ML20087D382

Monthly Operating Repts for Feb 1984

ML20087D382
Person / Time
Site:	Quad Cities
Issue date:	02/29/1984
From:	Kalivianakis N, Misak A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-80, NUDOCS 8403130382
Download: ML20087D382 (24)

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l QUAD-CITIES NUCLEAR POWER STATION UNITS I AND 2 4

MONTHLY PERFORMANCE REPORT FEBRUARY 1984-COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLINOIS GAS & ELECTi'IC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 LICENSE NOS. DPR-29 AND DPR-30 2

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TABLE OF CONTENTS I. Introduction i

j 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-

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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 4

V. Data Tabulations A. Operating Data Report

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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 t

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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 Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.

II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One Febr uary 1-11 : Unit One began the month operating at full power and continued at this level until 0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> on February 5 when the unit dropped load to 700 MWe for weekly Turbine tests. Following the tests, the unit increased load to full power and maintained that load until February 7 when the unit began experiencing fuel depletion deratings due to end of cycle coastdown.

February 12-26: At 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on February 12, the unit dropped load to 700 MWe for weekly Turbine tests. Following the tests, the unit dropped load to 660 MWe for control rod pattern adjustments.

Following these adjustments, the unit began a normal load increase.

On two other occasions, February 19 and February 26, weekly Turbh~

tests were performed which necessitated load reductions to 700 MWe.

February 27-29: At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br /> on February 28, the unit dropped load to 650 MWe in preparation for an Economic Generation Control (EGC) system test. At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> on February 29, the unit increased load to 740 MWe and maintained this load until 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> when the unit dropped load to 700 MWe in preparation for an EGC system test. -

B. Unit Two February 1-20: Unit Two began the month shutdown for End of Cycle Six Refueling and maintenance. At 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> on February 18, unit startup commenced. At 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, the Reactor was critical, and the unit was on line at 1957 hours0.0227 days <br />0.544 hours <br />0.00324 weeks <br />7.446385e-4 months <br />. At 2033 hours0.0235 days <br />0.565 hours <br />0.00336 weeks <br />7.735565e-4 months <br />, the Turbine was manually tripped due to high Turbine vibration. At 0348 hours0.00403 days <br />0.0967 hours <br />5.753968e-4 weeks <br />1.32414e-4 months <br /> on February 19, the unit was placed on line with a load of 160 MWe, This load was ma'ntained until 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> when the unit was shutdown to repair various valve packing leaks. The unit remained shutdown until 1820 hours0.0211 days <br />0.506 hours <br />0.00301 weeks <br />6.9251e-4 months <br /> on February 20 when the Generator was placed on line with a load of 150 MWe.

February 21-29: At 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> on February 21, the unit began increasing load to 350 MWe by pulling control rods. Load was maintained at 350 MWe due to the 2B Recirculation Pump Motor-Generator Set being out of service for repairs. At 1405 hours0.0163 days <br />0.39 hours <br />0.00232 weeks <br />5.346025e-4 months <br /> on February 23, the unit was placed in Hot Standby due to high Turbine vibration. The unit was placed on line at 0210 hours0.00243 days <br />0.0583 hours <br />3.472222e-4 weeks <br />7.9905e-5 months <br /> on February 25 with a load of 180 MWe. At 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />, the unit began increasing load to 500 MWe. At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, the unit began a nornel shutdown to replace the notor on the 'B' Recirculation Pump Suction Valve. The unit was of f line from 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> on February 25 to 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br /> on February 27 when the Generator was placed on line, and a normal load increase was initiated.

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III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY

, RELATED MAINTENANCE-i A. Amendments to Facility License or Technical Specifications On January 24, 1984, the NRC issued Amendment 80 to License DPR-30. This Amendment established new actuation setpoints for the Target Roc.k Safety Relief Valve and two Electromatic Relief Valves, i t also defined new Minimum Critical Power Ratio limits for steady state operation at ' rated core flow. The Amendment also shows the new Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) versus Planar Average Exposure curve for the new Unit Two core.

