2CAN101201, Cycle 23, Core Operating Limits Report: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:2CAN101201  
{{#Wiki_filter:Entergy Operations, Inc.
 
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 2CAN101201 October 3, 2012 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
October 3, 2012  
 
U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001  


==SUBJECT:==
==SUBJECT:==
ANO-2 Cycle 23 COLR Arkansas Nuclear One, Unit 2  
ANO-2 Cycle 23 COLR Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
 
Docket No. 50-368 License No. NPF-6  


==Dear Sir or Madam:==
==Dear Sir or Madam:==


Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 23 COLR, which has been issued for shutdown Modes 3, 4, and 5 only. This completes the reporting requirement for the referenced specification.  
Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 23 COLR, which has been issued for shutdown Modes 3, 4, and 5 only. This completes the reporting requirement for the referenced specification.
 
This submittal contains no commitments.
This submittal contains no commitments.
If you have any questions or require additional information, please contact me.  
If you have any questions or require additional information, please contact me.
 
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/dbb
Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE  
 
SLP/dbb  


==Attachment:==
==Attachment:==
ANO-2 Cycle 23 Core Operating Limits Report (COLR)
ANO-2 Cycle 23 Core Operating Limits Report (COLR)
 
Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One Entergy Operations, Inc. 1448 S.R. 333 Russellville, AR  72802 Tel 479-858-4704 2CAN101201 Page 2 of 2
 
cc: Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX  76011-4511 NRC Senior Resident Inspector
 
Arkansas Nuclear One P.O. Box 310 London, AR 72847
 
U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike
 
Rockville, MD  20852
 
Mr. Bernard R. Bevill
 
Arkansas Department of Health    Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205
 
Attachment To 2CAN101201 ANO-2 CYCLE 23 CORE OPERATING LIMITS REPORT (COLR)  


CALC-ANO2-NE-12-00002 Revision 0 1 
2CAN101201 Page 2 of 2 cc:  Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205


ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 REVISION 0 MODES 3, 4, AND 5 ONLY
Attachment To 2CAN101201 ANO-2 CYCLE 23 CORE OPERATING LIMITS REPORT (COLR)


CALC-ANO2-NE-12-00002 Revision 0 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY  
CALC-ANO2-NE-12-00002 Revision 0 ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 REVISION 0 MODES 3, 4, AND 5 ONLY 1


INDEX PAGE I. INTRODUCTION........................................................................................................3 II.  
CALC-ANO2-NE-12-00002 Revision 0 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY INDEX                                                                                                                 PAGE I. INTRODUCTION ........................................................................................................ 3 II.


==SUMMARY==
==SUMMARY==
OF CHANGES.........................................................................................3  
OF CHANGES......................................................................................... 3 III. AFFECTED TECHNICAL SPECIFICATIONS ............................................................ 3 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS ........................... 3 V. CORE OPERATING LIMITS....................................................................................... 4 2
 
III. AFFECTED TECHNICAL SPECIFICATIONS............................................................3  


IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS...........................3
CALC-ANO2-NE-12-00002 Revision 0 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY I. INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for Technical Specifications 3.1.1.1 and 3.1.1.2, Shutdown Margin only for ANO-2's Cycle 23.
 
This is Revision 0 of the Cycle 23 COLR. It is applicable for Modes 3, 4, and 5 only. This document will be revised to address the remaining parameters listed in Technical Specification 6.6.5 prior to entering Mode 2 operation.
V. CORE OPERATING LIMITS.......................................................................................4
II.
 
CALC-ANO2-NE-12-00002 Revision 0 3 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY I. INTRODUCTION
 
This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for Technical Specifications 3.1.1.1 and 3.1.1.2, "Shutdown Margin" only for ANO-2's Cycle 23.
This is Revision 0 of the Cycle 23 COLR. It is applicable for Modes 3, 4, and 5 only. This document will be revised to address the remaining parameters listed in Technical Specification 6.6.5 prior to entering Mode 2 operation.  
 
II.  


==SUMMARY==
==SUMMARY==
OF CHANGES This is the initial issuance of the Cycle 23 COLR. It is applicable to operations in Modes 3, 4, and 5 only. There are no changes to the values for the required Shutdown Margin in Modes 3, 4, and 5 from the latest revision to the Cycle 22 COLR.  
OF CHANGES This is the initial issuance of the Cycle 23 COLR. It is applicable to operations in Modes 3, 4, and 5 only. There are no changes to the values for the required Shutdown Margin in Modes 3, 4, and 5 from the latest revision to the Cycle 22 COLR.
 
III. AFFECTED TECHNICAL SPECIFICATIONS
III. AFFECTED TECHNICAL SPECIFICATIONS
: 1) 3.1.1.1 Shutdown Margin - T avg > 200 °F
: 1)   3.1.1.1     Shutdown Margin - Tavg > 200 °F
: 2) 3.1.1.2 Shutdown Margin - T avg 200 °F   IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS
: 2)   3.1.1.2     Shutdown Margin - Tavg 200 °F IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and approved by the NRC.
 
