ML20027D410

Monthly Operating Repts for Mar 1980

ML20027D410
Person / Time
Site:	Quad Cities
Issue date:	04/01/1980
From:	Beth Brown COMMONWEALTH EDISON CO.
To:
Shared Package
ML20027D409	List: ML20027D408 ML20027D410
References
NUDOCS 8211040256
Download: ML20027D410 (23)

Text

.__

I i

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l i

l QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 1

1 MONTHLY PERFORMANCE REPORT MARCH 1980 COMMONWEALTH EDIS0N COMPANY AND

.?

i IOWA-ILLIN0IS GAS & ELECTRIC COMPANY j

NRC DOCKET NOS. 50254 and 50-265 LICENSE NOS. DPR-29 and DPR-30 i

I j

hDR D

OM n

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TABLE OF CONTENTS 1.

Introduction ll.

Summary of Operating Experience A.

Unit One B.

Unit Two Ill.

Plant or Procedure Changes, Tests, Experiments, and Safety Related Maintenance i

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 Vlli. Glossary I

l l

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1.

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 towa-1111nois 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 u ted 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 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 pow r' began on February 18, 1973 for Unit I and March 10, 1973 for Unit 2.

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

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11.

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One March 1: Unit One began the reporting period holding load at 779 MWe. At 2200, load was reduced at a rate of 100 MWe/hr. until a load of 550 MWe was achieved at 0015 on March 2.

The load was reduced to this level to perform a control rod pattern change.

The weekly turbine generator test was performed and the main condenser flow was reversed.

March 2: At 0131 Unit One load was increased at a rate of 8 MWe/hr.

March 3: At 1445 Unit one load was leveled at 820 MWe.

March 4: At 0100 Unit One load was reduced at a rate of 100 MWe/hr. until a load of 685 MWe was achieved at 0200.

The load was dropped to change over condensate pumps and condensate demins. At 0216 the load was increased at a rate of 50 MWe/hr.

to 750 MWe. At 0300 the rate was decreased to 25 MWe/hr. until a power level of 775 MWe was reached. At 0331 tcad was increased at a rate of 8 MWe/hr. until at 0755 a load of 800 MWe was reached.

March 5-9: Unit One held an average load of 803 MWe.

A ~

2330 on March 8, load was decreased at a rate of 100 MWe/hr. to 700 MWe at which time the weekly turbine generator test and a control rod pattern change were performed. At 0200 on March 9, load was increased at a rate of 8 MWe/hr. until 1515 when the load was leveled at 806 MWe.

March 10-11: Unit One held a load of 814 MWe until 2305 on March 10.

At that time the load was dropped to 650 MWe at a rate of 100 MWe/hr to change over condensate demins.

The load was then dropped to 400 MWe to change control rod pattern.

The load was then increased at a rate of 50 MWe/hr. to 750 MWe, then 8 MWe/hr. to 815 MWe. At 1105, load was dropped to 725 MWe due to high differential pressure in the condensate demineralizer system.

March 12: At 0135, load was dropped at a rate of 100 MWe/hr.

to 645 MWe due to high differential pressure in the condensate demineralizer system. At 1235 Ioad was increased to 695 MWe.

March 13: At 0135. Ioad was dropped at a rate of 100 MWe/hr.

to 650 MWe to change over condensate demins. At 0430 the load was increased at a rate of 20 MWe/hr. for one hour, then 8 MWe/hr.

until a load of 812 MWe was achieved.

March 14-15:

Unit One held an average load of 813 MWe.

At 1000 on March 15 the load was reduced at a rate of 100 MWe/hr.

to 650 MWe. At this power the condenser flow was reversed, the weekly turbine test, monthly MSIV test, monthly Turbine stop valve test, and monthly turbine control valve test were performed.

March 16: At 0315, load was increased at a rate of 8 MWe/hr. untII a level of 794 MWe was reached.

March 16-23: Unit One held an average load of 795 MWe.

