ML20217C485

Monthly Operating Repts for June 1991 for Quad Cities Nuclear Station Units 1 & 2

ML20217C485
Person / Time
Site:	Quad Cities
Issue date:	06/30/1991
From:	Robey R, Short C COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RAR-91-28, NUDOCS 9107150388
Download: ML20217C485 (26)

Text

{{#Wiki_filter:_ - _ - _ _ _ _ _ _ _ _ - j RAR-91-28 July 2, 1991 i U. S. Nuclear Regulatory Commission ATTH: Document Control Desk Hashington, D.C. 20555 SUDJECT: Quad Cities Nuclear Station Units 1 and 2 Monthly Performance Report RRC DocLe.t_.lios. 50-251_anL5D:265 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 June 1991.. Respectfully, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION /?.h. R. A. Robey Technical Superintendent. RAR/CALS/dak Enclosure cc: A. B. Davis, Regional Administrator l T. Taylor, Senior Resident Inspector l IL L L -kbbE0h$b$8sg [8dY TS-14 !p

+ QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCL REPORT JUNE 1991 4 COMMONHEALTH EDISON COMPANY AND I0HA-ILLIN0IS GAS & ELECTRIC COMPANY NP,C DOCKET NOS. 50-254 AN9 50-265 LICENSE HOS. DPR-29 AND DPR-30 TS 14

TABLE Of CONTENTS 1. Introduction 11. Summary of Operating Experience A. Unit One B. Unit Two III. Plant or Procedure Changes, Tests, Experiments, and Safety Relcted Maintenance A. Amendments to facility License or Technical Specifications B. Facility or Pro edure 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 TS 14

t I. IRIROWCUOli Quad-Cities Nuclear Power Station is conposed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 MHe Net, located in Cordova, Illinois. The Station is jointly owned by Lommonwealth 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 prima'y construction contractor was United Engineers & Constructors. The Missi:sippi 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 Cynthia A. Losek-Short and Debra Kelley, telephone number 309-654-2241, extensions 2938 and 2240. IS 14

I I1. SWLMRLQ 10PERATING_EXEERLEllCI A. UnLLQne. L Unit One remained :hutdown from the previous month due to main k transformer replacement. The reactor became critical at 1009 hours on the 24th and the unit generator went on-line at 0115 hours on the 26t' respectively. The unit remained at full power for the rest of the month *ith the exception of load drops on the 28th, 29th, and 30th, per ) Chicago load Cispatch requests. F B. UniLTyo Unit Two began the month of June operating in Economic Genpratic-Control (EGC). The unit was taken out of EGC on the 3rd and 16i 'or Turbine Stop Valve Testing and "C" Reactor Feed Pump Troub'9 She> ting. The unit was also taken ott of EGC on 2nd, 4th, 5th, 13th, 17th, 18th, 19th, 20th, i3rd, 24th, and 25th, per Chicago Load Disp \\tch requests. P,J,' W TS 14

4 4 III. ELANLOLER0CEDURE_CHANGESJISIS EXPIRIMENIS. - AND_SAfflLRELAIIDJAIN1ENANCE A. AmendmeniLt9 EAC111tylkenie_Dr_lechtilcAl_SptcifitfLt.lotu There were no Amendments to the Technical Specifications for the reporting period. An Amendment to the Facility License was that the Offsite Dose Calculation Manual (ODCM) was changed and is reoortable to the Nuclear Regulatory Col.. mission (NRC) in sccordance with station Technical Specifications. This document contains the models for the public dose assessment from gaseous effluents, liquid discharges, and direct radiation. The NRC. per Generic letter 89-01, requested that the information found in the station Radiological Effluent Technical Specifications to be transferred tt the ODCM and Process Control Program (PCP), as applicable. The major. changes-to the ODCM complied with this request. The remaining minor changes were editorial, outstanding from the previous distribution, Revision 0, dated March, 1989. This revision does not reduce the accuracy and reliability of dose calculations or set point determination methodology. Any changes to the ODCM computer program required by this document are in the-process of being implemented now and should be fully available by July 8, 1991. MAJOR CHANGES The generic manusl both introduces and references the Radiological -Effluent Technical Specifications contained in the site annexes, in i Chapter 12,-now titled the " Radiological Effluent Technical Standards ( RETS ) . " Operability Requirements" in the RETS are equivalent to Limiting Conditions for Operations in the station Technical Specifications. The generic manual is common for six sites, therefore the reporting requirement for " Changes to the ODCM" deviates slightly from the recommendation given in the Generic Lotter. An effective date for generic manual implementation is to specified in the station Onsite Review. As in the past, the official transmittal to the NRC is made' through_the stations' Monthly Operating Report within 90 days of the effective date. .TS 14 ae:

