ML20062D369

Monthly Operating Rept for Oct 1978

ML20062D369
Person / Time
Site:	Quad Cities
Issue date:	10/30/1978
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20062D366	List: ML20062D364 ML20062D369
References
NUDOCS 7811220033
Download: ML20062D369 (30)

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 i

MONTHLY PERFORMANCE REPORT FOR OCTOBER 1978 l

COMMONWEALTH EDISON COMPANY 10WA-lLLIN0lS GAS & ELECTRIC COMPANY i

j NRC DOCKET.NOS. 50-254 AND 50-265 LICENSE NOS. OPR-29 AND OPR-30 i

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l TABLE OF CONTENTS 1.

INTRODUCTION

11. '

SUMMARY

OF OPERATING EXPERIENCE A.

Unit One B.

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

Amendments to Facility License or Technical Specifications

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B.

Facility or Procedure Changes Requiring NRC Approval

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C.

Test and Experiments Requiring NRC Approval D.

Other Changes, Tests and Experiments 1.

Facility Modifications 2.

Special Tests

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E.

Corrective Maintenance of Safety-Related Equipment IV.

LICENSEE EVENT REPORTS V.

DATA TABULATIONS A.

Operating Data Report B.

Average Daily Unit Power Level C.

Unit Shutdowns and Power Reductions e

VI.

UNIQUE REPORTING REQUIREMENTS A.

Main Steam Relief Valve Operations i

B.

Control Rod Drive Scram Timing Data Vll. REFUELING INFORMATION Vill. GLOSSARY

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INTRODUCTION Quad-Cities Nuclear Power Station is composed of two Boiling Water Reactors, each with a Maximum Dependable Capacity of 769 Mbe net, located in Cordova, Illinois. The Station is jointly owned by Common-

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wealth Edison Company and towa-lilinois Gas & Electric Company. The Nuclear Steam Supply Systems are General Electric Company Boiling Water Reactors. The Archittet/ Engineer was Sargent & Lundy, Inc., and the primary construction contractor was United Engineers & Constructors.

The condenser cooling method is a closed-cycle spray canal, and the -

Mississippi River is the condenser cooling water source. The plant is subject to license numbers OPR-29 and OPR-30, Issued October 1, 1971, and March 21, 1972, respectively, pursuant to Docket Numbers 50-254 and 50-265 The date of initial reactor critica11 ties for Units 1 and 2, respectively, were October 18, 1971 and April 26, 1972. Commerical generation of power began on February 18, 1973, for Unit I and March 10, 1973, for Unit 2.

Thi's report was compiled by Michael Reed.

Telephone number 309-654-

', 2241, extension 252.

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SUMMARY

OF OPERATING EXPERIENCE The following is a chronological description of plant operation for the month of October, 1978.

A.

Unit One October 1: Unit I began th'e. reporting period operating at an-electrical load of 588 Mwe.

October 2-7: Unit One held an average electrical load of 616 MWe.

4 October 8-9: Load was reduced to 450 MWe both days-for condenser flow reversal.

October 10-14: Unie One held an average electrical load of 616 Mwe.

T October 15:

Load was reduced to 279 MWe for the MSIV bi-weekly surveillance and was then held at 450 MWe for main condenser flow reversal.

October 16-20:

Load was increased steadily on October 16 to 593 MWe.

Unit One then held an average electrical load of 591 MWe for the next four days.

October 21:

Load was reduced to 400 MWe for main condenser flow reversal.

October 22-25:

Load was increased to 420 MWe and held steady.

i October 26: Load was-reduced to 305 MWe in order to test the main steam relief valves and change the recirc MG set brushes.

All five relief valves were test' operated satisfactorily.

October 27-30: Unit One held an average electrical load of 417 Mwe.

October 31:

Load was reduced to 410 MWe for main condenser flow resersal.

B.

Unit Two Octccer 1-2: Unit Two began the reporting pericd in the ShUTOCWN mode due to the continuation of the maintenance outage which began on September 29 The Unit was put on line l

cn October 2 at 0745 and held at 250 MWe for control Red Scram Timing.

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October 3-7: Unit Two steadily increased load on a precondi-tioning ramp of 3 MWe/hr.

October 8-13: Unit Two held an' average electrical load of 766 Mwe due to rod pattern limitation.

October 14: Load was reduced to 450 MWe for main condenser flow reversal.

October 15-17: Unit Two steadily increased load on a preconditioning ramp of 3 MWe/hr.

