ML19207B140

Monthly Operating Rept for Jul 1979

ML19207B140
Person / Time
Site:	Quad Cities
Issue date:	08/06/1979
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML19207B135	List: ML19207B134 ML19207B140
References
NUDOCS 7908230439
Download: ML19207B140 (24)

Text

. ,

QUAD-CITIES tiUCLEAR i'0WER STATION UNITS 1 AND 2 MONTHLY PERFORMAt4CE REPORT JULY 1979 COMMONWEALTH EDISON COMPANY AND 1OWA-ILLItiOIS GAS & ELECTRIC COMPANY tlRC DOCKET t10S. 50-254 and 50-265 LlCENSE fiOS. DPR-29 and DPR-30 790823o4M 784a11

TABLE OF CONTENTS

1. Introduction

11. Su:..na ry of Opera ti ng Experience A. Uni t One B. Uni t Two Ill. Plant or Procedure Changes, Tests, Experiments, and Safety Rela *ed Maintenance A. Ammendments to Facility License or Technical Specifications B. Facility or Procedure Changes Requiring NRC Approval C. Tes ts and Experiments Requi ring NRC Approval D. Other Changes, Tests and Experiments

1. Facility Modifications

2. Special Tests E. Corrective Maintenance of Safety-Related Equipment IV. License Event Reports V. Data Tabulations VI. Unique Raporting Requirements A. Main Steam Relief Valve Operations B. Control Rod Drive Scram Tining Data Vil, Refueling Information Vlli. Glossary

'2 @l3.'$.2

1. INTRODUCTION Quad-Ci ties Nuclear Power Station is composed of two Boiling Water Reactors, each wi th a Maximum Dependable Capaci ty of 769 tiWe net, located in Cordova, Illinois. The Station is jointly owned by Commonwelath Edison Company and lowa-Illinois 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 Uni 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 subiect to license numbers DPR-29 and DPR-30, issued October 1, 1971 and itarch 21, 1972 respectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor cri ticali ties for Units 1 and 2 respectively were October 18, 1971 and April 26, 1972. Commercial generation of power began on February 18, 1973 for Uni t I and tia rch 10, 1973 fcr Uni t 2.

This report was compiled by David Hannum, telephone number 309-654-2241, ext. 179

"/64213

11.

SUMMARY

OF CPERATitiG EXPERIENCE A. Unit One July 1: Unit One began the reporting period opera ting at 547 MWe. Load was increased to 650 MWe immediately after the main condenser flow reversal was completed.

July 2 - 3: Load was steadily increased to 791 MWe and held.

July 4: Unit One was reduced to 550 MWe for main condenser flow reversal.

Load was subsequently increased to 750 MWe.

July 5 - 20: Uni t One held an average load of 791 MWe. On July 8 load was reduced to 700 MWe for main condenser flow reversal . On July 14 load was reduced to 691 MWe for weekly turbine testing.

July 21: Electrical load was reduced to 150 MWe for an on-line control rod sequence exchange. Upon successful completion of the sequence exchange, load was increased at a rate of 100 MWe/hr to 400 MWe.

July 22 - 31: Load was steadily increased to 790 MWe and the unit held an average load of 775 MWe. Electrical load was reduced on July 27 and 28 to 635 Mye in order to remove a condensate demineralizer from service to change the filter elements.

7 @i23_4

B. Unit Tv:0 July 1. Unit Two began the reporting period operating at 625 MWe.

July 2 - 24: Unit Two held an average load of 575 MWe. On July 4 load was reduced 100 MWe due to 'ow systen electrical load demand.

July 25: The drywell was deinerted and load was reduced to 290 MWe for a drywell entry. The torque switch on the MO 2-1301-16 RCIC steam supply valve operator nalfunctioned and had to be replaced.

July 26 - 31: Unit Two held an average load of 550 MWe. On July 28 load was reduced to 350 MWe for main condenser flow reversal.

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111. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A. Amendments to Facility License or Technical Specification There were no amendments to the f acility license or Technical Specifications during the reporting period.