4 MINOR Ct gre The remalring minor changes are editorial. Below is the' abbreviated - version of an itemired list of changes available in Emergency Preparedness _ir at the Corporate Office: - Revised titles for toe Corporate Office Department and Positions Prepared a stand alone section for the EPA's Clean Air Act (if and when enacted) Deleted references to Commonwealth Edison (or CECO) Added text regarding the H11mington Public Hater Snoply nearby Braidwood Station Corrected parameter symbols, values and units. D. Ear 1))iy or Procedurf_ Change 1JaguitingJRCJpproyal There were no facility or Procedure changes requiring NRC approval for the_reportir, oefied. C. IeitLAndlxnerimeat13eauf r_inglRClparoyAl There were no Tests or Experiments requiring NRC approval for the reporting period. D. Corrective Malatfnance of_ SafelylelAtedlquipment 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 Halfunctions,

Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

TS 14

~ ~ ~ UNIT 1 MAINTENANCE

SUMMARY

~ HORK REOUSSI SYSTEM EID DESCRIPTION HORK PERFORMED l Q93249 6601 Investigate and repair 1/2 D.G. As Found: Tested thermostats and two did not open which tripped high engine to the full 3/4" position. They all stayed closed temperature. at 160 degrees and the thermostat seals were brittle a..d cracked.As Left: Installed and tested 9 new thermostats'and they were found to work properly. Cleaned all gasket surfaces and holes for thermostats, also ran brushes thru all the tubes. Q80309 7504 Investigat? and repair air in kes>ved and replaced gasket material arouno access leakage around door when Standby doors, as well as, adjusted door latches. Gas Treatment is run. Q92973 0901 LPRM found with high light on and As Found: Found all alarms and alarms indications no alarm on 901-5 parel. tn be reset. As left: Notified SCRE of' jumpering Investigate this occurrence since

a. arm points on the 901-34 and 901-37 panel. NSO:

several LPRMS have done this in got alarm and cleared it and repeated with same the past. results. No problem was found. Functionally tested high alarm for LPRM.48-49A verified hi-light on 901-37 panel came up and alarm D7 on 901-5 panel came up and alarm light on full core display. Reset alarms and put everything back to normal. TS 15

'JNIT 2 MAINTENANCE

SUMMARY

HORK RE00EST SYSTEM .EID DESCRIPTION ~ WORK PERFORMED Q93330 3941 Investigate adnormal readings As Found: Indicator was reading 1200 GPM Flow. from U2'DG CHP Flow Meter When valve out and equalized the reading dropped 2-3941-26. to O GPH. As Left: Backfilled sensing lines and checked calibration which was in tolerance. Performed final calibration and returned instrument to service. Q93248 Investigate 1/2 DG tripped on As Found: Temperature switches 1/2-6641-ETS and high temperature suspect a bad 1/2-6641-TC would not calibrate to whithin temperature switch. tolerance. As Left: Installed and calibrated new temperature switches for 1/2-6641-ETS and 1/2-6651-TC. Also, functionaly tasted the 1/2-6641-ETS and 1/2-6642-TV for local panel annunciator alarms. TS 15

= - _ IV. LICENSELEVERLREEORIS The following is a tabular summary of all licensee event re" orts 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.C,1 and 6.6.B,2 of'the Technical Specifications. UN11_1 Licensee Event ReporLNumber DAte 1ttle_oLDccurr.ence i. I 91-010* 04-27-91 Plant Shutdown due to RCIC INOP Ref. T.S L 3.5.E.4. 91-010 06-14-91 1/2 Scram on loss of A 24/48 VDC (near Miss). 91-013 05-14-91 Control Room Smoke Detectors are below the minimum. UNII_2 There were no licensec event reports for Units 2 for this reporting period,

