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Text

Monthly Operating Repts for Oct 1991 for Quad-Cities Units 1 & 2
	ML20079P546
Person / Time
Site:	Quad Cities
Issue date:	10/31/1991
From:	Losekshort C, Tietz G; COMMONWEALTH EDISON CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GCT-91-16, NUDOCS 9111130046
	Download: ML20079P546 (26)
	v • d • e

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GCT-91-16 l

November 5, 1991 U. S. Nuclear Regulatory Commir.ston ATTN: Document Control Desk Hashington, D.C. 20555

SUBJECT:

Quad Cities Nuclear Station Units 1 and 2 Honthly Performance Report B C Docket Nos. 50-254 and 50-265 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 October 1991.

Respectfu11(,

COMMONKALTH EDISON COMPANY QUAD..:ITIES NUCLEAR POWER STATION f( A$ n G. C. T1 tz Technical Superintendent GCT/CALS/dak Enclosure 2

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A. B. Davis, Regional Administrator T. Taylor, Senior Resident Inspector i

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QUAD-CITIES NUCLEAR POWER STATION UNITS 1 AND 2 HONTHLY PERFORMANCE REP 0kI OCTOBER 1991 COMMONHEALTH EDISON COMPANY AND IDHA-ILLIN0IS GAS & ELECTRIC COMPANY l

NRC DOCKET NOS. 50-254 AND 50-265 i

LICENSE NOS. DPR-29 AND DPR-30 l

TS 14

l TABLE OF CONTENTS I.

Intradettion II.

Summary of Operating Experience A.

Unit One B.

Unit Two III.

Plant or Procedure Changes, Tests, Experiments, and Safety Re ste i

Maintenance A.

Amendments to Factitty License or Technical Specificat!6nt B.

Facility or Procedure Changes Requiring NRC Approval C.

Tests and Experiments Requiring NRC Approval D.

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 Po. r Redur.tions e

VI. Unique Reporting Requirements A.

Main Steam Relief Valve Operations B.

Control Rod Drive Scram Timing Pata VII.

Refueling Information VIII. Glossary TS 14

1.

]MIRODUC110h Quad-Cities Huclear Power Station is composed of two Boiling Hater Reac"Jrs, each with a Maximum Dependable Capacity of 769 MWe Net, located in Cordova, Illinois.

The Station is jointly owned by Commonwealth Edison Company and Iowa-Illinois Gas & Electric Company.

The Nuclear Steam Supply Systems are General Electric Company Boiling Hater Reactors.

The Architect / Engineer was Sargent & Lundy, Incorporated, and the pilmary construction contractor was United Engineers & Constructors.

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, 1971, respectively; pursuant to Docket Humbers 50-254 and 50-265.

The date of initial Reactor criticalities for Units One ard Two, resptctively were October 18, 1971, and Apri' 26, 1972. Commercial generation of power began on February 18, 1973 for Unit One and March 10, 1973 for unit Two.

This report was compiled by Cynthia A. Losek-Short and Debra Kelle'y, telephone number 309-654-2241, extensions 2938 and 2240.

TS 14

II.

SUMMARY

OF OPERATING EXPEE1ERCE A.

Unit One Unit One began the month of October operating at full power.

Load drops occurred on the 9th and lith as requested by Chicago Load Dispatch.

Load drops occurring on the 1st and the 15th were for Heekly turbine testing. Other load drops occurring in the month of October were on the 4th, 12th, 22nd, 20th and the 29th.

These load drops were for the IC2 Extraction Steam Valve work, RCIC/HPCI Monthly Vent.

Verification, Turbine Generator Monthly testing, ERV Surveillance, and fer Main Turbine Thrust Wear Detector work, respectively.

B.

Unit _lxo Unit Two continued to be shutdown due to a MSIV failure which occurred the previous month.

The unit went critical on 10/8/91 at 0020 and the generator went back on line the same day at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br />.

Load drops that occurred on the 21st and the 28th were both for 2C3 Heater LCV work.

s I

w TS 14

III.

PLANT OR PROCEQURE__CliANGEL TEST 5mEPERitiENIL AND SAFEILRELATED MAINTENANCE A.

Amendments _to facility _ License or Technical Specificationi Technical Specification Amendments No. 132 and No. 127 were issued on September 25, 1991 to facility Operating Licenses DPR-29 and DPR-30, respectively, for Quad Cities Nuclear Power Station.

