ML20024C752

Monthly Operating Rept for June 1983.W/830701 Ltr

ML20024C752
Person / Time
Site:	Quad Cities
Issue date:	07/05/1983
From:	Kalivianakis N, Misak A COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-83-234, NUDOCS 8307130219
Download: ML20024C752 (21)

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1 QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JUNE 1983 C(HMONWEALTH EDISON COMPANY AND

, IOWA-ILLINOIS CAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 I

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TABLE OF CONTENTS 4

I, Introduction -

i II, Summary of Operating Experience A. Unit One B. Unit Two i

d III, Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance A. Amendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tests and Experiments Requiring NRC Approval D,

Corrective Maintenance of Safety Related Equipment IV. Licensee Event Reports V, Data Tabulations A, Operating Data Report B. Average Daily Unit Power Level -

C, Unit Shutdowns and Power Reductions VI, Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data f

VII, Refueling Information VIII, Glossary h

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• ' I, INTRODUCTION i

Quad-Cities Nuclear Power Station is camposed 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 Boiling Water Reactors. The Architect / Engineer was Sargent & Lundy, Incorporated, and the primary construction contractor was United Engineers & Constructors. The condenser cooling method is a closed cycle spray canal, and the Mississippi River is the condenser cooling water source. The plant is subject

{ to license ntunbers 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 1 and 2 respectively were October 18, 1971, and April 26, 1972.

Commercial generation of power began on February 18, 1973 for Unit 1 and~ March 10, 1973 for Unit 2.

This report was complied by Becky Brown and Alex Misak, telephone number 309-654-2241, extensions 127 and 194.-

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II,

SUMMARY

OF OPERATING EXPERIENCE A. UNIT ONE June 1-19: Unit One began the month derated to 770 MWe as a result of the IDI Feedwater Heater being out of service due to tube leaks.

The unit maintained this load throughout this period except en three occasions when the unit dropped load to 700 MWe for weekly Turbine tests. In addition, on June 19, the unit dropped load additionally to 650 MWe for half an hour as requested by the Load Dispatcher due to low system demand.

June 20-30: The unit continued operating at a load of 770 MWe throughout the remainder of the month except for two occasions. On June 26 the unit dropped load to 700 MWe for weekly Turbine tests.

Also, on June 30, the unit dropped load to 670 MWe for hal f an hour due to a Main Condenser Loop Seal problem.

B. UNIT TWO June 1-19: Unit Two continued to be derated throughout the month due to End of Cycle Fuel Depletion. In addition, the unit dropped load six times during this period as requested by the Load Dispatcher due to low system demand.

June 20-30: The unit dropped load twice during the remainder of the month. The unit dropped load to minimum recirculation flow, approxinetely 310 MWe, on June 25, as requested by the Load Dispatcher.

Then, on June 28, the unit' dropped load to 330 MWe in preparation for a Drywell entry to investigate apparent increased Drywell sump pump discharge. Af ter the investigation was completed, and no unusual leakage was identified, load increased back to full power of 530 MWe.

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l III, PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications for the reporting period.

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 Unit One and Unit Two during the reporting period. This summary includes the following headings: Wo rk Request Numbers, LER Numbers, Components, Cause of Mal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

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UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 024708 #15 IRM The IRM DC amplifier The IRM went down- The amplifier was failed. scale. All other IRMs replaced.

were operable.

Q26658 Off Gas The low calibration The low calibration The R-40 resistor was Radiation potentiometer, R-40, could not be replaced.

Monitor #2 was not operating performed. This properly. did not affect the operability of the monitor.

Q26708 RHR Minimum Pressure switches The 1-1001-18A valve The pressure switches Flow Bypass 1-1001-81A & B were would not open on low were calibrated and a Valve out of calibration; flow, but could have terminal lug replaced.

M0-1-1001- and a wire was found been opened from the 18A loose. Control Room. Thus, HPCI operability was not affected.

Q26807 Recirc MG A current faul t The trip of the main The breaker and motor Vent Fan resul t ing. f rom breaker on Bus 19 starter coil were Breaker IA failure of a motor caused a half scram replaced. The balance starter coil caused due to the loss of one of the plant is being the main breaker at of the RPS MG Sets. investigated for other Bus 19 to trip. problems of coordination Breaker IA on Bus between main and local 19-2 was consequently breakers.

removed to determine why it did not trip.

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7 UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS '

W.R. LER OF ON , ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q17125 Un i t 2 Drywel l Operat ional ampli fier. The monitor went up- The original monitor Radiation Monitor #1 failed. scale. It was replaced was repaired, tested, 2-2419A with a spare, and placed in the panel.

Q23659 2A 125 VDC A letter was received At other plants the The fuses were replaced Battery concerning a problem fuses were continually with 300 amp fuses.

