ML19340C789

Monthly Operating Repts for Nov 1980

ML19340C789
Person / Time
Site:	Quad Cities
Issue date:	12/01/1980
From:	Tubbs R COMMONWEALTH EDISON CO.
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ML19340C787	List: ML19340C786 ML19340C789
References
NUDOCS 8012170449
Download: ML19340C789 (25)

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 MONTHLY PERFORMANCE REPORT NOVEMBER 1980 COMMONWEALTH EDISON COMPANY AND IOWA-ILLINOIS GAS & ELECTRIC COMPANY NRC DOCKET NOS. 50-254 AND 50-265 I

LICENSE NOS. DPR-29 AND DPR-30 l

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8012170 'fsf4

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 B.

Facility or Procedure Changes Requiring NRC fpproval C.

Tests and Experiments Requiring NRC Approval D.

Corrective Maintenance of Safety Related Equipment IV.

Licensee 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 Vill. Glossa ry l

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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 MWe net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and towa-1111nois Gas S Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Bolling Water Reactors.

The Architect / Engineer was Sargent & Lundy, incorporated and the primary construction contractor was United Engineers & Constructors. The con-denser 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 humbers 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 power began on February 18, 1973 fo.- Unit I and March 10, 1973 for Unit 2.

This report was compiled by Becky Brown and Robert Tubbs, telephone number 309-654-2241, extensions 245 and 174.

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II.

SUMMARY

OF OPERATING EXPERIENCE 4

A.

UNIT ONE November 1-30:

Unit One remained shutdown for the entire reps ting period for End of Cycle Five Refueling Outage.

P t

B.

UNIT TWO November 1-3:

Unit Two began the reporting period holding a load of 811 I

j MWe and held an average load of 809 MWe until 2300 on November 1 At that time load was reduced to perform weekly turbine tests, reverse con-denser flow, and change control rod pattern. On November 2 load aas in-creased until 1050 when the reactor scrammed on APRM High Flux, due to the 2A Recirc Pump MG Set experiencing a speed transient.

The reactor was brought critical at 2056 that same day, and the generator put on-I line at 0246 on November 3 Power was increased at 100 MWe/ hour until at 0555; a Recirc Pump B seal cooling water low flow alarm was received.

2B Recirc Pump was secured, with load held at 280 MWe. The unit was then shutdown, tripping the generator off-line at 1133 on November 3, to effect repairs to a leaking B Recirc Pump Suction valve, MO-2-202-4B.

November 4-6: During this three day period, the reactor was shutdown to repair B Recirc Suction valve and perform other maintenance until 2247 on November 6, when the reactor was brought critical.

November 7-11: On November 7, at 0633, the generator was synchronized and load increased until a load of 450 MWe was held at 1050, per the Nuclear Engineer.

At 1300 load was increased at various rates until 5 MWe/ hour was reached at 1430. This rate was maintained until maximum recire flow was achieved at a load of 640 MWe, on November 8 at 1045 Load was dropped to 450 MWe at 0030 on November 9 to change the control i

I rod pattern and the lord was again increased at 5 MWe/ hour.

On Novenber 10, at 0800,.ne rate was increased to 7 MWe/ hour, until load was held at 820 MWe on November 11 at 1010. At this time the load was held steady at 820 MWe, using rod movement to override the Xenon transient, for the remainder of this period.

November 12-15:

Over this four day period an average load of 819 MWe was held.

November 16-17: At 0400 on November 16 load was reduced to 400 MWe at 75 MWe/ hour to perform maintenance on a malfunctioning RCIC valve. At 0915, HPCI was declared inoperable, and per Technical Specification, a manual shutdown was initiated.

At 1145 both HPCI and RCIC were restored to service and load was held at 360 MWe. At 1340 load was increased at various rates, until a rate of 5 MWe/ hour was reached at 1840. The rate was increased to 7 MWe/ hour at 0830 on November 17 until a load of.825 was reached and held.

