ML20077S363
| ML20077S363 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 08/19/1980 |
| From: | Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fasano A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20077S281 | List: |
| References | |
| FOIA-83-349 NUDOCS 8309220042 | |
| Download: ML20077S363 (1) | |
Text
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!,,( ~(g UNITED STATES NUCLEAR REGULATORY COMMISSION E
REGION I 3.h% _[.. [
631 PARK AVENUE
%V KING OF PRUSSIA, PENNSYLVANIA 19406 g.i ? ir,'
MEMORAN'DUM FOR:
Anthony N. Fasano, Chief. Site Operations Section, TMI Program Office FROM:
Lowell E. Tripp, Chief, ESS#1, RC&ES Branch, RI
SUBJECT:
USE OF FURMANITE FOR TEMPORARY REPAIR OF DH-V1 AT TMI-1 As requested in June 1980, and in your August 12,1980 memorandum on this subject, we have reviewed the subject concern.
Our findings and coments are as follows:
1.
The operating plant service temperature is 140F.
l 2.
The d'ecay heat condition temperature may be 280F, but this is for a relatively short period of time.
3.
The valve is 316 stainless steel solution annealed with very low residual stresses and low service induced stresses.
4 4.
The ferrite content of the valve is high.
5.
The oxygen content is n.egligible.
I 6.
Our metallurgical conclusions are that stress corrosion probability is negligible for the valve and the quantity of leachable chlorides'that can get into the loop are also negligible.
Thus,.our recommendation is that th.. is no need for additional licensee or NRC actions.
Please contact S. D. Reynolds of my Section if you have any further questions concerning this matter.
[. h owell E. Tripp, Chief Engineering Support Section #1 l
RC&ES Branch l
l cc:
J. M. Allan J. T. Collins R. T. Carlson R. R. Keimig L. W. Gage 8309220042 830728 PDR FOIA PETCHE83-349 PDR Sqb - 2g ry
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