Text

Monthly Operating Repts for Dec 1979
	ML19257B197
Person / Time
Site:	Quad Cities
Issue date:	01/03/1980
From:	Beth Brown; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML19257B194	List: ML19257B193; ML19257B197;
References
	NUDOCS 8001150364
	Download: ML19257B197 (22)
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. .

QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT DECEMBER, 1979 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. DPR-29 and DPR-30 1747 253 soonso 367

TABLE OF CONTENTS

1. Introduction ll. Summary of Operating Experience Ill. Plant or Procedure Changes, Tests, Experiments, ar.J 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. License Event Reports V. Data Tabulations VI. Unique Reporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Timing Data Vll. Refueling information Vill. Glossary 1747 254

1. 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 lowa-Illinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors. The Architect / Engineer was Sargent & Lundy, Inc. 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 numbers DPR-29 and DPP,-30, Issued October 1, 1971 and March 21, ,972 respectively, pursuant to Docket Numbers 50-254 and 50-265. The date of initial reactor criticalities for Units 1 and 2 respec-tively were October 18, 1971 and April 26, 1972. Commercial generation of power began on February 18, 1973 for Unit I and Marcn 10, 1973 for Uni t 2.

This report was compiled by Becky Brown. Telephone number 309-654-2241, extension 245 1747 255

ll.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One December 1: Unit One began the reporting period operating at 791 MWe.

December 3-8: Unit One held an average load of 808 MWe.

December 9: Load was reduced to 791 MWe for weekly turbine tests and to 700 MWe due to high condensate demineralizer differential pressure.

December 10: Load was reduced to 733 MWe in order to switch over condensate pumps.

December 11-12: At 2341, Unit One scrammed due to a blown fuse in the potential transformer supplying the generator voltage regulator.

The fuse was replaced. The reactor was made critical December 12 at 0617; and at 1220 the unit was placed on-line. Generator voltage regulator performance was satisfactory during start-up.

December 13: Unit One held an average load of 635 MWe.

December 14: At 0113 Unit One was taken off-line; and at 0418 all control rods were fully inserted. Unit One was shutdown for the Unit Two 125/250 volt battery discharge tests and to install required modifications to comply with NUREG 0578.

December 19: At 2000 the reactor was made critical and on December 20 at 0948 Unit one was placed on-line.

December 21-22: Load was steadily increased to 750 MWe.

December 23-25: Unit one held a steady load of 766 MWe.

December 26: Load was reduced to 350 MWe in order to shut off the IC reactor feed pump in order to inspect the 4 MV breaker. Following inspection, a second feed pump was started and load was increased.

December 27-28: Unit One steadily increased load to 775 MWe.

December 29-31: Unit One held an average load at 750 MWe. On December 31, at 2200, load was reduced to 600 MWe for main con-denser flow reversal.

1747 256

6 II.

SUMMARY

OF OPERATING EXPERIENCE (continued)

B. Unit Two December 1-31: Unit Two remained shutdown for the end of Cycle Four Refueling Outage.

1747 257

Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED HAlNTENANCE A. Amendments to Facility License or Technical Specification There were no amendments added to the facility license or technical specification during the reporting period.

B. Facility or Procedure Changes Requiring NRC Approval There were no facility or procedure changes requiring NRC approval.

C. Tests and Experiments Requiring NRC Approval There were no tests or experiments performed during the reporting period requiring NRC approval.

D. Corrective Maintenance of Safety Related Equipment The following represents a tabular summary of the safety related maintenance performed on Unit One and Unit Two during the reporting period. The headings indicated in this summary include Work Request Numbers, LER Numbers, Components, Cause of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

1747 258

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UNIT ONE ttAINTENAllCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION

- Q01837 24/48 VDC A terminal of the The 24/48 VDC batteries The terminal was cleaned, Battery (1-8325) IBl cell I was were available and greased, and the bolts corroded operable were tightened. The voltage was checked.

QO2187 #1 Control Valve The scram reset There was a delay before The limit switch was limit switch was the 1/2 scram could be replaced and the control sticking reset. RPS function valve and scram relay was operable were tested.

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UNIT TWO MAlHTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER HUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION 002076 79-27/03L MSIV (2-203-28) The valve seat The HSIV failed leak The stroke was extended was worn rate test and the valve was leak rate tested successfully.

1011-79 U-2 D.G. Air The valves were The valves were leaking. The valves were replaced.