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November 18-21: Over this four day period an average load of 822 MWe was held. At 2300 on November 21 load was dropped to prepare for shutdown on November 22.

November 22-26: At 0600 on November 22, the turbine was tripped off-line and at 0655 the reactor was placed in Hot Standby in order to repai r the "B" Recirc Suction Valve. At 1040 the reactor was brought critical, and on November 23 at 0426 the generator was put on line and load was increased to 400 MWe at 100 MVe/ hour.

At 1200 load was again increased, maintaining a rate of 5 MWe/ hour until 0500 on November 26 when a load of 800 MWe was held, due to reaching maximum recire flow limit..At 0800 rods were pulled to increase load to 820 MWe.

November 27-29:

During this three day period an average load of 816 MWe was held, November 30: At 0015 load was dropped to 700 MWe for weekly turbine tests.

Load was increased at various rates until 820 MWe was held at 2200 ending the reporting period.

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PLANT OR PROCEDURE CHANGFS, TESTS, EXPERIFjENTS, AND SAFETY RELGTED_

MAINTENANCE A.

Amendments to Faciilty License or Technical Specification Amendments to Licenses DPR-29 and DPR-30 Per Order Dated 10/24/80.

These amendments were issued pursuant to Orders for Modification of Licenses for Licenses DPR-29 and DPR-30.

This change is a result of the Commission Memorandum and Order of May 23, 1980, which required the NRC staff to codify the documentation requirements for the qualification of safety-related electrical equipment.

These Tech Spec changes included two items:

(1)

By 6/30/82, all safety-related electrical equipment shall be environmentally qualified.

(2)

By 12/1/80, documentation is to be available, at a central location, which shows the methods use?,to qualify safety-related electrical equipment.

This documentation is to be retained for the life of the plant.

B.

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

C.

Tests anj__E~periments Requ'.-Ing NRC Approval There were no tests or experiments requiring NRC approval for the reporting period.

D, Corrective Maintenance of Safety Related Equipment l

l The following represents a tabular summary of the safety i

related maintenance performed on Unit One and Unit Two during l

the reporting period.

The headings 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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Ut'IT Oi1E_ 11AliiTENAtlEE SuttMARY CAUSE i'ESUdS c E6LCTS U.R.

LER OF ON ACT10:1 U o

t!U!! DER NUMBER COMPONENT MALFUNCTION FAFE GPERATIOM PREVC'IT n

IMI Q08268 80-26/03L 1/2 Diesel Cooling Faulty Motor Sent out motor for repair Installed motor &

Water Motor 1/2-and re-install.

wired; tested.

Q08805 80-29/0'IT 1A Electromatic Special in-Inspect penetration &

Magnetic particle in-Blowdown line I-spection 105 cibow for in-spection performed 3019A-8"M dications.

satisfactory.

l Q08806 80-29/0lT IB Electromatic Special in-Inspect penetration &

Magnetic particle in-Blowdown line 1-spection 105o elbow for in-spection performed l

30198-8"M dications.

sa t i s fac to ry.

Q08807 80-29/0lT IC Electromatic Special in-Inspect penetration &

Magnetic particle in-Blowdown line 1-spection 105 elbow for in-spection performed 3019C-8"M dications.

satisfactory.

Q08UO8 80-29/0lT ID Electromatic Special in-Inspect penetration &

Magnetic particle in-Blowdown line l-spection 105 elbow for in-spection performed 3019D-8"M dications.

satisfactory.

Q08792 80-29/0lT IE Electromatic Crack indication The indications were Work request was Blowdown line 1-observed due to caused by construction initiated to repair 3019E-8"M improper con-while unit was shutdown.

the pipe and penetra-struction

tion, techniques.

Q07527 80-21/03L Drywell Exhaust Valve needed Valve failed leak rate Adjusted valve and re-Valve A0-1-1601-adj us ting test.

tested satisfactory.

23 Q05984 IB RPS Set Out-Faulty circuit Circuit breaker wil1 Replaced circuit put Circuit breaker not close.

RPS system breaker & tested.