October 18-21:

Load was reducad from 716 MWe to 682 MWe due to high condenser backpressure.

October 22:

Load was reduced from 670 MWe to 620 MWe due to high spray canal temperature.

October 23-29:

Load was increased to 750 MWe on October 23 and held due to MCPR limibtions.

October 30: Load was reduced from 740 MWe to 633 MWe due to high service water temperatures.

October 31: Load was redeuced from 633 MWe to 500 MWe to switen reactor feedpumps.

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

Amendments to facility License or Technical Specification There were no amendments to the facility license or Technical Specification during the reporting period.

B.

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

C.

Test and Experiments Requiring NRC Approval There were no tests or experiments performed during the reporting period requiring NRC acpreval.

D.

Other Changes, Tests, and Ex:eriments The facility modifications during the reporting period are as fo11cws:

s M-4-1 & 2 29 i

Piping Restraints Description of Modification i

These modifications involved the redesign and installation of new and revised restraints on various pipin3 and equipment throughout the station.

1 The affected restraints on both safety related and non-safety related systems were required to reduce vibration and to reduce systems susceptibility to flow incuded transients.

4 Summary of Safety Evaluation:

The reliability of the affected systems is improved via the.reduct on of i

effects from vibration and transients.

Since the functions of the systems and equipment are not altered, no possibility is created for an accident or malfunction of a different type than'any previously evaluated in the FSAR.

M-4-1/2-76-30 i

Standby Gas Treatment Test Descriotion of Modification:

I This modification involved the installation of a series of sample test penetrations in the Standby Gas Treatment System piping.

The sample i

points allow for flow capacity and flow distribution testing. 'This modification was installed.in order to comply with technical specificaticos which require verification by testing of air flow distribution on the i

HEPA filters.

1 Summary of Safety Evaluation:

J No possibility is created of an accident or malfunction of a different type than previously evaluated in the FSAR because neither the intended function nor actual structure of the system are changea.

The margin of safety as defined in the basis for Technical Specifications is increased since the penetrations allow more extensive testing to ensure correct operation of the Standby Gas Treatment System.

M-4-1(2)-76-38 Torus Support Colunns Descriatien of Mcdification:

These mcdifications involved increasing the integri ty of the torus structural succort columns as per tse Mark I short term fix pecgram.

The reinforcement was acccmolished by increasing the weld threat size of the web-to-torus and flange-to-terus fillet welds.

The Intent cf the:e modifications was to develop the full strength of each column supcort.

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i Summary of Safety Evaluation:

The modifications provide a marked increase in the structural capacity of the torus supports.

Safety eargins identified in the FSAR are Improved so that LOCA pool swell loads can be accommodated within the criteria accepted for safe operation. The margins of safety, as defined in the Technical Specifications are not reduced, but rather improved.

M-4-2-76-57 HPCI Auto Start Description of Modification:

This modification changed the HPCI control circuitry to eliminate the HPCI discharge valve from improperly cycling when high drywell pressure and high reactor water level occur simulatenously.

The circuitry was changed such that high reactor vessel water level still trips the HPCI turbine, but automatic or manual reset is inhibited until the high water l et.e l is cleared. This modification was accomplished by Installing a aormally closed contact in series with the high primary containment pressure contact which will monitor the reactor vessel high level.

This will eliminate the potential of damaging the HPCI pump discharge valve.

Summary of Safety Evaluation:

The intent of the HPCI logic is unchanged even though this modification slightly changes the method by which this intent is accomplished.

The probability of a loss of HPCI is not increased and no new consequences different from any previously evaulated in the FSAR are created. The HPCI system is operability cested as before, thus the margins of safety for HPCI are unaf fected.

M-4-1-77-3 Torus Orain Line Description of Modification:

This modification involved the installation of a double valved drain line from an existing 3-inch torus penetration.

This drain provides a methcd for draining the torus during cutages when the water level is belcw the ECCS torus suction penetrations.

This modification also included provisions for pneumatic leak rate testing.

Senmarv of Safety Evaluaticn Torus structural integrity has been maintained, therefore no pcssibility is created for an accident or malfunction of a different type than any previously evaluatee in the FSAA. The use of recundant, 1ccked-closed isolation valves and screwed pipe end caps assure centainment systen integrity and tnus, margins Of safety as defined in tne basis for Tecnnical Specifications are not reduced.