B. Facility or Procedure Changes Requiring flRC Aporoval There were no f acility or orocedure changes requiring flRC approval during the reportir.g period.

C. Tests Exoeriments Requiring flRC Aporoval There were no tests or experiments performed during the reporting period requi ring flRC approval .

D. Other Channes. Tests, and Exoeriments

1. There were no facility modifications completed this month which require reporting to the NRC.

2. Special Tests Special Test 1-44 Unit One Reactor Feed Pumo Minimum Flow Line isolation and Valve Leakage Test

Purpose:

The purpose of this test was to qualitatively determine the magnitude of feedwater leakage back to the main condenser through the minimum flow lines and its impact on plant performance.

Summa ry of Sa fety Evalua t ion:

Basic feedwater operation was not altered during the test. Flo safety related systems, structures, or componenets were involved in the test.

/@ie316

The normal feedwater flow path was not changed and in the event of a feedwater problem, all ECCS was available to supply water to the vessel. No Technical Specification itens were affected.

Special Test 2-15 MSIV Limi t Switch investigation Purnose:

The purpose of this test was to outline the method used to investigate the performance of the new 740 series MSIV limit swi tches , along wi th the relocated MSIV limit switches on cutboard valve A0 2-203-2C.

Summary of Safety Evaluation:

The design function and intent of the MSIV's were not altered by this test. The new switches and relocation have been previously evaluated, and no new additions were nade to ccmplicate the indicating or protecti"e functions of the valves. The 10% closure RPS setpoint was not changed and no LlRT or PCI closure time values were reduced.

E. Corrective haintenance of Safety Related Equipment The following represents a tabular summary of the safety-r lated maintenance performed on Uni t One and Uni t Two during the reporting period. The head!ags 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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UnlT ONE mal hTENANCL SU:'.hA!<Y CAUSE RESULTS c EFFLCIS

.. R. LER OF CH ACTicN TAKEN TO NUMBER COMPONENT MALFUNCTICH SAFE OPERATION PREVENT REPETITION NUMBER Diesel Cen. Oil The fuel oil fil- The line was leaking. The gasket was replaced.

3306-79 79-22/03L Line (1-6600) ter gasket was The diesel was operable. DG was tested satisfac-worn. tory.

The digital weight The digital weight The monitor was replaced 364-79 Rx Bldg Crane monitor was defec- indicator was inoperable. and calibrated.

(1/2-5800) f*vd.

Core Spray Test An aux. contact The valve would not open. The aux. contact was 3620-79 Core spray was operable. replaced.

Valve (1-1402-4A) was defective.

Of f Gas liigh Pressure switch The operator received The switch was calibrated 3550-79 and tested.

Pressure Switch needed calibration. the off gas high pres-(PIS-1-5441-16A sure alarm. The off gas system was operating c B) properly.

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UNIT T' 0 MAINTENANCE

SUMMARY

CAUSL RESULlS S LFFtLib OF CN ACTION TAKEN TO k' . R . LER MALFUNCTION SAFE OPERATICN FREVENT REPETITION N U.'i3 E R NUMBER COMP 0"ENT IRii Ch. 13 The pre-amp a.d Channel 13 was reading The pre-emp and powe r 734-79 aupply were re-calibrated.

(2-700) po.;er supply were incorrectly. Other IRM out of calibration. channels were operable.

2076-75 CRD 34-15 The accumulator The water level was The accurulator was was defective. excessive. Scram replaced.

(2-300) operability was unaf-fected. __

RHR Suction The thermals The valve would not open. The thermals were reset.

3551-79 79-13/03L This made the 2C n.R pump Amperage checks were made Valve (2-1001-7C) tripped.

and the valve test oper-inoperable. The 2A, 2B and 20 pumps were oper- ated 3 times, able and available if needed.

RHR HX Bypass The the rmals t rip- The bypass valve failed The thermals were reset.

3593-79 Amperage checks were rade Valve (2-1001- ped. closed. RHR was still operable with flow and the valve was cycled 163) through the HX. 3 t i rce s .

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70 9E"$.

