ML20236E216

Monthly Operating Repts for Aug 1987

ML20236E216
Person / Time
Site:	Quad Cities
Issue date:	08/31/1987
From:	Robey R, Schmidt K COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RAR-87-41, NUDOCS 8710290126
Download: ML20236E216 (20)

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QUAD-CITIES NUCLEAR POWER STATION.

UNITS 1~AND 2 MONTHLY PERFORMANCE REPORT AUGUST. 1987..

COMMONWEALTH EDISON COMPANY.

AND IOWA-ILLINOIS ~ GAS & ELECTRIC COMPANY

~NRC' DOCKET'NOS, 50-254.AND 50-265 1

LICENSE'NOS. DPR-29 AND DPR-30 l

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TABLE OF CONTENTS-

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1.

. Introduction 4

.II.

Summary.of Operating Experience A.

Unit On'e 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 NRC Approval C.

Tests and Experiments' Requiring NRC Approval D,

Corrective Maintenance of Safety Related Equipment u

1 IV.

Licensee Event Reports 1

i V.

Data Tabulations A.

Operating. Data. Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions VI.

Unique Reporting Requirements 1

A.

Main. Steam Relief Valve Operations J

B.

Control Rod. Drive Sr, ram Timing Data 1

VII.

Refueling Information VIII.

Glossary

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4 1

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INTRODUCTION.'

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g Quad-Cities Nuclear Power Station is composed'of two Boiling Hater s

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.a Reactors,eachwithlhMaxillumDependableCapacityof769MHeiNet,locatedin

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'Cordova,' Illinois.

The Station'1s jointly owned by. Commonwealth Edison

l Company and Iowa-Illinois Gas & Electric Company. 'The Nuclear Steam Supply j

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LSystems are General Electr)ic Company Boiling Hater Reactors.

The 1

N gp Architect / Engineer was Sargent & Lundy, Incorporated, and the primary 1

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0 construction contractor was United Engineers & Constructors.

The'. Mi s s i s s i ppi -

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River h thc c$vd6psgr cooling water source.

The plant is: subject t'o license-i g

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.Q numbersJ0PR-29,and OPR-30,.4ssued October 1, 1971, and March 21,'1972, 7':,' f.

'x, respectively; pursuant tc.00t.kat Numbers 50-254 and 50-265.

The date of 4,e 4

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4 U, '( *" ' i n i t i a l. Reactor'criticalit,1"es for Units One and Two, respectively were.0 s

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18, 1971, and April 26, 19721 Commercial generation of power began on February 18 -1973 for~ Unit One and March 10, 1973 for Unit Two.

ithis repo'rt was compiled by Verna Koselka.and Kurt Schmidt, telephone 3

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.s k - number 309-654-1241, exter'sions 2240 and 2147.

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SUMMARY

OF OPERATING EXPERIENCE' 4

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A. 'dnit One 4

' August'l-15

(

Unit One' began the month holding load. At 0130 on August 1 a los'd-reduction to 'a minimum of 500 We was ? initiated. co facilitate a control rod pattern.

adjustment. :Following the pattern adjustment.a. slow load ascent was begun at'0530'and continued until 1125 on August.2 when more required rod move-iments caused a. slight load reduction.'.The load ascent'was resumed at 1200 and continue 6lunt11 1250 on August.3.. Load was held at 788 We until 2203.

Load was reduced to 589 We by. 2305 in order to reduce the downstream river 1

-temperature.-to'below 86 F.

' Reduced load was held until 1140'on' August 4 i

' and this raised to 720 We by 1230.. A' slow load ascent continued and the unit reached full load at 0400 on August 5.

Full load was held until August 8.

At 0045 a load reduction to a minimum of 550 We was performed E

.to allow control" rod, pattern adjustments. The pattern adjustments were performed from 0255 to'0355.and.atl0422lan ascent to full load was begun.

Full load was achieved at 2140 and held.until 0550 on August 9.

Power was reduced rapidly by reducingLre' circ pump speed to minimum. A condenser pit

.high level alarm'and a report of water leakage under the main' condenser led operators to believe that there was a major leak from the condenser hotwell. At 0620 it was discovered that a fire suppression deluge for the a

main ~ turbine number'8 and 9 bearings hadsbeen. actuated and was flooding these bearings. Power was further: reduced with control rods at 0630 to prepare 31 for-tripping the turbine' At 0635 it was determined that the fire suppression j

actuation had been spurious, the deluge' water supply was isolated;and the leakage:below!the condenser veriffid to be stopped. At 0650 the oil returns-from bearings 6, 7, 8 and 9 were checked and determined not to be water q

j contaminated. A slow power ascent was begun at 0812 and continued until

-l full power was~ reached on August.12 at 0030.