Breaker supplled from backup i

power source.

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UNIT OrlE MAIMTE!!.1NCC SUltitARY ChbSE Rt.SULIS S LFFLCfS U.R.

LER OF CN ACT!DN Ti -

9 h U ".3 E R NUN 3ER C 0.".: 'O M U4T tDLTUNCT10N SAFE OPERATION PRT!:::T n

~.. ; C.1 Q07523 80-22/03L HPCI Turbine Area Faul ty temperature Switch found out of high Replaced temperature Hi Temperature swtich setpoint limit.

switch with like; Switch 1-2371A tested.

Q08167 SRM Detector Faulty cable SRM reads downscale.

Installed 100 ohm Cabic, SRM connector.

resistor at preamp Chunnel 23 Damaged sec ton end of cable.

Replaced of cable.

cable connector under vessel.

Remated &

tested.

Q08168 SRai Detector Faulty cable SRM reads downscale, iistalled 100 ohm 1

Cable, SRM connector.

resistor at preamp Channel 21 Damaged section end of cable.

Replaced of cable.

cable connector under vessel. Reraated &

tested.

Q08175 SRM Detector Faulty cable SRM reads downscale.

Installed 100 ohm Cable, SRM connector, resistor at preamp Channel 22 Damaged section end of cable.

Replaced of cabic.

cable connector under vessel.

Remated &

I tested.

Q08174 SRM Detector Faulty cable SRM reads da nscale.

Installed 100 ohm Cable, SRM cornector.

resistor at preamp Channel, 24 Damaged section end of cable.

Replaced of cable.

cable connector under vessel.

Remated &

tested.

UNIT ONE MAINTENtJ:CE SUitMARY CAUSE RESULTS 5 EFFECTS U.R.

LER OF ON ACTIC'i T/aEN TC NUM3ER NUMBER COMPCNENT MALFUNCTION SAFE OPERATION Pr. EVENT prPETIT!CN Q08165 lRM Detector Faulty cable IRM reads downscale.

Installed 100 ohm Cable, IRM connector, resistor at g tamp Channel 16 Damaged section end of cable.

Replaced of cable.

cable connector under vessel.

Remated &

tested.

Q08164 IRM Detector Faulty cable IRM reads downscale.

Installed 100 ohm Cable, IRM connector.

resistor at preamp Channel 17 Damaged section end of cable.

Replaced of cable.

cable connector under vessel.

Remated &

tested.

Q08163 1RM Detector Faulty cable IRM reads downscale, installed 100 ohm Cable, IRM connector.

resistor at preamp Channel 18 Damaged section end of ca' ale.

Peplaced cable connector under of cable.

vessel.

Remated &

tested.

Q09041 Standby Gas Faulty contacts.

When SBGT train was Replaced auxiliary Discharge shutoff, the valve did contacts in main 1/2-7507A not auto close.

breaker.

Q07483 Head Spray Broken line.

Pac _kiag drain line is Installed nipple and Valve 1-1001-63 broken off at packing cap.

Re-tapped threads gland.

prior to inserting nipple.

UNIT ONE MAINTENANCE

SUMMARY

1 CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q08954 Cleanup Suction Faulty torque Valve will only partially Replaced torque Valve Outboard switch.

close to get a dual in-switch; tested.

1-1201-5 dication.

4 Q07535 80-21/03L Drywell Purge Valve disc was Valve failed local leak Adjusted valve and Valve A0-1-1601-out of adjustment.

rate test.

re-tested satisfactory.

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Q09052 CRD 14-47 Faulty accumu-Continuous high water Installed new accumu-i lator.

level alarm was present, lator; tested.

q07860 80-21/03L Feedwater Check Faulty parts.

Valve failed local leak Disassembled valve, Valve "A" Loop rate test.

cleaned, replaced "0" l-220-62A and seal rings; torqued; tested.

q07534 80-21/03L Outboard Feed-Faulty parts.

