ML19210E907
| ML19210E907 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 11/08/1979 |
| From: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Stewart W FLORIDA POWER CORP. |
| References | |
| NUDOCS 7912130181 | |
| Download: ML19210E907 (2) | |
Text
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NUCLEAR REGULATORY COMMISSION 3 \\ be
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Docket No. 50-302 UU
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- lorida Power Corporation I E '1 F 3201 34th Street, South 5t. Detersburg, FLA 33733
- ear Mr. Stewart:
eknekron Rcsearch, Inc. was requested by.the IE staff to pe.4crm a study of operating nuclear power plants with B&W nuclear steam supply iy-tems using their technique for analyzing causally linked events.
Teknekron oerformed a two chase study using this technique which has been previously reported in NURE3/CR 0110 (Phase I) and NUREG/CR 0979 (Phase II).
The results of Phase I
-ere used as one of the three trial methods for Licensee Regulatory Performance Evaluation (LRPE) attempted by the IE staff in 1977 and 1978.
-ne.cs: recent Teknekron stu::y, the results of whicn are sumT.ariced in the enclosed report, is a part of a continuing effort by tne IE staff to develop an ef fective program for LRPE.
Several approaches to LRPE were attempted
- resiously and tre results were made available to the public in November 1978.
It tnat time it was reported that each of the three approaches attempted l statistical treatment of noncompliance history, ratings by regional inspectors, anc analysis of causally linked events) had strengths and weaknesses, but no single method aas favored by the IE technical staff Foll'ce'ng the Three Mile Island accident, Teknekron was requestec to perform a stud. of operatirq reactors with B&W nuclear steam supply systems to determine if any further safety insights could te gainec by the analysis of coerating experience at these facilities as reportec through Licensee Event Reports
( LE P.).
The importance of evaluating cperating ex::erience is empnasized as a lesson learned from the Three Mile Island accident.
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