Full load was held until

)

2145 when power was reduced and the unit placed in EGC at 2205. On

-August 13,'a reserve emergency required EGC to be tripped at 0735 and the unit raised to full load which it held until 0540 on August 16.

August 16-31 At;0540 on August 16, load was reduced and the unit placed in EGC at 0600.

.At.1635, EGC was tripped and a power ascent started. The power ascent was stopped at 2325 and'at 2345 the unit was returned to EGC.

ECC operated with only minor interruptions until 0255 on August 19.

Load was reduced for load following to a minimum of 613 We at 0335 and held until 0450 when La power ascent was begun.

Full load was reached at 1130 and held until 0130 on August 20.

Load was reduced and the unit placed in EGC at 0200.

EGC was operated until 1755 on August 21.

A scram of Dresden unit II 0027H/0061Z L

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caused-a reserve emergency'and EGC was tripped.- The unit was returned to-EGC at 1853 and taken.back'out of EGC at 1935. A subsequent load ascent was stopped at 2000.and power held at 786 MWe until August 22.

At 0020 a load reduction was initiated to facilitate control rod pattern ' adjustments a minimum of'500 MWe was' reached at 0212. Rod movements were completed at 0413 and a slow load ascent' begun at 0450. The load ascent was halted on August 23 at 0300. Load was held at 655 MWe until 0330 on August 24 when the load ascent was resumed.

The ascent was stopped and load held-at-735 MWe from 1950 until. August 25 at 0100. The load ascent raised power to_760 MWe by 0720; this_was held until 1130 when the ascent resumed.

Full load'was finally reached on August-26 at 0620 and held until August 29_at 0850. Load was reduced and the unit placed in EGC at'0930. Except for short interruptions, the unit ran in EGC until'0800 on August 31.

The unit was taken out of EGC due to a failed open recirculation valve on the i

1B reactor feed pump. Load was held at the EGC low limit (730 MWe) for the remainder of'the day.

B.

Unit Two August 1-31 Unit Two experienced a reactor scram at 1422 on August 1.

The scram was' caused 'by a failed main output transformer. The reactor was placed in cold shutdown and remained shutdown for the entire month while a transformer

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replacement was in progress.

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III.

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

A.

Amendments to Facility License or Technical Specifications Technical Specification Amendments 102 and 99 were issued on August 6 to facility operating licenses DPR 29 and DPR 30.

These amendments incorporate operability and surveillance requirements for the common unit 4 KV bus cross tie into TS 3.9/4.9 (Auxiliary Electrical Systems). The necessity for these additional TS requirements came as a result of an event at Dresden 2.

B.

Facility or Procedure Changes Requiring NRC Approval There were no Facility or Procedure changes requiring NRC approval for the reporting period.

C.

Tests and Experiments Requiring NRC Approval There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Corrective Maintenance of Safety Related Equipment There were no Deviation Reports or License Events Report associated with the Safety Related Work Request Log this month for Unit 1 or Unit 2.

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IV.- LICENSEE EVENT REPORTS ~

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EThe:following is a. tabular summary'of all licensee event reports for Quad-Cities Units One and Two' occurring during the reporting period, pursuant

to the reportable occurrence reporting requirements as~ set forth inisections 6'.6.8.1. Land 6.6.8.2. of the Technical Specifications.-

UNIT'l' Licensee Event Report Number!

Date Title of' Occurrence 87-017

.8-5-87 HPCI Group IV-Isolation - ESF' 1

UNIT.2 87-009 8-1 Reactor Scram T/G:

load mismatch l-PSE 87-010-8-17-87 Rdacto'r Scram while SD -

while draining H 0.to torus -

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V.

DATA TABULATIONS.

. The following data'_ tabulations are_ presented in.'this-' report:

'A.

Operating Data Re' port:

~~B.'AherageDaily'UnitPowerLevel C. ~ Unit Shutdowns and P6wer. Reductions i

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,..TAPPENDIX;B:

! o - a-AVER AGE DAILY ' UNIT! POWER LEVEll' 99 4

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- DOCKETLNO.---50-254

-. UNIT

.,_,_,_$ NE :

DATEj0f_S,.Ef,I_19,97'

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COMPLETED ' BYK11,R1,A SCHMIDT' s

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TELEPHONE 3,09,-fa5,_4 ;2241 MONTH;,___ _ A u cLu s t' i 90'/

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DAY. AVERAGE DA.ILY: POWER' LEVEL DAY AVERAGE DAILY. POWER' LEVEL.