Valve failed local leak Replaced disc and ring; water Check Valve rate test.

made two welds; torqued 1-220-62B and tested.

4 Q09274 CRD 50-51 Accumu-Bad accumulator.

Accumulator has frequent Installed new accumu-lator Hi water level alarms.

lator.

Q04530 RCIC Steam Supply Valve seat was Valve leaks.

Lapped seat in valve M0-1-1301-61 cut and leaking body at new sur.f. ace through.

on valve plug; tested.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q04906 LPRM 40-33A, 40-Faulty connector.LPRM 40-33A went high Replaced LPRM connector; 25A

& stayed high while tested.

maintenance was re-placing CRD at 34-35 Q08881 Inboard MSIV-Faulty "0" rings.

Pilot block was leaking Replaced two "0" rings 2-203-1A instrument air.

on pilot block.

Q08848 Retirc Valve Loose bolts on Valve bonnet leak.

Torqued bonnet bolts 7-202-4B valve bonnet.

to 3300 ft/lbs.

Fermanited flange; tested.

Q08289 Main Steam Shorted Temper-Received 1/2 of a Group Replaced temperature Tunnel Temper-ature Switch.

I isolation on Channel switch, with like for ature Switch "A" ma:n steam tunnel like; tested.

high temperature.

Relay 595-101A is dropped out.

Q08296 IRH 17 Found no p.oblem.

The full out light in-Found no problem; dication does not light

tested, when IRM appears to be full out.

Q09166 80-31/0lT RCIC Pump Faul ty Torque Valve will not open from Changed torque switch Discharge Switches.

Control Room.

and cleaned controls 2-1301 on limit switches.

Q09076

.MCC 28-3 Main Feed.

MCC 28-3 keeps Replaced main feed 480 VAC Breaker tripping.

breaker at Bus 28 defective.

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UNIT TWO MAINTENANCE

SUMMARY

CAUSE RESULTS & EFFECTS W.R.

LER OF ON ACTION TAKEN TO NUMBER NUMBER COMPONENT MALFUNCTION SAFE OPERATION PREVENT REPETITION Q09169 80-32/01T HPCI Turbine Stop Cracked cover on HPCI system was in-Replaced cover with Valve M0-2-2301-3 valve hydraulic operable.

identical cover and operator.

tested.

Q0(274 SRM Channel 23 Bad capacitors.

SRM gave erratic Replaced capacitors readings at short C2, C4, and C6 for periods.

SRM 22 & 23; tested.

Q05242 LPRM 48-33D Bad connector.

LPRM is pegged up-Replaced connector scale & gives APRM and tested.

Hi HI Q09167

.HPCI Speed Failed electro-Controller acts Rei.

4 MOSFET in Control 2-2340-1 ic components, sluggish.

Controls op. a.

ested.

flow at 600 gpm above setpoint.

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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 Spr-ifications.

UNIT ONE Licensee Event Report Number Date Title of Occurrence 80-29/0lT 11-03-80 C rack in ' E' Elect ro-matic Line Penetration 80-30/03L 11-04-80 1/2 'A' Diesel Fire Pump Out of Service Greater than 7 Days 80-31/03L 11-24-80 Main Steam Line Low Pressure Switch (1-261-30D)

UNIT TWO 80-31/01T 11-16-80 RCIC Inoperable 80-32/0lT 11-16-80 HPCI Turbine Stop Valve Oil Leak 80-33/03L 11-24-80 A0-1-1601-32F. Unit 2 Sepp ress i or. Chamber to l

Drywell Vacuum Breaker Dual Indication 1

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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 t

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OPERATING DATA REPORT l

\\

DOCKET NO.

50-254 I

UNIT ONE DATE_ December 1,1980 COMPLETED BY R C Tubbs TELEPHONE 309-654-2241. ext 174 OPERATING STATUS 0000 110100

1. Reporting period:2400 113080 Gross hours in reporting period:

720

2. Currently authorized power level (MWt): 2511 Max. Depend copocity (MWe-Net): 769* Design electrical rating (MWe-Net): 789 3.