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M-4-1(2)-78-19 RCIC Turbine Governor Hydraulic Tubing Changes Description of Modification:

These modifications involved the esplacement of hydraulic tubing on the RCIC turbine governor and the installation of an auxiliary oil sump on the RCIC hydraulic actuacor oil supply line. These modifications are the result of General Electric Field Disposition Instruction FDI 301/63060 intended to improve the reliability of the RCIC turbine. This is accomplished by prevsnting air entrapment within the hydraulic system and by preventing turbine overspeed trips due to starved oil supply.

Summary of Safety Evaluation:

The probability of an occurrence of an accident or malfunction of the RCIC turbine governor system is not created or increased since the tubine and oil sump changes do not alter the design function or required flow rate for operabili *.y of the system.

The margin of safety as defined in the basis for Technical Specifications is increased as a result of these modifications.

The following special test was completed during the reporting period:

Test 2-17 Electromatic Relief Valve Vibration Sludge Summary:

The purpose of this test was to monitor vibration of the electromatic relief valves and associated piping. Accelermeters, deflection and pressure transmitters were installed on the valves and piping, ano electrically connnected to monitoring equipment located outside the Unit Two drywell.

A report produced by Stone and Webster Co. has been received covering the results of the test.

l Summary of Safety Evaluation:

The pressure top location on the valve flange was evaluated by the valve manufacturer, Dresser Industries, and was determined to have no effect on the structural integrity of the flange.

The function of the valve in the pressure relief and auto-blowdown modes was not altered. All data l

for this test was taken externally and the relief valves remained operable throughout the test.

Thus the margin of safety was not reduced and the probability of a malfunction of equipment important to safety as previously evaluated in the Final Safety Analysis nas not increased.

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1 MAINTENANCE

SUMMARY

October CAUSE RESULTS & EFFECTS U.R.

LER OF ON ACTION TAKEN TO HUMBER HUMBER COMP 0NENT HALFUNCTION SAFE OPERATION PREVENT REPEllTION Corrective Refuel Grapple The proximity switd The grapple posi tion in-The proximity switch.vas

$111-7/

(1-833) was defective.

dicating light was not

replaced, working properly.

Corrective R0-78-28/03L-0 Of f Gas Radiat iori The high voltage The monitor failed down-The capacitors were 44'J0-78 Honitor power supply capa-scale. Other monitors tightened. The nonitor (1-1705-03A) citors were loose, were operable, was recalibrated.

(:orrective R0-78-12/03L E lec t roma t i c The rings had worn The viv was stuck closed.

The valve internals were 2108-/8 Relief VIv.

Into the guide Other relief valves replaced.

1-203-3C sleeve.

operated properly.

CEriective RCIC Turbine The trip mechanism The nechanism tripped be-The tappet button was 4010-78 1-1300 was defect i ve, fore reaching the over-replaced.

speed setting. RCIC was operable.

Corrective Drywell-vent valv-The speed controlle: The valve was operating fhe speed controller was 48-16-/8 (1-1601-23) was out of adjust-too slow, Valve was adjusted.

nent.

operable & within Tech Specs.

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2 MAINTENANCE

SUMMARY

October CAUSE RESULTS & EFFECTS tl. R.

LER OF ON ACTION TAKEN TO NUttilER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Corrective feedwater Check The seal ring was The pressure seal ring The seal ring was replaced.

2938-78 Valve (2-220-62A) worn.

was leaking, Corrective R0-78-34/03L-0 CRD N-10 (2-300)

CR0 50-39 scram Rod would not scram from Rebuilt both scram solenoid 456S-78 solenoid 2-305-118 test position, would have valves.

valve would not inserted on a full core de-energize, scram.

Corrective R0-78-32/03L-0 Target rock S/R Air supply line was The valve did not open The air line coupling was 4529-/8 valve (2-203-3A) broken.

during nanual test rethreaded and re-installed.

actuation.

Other relief valves were operable.

Coirective HSIV (2-203-1B)

The limit switch The limit switch was not The limit switch was replacu 4538-78 was defective, picking up for the test mode of operat lon.

RPS function was not impaired.

Corrective llPCI Limitorque The operator gasket: The valve was fully The gaskets were replaced.

4021-78 (2-2301-49) were defective, operable.

4 pressure relief kit was added to the operator.

Corecctive ilPCI Limitorque The operator gaskets The valve was fully rhe gaskets were replaced.

4020-78 (2-2301-15) were defective, operable.

.4 pressure relief kit was

,idded to the operator.

Corrective llPCI Limitorque The operator gasketsThe valve was fully

'he gaskets were replaced.

4019-78 (2-2301-14) were defective, aperable.

A pressure relief kit was added.