Charger at other plants blowing.

concerning 200 amp fuses installed in 250 amp chargers.

Q26482 APRM #1 The calibration The failed calibration The potent iometer was potentiometer was potentiometer made it replaced, bad, impossible to test the Hi-Hi trip, but the APRM was still operable.

and calibrated.

Q26683 APRM #5 DC amplifier The APRM read 60% Components of the DC failure while all others read amplifier were replaced, 72%. The other two and the APRM was APRMs on the 'B' RPS returned to service, were operable and thus

, would have performed the intended function.

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F' IV, LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for Quad-Cities Units One and Two occurring during the reporting period, pursuant to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1. and 6.6.L.2. of the Technical Specifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 83-24/03L 6-10-83 Torus /Drywell Vacuum Breaker Not Closed 83-25/03L 6-21-83 Bent stem on M0-1-1001-34B Valve UNIT TWO 83-9/01T 6-30-83 Core Spray Pump Pressure Switches " valved-out" 83-10/03L 6-23-83 'A' Standby Gas Treatment Heater Tripped i

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V, DATA TABUIATIONS 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 W

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OPERATING DATA REPORT DOCKET NO. 50-254 UNIT ONE DATE07/05/83 COMPLETED BYAlex Hisak TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 060183

1. Reporting period 2400 063083 Gross hours in reporting period: 720

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons f or restriction (if any):

This Month Yr.to Date Cumulative

5. Number of hours reactor was critical 720.0 4135.6 79306.8

6. Reactor reserve shutdown hours 0.0 0.0 3421.9

7. Hours generator on line 720.0 4095.5 76182.2

8. Unit reserve shutdown hours. 0.0 0.0 909.2

9. Gross thermal energy generated (MWH) 1721052 9841093 156054084

10. Gross electrical energy generated (MWH) 550694 3221230 50343111 ii. Net electrical energy generated (MWH) 518663 3033793 46862701

12. Reactor service factor 100.0 95.2 81.2

13. Reactor avo11ob111ty factor 100.0 95.2 84.7

14. Unit service factor 100.0 94.3 78.0

15. Unit avo11ob111ty factor 100.0 94.3 79.0 16.' Unit copocity factor (Using MDC) 93.7 90.8 62.4

17. Unit capacity factor (Using Des.MWe) 91.3 88.5 60,8

~18. Unit forced outage rote 0.0 1.8- 6.5

.19 . Shutdowns scheduled over next 6 months (Type,Date,ond Duration of each):

11 0 . If shutdown at end of report period, estimated date of startup NA

• Tse IOC not be louer then 769 Ille dering perleds of high emblent tenperatore dee

'to the thernel perfernance of the sprey canal.

t 81RIFFICIAL ColFAlff IMWERS A_RE USED Ill THIS REPORT

OPERATING DATA REPORT DOCKET NO. 50-265 UNIT TWO DATE07/05/83 COMPLETED BYAlex Hisok TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 060183

1. Reporting period 2400 063083 Gross hours in reporting period: 720

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical rating (MWe-Net): 789

3. Power level to which restricted (if any)(MWe-Net): NA

4. Reasons for restriction (if any):

This Month Yr.to Date Cumulative

5. Number of hours reactor was critical 720.0 4079.0 76342.4

6. Reactor reserve shutdown hours 0.0 0.0 2985.8

7. Hours generator on line 720.0 4049.7 73637.8

8. Unit reserve shutdown hours. 0.0 0.0 702.9

9. Gross thermal energy generated (MWH) 1275663 8587158 153178652

10. Gross electrical energy generated (MWH) 395978 2739414 48776949 ii. Het electrical energy generated (MWH) 366991 2562607 45746174

12. Reactor service factor 100.0 93.9 78.9

13. Reactor ovallobility factor 100.0 93.9 82.0

14. Unit service factor 100.0. 93.2 76.i

15. Unit ovallobility factor 100.0 13.2 76.9

16. Unit capacity factor (Using MDC) 66.3 76.7 61.5

17. Unit capacity factor (Using Des.MWe) 64.6 74.8 59.9

18. Unit forced outage rate 0.0 2.5 8.8

19. Shutdowns scheduled over next 6 months (Type,Date,and Duration of eath):

20. If shutdown at end of report period, estimated date of startup __ Jut ________

• The MBC ney be lower then 769 luie during perleds of high enbient temperatere die to tk thenni performmce of the gre, cael. .

