ML20076K474

Rev 3 to Catawba Unit 2 Cycle 7 Colr

ML20076K474
Person / Time
Site:	Catawba
Issue date:	10/24/1994
From:	Clark R, Elder M DUKE POWER CO.
To:
Shared Package
ML20076K468	List: ML20076K465 ML20076K474
References
CNEI-0400-25, CNEI-0400-25-R03, CNEI-400-25, CNEI-400-25-R3, NUDOCS 9411010181
Download: ML20076K474 (5)

Text

CNEI-0400-25 Page 1 of 19 Rev. 3

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Catawba Unit 2 Cycle 7 Core Operating Limits Report October 1994 Duke Power Company DATE PREPARED BY: /fdi' h fo/z</[NM CHECKED BY: 4 269/

APPROVED BY: L 2Vocf9Y QA CONDITION 1 NOTE This document does not contain information that affects the results and conclusions presented in the C2C7 Reload Report, Safety Analysis.

9411010181 941024 PDR ADOCK 05000414 '

P PDR

Cctawba 2 Cycle 7 Core Operating Limits Report CNEI-0400-25 Page 2 of 19 Rev.3

( INSERTION SHEET Remove Insert pages 1-302; rev. I pages 1-19; rev. 2 I pages 1-4,19; rev 2 pages 1-4,19; rev 3 l

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Catawb2 2 Cycle 7 Core Operating Limits Report CNEI4)400-25

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( REVISION LOG 1 Revision Effective Date Comment OriginalIssue 15 February 1993 C2C6 COLR 'I Revision 1 14 April 1994 C2C6 COLR rev.  !

Revision 2 19 May 1994 C2C7 COLR l Revision 3 24-October 1994 C2C7 COLR rev l

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Cctawba 2 Cycle 7 Core Operating Limits Report CNEI-0400-25 Page af19 l Rev. 3 <

r 1.0 Core. Operating Limits Report 7 This Core Operating Limits Report (COLR) for Catawba Unit 2, Cycle 7 has been prepared _

- in accordance with the requirements of Technical Specification 6.9.1.9. '

The Technical Specifications affected by this report are listed below:  ;

2.2.1 Reactor Trip System Instrumentation Setpoints +

3/4.1.1.3 Moderator Temperature Coefficient .

3/4.1.2.5 Borated Water Source - Shutdown .

3/4.1.2.6 Borated Water Source - Operating 3/4.1.3.5 Shutdown Rod Insertion Limit 3/4.1.3.6 Control Rod Insertion Limit t 3/4.2.1 Axial Flux Difference 3/4.2.2 Heat Flux Hot Channel Factor 3/4.2.3 Nuclear Enthalpy Rise Hot Channel Factor 3/4.3.3.11 Boron Dilution Mitigation System i 3/4.5.1 Accumulators 3/4.5.4 Refueling Water Storage Tank 4.7.13.3 Standby Makeup Pump water supply - Boron Concentration  ;

3/4.9.1 Refueling Operations - Boron Concentration '

( 3/4.9.2 Instrumentation l

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.- , Csuwba 2 Cycle 7 Core Oper ting Limits Rtport CNEI-0400 *

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( . Refueling Water Storage Tank maximum boron 2,275 ppm )

concentration, for LCO 3.5.4b l

3.11 Instrumentation (Specification 3/4.9.2) 3.11.1 Reactor Makeup Water Pump Flowrate Limit:

Apolicable Mode Limits Mode 6 s 70 gpm 3.12 Refueling Operations - Ibron Concentration (Specification 3/4.9.1) 3.12.1 Minimum ;oron concentrations for the filled portions of the Reactor Coolant System and the refueling canal. Applicable for mode 6 with the reactor vessel head closure bolts less than fully tensioned, or with the head removed.

Parameter Limit Refueling boron concentration for the filled portions of the 2175 ppm

( Reactor Coolant System and the refueling canal, for LCO 3.9.1.b.

3.13 Standby Makeup Pump Water Supply - Horon Concentration (Specificatio.. 4.7.13.3) 3.13.1 Minimum boron concentration limit for the spent fuel pool, or a contained borated water volume (rneeting additional requirements of surveillance  :

4.7.13.3.a.2). Applicable for modes 1,2, and 3.

Parameter Limits Spent fuel pool minimum boron concentration, for 2175 ppm '

surveillance 4.7.13.3.a.1 Contained borated water volume, for surveillance 2175 ppm 4.7.13.3.a.2

• Values provided as Tables in the Appendix to this document were generated in the C2C07 Maneuvering Analysis calculational file (CNC-1553.05-00-0177). The CNS Nuclear Engineering Group will control this information via computer file (s) and should be contacted if there is a need to access this information.