Supply Valves worn Starting Air was avail-(2 4699-121 & able and the diesel was 122) operable Q02288 79-29/03L 02 Analyzer The packing was The valve would not The valve was replaced and Valve (2-8803) worn and a gasket close. The 2-8804 valve a new gasket was placed on

. In the operator was operational for PCI the operator.

was worn s

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IV. LICENSEE EVENT REPORTS The following is a tabular summary of all license 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.I. and 6.6.B.2. of the Technical Specifications.

UNIT 0NE Licensee Event Date of Report Number Occurrence Title of Occurrence 79-39/03L 12-20-79 Exceeded MAPLHGR Exposure Limits 79-40/03L 12-23-79 Torus Water Level exceeded +2 inches 79-41/03L 12-17-79 Drywell N2 Purge Valve A0-1-1601-21 closing time greater than ten seconds 79-42/03L 12-14-79 MSIV l-203-1C closing time greater than five seconds UN IT TW0 79-28/03L 12-5-79 RCIC Turbine Area High Temperature Switch Drift 79-29/03L 12-6-79 isolation Valve 2-8803 failed to fully close 79-30/03L 12-28-79 RHR Service Water Vault Bed Plate Drain Valve 2-4999-59 failed to isolate 1747 262

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 1747 263

,' QTP 300-Si;

, I.f*V i G O .". 3 February 1977

D** *D'T f i

' 1

% CO WI , .. 3 OPEP.ATl;:G DATA REPORT j DOCFET !!0. 050-254

. U:;;T ONE

-2 DATE l-3-80 .

.- y - -l n y __ B Brown TE'. PMT:I 309-654-2241,

ext. 245 j OPEP.ATit;G STATUS 0000 120179 2400 123179

~j 3. Reporting period: Gross hours in reporting period: 744

-)

2. Currently authorized power level (Mut) : 2511 liax. depend. capaciiy

_. (MWe-fla t) : 769A Design electrical rating (tule-fic t ) : 78') .

, 3 Power level to which restricted (if any) (MWe-i:et)- NA .

~

-l 4. Reasons for restriction (if any):

J This Month Yr. to Date Ct.mu l a t i ve 5 r: umber of hours reactor was cri tical 601.7 7381.2 54714.1

, 6. Reactor raserve shutdown Scurs 0.0 92.3 3421.9

-i

, 7 Hours generator on line 578.8' 7098.0 52040.9

8. Unit reserva shutdown hou.s. 0.0 19.8 909.2 _

1 9., Gross thermal energy genera:cd (MWH)

' 1287315 15736105 104543981

10. Gross electrical engergy generated (tiWH) 424452 5050559 33623054 11, ::et electrical Energy Generated 403160 4782963 31415536

. 12. F.eactor sarvice factor 80.9 84.3 81.7 13 Reactor availabilify factor 80.9 85.3 86.8.

j 14 Unit service factor 77.8 81.0 77.7 15 Unit availability factor 77.8 81.3 79.0

~

15. Unit capactly factor (U: ing .'ec) 70.5 71.0 61.0 17 Unit cspacity factor (Using Des. MU ) 68.7 69.2 59.4

18. Uni: Forced outage rate 22.2 8.0 8.2 19 Shu de ;ns sch2duled c,e :r nex.: G .cn:h, (Typ., da.2, .r-' ciura t i er. o f e ac'1) '. None

20. I f shu:cc..1 at e.nd o f repor t p e r i c'J , .2 s t in > ' ed Ja t e e,f s ta r t up :

NA Tha 'tCC riaye ' <: l o .o r tMn 753 Mie during p2ric !s of liigh e 6iant ten eratur., c: -

to t h e ther; :I par f >r- 2nce of ::- 5; ray cann1. . .

i vi~n 1747 264 + -.. .o

. tiTP 300-312 OQ

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OPERATI:;S DATA REPG.'T DOCKET NO. 050-265 UillT TWO DATE l-3-80 Cu,9 L ET. 3 dY B B rown TELE PHO.'lE 309-654-2241,

! ext 245

. 0?ERATit:G STATUS 0000 120179 2400 123179

. J. Reporting period: Gross hours in reporting period: 744

2. Currently authorized power level (Mut) : 2511 Max. depend. capacity

(.1We-Me t) : 769t: Design electrical rating (mie-Ne t) : 789 .