Corrective llPCI Steam Supply The seal ring was fhe valve was leaking. The The pressure seal ring was 338/-78 valve (2-2301-3) worn.

salve was fully operable.

replaced and the valve was repacked.

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2 MAINTENANCE

SUMMARY

October (cont'd.)

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN 10 NtutHER HUMUER LOMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Coriccaive Electromatic The limit switch The valve was showing The limit switch was replace 3212-/8 Relief Valve was defective.

duel indication. The (2-203-30)

Valve was operable.

Corrective Shutdown cig to The torque setting The breaker tripped The viv operator torque 4$33-78 RilR valve on operator was preventing valve opening.

setting was decreased.

(2-1001-43C) too high.

RilRS operability was not a f fected.

Corrective 125V DC ground Pinched wire was A 125 VDC ground was The pinched was replaced.

2115 9 - 78 detection system found in PNL detected.

(2-8300) 902-39.

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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 during the reporting period which were submitted to the commission 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 Report Number Occurrence Title of Occurrence

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R0-78-29/03L 10-25-78 Service Building Fi re Detection I nope rab l e.

R0-78-30/03L 10-26-78 Drywell to Suppression Chamber Vacuum Breaker Dual Indication Unit Two R0-78-32/03L S-29-78 Target Rock Pressure Relief Valve Failed to Open.

R0-78-33/03L 9-30-78 Inoperable Snubbers on Target Rock Piping, and Core Spray Piping.

R0-78-34/03L 10-2-78 CR0 N-10 would not scram from test panel.

R0-78-35/03L 10-4-78 Radiation Monitor Failures -

2A Fuel Pcol and 2A Reader-Building Vent.

R0-78-36/03L 10-16-78 Core Soray Low-Low level Ini tation Switch Out of Calibration.

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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 l

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nen_9gn/npo_,g U!1 t T One 0;.TE 11/8/78 CCM?LETED SY M.

Reed TELEPH0;;E (109) 654-2241 G

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0001 781001 2.

Reporting period: 2400 781031 Gross hours in report

• ng pc.-icd:

745 2.

Currently authorized pc.ier level (M.!:) :

2511 Max. depend. capacity I

f, (n'..*:-fie t) :

76% Design electrical rating (:r.c-!!et):

7E9 3

Powar level to which restricted (if cny) (.TJe-!:et):

NA 4.

Recsens for restriction (if an/):

This Month Yr. to Date C u..u l a t i ve 5

enber of hours reactor was critical 745.0 6.c97.0 hs.868.c 6.

Recetor reserve shutde.:n heurs 0.0 0.0 1.12o.6 7

Hours generater en line 745.0 6,853.1 43,478.9 0.0 45.2 889.4 3.

Unit reserve shutdown hours.

1,319,010 14,168,782 86,445,857 9., Grcss thermal energy generated (M'I.i) 392,378 4,435,734 27,859,450 10.

Gross electrical engergf generated (M'.m) 3h9,565 4,089,193 26,000,711 a

c, ical.nergy eaenerate.

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12.

F.e:ctor service factor 100.0 95 9 79.9 13 Re:ctor availchili fy facter 100.0 cc.o se y 1 r.

,Jn.t serv. ice ractor too.o ue

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i 15 Unic avat: 3bility ft,tter ico,o-ch c n,

16.

Uni: capc tl y f ac.:r ('Js i g ".:C) 61.0 72.3 c3. c,

17 Uni". ce.::ci;y f : tor (Using Cas. "!e )

59.5 71.0 57.5 ii.

Crit fort;d cuttg2 r:ta 0.0 kg 3,y 19, inu:d:'.;st 10 M d' ie. :.c a..

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050-265/0PR-]O U!!!T Two DATE 11/8/78 C0it?LETED BY M. Reed TELEPH0i!E 1309) 654-2241 GPETATl?iG STATUS 0001 781001 J.

P.cporting period: 2400 781031 Gross hours in reportini! 93. Iod:

745 2.

Currently author ized pc.ier level (f.'.lt ) :

2511 Max, depend. capacity (M'.,'e-fic t) :

769t. Design ele:tricci rating C;.!e-!!c t) :

769

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Pc..2r level to which restricted (if any) (i".le ';et):

NA 4.

P.casens for restriction (if any):

This Month Yr. to Onte Cumulative

en' er of hours rcector was critical 724.8 5679.0 43883.7 5

s 6.

Recctor reserve shutde..n hcurs 0.0 113.1 2985.8' 7

Hours generator en line 713.2 5561.1 41638.9 0.0 128.2 702.9 8.

