ML20039F247
| ML20039F247 | |
| Person / Time | |
|---|---|
| Site: | 05000561 |
| Issue date: | 05/18/1976 |
| From: | Suhrke K BABCOCK & WILCOX CO. |
| To: | Boyd R Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML111090060 | List:
|
| References | |
| FOIA-80-515, FOIA-80-555 NUDOCS 8201120264 | |
| Download: ML20039F247 (3) | |
Text
Jx.ay labcock & Wilcox pour ceneracon croup P.O. Box 1260, Lynchburg Va. 24505 Telephone: (804) 384 5111 l
May 18,1976 DOCKET STN 50-561 i
Mr. Roger S. Boyd, Director l
Division of Project Management j
Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l
Washington, D. C.
20555 i
Subject; B-SAR-205 Request for Review of NRC Position on Code Case 1592-7
Dear Mr. Boyd:
The Babcock & Wilcox Company has evaluated a new design for reactor coolant system pressurizer heater elements which is being implemented on B-SAR-205.
This letter is to request thct a code case interpretation by the NRC relating to allowable material temperatures be reviewed on the B-SAR application with regard l
to the proposed design. We request that this review be expedited because we also intend to use the proposed design on other on-going 205 FA NSS units.
The specific item that requires review and concurrence by the Staff is described below.
i An analysis of the temperature distribution across the heater elements (see attached sketch) indicates that the inner surface of the heater sheath will operate at a temperature of 825F. The present ASME Code (Section III) limits temperatures to 800F. However, ASME Code Case 1592-7, " Class 1 Components in Elevated Temperature Service," which would allow operation at this temperature, has been approved by the ASME Council for general use.
The NRC, however, has to date limited application of the subject Cede Case to high temperature reactors as discussed in Regulatory Guide 1.87.
g Our specific request is that the Staff approve Code Case 15i
-7 for application to the pressurizer heater element design. We emphasize that we wish to limit the Code Case approval to the heater shecth design as discussed in this letter.
As background to assist the Staff, we also noce that only a small volume of sheath material at the inside surface of the sheath and which is not in contact with reactor coolant will experience temperatures in excess of 800F.
In addition, the bulk sheath material temperature will be approximately 750F and the inside sheath temperature of 825F will not significantly affect the creep or stress rupture characteristics of the sheath material (SA-213, Type 316).
l Your prompt attention to this matter will be appreciated. Our key need date for NRC concurrence with this aspect of the proposed design is July 30, 1976.
s 8201120264 810403 PDR FOIA MADDEN 80-515 PDR The Babcock & Wilcox Company / Estabbshed 1867
L s
abcock & Wilcox Mr. Roger S. Boyd May 18, 1976 This letter request will be referenced in the transmittal letter for pending Amendment 2 to B-SAR-205.
If you desire further information, we are willing to discuss this matter with you.
Very truly yours, BABCOCK & WILCOX COMPANY Nuclear Power Generation L>
Kenneth E. Suhrke Manager, Licensing KES/db Attach.
cc:
T. H. Cox (NRC)
J. J. Happell (B&W)
R. B. Borsum (B&W)(2) l 4
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