: 1)   Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores, (WCAP-11596-P-A), June 1988, ANC: A Westinghouse Advanced Nodal Computer Code (WCAP-10965-P-A), September 1986, and ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins)
Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and  
: 2)  Technical Manual for the CENTS Code, WCAP-15996-P-A, Rev. 1, March 2005 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin)
 
: 3)  Qualification of the Two-Dimensional Transport Code PARAGON, WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins) 3
approved by the NRC.
: 1) "Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores," (WCAP-11596-P-A), June 1988, "ANC: A Westinghouse Advanced Nodal Computer Code" (WCAP-10965-P-A), September 1986, and "ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery" (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specifications 3.1.1.1 and 3.1.1.2  


for Shutdown Margins)
CALC-ANO2-NE-12-00002 Revision 0 V. CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.
: 2) "Technical Manual for the CENTS Code," WCAP-15996-P-A, Rev. 1, March 2005 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin)
: 1) 3/4.1.1.1 - SHUTDOWN MARGIN- Tavg  200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % k/k in Modes 3 and 4.
: 3) "Qualification of the Two-Dimensional Transport Code PARAGON," WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins)
: 2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg  200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/k in Mode 5.
CALC-ANO2-NE-12-00002 Revision 0 4 V. CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.
4}}
: 1) 3/4.1.1.1 - SHUTDOWN MARGIN- Tavg  200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % k/k in Modes 3 and 4.
: 2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg  200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/k in Mode 5.}}

Latest revision as of 22:38, 11 November 2019

Cycle 23, Core Operating Limits Report
ML12278A089
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 10/03/2012
From: Pyle S
Entergy Operations
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
2CAN101201 CALC-ANO2-NE-12-00002, Rev 0
Download: ML12278A089 (7)
v • d • e


Text

Entergy Operations, Inc.

1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4704 Stephenie L. Pyle Manager, Licensing Arkansas Nuclear One 2CAN101201 October 3, 2012 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001

SUBJECT:

ANO-2 Cycle 23 COLR Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6

Dear Sir or Madam:

Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 23 COLR, which has been issued for shutdown Modes 3, 4, and 5 only. This completes the reporting requirement for the referenced specification.

This submittal contains no commitments.

If you have any questions or require additional information, please contact me.

Sincerely, ORIGINAL SIGNED BY STEPHENIE L. PYLE SLP/dbb

Attachment:

ANO-2 Cycle 23 Core Operating Limits Report (COLR)

2CAN101201 Page 2 of 2 cc: Mr. Elmo Collins Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 1600 East Lamar Boulevard Arlington, TX 76011-4511 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U. S. Nuclear Regulatory Commission Attn: Mr. Kaly Kalyanam MS O-8 B1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. Bernard R. Bevill Arkansas Department of Health Radiation Control Section 4815 West Markham Street Slot #30 Little Rock, AR 72205

Attachment To 2CAN101201 ANO-2 CYCLE 23 CORE OPERATING LIMITS REPORT (COLR)

CALC-ANO2-NE-12-00002 Revision 0 ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 REVISION 0 MODES 3, 4, AND 5 ONLY 1

CALC-ANO2-NE-12-00002 Revision 0 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY INDEX PAGE I. INTRODUCTION ........................................................................................................ 3 II.

SUMMARY

OF CHANGES......................................................................................... 3 III. AFFECTED TECHNICAL SPECIFICATIONS ............................................................ 3 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS ........................... 3 V. CORE OPERATING LIMITS....................................................................................... 4 2

CALC-ANO2-NE-12-00002 Revision 0 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 23 MODES 3, 4, AND 5 ONLY I. INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for Technical Specifications 3.1.1.1 and 3.1.1.2, Shutdown Margin only for ANO-2's Cycle 23.

This is Revision 0 of the Cycle 23 COLR. It is applicable for Modes 3, 4, and 5 only. This document will be revised to address the remaining parameters listed in Technical Specification 6.6.5 prior to entering Mode 2 operation.

II.

SUMMARY

OF CHANGES This is the initial issuance of the Cycle 23 COLR. It is applicable to operations in Modes 3, 4, and 5 only. There are no changes to the values for the required Shutdown Margin in Modes 3, 4, and 5 from the latest revision to the Cycle 22 COLR.

III. AFFECTED TECHNICAL SPECIFICATIONS

1) 3.1.1.1 Shutdown Margin - Tavg > 200 °F
2) 3.1.1.2 Shutdown Margin - Tavg 200 °F IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and approved by the NRC.
1) Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores, (WCAP-11596-P-A), June 1988, ANC: A Westinghouse Advanced Nodal Computer Code (WCAP-10965-P-A), September 1986, and ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins)
2) Technical Manual for the CENTS Code, WCAP-15996-P-A, Rev. 1, March 2005 (Methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margin)
3) Qualification of the Two-Dimensional Transport Code PARAGON, WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for Specifications 3.1.1.1 and 3.1.1.2 for Shutdown Margins) 3

CALC-ANO2-NE-12-00002 Revision 0 V. CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.

1) 3/4.1.1.1 - SHUTDOWN MARGIN- Tavg 200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % k/k in Modes 3 and 4.
2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg 200 °F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/k in Mode 5.

4

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