Unit reserve shutdcwn hours.

1,543,709 11,683,051 85,547,244 9., Gross thermal energy generated (MVd) 476,217 3,655,869 27,487,384 10.

Grcss electrical engergy sencrated (MMI)_

453,611 3,472,706 25,807,654 1,,.

,,et electr.ical energy Generated

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P.ecctor service factor 97.3 77.8 77.6 13 F.esctor cvailabiliCy facter.

97.3 79.4 82.9 14 Unit service factor 95.7 7 6. 2,__,

_73.7 I5 Unit availability facter oz.7 78.0

-7h.o 16.

Uni! capactiy f acar (Using 200) 79.2 61 9 59.4 17 Uni: c,pacicy fc:ter (U s i n g C e s. !',1!c) 77.2 60.3

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.iune 1976 Dochet t!o. 050-254/DPR-29

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Unit One Date 11/8/78 M. Reed Cc;pleted by (309) 654-2241 Telephone f10!?TH October DAY AVERAGE CAlLY PO'.!ER LEVEL' DAY AVERAGE DAILY POWER LEVEL

(!P.le-l'e t)

(MWe-t!e t) 524 1,

17 541 2.

534 18, 615 449 3.

571 19 528 4.

562 20.

560 21 341

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561 22.

361 7.

23, 363 479 24.

410 9.

504 25.

315 10.

562 26.

333

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550 27 358 r

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547 28.

362 368 13 551 29 14.

541 30, 371 404 15.

379 3j, 6-e rt uVED 16.

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On this forr.s. ii:: th: :verar-d si!y unit rav. : !:'.:: in.'.iY.'e ? :t for each day in the r:per:ia; c-Sm9;$8te%

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U:l li - P! '... !.EV E L June 1976 Occhet !!o.

050-265/DPR-30 Unit Two Date 11/8/78 M. Reed Completed by Telephone (309) 654-2241 fl0t;TH October DAY AVERT.Gd CAlLY PO'.!ER LEVEL DAY AVERAGE DAILY POUER LEVEL (Wa-Het)

(MWe-tie t) 1.

-11 17 646 2.

189 18, 672 664 3

403 19 661 4.

471 20.

646

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565 21 604 6.

~ 646 22.

7.

706 23 661 8.

733

- 24.

797 9

723 25 654 10.

720 26.

719 705 11.

720 27 709 721 28.

12, i

727 i

i 13-720 29 14.

463 30.

505 15 31.

507 m. r rt uVED l o,.

3/4, JUil 2 C 1975 1

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.o APPENDIX D QTP 300-S13 UNIT SilVTDOWNS AND POWER REDUCTIONS Revision 5 DOEKLT tl0.

O r>0- ? S h - DP R- ? r)

March 1973 UtilT NAf tE Quad Cities one COMPLETED BY M. Reed II/0#70 REPORT MONTH October 1978 TELEPil0NE (309) 654-2241 DAIL a

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EVENT

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'p ' ' DURATION

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CORRECTIVE ACT10NS/ COMMENTS (110VRS)

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'f.! 5 g REPORT NO.

11 0 DATE R

30 10-8-78 S

NA NA NA NA NA NA Load was' reduced to 450 MWe for condenser flow reversal.

31 10 ')-78 S

NA NA NA NA NA NA Load was reduced to 450 MWe for condenser flow reversal.

37 10-15-78 S

NA NA NA NA NA NA Load was reduced for MSIV bi weekly surveillance and condenser flow reversal.

33 10-4-/8 S

NA NA flA NA NA.

NA Load was reduced to 400 MWe for condenser flow I

reversal.

34 10- 2 ',- / 8 S

flA NA NA NA NA NA Load was reduced to 305 MWe in order to test relief valves and change recirc. MG' Set brushes.

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. (finai)

o APPENDIX D QTP 300-513 UllT 511UTDOWNS AND POWER fiiDUCTIONS Revision 5

00LKET NO. 050-2(,5 DPR-30 March 1973 Quai C i t ies -Two UNIT NAttE COMPLETED BY H. Reed DATE REPORT HONTil TELEPil0HE (309) 654-2241 new mn w

m 5

EU r

m

=

LICENSEE pg g8 fa 8

po DURATION p{3 a-EVENT y8 R: 8 8

CORRECTIVE ACTIONS /C0ttHEilTS (llGURS) y5g REPORT NO.

m il0.