Power level to which restricted (it any)(MWe-Net): NA 4.

Reasons for restriction (if any):

This Month Yr.to Dote Cunulotive 5.

Number of hours reactor was critical 0. 0_

5725.1 60439.2 6.

Reactor reserve shutdown hours 0.0 0.0 3421.9 7.

Hours generator on lin-0. 0_

5623.1 57664.0

8. Unit reserve shutdow.i h u 'i r s.

0.0 0.0 909.2 9.

Gross thernal energy generated (MWH) 0 11394718 115938699

10. Gross electrical energy generated (MWH) 35 3662846 37285900

11. Net electrical energy generated (MWH)

-2642 3358241 34773777

12. Reactor service factor 0.0 71.2 80.6

1. 3. Reactor availability factor 0.0 71.2 85.1

14. Unit service factor 0.0 69.9 76.9

1. 5. Unit ovallobility factor 0.0 69.9 78.1

16. Unit copocity factor (Using Des.MWe)

.5 54.3 60.3

17. Unit capacity factor (Using MDC)

.5 52.9 58.7

18. Unit forced outage rate 0.0_

3.6 7.8

19. Shutdowns scheduled over next 6 nonths (Type,Date,and Duration of coch):

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

__ -29_-80 I2

_____9 8The MLC ncy te Icwer than 769 M'Je during periods of high cnbient tenerature due to the therncl perfornuce of the spray cenal.

OPERATING DATA REPORT DOCKET NO.

50-265 UNIT TWO D ATE December 1,1980 COMPLETED BY R C Tubbs TELEPHONE 309-654-2241, ext 174 OPERATING STATUS 0000 110180 1.

Reporting period:2400 113080 Gross hours in reporting period:

720

2. Currently authorized power level (MWt): 2511 Max. Depend capacity (MWe-Net): 769* Design elect.ical roting (MWe-Net): 789 l

3.

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

Reasons for restriction (if any):

l This Month Yr.to Date Cumulative 5.

Number of hours reactor was critical 623.0 5056.8 58185,7 6.

Reactor reserve shutdown hours 0,0 0.0 2985.8 7.

Hours generator on line 590.6 4869.7 55661.5 8.

Unit reserve shutdown hours.

0.0 0.0 702.9 9.

Gross thernal energy generated (MWH) 1306085 10852830 113868939

10. Gross electrical energy generated (MWH) 424374 3425110 36288160 j

li. Net electrical energy generated (MWH) 395711 3212980 33965505

12. Reactor service factor 86.5 62.9 78.5

13. Reactor ovallobility factor 86.5 62.9 82.5 l

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14. Unit service factor 82.0 60.6 75.1 I

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15. Unit availability factor 82.0 60.6 76.1

16. Unit copocity factor (Using Des.MWe) 71.5 52.0 59.6

17. Unit capacity factor (Using MDC) 69.7 50.6 58.1

18. Unit forced outoge rate 18.0_

7.1 9.1

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

20. If shutdown at end of report period,estinated date o f s tor t up

___NA 3Th2 fLC nc7 he lower then 767 L'e duririg perieds of high ambient te=perature due to the thern21 perforn:nce of the sprcy canal.

i APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.90-254 UNIT ONE 1

~

DATE December'1, 1980 COMPLETED BY R C Tubbs

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TELEPHONE 309-654-2241, ext 174

.i HONTH N o v e mb e r-1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) i 1.

-2.1 17.

-3.6

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~~

~~ ~

~

~

2.

-2.3 18.

-3.6 1

3.

-2.3

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-3.4 i

4.

-2.5 20.

-3.8

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5.

-3.5 21.

-3.5 6.

-3.5

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--4.2 7.

-3.6 23.

-5.7 J

B.

-3.4 24.

-5.4 f

.9..

-3.5

__. 2 5. _

-4'6 i

10.

-3.2 26.

-4.4

.._._e.

11.

-3.9 27.

-3.0

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-2.8

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-4,1 13.

