ML20062H745
| ML20062H745 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/22/1980 |
| From: | Thornburg H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Thompson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19344E167 | List: |
| References | |
| NUDOCS 8008270506 | |
| Download: ML20062H745 (2) | |
See also: IR 05000322/1979024
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UrnTED STATES
Enclosure 1
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NUCLE'AR REGULATORY COMMISSION
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G'ORANDUM FOR:
D. Thompson, Executive Officer for Operations Support, IE
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FRDXf
H. D. Thornburg, Direct 6r, Division o' Reac'q renstruction
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Inspection. IE
SUBJdCT:
SHOREHAM NUCLEAR POWER STATION INVESTIGATION REPORT
NO.
50-322/79-24
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As requested, RCI has reviewed the subject report and associated' documents
for technical validity.
We have the following comments.
1.
There are.five locations where we question the appropriateness or
accuracy o_f the conclusions.
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a.
On page 45, in the first sentence of allegation 22. finding b, and on
page 48, in the first sentence of allegation 23
finding b, the state- + 4
rent is cade that the condenser is not classified as a Code vessel 'as
the shell side is under vacuum".
This conclusion is not valid.
The
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ASME Boiler and Pressure Vessel Code, in both Section III Nuclear
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Co:ponents, and Section:YIII, Unfired Pressure Vessels, provides rules
for design and construction of components to operate under vacuum (or
external .p essure).
It is a true, and in 'our opinion, sufficient,
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state:aent that the condenser is not a safety-related unit, and is not'
classified as an ASME Code Vessel . We recommend the quoted phrase be
deleted in both locations.
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b.
On page 47, the last sentence of the first (partial) paragraph reads, .
"This was confirmed by the NRC."
We find no basis or support for
that statement.
c.
On page 48, the first full sentence.
We do not understand the rationale
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for selecting the outlet tube ends for examination since, if the tubes
we e inserted from the outlet side, 'the end projection would be the only
part of a tube which had not been pushed through a tube sheet or support
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plate. Tube end damage, if any were to be found, would most likely
occur on the inlet tube end which would have been. pushed through both
t::be sheets, and every support plate.
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d.
Page 54, the last sentence of the first (partial) paragraph. We do not
understand the use of the words, "This request to withold." We find no
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CD.'iTACT:
J. E. Henderson
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reference to a "recuest to withold."
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2.
Subject to the above cor nents, we find that the report documents what
appears to be an extensive and well performed irivestigation.
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H. D. Thornburg.
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Director
Division of Reactor Construction
Inspection
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Office of Inspection
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and Enforcement
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B. H. Grier, RI
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C. O. Gallina, RI
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