QVEm NEXT 8 WONTHS ITYPE DATE. AND CURATION OF EACM):
M. IP SMUT DOWN AT END 07 REPCRT PEml00. ESTlWATED DATE CP ITARTUP.
)
l
- 11. Units IN Test status iPRioR To CowutRCi AL ceER AT10Nh PCRECAST ACHIEVED l
INITI AL CRITICAUTY INITI AL ELECtMICITY COMMERCIAL OPERAT10N i
i 1.16 9 t
APPENDIX 3 AVERAGE DAILY UNIT POWER LEvitL DOCKET NO. 50-254 UNIT one DATE November 9,_1988 COMPLETED BY L. neelsnyder TELEPHONE 309-654-2241 go g October, 1988 DAY AVERAGE DAILY. POWER LEVEL DAY AVERAGE DAILY POWE2 LEVEL (MWen%)
(WWeNet) 740 709 gy j
i 699 757 2
gg 701 802 y
gg 755 775 4
g 718 795 g
y 705 734 g
23 696 734 y
23 765 772 24 8
g 713 3
729 729 795 10 26 716 667 27 gg g3 315 3
764 g3 748 3
770 802 766 g
14 745 720 y
16 l
m 3.
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INSTRUCTIONS On this form. lat the antsp datly unit power level m MWeNet for eadi day m the reportuig enooth.Compate to the neWsit whole megawatt.
I Dew figures wdl be used to pivt a rjaph for ca.h teWrung month, Nute aliat when rneumum dependable especily a used toe the net elestncal ratmg ut the unit ibere may be owntons when the daily aterap power levcl exceeds the 1003 lee (ce the rntn.ted powet lesel hnc). In such c.ases, the aver 4p duly utut power output sheet should be foutnoted to e spim the apparent anumaly.
l.l H s
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AMENDlX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT Two DATE Nm'o-Mr 4 1988 COMPLETED BY L. Deelsnyder TELEPHONE 309-654-2241 MONTH _ oc e ber, 1988 DAY AVERAGE DAILY MWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe B et)
(MWeNet) 706 gy 762 9
2 638 it 746 735 3
_694 gg 767 778 4
at 8
21 795 715 696 356 e
g r
694 594 7
g g
24 795 718 714 730 g
3 10 26 800
. 698 gg 27 733 700
_g 7
731 12 g
13
- 716, y
751 739 30 770 14 l
gg y
751 126 635 14 l
l i
INSTRUCTIONS L
f On this form, hat the awraps daily unit power lev.' m MWe Net for each day m the reportmg mocth. Compute to the neusst whole megawatt.
j I
Thew figures wdl be used to plot a stech for cash reporting month Nute that when naamum dependable capacity a f
udd toe the net eteetncalistmg ut tne umt ihere may be ou;ssions when ths daily average powy level exceeds the 1005 hee (or the rntn.ted power Iciel Itac) In such cases, the average duly wut power output sheet should be l
fovvioted to esplana the apparent anomalv.
i I.!M 1s 1
ID/SA APPENDIX D Qi? 300-SI3
~
UNIT SHUTDOWNS AhT) FOhT.R REDUCTIONS ReJision 6 DOCKET NO.
50-254 August 1982 UNIT NAME
_ Quad-Citles Unit One COMPLETED BY L. Deelsnyder I
DATE November 9, 1988 RFPORT MONTH October, 1988 TELEPHONC 309-654-2241 d
w t-et 3
m x
r LICENSEE R
H DURATION gE..
EVENT w
NO.
DATE (HOURS)
%"g REPORT NO.
CORRECTIVE ACTIONS /CCMMENTS 88-24 8810.12 F
0.0 H
5 CC VALVEX Power Reduction Taken to Perform Mainsteam Drain Tank Emergency Drain Valve Repairs APPROVED AUG161982
-I-(final)
Q C. O S H
ID/SA APPENDIX D QTP 300-S13
~
UNIT SHUTD0kNS AND POkT.R REDUCTIONS Revision 6 DOCKET NO.
