ML20080N739

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Jan 1984
ML20080N739
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 01/31/1984
From: Kalivianakis N, Misak A
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NJK-84-43, NUDOCS 8402220332
Download: ML20080N739 (21)
v • d • e


Text

. -.

t QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT JANUARY 1934

. CCMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS, 50-254 AND 50-265 LICENSE NOS, DPR-29 AND DPR-30 i

+

I S402220332 840131 PDR ADOCK 05000254 R

PDR

~

4 L

TABLE OF CONTENTS I,

Introduction II, Summary of Operating Experience 4

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 B.

Facility or Procedure Changes Requiring iiRC Approval C.

Tests and Experi:nents Requiring NRC Approval D.

. Corrective Maint 2 nance of Safety Related Equipment I -

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 l'

A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scran Timing Data VII. Refueling Information

.VIII, Glossary 1

t 1

i f

.~

_m.

I.

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 1

Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

l 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 Farch 21, 1972, respectively; pursuant to Docket Numbers 50-254 and 50-265.

The date of initial Reactor critica1Lties 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 complied by Becky Brown and Alex Misak, telephone r

number 309-654-2241, extensions 127 and 194.

4 e-4 p,

,-n..,...,.,,

,,..n

-r..-

we,.----r,-,

,. w w-. e,

II,

SUMMARY

OF OPERATING EXPERIENCE A.

Unit'One January 1-10: Unit One began the month dropping load for a Drywell entry to determine the cause of excessive leakage in the Drywell. At

'0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> on January 1,-the unit held load at 320 MWe while Operating Department personnel entered the Drywell. At 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />, a leak was located from an isolation valve on the bonnet leak-off line of the IB Recirculation pump discharge valve and was repaired. At this time, the unit began a normal load increase to full power. At 0045 hours5.208333e-4 days <br />0.0125 hours <br />7.440476e-5 weeks <br />1.71225e-5 months <br /> on January 8, the unit dropped load to 600 MWe to perform weekly Turbine tests and Control Rod Pattern adjustments. At 0600 hours0.00694 days <br />0.167 hours <br />9.920635e-4 weeks <br />2.283e-4 months <br />, the Control Rod adjustments were completed, and a normal load increase was initiated.

1 '

January 11-20: At 0055 hours6.365741e-4 days <br />0.0153 hours <br />9.093915e-5 weeks <br />2.09275e-5 months <br />, on January 12, the unit dropped load to 700 MWe to perform weekly Turbine tests.

At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br />, testing was completed and the unit began a nornel load increase. At 0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on January 15, the unit dropped load to 700 MWe for Turbine tests.

Following completion of the tests at 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br />, the unit began a normal load. increase.

January 21-31: At 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />, on January 21, the unit dropped load to 550 MWe-to adjust the Control Rod Pattern. At 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, on January 22, the adjustments were completed and the unit began a normal load increase. At 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on January 29, the unit dropped load to 720 MWe for Turbine tests. At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br />, the tests were completed and the unit began a normal load increase.

B.

Unit Two Unit Two remained shutdown throughout the month for End of Cycle Six Refueling and maintenance.

L.

1 4

1

.--v..-,

~.-m._-,,

III.

PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED Mh!NTENANCE A.

Amendments to Facility License or Technical Specifications There were no Amendments to the Facility License or Technical Specifications during 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 Haintenance of Safety Related Equipnent 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:

W rk Request Numbers, LER o

Numbers, Components, Cause of Mal functions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

b

-w-----

---r

4 UNIT ONE MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO

- NUMBER NUMBER COMPONENT MALFUNCT10N SAFE OPERAT10N PREVENT REPET1 TION There were no Safety Related Work Requests for Unit one for the reporting period.

1 i

1 j

i i

1 1

t l

l

,i Y

4 e

m g

UN IT _ TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q31191 83-15/03L Check Valve 2-1301-Vavle seat wear.