• 010 Report for the Month of April has been downgraded.

l l TS 14 l

. ~,... -..-.. ~. .~ .i V. DATA _IABU.'AIIQ115 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 l 1 4 h l. i: [ i TS 14--

APPENDIX B AVERAC,E DAILY UNIT POWER LEVEL Docket No. 50 254 Unit one Date July 1, 1991 Conpleted By Cynthia Short Telephone 309 654 2241 i MONTH 6,P!R,1( DAY AVERACE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Net) (MWe Net) l 1 7 17 7 l 2 8 18 -7 3 -8 19 7 4 7 20 -7 l 5 7 21 7 6 -7 22 7 7 7 23 7 8 7 24 7 9 7 25 7 10 -7 26 564 11 -7 27 783 12 7 28 699 13 7 29 727 14 -7 30 759 15 -7 31 16 -7 INSTRUCTIONS Dn this form, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maxisun dependable capacity is used for the net electrical rating of.the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line), in such cases, the average daily unit power output sheet should be footnoted to explain the apparent anomaly. 1. I-L.

4 4 APPENDIX S AVERAGE DALLY UN11 POWER LEVEL Docket No. 50 265 tini t two Date July 1, 1991 Conpleted By Cynthia Short Telephone 309 654-2241 MONTH AM DAY AVERAct DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Net) (MWe Net) 1 722 17 6 75 2 640 18 702 3 688 19 707 4 678 20 721 5 702 21 76) 6 762 22 707 7 783 23 663 8 717 24 688 9 747 25 691 10 737 26 738 11 74e 27 727 12 728 28 778 13 713 29 745 14 759 30 707 15 739 31 16 525 INSTRUCilONS On this form, list the average daily unit pnwer level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt. These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions when the daily average power level exceeds the 100% line (or the restricted power level line). In such cases, the av. 3 1 ally unit power output sheet should be footnoted to explain the apparent anomaly. D 4

Wl DTR/T17&V?u /dd hyt* APPtWOIR 8 AVERAGE DAILY UNIT POWER LEVEL Dorket No. 50 254 Unit One Date June 3, 1991 Conpleted By Cynthia Short telephone 309 654 2241 MONTH.M DAY AVERACE DAILY POWER LEVEL DAY AvtRAGE DA1LY POWER LEVEL (MWe Net) ( we Net) 1 146 17 792 2 292 18 794 3 409 19 455 i; 4 666 20 736 l-5 670 21 676 6 673 22 3 7 749 23 7 l 8 800 24 7 9 798 25 7 10 798 26 7 11 798 27 7 12 796 28 -7 13 796 29 7 14 796 30 7 15 794 31 7 16 793 INSTRUCTIONS On this form, List the average daily unit power level in MWe Net for each day in the reporting month, Conpute to the nearest whole megawatt. These figures will be used to plot a grepn for each reporting month. Note that when monian dependable capacity is used for the ne' electrical rating of the unit, there may be occasions when the dally average power Levet exceeds the 100% line (or the rostricted power level (ine). In such cases, the average daily l_ unit power output sheet should be footnoted to explain the appcrent anomaty. l l l l

Abit : dkeren a meOCwE 4 .s i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-265 Unit Two Date June 3, 1991 Coupleted By Cynthia Short Telephone 309 654-2241 MONTH 6PRl( DAY AvERAC,k DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe Net) (MWe Net) e 1 752 17 745 2 744 18 730 3 732 19 719 L 4 707 20 764 5 648 21 770 6 754 22 .780 7 740 23 773 i 8 738 24 766 j 9 754 - 25 731-10 754 26 730 11 732 27 688 12 735 28 760 l 13 774 29 763 14 772 30 750 L 15 771 31 768 ) i 16 764 1 INSTRUCTIONS On this form, list the average daily unit power level in MWe-Net for each day in the reporting month. l-Coqmte to the nearest whole megawatt. -These figures will be used to plot a graph for each reporting month. Note that when maximum dependable capacity is used for the net electrical rating of the unit, there may be occasions t hen the daily everage t power level exceefs the 100% line (or the restricted power sevel line). In such cases, the average daily unit power output sheet should be footnoted to explain the apparent ancmaly. +%w i &e +,m-- 7-