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- cr 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 Unit i and Unit 2 during the reporting period. This summary includes the following headings: Work Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Ef fects on Safe Operation,- and Action Taken to Prevent Repetition.

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UNIT OrlE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q31892 1-3999-515A RilR Rust and dirt froze The valve leaked through The valve was dis-Service Water the plunger, but the vault sump pump assembled, cleaned, Vault Sump Dis- maintained the integrity lapped, reassembled, charge Check Valve of the vault. and LLRT'd. An investigation was started concerning the vavle reliability.

-Q31893 1-3999-516A RiiR Rust and dirt froze The valve leaked through The valve was dis-Service Uater the plunger. but the vault sump pump assembled, cleaned, Vault Sump Dis- maintained the integrity lapped, reassembled, charge Check Valve of the vault. and LLRT'd. An investigation was started concerning the valve reliability.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS

.W.R. LER OF ON ACTION TAKEN TO NUM8ER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q25817 83-6,'03L 2-203-2B tiSIV The 'B' channel The ittiv failed to The limit switch Limit Switch 10% closure limit ini tiate a hal f-scram was replaced.

switch failed. during testing. The half-scram was initiated mancally.

- Q27288 2-5401B SJAE ilorizontal position The valve did not The valve internals Suction Valve of valve. close. It was were cleaned. The manually assisted valve has a person closed. stationed near it to assist it, and is always, otherwise, kept closed. The valve has since been replaced.

Q28869' 2-54010 SJAE The valve was The valve failed to The SJAE suction Suction Valve improperly close on an valve has since been installed. isolation signal. It replaced with a is normally kept Butterfly valve.

closed.

Q28972 83-15/03L FCV 2-8802C- The valve internals .

The seat was lapped were worn. The valve leaked and the disc was substantially auring cleaned.

LLRT.

Q29176 83-15/03L CV 2-1301-41 The valve internals The valve leaked The seat was lapped we re worn. s6bstantially during and the hinge pin, LLRT. disc, and all seats

._. and gas'kets were replaced.

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UNIT TU0 MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q30316 Various Mechanical Wear. Various Mechanical The Snubbers that Snubbers Snubbers were failed the functional functionally tested. test were sent to 9481, 7327, 7732, Wyle Laboratories 16565, 16558, 12700, to be overhauled.

and 1488 failed.

Q31102 2-2301-5 had The control and The valve tripped during The cables were control and rnotor motor cable had. logic testing. It was replaced and cables cable replaced. failed due to a not required ope rable in the area and on small steam leak. at the time. The valve Ul were inspected.

would fail open to -

provide llPCI service and the in-line 2-2301-4 valve would provide isolation.

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i IV. LICENSEE EVENT-REPCRTS a

The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two_ occurring during the reporting

,t period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.I. and 6.6.B.2. of the Technical Specifications.

l UNIT ONE i Licensee Event

Report Number Date Title of Occurrence There were no Licensee Event Reports, for Unit One, for the reporting pe riod.

I l UNIT TWO l 84-03/03L 2-11-84 Loss of Rus.28 & 29 j 84-04/03L 2-15-84 Reactor Scram While t Shutdown 2

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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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9 OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184

1. Reporting period 2400 022984 Gross hours in reporting period: 696

2. Currently authorized power lev,, (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical '.nting (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. Number of hours reactor was critical 696.0 1440.0 84995.6

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 696.0 1440.0 81787.9

8. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thermal energy generated (MWH) 1643681 3406884 168513590

10. Gross electrical energy generated (MWH) 545050 1129512 54380128

11. Het electrical energy gencroted(MWH) 517997' 1073371 50679338

12. Reactor service factor 100.0 100.0 82.1

13. Reactor avo11ob111ty factor 100.0 100.0 85.4

14. Unit service factor 100,30 100.0 79.0

15. Unit availobility factor 100.0 100.0 79.9 63.7

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L6. Unit capacity factor (Using MDC) 96.8 96.9 L7. Unit capacity factor (Using Des.MWe) 94.3 94.5 62.1