DATE R

24 10-1-78 5

31:45 0

1 NA CC Valves Unit Two remained in the SHUTDOWN mode for the maintenance outage which began on Sept. 29, 1978.

25 10-14-78 S

NA NA NA NA NA NA Unit Two was reduced in load for condensar flow reversal.

2(,

10-31-/8 5

NA NA NA NA NA NA Unit Two was reduced in load from 633 HWe to 500 MW.

to swi tch reactor feedpumps.

. ( f i na l')

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 B.

Control Rod Drive Scram Timing Data A.

MAIN STEAM RELIEF VALVE OPERATIONS:

Relief valve operations during the reporting period are summarized in the following table. The table includes information as to which relief valve was actuated, how it was actuated, and the circumstances resulting in its actuation.

VALVES NO. & TYPE PLANT DESCRIPTION UNIT DATE ACTUATED ACTUATIONS CONDITIONS OF EVENTS 2

10-1-78 2-203-3A 1 Manual Rx Press.

3A VLV TESTED 2-203-3E 1 Manual 200 AFTER FAILURE TO OPEN 9-29-78.

3E VLV TESTED POST MAINT.

(VLV WAS REPLACED)

I 10-26-78 1-203-3A 1 Manual Rx Press Surveillance 1-203-38 i Manual 940 T.S. 4.5.0.1.b l-203-3C I Manual 1-203-30 1 Manual 1-203-3E 1 Manual

B.

CONTROL ROD ORIVE SCRAM TIMING DATA FOR UNITS ONE AND TWO The basis for reporting this data to che Nuclear Regulatory Commission are specified in the surveillance requirements of Technical Specifications 4.3.C.1 and 4.3.C.2.

The following table is a complete summary of Units One and Two Control Rod Drive Scram Timing for the reporting period. All scram timing was performed with reactor pressure greater than 800 psig.

AVERAGE TIME IN SECONDS AT

. Max. Time NUMBER

% INSERTED FROM FULLY WITH)RAWN for 90%

DATE OF RODS 5

20 50 c0 Insertion DESCRIPTION lecnnical specstacation 3 3.G.6 0.375 0.900 2.00 3.5 7

3.3.C.2 (Averace Scram insert. T~

lt _-78 88 0 34 0.71 1.47 2.54 Hot Scram Times, U-2 l

i l

l l

Vil REFUELING INFORMATION The following information about future reloads at quad Cities Station was requested in a January 26, 1978 Ilcensing memorandum (78-24) from D.E. O'Brien to C. Reed e t. al. ti tled "Dresden, quad-Ci ties, and Zion Station - NRC request for refueling information dated January 18, 1978.

l l

l I

l

QTP 300-532 i

Revision 1 quad-CITIES REFUILING Harch.1973 INFORMATION REQUEST 1.

Unit:

1 Reload:

4 Cycle:

5 Januarv 12. 1974 (Shutdown 2.

Scheduled date for next refueling shutdown:

ECC4) i

~

3 Sched'uled 'date for restart following refueling:

Apr'il 12. 1979 (Startup 200' Will refueling or resumption of operatien thereaf ter require'a technical 4.

specification change or other license amandment:

Yes; See attached checklist for Tech. Spec. and License Amendment.

Scheduled date(s) for submitting proposed licensing action and supporting 5

Informa tion: The QC1 R4 IIcensing-submittal is scheduled for'Nov. 11,-1978.

6.

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

' dif fere'nt fuel design or supplier, unreviewed design or performance analysis methoos, significant changes in fuel design, new operating procedures:

New fuel designs:

Retrofit 8 x 8 fuel '(192) a) nat. U at bundle top and bottom,-

b). two larger water rods, c) nev enrichment distribution.

Last Test Assemblies (4)-

s

~

for GE PCI-resistant design. development program.

7 The number of fuel assemblies.

724 a.

Number of assem'alies in care:

ISI b.

Number of assemblies in spent, fuel pool:

l'icensed' spent fuel pool storage capacity and the size of any 3.

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

Licensed storage capacity for spent fuel:

14;e a.

Ncne b.

Planned increase in licensed storege:

s.

The projec:cd d-:ite ci the last refuelingth?.t can bc discherged to :he t :e cresen: liccased ccpa:it,'.

Last refueiing t

spent iv0! j'oc! nssaain; date wi:h present capcci y:

March, SS.