3 Po..ar level to which rastricted (if any) (M'.le-::e t ) : NA .

] 4. Reasons for restriction (if any):

J This .'tonth Yr. to Date Cu:aula t ive i 5 ::urber of hours reactor was critical 0.0 7752.5 53128.9

, 6. Recctor reserve shutdown hours 0.0 0.0 2985.8 i

7 Hours generator on line 0.0 7688.9 50791.8 C. Unit reserva shutdo.in hours. 0.0 0.0 702.9

.I 0

9., Gross thermal energy generated (MVH) 14273985 103016109

10. Gross electrical engergy generated (MWH) 15 4374673 32863050 2

11. Not electrical Energy Generated -12405 3981065 30742525

_, 12. Reactor service factor 0.0 88.5 80.4 13 Reactor availabilify f : tor 0.0 88.5 84.9_

14 Unit service factor 0.0 87.8 76.9

{ 15 Unit availability factor 0.0 87.8 77.9

16. U.,it capactiy factor (Us ing MDC) -2.2 59.1 _

60.ji _

17 Unit capacity factor (using Des. Mue) -21 57.6 59.0

13. Unit forced cutage rate 0.0 0.9 9.2 19 Shutde..ns scheduled over next 6 rcnths (Type , da t e , am; dur oticn of each):

a. i shutdc..a at end of report p e r i c.f , es t ima u.! date of s tartupj. Feb 29, 1980 The : r.cy be Ic.er than 763 MWe durir,g pericJs of high ambiant t e.npe ra t u re du; to th; ther 21 perfor ance of the spray canal . .. '

! (final) 1747 2 5 ., ~:.c.,.,

QTP 300-S!1 APPEt: DIX B Revision 4 AVETsAGE DAILY Utili-PO'.!EP LEVEL June 1976 Docket fio. 050-250 Unit ONE C., ,p l e t e b on ,

, leiep:nne 309-654-2241,

ext. 445 110NTM

., December 1979 JAY AVEPJAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (tNe-Net) (MWe-Ne t)

l. 748 17 -5.1

2. -

713 18. -11.1 1

.. 3 776 19 -11.9 1

..] 4. 769 20. 151 5 762 . . 21 491

6. 768 22. 642

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7. 775 23 772 1

8. 764 24. 770 i

J 9 744 25 759 1 10. 741 26. 691

11. 743 27 54.1 j 12. 173 28. 702

, 13 605 29 775

.3 14. -8.3 30. 748 15 -11.3 31. 733 aeeHOVED

16. -10.6 1747 266 "2" INST!!L'CTIONS On this for. ., L.* the :ve :: d ..!y u ,;: pc . ': ...' .. v'.'*;3: : rn , ......

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1 (final)

QTP 300-511

, APPEt:DIY B P'UVISIC' 4 AVERAGE DAILY UillT-PO.iER LEVEL June 1976 1

Docket flo. 050-265 Unit TWO 1

Date 1-3-80 i .

Completed by B Brown ephone 309-654-2241, j b ext. 245 110 ;T3 December. 1979 1

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

' (Mtle -Me t ) (MWe-Me t )

1. -20.0 17 -5.1

2. -22.0 18. -5.1

.. 3 -23.9 jg, -5.0

..! 4. -19.4 20. -14.7 5 - 21..i 21 -18 3 J

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I 7, -21.1 -17.6 23 i

8. -19.1 24. -19 9 t

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.J 9 -20.2 25 -18.3 1 10. -17.0 26. -23.0 i

11. -19.5 27 -15.7 -

i 12. -18.8 28. -16.8 4

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29 -18.5 J 14. -12.2 30. -17.6 15 -6.2 31. -19.5 aeeHvVED

36. -5.4 1747 267 "2" INSTI UCT!ONS On this form. !":t the neng- h!y u,it pa ce !c.. ' ;r, t:w.Nc: rm ;. .h e y

. .- m: repc tia;i 96G. C. 3 2 e f.CJi .4! b by!0 is. 32 v. .'.t i .

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u.ed tur 11.. net <!cetric.*i r.-ting of the unit there may he occaua:n v. hen t!.e Ja!!y aserag: po..:r le.;! exce d: :h:

1014 Lee (o: th res:ncied po cr ::vei hne) In such ca<.:;. the ac:ar.: J.:ily unit pae.er e tput sheet ::.cu!J b fau:n91-;J :u s , :a : !!.; app:en; ,no:::2y.

