ML19282A860
| ML19282A860 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 03/02/1979 |
| From: | Schmieder J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| JPN-79-10, NUDOCS 7903070209 | |
| Download: ML19282A860 (1) | |
Text
POWER AUTHORITY OF THE STATE OF NEW YORK to CoLuusus CIRCLE NEW YORK. N. Y. loo 19 (212) 397.6200 TR tJ STE ES G EORG E T. BER RY FREDERICK R. CLARK
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CO N T R Q LL E R Director of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Thomas A.
Ippolito, Chief Operating Reactors Branch No. 3 Division of Operating Reactors
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 Containment Purging During Normal Plant Operation
Dear Sir:
By letter dated January 9, 1979 (JPN-79-3), the Authority advised you that we would provide the response to your request on the above subject by February 26, 1979.
It now appears that we can not meet this date and request an extension of 90 days.
We shall respond to your request by May 28, 1979.
Our investigations have revealed that the valves used for purging are not opened by utilizing the separate override relay, and will receive a close signal in the event of a LOCA.
Contain-ment purge is always routed through the charcoal beds of the standby gas treatment system.
We, therefore, request that we not be limited to 90 hcurs per year of purging since this will limit our ability to continue plant operations.
It is necessary for us to operate these valves to maintain our drywell to torus differential pressure requirement.
We plan to justify unlimited purging by the above referenced date.
Very truly yours,
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Joseph R.
Schmieder g
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QN 79030702o9 b
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INTERIM REPORT ACCESSION NO.19 @ @ @ C1 6 ORNL/HASRD-25 Contract Program or Project
Title:
Safeguards Analysis for Byproduct Materials and Small Quantities of SNM Subject of this Document:
Technical Progress Type of Document:
Monthly Progress Report December 1978 Author (s), Affiliation and Address:
R. O. Chester and K. A. Kirkscey Health and Safety Research Division
- Date of Document:
January 13, 1979 NRC Individual and NRC Office or Division Mr. Gladstone S. Lewis, Jr.
to Whom Inquiries Should be Addressed:
Office of Nuclear Material Safety and Safeguards This document was prepared primarily for preliminary or internal use.
It has not received full review and approval.
Since there may be substantive changes, this document should not be considered final.
Prepared for U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Under Interagency Agreement DOE #40-549-75 NRC FIN No. B6108
- 0ak Ridge National Laboratory Oak Ridge, Tennessee 37830 operated by Union Carbide Corporation for the U. S. Department of Energy INTERIM REPORT