At 2230 on March 22, load was reduced at a rate of 100 MWe/hr to 650 MWe to reverse the main condenser flow and perform the weekly turbine test. -At 0630 load was increased at 8 MWe/hr. to 775 MWe at 0230 on March 24.

March 24-29:

Unit One held an average load of 770 MWe.

At 2200 on March 28, load was decreased to 550 MWe at a rate of 100 MWe/hr.,

at this level a control rod pattern change was performed.

At 0045 on March 29, load was dropped to 450 MWe to perform a control rod pattern change and change over condensate demins.

At 0255 the load was increased at a rate of 8 MWe/hr. At 0900 this rate was reduced to 5 MWe/hr. to reverse the main condenser flow.

March 29-31: Unitoneloadwasincreasedatarateof5MWefh.r.until at 0000 on March 31 the rate was increased to 8 MWe/hr.

At 1430 on March 31, load was leveled off at 813 MWe.

B.

Uni t Two March 1-31:

Unit Two remained shutdown for End of Cycle Four

^

Refueling Outage.

Ill. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.

Amendments to Facility License or Technical Specification On March 20, 1980, Amendment No. 51 to License DPR-30 was issued for Quad-Cities Unit 2.

This amendment authorizes changes to the plant Technical Specifications to support review of future reloads, under provisions of 10 CFR 50.59 It also modifies license condition 3.C. to assure a conservative MCPR operating limit during coastdown operation.

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.

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 du, ring the reporting period.

The headings indicated in this supary include Work Request Numbers, LER Numbers, Components, Cdu'se of Malfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

I i

MAINTENANCE

SUMMARY

UNIT nur CAUSE RESULTS & EFFECTS ON ACTION TAKEN TO W.R.

LER OF.

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION q0 3758 1A1 24/48V The float-equalize The float-equalize timer The potentiometer was battery charger timer had a bad switch did not function cleaned and the charger potentiometer.

properly.

Battery sys-was tested.

tem was operable, as was alternate charger.

q03722 80-05/03L IB MSIV The exhaust res-The valve would not The solenoid assembly, (1 -203-1 B) trictor was plugged. close after the control pilot valve assembly, and switch was operated.

exercise valve were replaced.

The unit was cleaned. The exhaust restrictor was re-installed.

The valve was stroked and timed.

403985 80-08/03L 1/2 D.G.

Fuse holder F24 The D.G'. would not The fuse holder was tightenec (1/2-6602) was loose start from the control and the D.G. was tested.

room. Unit One D.G.

was operable and off-site lines were available.

QO 3984 1/2 D.G. Oil The casing was The oil filter housing The casing was repaired.

Filter Housing cracked.

was leaking.

D.G. was operable.

Q0 3615 80-07/03L Main Steam Line The monitor was The monitor,'was reading The monitor was calibrated Moni tor (1-1705-out of calibration.

Iow.

Other' monitors and tested.

2B) were operable.

M 9

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l UNIT Two MAINTENANCE

SUMMARY

CAUSE RESULTS G EFFECTS ON ACTION TAKEN TO W.R.

LER OF.

NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO3275 Solenoid valve The solenoid valve The 2-1601-23 valve The solenold valve would not open.

Unit was rebuilt and stroked (2-1601-528) was worn..

was shutdown for refuel-three times.

Ing.

QO3705 79-27/03L RCIC Steam Supply The valve seat The valve failed LLRT.

The valve was replaced valve (M0-2-1301-was defc,rmed.

MO-2-1301-17 had and tested for operability.

16).

satisfactory leakage.

QO3908 80-05/03L Timer 10A-M2B The spring tension The tirer's clutch The spring tension on the clutch was

.cs.:ct engag;ng.

was adjusted and the out of adjustment.

Timers 3B and.4B timer was tested.

were available.