This amendment revises the Technical Specification to reflect the changes relative to pressure / temperature operating limits for both Quad-Cities units.

B.

EAC111ty or PrntedEt_ Changes _ Requiring NRC._Appro111 There were no facility or Procedure changes requiring NRC approval fc-the reporting period.

C.

leits_anLExp eriment LRe q uirin9_NRC_Aparanl There were no Tests or Experiments requiring NRC approval for the reporting period.

D.

Correttive Maintenance.Sf_ Safety Relattd_Laulpment The following represents a tabular summary of the major safety related maintenance performed on Units One and Two during the reporting period.

This summary includes the following:

Work Request Numbers, Licensee Event Report Numbers, Components, Cause of Halfunctions, Results and Effects on Safe Operation, and Action Taken to Prevent Repetition.

TS 14

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UNIT 1 MAINTENANCE SUh'_%RY HORK R200ESI SYSTEM EID DESCRIPTION lfQRK PERFtatiED 096187 7502 Replace the Pre-Hepa filter on As Found: Hold down clamps were s11ghtly loose the "A" Standby Gas' Treatment and filters were dirty. As Left: Installed four train.

f11ters, and tightened all hold down clamps.

Q95371 7541 Repair "A" Standby Gas Treatment As Found: Set point change was needed. As Left:

Heater doesn't trip off on low Calibrated and adjusted set point.

flow as it should.

' Q95967

'0590 Received Channel 5 half scram due As Found: It appears to look like there was a to LPRM spike on APRM #5.

Relay voltage drop across. coll, caused by the contacts 590-1000 problem.

for discharge volume H1 Level. Found the 1-302-82H switch to be ci.attering excessively. As Left: Replaced chattering switch with new switch and performed QIS 25-1.

095964 0750 Repair U1 IRM.12, which is broken As Found:

Indication was downscale with no I

and keeps blowing fuses.

chassis light. As left: Replaced test fuse with approved 3/4 amp slow blow and installed new pre I

regulator from stores and adjusted voltages.

Q73104 0756 Repatr LPRM which drifts high and Ran TDR traces, also cleaned conrectors checked cannot be calibrated; card ok.

Q95146' 1053 Replace test fitting on RHR As Found: Found the test fittings for pressure Pressure. Switches which stripped switches 1-1053E, 1-1053F and 1-1053J stripped out.

out. As left: Replaced the test fittings and caps for pressure switches 1-1053E, 1053F and 1053J while performing QIS 22-2.

i 092334 2402 Replace PCV-2 pressure regulator As Found: Out of service Regulator #2 and Flow on hydrogen analyzer reagent gas Indicator #2 to be replaced. As Left: Replaced line.-

Flow Indicator #2 and Regulator #2.

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UNIT 2 M471 LNANCE_SUMl RY HORK P10 MESI SYSTEM EID DESCRIPTION HCRK PERFORMEQ Q95324 0203 Inspect and repair 2-0203-1B Main As Found: Visual examination of internals Steam Isolation valves.

following bonnet removal showed the following:

the disc nuts and nut locks were located at the bottom of the disc; the stem had separated from the main disc. As left:

Installed limit switches and hardware 28 had a bent arm on switch. A1!

valve internals were replaced and the valve was reassembled with new packing and gasket.

Q95773 0203 Investigate and repair U2 18 MSIV As Found: The 2B limit switch arm was bent. As limit switches which didn't give Left: Replaced 2B limit switch arm with new and 1/2 scram signal when fuse was adjusted plate and limit switch arms for 107., made l

removed.

sure 1A limit switch picked up before 28 did.

Q95685 0203 Investigate problems with U2 28 As Found: Actuator had worn parts, with dry,a and Outboard HSIV :ctuator.

dirty o-rings. As left: Parts were cleaned and lubricated then reassembled and installed.

Q95325 0203 Inspect and r % r U2 2B Hain As Found: Found outside of valve to be in good I

Steam Isolation valve.

condition and #3 lock tap is loose approximately l

1/8" of washer. All locking tabs were locked in l

place properly. As Left: Disassembled and J

reassembled valve for inspection. Also locked all I

eight new lock tabs down in the proper order to j

retain nut movement.

