ML14184A094
| ML14184A094 | |
| Person / Time | |
|---|---|
| Site: | Robinson, Brunswick  |
| Issue date: | 07/19/1979 |
| From: | O'Reilly J NRC/IE, NRC/RGN-II |
| To: | Jackie Jones Carolina Power & Light Co |
| References | |
| NUDOCS 7908070305 | |
| Download: ML14184A094 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 JUL 19 1979 In Reply Refer To:
RHI:JPO 50-325 50-324 Carolina Power and Light Company ATTN: Mr. J. A. Jones Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, NC 27602 Gentlemen:
Since the Three Mile Island incident, the NRC Commissioners, the public and the media have expressed an increased interest in the status of operating nuclear power plants and fuel facilities.
This interest has now reached a level where it is desirable to know, on a daily basis, the status of nuclear facilities with an operating license.
We request your cooperation in obtaining this information.
We plan to contact each operating facility on the dedicated phone during the last half of the 12:00 midnight to 8:00 a.m. shift each day.
This call will also be used as the check of the dedicated telephone line.
The amount of time required should not exceed one or two minutes for any facility since we will only be asking for the operating status of each plant.
If a unit is not fully operational, we would like to have a very brief description of the reason for this. During prolonged outages, we will not make these status calls. Implemen tation of this program will start Monday, July 23, 1979.
Please notify your responsible plant personnel of this program. If you have any questions, please call the Regional Office.
Sincerely, ames P. O'Reilly D rector cc:
R. B. Starkey, Plant Man r
P. 0. Box 790 Hartsville, SC 29550 A. C. Tollison, Jr.
Plant Manager Box 458 Southport, NC 28461 Z908070 36,
NRC-HBR Box NRCHBR_3492_0005 Accession 7908080070
++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 July 18, 1979 ALL PRESSURIZED WATER REACTOR LICENSEES Gentlemen:
Enclosed is a copy of Revision 2 of the Draft Radiological Effluent Technical Specifications, (NUREG-0472, PWR; NUREG-0473, BWR).
This revision embodies corrections of errors found in previous revisions, revisions in format for consistency with Appendix "A" Standard Technical Specifications, and some rewriting for clarification.
If you have prepared Radiological Effluent Technical Specifications to a previous revision but have not submitted them to NRC, do not convert them to this Revision 2 format. You should submit them in their present format since the information required for Revision 2 is available in previous revisions. Otherwise, Revision 2 should be used to prepare your Technical Specification submittal.
In those cases where submittals of-Radiological Effluent Technical Specifications in a previous format are made to NRC, the final specifications, after negotia tions and reviews have been completed, will be based on Revision 2.
If you have any questions, please contact us.
Sincerely, William P. Gammill, Acting Assistant Director for Operating Reactor Projects Division of Operating Reactors
Enclosure:
NUREG-0472, Revision 2 79008007-0