QO3909 80-08/03L Timer 10A-M1B The micro-switch The terminals 8 and 9 The micro-switch was on the timer was on the timer did not adjusted and tested.

out of adjustment.

pick up.

QO2075 79-27/03L 1B MSIV The valve was worn. The valve failed-LLRT.

The valve was overhauled and (2-203-1B) tested.

QO2863 80-01/03L SBLC Relief Valve The valve wa's,out The valve actuated at The valve was lapped, (RV 1105A) of adjustment.

too high of a pressure.

adjusted, and tested.

QO2921 80-01/03L

.SBLC Relief Valve The valve was out The valve actuated at too The valve was adjusted and (RV-1105B) of adjustment.

high of a pressure.

tested.

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s :s g

UNIT TWO IMIMTENANCE

SUMMARY

CAUSL ltLSUL~l S G Ll'l LCI S W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION QO 3329 D.G. cooling water A stud was broken.

The locking mechanism The stem, bearing, stud shaft would not lock.

D.G.

and sleeve were replaced.

F 1.

Dezurik valve 4

(2-3907) cooling was not

.through the heat exchanger compromised.

was verified when the D.G.

was running.

QO3752 Control Rod C-G.

The velocity limit;- Water was leaking The control rod was

~

er was leaking.

through while changing replaced and tested.

a control-rod drive.

QO 3806 &

CRD P-5 and C-9 The scram inlet The drive failed. cold The scram inlet valve was 3807 valve was out of scram timing.- Unit adjusted and the drive was adjustment.

shutdown for refueling.

. scram timed.

QO3936 RHR shutdown The breaker was The valve would not The circuit was modified and cooling valve.

burned.

operate. Unit was shut-the valve was stroked (2-1001-50) down for refueling.

three times.

QO 3992 LPRM 48-090.

The cabic_ connector The LPRM was spiking The cable connector was was bad.

high. The other LPRMs replaced and calibration were operational.

was verified.

Qo0630 79-17/03L D.W. to Supp.

Relay CR 120HCJ02 The vacuum breaker did The relay was replaced and chamber vacuum in circuit for not give.a red light the circuit was tested.

breaker (2-1601-2-1601-32A"was or alarm on~Div. 1.

32A) bad.

The other vacuum breakers were available.

/

M 6

I L

UNIT TWO MAINTENANCE

SUMMARY

i

~

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT HALFUNCTION SAFE OPERATION PREVEMT REPETITION Q01253 79-22/03L D.W. to Supp.

The Limit switch The vacuum breaker did The limit switch was adjustec!

chamber vacuum was out of,

not give a full open and the vacuum breaker was breaker (2-1601-adjustment.

indication.

The other tested three times.

328).

vacuum breakers were

)

available.

1 QO2090 79-27/03L F.W. Check valve The valve was The valve failed The valve was rebuilt and valve (2-220-62B) worn.

LLRT.

tested.

QO3877 2-1601-21 valve The valve The solenoid valve The actuator was rebuilt (50-2-1601-21) actuator was was leaking. Valve and the valve was tested worn.

was still operable.

and timed.

QO 2073 79-27/03L MSIV The valve was The valve failed The valve was overhauled (2-203-1A) worn.

LLRT.

and re-tested.

l Q0 2310 D.W. and particu-The valve was The ASCO valve was The valve was rebuilt and j

late sample valve worn.

leaking. Valve operated and checked j

(AO-2-8803) operability was not for leaks.

O affected.

Q0 3537 D.G.

(6600)

The oil seaf was Oil was leaking around The oil seal'was replaced an:

worn.

the scavenge oil pump the D.G. was tested.

i shaft.

404198 80-07/03L Beam on pump The beam was found The jet pump remained The beam was replaced.

16 (201-2-36) defective during intact.

Other jet pumps i

inspection.

were inspected to be f

l satisfactory.

4 I

i 1

m UNIT Two MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER 0F ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION.

