ML19329C750
| ML19329C750 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/18/1975 |
| From: | Ippolito T Office of Nuclear Reactor Regulation |
| To: | Benaroya V, Lainas G, Novak T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8002190866 | |
| Download: ML19329C750 (1) | |
Text
l CEC 13 1975 Docket Number 50-346 NOTE TO:
V. Benaroya, Auxiliary Power and Conversion Systems Branch, TR T. Novak, Reactor Systems Branch, TR G. Lainna, Containment Systems 3 ranch, TR
- 3. Grimes, Accident Analysis Branch, TR DAVIS BESSE UNIT 1 - ESSENTIAL POST-ACCIDENT MONITORING PARAMETERS Branch Technical Position EICSB 23 (in Appendix 7-A of the SRP) addresses requirceents for qualification of safety-related display instrumentation for post-accident condition monitoring and safe shutdevn. The position establishes the acceptability of and the criteria for providing the operator with sufficient reliable in-for=ation to allow hin to follow the event and take appropriata action if necessar/.
In order to inaure complete EICSB review covera;;e of all systems, we request that the cognizant reviewers in your branch be advised to identify (in writing to the EICSJ raviewer) the speicfic parameters in their systems to which 3T' EICS3 23 should be applied, for the Davis Lesse Unit 1 (OL) application, me.d suned by T. A. IM",hto Thomas A. Ippolito, Chief Electrical, Instrumentation and Control Systems Branch Division of Technical Review cc:
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