(MWe-Net)

- ( MWe-Ne t )-

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462 8' i7.

726,2_4, 3

2.;

720,7 18.

7,0 5,,d?

3,--

~634,3 19.

'731;6 4 f.,,, _ _

,_,,,6_38,0 20.

741',9 5,-

779,9 21.

71 f. 2_

6. -...,

7,44,0-22, _,,,,

5 5 6.3 _,, _,_,_

2 7 J, -

-749;7 23,

____,,__,,,,,,.,,630,7_,,,,,,,,,_.

8,'..,,,,_,,,.,,,-

7 0 4, 0,,,_,

2 4.-

66i',7' 9.

545,2 25.

736,8 10 '.

-616.8

,26.

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'11.

690.4 2 7.,__ _

'770,'S-

- 12. -

773,0 28, 787.9

ii3, 7_5.2,9 29.

734.2

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763,2 30,

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77i,3 3i, 704.1

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' INSTRUCTIONS i

- On this forn, list the everage daily enit pewt level in Me-Net for each day in the reperting nenth.Conpete to the nearest whole negewett.

~ These figeres will be used to plet's graph for each reporting month, Note that when notinen dependable capacity is used for the net electrical rating of the snit there not be occasions when the delly everoqe power Itvel exceeds the

- 1H1 line (or the restricted power level line),.In such cases,the overage dolly snit power evipet sheet should be

.festnoted to esplein the opperant onently

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. APPENDIX'B-

• AVERAGE DAILYJUNIT POWER LEVEL.

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DOCKET.NO.,_

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i DATE10 St!PT'1907 C 0 M P L E T E D B Y K U R,J,.. A_,S,.,, il.til D T. _,_

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MONTH _,,,_,,_

A u u t,Lqt _ i_987

. DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWE'R l.EVEL.

(MWe-Net)

(MWe-Net) 17 1. '..

_447.7

17..

-7.0

.2.

-12, i '

18.

-66,

3..,

-11,1 19.

-74.2

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-- 2, 9 '

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-10,0 21,

-10,7-6 '.

-10,3 22,

-7,4' 7.:

10.3 23,

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-10,6 24.

-- 7, 0.

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-10.4 25,

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-7.2 INSTRUCT 10NG On this forn, list the overage dolly snit power level in MWe-Net for each day in the reporting month, Compete to the neartst Whole negawatt.

These figures will be used to plot a graph for each reporting nonth. Note that when noninen dependable capacity is estd for the net electrical roting of the Unit,there may be occasions when the dolly overage power level exceeds the 1H1 line (or the restricted power level line).In such cases,the overage daily unit power output sheet sheild be footnoted to explain the apparent anonely 1

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,j OPERATING DATA REPORTL q

LDOCKET NO.

7, 5.0. 2. 5 4'~

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) UNIT; ONE 1

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. D A T E 1.4,,,,S E P T -17 8 7,_ _,.

COMP L ETE D BYli,, A - SC.ljMDT.

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. TELEP HONE 3 0 9-654-2J4_i' 0PERATING STATUS 0000 080187

.1, R e p o r t i n g p e r i o d i i,g' } 0 0 083,M17 Gr o s s h o ur s i n r e p o r t in g ' isc r i o d i..,'/.,44.

ci 2.

Currently authorize,d power level (MWt): J 2511' Max. Depend capacity'-

(MWe-Net): 76'7* Design electrical' rating (MWe-Net)i 789

3. Power level;to which restricted (if any)(MWe-Net).NA 4.

Reasons'for' restriction (if any):

1his. Month Yr.to Date Cumulativ

5. Number-of hours reactor was crit.ical 744.0 5768.6. '108581 3

6.

Reactor reserve shutdown. hours 0.0.

0.0

..,,,, 3421,,

7..

Hours generator on'31ne 744.0,

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,, 1 0 1 0 6 2,,,,

8, Unit reserve shutdown' hours.

0.0.

0_. 0

._, 7 0y 9.

Gross thermal energy generrated(MWH) i'70.0Q.38.,,

__,.11.569223;

,,,2,, 22f. 22,.(,14 10, Gross elec trical - ener;;y generated (MWH).

550745 4445198' 72198503

11. Net electrical energy generated (MWH) 524318

-4247641' 3, 7,6 9 4 8 4

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.12.'Retactor nerv. ice factor 100.0_

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13 Reactor availability factor j 0,Q 2 0 98.9-83.