PREVENT REPETITION q0 4264 80-09/03L TIP machine #2 Relay KA-477B The machine did not The relay was replaced withdraw and isolate and the machine was tested.

(2-700) was bad.

on a Group 11 Isolation signal.

9 9

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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.1. and 6.6.B.2. of the Technical Specifications.

UNIT 0NE Licensee Event Date of Report Number Occurrence Title of Occurrence 80-06/03L 2-22-80 RCIC Steam Valves 1-1301-16

^

and 17 found in the closed position.

80-07/03L 3-8-80 Steam Line "B" Rad Monitor setpoint drift.

80-08/03L 3-8-80 1/2 Diesel Generator failed to start from Control Room.

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UNIT TW0 80-05/03L 3-3-80 RHR Timer 'A' Loop 10A-M2A failed to actuate Relay K21A.

80-06/01T 3-8-80

'A' and

'B' Core Spray Line crack indications.

80-07/03L 3-16-80 Jet Pump #16 Beam Assembly Failure.

80-08/03L 3-5-80 RHR Timers 'B' Loop 10A-MIB and 10A-M2B failed to operate.

80-09/03L 3-22-80 TIP Machine #2 failed to isolate.

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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.

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 during the reporting period.

B.

CONTROL R0D DRIVE SCRAM TIMING DATA There were no control rod drive scram timing operations during the reporting period.

"k Vlil.

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.

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i OPER ATING DATA REPORT

~- DDCl(ET ND.

50;254 UNIT ONE April 1, 1980 DATE 1

COMPEETED'Tr BeckTBrsn TELEP' HONE -

309-654-2241,

- Ext.- 245

~~

OPERATING STATUS 0000 030180 iT Reporting perlTdi2400 033180 Gross hours in reporting period:

744~

2. Currently authorized power level'(MWt): 2511 Max'. Depend capacity (HWe-Ne~tW769*~ Design else tr'ical rot Ang (MWe=Ne tTi 789.,

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

~

4. Reasons for restriction (if any):~

~ ~~ - -

thTs Month fr to Do~te UUHUTotIWe"

- _ 5._N_ umber of hours reactor was critical 744.0 2184.0 56898.1 b.

Reactor reserve shutdown hours 0.0 O.IT

'3421.9 R W ~ Hours generator on IT5e 74~47U 2184 T ' ^ 54224T9" l

8. Unit reserve shutdown hours.

0.0 0.0 909.2~

t

9. Gross thermal energy generated (MWH) 1709686 4989236 109533217.

~

561570 i~637457

.5826V51f 10~. Gross electrital~~ energy TfEnerated(MWHi

~

t ii. Net electricci energy generated (MWH) 529713 1556629 32972165,

12. Reactor service factor. _

3 -

100.0 100.0'

'82.3

13. Reactor avallab111ty foctor i~00TO f00 0 8772 -

~

-~

14. Unit service factor 100.0 100.0 78.4

.. +%c

15. Unit avo11ob111ty factor CP 100.0 C" 100.0.

79.7

~ ~- 67 utilTc ap acit y f ac t or (Usl'Rg HDC>

9 0-~2 90T3 60 f i

17. Unit capacity factor (Using Des.MWe');

92.6 -

92.'7

~

'62.0:

2-0.0 T

0.0_ ~~

7.9'

18. Unit forced, outage rate

.; x.- 7 g.

m

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

~

~-

~. V,

. x -

h 2_0. If shutdown at end of' report period,esiinated'date of storIup-l 8-NA P.

: 9, 7.:.,...

n

m. mg.m,;2 v

.m

~

• The IOC nef e louer then 769 IWe dering periods of high'edient tenperatere doe " / [

""NQ, ;; /M

~

b ta _the thernal perfornonce_of the sprey_ceneli

• v

~ *

' < ^ '

+

c -

M

" r".;"

~

, J.a. '.

y

p,.

e

..m -

,., 7 j.

9,' p. 7; 4

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=_

l OPERATING DATA REPORT DOCKET NO.