095684 0203 Investigate problems with 2C As Found: Actuator had E n parts, with dry and outboard MSIV actuator.

dirty o-rings. As left: Parts were cleaned and lubricated then reassembled and installed.

TS 15

UNIT 2 MAINTENANfE_

SUMMARY

lORK PERFCRMFJ H

HORK REOUESI SYSTEM EID DESCRIPTION 095630 0203 Replace Electromatic R.V. pilot As Found:

Found the pilot bushing to be hitting valve 2-203-3C.

on the pilot bracket while trying to operate.

This would make the pilot want to stick. As Left: Cleaned the valve body Internals, also installed new flex gasket and new rebuilt pilot valve. Rotated bracket assembly 180 degrees from original location and the bracket went on easier.

Operated the valve to see if any binding was present none was evident.

Q95774 0220 Repair breaker for steam line As Found:

The control power transformer was found drain valve.

burnt up.

As left:

Installed new transformer and taped connectors.

Q95785 0312 Investigate and repair U2 CRD HCV As Found: Accumulator was leaking.

As left:

46-55 has high water leakage and Changed out accumulator with new one.

cannot be drained down.

l 095771 0312 Repair U2 Control Rod 18-39 which As Found:

Scram inlet valve was leaking by seat.

drifts in past 00, suspect As Left: Adjusted seating pressure for valve and I

leakir.g scram inlet valve.

checked spring tension which was ok.

094004 2252 Investigate and repair 02 monitor As Found: 02 span was low and found leaky needle which won't span to the 7 percent valve. As left: Repaired needle valve and calibration gas.

swapped Hydrogen 2 ampilfter circuit board with one from 2A Drywell H202 Analyzer.

Q95981 2303 Investigate and repair U2 HPCI As Found:

Found mercury bulb had fallen out of gland seal hotwell pump which clip and was hanging by wires from terminal cycles on and off when in auto.

block. As left: Put mercury bulb back into c11p and glued into place with insulating varnish.

Checked for operability pump passed.

095871 4641 There was an air leak between As Found:

There was air leaking by at fitting on receiver tank and pressure switch line between receiver tank and pressure switch.

2-4611-42A's isolation valve.

As left: Removed damaged tubing and fitting.

Replace fitting.

Tubing was broken off in male connector due to repeated tightening on the stripped threads of the connector. Also replaced the connector when T2 1@

making up the__new tubing.

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IV.

LEEEfLlyENT REP 0 BIS

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yi The fol kwing is a tahd ar summary of all licensee event reports for

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-6 Dr.!-Cities Units One a.:d Two occurring during the reporting period, pursuant

, op to the reportable occurrence reporting requirements as set forth in sections 6.6.B.1 and 6.6.B.2 of the T V -

al Specifications.

L UhlL1 Licensee Event Recort Number Dgig Tit 1e of Occurrence 91-019 10/05/91 Control Room HVAC Inop due to imprcper Equipment Configuration and partially fouled HEPA filters.

91-M0 09/19/91 Hissed Tech Spec Surveillance for P: combiner Outlet Temperature /Rx Power.

j 91-021 10/25/91 RCIC Inop from exceeding IST Max Flow Rate.

I 5

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91-011*

09/iB/9i

Cor<: Spray & RCIC declared Inop because

'ar fn er drain ch'ck valves failed test.

Thi was cancelled this month.

91 011 10/15/91 HPCI Inop from Gland Hotwcli Dump Cycling On and Off.91-012 10/07/91 Manuci (Full) Rx Scram from 3C Electromatic Relief Valve Opening.

91-011 Report for the Month of September 5as been cancelled.

TS 14

1 9

V.

DATA TABULATIORS 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 I

f I

l TS 14 w

APPENDIX C OPERATING DATA REPORT DOCKET NO. 50-254 UNIT 0" OATE 11/4/91 COMPLE1 ED EY Cvnthia 1.osek-Short l

TELEPHONE 309-654-2241 OPEHATING 8TATUS 0000 100191 700 2400 101191 Gross HOURS IN REPORTING PERIOO:

1. REFORTING PtRIOD:

2511 M AX. DEPEND. CAP ACITY (m 769

2. CURRtNTLY AUTM.T'?ID POWER LEV EL (WWti:

DESION ELECTRICAL RATING (WNah 794 N/A

3. POWER LEVEL TO WHICH RES1 RICTED (IP ANY) (bh Neth

4. REASONS POR RESTRICTION tlP ANYh THIS MONTH YMTO OAft CUMULATIVE 744.0 3731.0

__135212.9 S. NUMBER OF HOURS REACTOR WAS CRITICAL 0.0 0. 0__

1421.4

s. REACTOR RESERVE SHUTDOWN HOURf.