14. Unit. service' factor 100.0 9 0. 7.,

70. l

15. Unit avu11 ability factor

_i_g 0_, 0 98.7 79.j

16. Unit cupacity factor (Using MDC)

...,_,_fi.6

,? 4_,2 65, i

17. Unit capacity factor (Using Des.MWa) 89.3 92.3 6 3.-

.18 ', Unit forced o u t a g e-res t e 0.0

.5 5,, l Duration of each): l iY. Shutdowns scheduled over next 6 months (Refueling and Maintenance, September 1, lh87,(T pe Date$and 1 weeks)

20. If shutdown at end of report period, estimated date of startup i.

t SUN 0FFICIAL COMPANT NUMBERS ARE USED IN THIS REPORT

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OPERATING DATA REPORT;

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' DOCK ET NO.' _,_

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UNIT?

TWO N:

I D' ATE $4 SEPT 1987 t

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)j COMPLETED BYB_.A._S_Q,,HjiI D T a

T E LEP HO NE3 0 9-6J 4-22 4_A,,,,,,,,__

n OPERATING STATUG 0000 080187

i. Reporting periodigA0_0 00_3_18.Z, Gr o s s h o u r s 'in ; re p o r t in g L p e r i o d :

744

2. Currently cuthorized power level'(MWT): '2511 Max. Depend capacity (mwd-Net):.769* Deul.gn clectrical roting (MWe-Net): '789 h

3.

Power. level to which restricted (if any)(MWe-Net): NA 4.' Reasons, f or restriction (if any)::

1his Month Yr.to Date.CuMolutiv..

5.~ Number of hours reactor w u r., c r 'i t i c a l 14.4 4474,1-

_, iJ1214?.. t '

6. Reactor reserve shutdown hours 0.0 0.0 299C,i s 7..-Ho~rs generator on line J.4 4_

4421.i

,_,22,i R0 u

2,

8. Unit reserve shutdown hourn.

0.0 0.0

,,,,7 0 2., [

9. Gross thermal energy generated (MWH) 3603,R:

10512606 21185270' j

-10.

Groes electr.icci energy generated (MWH) 113@5

339165Z,

,,_ 6 72M 94.!

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W.et electr.ical-energy generated (MWH) 59.,g2, 3230643

__,,630356.U'

12. Reactor' service factor i.9, 76'.7

76..

I 13..Muuttor avo11obility factor 1.9 76.7 70 2

14. Unit service factor 1.9

_ _.,_ 75 8 74_.

15. Unit avo11ob111ty factor i. 2,

__,,,,..___Z5.8 74.'

16. Unit capacity factor (Using MDC) 1.0 72,,_R.

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17. Unit capacity factor-(Using Des.MWe) 1.0 70.4 n,'

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18.= Unit forced outage rate 98.i

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

20.-If shutdown ut end of report period, estimated date o f s t ar t u p _., 9],5f87_ _

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VI. UNIQUE REPORTING REQUIREMENTS l The~followinglitems,are included.In this' report. based'on prior commitments to.;

.the commission:

fA.." MAIN STEAM RELIEF VALVE OPERATIONS-

'There w'ere.no Main. Steam Relief _ Valve. Operations for the.

reporting period.

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B.-fCONYROL ROD DRIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO

-There was no Control: Rod Drive Scram Timing Data for Units One;and Two for:the~ reporting period.

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REFUELING INFORMATION

~

The following information_about-future reloads'at Quad-Cities Station was

. requested in a January 26, 1978, licensing memorandum-(78-24) from O. E.

. 0'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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QTP 300-532 Revision 1 l

QUAD-CITIES REFUELING March 1978 l'

INFORMATION REQUEST e

1.

Unit:

Q1 Reload:

8 Cycle:

9 2.

Scheduled date for next refueling shutdown:

9-14-87 3.

Scheduled date for restart following refueling:

'12-7-87 4.

Will refueling or resumption of operation thereafter require a technical speelfication change or other license amendment:

YES. TECHNICAL SPECIFICATION CHANGES WILL BE REQUIRED FOR NEW FUEL TYPES (MAPHLGR CURVES) AND A LICENSE AMENDMENT TO MOVE SINGLE LOOP OPERATION INTO TECHNICAL SPECIFICATIONS. CHANGE TO MCPR LIMIT AND OPERATION AT INCREASED CONG FLOW / FINAL FEEDWATER TEMP. REDUCTION.

5.

Scheduled date(s) for submitting proposed IIconsing action and supporting Information SEPTEMBER 9, 1987 6.