APPENDIX C OPERATING DATA REPORT DOCKET NO _50-254 UNIT One DATE Julv 9 1991 COMPl.ETE D ilY Cynthia Losek-Short TEl.EPHONg 109-654 7/41 OPSRATlhGSTATUS 0000 060191 2400 063191 720

t. Pl8 PORTING PERICO:

. Gross HOURE IN REPORTINC PERICO:

2. CURRENTLY AUTHOR 12EO POWER LEVEL (gh 2 % 11 gAx. OEPgNO. CAPACITY temeratosi. 769 DESIGN ELECTR! CAL RATING (WWtNe@

3. POW 8R LEVEL TO WHCH RESTRICTED IIP ANYI (WWu.Ns*

l

4. REASONS POR RESTRICTION llP ANYll l

THIEMONTH YR TO Daft Cue #ULAfivt 157.8 779.0 13??60.9

5. NUM64R OP HOUR 8 REACTOR WAo CntficAL O.0 0.0 3741,a

8. REACTOR RESERVE SMUTOOWN HOURE...................

I18.8 652.3 1780?I,6

7. HOUR $ GENER ATOR ON LING.........,,,.....,,....

0.0 0.0 909.2

8. UNIT RESERVE SHUT 00WN HOUR $......................

9. GROSS THEAMAL ENERGY OENER ATED (MWH1.,........... 277555.0 1390411.0 274121851.0 87684.0 444402.0 88838256.0 M. OR088 ELECTRICAL ENEROY GENER ATED (WWH1...........

80110.0_ ~ 401844.0 83576085 0-

11. NET ELECTRICAL ENERGY GENEst ATED (MWH1 21.9 17.9 78.5

12. ' EACTOR SE R VIC E P ACTOR...........................

21.9 17.9 RO 5_

13. R E ACTOR AV AILABILITY P ACTOR.......................

16.5 15.0 76.0

14. U NI T S E R V iC E P ACT OR.............................

16.5 15.0 76.5 1$. UNIT AVAILABILITY P ACTOR.................... 10*5 I? 0 ~64,5

16. UNIT CAPACITY PACTOR lusinEMOC1.....................

14.I i1.7 6?.9 I

17. UNIT CAPACITY P ACTOR (UwnE Osme MWel.................

0.0 0.0 5.7

15. UNIT 70RCE D 0bTA08 MATE..........................

19. SHUTDOWNS SCHEDULEO OVER NEXT 8 MONTHS (TYPE. DATE. AND OURAflON OF EACMh

~20. IP SHUT DOWN AT END 0F REPORT PERIOD. ESTIMATED DATE OP STARTUP;

21. UNIT 3 IN TEST 57ATUS (PRIOR TO COMMERCI AL OPERATIONI:

FORECAST ACHIEVEO INITI AL CRITICALITY INITIAL ELECTRtCITY COMMERCIAL OPERAT1088 I l.11M m 1

.c 1 APPENOlX C OPERATING DATA REPORT 00CKET NO. 50-265 UNIT Two -DATE J"IY'9 199I COMPLETED BY Cynthia Losek-Short TELEPW)Ng _109-654-2241 OftAATING STATUS 0000 060191 2400 063091 720

1. RSPORT1880 PSme00:

GR0es Mouns IN REPORTINO PgRe00: 2511~ MAN. OSPENO. CAPACITY usuu>40sel. 769-

3. CURR8NTLY AUTM08tl280 LOWER LEVEL g):

08840N SLSCTRICAL RAT 1000 lesut>80so: 1 P0 HOR LEV 8L 70 UIMcCM RGSTRICTCO IIP ANY) lessupeesel:

4. RSA80se POR ResTReCTION llP A'tYl THet as0e m e YR TO OAft CutsWLATIVs i

720.0 3887.0 129576._2 S. leusseWI 0F MOURS REACTOR UUA8 CRITICAL............... 0.0 -O.0 2985.8-

8. htACToft RSSSRVE SMUTOCUW6 MOURS........

720.0 3856.5-126143.5

f. Moume GeNsR ATOR ON UNS..................,,......

