ML19308E172
| ML19308E172 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, 05000303  |
| Issue date: | 01/10/1968 |
| From: | Ross D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Boyd R US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8003240699 | |
| Download: ML19308E172 (2) | |
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I for Reactor Projects,'.DRL THRU: Charles C. Lcng, Chief, R*3-3, DRLfS J410 ip DenwoodF.Ross,ReactorProject3ranchNo.)3 Division of Reactor Licensing CONTROL AND INSTRUEiTATION IGETING WIT 3 FLORIDA POWER CORPORA!10N, JANUARY 5, 1960 DOCKET NOS. 50- p & 50-303 A meeting was held with the Florida Power Corporation on January 5,1968.
for the purpose of discussing the control and instrunentation aspects of the Crystal River nuclear units.
Several points of junction of control and safety were noted.
The primary coolant temperatura appeared to be ene, but was resolved to be diagtm-satic enly. However, there is an unresolved joining of the primary coolant pressure measuring channels.
Four are provided, with two out of four required for trip action. One of the four is selected as input to the pressure control circuit. Since all four pressure si: mala are joined in soce canner so as to eclect one for centrol, we asked for further detail as to their physical arrangement.
W asked if the currcat frot.: each four-foot icu chambar could be net surad nr parately and were informd @t it m pessible.
In response to a cuestion about splitting tha scran bus. FpC rene.cd cc;r.cn t.
The undcratand the question, from 7.ctropolitan Edison, but do not care to cermit themselven at this tim.
Va ashed for details on in-a.ervice tecting netheds, protsetion and 2SF systcea, sa related to IEEZ standards.
The applicant stated that the Borated Water Storage Tank level instru-mentation trould be redundant.
We discussed' Criterica 11. Philosophically the applicant objects, but pragmatically he will comply.. Both FPC.and B&W are of the opinion that safety is degraded by local control stations.
There was extended di rcussion en flow =casurmnent, or the lacic of it.
W pointed out car concern, which is castly lack of protaccion to certain flou loss incidents. B&W understands the additional thermal-hydraulic analyses are needed. 7FC asked if dP switches across tha steam gecerator, which would _ trip at a single preset low & P, would be satisfactory; we did_ not approve. The applicant was actified that direct flow acasurement and protective actica may be required.
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FPC noted that they were updating radiation toonitoring section to applicable standards of the. Hatropolitan Edison casa.
We asked about use of in-core instrumentation as related to core hot spots. We also inquired as to the function of out-of-core ion chambers for the sama purpose.
THe applicant did not believe that the out-of-core instrumentation would be called on to detect hot spots; such as those caused by xenon oscillation. However, results of a forthconing core flux computation could cause revision of that position.
Stevens. of 3&W asked if there was any proce' dure that he (or his co=pany) could do to expedito cattara. Rio cencern v.ts replication of effort with different applicants cad different reviewers. We suggeste:i and encouraged the topical report for:aat.
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