Leakage thru valve was Valve seat was polished 41 not excessive.

and gaskets were replaced; the valve was successfully leak rate tested.

Q30850 83-18/01T Reactor Water Stress corrosion The crack was not thru Elbow was cut out and Clean-up Elbow cracking.

wall and thus did not replaced. It was then leak. Any leakage successfully hydro-would have been static tested.

isolated' by MO 2-1201-2.

Q30186 Three RiiR Service Seal deteriora-flone.

Leaks were The penetrations were Water Vaul t

tion, small. Vault's sumps repaired, and Penetrations would have removed successfully leak rate any leakage.

tested.

Q31077 83-15/03L M0 2-1301-17 Any leakage would have The valve's seat was Valve been controlled by in-cleaned, its disc was line NO 2-1301-16 lapped, and the valve valve.

was successfully leak rate tested.

IV, LICENSEE EVENT REPORTS l'

The following is a tabular summary of all licensee event reports for Quad-Citlec 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 ONE License Event Report' Number Date Title of Occurrence There were no Licensee Event Reports for Unit One for the Reporting Period.

UNIT TWO 83-25/03L 12-29-83 RHR Service Water Vault Sump Check Valves Failed 84-01/03L' l-3-84 Reactor Scram While Shutdown 84-02-03L l-6-84 Reactor Scram While Shutdown i.

h I

T

..e,+,-

,.-.-s--

y,

.-,,,ryy,w,-,,,

-,--wy

,,m wr--

  • vc y-.---,w-r.-y-.-,--

-w-

--a

---,,wy

-, - --w-79--y.vy.-ww.-.,

m----

.er.

.-. _ ~..

-. ~.

r n

i i

V, DATA TABUIATIONS i

The following data tabulations are presented in this report:

A, Operating Data Report l

B, Average Daily Unit Power Level C,

Unit Shutdowns and Power Reductions i

?

I L

i 4

4 b

L 4

1 0

4 t

a I

A 1

J a

4 2

l l

1-I u-,

.--.-...--..,.,_.,..--..-,..-.-.-_._.m_,m...

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

OPERATING DATA REPORT DOCKET NO.

50-254 UNIT ONE DATEFebruarv 7 COMPLETED BYAlex Misak TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 010184 1.

Reporting period:2400 013184 Gross hours in reporting period:

744 2.

Currently authorized power level (MWt): 2511 Max. Depend copocity (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 744,0 744,0 84299.6 6.

Reactor reserve shutdown hours 0.0 0.0 3421,9 7.

Hours generator on line 74t 0 744,0 81091.9 8.

Unit reserve shutdown hours.

0.0 0,0 909.2 9.

Gross thermal energy generated (MWH) 1763203 1763203 166869909

10. Gross electrical energy generated (MWH) 584462 584462 53843078 ii. Het electrical energy generated (MWH) 555374 555374 50161341
12. Reactor service factor 100,0 100.0 82.0
13. Reactor avo11ob111ty factor 100.0 100.0 85.3
14. Unit service factor 100,0 100.0 78.9 L5. Unit availability factor 100,0 100.0 79,8
16. Unit capacity factor (Using MDC) 97.1 97.1 63,5
17. Unit capacity factor (Using Des.MWe) 94,6 94,6 61,8
18. Unit forced outage rate 0.0 0.0 6.2
19. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of each):
20. If shutdown at end of report period, estimated date of startup ___[_A________
  • The MDC nay be twer than 769 MWe dering periods of high ambient tenperatere due to the thernel perhrnance of the spray renal,

$ UNOFFICIAL COMPANY NUMBERS ARE USED IN THIS REPORT

1 i

OPERATING DATA REPORT DOCKET NO.

50-265 l

UNIT TWO DATEFebruary 7 COMPLETED BYAlex Hisak TELEPHONE 309-654-2241xi94 OPERATING STATUS 0000 010184

-1.