0.0 0.0' 702.9

8. UMT R888RV8 SMUT 00spe HOURS......................

S. GROSS TMentAAL ENSROY OtfeSRATED lasyste............. 164 7852. 0 8994100.0 272225421.0

10. GROW ELOCTRICAL ENERGY GENERATED ltegpHI............ $31554.0. 2918681.0 87379888'.0

11. Ntf ELECTR4CALINERGY 08NERAT80 (WevMI............. 513892. 0 2824038.0 82654590.0 100.0 89.5 77.6

13. ' TACT 0fl SERV 8CS P ACTOR...........................

-100.0 89-5 79,_4

13. REACTOR AV AILAtiLITY P ACTOR..............,........

~ 100.0 88.8 75.6 to. UMT SSRVICE P ACTOR.............................. 100.0 88.8 76.0 .15. UMT AVAILAtiLITY P ACTOR.......................... 92.8 84.5 64.4

14. UMT CAPACITY P ACToft lusing 880C5 -.....................

90.5 82j ~62.8 17.' U88t? CAPACITY PACTOR luong Oany assasi '................. O.0 .I1;0 7.9

18. UMT P0ftC40 OUTA08 Raft..........................

l.

19. SMUTDoupe8 SCH00ULEO OvER NEXT 4 MONTMS ITYPE. OATE. ANO OURATION Ce gAce0:

i I i

20. IP StTT 004WN AT ENO OF REPOR r PamiOO. ESTIMAT50 Ot.TE OP t/ARTUP:

i

21. UMTS IN TEST STATUS (Pftlost 70 COMMERCIAL OPERATIOM):

PORECAST ACHIEVES IMTIAL CRIT *CALITY IMTIAL GLSCTftlCITY ? C00stesRCIAL OPERAftest L l.164 l

YO*/d.' OM/Cn cas FOR $sMi APPENDIX C OPERAilhG DATA PEPORT Docket No. 50 254 Unit one Date June 3, 1991 Coppleted By Cynthia Losek short Telephone 309-654 2241 OPERAllNG $18.1US 0000 050191 1. Reporting Period 2400 053191 Gross Hours in Report Period: Z44, 2. Currently Authorited Power Level (MWt): gill Max. Depend. Capacity (MWe-Net)? Z{9 Design E*ectrical Rating (MWe Net): ZE9 3. Power Level to Which Restricted (If Any) (MNe Net)1 !!/,A, 4. Reasons For Restriction (if any): THis MON 1H YR TG DATE CUMUL4TIVE 5. Nuter of hurs Reactor Was Critical 505.6 621.2 132103.1 6. Reactor Res4 ave Shutdown Hours 0.0 0.0 3421.9 7. Hours Generator on Line 505.6 533.5 127902.8 8. Unit Reserve Shutdown Hours 0.0 0.0 909.2 9. Gross Thermal Energy Generated (MWh) 1079784.0 1112856.0 273844296.0

10. Gross Electrical Energy Geneisted (MWh) 353533.0 356718.0 88750572.0

11. Net Electrical Energy Generated (MWh) 340d ?.0 3215?4.0 83495775.0

12. Reactor Service Factor 68.0

) ?.1 78.8

13. Reactor Availability Factor 68.0 17.1 80.8

14. Unit Service factor 68.0 14.7 76.3

15. Unit Availability Factor 68.0 14.7 76.8

16. Unit Capacity Facter (Using MDC) 59.5 11.5 64.7

17. Unit Capacity Factor (using Design MWe) 58.0 11.2 63.1

18. Unit Forced Outage Rate 0.0 0.0 5.3

19. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

20. If Shut Down at End of Report Period, Estimated Date of Startup:

21. Units in Test Status (Prior to Comercial Operation):

iorecast Achieved initial Criticality Initial Electricity Comercial Operation t

6E bRJ*fCY/C MS SUA

• A l

APPENDIX C OPERATING DATA REPORT Docket No. 50+265 Unit Two Date June 3, 1991 Conpleted By Cynthia Losek short Telephone 309 654 2241 OPERATING STATUS 0000 050191 1. Reporting Period 2400 053191 Gross Hours in Report Perloo: Z44. 2. Currently Authorized Power Level (MWt): ullMax. Depend. Capacity (HWe%et): 71 9 Design Electrical Rating (MWe-Net): 7,19 3. Power Level to Which Restricted (If Any) (MWe Net): M 4. Reasons For Restriction (If any): l THl$ MONTH YR TO DATE CUMULAT!VE 5. Nud>er of Hours Reactor Was critical 744.0 3167.0 128856.2 6. Reactor Reserve shutdown Hours 0.0 0.0 2985.S 7. Hours Generator on Line 744.0 3136.5 125423.5 8. Unit Reserve shutdown Hours 0.0 0.0 702.9 9. Gross Thermal Energy Generated (MWh) 1748947.0 7346248.0 270577569.0