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

' different fuel design or supplier, unreviewed design or performance analjls methods, significant changes in fuel design, new operating procedures g

FIRST RELOAD OF GENERAL ELECTRIC, GE8E FUEL WITH 4 WATER-RODS AND LHGR LIMIT OF 14.4 KW/FT.

7.

The number of fuel assemblies, a.

Number of assemblies In core:

724 b.

Number of asrambiles in spent fuel pool:

1573 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:

l.icensed storage capacity for spent fuel:

3657 a.

b.

Planned increase in licensed storage:

0 9

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

2008 XPPROVED APR 2 01978 Q. c. o. S. R.

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QTP 300-s32-QUAD-CITIES REFUEL.!NG Revision I INFORMATION REQUEST March 1978' l

i e

1.

Unit:

'02 Reload 8

Cycle: _

9 2.

Scheduled date for next refuel!ng shutdown:

3-14-88 3.

Scheduled date.for restart following refueling:

5-22-88 4.

Will refueling or resumption of operation thereafter require a techni specification change or other license amendment:

cal.

NOT AS YET DETERMINED.

5.

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

DECEMBER 14, 1987

6. 'important licensing considerations associated with refueling, e g i

' different fuel design or supplier, unreviewed design or performa

., new or methods, significant chang 8te la fuel design, new operating procedures:

s NONE AT PRESENT TIME.*

1l 1

7.

The number of fuel assemblies.

Number of assemblies in core:

a.

724 b.

Number of assemblies in spent fuel pool:

1311 8.

The present IIcensed spent fuel pool storage capacity and the size in number of fuel assemblies: increase in licensed storage capacity anned 1

Licensed storage capacity for spent fuel:

a.

3897 b.

Planned Increase in licensed storage:

0 I

9.

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

1 2008 APPROVED APR 2 01978 Q. C. O. S. R.

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k VIII. GLOSSARY:

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The following. abbreviations which may have been used in the Monthly Report,

~

.are defined below:.

ACAD/ CAM

. Atmospheric Containment Atmosphe'ric Dilution / Containment ^

-Atmospheric Monitoring'

ANSI

American National Standards Institute g

l Average Power Range-Monitor

-APRM Anticipated Transient Without Scram ATHS

. Bolling Water Reactor BWRL LCR0 Control Rod Drive

'EHC Electro-Hydraulic Control. System

~ EOF Emergency Operations Facility GSEP

Generating Stations Emergency. Plan HEPA-High-Efficiency Particulate Filter-High' Pressure Coolant. Injection System

,HPCI~

l High: Radiation; Sampling System HRSS.

lIPCLRT Integrated l'rimary Containment Leak Rate Test l

IRM

' Intermediate Range Monitor ISI:

Inservice Inspection

.LER.

Licensee Event Report LLRT-Local Leak Rate Test LPCI Low Pressure Coolant Injection Mode of RHRS

. Local' Power Range Monttor LPRM.

' MAPLHGR Maximum Average Planar Linear Heat Generation. Rate' MCPR Minimum Critical Power Ratio MFLCPR

-Maximum Fraction Limiting Critical Power Ratio MPC Maximum Permissible Concentration H;IV Main Steam Isolation Valve NIOSH

' National Institute for Occupational Safety and Health PCI Primary Containment Isolation PCIOMR Preconditioning Interim Operating Management Recommendations RBCCH

. Reactor Building Closed Cooling Water System i

4 RBM Rod Block Monitor RCIC Reactor Core Isolation Cooling System RHRS Residual Heat Removal System RPS Reactor Protection System RWM Rod Worth Minimizer Standby Gas Treatment System SBGTS.

Standby Liquid Control SBLC' LSDC Shutdown Cooling Mode of RHRS q

-SDV Scram Discharge Volume 1

Source Range Monitor l

SRM TBCCW Turbine Building Closed Cooling Water System Traversing Incore Probe TIP

'TSC Technical Support Center 0027H/0061Z m

qwr tw l'

Commonwealth Edison I

ouad Cities Nuclear Power Station I

22710 206 Avenue North USNRC-DS Cordova, Illinois 61242

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i.'

Telephone 309/654 2241 m a A cb 51

.i RAR-87-41 September 2, 1987 U.S. Nuclear Regulatory Commission Attn: Document Control Desk i

Office of Nuclear Reactor Regulation Washington, D. C.

20555 Enclosed 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 August, 1987.

Respectfully, COMMONWEALTH EDISON COMPANY QUAO-CITIES NUCLEAR POWER STATION R. A. L&

R A. Robey Services Superintendent yk Enclosure i

i I

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,7 4

0027H/0061Z

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