ML13225A061
| ML13225A061 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 08/13/2012 |
| From: | Carolyn Fairbanks Division of Engineering |
| To: | Jeffrey Poehler Division of Engineering |
| References | |
| FOIA/PA-2013-0139 | |
| Download: ML13225A061 (2) | |
Text
Poehler, Jeffrey From:
Fairbanks, Carolyn *0\\ \\(L4-Sent:
Monday, August 13, 2012 1:20 PM To:
Poehler, Jeffrey
Subject:
Watts Bar 2 did have a (joint) GL 92-01 response From NUREG-15 1" Plant Name: Watts Bar 2 Docket Number: 50-391 NSSS Vendor: Westinghouse Vessel Manufacturer: Rotterdam Dockyard Edition of ASME Code for Design: Summer 1971 Addenda to the 1971 ASME Code Date-of Commercial Operation: License has not been issued Date of License Expiration: License has not been issued RTpt, for the Limiting Beltline Material:
Limiting Beltline Material: Circumferential weld, heat 895075 ID Fluence at EOL: 3.18E19 n/Cm2 Initial RT -50*F Method of Determining Chemistry Factor: Chemistry data per Paragraph C. 1.1 of RG 1.99, Rev. 2 Increase in RTNDT at EOL: 89°F Margin: 56°F RTt at EOL: 95oF Date at which PTS Screening Limit will be exceeded: After EOL USE for the Limiting Beltline Material:
Limiting Beltline Material: Lower shell forging 04, heat 528658 1/4T Fluence at EOL: 1.90E19 n/cm2 Initial USE: 105 ft-lb Percent Drop at EOL: 22.1%
USE at EOL: 82 ft-lb Date USE Screening Limit will be Exceeded: After EOL Bases for Accepting the USE at EOL: Chemistry data per Paragraph C. 1.2 of RG 1.99, Rev. 2
REFERENCES:
July 7, 1992, letter from Rt M. Shell (TVA) to USNRC Document Control Desk,
Subject:
Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and
Watts Bar Nuclear Plant--Response to Generic Letter 92-01 (Reactor Vessel Structural Integrity) 2