744.0 1604.3 130471.6

7. HOURS GENERATOR ON LINE..,

s. UNIT RESERVE SHUTDOWN # CUR $

O_O nn 000.o

9. GROSS THERMAL ENERGY GENERATED (MWHI

.........1799091.0 8386140.0 281117SRo.0

10. GROSS ELECTRICAL ENERGY GENER AT*.D (WWH)....

590626.0 2717923.0 91111777.0 6W08.0, 898W.0

11. NET ELECTRICAL ENERGY GENERATED (NYTH) 100.0 51.1 78.9

12. r EACTOR SERvlCE P ACTOR.....

100.0 51.I 9n 9

13. REACTOR AVAILABILITY PACTCO 100.0 49.4 76_6

14. UNIT SERVICE F ACTOR.........

100.0

~49,4 76.9

15. UNIT AVAILAtluTY P ACTOR,.

98.1 46.5 65.t If UNIT CAPACITY P ACTOR tueng MDC1 95.6 45.1 63.4

17. UNIT CAPACITY P ACTOR tum6 Deatn WWel......

0.0_

18.7 5,6 1E. UNIT PORCED Ot/7 AGE RATE...

19. SHUTDOWNS SCHEDULIO OVER NEXY 6 MONTHS (TYPE. DATE. AND DURATION OF EACW';

M. IP SHUT DOWN AT END OF REPORT PERIOD. ESTIM ATED D ATE OF STARTUP:

21. UNITS IN TEST STATUS IPRIOR TO COMMERCI AL OPERATIONh POR EC AST ACHIEVED INITI AL CRITICALITY INITI AL ELECT 2l CITY COMMERCI AL OPERAT10N 1.169 z

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- APPENDIX C l

l OPERATING DATA REPORT 00CXET NO, 50-265 i

UNIT D.

I 11/4/91 l

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COMPLETED 8Y Cynthia Losek-Short i

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- TELEPHONg 309-654-2241 l

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OMRATING STATUS 0000 100191 M

2400 103191 anogg No.,.=

. =ap..wlNo PsMioO:

1. REPORTING PERICO.

?511 u A...-.. 3.CApactTy im, 769

2. CURRENTL1 AUTHOR 12EO POWER LEVEL g%I DE880N ELECTRICAL RATING IMWe eeed:

N/A

3. POWER LSVEL TO WHecM RESTRICTED tiP ANY) (MWo.Ned:

4. REAa0NE POR RSSTRICTION llP ANY):

THIS MONTH YA TO DATE C.'48ULATIVS S. NUMSSR OF MOURS REACTOR M4 CRITICAL..........

575.7_

6329.5 132018.7 0.0 0.0-2985.8

4. REACTOR RESERVE SMUTDOWN MOURS...................

561.9 6267.9 128554.9 i

7. MouR$ GENERATOR 0N LINE..........................

l 0

O_

0^0 7n9 - o E. UNIT RESERVE SMUTDOWN MOURS,......

I

9. GROSS THERMAL ENEROY GENERATED (MWM)........... 1135637.0 14325186.0 277556507.0

10. GROSS ELECTRICAL ENERGY GENER ATED (WWM)........... 371425.0- 4641787.0 89102994.0

11. NET ELECTRICAL ENERGY GENERATED (WWM)

.,. 2.58528.0: 4487596.0- 84 '11 a 14 9 - 0 77.4 R6.A 77.7

12. 8' F ACTOR SE *VICE P ACTOR.......................

77.4 8 6. 8 --

74.5;

13. REACTOR AVAILABILITY PACTOR......

75.5_

-85.9 75.7 le. UNIT SERVICE P ACTOR,.......................

75.5 85.9 76.1

15. UNIT AV AILAtiLITY P CTOR.............

64.6 5 2.3__

80 3

18. UNIT CAPACITY F ACTOR (Uelne MOC) :............,......

51.' 3 _

78.0 62.9

17. UNIT CAPACITY 8 ACTOR (Uung Dame WWeel.......,.....

23.0 11 1._

8.I it UNIT PORCEO QUTAGE RATE,..