18. Un it forced outage rate 0.0 0.0 6.2

19. Shutdowns scheduled over next 6 nonths (Typa,Date,and Duration'of each):

20. If shutdown at end of repcrt period, estimated dote of startup __"___________ ^

IThe MDC ney be lower then 769 MWe dering perleds of high onbient temperatore det to the tlwrm1 performece of tra sprey comd. I i

sWOFFICIAL COMPANY NWBERS ARE USED IN THIS REPORT )

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l OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATEFebruarv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 020184

1. Reporting period 2400 022984 Gross hours in reporting period: 696

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (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. Number of hours rinctor was critical 245.5 245.5 78163.0

6. Reactor reserve shutdown hours 9.0 0.0 2985.8

7. Hours generator on line 160.3 160.3 75370.1

8. Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross thernal energy generated (MWH) 193783 193783 155575871-

10. Gross electrical energy generated (MWH) 58218 58 rib 49493998

11. Net electrical energy generated (MWH) 53862 53338 46307398

12. Reactor service factor 35.3 17.0 76.2

13. Reactor avullobility factor 35.3 17.0 79 i

14. Unit service factor 23.0 11.1 73.5 LS. Unit avo11ob111ty factor 23.0 ii.i '< 4. 2

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16. . Unit capacity factor (Using MDC) 10.1 4.8 58.8-

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L7. Unit capacity factor (Using Des.HWe) 9.8 4.7 57.3

18. Unit forced outage rate 40.2 40.2' B '.' 7

19. Shutdowns schedule.d over next 6 months (Typc,Date,and Duration of each):1

20. If shutdown at end of teport p er i o d ,e st ina t ed dat e o f. s t ar t up , ___jiA______,.3 SThe 19C ney be lever then 769 mit dering per 7 of high onblent tenperstere det to the thernal perfernance of the grey cenei.

$W10FFICIAl. ColtAIN lluleERS ARE USED H WIS REPORT

i-APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254

' UNIT ONE DATEFehroorv 7 COMPLETED BYAlex Misok TELEPHONE 309-654-2241x194 MONTH February 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWemlet)

(MWe-Net)

17. 749.4

1. 779.8 768,3 18, 746.8 2.

19. 737.9

3. 780.7

20. 744.5 4, 790.8

21. . 737.7

5. 619.0 22, 745,7

6. 870.5 23, 737.5

7. 783.1

24. 708.4

8. 783.0 2F 732.8

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777.7 780.8 26, 713.8 10, 763,6 27. 719.9 li.

672.6 28, 710.0 L2, 784.4 29. 637.8 L3.

L4, 749.0

15. 760.0

16. 762.0 INSTRUCTIONS Cn this forn, list the overage daily unit power level in 1%ie-Net for each day in the reporting nonth Conpete to the nearest Whelt negawatt.

These figures Will be ssed to plat a graph for each reporting conth. Note that when notinin dependable used 1981 line for the (or net the electrical restricted rating power of theline).

level init,In sich cases,the average daily snit power entpst sheet sheeld be festnetad to esplein the apperent onenaly I

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APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATEFebroorv 7 COMPLETED BYAlex Misak TELEPHONE 309-654-2241x194 HONTH Febroorv 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY P014ER LEVEL (MWe-Net) (MWe-Net)

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-4.3 17. -7.8

2. -5.0 18. -11.0

3. -7.2 19, 32.5

' 4. -7.4 20, 17.6

5. -7.0 21, 185.7

6. -7.4 22, 330.0

7. -7.7 23. 147.7

8. -6.3 24. -14.2

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-6.1 25. 155.9 to. -6.0 26. -9.8

11. -6.0 27. 276.2-

12. -6.9 28. 506.9

13. -6.6 _

E9. 617.9

14. -7.1

15. -2.7

16. -11.5 INSTRUCTIONS On this Fern, list the estrege dolly snit i,wer level in IGit ilet for each day in the reporting nenth. Compete to the nearest whole negewett.