50;265

~ ~ '

~

+

4 UNIT

~TWO x

DATE April 1. 1980

]

COMPl.ETED sT tsERTBi oWn 1

' TELEPHONE' 309-654-2241.

" ' ~

'~

Ext 7 24)

OPERATING STATUS 0000 030180 h44 i-- Rep or t Ang perTidT2400U33180 Gr~oss h ours-In7eycetTrng ptrTod i

.s,.

y.

+

a.

. :t.

x,

., -. x.

na,

2. Currently authorized power' level (MWt):'.2511. Max. Depend capacity'.._

-~--(MWe-Ne t )T 769* Design elec tr1 col ~ rating-(MWe NetTI-789 j

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

4.

Reasons for restriction'(if any):.

4 l

~ '.

Inis Month f rTt'o Da t e-C u n uTo tTv e'*-~

5. Number of hours reactor was critical 0.0 0.0 53128.9 ~

____.s

~

_ O. k,'\\,

6.

Reactor reserve shutdown hours 0.0 2985.8

~77 Hours generator onhlife 07 u0

'50791TB -

0.0 0.0 702.9 8.

Unit reserve shutdown hours;'"

.Grossthernalenergygeneoted(bH)~

'0' 0

103016109-

^

9.

e e

H ~i'0-~~ Gross electricol energy generated (MWH) 22 49

.52863099-~

t.

ii. Net electrical energy generated (HWH).

-10501

-37666~

30704859 r-

l

.o 0.0

O.'O 77.8

12. Reactor service factor

13. Reoctor avallobillty factor DT0 070 82 2~~~

1_4_._U_n_i t_ s e.r_v ic e f ac t o r 0.0'.

0.0 74.4-L5. Unit avo11ob111ty factor!-

.w..,_.

.~.

.. :. 75,4

'O. 0.0 s

.c_

- ~ T6~~ Uril t copHcItp fdctor (Using HDC) -

-i.e

-2.2 57 O~

n ;r

~

-2.2-58.5.

'i.B

17. Unit capacity factor (Using' Des.MWe)'

y n.-

m.

~ 3.,_

 :;~

< ; ~ ;:p t 0.0, 9.2

18. Unit forced outage rotel.,;, M. ; ~ ~ ~ L. '

~0.0~

s 5.

H.i A,:.

. y ;, ~, sr> : c;~,

. \\ -

,e;, y. ;.. ;,,

~ 6 nonthi-(Type,Date,and DUiration of eacN):. _

19'- ShiitTowns schediiiled over next

-...w

.r..

m m

5

~~=

.a.

20. If shutduwn at end'of r'eport ~p e r i o d ', e s t I no t e d d a t e. o f s t a r t u p __4.-21_- 803._,,,

-.

• qu y.

,- ; g ;;.; w. y

, g. p;. g l.

~"

< g M 7.'

8The IGC nor be louer then 769 leie dering perleds of high ombient tenperators, dee ;;ypf-

, i % ^ W+i'.-l C...

'te the thersel perfernance of the sprey canal.h ' MN:

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aL

++.

I T

+19*

N 4

a p.

$ a%?

._E YD $*l, e ';.e, Y 'u

- -, = s, w c 32 ;;. m ;. a q,. >,;

- ^- $

Y

&{.N.bh

• N

_..*I'% 1h

'Y.

, __ _ " ~

I APPENDIX B i

AVERAGE DAILY UNIT POWER LEVEL w,.e.

we

• ~ee.4m.*ww-====

-*-e-

., -e

• w.de wM e

-.-..-e e+e DOCKET NO.

50-254 UNIT ONE DATE April 1, 1980-7 1

COMPLETED BY Becky Brown TELEPHONE 109;654;2241.

Ext. 245 HONTH March 1980 e..

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

~

(MWe-Net) 1.

719.3-17.

775.6 2.

~

597.6 18, 746.5 j

i 3..

