ML17276A941
| ML17276A941 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 01/06/1982 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| GO2-82-04, GO2-82-4, NUDOCS 8201250353 | |
| Download: ML17276A941 (11) | |
Text
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+8201250353 820i06 PDR ADOCK 05000397 PDR Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 January:6, 1982 G02-82-04 SS-L-02-CDT-82-002 Docket No. 50-397 Mr. A. Schwencer, Director Licensinq Branch No.
2 Division of Licensinq U.S. Nuclear Regulatory Commission Washinqton, D.C.
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Dear Mr. Schwencer:
Subject:
Refer ence:
NUCLEAR PROJECT NO.
2 CHANGED RESPONSES TO MATERIALS ENGINEERING BRANCH QUESTIONS Letter G02-81-532, GD Bouchey to A Schwencer, "Appendix G and H Information Responses to Materials Engineerinq Branch - Component Integrity Section",
dated December 18, 1981'nclosed are sixty (60) copies of revised responses for two (2) Materials Enqineering Branch questions.
These two questions wer'e submitted to the NRC by the reference letter;
- however, they were found by the Supply Sys-tem to be incomplete.
These responses will appear in the WNP-2 FSAR in a future amendment.
Very truly yours, G.
D. Bouchey Deputy Director, Safety and Security CDT/jca Enclosures cc:
R Auluck -
NRC WS Chin BPA R
Feil NRC Site
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MNP 2
REFERENCE:
1 ~
Letter G02-81-532r G.
D. Bouchey to A. Schwencerr "Appendix G and H Informationr Responses to Naterials Engineering Branch
Component Integrity Section"r dated December 18r 1981.
WNP-2 Q.
121.011 Provide data to justify that the value of -50 F used to estimate the niL ductility temperature for the beltline welds was obtained from test samples that represent the belt line welds in the MNP-2 reactor pressure vessel.
This information should include a
comparison of. the significant weld parameters (e.g.i weld. tirei flux'hermal'reatment) and mechanical properties from both the sampLe and beltl inc welds.
Response
This question was responded to in the Appendix G and H submittal to the NRC.
CSee Reference 1)
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WNP-2 Q.
121.019 Indicate the inside diameter and minimum wall thickness of the reactor vessel beltline.
~Response:
The inside diameter with clad
= 251" (minimum).
Llall thickness with c Lad 6.625%.
Clad thickness 0.1875" '(nominal).
0.125" (minimum).
Refer to VFP No. 3133-31'hich is included in the Appendix G
and H submittaL (see Reference 1 to Question 121.011).*
- Attac hed.
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