These figeres ulll be esed to plot a graph for each reporting nenth. Note that when notinen dependable copecitt is esed for the net electrical reting of the enit there ney le eccesiens when the dellt eserege peer level exceeds the .

iHI line (or the restricted peer level line),.In suh cases,the estrega daily enit power setpet sheet should he festnoted to explain the apperant enently ,

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O M M M M M M M M M M M M M M M M M p ID/5A APPENDIX D QTP 300-S13 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Cities 1 COMPLETED BY Alex Misak DATE March 6, 1984 REPORT HONTil FEBRUARY 1934 TELEPileNE 309-654-2241 w $ g

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$ Q d LICENEEE m@ @

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g"g EVENT $U o u

NO. DATE (Il0URS) REPORT NO. CORRECTIVE ACTIONS / COMMENTS g

84-6 840205 5 0,0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-7 840212 S 0.0 8 5 RB COUROD Reduced load for Control Rod Pattern adjustments 84-8 840215 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-9 840276 5 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine

+ests 84-10 840228 5 0.0 B 5 CB INSTRU Reduced load in preparation for an Economic Generation Control System test 84-11 840229 5 0.0 B 5 C8 INSTRU Reduced Icad in preparation for an Economic Generation Control System test APPROVED i

AUG 1 G 1982 i

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o R R R R M M - M M M M M R R R ID/5A APPENDIX D QTP 300-SI3 UNIT SIIUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities 2 CorfPLETED BY Alex ttisak DATE tiarch 6, 1984 REPORT HONTil FEBRUARY 1984 TELEPil0NE 309-654-2241 w 5 g w" E aS$ go !d w

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w DURATION E EVENT $ o NO. DATE (Il0URS) REPORT NO. CORRECTIVE ACTIONS /C0titlENTS 83-66 830901: s 428.0 C 4 RC FUELXX Unit Two remains shutdown for End of Cycle Six Refueling and ttaintenance 84-1 840218 F 7.2 B 1 HA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-2 840219 F 32.3 B 1 ZZ VALVEX Unit Two shutdown to repair r..f acellaneous valve packing leaks 84-3 840223 F 36.1 B 1 IIA ZZZZZZ Unit Two placed in Hot Standby due to high Turbine vibration 84-4 840225 F 22.0 B 1 CB tiOTORX Unit Two shutdown to replace the motor on the 'B' Recirculation pump suction valve APPROVED AUG 1 G 1982 (final) gjgg3g

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.

Valves No. & Type Plant Description Unit Date Actuated Actuations Co,nditions of Events 2 2-18-84 2-203-38 1 Manual Rx Press Surveillance 2-203-3C 1 Manual 920 T.S. 4.5.D.I.b 2-203-3D 1 Manual (Post Maintenance) 2-203-3E I Manual Replaced Valve 2-203-3A 1 Manual l

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B. CONTROL ROD DRIVE SCRAM TINING DATA FOR UNITS ONE AND TWO The basis for reporting this cata to the Nuclear Regulatory Commission are specified in the surveillance requireraents of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units On3 and Two Control Rod Drive Scram Timing for the reporting period. All scram t.iming was performed with reactor pressure greater than 800 psig.

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL 4

ROD DRIVES, FROM l-1 TO 12-31-04 AVERAGE TIME IN SECONDS AT % Max. Time INSERTED FROM FULLY WITHDRAWN For 90%

insertion DESCRIPTION NUMBER 5 20 50 90 Technical Specification 3.3.C.I &

DATE OF RODS 0.375 0.900 2.00 3.5 7 sec. 3.3.C.2 (Average Scram Insertion Time) 2-21 177 0.31 0.69 1.47 2.59 3 25 unit 2 Hot Scram Timing (J-10) A & B Sequence l

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l VII. REFUELING INFORtfATION 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.

QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING M::rch 1978

(- INFORMATION REQUEST

1. Unit: Q1 Reload: 7 Cycle: 8

2. Scheduled date for next refueling shutdown: 3-11-64 -

3 Scheduled date for restart following refueling: 5-21-84

4. Will refueling or resumption of operation thereafter require a technical specification change or other IIcense amendment: Yes. Preparatory Technical Specification changes will be submitted to include MAPLHGR curve for one of the reload fuel types and extending MAPLHGR curve for BLTA to 45,000 MWD /t.

