ML20203D819

Revised App D of Monthly Operating Rept for Oct 1997 for Quad Cities Nuclear Power Station,Unit 2

ML20203D819
Person / Time
Site:	Quad Cities
Issue date:	10/30/1997
From:	Sirles K COMMONWEALTH EDISON CO.
To:
Shared Package
ML20203D798	List: ML20203D795 ML20203D808 ML20203D819
References
NUDOCS 9712160298
Download: ML20203D819 (7)

Text

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APPENDIX D Rev. 1 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET 80. 50-265 UNIT NAME Two COMPLETED BY fristal Sirles DATE November 7. 1997 REPORT MONTH October 1997 TELEPHONE 309-654-2241 m

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N gM m o E W$ LICENSEE o DURATION S EVENT CORRECTIVE ACTIONS / COMMENTS NO. DATE (HOURS) REPORT V7-12 971001 F 72.0 11 4 - ----- ---- --

Continuauon of Safe Shutdown issues.

97 13 971004 S 552.0 A 2 ------ --- --- Conunenced Q2P01 to Replaced Leaking Fuct Bundle.

97-14 971027 F 121.0 11 4 ------- --- --- Continuaton of Safe Shutdown issues.

t Last month 9713 was reported as 522.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />. The correct number is 552 Ohours.

9712160298 971210 PDR ADOCK 05000254' R PM

p VI. UNIOUE REPORTING REQUIREMENTS The following items are included in this report based on prior commitments to the commission:

A. Main' Steam Relief Valve Operations There were no Main Steam Relief Valve Operations for the reporting period.

2 B. Control Rod Drive Scram Timina Data for Units One and Two .

The basis for reporting this data to the 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.

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. s r RESULTS OF SCRAM TIMING MEASUREMEMTS ' '

l PERFORMED ON UNIT 1 6 2 CONTROL . .

ROD DRIVES, FROM 01/01/97 TO 11/30/97 j j AVERAGE TIME IN SECONDS AT % l MAX. TIME l l l ' INSERTED FROM FULLY WITHDRAWN l FOR 90% ,

!  !  ! INSERTION DESCRIPTION

! i- NUMBER l 5-  ! 20 t 52 1 90  ! l Technical Specification 3.3.C.1 & ,

l DATE  ! OF RODS I 0.375 ! O.900  ! 2.00  ! 3.5  ! 7 sec.  ! 3.3.C.2 (Averaae Scram Insertion Times i \ i 1 l 1 i .

2/17/97 l 14 l 0.314 0.712 1.528 l 2.671 3.010 l STT for Viton Issue'U-1 (Core Wide Ave. Times) ,

l l l l 6 (J-14) l

! I 1 1 I l 3/29-31/97 l 21- l 0.316 1 0.708 l 1.513  ! 2.645 i 3.010- l STT for Tech Spec (19) (Core wide Ave. Times)_'

l l  ! l l l (J-14) .! PMTV (2) ,

! l i 1 W  !  !

4/35/9"t j 1 l 0.29 i O.64  !.1.37 l 2.4 j 3.010 l Post Maintenance Test for Accumulator Replacment i l l ll l (J-14) l Unit 1

!  ! .i j i 5/31/97 l 14 l 0.354 0.725 '1.497  ! 2.576 , 2.77 i STT for Viton Issue.- U1

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(G-15) 'l

! l l  !  ! l 'l l l l l  !  !

! 6/23/97 l '13 l 0.297 j 0.681 j 1.478 l 2.615 l 2.95 Post Outage Scram Test Timing and PMTV - U2 l l l 'l l l (M-12) l l 1 l l l l G/29/97 i 4 0.278 l' O.630 1.348 ' 2.350 2.46 1 Post Outage Scram Testing and PMTV - U2

! (P-6) l i l a l l 7/16/97 1 .l 0.280 ,l 0.630 , 1.324 .

2.306 l 2.306 l PMTV - U2

, j j j l (N-6) a l- l l I 7/20/97 l 32 l 0.312 l 0.701 l, 1.497 l 2.617 l 2.67 TS & SSPV Testing U-1 t l l l l l l (G-15) l l l 1  ! l 9/18/97  ! 14 0.312 0.702 j 1.499 l 2.621  ! 2.77 i STT for Viton Issue U-1 i l L l l l (G-14) l l .

l  ! l l; 11/01/97 l 1 0.29 0.62 1 1.13 '

2.3 2.850 PMTV U-1 l . l ,

(D-11) .

