ML20027D413

Monthly Operating Repts for Jan 1980

ML20027D413
Person / Time
Site:	Quad Cities
Issue date:	02/01/1980
From:	Beth Brown COMMONWEALTH EDISON CO.
To:
Shared Package
ML20027D407	List: ML20027D406 ML20027D413
References
NUDOCS 8211040262
Download: ML20027D413 (20)

Text

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{

I QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 .

MONTHLY PERFORMANCE REPORT JANUARY 1980 COMMONWEALTH EDISON COMPANY AND IOWA-ILLIN0IS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 and 50-265 LICENSE NOS. DPR-29 and DPR-30 i

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A TABLE OF CONTENTS I. Introduction ll. Summary of Operating Experience Unit One

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A.

B. Unit Two Ill. Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance .

A. Ammendments 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 f

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l. INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors,

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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-lilinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling 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 DPR-30, issued Octooe 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 rejpectively were October 18, 1971 and April 26, 1972. Commercial generation of pow r began on February 18, 1973 for Unit 1 and March 10, 1973 for Unit 2.

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

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II.

SUMMARY

OF OPERATING EXPERIENCE A. Unit One January 1: Unit One began the reporting period operating at 700 MWe. Load was reduced to 550 MWe for main condenser flow reversal.

Load was subsequently increased at a rate of 8 MWe/hr.

J'anuary 2-5: Unit One held an average load of 816 MWe.

January 6: Load was reduced to 600 MWe for main condenser flow reversal.

January 7-12: Unit One held an average load of 808 MWe. On January 10, load was reduced to 766 MWe in order to change over condensate demineralizers.

January 13: Load was-reduced to 600 MWe for turbine weekly and MSIV monthly testing.

January 14-19: Unit One held an average load of 758 MWe. On January 19 at 2245 load was reduced at the rateinf 100 MWe/hr to 550 MWe for control rod pattern adjustment.

January 20: While load was reduced to 550 MWe, control rod pattern adjustments and main condenser flow reversal were pegformed.

Load was subsequently increased at the rate of 8 MWe/hr.

January 21-25: Unit One held an average load of 800 MWe. On January 25 at 2200, load was reduced to 650 MWe in order to change over condensate demineralizers.

January 26: Load was held at 650 MWe. The IE condensate demineralizeriwas placed on-line and load was increased at 50 MWe/hr.

January 27-31: Unit One held an average load of 775 MWe. Load was reduced by 10 MWe on January 27 and 31 in order to change over reactor feed pumps.

c-' B. Unit Two

'- January 1-31: Unit Two remained shut down for End of Cycle Four Refueling Outage.

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111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specification The following amendment was added to the Technical Specifications _

during the reporting period:

Amendment 54 The NRC issued Amendment No. 54 to Facility Operating License No. DPR-29, in response to Commonwealth Edison Company letters dated December 4,1979, and December 20, 1979 The amendment extends the MAPLHGR curves for improved 7x7 (7D230) and 7x7 mixed oxide fuel bundles to planar average exposure values of 40,000 MWD /t. This license amendment becomes effective December 28, 1979.

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.

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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 QO2687 Reactor water Instruments were out instruments read instruments were Level Instrument of calibration approx. 10" calibrated & tested.

(1-263-57A & 578) higher than the other Yarways. Trip functions of inst-ruments not affected.

q02967 80-02/03L 1/2 SBGTS A gasket was worn. The charcoal adsorber The gasket was replaced (1/28-7509) failed the freon test. and the adsorber was tested.

402973 Reactor Building The coil in the IB- The vent system The coil was replaced Vent System 5741 Reactor Bldg. tripped ~& would not & the system was tested.

Supply Air isolation reset. The Reactor valve was shorted. Bldg was isolated, &

SBGTS started.

q03122 SBLC Level Bubbler tube was The level indicator was Bubbler tube was cleaned.

Indicator plugged. pegged upscale.

(Ll-1-Il40-2) Actual level and

• concentration were within Tech Spec limits.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q00694 Channel 2 A connector pin on The LPRM's were The pin was replaced.