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$WWFFICIAL CWFAlff itBEERS ARE USD Ill THIS REP 0pi

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-254 UNIT ONE DATE07/05/83 COMPLETED BYAlex Misak TELEPHONE 309-654-2241x194 MONTH June 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 727.4 17. 715.0

2. 722.4 iO. 731.0

3. 724.8 19. 679.2

4. 719.2 20. 717.6

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725.2 21. 718.7

6. 722.2 22, 722.2

7. 715.0 23, 723.1

8. 730.6 24, 721.0-

9. 638.3 25. 720.2

10. . 805.6 26, 733.5 ii. 720.1 27. 704.1

12. 714.5 28. 715.6 13, 723.5 29. 730.2

14. 723.0 30. 715.5 15, 722.7

16. 729.7 INSTRUCTIONS On this forn, list the everage dolly unit power level in inle-Met for each 409 in the reporting nenth.Cenpete to the nearest dele negemett.

These figures will be used to plot a graph for each reporting nenth. Note that when notinen dependeble copecite is esed for (or 100% line thethenet electrical restricted reting power of the snit,In such cases,the everage dailt enit pour setpet sheet sheeld bethere n level line).

'getnoted to esplein the apparent onenelp

l APPENDIX B l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-265 UNIT TWO DATE07/05/83 COMPLETED BYAlex Hisok TELEPHONE 309-654-2241x194 NONTH June 1983 .

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

1. 539.4 17. 496.8

2. 561.2 10. 519.3

3. 556.7 19, 448.9

4. 556 i 20, 480.4

5. 453.5 21. 502.7

6. 551.0 22. 497.1

7. 544.4 23, 493.8

8. 539.1 24, 489.4

9. 534.9 25, 467.4 10, 535.4 26, 490.6 ii. 529.0 27. 478.8 12, 527.2 28. 467.6 13, 523.8 29. 490.8 14, 520.8 30, 482.4 15, 518.8

16. 494.1 INSTRUCTIONS On this forn, list the estrege delly snit peer level in Mlle-Met for each day in the reporting nenth Compete to the neerest uhelt negemett.

These figeres will be esed to plot a graph for each reperting nenth. Note that uhen notinen dependable cepetite is used for the net electrical rating of the snit there net be occasions when the daily eserage pwer level exceeds the 1991 line (or the restricted power level line),.In such cases,the eseregt daily enit pwer setput sheet should be futnoted te esplein the apperent onenely

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M ID/5A APPENI)IX D QTP 300-S13 UNIT SilUTDOWN3 AND POWER REDUCTIONS Revision 6 DOCKET NO. 050-254 August 1982 UNIT NAME Quad-Citles Unit 1 COMPI.ETED BY Alex Misak DATE July 1, 1983 REPORT HONTil June 1983 TEl.EPil0NE 309-654-2241 N $ g w" 5 29 gm Wm h$w DURATION M hM I.ICENSEE EVENT w@

U o" NO. DATE " REPORT NO. u (ll0URS) CORRECTIVE ACTIONS /CONNENTS ca 83-35 830604 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 83-36 830612 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turoine-tests i

83-37 830618 S 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests 83-38 830626 5 0.0 B 5 HA XXXXXX Reduced load to perform weekly Turbine tests

, 83-39 830630 F 0.0 A 5 HC XXXXXX Reduced load due to high backpressure due

to loop seal problems

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, APPROVED i  :

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ID/5A APPENDIX D QTP 300-S13 UNIT SilUTDOWNS AND POWER REDUCTIONS Revision 6 DOCKET No. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY Alex Misak DATE July 1, 1983 REPORT HONTil June 1983 TELEPil0NE 309-654-2241 N $ g w" 5 O EE gm Ww

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NO. DATE (110URS) REPORT NO. CORRECTIVE ACTIONS / COMMENTS o

83-36 830601 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-37 830605 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand i

83-38 830606 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-39 830616 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand 83-40 830617 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load

Dispatcher due to low system demand 83-41 830619 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load j Dispatcher due to low system demand 83-42 830619 S 0.0 F 5 EA ZZZZZZ Load reduction requested by Load Dispatcher due to low system demand

, 83-43 830625 5 0.0 F 5 EA ZZZZZZ Load reduction requested by Load

' Dispatcher due to low systeA PP ROVE D demand '

AUG 1 G 1982

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ID/5A APPENDIX D QTP 300-S13 l UNIT SlfUTDOWNS AND POWER REDUCTIONS Revision 6 t

DOCKET NO. 050-265 August 1982 UNIT NAME Quad-Cities Unit 2 COMPLETED BY Alex Misak DATE July 1, 1983 REPORT HONTil June 1983 TELEPil0NE 309-654-2241 N $ g w" 5 $$$ @w Mw g@ d LICENSEE v3 @ @

v w DURATION EVENT $u 0 u

NO. DATE (110URS) REPORT NO. CORRECTIVE ACTIONS / COMMENTS ca 83-44 830629 F 0.0 H 5 ZZ ZZZZZZ Reduced load fer Drywell entry to investigate increased Drywell sump discharge a

APPROVED i - AUG 1 G 1982 i

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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 There were no Main Steam Relief Valve Operations for the reporting period.