10. Gross Electrical Energy Generated (MWh) 573640.0 2406206.0 868o/413.0

11. Net Electrical Energy Generated (MWh) 554986.0 2328594.0 82159146.0

12. Reactor Service Facter 100.0 87.4 77.5

13. Reactor Availability Factor 100.0 87.4 79.3

14. Unit, service Factor-100.0 86.5 75.5

15. Unit Availability Factor 100.0 86.5 75.9

16. Unit capacity Factor (Using NDC) 97.0 83.6 64.3~

17. Unit Capacity Factor (Using Design MWe) 94.5 81.4 62.7 i

18. Unit Forced Outage Rate 0.0 13.1 8.0

19. Shutdowns Sched, led Over Next 6 Months (Type, Date, and Duration of Each):

1

20. If Shut Down at End of Report Period, Estimated Date of Startup:

21. Units in Test Status (Prior to Cwmerciel Operation):

Forecast Achieved initial Criticality Initial Electricity consnercial operation

~ APPENDIX'D UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-254 UNIT NAME QUAD CITIES UNIT 1 COMPLETED By CYNTHIA A. LOSEK-SHORT ~ DATE JULY 1 1991 REPORT HONTH JirNE TELEP:10NE 309-654-2241 ac 0 5 a5< gw@ {"@ = O g M LICENSEE e DURATION' EVENT UV o w U NO. DATE (HOURS) REPORT NO. CORRECTIVE ACTIONS /COPMENTS 91-02 91 iOI F 362.2 R 2 UNIT CONTINUED TO BE SHUTDO*JN DUE TO MAIN TRANSFORMER PROBLEM. E s j 1 I h i 1 l t 1 I t I i

l. (final) i

l l 1 H H 3 3 H H H H H H IP C ( C C C C L C C L C T T T T I T T T T T T T A A A A A A A A A A A ? P P P P P P P P P P P O S S S S S S S S S S S H I I I I I I I I I I I S D D D D G D D D D D D D 1 N K 4 D D D D I D D D D D D D E 2 S S 2 T A G A A A T A A A A A A A O N O O O O O O O O O O O O N L I L L L O L L L L L L L L 4 E T H 5 f O S O O O S O O O O O O O 6 f G E G G G G G G G G G C A 0 A T A A A E A A A A A A A 9 C C C C C L C C C C C C C A 0 / I E I I I B I I I I I I I I 3 S H V H H H U H H H H H H H H N C L C C C O C C C C C C C T O A R N I R V R R R T R R R R R R R T T E f E E E E E E E E E C C P E P P P P P P P P P P P A N F Y D I D D D R D D D D D D D B E E B E E E E E E E E E E V T R T T T T T T T T T T D E I S U S S S C S S S S S S S E N T E T E E E E E E E E E E T O C U U U U U U U U U U U E H E Q R Q Q Q R Q Q Q Q Q Q Q L P R E O E E E O E E E E E E E P E R R F R R R F R R R R R R R M L O O E C P P P P P P P P P P P P P O O O C O O O O O O O O O C T R R R R R R R R R R R R. R D D D D D D D D D D D D D D D D D D D D D D D D D D A A A A A A A A A A A A A O O O O O O O O O O O O O L L L L L L L L L L L L L S NO ITCU W@" DE g o" R R E ) DW l O XP E W@" a I N n DD U xgm$ i NN J f EA ( P 1 PS E O AN E N W n ST f NNT O f D O EER T M CVO U IEP N T L E S R R O T P I E co 0 ;< M N R a U 2 -{g

