ML20076K474
| ML20076K474 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 10/24/1994 |
| From: | Clark R, Elder M DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20076K468 | List: |
| References | |
| CNEI-0400-25, CNEI-0400-25-R03, CNEI-400-25, CNEI-400-25-R3, NUDOCS 9411010181 | |
| Download: ML20076K474 (5) | |
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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
Cctawba 2 Cycle 7 Core Operating Limits Report CNEI-0400-25 Page 2 of 19 Rev.3
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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 Page 3 of 19 Rev.3' i
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1 REVISION LOG 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
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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
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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
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3/4.9.2 Instrumentation 1
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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
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concentration, for LCO 3.5.4b 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
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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.