Reporting period 2400 013184 Gross hours in reporting period 744

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design electrical roting (MWe-Net): 709
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 0. 0_

0.0 77917.5

6. Reactor reserve shutdown hours 0.0 0.0 2985.8
9. Hours generator on line 0.0 0.0 75209.8
8. Unit reserve shutdown hours.

0.0 0.0 702.9 9.' Gross thernal energy generated (MWH) 0 0

155382088

10. Gross electrical energy generated (MWH) 0 0

49435780

~

ii.. Net electr1 col energy generated (MWH)

-524

-524 46333536

12. Reactor service factor 0.0 0.0 76.5
13. Reactor avo11ob111ty factor 0.0 0.0 79.4
14. Unit service factor 0.0 0.0 73.8
15. Ur.it avo11ob111ty factor 0.0 0.0 74.5
16.. Unit capacity factor (Using MDC)

.i

.i 59.i

17. Unit capacity.foctor (Using Des.MWe)

.i

.i 57.6

18. Unit forced outage rate 0.0 0.0 8.6
19. Shutdowns scheduled over next-6 nonths (Type,Date,and Duration of each):

20.-If shutdown at end of report period,estinated date o f s t a r t u p __2_ _1,@- 8,4____ __

8the MBC not be louer then 769 Inle dering perleds of high onblent temperature due to the thernel perfernance of the sprey tenel.

8510FFICIN. COMPM IUWERS ARE USED IN THIS REPORT

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-254

+

UNIT ONE DATEFebruarv 7 COMPLETED BYAlex Hisak TELEPHONE 309-654-224ix194 MONTH Janvarv 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net)

L.

559,8 17.

773.8 2.

710!D 18.

772.0 3.

784.9 19, 773.7 4.

783.1-20.

757.7 5.

784.9 21.

747.0 6.

774.9 22.

552.6 7.

791,4 23.

668.5 B.

624.9 24.

763.6 9.

725.7 25.

776.9 LO.

775.4 26.

786.1 110 784.8 27.

777.1 12.

747.8 28, 787.7 13, 789.6 29.

747.2 14.

780.9 30.

784,1 15, 765.8 31, 789.8 16, 780.8 INSTRUCTIONS On Q is forn, list the overage dolly unit power level in ille-Net for each day in the reporting nenth. Compete to the heerest whole a gewett.

Thew figeres will be esed to plot a graph for each reporting nenth. Note that when notinsn dependable capacity is esed for the ut electrical reting of the snit,In such cases,the average daily snit power output sheet should bethere 1881 11ae (or the restricted over level line).

- feetnoted to esplein the entenenely

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATEFebruarv 7 COMPLETED BYAlex Hisok TELEPHONE 309-654-2241xi94 MONTH Januorv 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (HWe-Net)

(HWe-Net) 1.

-3.3 17.

-i.3 2.

-2.8 18.

-6.3 3.

-i.9 19.

-0.1 4.

-2,4 20.

-7.3 5.

-3.0 21.

-6.6 i

1 6.

-3.2 22.

-7.4 7.

-3.0 23.

-7.4 8.

-4.i 24.

-6.8 7.

-4.3 25.

-7.4 LO.

-4.5 26.

-7.4 Li.

-4.4 27.

-6.8 12.

-4.9 28.

-4.4 13.

-4.3 29.

-4.6 L4.

-4,5 30.

-4.4 15.

-4.4 31.

-4.3 16.

-8.6 INSTRUCTIONS Or. this forn

. neDest uhele, list the estrege delly snit power level in IWe-ht for toch do; in the reporting nonth.Conpite to the negewett.

These figeres vill be esed to plot a graph for each reporting nenth. Note that when noninen dependeble capacitt is esgd for the set electrical reting of the snit there ney be occasions when the daily everage power level exceeds the 1951line (or the restricted sewer level line).,In sech cases,the average daily enit power setpet sheet sheeld be feetnoted to esplein the appeFent onenely

nn nn m

M 255 m

M Pl?J3 n

e REN FEP!5 A

n.n p

+

.J ID/5A APPENDIX D QTP 300-S13 IINIT SilllTDOWNS AND POWER REDIlCTIONS Revisson 6

' DOCKET NO.