LPRM/APRM J55 was pushed out erratic, causing a The system was tested.

In PS-7 1/2 scram. Other APRM's were functional.

QO2512 Refuel Platform The air piston on The open-close switch The air piston on the (834) the main mast was on the main mast would grapple was replaced.

defective. not cause the action.

QO2003 D.G. (2-6601) The oil seal was worn. Oil was leaking from The oil seal was replaced the scavenging oil & the line checked for pump inlet. The D.G. leaks, was available. .

QO2023 RHR shutdown The valve stem RHR was available. The shaft was cleaned &

cooling valve was burned The valve was hanging the valve was stroked (2-1001-43D) on closing. three times.

QO2870 80-02/03L Cond Pump Room The bolts were loose. The penetration failed The bolts were tightened vault penetration leak rate testing. & the penetration was P12. leak rate tested.

QO2646 79-27/03L F.W. Check The 0-Ring & seal The valve failed The 0-Ring & seal were Valve (2-220-62A) were worn. Leak Rate Testing. replaced & the valve was tested.

QO2647 79-27/03L F.W. Check The seat was worn. The valve failed The seat was re-built &

Valve (2-220-53A) leak rate testing. the valve was tested.

QO2211 79-27/03L Drywell Purge The valve was out of The valve failed The valve. was adjusted &

I Valve (2-1601-21) adjustment leak rate testing. tested.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R. LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO2240 IRM Channel 18 The cable was damaged. The other IRM The damaged cable was channels were replaced & the channel operational. was tested.

QO2241 IRM Channel 13 The cable was damaged. The other IRM The damaged cable was channels were replaced & the channel operational. was tested.

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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 80-01/03L 01-11-80 Torus'to Drywell Delta-P Transmitter 1-8741-51

! would not calibrate.

80-02/03L 01-11-80 SBGTS (B Train) failed Freon Test; charcoal absorbers were found to have leakage in excess of 1%.

UNIT TWO l 80-01/03L 01-08-80 SBLC Relief Valve

' setting failure.

. 80-02/03L 01-08-80 Leak Rate Test failure on Condensate Pump Room vault Penetration P-12.

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i 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.

VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission.

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A. Main Steam Relief Valve Operations There were no main steam relief valve operations during the reporting period.

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B. Control Rod Drive Scram Timing Data For Units One And Two There were no control rod drive scram timing operations during the reporting period.

J' Vill. REFUELING INFORMATION

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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.

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3 J . hevi:, wa - 5 g., - *Febru ry 1977 ,

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• OPERATING DATA REPORT - - .. ..

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{ DOCKET NO. ' 50-254 L -

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UNIT ONE

', . . DATE January 1,1980

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COMPLETED BY B. Brown ,

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309-654-2241, ext. 245 .-

' TEl.EPHONE T@- - . . .-.

Is OPERATING STATUS

- 0000 010180 Reporting period:2400' Ol318 gross hours in reporting period: 744 .

g 3.

Lg Max. depend. capacity L 2. Currently authorized power level (HWt): 2511 (MWe-Net) : 769* Design electrical rating (f1Ve-Net): 789 , .  ;

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

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

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13 ufative

" . This Month Yr. to Date C

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744 746 scoca i

~5 Number of hours reactor was critical ,

a s 0 0 1491.9

6. Reactor reserve shutdown hours '

i; <;2784.9 744 745 s 7 Hours generator on line 0 0 909.2 -

g 8. Unit reserve shutdown hours.

ti 1747'213 106>91194 9., Gross thermal energy generated (HWH)

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" 1747213 10.- Gross electrical engergy generated (HWH)_ 576126 576126 Wloo180 b 559771 3I965307

11. Het electrical Energy Generated _ 54977I ,

81.9 I 12. ' Reactor service factor 100 100 tu 10'O 86.9

13. Reactor availabillfy factor !99 '

{e 14. Unit service factor 100 100 77.o

" 100 79.3

15. Unit availability factor tog

16. Unit capactly factor (Using HDC) 96.1 96.1 61.4 1 Unit capacity factor (Using Des. HWe) 93.7 59.8

17. 93 r ,

18. Unit forced outage rate 0 0' 8i

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~- 19 Shutdowns scheduledover next 6 months (Type, date, and duration of each):

20. If shutdown at end of report period, estimated datc hf startupA - .w.

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• The MDC may be lower than 769 MWe during periods of high ambiant temperature due l to the thermal performance of the spray canal. 1/,.J1 *t (. 'C77 -l

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OPERATING DATA REPORT - -

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DOCKET NO. 50-265 .

