ML050830393
| ML050830393 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/20/2004 |
| From: | Chernoff H NRC/NRR/DLPM/LPD3 |
| To: | Gadzala J Nuclear Management Co |
| References | |
| FOIA/PA-2004-0282 | |
| Download: ML050830393 (2) | |
Text
jHaroldChernotff-Draft RAI I
-i PageI I
-26 From:
To:
Date:
Subject:
Harold Chernoff Gadzala, Jack Nmz/-
Thu, May 20, 2004 5:03 PM Draft RAI The attached file contains draft RAI questions for discussion in conformance with LIC-1 01 to ensure accuracy prior to issuance.
hkc Harold Chernoff, Project Manager - Point Beach Project Directorate 111-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Office: (301) 415-4018 Fax: (301) 415-1222 46 - Z
Draft Request for Additional Information The NRC staff has reviewed the information the licensee provided that supports the proposed relaxation request and requests the following information to clarify the portion of the submittal regarding the limited examination distance below the J-groove nozzle weld.
1 )
The request states that "UT of the most highly stressed portion of the nozzle (the weld heat affected zone) is unaffected by this limitation." Provide tabular listings or graphs of the maximum stresses in the cross-section from the top of the J-groove weld region to the nozzle end for a range of nozzle angles. Indicate the location of the weld on these graphs.
- 2)
Does the structural integrity evaluation use the crack-growth formula in industry report MRP-55? The staff has not made a determination on the subject industry report. Therefore, if using MRP-55 agree to and document the following condition:
If the NRC staff finds that the crack-growth formula in industry report MRP-55 is unacceptable, the licensee shall revise its analysis that justifies relaxation of the Order within 30 days after the NRC informs the licensee of an NRC-approved crack growth formula. If the licensee's revised analysis shows that the crack growth acceptance criteria are exceeded prior to the end of the current operating cycle, this relaxation is rescinded and the licensee shall, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, submit to the NRC written justification for continued operation. If the revised analysis shows that the crack growth acceptance criteria are exceeded during the subsequent operating cycle, the licensee shall, within 30 days, submit the revised analysis for NRC review. If the revised analysis shows that the crack growth acceptance criteria are not exceeded during either the current operating cycle or the subsequent operating cycle, the licensee shall, within 30 days, submit a letter to the NRC confirming that its analysis has been revised. Any future crack-growth analyses performed for this and future cycles for RPV head penetrations must be based on an acceptable crack growth rate formula.
- 3)
What is the initial flaw size (depth and length) forthe flaw tolerance evaluation calculations.
Discuss the basis for the initial flaw size. In addition, provide a basis for the calculations based on nozzle 20 are bounding for the other 16 nozzles that did not receive a minimum examination of one inch below the weld. What are the stresses for the 17 nozzles at the lowest examined distance. Provide the folowing information regarding figures 1-7 of the Si calculation PBCH-09Q-310 Rev. 1: 1) indicate the location of the weld; 2) what is meant by reference to the "top"; 3) what is the 'OD node"; 4) what do the values of the x-axis represent.
- 4)
Provide additional technical discussion of the basis for the K factor of 55 Ksi representing a conservative value.