-2.6 29.

-4.5 15.

-3.7 4

16.

-3.5 i

INSTRUCTIONS

- On this ferri, list the average daily snit power level in $le-Net for each day in the reporting nonth.Cenpete to the nearest while neacultt.

T.Sse figures Will be ssed to olet a crcph fer each reporting nonth. Note that when nexinn dependable concity is

?

use.1 for the net electrical rating of'tr.e Unit there nay be occasions when the daily cretage power level exceeds the -

ill& line (or the restricted power level line),In such cases,the average daily init pewer output sheet should be footr.ated to explain the cpparent enanaly i

r

-y-we_r.,.w+w.,-,-m w.w..

-t-s y m w~ w w,-,w e 's +

e-e t w e*+-e -

-r-e.e-+-ew---

=-

e-,m'-*e--w-rrm-+we**e-*-e s**-we,6-_v-*rew -e-v v =e w *-tve* + -re -r e w i,e w-r w w-

-****-vrns

-ur v * * +- w-e

APPENDIX B AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-265 UNIT TWO DATE Decernber 1, 1980 COMPLETED BY R C Tubbs TELEPHONE 309-65-42241, ext 174 NONTH November 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe "It)

(MWe-Net) 1.

774.6 17, 727.1 2.

187.3 18.

754.9 3.

54.7 19, 763.1 4.

-12.0 20.

765.4 5.

-12.0 21.

769.7 6..

-12.0

22..

66.0

'7.

309.4 23, 323.6 8.

568.5 24, 544.1 4

9.

504.4 25..

658.8 10, 618.8 26.

776.6

~~

11.

754.5 27.

749.8

.12.

762.6 28.

763.2 13.

775.1 29.

768.9 14.

762.7 30, 722.6 15, 770.4 t6.

527.3 INSTRUCTIONG On this fern, list the overage hily unit power level in M'h-Net for each day in the reporting.sonth. Compete to the acorest while recewstt.

These figures will be used ta plot c arc;h for ecch reporting ranth. Note that when sciine.1 depenhble ccoccit!s the is used for tr.e t.et electrical r2 ting of~tne sait,there nay be cccasiens wr.en the daily cvercae ocwer level excee 100% line (or the restricted sc.ier level line).In such cases,the averege dcily unit pewer iotput sheet should be fostnoted to explain the app: rent oncn11y

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(3 APPENDIX D QTP 300-513 UNIT SliUTDOWNS AND POWER REDUCTIONS Revisio3 5 DOCKET NO.

50-265 March 1978 quad-cities Unit Tw U. NIT NAME COMPLETED BY R C Tubbe D c mber 1, 1980 DATE REPORT MONT11 NOVEMBER 1980 TELEPHON-309-654-2241, ext. 174 3

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$g M

LICENSEE yo DURATION I t;; 5 EVENT

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(HOURS)

NO.

DATE yIy REPORT NO.

8 CORRECTIVE ACTIONS /COMMEt,TS om 19 801102 F

15 9 G

3 CB-INSTRU Reactor scrammed on APRM High Flux, due to Reci rc Pump MG Set Speed Transient

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20 801103 F

91.0 A/B 1

CB VALVEX Shutdown to repair leaking Recirc Suction Valve, and perform other miscella.icous work items 21 801116 F

0.0 A

1 80-32 SF VALVEX Initiated shutdown due to simu'taneous mal-functions in the RCIC and HPCI systems 22 80T122

'F 22.4 A

1 CB VALVEX Reactor shutdown to repair leakage Reci rc Suction Valve 4

4 4 0

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VI.

UNIQUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

i A.

Main Steam Relief Valve Operations There were no Main Stear Relief Valve Operations during the reporting period.

B.

Control Rod Drive Scram Timing Data for Units One and Two There were no Control Rod Drive Scram Timings for the reporting period.