50-265 August 1982 UNIT NAME Quad-Cities Unit Two COMPLETED BY L. Deelsnyder DATE November 9, 1988 REPORT MONTil October, 1988 TELEPHONE 309-654-2241 x
DoO m"
5 a54 Sm Wm gg u
egg tiCENSEE t;8 28 LURATION M
EVENT 8
s.,
mg U
NO.
DATE (HOURS)
REPORT NO.
CORRECTIVE ACTIONS /COrirRhT3 88-15 881015 F
13.0 G
2 88-026 PA ZZZZZZ Reactor Manually Scrammed on Loss of Instrument Air 88-16 881022 F
0.0 11 5
HA VALVEX Power Reduction Taken Due to Failure of
- 4 Turbine-Control Valve t
i l
I i
i 1
APPROVED AUG161982 (final) j yCUSH i
'h VI. UNIOUE REPORTING REOUIREMENTS The following items are included 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 There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.
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0027H/0061Z
VII.
REFUELING IMFORMATION 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 InformatlM", dated January 18, 1978.
0027H/00612
o
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QTP 300-532 Revision I QUAD-CITIES REFUELING Harch 1978 INFORMATION REQUEST A
1.
Unit:
Q1 Reload:
9 Cycle:
10 2.
Scheduled date for next refueling shutdown:
9-9-89 3
Scheduled date for restart following refueling:
1L-11-89 4.
Will refueling or resumption of operation thereaf ter require a technical specification change or ther license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed IIcensing action and supporting information:
MARCH 10 1989 6.
Important licensing considerations associated with refueling, e.g., new or
' different fuel design or supoller, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7 The number of fuel assemblles, 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 l
Increase In licensed storage capacity that has been requested or is planned in number of f uel assemblies:
a.
Licensed storage capaci y for spent fuel:
3657 t
b.
Planned increase in licensed storage:
0 9
The projected date of the lest refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2008 WPPROVED
, APR E 01978 Q. C. O. S. R.
QTP 300-S32 Revision 1 QUAD-CITIES REFUELING Harch 1978 INFORMATION HiquEST 1.
Unit:
Q2 Keload:
9 Cycle:
10 2.
Scheduled date for next refueling shutdown:
2-3-90 3
Scheduled date for restart following refueling:
5-7-90 4.
Will refueling or resumption of operation thereafter require a technical speciff;ation change or other license amendment:
NOT AS YET DETERMINED.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
SEPTEMBER 2, 1989 6.
leportant IIcensing considerations associated with refueling, e.g., new or
' different fuel design or supplier, unreviewed design or pcrformance analysis methods, significant changes in fuel design, new operating procedures:
NONE AT PRESENT TIME.
7 The number of fuel assemblies, a.
Number of acsemblies in core:
724 b.
Number of assemblies In spent fuel pool:
1475 8.
The present licensed spent fuel pool storagc capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number c' fuel assemblies:
a.
Licensed storage capacity for spent fuel:
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 APPROVED AJ)R 2 01978 C). C:. C). S. R.
t
VIII. GLOSSARY The fellowing abbreviaticns 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 Bolling Water Reactor BWR CR0 Control Rod Drive EHC Electro-Hydraulic Control System Emergency Operations facility EOF Generating Stations Emergency Plan GSEP High-Efficiency Particulate Filter HEPA High Pressure Coolant Injection System HPCI High Radiation Sampling System HRSS Integrated Primary Containment Leak Rate Test IPCLRT IRM Intermediate Range Monitor ISI Intervice Inspection Licensee Event Report LER Local Leak Rate Test LLRT LPCI Low Pressure Coolant Injection Mode of RHRS Local Power Range Monitor t.PRM 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 hational Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations Rea: tor Building Closed Cooling Hater System RBCCH RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System Residual Heat Removal System RHR$
Reactor Protection System RPS RWH Rod North Minimizer SBGTS Standby Gas Treatment System Standby Liquid Control SBLC Shutdown Cooling Mode of RHRS SDC Scram Discharge Volume SDV Source Range Monitor SRM Turbine Building Closed Cooling Hatec System TbCCH Traversing Incore Probe TIP Technical Support Center TSC 0027H/00612