13. SMUTDOWNS SCMEDULED OVER NEx* $ MONTHS ITYPE. DATE. AND OURATION OF E ACIC:

1 l

20. IF SMUT DOWN AT EMt; CP REPORT PERICO. E5flMATED CATE OF STARTUP:..

21. UNIT 5 IN TEST I'ATUS IPRIOM TO COMMERCI AL OPERATICNh

'PORECAST ACMIEVED INITI AL CRITICALITY INITIAL ELECTRICITY.-

l-COMMERCIAL OPERATIC 90 l

1.16 9 l

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OCORRECTION FJR AUGUST 1991 APPENDIX C OPERATING DATA REPORT DOCKET NO.

50-265 WO UNIT DATE 9/3/91' COMPLETED BY Cynth!n Losek-Sho_rt 309-654-2241 TELEPHONE OPERATING 8TATUS 50000 080191 743 g,,,,o,7,,,pg,,og.52400 083191 GRo88 HOUM8 IN REPORTING PERIOO:

2511 max. oEPEND. CAPACITY (MWHemi. _769

2. CURRENT 1.Y AUTHORIZED POWER LEVEL (mwd:7 83 DEtlCN ELECTRIC AL RATING IWWo.Ned:

3. POWER LEVEL TO WHICH RFETRICTED (IP ANY1 (MWo.Ned:

N/A A. REASONS POR RESTRlCTION (19 ANY):

THIS MONTH YM TO DATE CUMULAT1VE 744.0 5316.6 131005.8 L NUMSER OF HOUR 8 REACTOR WAS CRITICAL...............

0.0 0.0 2985.8_

E. R EACTOR RESERVE SHUTDOWN MOURS...................

744.0 5268.8 127555.8

f. MOuRs GEN ER ATOR ON LINE..........................

0.0

_ 0. 0 702,9

8. LNIT RESERVE SNUTDOWN W)UR$................

1728727.0 12235885.0 275467206.0

9. CROSS THERMAL ENERQY f>EMERATED (MWr0 558938.0 3960947.0 8842?154 '1

to. Gross ELECTRICAL ENERC Y GENER ATED (WWHI...........

540179.0 3831949.0 836624 % Q

11. NET ELECTRICAL EN2RO't CENERATED (MWM) 100.0 91.2 77.8

11. ** E ACTO R SE RVIC'4 'r '.CTOR...........................

100.0 91.2 79.6

13. REACTOR AV AILABILITY PACTOR..

90.3 75.8

14. U NIT S ERVIC E P ACT 7R..............................

.0

%.3 M.2 ts. UNIT AVAILAslL'7 P ACTOR.............

94.5 d5.4 64.6 '

it. UNIT CAPActTY P ACTUR (U*g MD: 3...............

92.I 83._3_

63.0

17. UNtf CAPACITY PACTOR (Uung Demon WWel.....

0.0 9.2 7.9

18. 'JNIT PORCEQ QUTACg Rt.YE..,.........,,....,,,,,,

19. SHUTDOWNS SCHEDULED QVER NEXT S MyNTHS (TYPE DATE. ANO DURATION OF EACHit

20. IP SHUT DOWN AT Ehc OF REPORT *ERIOD ESTIMATED QATE CP STARTUP:

21. UNIT 3 IN TEST STATUS (PRIOR TO COMMERCI AL QPERATIONh PORECAST ACHIEVE *3 INiT1AL CRITICALITY k

INITIAL FLECTRICITY

@JdE!.t's AL OPERATtON 1.16 9 X

APPENDIX is -

AVERAGE DAILY UNIT POWER 12 VEL 9

DOCKET NO. 50-254 UNIT one DATE 11/'/91 COMPLETED BY Nn*W i n ak-sho TELEPHONE 309-654-2241:

MON 11g october 1o91-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe&t) -

803 i;

800 g

769 goo 2

gg 804 801 3

gg 799 4

799 20 79b 5

617 21-804-a g

p,7 805 671 7

g 800 798 8

24 758 798-g g

800 798 l

10 28 760 702 gg 27 615 787 12 g

79E-759 13 3

l 696 798 3

9 792

'787 gg -

y-785 16 INSTRUCTIONS On this form, hat the average dady unit powet level in MWWet for each day m the reporting month.Compuis to the :

neascst whole megawatt.

