ML092310748: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:From: Kalyanam, Kaly Sent: Tuesday, August 11, 2009 2:17 PM To: Bob Murillo; MASON, MICHAEL E (WF3) Cc: Miller, Joshua  
{{#Wiki_filter:From:                   Kalyanam, Kaly Sent:                   Tuesday, August 11, 2009 2:17 PM To:                     Bob Murillo; MASON, MICHAEL E (WF3)
Cc:                     Miller, Joshua


==Subject:==
==Subject:==
RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Dave/Bob, Bob/Mike,  
RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Dave/Bob, Bob/Mike, By letter dated June 3, 2009, Entergy requested an amendment to the Waterford Steam Electric Station, Unit 3,(Waterford 3) technical specifications (TS) 2.1.1.1, Departure from Nucleate Boiling (DNB) ratio safety limit based upon the Combustion Engineering 16 x 16 Next Generation Fuel design and the associated DNB correlations. The NRC staff has reviewed the request and has determined that we require additional information to complete our review. A request for additional information appears below.
 
This request was discussed with Bob Murillo of your staff. It was agreed that Waterford 3 would generate a response as early as possible, in view of the urgent need of the approved LAR.
By letter dated June 3, 2009, Entergy requested an amendment to the Waterford Steam Electric Station, Unit 3,(Waterford 3) technical specifications (TS) 2.1.1.1, Departure from Nucleate Boiling (DNB) ratio safety limit based upon the Combustion Engineering 16 x 16 Next Generation Fuel design and the associated DNB correlations. The NRC staff has reviewed the request and has determined that we require additional information to complete our review. A request for additional information appears below.
REQUEST FOR ADDITIONAL INFORMATION:
 
: 1. Address compliance with the conditions stated in the NRC safety evaluation reports approving the topical reports that allow application of the ABB-NV and WSSV-T critical heat flux correlations to the Next Generation Fuel design for the ANO-2 core. The following topical reports should be considered when they are applicable: WCAP-16523-P-A; CENPD-387-P-A; CENPD-161-P-A; CEN-356(V)-P-A; CEN-139(A)-P; and WCAP-16500-P-A (Rev.00).
This request was discussed with Bob Murillo of your staff. It was agreed that Waterford 3 would generate a response as early as possible, in view of the urgent need of the approved LAR.  
 
REQUEST FOR ADDITIONAL INFORMATION
:
: 1. Address compliance with the conditions stated in the NRC safety evaluation reports approving the topical reports that allow application of the ABB-NV and WSSV-T critical heat flux correlations to the Next Generation Fuel design for the ANO-2 core. The following topical reports should be considered when they are applicable: WCAP-16523-P-A; CENPD-387-P-A; CENPD-161-P-A; CEN-356(V)-P-A; CEN-139(A)-P; and WCAP-16500-P-A (Rev.00).
 
Any conditions resulting from the review of Supplement 1 of WCAP-16500 (Revision 1) should also be met.
Any conditions resulting from the review of Supplement 1 of WCAP-16500 (Revision 1) should also be met.
: 2. The NRC Staff may need to perform an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the value of 1.23 was determined from the WSSV-T and ABB-NV values of 1.12 and 1.13. This audit can be arranged for the week of July 13, 2009. The exact date has to be decided.
: 2. The NRC Staff may need to perform an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the value of 1.23 was determined from the WSSV-T and ABB-NV values of 1.12 and 1.13. This audit can be arranged for the week of July 13, 2009. The exact date has to be decided.
 
For ANO-2, the NRC Staff performed an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the new safety limit was determined. However, the audit was not done for Waterford 3. Please describe how the safety limit DNBR of 1.24 was obtained, including codes and methods used Thanks Kaly N. Kalyanam
For ANO-2, the NRC Staff performed an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the new safety limit was determined. However, the audit was not done for Waterford 3. Please describe how the safety limit DNBR of 1.24 was obtained, including codes and methods used  
 
Thanks  
 
Kaly N. Kalyanam


E-mail Properties Mail Envelope Properties ()  
E-mail Properties Mail Envelope Properties ()


==Subject:==
==Subject:==
RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Sent Date:       8/11/2009 2:04:45 PM Received Date:       8/11/2009 2:17:00 PM From:               Kalyanam, Kaly  
RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Sent Date:     8/11/2009 2:04:45 PM Received Date:       8/11/2009 2:17:00 PM From:           Kalyanam, Kaly Created By:       Kaly.Kalyanam@nrc.gov Recipients:
 