IV. LICENSEE EVENT REPORTS The following is a tabular sun. mary 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 One Licensee Event Date of Title of Report Number Occurrence Occurrence 79-23/03L 7-18-79 Electromatic Relief Valve 203-3A Controller Inoperable 79-24/03L 7-24-79 Suppression Chamber -

Reactor Building Pres-sure Switch PS 1-1622B Drift Unit Two Licensee Event Date of Title of Report Number Occurrence Occurrence 79-13/03L 7-12-79 RHR Pump Suction Valve MO 2-1001-7C Breaker Failure 79-14/03L 7-23-79 RCIC Steam Supply Valve MO 2-1301-16 Failed to Close 79-15/0lT 7-24-79 Suporession Chamber -

Reactor Building Pres-sure Switch PS 2-1622A and B Dri f t

';B4220

V. DATA TASULATIONS The following data tabulations are presented in this report.

A. Operating Data Report B. Average Daily Unit Power Level C. Unit Shutdowns and Po.,er Reductions D* ' (, ". O f'7 4 4' O ' i / e k f.

I Crtn ':A M U ID0s T

[ LIT f:9 050-254

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1 o nQRT A ng7g 8-6-79 O C 0!!Pt.Ei i.D B Y D- H3' "

TELEN:0!!E (309) 654-2241, Ext. 179 g , o.. .o._ ; ..a- c .mT ' '"

0000 070179 2400 073179 7 4

J. P 2;.or t ing pe r iod : G r o s r. hours i i reporting period:

2. Current 1' authorized po.ver level ( : tit) :

2511 liax. depend. capaci ty

(.T1.-::e t) _ 769 Des ign elec t rical ra t inI;~0;Ue-f e t) : 709 .

F o.. .: r level to v.hich res t ric ted (i f any) (ti',le-!:2t) . flA _,

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h. F.easons for restrictica (if any)

This liont h Yr. to Date Curau l e t i ve 5 I u- {ie r of hour s reector tras critical 744.0 4022.8 51355.7

6. P.cactor reserve shutdo.2n hour, 0.0 0.0 3329.0 _ , _ _

7 Ecurs geaarater cn line 744.0 3893.9 48836.8 __

S. Unit re w rve shutdo.n hours. 0.0 19.8 9.39.2

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G ros s .he rna l c ae rgy gene ra teo. ( .<, ,. -,a,

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1755294 8344962 97152338 9., t ,

10. Gro :s electrical engercy generated (!n!H) 558445 2642274 312.4769

11. Net electrical Enargy Generated 532587 2489725 29122298 I?. F, 'ac t or serv ice factor 100.0 70.I 81.1 13 P,ecc tor availabi l i ty fac tor 100.0 79.1 86.4 14 Unit service factor 100.0 76.5 77.1 . _ _

15 Unit a va i l a b i l i t y .'a c'.t c r 100.0 76.9 78.6 .

16. Unit capactiy factor (Using ::DC) 93.1 63.6 59.8

17. Unit capacity factor (Using Des. !n!2) .10.7 62.0 58.3 .

l ?. . U if t forced outc9 rate 0.0 3.7 7.9 19 S h u t d o..:n s sch2duled ovcr n= < t C r enths (lypu, date, an:1 dura t i on of er.ch):

20. If shutde..n at end of report pe riod , es t ina ted d :ta of s tartup;- .*

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Th2 ti3C r' rf la 1 0.. fr t h r. n 7 9) F.' ' ' d u - i rj p r r i o:i n of hi:;h :.tiaat t e .,1 ? r a t u r e c' i j to th' th2rcal p ; .- f o r . o . . c . cf t i. s; rc , cc:.a i , ,, ,

l 1 (i i n < ') %G Gr'3t 9c,9 in,4 w G,. t  % ~

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TELrpng"; (309) 654-2241, Ext. 179 0'ERATI:;3 STATUS 0000 070179

3. n_.;:orting period:2400 073179 Gross hours in reporting period: 744

2. Currently <._ SoH ud poaer level (MWt) : 2511 Max. depend. cepacity

(%-::ct) . _yg.; Design elect ri cal r3 ting ( U ffot): 719 .

