ML041410104
| ML041410104 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf, Arkansas Nuclear |
| Issue date: | 04/05/2004 |
| From: | Bhalchandra Vaidya NRC/NRR/DLPM/LPD4 |
| To: | Davant G Entergy Operations |
| Alexion T W, NRR/DLPM, 415-1326 | |
| References | |
| Download: ML041410104 (4) | |
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Proposed Meeting Agenda for April 16, 2004 Meeting, Relief Requests 005 & 006 4/5/04 11:1 1AM Bhalchandra Vaidya Created By:
BKV@nrc.gov
\\ A~ol osyS.§-v Recipients entergy.com gdavant (gdavant@entergy.com)
Action Transferred Date & Time 04/05/04 11:12AM nrc.gov owf2_po.0WFNDO JCT CC (John Tsao)
RAG CC (Robert Gramm)
RHD CC (Davis robert) nrc.gov owf4_po.0WFNDO MCT CC (Mohan Thadani)
TWA CC (Thomas Alexion)
Post Office owf2_po.OWFNDO owf4_po.0WFNDO Delivered Delivered Delivered 04/05/04 11:12AM 04/05/04 1:11AM 04/05/04 11:12AM 04/05/04 1:11AM Route entergy.com nrc.gov nrc.gov Files Size Date & Time ANO-I Rlief Reuest 005 & 006-proposed meeting agenda-Rev 1.wpd 11:02AM MESSAGE 1020 04/05/04 11:11AM 4610 04/05/04 Options Auto Delete:
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- I,
BhalchandraVaidy_
- Proposed Meeting Agenda for April 16, 2004 Meeting RelieflRequests 005 & 006 Page 1 From:
gdavant~entergy.com Date:
4/5/04 11:11 AM
Subject:
Proposed Meeting Agenda for April 16, 2004 Meeting, Relief Requests 005 & 006 As discussed in our tele-con thismorning, the proposed Agenda for the Meeting on April 16, 2004 on Relief Requests 005 and 006 is attached.
Thanks.
Bhalchandra Vaidya NRR/DLPM Licensing Project Manager, PDIV-1 Grand Gulf Nuclear Station, Unit 1 301-415-3308 M/S: 0-7D1 CC:
Alexion, Thomas; Davis robert; Gramm, Robert; Thadani, Mohan; Tsao, John
1 Bhalchandra Vaidya - ANO-1 Rlief Reuest 005 & 006-proposed eting ageda-Rev.wpd Page 1 PROPOSED AGENDA FOR THE MEETING BETWEEN ENTERGY AND NRC ON RELIEF REQUEST 005 AND 006 AT ARKANSAS NUCLEAR ONE, UNIT 1 APRIL 16, 2004 AT NRC HEADQUARTERS
- 1. Introduction-NRC (Tom Alexion) 8:30 - 8:35
- 2. Discussion of the history of Relief Request 005 and 006-Entergy 8:35 -
- 3. Discussion of revised Relief Request 006-Entergy
- 4. Discussion of the plan for the 6 repaired nozzles-Entergy
- 5. Discussion of Revised Flaw Evaluation-Entergy
- a. Flaw Model.
- b. Reactor head fabrication--weld residual stresses
- c. Analysis Assumptions, input parameters.
- d. Applicability of the input parameters (e.g., applied loads, boundary conditions) to the weld configuration.
- e. Step-by-step Methodology.
- f. Results.
- 6.
Discussion of the Alternate Acceptance Criteria for the Revised Analysis.
- a. Technical justification
- b. Precedents
- c. discuss why the ASME Code allowable is not applicable
- 7.
Discussion of the Previous Flaw Evaluation-Entergy
- a. Discuss the differences between the previous flaw analysis in ANO-calculation 86-E-0074-156 and the revised flaw evaluation.
- b. Compare the previous analysis and the revised analysis.
- 8.
Closing remarks regarding the Integrity of the repaired nozzles and future repairs-Entergy