5. Scheduled date(s) for submitting proposed licansing accion and supporting informa tion:

Tec,nical Specification change will be submitted February 15, 1984.

6. Important licensing considerations associated with refueling, e.g., new or

' different fuel design or suppIIer, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

1) All new fuel assemblies will be GE7B-type (barrier clad, extended exposure design).

2) A generic methodology was used for the analysis of the Control Rod Drop Accide.nt and Rod Withdrawal Error events.

3) The two Zirconium Barrier Lead Test Assemblies will be re-inserted to gather Information on the ef fects of extended exposures.

7 The number of fuel assemblies.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 1730

8. The present Itcensed 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 l

b. Planned increase in IIcensed storage: 0 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 I

[- APPROVED APR 2 01978 Q.C.C.S.R.

QTP 300-S32 R: vision 1 QUAD-CITIES REFUELING March 1978

(- INFORMATION REQUEST

1. Unit: Q2 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-5-83 3 Scheduled date for restart following refueling: 11-12-83

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment:

No, however, a change to the Technical Specifications is being submitted (see below).

5. Scheduled date(s) for submitting proposed licensing action and supporting information:

June 14, 1983 (Scheduled)

6. In.portant licensing considerations associated with refueling, e.g., new or

' ditferent fuel desigit or supplier, unreviewed design or performance analysis methods, significant changas in fuel design, new operating procedures:

1) All new fuel assemblies will be of barrier design; MAPLHGR curves will be relabe.ed to include the barrier designation.

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2) The use mf impr'ved o assumptions in the load reject wi thout bypass analysis '

resulted in e much improved MCPR operating limit. Technical Specifications l are being changed to provide this adc. Ional operating margin.

7 The number of fuel assembites.

a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 412

8. The present licensed spent fuel pool storage capacity and the size of any increase in IIcensed storap capacity that has been requested o,- is planned in number of fuel assemblies:

a. Licensed storage capacity for spent fuel: 3897

b. Planned increase in IIcensed storage: O l 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present IIcensed capacity: 2003 (7 4PPROVED

, APR 2 01978 Q.C.C.S.R.

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, VIII. GLOSSARY 2

3 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 ATWS -

Anticipated Transient Without Scram i BWR -

Boiling Water Reactor  !

CRD -

Control Rod Drive EHC -

Electro-Hydraulic Control System j 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 i IRM -

Intermediate Range Monitor

'ISI -

Inservice Inspection

. LER -

Licensee Event Report

LLRT -

Local Leak Rate Tert LPCI -

Lcw 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 -

M:ximum Fraction Limiting Critical Power Ratio 1- MPC -

Maximum Permissible Concentration

MSIV -

Main Steam Isolation Valve .

l NIOSH -

National Institute for Occupational Safety and Health

! PCI -

Primary Containment Isolation i

PCIONR -

Preconditioning Interim Operating Management Recommendations RBCCW -

Reactor Building Closed Cooling Water System

, RBM - Rod Block Monitor RCIC -

Reactor Core Isolation Cooling System RHRS -

Residual Heat Removal System

, RPS -

Reactor. Protection System RWM -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System SBLC -

Standby Liquid Control SDC -

. Shutdown Cooling Mode of RHRS i SDV. -

' Scram Discharge Volume SRM --

~ Source Range Monitor. . .

TBCCW- -

Turbine Building Closed Cooling Water System-

- TIP -

-Traversing Incore Probe TSC -

Technical Support Center

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Coramonwealth Edison l

C. Quad Citits Nuchar Powar Station

- , 22710 206 Avenue North Cordova. Illinois 61242 Telephone 309/654-2241 NJK-84-80 March 8, 1984 Director, Office of Inspection & Enforcement i

United States Nuclear Regulatcry Commission Washington, D. C. 20555 Attention: Document Control Desk Gentlemen:

Enclosed for your information is the Monthly Performance Report covering the operation of Quad-Cities Nuclear Fower Station, Units One and Two, during the month of February 1984.

Very truly yours, COMMONWEALTH EDISON COMPANY-QUAD-CITIES NUCLEAR POWER STATION N. J. Kalivianakis Station Superintendent bb Enclosure l

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