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,7 UNIT -

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TEl.EPHONE 309-654-2241 ext. 245. ]

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!! OPERATING STATUS 0000 010180 '

"" 2400 0.31801 Gross hours in reporting period

744

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i Currently authortted power level (MWt): 2511 Max. depend. capaci ty 5 2. 789 (MWe-Net) : 769* Design electrical rating (MWe-Net): , _.

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Power level to which restricted (if any) (MVe-Net):

NA . .

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Reasons for restriction (if any):

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) Cumulative

'" . This Month Yr. to Date ~

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0 0 ;1128.o lf2 Number of hours reactor was criticai

'a,,,7 -.s5 0 2985.8 0 .

6. Reactor reserve shutdown hours ' ~

If Hours generator on line 0 0 50791.8 1 7 0 702.9 0

8. Unit reserve shutdown hours.

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0 .U3016109.

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9., Gross thermal energy generated (MWH) '

,e 7 _ '32863057 10.- Gross electrical engergy generated (HWH) 7 r.a 30728710.

-13815 -13815

11. Net electrical Energy Generated 0

0 79.5 fd 12. Reactor service factor l Is Reactor availabil.ify factor 0 0 84.0 13 .

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0 0 76.0

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14. Unit service factor '

I Unit availability factor o o 77_i 15 c;o. g

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16. Unit capactly factor (Using HDC) 0 o 1 17. Unit capacity factor (using Des. MWe) n n en 3

18. Unit forced outage rate 0 0 N 9.2

[ Shutdowns scheduledover next 6 months (Type, date, and duration of each):

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, d.1 .- If shutdown at end of report period, estimated date .of startupA arch. H JO, 1980 i , L.A 20. - . s. a ,,. E n

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• The MDC may be lower than 769 MWe during periods of high ambiant temperature due

" to the thermal performance of the spray canal. ;ffR 1 c. 377 -

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QTP 300-511 R; vision 4

']kl APPENDIX B Juna 1976 <

AVERAGE DAILY UNIT-POWER 1.EVEL sa Docket No. 50-254

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3 Unit ONE ,

2-1-80 ~ $_ .

Date 7

Completed by B. Brown .

309-654-2241,

- Telephone ext. 245 Pd . .

a HONTH Januarv 1980 ,

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• DAY AVERAGE DAILY POWER LEVEL g DAY AV.ER*AG,E DAILY POWER LEVEL'

.in (HWe-Net) (HWe-Net) 3.] 17 727

1. 598 .

9 18.

2. 752 750 .

e2 d .

770 19 744

, 3 1:; I 4, 20. 615 NI 774 YO W' 5 763 21 750

~ 698 22. 753 6.

802 23 736 7 .

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L 8. 745 24.- 775 Di -

763 25 753 -

bG 9 766 26, 610 x 10.

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• 771 27 7N

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28. 745 75 12. 766

ps 720 29 743 13

14. 771 30. 739 31- 737 7, 15 761. a y y go y p

1. 773

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.10N 2 01976 8

INSTRUCTIONS

'- On this form, list the average daily unit power level in MWc. Net for each day in the reporting obthkuh

/ nessest whole sneeswatt.

J These figures will be used to plot a graph for caeh reporting month. Note that when nuximurn dependsble espacityis Nd used for lhe net cicetrical rating of the unit. there may be ocessions when the daily aserage power level exceeds the 100'4 line (or the restricted power lesel hac). In such cases, the average d.iity unit power oatput sheet should be footnoted to exp!aits the Jpparent anumsly.

' ' QTP 300-511 .