• 5 5

5 5 5 5 5 5 5 5 5 5 5 oO s =og3 H B H H H B H H H H H H H N) OS I R TU 1 3 5 3 9 3 9 8 8 6 5 0 1 2 AO RH 8 6 7 5 3 8 1 5 5 3 8 6 6 T U( 1 I D NU 1 S 9 . g,,, E 9 S S S S S S S S S S S S S w I 1 T 5 I 6 C 1 2 2 3 4 5 3 6 7 8 9 0 3 4 5 E D Y 0 0 0 0 1 1 1 1 1 2 2 2 2 0 A L T 6 6 6 6 6 6 6 6 6 6 6 6 6 5 U U A 0 0 0 0 0 0 0 0 0 0 0 0 0 D 1 1 1 ~ 1 1 1 1 1 1 1 1 1 1 Q J 9 9 9 9 9 9 9 9 9 9 9 9 9 O E N MA T N 8 9 0 1 2 3 4 5 6 7 8 9 0 E O 0 0 1 1 1 1 1 1 1 1 1 1 2 K T E N 1 1 1 1 1 1 1 1 1 1 1 1 1 C I T O N A 9 9 9 9 9 9 9 9 9 9 9 9 9 D U D 4 I 1!

VI. UNIQUEJEEORIINGJEQUIREtMIS The following items are included in this report based on prior commitments to the commission: A. M ain_S t e am.RelteLValv e_Op e ration s There were no Main Steam Relief Valve Operations for the reporting period. B. ControLRQ1.Dr.lte_Sr t am _Li min gla t tf or_UnLt s _0n e _and_1wo There was no Control Rod Drive scram timing data for Units One and Two for the reporting period. TS 14

+ VII. REEUELING_INE0RMATION 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 Informatiofi", dated January 18, 1978, i TS 14

1 m. o QTP 300-532 Revision 2 -QUAD ClTIES G UELING October 1989 -INFORMATION REQUEST 1. Unit: 01 Reload: 11 Cycle: 12 2. Scheduled date for next refueling shutdown: 9-5-92 3. Scheduled date for restart following refueling: 12-5-92 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: NOT AS YET DETERMINED. l 6. Inportant licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods,-s!gnificant changes in fuel design, new operating procedures: NONE AT PRESEhT TIME. l-i l .7. The number of fuel assemblies, a. Number of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 1405 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: _1657 l b. Planned increase-In licensed storage: 0 9. The projected date of i:he last refueling the.t can be discharged to the spent fuel pool assuming the present licensed capacity: 2009 APPROVEO. 1 (final) DCT 3 01989 14/0395t Q.C.O.S.R.

QTP 300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1. Unit:- .Q2 Reload: 10 Cycle: 11 2. Scheduled date for next refueling shutdown: 12-28-91 3. Scheduled date for' restart follo' sing refueling: 3 7-92 4. Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment: NOT AS YET DETERMINED. S. Scheduled date(s) for submitting proposed licensing action and supporting information: NOT AS YET DETEPli1NED. 6.- Important licensing considerations associated-with refueling, ~e.g., new ^ sr different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures: NONE AT PRESENT TIME. J 7. The-number of fuel assemblies, a. Number'of assemblies in core: 724 b. Number of assemblies in spent fuel pool: 2287 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 fsr spent fuel: 3897 b. Planned increase in licensed storage: 0 9. The projected date of the last rer'ieling that can be discharged to the-spent fuel pool assuming the present licensed capacity: 2009 4 APPROVED i 14/0395t O.C.O.S.R.

s ar, - VIII. GLOSSARY The following abbreviations which may have been used in the Monthly Report, are defined oelow: ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring ANSI - Araerican National Standards Institute APRM - Average Power Range Monitor ATHS - AnticipatJd Transient Without St am BHR - Boiling Hater Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emecgency Operations facility GSEP - Generating Stations Emere)?ncy Plan llEPA - High-Efficiency Particuloh filter HPCI - High Pressure Coolant Ir.hetion System HRSS - High Radiation Sampilng S> stem IPCLRT - Integrated Primary Containment Leak Rate Test IRM - Intermediate Range Monitor ISI - Inse " ice Inspection LER - Licei..ee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode of RHRs tPRM - 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 RBCCW - 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 TBCCW - Turbine Building Closed Cooling Water System IIP - Traversing Incore Probe TSC - Technical Support Center TS 14}}