050-254 August 1982 IINIT NAME Quad-Cities Unit One COMPl.ETED HY Alex Misak DATE-February 6, 1984 REPORT HONTil JANUARY 1984' TEI.EPil0NE 309-654-2241

~

8

~-

s w"

E a$$

"w Am Q

OyM I.ICENSEE 80 l'URATI ON M

M EVENT 5"

m u

'NO.

DATE (llollRS)

REPORT NO.

CORRECTIVE ACTIONS /CONNENTS A

84-1 840108 S

0.0-B 5

RC CONROD Reduced load for Control Rod Pattern adj us tmen t 84-2 840112 S

0.0 B

5 HA XXXXXX Reduced load to perform weekly Turbine tests 84-3 840115 S

0.0 B

5 llA XXXXXX Reduced load to perform weekly Turbine tests 84-4 840121 S

0.0 B

5' RC CONROD Reduced load for Control Rod Pattern adjustment 84-5 840129 S

0.0 B

5 IIA XXXXXX Reduced load to perform weekly Turbine tests t

5 i

APPROVED AUG 1 G 1982 I (final)

VCUbH

M M

M n

n n

p n

n M

M _I"55 E4 m

m D

E2"3 m

4,-

ID/SA ape'ENDIX I)

QTP 300-313 IINIT SilHTDOWNS AND POWER REDIICTIONS Hevision 6 DOCKET HO.

050-265 August 1982 UNIT NAME Quad-Cities Unit Two COHPl.ETED RY Alex Hisak I) ATE February 6,1984 REPORT HONTil JANUARY.1984 TEI.EPilONE 309-654-2241 e

~

j$

eu n

m x

O O

o, o M

I.lCENSEE mo hm n

o c

g DURATION d

EVENT g.

u NO.

DATE (Il00RS)

REPORT NO.

CORRECTIVE ACTIONS /CorlHENTS o

83-66 830904 S

744.0 C

4 RC FUELXX Unit Two remains shutdown for End of Cycle Six Refueling and Maintenance I

APPROVED AUG 1 G 1982

-I-(final)

V G U d tt

l' VI, UNIQUE REPORTING REQUIRD4ENTS The following items are included in this report based on prior c e mitments to the cm mission:

A.

MAIN STEAM RELIEF VP."E OPERATIONS There were no Main Steam Relief Valve Operations for the reporting period.

B.

CONTROL ROD DRIVE SCRAM iiMING DATA mR UNITS ONE AND WO There was no Control Rod Drive Scram Timing Data for Units One and Two for the reporting period.

VII, REFUELING INFORMATION 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.

6 8

4 i

p-ysyy-

,,,,m-

-y w

QTP 300-S32 Rr.visicn 1

~

QUAD-CITIES REFUELING Mtrch 1978

, (-

INFORMAT10N REQUEST l

1.

Unit:

Q1 Reload:

7 Cycle:

6 2.

Scheduled date for rext refueling shutdown:

3-11-84 L

3 Scheduled date for restart following refueling:

5-21-84 4.

Will refueling or resumption of operation thereaf ter 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 DLTA to 45,000 MWD /t.

I l

5.

Scheduled date(s) for submitting proposed licensing action and supporting Information:

Technical Specification change will be submitted February 15, 1984.

6.

Important IIcensing 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:

1) All new fuel assemblies will be GE78-type (barrier clad, extended exposure design).

2)

A gener~ic methodology was used for the analysis of the Control Rod Drop Accident and Rod Withdrawal Error events.

3)

The two Zirconium Barrier Lead Test Assemblies will be re-inserted to gather information on the effects 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 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:

3657 b.