Created By:         Kaly.Kalyanam@nrc.gov  
 
Recipients:
rmurill@entergy.com (Bob Murillo)
rmurill@entergy.com (Bob Murillo)
Tracking Status: None MMASON@entergy.com (MASON, MICHAEL E (WF3))
Tracking Status: None MMASON@entergy.com (MASON, MICHAEL E (WF3))
Tracking Status: None Joshua.Miller@nrc.gov (Miller, Joshua)
Tracking Status: None Joshua.Miller@nrc.gov (Miller, Joshua)
Tracking Status: None  
Tracking Status: None Post Office:
 
Files         Size     Date & Time MESSAGE         8753     8/11/2009 Options Expiration Date:
Post Office:  
Priority:               olImportanceNormal ReplyRequested:        False Return Notification:     False Sensitivity:     olNormal Recipients received:}}
 
Files               Size       Date & Time  
 
MESSAGE       8753       8/11/2009  
 
Options Expiration Date:
Priority:                       olImportanceNormal ReplyRequested:        False Return Notification:       False  
 
Sensitivity:         olNormal Recipients received:}}

Latest revision as of 03:05, 14 November 2019

RAI, License Amendment Request to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit
ML092310748
Person / Time
Site: Waterford Entergy icon.png
Issue date: 08/11/2009
From: Kalyanam N
Plant Licensing Branch IV
To: Mason M, Murillo B
Entergy Operations
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC ME1424
Download: ML092310748 (2)
v • d • e


Text

From: Kalyanam, Kaly Sent: Tuesday, August 11, 2009 2:17 PM To: Bob Murillo; MASON, MICHAEL E (WF3)

Cc: Miller, Joshua

Subject:

RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Dave/Bob, Bob/Mike, By letter dated June 3, 2009, Entergy requested an amendment to the Waterford Steam Electric Station, Unit 3,(Waterford 3) technical specifications (TS) 2.1.1.1, Departure from Nucleate Boiling (DNB) ratio safety limit based upon the Combustion Engineering 16 x 16 Next Generation Fuel design and the associated DNB correlations. The NRC staff has reviewed the request and has determined that we require additional information to complete our review. A request for additional information appears below.

This request was discussed with Bob Murillo of your staff. It was agreed that Waterford 3 would generate a response as early as possible, in view of the urgent need of the approved LAR.

REQUEST FOR ADDITIONAL INFORMATION:

1. Address compliance with the conditions stated in the NRC safety evaluation reports approving the topical reports that allow application of the ABB-NV and WSSV-T critical heat flux correlations to the Next Generation Fuel design for the ANO-2 core. The following topical reports should be considered when they are applicable: WCAP-16523-P-A; CENPD-387-P-A; CENPD-161-P-A; CEN-356(V)-P-A; CEN-139(A)-P; and WCAP-16500-P-A (Rev.00).

Any conditions resulting from the review of Supplement 1 of WCAP-16500 (Revision 1) should also be met.

2. The NRC Staff may need to perform an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the value of 1.23 was determined from the WSSV-T and ABB-NV values of 1.12 and 1.13. This audit can be arranged for the week of July 13, 2009. The exact date has to be decided.

For ANO-2, the NRC Staff performed an audit of the Westinghouse calculation, at its Rockville, Maryland, offices. These calculations show how the new safety limit was determined. However, the audit was not done for Waterford 3. Please describe how the safety limit DNBR of 1.24 was obtained, including codes and methods used Thanks Kaly N. Kalyanam

E-mail Properties Mail Envelope Properties ()

Subject:

RAI for Waterford 3 LAR to Revise the Departure from Nucleate Boiling Ratio (DNBR) Safety Limit Sent Date: 8/11/2009 2:04:45 PM Received Date: 8/11/2009 2:17:00 PM From: Kalyanam, Kaly Created By: Kaly.Kalyanam@nrc.gov Recipients:

rmurill@entergy.com (Bob Murillo)

Tracking Status: None MMASON@entergy.com (MASON, MICHAEL E (WF3))

Tracking Status: None Joshua.Miller@nrc.gov (Miller, Joshua)

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 8753 8/11/2009 Options Expiration Date:

Priority: olImportanceNormal ReplyRequested: False Return Notification: False Sensitivity: olNormal Recipients received:

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