These fit;ures will be used to plot a graph 'or cash reporting month. Nute that when munimum dependable Capucity as uwd for the net eteetncal rating ut the unit. there may be onasions when the daily average power level exceeds the 1073 hoc for the restrwted power Icut hnc). In sve.h cases, the average d.uly unat power output sheet abould be '

footnoted to caplaua the apparent anomaly.

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q APPENDIX B AVERAGE DAILY UNIT POWhR LEVEL DOCKET NO.126s UNIT Two

. DATE 11-4-91 COMPLETED BY evnthin tor.ek-shor:

TELEPHONE 309-654-2241 MON 1H Oc t *e r 1991 DAY AVERAGE DAILY POWER LLVEI.

DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe Net) -

1

-7 17 646

-7 644 3

- gg

-7 3

gg

'641

-7 4

20 642

-7 5

21 650

~7 4

23 633

-7 7

22 662 3

59 24 -

6'^

g 544 M

613 601 10 745 as 616-gg 7 0',

p 621 12 654 g

13 656 616 g

652 14 703 g

'642 15

' '8 7 21 18 6T{.

1 INSTRUCflONS '

On this form, hst the average daily umt power newt m MWeNet for each day m the reporting month. Compute to the ~

neassst whole megawatt, Thew figures will be used to plot a grgh for cash reporting month. Nute that when maximum dependable capacity n.

u.ed lor the net clesmcal ratmg ut the umt, there may be oseassons_wheti the daily averagg power level exceeds the 1001 lee (or the restrwted power level ime). In such caras, the awrage daily urut power output shest shouid be footnoted to explana the apparent anomaly, l.!M e

JM A

APPENDIX D UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-254 COMPLETED BY Cynthia A. Losek-Short UNIT Nt.NE One DATE Novamber 4,'I991 REPORT MONTH October. I991 TELEPHONE 309-654-2241 as ooO h

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CORRECTIVE ACTIONS /COf9ENTS REPORT NO.

NO, DATE (HOURS)

Load Reduction for Weekly Turbine Test-91-10 100291-S 4.9 B

5 Load Reduction for 1C2 Extraction Steam 91-11 100'491 F.

11.9

'A 5

Valve Work

.j HPCI/RCIC Monthly Vent Verificaiton 91-12 101191'

'S' 5.0

.' B.

5 91-13.

101591 S

_2.8 B

5 Load Reduc <i'n.for Weekly Turbine Test Load Reduction for Mootly Turbine 91 102291 S'

6.1 B

.5.'

Generator Test Load Reduction for ERV Surveillance 91-15 102691 S-3.3 B

5 Load Reduction for Main Turbine Thrust-91-16 102991=

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6.2

_B 5

Wear Detector Vork 1

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t APPENDIX D UNIT SHirTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-265

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' UNIT NAME Two COMPLETED BY Cynthia A. Losek-Short DATE November 4, 1991 REPORT MONTH October 19DI TELEPHONE 309-554-2241 f

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91-29 102191 S

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91-30 102891 S

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e VI. UN1QUE REPORIING_REMIREBERIS The following items are included in this report based on prior commitments to the commission:

A.

Main Stjam Relief Valyg_Qperations 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.

Unit: One Date. October 27, 1991 Valves Actuated No. & Tv.ps of Actuation 1-203-3A 1 Marual 1-203-3B 1 Manual 1-203-3C 1 Manual 1-203-3D 1 Manual 1-203-3E 1 Panual EJagt Conditions:

Reactor Pressure - 955.5 PSIG kescr10 tion of Events: Operating Surveillance, QCOS-203-3, Main Steam Relief Valve Operability Test.

Valve 1-203-3B did not open, that valve will be retested at a later date.

Un11:

Two Date: October 7, 1991 Valve Actuated:

2-203-3C No. & Tyne of Actuation:

1 Automatic Plant Condition 1:

Reactor Pressure - 63 psig, Start Up Liode Descriotion of Eventi:

While starting up Unit Tvo, per QGP 1-1, the 3C ERV came open inadvertently.

TS 14 l

Un11:

Two Data: Oc tober 8,1991 ya!ves Actuated:

do. L Tvoe cf Jctuation:

2-203-3A 1 Ma.lual 2-203-38 1 Manut.1 2-203-3C 1 Manu11 2-203-30 1 Manual 2-203-3E 1 Hanual EJant Conditlan1:

Reactor Pressure - about 900 psig Descriotion of Eventi: Operating Surveillance, QCOS-203-3, Main Steam Relief Valve Operability Test B.