Planned increase in licensed storage:

0 9

The projected date of the last refueling that can be discharged to the g

spent fuel pool assuming the present IIcensed capacity: 2003

-J~[

4PPROVED

-6 APR 2 01978 Q.C.C.S.R.

I qTP 300-s32 Rsvision 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 IIcense amendment:

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

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

June 14, 1983 (Scheduled) 6.

Important IIcensing 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:

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

2)

The use of impr~ved assumptions in the load reject without bypass analysis o

resulted in a much improved MCPR operating limit.

Technical Specifications are being changed to provide this additional operating margin.

T 7

The number of fuel assemblies.

a.

Number of assemblies in core:

724 p'

b.

Number of assemblies in spent fuel pool:

412 L

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:

3897 0

b.

Planned increase in IIcensed storage:

?

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

4PPROVED r --

1-APR 2 01978 r

[

Q. C. C. S. R.

.e

--e,-,

-n

---,p,,

y

-,----n ee

o 1,

- VIII, GLOSSARY

~

The following abbreviations Which may have been used in the Monthly Report, are defined below:

' ACAD/ CAM Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring.

4 ANSI American National Standards Institute

-Average Power Range Monitor APRM-Anticipated Transient Without Scram ATWS Bolling Water Reactor BWR Control Rod Drive CRD Electro-Hydraulic Control System EHC EOF Emergency Operations Facility Generating Stations Emergency Plan e

GS EP.

HEPA

, High-Ef ficiency Particulate Filter HPCI-

~ High Pressure Coolant Injection System High Radiation Sampling System

~HRSS Integrated Primary Containment Leak Rate Test IPCLRT Intermediate Range Monitor IRM-Inservice Inspection ISI

-LER' Licensee Event Report LLRT.

Local Leak Rate Test Low Pressure Coolant Injection Mode of RHRS LPCI LPRM Local Power Range Monitor 4

Maximum Average Planar Linear Heat Generation Rate i

MAPLHGR Minimum Critical Power Ratio

.MCPR' Maximum Fraction' Limiting Critical Power Ratio

~

MFLCPR Maximum. Pe rmiss ible Concent ration

- MPC Main Steam Isolation Valve MSIV '

National Institute for Occupational Safety and Health

.NIOSH Primary Containment Isolation PCI PCIONR

.. Preconditioning Interim Operating Management Recommendations RBCCW

. Reactor Building Closed Cooling Water System Rod Block Monitor RBM

- Reactor Core Isolation Cooling System RCIC Residual Heat Removal System l

}

RRRS RPS Reactor Protection System Rod Worth Minimizer RWM' SBGTS Standby Gas Treatment. System Standby Liquid ' Control

-SBLC Shutdown Cooling Mode of RHRS

.SDC Scram Discharge Volume SDV Source Range Monitor SRM ETBCCW Turbine-Building Closed Cooling Water System Traversing Incore Probe

-TIP TSC

. Technical Support Center i

4

>w s

4-, -,-

,wwp.y

,w..-

g

_,,,p9.y 9 gw w-vpwe.9-,pp q, y.y99,pg-,p9pqg y

g.-yp-9,..

9

+.

esn,,

.ewyy,,,,q5,w,-9-p h9-

-y

F

~

/

f~~'N Commonwrith Edison l'

n_

) Outd CitiIs Nucliar Pow;r Station

(

~, h 22710 206 Avinua North

\\

,' Cordova, Illinois 61242

(,_ /

Telephone 309/654-2241 NJK-84-43 February 1, 1984 Director, Of fice of Inspection & Enforcement United States Nuclear Regulatory Commission Washington, D C.

20555 Attention: Document Control Desk Gentlemen:

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

Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR POWER STATION P

')

N, J, Kalivianakis Station Superintendent bb Enclosu re I

Retrieved from "https://kanterella.com/w/index.php?title=ML20080N739&oldid=4379746"