ML20086L657

Revised Monthly Operating Repts for Oct 1989 for Quad Cities Nuclear Station,Units 1 & 2,consisting of Refueling Info

ML20086L657
Person / Time
Site:	Quad Cities
Issue date:	10/31/1989
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20086L639	List: ML20086L635 ML20086L644 ML20086L648 ML20086L657
References
NUDOCS 9112170026
Download: ML20086L657 (3)

Text

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QTP 300-532 Revision 2 QUA0 CITIES REFUELING October 1989 INFORMATION REQUEST 1

Unit:

41 Reload:

11 Cycle: __ __12 2.

Scheduled date for next refueling shutdown:

9-5-92 3.

Scheduled date for restart following refueling:

12-5-92 4.

Will refueling or resumption of operation thereaf ter require a Technical Specification change or other license amendment:

UOT AS YET DETERMINED.

5.

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

NOT AS YET DETERMINED.

r

~

6.

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

NONE AT PRESENT TIME.

i t

7.

The number of fuel assemblies, a.

Number of assemblies in core:

724 b.

Number 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:

L j~

a.-

Licensed storage capacity for spent fueli 3657 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 _Ilcensed capacity:

2009, APPROVED-( ' " "

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QTP 300-S32 Revision 2 QUAD CITIES REFUELING October 1989 INFORMATION REQUEST 1.

Unit:

02 Reload:

10 Cycle:

11 2.

Scheduled date for next refueling shutdown:

01/01/92 3.

Scheduled date for restart following refueling:

03/11/92 4.

Hill refueling or resumption of operation thereafter require a Technical Specification change or other Ilcense amendment:

Yes, as listed below:

1. Remove Table 3.7-2

2. Modification to turbine control valve fast acting solenoid valve.

3. Modification to llPCI turbine exhaust steam line.

4. IIPC1/RCIC 94-hour shutdown action provision.

5.

Scheduled date(s).'or submitting proposed licensing action and supporting /92 informatism:

1. 01/15

2. 04/18/91

3. 06/28/91

4. 12/31/91 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 o# fuel assemblies, a.

Number of assemblies in core:

724 b.

Number of assemblies in spent fuel pool:

2287*

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:

3697 b.

Planned increase in licensed storage:

0 9.

The projected date of the last refue.ing that can be discharged to the spent fuel pool assuming the present 'icensed capacity:

2009

• 152 new fuel assemblies in new fuel vault.

APPROVED I

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OCT 3 01989 l

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

v VIII. GLOSSARY 4

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

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

- American National Standards Institute APRM

- Average Power Range Monitor ATHS

- Anticipated T1ansient Without Scram BHR

- Soiling Hator Reactor CRD

- Control Rod Drive EHC

- Electro-Hydraulic Control System i

EOF

- Emergency Operations facility GSEP

- Generating Stations Emergency Plan HEPA

- High-Efficiency Particulate filter HPCI

- High Pressure Coolant Injection System HRSS

- High Radiation Sampling System IPCLRT

- Integrated Primary Containment Leak Rate Test j

IRH

- Intermediate Range Monitor i

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 HAPLHGR - Maximum Average Planar 1.1near Heat Generation Rate MCPR

- Minimum Critical Power Ratio HTLCPR

- Hax1 mum Fraction Limiting Critical Power Ratto HPC

- Maximum Permissible Concentration MSIV

- Main Steam Isolation Valve NIOSH

- National Institute for Occupational Safety and Health PCI

- Primary Containment Isolation PCIOMR

- Preconditioning Interim Operating Management Recommendations RBCCH

- Reactor Building Closed Cooling Hater System i

RBH

- Rod Block Honitor RCIC.

- Reactor Core Isolation Cooling System RHRS

- Residual Heat Removal System RPS

- Reactor Protection System RHH

- Rod Horth Minimizer SBGTS

- Standby Gas Treatment System SBLC

- Standby Liquid Control SDC

- Shutdown Cooling Modelof RHRS SDV

- Scram Discharge Volume SRM

- Source Range Monitor-TBCCH

- Turbine Bu11 ding Closed Cooling Hater System TIP

- Traversing Incore Probe TSC

- Technical Sepoort Center i

l TS 14

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