(and o f batch discharge ::ta$i t i:7) t

_1

l QTP 300-S33 RELOAD LICEllSING PACKAGE Revision 1 PREPARATION SCllEDULE Narch 1973 UtilT QI 1(L I.0 All 4

CYCLE r,

4:

.- ACTIVITY DATC RESP 0tlSIBILITY CEtiTER tlFS receives draf t Licensing Submittal f rom GE 1/15/78 GE ilFS Transmit copy of draf t to Station for Comments Transmit NFS and Site comments / questions to GE IlF S Benin Tech. Soec. changcis_5dety Fva.liint lon_and Cowns_.Lc.t t er J/ 2*J/ /8 11F S HFS receives final Licensing Submittal and answers to CECO questions f rom CE GL in CFrh nox t n,:

I anA gas 3 m rg 10/'O/78 HFS i

Complete final NFS review of I leend nn %ihmi t en t J

11/1/78 tlFS Transmit complete package for on/off site review' 11/3/78 Station On-site review completed ll/f>//fi PSA Off-site review comnleted 11/11/71)

ILLA Completed licensino narkana en-a l und by fine g

h-1/12/79 Anticipated. unit shutdown I

90 days 28 days i

'2/9//'l Receipt of operating License N'

Jf t

Anticipated Unit Startup - Assumes 56 day outage 3/9/79 8

weeks 3

14FS/0WR Prepared by Mc Dutc' 12/?y))..

PRELittlNARY CHECKLIST FOR RELOAD LICEMSE NIElicMEMTS UNIT:

quad-Cities 1 i

~

RELOAD:

4 i CYCLE:

5' )

Require Changes i

Jtem

pag, X

Scram Reactivity 4

Generalize wording and reference the submit.

HEDO-XYXYY Safety Valve Setpoints

~

None. Adequate pressure 1.2/2.2-1 margin.

NA LSSS 1.2/2.2-2.3 None, if the' peak vessel

'IA Bases pressure is 1325 psig. during S.V. sizing trans.

RBM Setpoints 3 2/4.2-14 Change to (.65w+XX) as regid.

X LCO 3.2/4.2-7 Change operability to'XX%

3.2/4.2-8 Change Reference I to NEDO-X

' Bases XXXXX.

A'uto Flow Control NA LCO 3 3/4.3-5 flone.

Stability analysis not limiting.

~'

NA Bases 3.3/4.3-11 None.

h i

HAPLHCR X

LCO Fio. 3.5,1

• Revise curves to reflect

('sh e s. I to 3) new analyses.

X Bases 3 5/4.5-14

• Change references to reflect new analyses of NEDO-20046.

MCPR 3 5/4.5-10 New values:

• • 1.XX (7 x 7) 1.XX (3 x 8)

X.

LCO 5

Bases 3 5/h 5-14 ceneralize description of limiting transien:(s).

i

'1** :.' r_5 n p ; are be! g handicd under separa:e co.Tr.

' ;';I le-a: d i t i r.-21 C. X f Co?. panc'.;y ':>r Feel Lc;Jir', Crece A:c:d2r; J 0; i n :c c-t- ' : c s; q r u ition).

QTP 300-532 4

Revision 1 QUAD-CITIES REFUELING llarch 1978 r

.i INFORMATION REQUEST

~

Unit:

2 Reload:

4

_ Cycle:

g (next outage) 1.

September 30,1979_(shu:down Scheduled date for next refueling shutdown:

EOC4) 2.

i.

January' 20.1980 (Startup' Sc'heduled date.for restart following refueling:

BOC5) 3

4. 'Will.' refueling or resumption of operaticn thereaf ter require a technical specification change or other license amendment: Simlar Tech. Spec. changes -

to Reload 3 cycle 4.

Scheduled date(s) for submitting proposed licensing action and supporting j.

Reload Submittal to be provided approximately 90 days prior Informa tion:

to shutdown.

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

..L 6.

Important

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

Retrofit 8 x 8 fuel (approximately 196).

j;'

New fuel designs:

I:

1

[-

's

~.7 The number of fuel assemblies.

a.

Number of assemblies in core:

_724 745 -

b.

Number of assemblies in spent fuel pool:

licensed spent fuel pcol storage capacity and the si:e of any 8.

The preser.t increase in licensed s:crage capacity that has been requested or is planned in number of fuel assemblies:

1460 Licensed stcrage capacity for spent fuel:

a.

None.

h.

Planned increase in licensed storage:

3 The projec:cd da:e of the las: rer cling tha: c:n be discharced to the spent fuel poo! asr.using the cresca: licenscf capacity:

Las refueling da:e.ai:-

pr2sent capacity:

Se,:evher. 3 5_.. -

RELOAD LICENSING PACKAGE QTP 300-S33 Revision 1 PREPARATION SCHEDULE Util r oc 2 lif 1.0AD 3

CYCLL 4

c.