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REFUELING INFORMATION The following information about t,*ure reloads at Quad-Cities Station was requested in a January 26, 1978, li:ensing memorandum (78-24) f rom 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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t QTP 300-S32 Revision 1 QUAD-CIT 1.IS REFUELING Harch 1978

_(. -

li:FORMAf;0N REQUEST

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s 1.

Unit:

1 Reload:

6 Cycle:

7 2.

Scheduled date for next refueling shutdewn:

9-12-82 (Shutdown _EOC6) 3 Scheduled date for restart following refueling:

12-5-82 (Startup BCC7) 4.

Will refueling or resumptien of operation thereafter require a technical specification change or other license amendment:

No, Plan 10CFR50.59 reloads for future cycles of Quad Cities Unit 1.

The review will be conducted in August, 1982.

5 scheduled date(s) for submitting proposed licensing action and supporting Information: August, 1982 for 10CFR50 59 related changes rv 90 days pr.*or to shutdown.

. 6.

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

' different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuci design, new operatii.2 procedures:

New fuel d.esigns:

7 The number of fuel assemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblics in spent fuel pool:

820 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:

4 a.

Licensed storage capacity for spent fuel:

1460 b.

Planned increase in licensed storage:

None 9

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: September, 1985 (end of batch discharge capability)

- APR 2 01973 Q. c. c. s. R.

~

L QTP 300-S32 Revision 1 QUAD-CITIES REFUELING March 1978

.(-

INFORMATION REQUEST 1.

Unit:

2 Reload:

5 Cycle:

6 2.

Scheduled date for next refueling shutdown 8-30-81 (Shutdown EOC5) 3 Scheduled date for restart following refueling:

12-20-81 (Startuo 80C6) 4.

Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment:

No, Plan 10CFR50.59 Reloads for futur'e cycles of quad Cities Unit 2.

The review will be conducted by early August, 1981.

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

Information: Early August, 1981 for 10CFR50.59 related changes os90 days prior to shutdown.

6.

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

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

New Fuel Design:

1.

Barrier Fuel 2.

Control Cell Core

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7 The number of fuel a.ssemblies.

a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

672 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:

t a.

Licensed storage capacity for spent fuel:

1460 b.

Planned increase in licensed storage:

None 9

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

September, 1984--

(End of batch discharge capability)

APPROVED (g APR 2 01973 (3. C:. (). S. Ft.

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

1 CRD Control Rod Drive System Standby Liquid Control System SBLC MSIV Main Steam isolation Valve RHRS Residual Heat Removal System Reactor Core isolation Cooling System RCIC HPCI High Pressure Coolant injection System SRM Source Range Monitor IRM Intermediate Range Monitor LPRM Local Power Range Monitor APRM Average Power Range Monitor TIP Traveling incore Probe Reactor Building Closed Cooling Water System RBCCW TBCCW Turbine Building Closed Cooling Water System RWM Rod Worth Minimizer SBGTS Standby Gas Treatment System HEPA High-Efficiency Particulate Filter j

RPS Reactor Protection System IPCLRT Integrated Primary Containment Leak ite Test LPCl Low Pressure Coolant injection Mode c RHRS RBM Rod Block Monitor BWR Boiling Water Reactor ISl In-Service Inspection Maximum Permissible Concentration MPC PCI Primary Containment i solation SDC Shutdown Cooling Mode or RHRS LLRT Local Leak Rate Testing MAPLHGR Maximum Average Planar Linear Heat Generation Rate RO Reportable Occurrence DW Drywell RX Reactor EHC Electro-Hydraulic Control System MCPR Minimum Critical Power Ratio PCl0MR Preconditioning Interim Operating Management Recommendations LER Licensee Event Report 4

ANSI American National Standards insititute NIOSH National Institute for Occupational Safety-and Health ACAD/ CAM -

Atmospheric Containment Atmospheric Dilution / Containment Atmospheric Monitoring Anticipated Transient Without Scram ATWS SDV Scram Discharge Volume TSC Technical Support Center l

EOF Emergency Operations Facility HRSS High Radiation Sampling System GSEP Generating Stations Emergency Plan P----

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