RBG-21-900, Forwards Revised Stuck Open Relief Valve Base Case & Suppl 2 to Preliminary Equipment Survivability Rept, Per 850812 Meeting.Analysis of Wetwell Hydrogen Igniters for Revised Thermal Profiles Will Be Submitted by 850821
| ML20134G949 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/19/1985 |
| From: | Booker J GULF STATES UTILITIES CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20134G952 | List: |
| References | |
| RBG-21-900, NUDOCS 8508280168 | |
| Download: ML20134G949 (2) | |
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.f-GULF. STATES UTELETIES COMPANY P O S T O F F I C E B O X 2 9 51.OEAUMONT. TEXAS 77704 AREACoDE 409 838 8831 August 19, 1985 RBG - 21,900 File No. G9.5 Mr. H. R. Denton Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 River Bend Station Unit 1 Docket No.~50-458
Dear Mr. Denton:
Gulf States Utilities (GSU) is providing supplementary information to assist in your evaluation of the adequacy of the Hydrogen-Control System at River. Bend Station. This supplementary information consists of two' attachments. provides a revised CLASIX-3 analysis for the Stuck Open Relief Valve (SORV) base case.
The revised SORV base case analysis used assumptions agreed upon during the August 12,
- 1985, meeting between the NRC Staff and GSU. During this meeting, the staff also suggested that condensation on heat sinks and equipment surfaces be included in the revised analysis.
Inclusion of condensation in the CLASIX-3 analysis is appropriate and would be effective in reducing the 2
predicted thermal environment.-
However, due to the time available to perform the re-analysis, this effect was not included.
evaluation of the River Bend Station equipment response to provides an deflagration type hydrogen burns. The thermal environment utilized in
.this analysis was obtained from the revised SORV base case. The results of this survivability analysis show that the analyzed equipment is capable of surviving the postulated hydrogen generation event. Since the equipment-analyzed has been -previously shown to be the most sensitive to.a deflagration burn environment, it can be reasonably concluded that all equipment in the intermediate volume will survive the
~
hydrogen ; generation event.
Analysis of the wetwell hydrogen igniters for the revised thermc1 profiles will be submitted by August 21, 1985.
8508200168 850819
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PDR ADOCK 05000458 i
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If this additional analysis and the results of the Hydrogen Control Owners Group quarter scale testing program indicate that measures should be taken to enhance equipment survivability, this information will be provided at the fi'.st refueling outage or some other schedule agreed to with your staff.
Very truly yours, I.
o J. E. Booker Manager-Engineering, Nuclear Fuels & Licensing River Bend Nuclear Group EJZ/MAM/do Attachments