3 ro..er level to vhich restricted (if any) (mle-!:e t ) : flA _.

4. Ecasons for restriction (if any)-

This ".on+h Yr. to Date C um i e c i ve 5 I:un'eer of hours recctor veas. critical 74; a 4984.9 0

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6. Reactor reserve shutdo.>n hours 0.0 0.0 2985.8 Ecurs generater on 1ine _744.0 4938.7 L30h1.6 7

0.0 0.0 32.9 C. Unit resnrve shutda.n hours. .

1400204 10191972 98934096 9., Gross the rra l ene rgy gera ra ted ("'-lH) 3168662 31657039

10. Cro s electrical engercy generated (M'!H) 424099

!i a t electrical Energy Generated 3S2556 2929367 29690827 11.

12. R actor service fcctor 100.0 98.0 80.7 =

13 R ector availabili Cy factor 100.0 98.0 85.5 I4 Unit service factor 100.0 _9] .1 77.0 15 Unit availability facter 100.0 _

97.1 78.1 IG. Unit capactly factor (Us ing ";c) 66.9 74.9 61.9 17 Unit capacity factor (u . i n a oc,. mtz) 65.2 73 0 60.3

13. Ulit forcc' outa3t rate 0.0 0.7 9.7 19 Shutdo.n: sch2dulud ove r nc x t t conths (Typ", date, and duration of ead)

20. If shutdo-, at e n c' of re,.nrt peri <?d, esti.otel date c f star tu;>:

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Telephone J309)654-2241, Ext. 179 liONTil July, 1979 DAY AVERAGE DAILY POWER LEVEL- DAY AVERAGE DAILY POWER LEVEL (fiUe-Me t ) (fiWe-fle t) 17 510

1. 562

18. 513

2. 554 555 19.. 513 3

498 20, 501 4.

21 500

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550

22. 488 6.

552 23 494 7 - . _

8. 519 - 24. 518

'131 25 476 9

524 26. 503 10.

11. 526 27. 507

12. 522 28. 496 518 428 13 29 522 30, 505 14.

507 089 15 31.

n is is aOVE 513 ,.~ S oo s,.

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VI. UNIQUE REPORTING REQUIREMENTS The following items are included in this repo r t based on prior commitments to the Commission.

A. "ain Steam Relief Va. e Ooerations There were no main steam relief valve actuations during the reporting period.

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

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OTP 300-532 Revisica 1 QUAD-CITIES REFUILING March 1970 INF03 MATT 0N REqu2ST

1. Unit: 1 R , l o n. d : 4 Cycle: 5 Scheduled date for next re f uel ing shu tdo'...,: J;in u a rv 12. 1979 (Shutdown 2.

EOC4)

Scheduled date for restart following refueling: Aoril 1?, 1979 (Startup 80C5) 3 tii l l refueling or resunptica of operation thereafter require a technical specification changa or other license amendment: Yes; See attached checklist for Tech. Spec. and License Amendment.

5 Scheduled data (s) for subnitting proposed licensing action and supporting i n f orma t i on : The QC1 R4 licensing submittal is scheduled for Nov. 11, 1978.

6. Irport:nt licensing considerations associated with refueling, e.g. , new or dif ferent fuel design or supplier, unreviewad design or performance analysis methods, significant changes in f uel desi gn , new opera ting procedures :

New fuel designs: Re t ro fi t 8 x 8 fuel (192) a) nat. U at bundle top and bottom, b) two larger water rods, c) new enrichment dist ribution.

Last Test Assemblies (4) for GE PCI-resistant design development program.

7 The number of fu21 assemblies.

c. Number of assemblies in core: 724

b. Number of assemblies in spent fact pool: 486

? The present licensed spent fuel pool storaga capaci ty and the size of any increase in licensed storaga capacity that has been requested or is planned in number of fu21 assemblies:

a. Licensed storage capacity for spent fual i r160

b. Plann .! increat in licensed storage. None _.

s. The projea J datt of th la .t refueling that can be dischargad to th spent foal cual .ssuning U.2 present licensed capacity: Last re fue l i n g date with present capacity: March, 85 (end of batch discharge capability)

- 3 300 r;Pjges&w) g

PRELIMINARY CHECKLIST FCR RELCAD LICENSE AMENDMENTS UNIT: Quad Ci ties 1 RELOAD: 4 CYCLE: 5 I

Iten page Require Changes Generalize wording and ref.