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11/13/97 l 34 0.351 0.731 l 1.501 '

2.593 l 2.3 l TS & SSPV Testing U-1

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! (P-5) l '

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VII. REFUELING INFORMATION The following information about future reloads at Quad-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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• QTP 0300-S32 Rsvicion 3 April 1997 QUAD CITIES REFUELING INFORMATION REQUEST

1. Unit: 01 Reload: 14 cycle: 15

2. Scheduled date for next refueling shutdown: 9/05/98

3. Scheduled date for restart following refueling: 10/15/98

4. Will refueling or rerumption of operr. tion thereafter require a Technical Specification change or other license amendment Yes

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

November, 1997

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:

Approx. 216 SPC 9X9IX Fuel Bundle s Q1R15 will be loaded.

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7. The number of fuel assemblies.

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a. Number of assemblies in core: 724

b. Number of assemblies in spent fuel pools 1933

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:

a. Licensed storage capacity for spent fuel 3557

b. Planned increase in licensed storage O

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity: 2002 (final) 1

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QTP 0300-832

. R3 vision 3 April 1997 l

QUAD CITIES REFUELING INFORMATIOh REQUEST ,

s j 1. Units 02 Reload: 14 cycle: 15

) 2. Scheduled date for next refueling shutdowns 9/25/99 j 3. scheduled date for restart following refueling: 10/31/99 i t

j 4. Will refueling or resumption of operation thereafter require a Technical specific atior. change or other license amendments j Yes b

• j 5. Scheduled date(s) foi submitting proposed licensing action and

< supporting informations Augu s t ,. 1998 i

6. Important licensing considerations associated with refueling, e.g., new 1

or different fuel design or supplier, us. reviewed design or performance ,

aralysis methods, significant ci,anges in fuel design, new operating procedures

i i

N/A

. i 1

j. 7. The number ". fuel assemblies.

L. Number of assemblies in core 724

b. Number of assemolies in spent fuel pool: 2943

! 8. The present licensed spent fuel pool storage capacity and-the size of F any increase in licensed storage capacity that has been requested or is planneo in number of fuel assemblies

a. Licensed storage capacity for spent fuel 3897

b. Planned increase in licensed storage _

0

9. The projected date of the last refueling that can .

i be discharged to the spent fuel pool assuming the present licensed capacity: 2002 t

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( , (final) 2

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VIII. GLOSSARY l

The following abbreviations which may have been used in the .

Monthly Report, are defined below: l ACAD/ CAM - Atmospheric Containment Atmospheric Dilution / containment Atmospheric Monitoring i ANSI - American National Standards Institute APRM - Average Power Range Monitor ATWS - Anticipated Transient Without Scram BWR - Boiling Water Reactor CRD - Control Rod Drive EHC - Electro-Hydraulic Control System EOF - Emergency Operations Facility GSEP - Generating Stations Emerger.cy Plar.

HEPA - High-Efficiency Particulate Filter HPCI - High Pressure Coolant Injection System HRSS - High Radiation Sampling System IPCLRT - Integrated Primary Containment Leak Rat" Test IRM - Intermediate Range Monitor ISI - Inservice Inspection LER - Licensee Event Report LLRT - Local Leak Rate Test LPCI - Low Pressure Coolant Injection Mode of RHRs LPRM - Local Power Range Monitor MAPLHGR - Maximum Average Planar Linear Heat Generation Rate MCPR - Minimum Critical Power Ratio MFLCPR - Maximum Fraction Limiting Critical Power Ratio MPC - Maximum Permissible Concentration MSIV - Main Steam Isolation Valve NIOSH - National Institute for occupational Safety and Health PCI - Primary Containment Isolation PCIOMR - Proconditioning Interim Operating Management ReCoF T,endations RBCCW - Reactor Building Closed Cooling Water System RBM - Rod Block Monitor RCIC - Roactor Core Isolation Cooling System RHRS - Residual Heat Removal System RPS - Reactor Protection Sys'em RWM - Rod Worth Minimizer SBGTS - Standbf Gas Treatment System SBL. - Standby Liquid Control SDC - Shutdown Cooling Mode of RHRS SDV - Scram Discharge Volume SRM - Source Range Monitor TBCCW - Turbine Building Closed Cooling Water System TIP - Traversing Incore Probe TSC - Technical Support Center TirHOM\NRC440NTHLYMT