ML050830372
| ML050830372 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  (DPR-024) |
| Issue date: | 05/17/2004 |
| From: | Chernoff H NRC/NRR/DLPM/LPD3 |
| To: | Raghavan L NRC/NRR/DLPM |
| References | |
| FOIA/PA-2004-0282 | |
| Download: ML050830372 (1) | |
Text
- Harold Chernoff - Point Beach RVHPs Page 1 tl Haol Chrnf
- Poin Bec RV.
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From:
Harold Chemoff
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P "Kt To:
Lakshminaras Raghavan I/
Date:
Mon, May 17, 2004 7:13 AM
Subject:
Point Beach RVHPs There are two submittals related to the Point Beach Unit 1 reactor vessel head penetration inspections.
The head is currentl in its stand. The licensee has stated that they will not set the head on the reactor vessel until technical issues are resolved with the NRC.
The first submittal is a relief request related to the repair performed on nozzle 26. The licensee performed a repair on nozzle 26 that required relief from the code. NRC staff had verbally indicated that the repair, which resulted in overlapping Alloy 52 repair material onto existing Alloy 82/182 material, would not be technically justifiable based on MRP-55 crack growth methodology for Alloy 600 matertial (base material -
rather than weld material). On May 15, 2004, the licensee submitted additional information, including crack growth calculations using correlations for Alloy 82 material. NRC staff is reviewing this additional information.
The second submittal is an Order relaxation request. There are two ares for which relaxation are requested. First there was a 60 degrees band of non-UT coverage above the J-groove weld on nozzle 33.
The licensee had originally proposed a probabilistic assessment that NRC staff found unacceptable. On May 15, 2004, the licensee provided a deterministic assessment of crack growth through this area. The other are of requested relaxation involved 17 nozzles that could not be excamined at least one inch below the toe of the J-groove weld on the OD. On May 15, 2004, the licensee submitted addtitional information concerning the assumed intensity factor used in the crack growth calculation and the length of postulated through-wall flaws. The NRC staff is reviewing this additional information.
hkc Harold Chemoff, Project Manager - Point Beach Project Directorate ll-1 Division of Licensing Project Management Office of Nuclear Reactor Regulation Office: (301) 415-4018 Fax: (301) 415-1222 CC:
hkc