X Scram Reactivity 4 the submit, NED0-24063 Safety Valve Setpoints NA LSSS 1.2/2.2-1 flone. Adequate pressure marg in.

X Bases 1.2/2.2-2,3 Clarify and add bounding peak pressure.

RBM Setpoints X LCO 3.2/4.2-14 Change to (.652+42) 3.2/4.2-7 Change operability to 304 3.2/4.2-8 Change reference I to NED0-24063 X Bases Auto Flow Control NA LC0 3.3/4.3-5 None. Stability analysis not limiting.

NA Bases 3.3/4.3-11 tion e .

MAPLHGR X LC0 Fig. 3 5-1 5 Revise curves to re flect new (shts. 1 to 3) analyses.

X Bases 3.5/4.5-14 : Change references to re fl ect new analyses of NED0-24046 MCPR 3 5/4.5-10 New values:**1.33 (7x7)

X LCO 1.35 (8x3)

Bases 3 5/4.5-14 Generalize description of

) liniting transient (s),

• MAPLHGR changes are being handled under separate cover.

"* locludes additional 0.XX CPR penalty for Fuel Loading Error Accident (NRC in terin licensing pos i tion) .

Values unknown at this time are i nd i ca ted a s "XX . . ."

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RELC AD L I CE""> l"3 PAC KAGE QTP 300-S33 P;'.EP/. RAT ION C CHEDULE Revi'iel I

a. ' ' O.1 March 1973 r ~. t_ C l.D ___4 CYCLE 5 D/.T E  ?.ESPONS!DlLITY CENTER ACTIVITY .

i 9/15/78  ! CE NFS receives draf t Licensing Submittal from GE

! N FS Transmi t copy of dra f t to Station for Comments l

l NFS Transmit NFS and Si te comments / questions to CE 9/29/78 NFS Benin Toch. S endnge..._S;tf_e t'g_.Eva l u n t ien ' nd-Ccv2r Lott"-

GE NFS receives final Licensing Submittal and answers to CECO questions from GE

""'"ri'"

10/30/78 NFS Canalete final NFS r< view of I i cons i ng subnt e r,1 ,nd :n;wur: to FFI^ -

11/1/78 NFS Transmi t complete package for on/off site review i

11/3/73 Station on-site review completed -

11/6 B8 PSA Off-site review complclui d\'

11/11/73 NLA Completed 1* censing onckaca corni ind hy HRC A l Anticipated unit shutdown \ 90 days 1/12/79 -

28 days ,

t i

2/9/79 -

Receipt of operating License J, N wi CC 1 3/9/79 Anticipated Uni t Sta rtup - Assumes 56 day outage f.3

+'

' 8 weeks v -'  ;

-__ ,m, -

Prepared by Mr NFS/Ct/R Date 12/23(11_.

. (final)

. . QTP 300-532 Revision 1 C:UAD-C IT I ES '< eft:iL i h0 tiarch 1973 t h,~0RMAT I O:. P.Er sU EST

1. Unit: 2 Reload: 3 Cycle. 6 (o,+ ,ge in progress)

2. Schedulen date for next refueling shutdo.in: Januarv 15. 1478 ( shutdown EOC 3)

Sch2duled date for restart folic.Ing refueling: March 15. 1978 3

(Startup BOCh) (In progress; See below for next outage) l.

i Uill refueling or resumption of operation thereaf ter requira a technical specificatica change or other license emendment: Yes; See at tached checklist for Tech. Spec. and License Amendments.