737.5 1.9.

737.8 4,

755.5 20.

731.9 5..

756.5 21.

-728.6

\\\\.

6.

.765.4 22.

716.9 7.

773.9 23.

644.8 8.

741.5 24.

732.6 9.,

746.7 25..

703.3 10.

755.0 26, 728.5 11.

693.0 27.

705.8

__12 655.5 28.

689.9-1 13.

703.8 29.

483.3

=

14.

766.6

-30.

594.0 15,_

~753.3 31.

718.7' ~

i 16.

711.3 INSTRUCTIONS On this forn, list the average daily enit power level is ille-Het for each do; in the reporting neath.Conpite to the' nearest whole ne awatt.

These figsres vi 1 be ssed to plet-e y,oph for-each reporting nenthrNete-thet-when-aorinen-dependeble-capacit s

used for the net electrical rating of toe snit be occasions when the daily everage power level excee the illI line (or the restricted power level line),there not.In such cases,the overage daily snit power estpet sheet s c-t festnoted to explain the apparent unently q

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./

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s g

3 l,.'*.'

i___

. n.e..'. ry.-

~

.y c> g, n 3

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL t

i DOCKET NO.

50-265

~

UNIT

-TWO

~

DATE April I, 1980 COMPLETED BY Becky Brown TELEPHONE 30926 F 2241, 5

Ext. 245 MONTH March 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL'

~

(MWe-Net).

~

{_.

~(MWe-Net).

i.

-17.4 17.

-24.0

.2.

-20 i ~

~

18._

-19.5

~

~

L

-21.1 if.

-12.3 4.

-19.2 20.

-5.2 5.

-19.3

.21.

5-3.0

\\ '.

6.

-21.8 22.

-3.3-7.

-21.5 23.

-4.1 8.

-20.1

~

24.

-4.4 9.-

-21.4

. 25.

-5.0 4

(

10.

-20.0 26 '.

-4.6.

11.

-22.3 27.

--5.0 12.1_

-19.9 28.

~

-5.1 l

13.

-21.4 29.

--5.3 14.

-22.7' 30.

-5.3 15,

' -22.0 31.

-5.i'

~

^

16.

-19.6 INSTRUCTIONS' '

/

On this forn, list the seerage daily snit power level in Ille-Met for each day in the reporting nenth.Conpete to the,; --

seerest whole negavett.

s -

These figeres will.be-esed-te plot-a graph for-eech reporting nonth.-Mete thet-when no inen4ependabletapacite Is

^

esed for the net electrical rating of the snit there nep be occasions when the daily everage power level e.'ceels the ill! line (or the restricted power level line),In such cases,the average daily snit power setpet sheet sheeld be :

c festnoted to explain the opperent onently

~#

p 4

, =

I g..

,,,s7~-

.--3

. a.-

u.

~

1-

- x;

n. -:

,~.

s

.o 24,

- 4,9..,

sy.

4

~,e*

.f

.1 l

_ ;- ~ Q..,

3

~

~

l

~

n ns r

r r C

e ee t

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F.evision 1 Harch 1973 QhAD-CITIESREFUEllllG

.I' JMFORMATION REQUEST

(

.1 Reload:

5

_ cycic:

6 s.

.1.

Unit:

8_qCan.(sw,,Q, n (EOC5)

Scheduled date for'next refueling shutdown:

~

2.

12-7-80(Startuo BOC6) scheduled date for restart following refueling:

i

~

3 i

l 11111 refueling or resumption of operation thereaf ter require a tech

~

4.

specification change or other license amendment:The review will be conducted for future cycles of Quad Cities Unit 1.

~

in June, 19BO.

scheduled date(s) for submitting proposed. licensing act' ion and supporting June,1980 for.100FR50.59 related changes ~ m 90 days 5

Information:

-orior to shutdown.