ACTIVITY DATL RLSP0:lSIBILITY CENTER NFS receives draf t Licensing Submictal from CE Transmit copy of draf t to Station 10/6/77 CE llFS for comments.

Transmit NFS and Site comments / ques ions to CE Begin Tech. Spec. changes, Safety NFS 10/20/77 11FS Evaluation and Cover I.etter.

Cl?

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

11/3/_77 TIFS Complete final NFS review of ifcensine Ruhmirrn1 nna answers to Ceco cuestion_

11/8/7/

NFS Transmit complete package for on/off site revieu 11/16//7 St at ion on-stre review comnleted ll/lH/77 1*SA Off/ site review completed 12/1/77 Hl.A Co.npl eted T.icensino packaee receivod by NRC 90 dayo 1/16//n Anticipated unit shutdown 28 days i

1/'>//M Receipt of operating License Day outage g

Anticipated Unit Startup - Assumes.

8 Weeks 1/I'2/78 Prepared by

.TAS.

NFS/ SWR Date 2/?l/78

. (final)

1

'PREL:P.'SAhY C1:dC4 LIST FOR ?.ELOAD LICE;:SE NtE:10P.E!iTS I

U:11T:

0.uad-Citics 2 4~ l 3'

RELCAO:

j CYCLE:

O i

Require Changes

_1 g..>

Page

,i i,

X Scram Reactivity 4

Generalize wording and reference the submit,

}

IIEDO-24063

}.

I l

i. Safety Valve Setpoints 1.2/2.2-1 None.

Adequate pressure NA

'LSSS

\\

margin.

Clarify and add bounding 1 2/2.2-2,3 peak pressure.

Bases RSH Setpoints 3.2/4.2-14 Change to (.65w+42)

X LCO 3.2/4.2-7 Change operability to-30%.

3.2/4.2-8 Change Reference 1 to X

Bases,

N, EDO-24063 Auto Flcw Control None stability analysis 33/4.3-5 MA LCO not 1imiting.

i

'3 3/4 3-11 None-

..A Bases -

MAPLHGR Fig. 3.5.1

• P;evise curves to reflect

-X LCO (shts. I to 3),

ne.s analyses.

3 5/4.5-14

Change references to reflect-X 3ases new analyses of NED0-24046.

t s.

w,...

~

3.5/4.5-10 New values: A*l.33 (7 x 7) ncpa l.35 (3 x 8)

X LCO 3 5/4.5-14 Generalize description of Cases

+-

limiting transient (s).

~

i 1

1

.t s

e ceditier3' C. 5..(

C P E ;;c".a ' t y 'c.r h:1 Leadi.; Errce A :! den; "e

• sf :

J l

l ': i - :c r : -- li:ca;in; c 3 I t '. ; ~ I -

a n

Vill CLOSSARY The following ebbreviation which may have been used in the MontN'y Report, a re defined below:

Control Rod Drive System CRD Standby Liquid Control System SSLC Main Steam isolation Valve MSIV Residual Heat Removal System RHRS Reactor Core isolation Cooling System RCIC High Pressure Coolant injection System HPCI Source Range Moni tor SRM Intermediate Range Moni tor IRM Local Power Range Monitor LPRM Average Power Range Monitor APRM Traveling incore Probe TIP RBCCW Reactor Building Closed Cooling Vater System TBCCW Turbine Building Closed Cooling Water System RWM Rod Worth Minimizer Standby Gas Treatment System S3GTS HEPA High-Ef ficientry Particula te Fil ter l

Reactor Protection System RPS Integrated Primary Containment Leak Rate Test IPCLRT LFCI Los Pressure Coolan t injection Mode of RMoS I

RBM Rod Slock Monitor EWR Boiling Water Reactor In-Service inspectien ISI MFC Maximum Permi s sab te :encantra tica L

I s*

~

/

y,-

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

Dryweil DW Reactor RX Electro-Hydraulic Control System EHC Minimum Cri tical Pcwer Ratio MCPR Precondi tioning Interim Operating Management PCIOMR Recommendations LER Licensee Event Report

+

American National Standards Institute ANSI National Insti tute -for,0ccupa tion i Safety.and NIOSH Health Atmospheric Containment Atmospheric Dilution / Containment ACAD/ CAM Atmospheric Moni toring

.