,k R;visI6n 4 gfQ Y APPEf1 DIX B Juna 1976 gf;j AVERAGE DAILY UtilT-POWER ' LEVEL m

Docket No. 50-265 -

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3 Unit TWO . 9,! 3 j, -%

2-1-80 '--

Date Completed by B. Brown l1 7 . .

Telephone 30!s-654-2241 ..;

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7 H0ffTH January 1980 .

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DAY AVERAGE DAILY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL g

(HWe-Het) (HWe-tiet)

1. -16.7 17 - n .1 4 2. -18.5 18. -17.9

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-18.7 g 3. -18.7 19

4. -18.4 20. -18.2 f

-18.2 21 -20.1 5

[y@ -17.7

6. ' -18.6 22. ,

%'i ,- -19 7 23 -19 4 7.

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-17 4 24.. -19.8

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f$ 25 -17.5 Fd 9 -17.9

-18.2 26. -18.6 52- .

10.

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-20.3 27 -18.6' -

11.

w'd -17.6 28. -19.2

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29 ' 18.5 l 13 3 -19.6 ' - -

L5 14. -19.6 30.

-19.1 31. -18.9 P'J aeet<uVED 15 rje I

l 16. -22.7 JUN 2 01976

?m l ' INSTRUCTIONS

- On this form. hst the average daily unit power level in f.!WNet for each day in the reporting mo9 nesses: whole anecawatt.

These figures will be used to plot a graph for caeh reporting month. No e that when nuximura dependable capac d used for the net electrical rating of the unit. there may be occasions when t!.e daily aserage power level exceeds the 1004 line (or the restriered power lesel hae). In such cases, the average daily unit power output sheet should be 1_ footnoted to explain the .ipparent anomaly. , .

(9 Erm1 F=9 P""9 r"'"1 r""5 r"'"5 F""5 L"""1 M r""'3 C""5 C. C"3 O M 'O.Li Cl

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s APPENDIX D QTP 300-S13 ~ ~ ~ ~ ~

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. UNIT SHUTDOWNS AND POWER REDUCTIONS Re'visl6F 5 DOCKET NO. 50-254 .

March 1978 U. NIT NAME Quad-Citie3 Unit One COMPLETED BY B. Brown DATE February 1,.1980 REPORT MONTH January 1980 TELEPHONE 309-654-2241 e'x t . 245 6 =

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LICENSEE gg gg .'

Rou. $

DURATION 5,* EVENT *8 g:8 NO. DATE " g5g m (HOURS) REPORT NO. 8 CORRECTIVE ACTIONS / COMMENTS ~~' .

R 28 800126 F HA NA HA NA HG DEMINX Load was reduced to change over condensate

. demineralizers.

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- . QUAD-CITIES REFUE!.ING *

' -  !!! FORMATION REQUEST ,

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.1 Reload: 5 _ cycle: 6 . y. .

.1. Unit:

8_m_~8n _ (sh,,f-amn (EOc5}

2. - scheduled date for 'next refueling shutdown: .

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following refueling: 12-7 80(Startito BOC6)'

3 Scheduled date for restart .

4.

Will refueling o'r resu.nption of operationd thereafNo, ter Plan require a technical 10CFR50.59

'reloadi

, specification change or other license amen ment:The review will be conducted foi future cycles of Quad Cities Unit 1. - .

in June, 1980. .

scheduled date(s) for submitting proposed . licensing action and a 90 supporting days 5 June,1980 for .100FR50.59 related changes ,

- . information: '

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prior to shutdown. .

e.g., new or

6. Important licensing considerations associated with r'efueling,

' di fferent fuel desig'n or supplier, unreviewed design 'or per,formance 6nalysis -

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

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

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7. The number of fuel a.ssemblies. -

- 724

a. Number of assemblies in core:

Number of assemblies in spent fuel pool: 596 '

b. .

fuel pool storage capacity and the size of any S.

The present licensed spentincrease in licensed storage capacity that has been re -

in number of fuel assemblies: ,

1460 . ,,- .

a. Licensed storage capacity for' spen't fuel: - . s.