5 Scheduled date(s) for submitting proposed licensing action anc supporting inforration: The QC2 R3 licensing package was t ransmi tted on Dec. 2, 1977

6. loportant licensing considerations associated with refueling, e.g. , new or different fuel design or supplier, unreviewed design or performance analysis ra thod s , signi fican t changes in fuel design, new operating procedures:

None. (180 2.62 w/0% 8 x 8's) .

7 The nu ber of fuel assenbites.

a. Nu.ber of assemblies in core: 724 (before EOC4 discharge)

b. Number of assemblies in spent fuel pool: 230 (before EOC4 discharge)

S. Tha present licensed spent fuel pool storage capacity and the size of any i n c r e.-i s e in licensed storaga capacity that has been requested or is planned in nun % r of fuel assemblies:

a. Licensed storage capacity for spent fu21- 1460

b. Planned increase in licensed storage: None.

D. T he praject H date of t;. last refueling that can be discharged to th2 spent fuel pNI a,suling th2 pres 2nt IIuJ:nsed capacity: Last refueling date with present capacity: September, 85 b 's( rs

/s c, d

P"ELIMINARY CNECKLIST F03 RELOAD LICEN5E /'tENDMENTS UNIT: 0.uad-Cities 2 RELCAD: 3 CYCLE: 4

' Require Changes 1 ten Page Scram Reactivity 4 Generalize wording and reference the submit, NEDO-24063 Safety Valve Setpoints NA LSSS 1.2/2.2-1 None. Adequate pressure margin.

X Bases 1.2/2.2-2,3 Clariff and add bounding peak pressure.

RBM Setpoints X LC0 3.2/4.2-14 Change to (.65w+42) 3.2/4.2-7 Change operability to-30%.

X Bases 3.2/4.2-8 Change Reference 1 to NEDO-24063 Auto Flow Control

% LCO 3.3/4.3-5 None. Stability analysis not limiting.

NA iases 3.3/4.3-11 None.

s MAPLHGR X LC0 Fig. 3.5.1 & Revise curves to reflect (shts. I to 3) new analyses.

X Bases 3.5/4.5-14 5 Chance references to reflect new analyses of NECO-24046.

MCPR , 3.5/4.5-10 New values: 21.33 (7 x 7)

X LCO 1.35 (8 x 8)

Bases 3.5/4.5-14 Generalize description of liniting transient (s),

a

' ftiPlilGR ch anga are bein,, handled under separate cover.

I n cl udes .::dd i t i ona l 0. XX CPP, penpity for En:1 loadin, Error Accident (NTC in terir: l i c en . i n e, :m i ti on) r 9 'r, o a

1. U ik

. ire i r J i c. te'J as XX.

8'.JS U ll'-' il ' ln d t thi< ti

Rt. LOAD LICENSING PACKAGE QTP 300-533 vi' ion 1

': l T OC 2 PP7.PARATl0 S C H E DlJ L t i.

"arce 1973

s. _ A2 -- 3

Y C '_ E 4 DATE RESPONS!BILITY CENTER ACTIVITY .

l 10/6/77 i CE' NrS receives draft Licensing Subnittal from GE Transmit copy of draft to Station ,

l UFS for co= lent s .

I t'i'S Transmit flFS and Site comments / questions to CE 13egin Tech. Spec. channes, Safety 10/20/77 I NES Evaluation and Cover Letter.

I GE til/S receive 1 final Licencing Submittal and answers to CECO questions f r or.i C E .

f "FS Camplete final tir9 revi eg_c f I (c.gnyino 9ub"Irrn1 w1 an tam r s t o Pfro <murrinn

__11/3/77

11/8/77 i

i NFS Transmit complete packae,e for on/off site review 11/16/77 Station on-site reviou compiered

!,_ ___ _11/18 / 7 7 PSA Offesite review comnleted 12/1/77 NLA Completed Licensino packnee receiver 1 by NRP 90 days

[

1/16/78 - Anticipated unit shutdown i

l 28 days i

j 3/5/78 - Receipt of operating License t Day outage ,

i 8 Weeks

' 3/15/73 - Anticipated Unit Startup - Assumes il M ,

!L @ ,

~,

N Prepared by JAS . NFS/UWR

[,

Date 2/23/78 (final)