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

' different fuel desig'n or supplier, unreviewed desig'n 'or performance snalys s 6.

methods, si..nificant cisanges in fuel design, new operating proce ures-d New fuel designs:

Retrofit 8x8' fuel 2.65 w/o% (^- 224) f o

(

)

~

7.

The number of fuel assemblies.

724 Number of assemblies in core:

a.

596 Number of assemblies in spent fuel pool:

b.

The present licensed spent fue1 pool storage capacity and the size of any

~

increase in licensed storage capacity that has been requested or is planned 8.

in number of fuel assemblies:

1460 Licensed storage capacity for' spen't fuel:

a.

. ~.

None b.

Planned increase in licensed storage:

refueling that can be ' discharged to the 9

The projected date of the last pent fuel ool assuming the present licensed capacity: Septeinber, 1985 end of ba ch discharge' capability)

. EPPROVED

..I APR 2.01973 -

• C Q.C.O.S.R.

e

QlP JOU -:>JZ Revision 1 ilarch 1973 4

QUAD-CITIES REF'JELIll,G

.s INFORMATION REQUEST i

(-

y 2-2 Reload:

4

_ Cycle:

5 1.

Unic: _

11 4'-79 (Shutdown EOC4)

Scheduled date for next refueling shutdown:

2.

1-17 80 (Startuo BOC Sche uled date for restart following refueling:

3 Will refueling o'r resumption of operation thereaf ter require a technical' 1;.

No, Plan 10CFR50.59 Reloads specification change or other license ' amendment: The review will be conducted-for future cycles of Quad Cities Unit 2.

by early September, 1979 3.

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

Early August,1979 for 100FR50.59 related changes go 5

Information:

l days prior to shutdown.

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

I

6. ' different fuel desig"n or supplier, unreviewed design 'or performance snalysis P

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

Retrofit 8x8 fuel (180)

,j New Fuel Design:

nat. U at bundle top and botto:a

.s t

b))/l two larger water rods

}

^

a i'

new enrichment distribution

~

c J-d) prepressurized

~

This fuel design was 'previously used for Quad Cities Unit 1 Cycle 5 l,j 4

and Dresden Unit 2 Cycle 7

?

'I 7

The number of fuel assemblies.

724 Number of assemblics in core:

a.

l 492 Number of assemblies in spent fuel pool:

b.

The present licensed spent fuel pool storage capacity and the sitze of any

. l S.

increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

1460 Licensed storage capacity for' spent fuei:

l' a.

None I

b.

Planned increase in licensed storage:

The projected date of the last refuelinD that can be discharged to the licensed capacity: March,' 1986 9

spent" fuel pool assuming the present

?

(End of batch discharge capability)

XPPROV.ED l 4 hPR 2.01973

[

l- "Q.C.O.S.R.

e i

..y..

m

("

Vill.

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

Control Rod Drive System CRD SBLC Stand-By Liquid Control System MSIV Main Steam isolation Valve Residual Heat Removal System RHRS RCIC Reactor Core isolation Cooling System HPCI High Pressure Coolant injection System Source Range Monitor SRM IRM Intermediate Range Monitor LPRM Local Power Range Monitor APRM Average Power Range Minitor TIP Traveling incore Probe k'

RBCCW Reactor Building Closed Cooling Water System TBCCW Turbine Building Closed Cooling Water System RWM Rod Werth 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 Bolling Water Reactor In-Service inspection ISI MPC Maximum Permissable Concentration N

Primary Containment isolation PCI Shutdown Cool'ng Mode of RHRS SDC Local Leak Rate Testing LLRT Maximum Average Planar Linear Heat Generation Rate MAPLHGR Reportable Occurrence R.0.

Drywell DW Reactor Rx Electro-Hydraulic Control System EHC MCPR Minimum Critical Power Ratio Preconditioning Interim Operating Management PCIOMR Recommendations Licensee Event Report LER American National Standards Institute ANSI National Institute for Occupational Safety and NIOSH Health Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Monitoring k