None .

b. Planned increase in licensed storage: _

h. The projected date of the last refueling that can be discharged to the licensed capacity: Septeinber, 1985 pent" fuel ool assuming the present end of ba ch discharge ~ capability) .

XPPROVED

- ,. APR 2.01973 d' -

Q. C. O. S. R.

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Revision 1

- QUAD-CITIES REFUELING H:rch 197.8 INFORttATION REQUEST

• ' 2 Reload: 4 _ Cycle: 5 Unit:

1.

Scheduled date for next refueling shutdown:

. 11-4'-79 (Shutdown EOC4

2. . .

i Scheduled date for restart following refueling: 11-17-80 (Startuo B005) 3 '

4. Will refueling o'r resumption of operation thereaf ter require a technical-No, Plan 10CFR50,59 Reloads specification change or other license' amendment: The review will be conducted-foi' future cycles of Quad Cities Unit 2.

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by early September,1979 . .

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scheduled date(s) for~ submitting proposed licensing action and supporting ~

information: Early August,1979 for 10CFR50 59 related changes a 90 l

.e days prior to shutdown..- .

6. Important licensing considerations associated w'ith refueling, e.g. ,' new or "

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' ' different fuci desig'n or supplier, unreviewed design or performance snalysis -

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

l New Fuel Design: Retrofit 8x8 fuel (180) - '

a nat. U at bundle top and bottom

_.j b two larger water roda j, .

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}- c new enrichment ~ distribution

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. d prepressurized ..

I This fuel design was previously used for Quad Citie~s. Unit 1 Cycle 5 1 and Dresden Unit 2 Cycle 7 -

7 The number of fuel assemblies.

Number of assemblies in core: 724 l! a.

b. Number of assemblies in spent fuel pool: 492 l<

The present licensed spent fuel pool storage capacity and the size of any fi B.

increase in licensed storage capacity that has been requested or is planned -

in number of fuel assemblies: .

,g 3460 -

' a. Licensed storage capacity for' spent fuel:

Planned increase in licensed storage: Non$ .

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1- The projected date of the last refuelinD that can be discharged to the l 9.

! spent fuel pool assuming the present licensed capacity: March, 1986 l

(End of batch discharge capability) X P P R O V .E D hPR 2.01973 l; .

- Q. C. O. S. R. '

Vlli. GLOSSARY The following abbreviations, which may have been used in the Monthly Report, are defined below:

CRD - Control Rod Drive System SBLC - Stand-By 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

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SRM -

Source Ra'nge Monitor IRM - Intermediate Range Monitor LPRM - Local Power Range Monitor APRM -

Average Power Range Minitor TIP -

Traveling incore Probe a, RBCCW - Reactor Building Closed Cooling Water System i TBCCW - Turbine Building Closed Cooling Water System RWM -

Rod Worth Minimizer SBGTS

- Stand-By Gas Treatment System HEPA -

High-Efficientry Particulate Filter RPS - Reactor Protection System IPCLRT - Integrated Primary Containment Leak Rate Test LPCI - Low Pressure Coolant injection Mode of RHRS RBM -

Rod Block Monitor

! BWR -

Boiling Water R2 actor ISI - In-Service inspection MPC -

Maximum Permissable Concentration i

l

_ __ _ _._ , __. _ _ _ _ . . _ _ _ . _ _ _ . . _ . _ - _ _ . _ . _ _ _ _ _ _ _ , _ , _ , _ _ .~_- _ _ _ _ _

r PCI - Primary Containment isolation SDC - Shutdown Cooling Mode of RHRS -

LLRT - Local Leak Rate Testing MAPLHGR - Maximum Average Planar Linear Heat Generation Rate R.O. -

Reportable Occurrence DW -

Drywell Rx -

Reactor EHC

- Electro-Hydraulic Control System MCPR - Minimum C,ritical Power Ratio ,

PCIOMR - Preconditioning Interim Operating Management Recommendations LER - Licensee Event Report ANSI -

American National Standards Institute National Institute for Occupational Safety and ,,

j.

NIOSH Health ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring

.