ML041410147

E-mailed on 04/30/04 ANO 1 - RAI for Relief Request R&R-005&006

ML041410147
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/30/2004
From:	Alexion T NRC/NRR/DLPM/LPD4
To:	Davant G Entergy Operations
Alexion T W, NRR/DLPM, 415-1326
References
Download: ML041410147 (3)

Text

Thomas AlexonI- FOR RELIEF REQUEST R&R-4 5I0I-- - Page 1 I[Thomas Alexion - RAI FOR RELIEF REQUEST R&R-005&006 Page 1 From: Thomas Alexion To: DAVANT, GUY H Date: 4/30/04 11:52AM

Subject:

RAI FOR RELIEF REQUEST R&R-005&006 Guy, See the attached.

Tom CC: SBENNE2@entergy.com

CA.W1ND0W!S\TEMP\qW}0091..TMP CMJPage 1I Mail Envelope Properties (40927648.65B : 0: 20628)

Subject:

RAI FOR RELIEF REQUEST R&R-005&006 Creation Date: 4/30/04 11:52AM From: Thomas Alexion Created By: TNVA@nrc.gov Recipients Action Date & Time entergy.com Transferred 04/30/04 11:57AM GDAVANT (DAVANT, GUY H)

SBENNE2 CC (SBENNE2@entergy.com)

Post Office Delivered Route entergy.com Files Size Date & Time R&R005&6RA1043004.wpd 3437 04/30/04 11:19AM MESSAGE 655 04/30/04 11:52AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard Reply Requested: No Return Notification: None Concealed

Subject:

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REQUEST FOR ADDITIONAL INFORMATION (REVISED 04/30/04)

RELIEF REQUEST R&R-005 AND R&R-006 ARKANSAS NUCLEAR ONE, UNIT 1 (ANO-1)

1. Describe briefly the latest technical basis in support of Relief Request R&R-006, including the following items:

1a. Methodology - Discuss the steps of elastic plastic fracture mechanics (EPFM) approach; discuss the applicability of the EPFM for the ferritic reactor vessel head material in the flaw evaluation; and provide references.

1b. Assumptions - Discuss flaw size, flaw path; the applicability of the upper shelf energy value used for the ANO-1 reactor vessel head; and provide references.

1c. Results - Discuss the preliminary results in terms of safety factors, J applied, and J material values; and flaw growth.

1d. Preliminary Conclusion - Entergy needs to make a preliminary conclusion regarding whether the postulated flaw in the J-groove weld remnant will affect the structural integrity of the ANO-1 reactor vessel head.

2. Entergy needs to make a preliminary conclusion regarding whether the nozzle repair proposed in Relief Requests R&R-005 and -006 will affect the reactor vessel head in maintaining the structural integrity and leakage integrity of the reactor coolant system.

3. Entergy needs to commit to submit its final technical basis, including the flaw evaluation, by a certain date. Entergy had proposed June 1, 2004, in its April 12, 2004 submittal.