B. CONTROL R0D DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no Control Rod Drive Scram timing data for the reporting period.

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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 memorandten (78-24) from D E, O'Brien to C, Reed, et al. , titled "Dresden,

Quad-Cities, and Zion Station--NRC Request for Refueling Information", l dated January 18, 1978. '

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QTP 300-S32 R: vision 1 k.

QUAD-CITIES REFUELING Harch 1978

( INFORMAT10N REQUEST a 1. Unit: Q1 Reload: 6 Cycle: 7

2. Scheduled date for next refueling shutdown: 9-6-82 3 Scheduled date'for restart following refueling: 12-18-82 -

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4. Will refueling or resumption of operation thereaf ter require a technical specification change or other IIcense amendment: Yes 5

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5. Scheduled date(s) for submitting proposed licensing action cad supporting

] . Information: 8-19-82: Tech. Spec. changes submitted to the URC.

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g 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:

a) All Tx7 fuel assemblies will be removed from the core.

b) MAPLHGR curves for fuel types in the core are being extended to h0,000 MWD /ST.

c) MCPR limits will be detemined by GE's ODYU computer code.

c d) The vessel pressure safety limit is being modified to acco=modate the d potential for higher reactor pressures as calculated by ODYN.

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7 The number of fuel assemblies.

R a. Number of assemblies la core: 724 d

b. Number of assemblies in spent fuel pool: 800 N

J 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 n in number of fuel assemblies:

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a. Licensed storage capacity for spent fuel: 3657 3 b. Planned increase in IIcensed storage: O a

9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present Ilcensed capacity: 2003 r APPROVED

APR 2.01978 Q.c.o.S.R.

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QTP 300-S32 1 Rsvision 1 I

QUAD-CITIES REFUELING March 1978

, INFORMATION REQUEST o

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. Vill refueling or resumption of operation thereaf ter 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. 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:

a) All new fuel assemblies will be of barrier design; MAPLHGR curves will be

, re-labeled to include the barrier designation.

b) The use of i.mproved assumptions in the load reject without bypass analysis resulted in a much improved MCPR operating limit. Technical Specifications are being changed to provide this additional operating margin.

7. The number of fuel assembites.

a. Number of assemblies in core: 724

b. humber of assemblies in spent fuel pool: 204

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:

f a. Licensed storage capacity for spent fuel: 3897 O

! b. Planned increase in licensed storage: ,

l 9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2003 1

r 4PPROVED APR 2 01978 Q.C.O.S.R.

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VIII. GLOSSARY The following abbreviations which may have been used in the Monthly

, Report, are defined below:

ACAD/ CAM -

Atrospheric Containment Atmospheric Dilution /Containnent 4 Attaspheric Monitoring ANSI -

American National Standards Institute APRM -

Average Power Range Monitor ATWS -

Anticipated Transient Without Scram BWR -

Boiling Water Reactor CRD -

Control Rod Drive I

EHC -

Electro-Hydraulic Control System EOF -

Emergency Operations Facility 4

GSEP -

Generating Stations Emergency Plan HEPA -

High-Ef ficiency Particulate Filter HPCI -

High Pressure Coolant Injection System HRSS -

High Radiation Sampling System IPCLRT -

Integrated Primary Containment- Leak Rate Test j LRM -

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 j MCPR -

Minimum Critical Power Ratio MFLCPR -

Maximum Fracticn Limiting Critical Power Ratio l MPC -

Maximum Permissible Concentration MSIV -

Main Steam Isolation Valve

NIOSH -

National Institute for Occupational Safety and Health PCI -

Primary Containment Isolation PCIOMR -

Precondition 1ng 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 Systen RPS -

Reactor Protection System EmH -

Rod Worth Minimizer SBGTS -

Standby Gas Treatment System SBLC -

Standby Liquid Control SDC -

Shutdown Cooling Mode of RHRS SDV. -

Scram Discharge Volume l SRM -

Source Range Monitor TBCCW -

Turbine Building Closed Cooling Water Systen TIP -

Traversing Incore Probe TSC -

Technical Support Center i

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N Commonwealth Edison C Quad Citi:s Nucistr Pow r Station '

C; ) 22710 206 Avenue North Cordova, Illinois 61242 i Telephone 309/654-2241 j.

NJK-83-234 July 1, 1983 Director, Of fice of Inspection & Enforcenent United States Nuclear Regulatory 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 Power Station, Units Cne and Two, during the month of June 1983.

. Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION f /

// / w k'f N, J, Kalivianakis

, Station Superintendent bb

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