ML19337B529
| ML19337B529 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/14/1980 |
| From: | Novarro J LONG ISLAND LIGHTING CO. |
| To: | Robert Carlson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19337B527 | List: |
| References | |
| SNRC-493, NUDOCS 8010020714 | |
| Download: ML19337B529 (2) | |
Text
,QLs.'
LONG ISLAND LIGHTING COM PANY FLCO SHOREHAM NUCLEAR POWER STATION j
pues by - - -
-- m P.O. BOX 618, NORTH COUNTRY RO AO + WADING RIVER. N.Y.11792 August 14, 1980 SNRC-493 Mr. Robert T. Carlson, Chief Reactor Construction and Engineering Support Branch U. S. Nuclear Regulatory Commission, Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 NRC Inspection No. 50-322/79-07 Raceway / Cable Separation Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322
Dear Mr. Carlson:
Your letter of July 1, 1980 agrees that the analytical effort, if approved by the Office of Nuclear Reactor Regulation, will support the general requirements of Section 3.12.3.5.1.1.
Further, this letter requests that we submit the analysis to NRR for their review.
As we have previously stated in our letter SNRC-471, dated April 16, 1980 we strongly suggest that the best approach to reviewing and expeditiously closing this issue is a meeting with the appropriate NRC Staff reviewers.
At this point, our preliminary report is available for such a review meeting.
Accordingly, on July 23, 1980, we requested Mr. J. N. Wilson, NRC Proj ect Manager, to set up a meeting.
NRR has been having difficulty since then in establishing a meeting pate with ti.e various branches involved.
We are prepared to support this meeting at the site or in Bethesda j
at the NRC's earliest convenience.
l l
We recognize the importance of this issue, as well as your l
concern with the requirements of 10 CFR 50, Appendix B, 1
1 re ses
Mr. Robert T. Carlson August 14, 1980 Re:
URC Inspection No. 50-322/79-07 Page 2 Criterion XVI.
However, we believe that the analytical separation analysis approach is a conservative means of assuring that any deviations from the stated criteria do not constitute a condition adverse to the quality of our construction effort or overall plant safety.
Very truly yours, 0
/
I
~
. P. Novarro, Proj ect! Manager Shoreham Nuclear Power Station RAH /cc cc:
J. Higgins J. N. Wilson 1