ML19242D043
| ML19242D043 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 07/30/1979 |
| From: | Dale L MISSISSIPPI POWER & LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AECM-79-81, NUDOCS 7908140424 | |
| Download: ML19242D043 (2) | |
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MISSISSIPPI POWER & LIGHT COMPANY A
Helping Build Mississippi P. O. B O X 164 0, J A C K S O N, MISSISSIPPI 39205
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July 30, 1979
..oo uction o c a ar u r ~ r Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
SUBJECT:
Grand Gulf Nuclear Station File: 0260/0272/L-334.0 Loads Adequacy Evaluation Program for Grand Gulf AECM-79/81 In our response to NRC first round requests for additional information, in particular, in FSAR Anendments 30 and 31, we discussed our methods of treating loads on safety related structures, systems and components.
In some instances, our approach differs from that requested by the NRC; in others, our approach may require amplification beyond what is provided in response to the question. These items with the corresponding NRC question number (in parentheses) are as follows:
1.
Out of phase safety relief valve bubble loading (SRVA) for equipment (021.4) 2.
In phase safety relief valve bubble loading (SRVD) for struc-tures.
(021.4) 3.
Use of G. E.'s Interim Containment Loads Report, Rev. 2, vs.
(021.1, 021.2) 4.
Choice of load cases for design of structures, systems and components.
(021.8, 110.34, 110.42, 110.47, 130.08, 130.09, 130.10) 5.
SRSS vs. absolute sus load combination methodology for piping.
(110.41) 6.
Annulus pressurization mass and energy release.
(021.12, 110.29, 130.09, 222.2) 7.
Idealized Raleigh bubble pressure reduction based on Caorso data.
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8.
Equipment qualification-valves.
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Member Middle South Utilities System 7 90814 Oe/77'
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MISSISSIPPI POWER & LIGHT COMPANY Mr. Harold R. Denton AECM-79/81 Due to the all-encompassing nature of the Grand Gulf loads adequacy evaluation, we feel that it is of the utmost importance to clarify our position and resolve any differences early in the operating license re-view cycle.
We, therefore, request a meeting with your management and technical branches to discuss the items listed, above. We recommend that such a meeting be held in mid August, 1979.
If these recommendations are not satisfactory, please inform us of dates and attendees suitable to the NRC.
Sincerely, L. F. Dale Nuclear Project Manager EWC/pa ec:
Mr. N. L. Stampley Mr. R. B. McGehee Mr. T. B. Conner Mr. John G. Davis, Director Division of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 n
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