Contrpl_ Rod Drive SCIam Timina Data for Units One and Two The basis for reporting this data to the Nuclear Regulatory Commission are specified in the surveillence 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.

l TS 14

RESULTS OF SCRAM TIMING MEASUREMENTS PERFORMED ON UNIT 1 & 2 CONTROL RGD DRIVES, FROM 1-1-91 TO 12/31/91 AVERAGE TIMd IN bECONDS AT %

MAX. TIME INSERTED FROM FUuLY WITHDRAWN FOP. 90%

INSERTION DESCRIPTION NUMBER S

20 50 90

[

Technical Specification 3.3.C.1 &

DATE OF RODO. 0.375 0.900 2.00 3.5 7 sec.

3.3.C.2 (Averace Scram Insertion Time) i 1-30-91 1

0.28 0.63 1.37 2.45 11 - 7 U2 scram timing for accumulator replacement (2.45) on 11-7

)

1-30-91 1

0.30 0.72 1.53 2.57 F-6 U2 scram timing for accumulator replacement (2.67) on F-6 4-30-91 22/177 0.29 0.67 1.46 2.57 11-11 Ul, liot Scram Timing during Start Up (3.0)

Sequence A&B, Cycle 12 (Paritial) 5-2-91 177 0.29 0.67 1.44 2.55 R-10 U1 Start Up Scram Timing Begin Cycle 12 (3.27) 5-5-91 89 0.31 0.fd 1.43 2.51 B-4 U2 Scram Timing For Sequence A (2.84) 5-6-91 1

0.26 0.62 8.40 2.52 E-12 Ul Scram Timing for WR on Scram Light (2.52)

L 7-12-91 4

0.27 0.62 1.33 2.38 N-12 UI Wort Requests for fccumulator Replacement (2.42)

/-17-91 1

0.28 0.62 1.32.

2.32 K-6 U2 Scram Outlet Fr i. lure (2.32) 10-8-91 2

0.32 0.70 1.5 2.72 E-10 U2 for WR Accumulator / Scram Valve (2.89) l l

l scrmtim l

l

4 1

VII.

REfilELiffG. IN'OMAI1ON The following information about future reloads at Quau-Cities Station was requested in a January 26, 1978, licensing memorandum (78-24) from D. E. O'Brien to C. Reed, et al., titled "Dresden, Quad-Cities and Zion Station--NRC Request for Refueling Information", dated January 18, 1978.

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A

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4 ac 2

TS 14 I

e QTP-300-532 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

Q1 Reload:

11 Cycle:

12 2.

Scheduled date for next refueling _ shutdown:

s 9-5-92 3.

Scheduled date for restart following refueling:

12-5-92 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment' NOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

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:

NONE AT PRESENT TIME.

7.

The number of fuel i.ssemblies.

a.

Number of assemblies in core:

724 b.

Nur.ber of assemblies in spent fuel pool:

1405=

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:

Licensed 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:

2009

(

APPROVED t

14/0395t

-1 0519 Q.C.O.S.R.

(

s QTP 300-532 Revision 2 QUAD CITIES REPJELING

-October 1989 INFORMATION REQUEST 1.

Unit:

02 Reload:

10 Cycle:

11 2.

Scheduled date for next refueling shutdown:

12-28-91 3.

Scheduled date for restart following refueling:

3-7-92 4.

Will refueling or resumption of operation thereafter require a Technical Specification change or other Itcense amendment:

NOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performar.ce analysis methods, signfficant changes in fuel design, new operating procedures:

NONE AT PRESENT TIME.

t 7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2237

8.

The present licensed spent fuel _ prol storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned in number of fuel assemblies:

Licensed storage capacity for spent fuel:

a.

3897 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refueling that can'be discharged to the spent fuel.;xyal assuming the present licensed capacity:

2009 In addition, 78 new fuel assemblies are presently' stored in the new fuel storage (dry) vault.

APPROVED 14/0395t O.C.O.S.R.

,5 i

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

ACAD/ CAM - Atmospheric Containment Atonspheric Dilution / Containment Atmospheric Monitoring ANSI

- American National Standards Inst 1 tete APRM