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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 B. Control Rod Drive Scram Timing Data A. MAIN STEAM REllEF VALVE OPERATIONS Relief valve operation 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 CONDITIONS OF EVENTS 1 12-20-79 l-203-3A 1 Manual Rx Press Acoustic l-203-38 1 Manual 920 Monitor 1-203-3C 2 Manual Modification 1-203-3D 1 Manual Test 1-203-3E 1 Manual B. CONTROL R0D DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO There were no control rod drive scram timing exercises performed during the reporting period.

1747 270

Vll. REFUELING INFORMATION The following information about future reloads at Quad-Cities Station was requested in a January 26, 1978 licensing memorandum (78-24) f rom 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.

1747 271

QTP 300-532 .

F.evi s i on 1 March 1973 QUAD-CITI ES REFUE!.ING INFORMATION REQUEST 1 Reload: 5 - cycle: 6

1. Unit:

2. Scheduled date for next refueling shutdown: 8_Cpn (hugen (E005)

Scheduled date for restart following refueling: 12-7-80(Startup BOC6) 3

4. Uill refueling o'r resumption of operation thereaf ter require a technical specification change or other license amendment: No, Plan 10CFR50.59 relonds for future cycles of Quad Cities Unit 1. The review will be conducted in June, 1980.

5 scheduled date(s) for submitting proposed licensing action and st.pporting ,

. i n forma tion: June, 1980 for 10CFR50.59 related changes a 90 days ,

prior to shutdown.

6. Important licensing consideratior.s associated with refueling, e.g. , new or '

' dif ferent fuel desig'n or supplier, unreviewed design or performance analysis :

methods, significant changes in fuel design, new operating procedures:

New fuel designs: Retrofit 8x8 fuel 2.65 w/o% (^- 224) t

~

7 The number of fuel assemblies. _

a. Number,of assemblies in core: 724

b. Number of assemblies in spent fuel pool: 596

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: 1460 .

~. .

Planned increase in 1icensed storage: None -

b.

9 The projected date of the last refueling that can be discharged to the pent fuel pool assuming the present licensed capacity: Se ptci:.ber , 1985

(<end of batch discharge ~ capability)

XPPROVED APR 2,o 1973 O. C. O. S. R.

8

. g m p ..-

QTP 300-532 .

. . Revision 1 QUAD-CITIES REFUEL!!1G tiarch 1973 it!FORtiATION REQUEST

1. Unit: 2 Reload: 4 Cycle: 5

2. Scheduled date for next refueling shutdown: 11 4-79 (Shutdown EOC4) 3 Scheduled date for restart following refueling: 1-17-80 (Startuo 2005)

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment: No, Plan 10CFR50.59 Reloads for future cycles of Quad Cities Unit 2. The review will be conducted by early September, 1979 5 scheduled date(s) for submitting proposed licensing action and supporting

. in forma ti on: Early August, 1979 for 10CFR50 59 related changes a 90 days prior to shutdown.

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

' dif ferent fuel desig~n or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

New Fuel Design: Retrofit 8x8 fuel (180)

~

a nat. U at bundle top and bottom b two larger water rods c new enrichment distribution d prepressurized This fuel design was previously used for Quad Cities Unit 1 Cycle 5 and Dresden Unit 2 Cycle 7 7 The number of fuel assemblies.

a. tiumber of assemblies le core: 724

b. flumber of assemblies in spent fuel pool: 492

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 f uel assemblies: ,

a. Licensed storage capacity for spent fuel: 1460 '

b. Planned increase in licensed storage: Nor$e 9 The projected date of the last refueling that can be discharged to the spent' fuel pool assuming the present licensed capacity: March. 198o (End of batch discharge capability)

APPROVED

-i-1747 273 O. C. O. S. R.

Vill GLOSSARY The following abbreviation which may have been used in the Monthly Report, are defined below:

CRD - Control Rod Drive System SBLC -

Standby Liquid Control System MSIV -

Main Steam isolation Valve RHRS - Residual Heat Removal System RCIC - Reactor Core isolation Cooling System HPCI -

High Pressure Coolant injection System SRM -

Source Range Monitor IRM - Intermediate Range Monitor LPRM -

Local Power Range Monitor APRM -

Average Power Range Monitor O Tie -

Treveiiao incore erose RBCCW - Reactor Building Closed Cooling Water System TBCCW -

Turbine Building Closed Cooling Water System RWM -