ML19224A811
| ML19224A811 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/19/1979 |
| From: | Milhoan J NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | Minogue R NRC OFFICE OF STANDARDS DEVELOPMENT |
| Shared Package | |
| ML19224A812 | List: |
| References | |
| NUDOCS 7905300437 | |
| Download: ML19224A811 (2) | |
Text
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UNITED STATES h
[1 NUCLEAR REGULATORY COMM!ssiON 7 ! * ! S WASHINGTCN, D. C. ' CESS
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APR 191975 MEMORANDUM FOR:
Robert B. Minogue, Director, Office of Standards Development FRCM:
J. L. Milhoan, RSSB, SD
SUBJECT:
SAFETY-RELATED OPERATOR ACTICN STUDY The Office of Standards Develcpment requested (R. B. Minogt memo to S. Levine dated January 6, 1978)
RES to initiate research egarding post-accident operator action times, in support of SD Task y RS-708-S.
We stated the results of this research would be used to evaluate the operator action time criteria specified in the ANS Standard N660,
" Criteria for Safety-Related Operator Action."
The N660 standard establishes requirements for determining whether a protective action to initiate or adjust a safety system may be performed by the operator or must be acccmplished by an autcmatic protection system.
PES has initiated a contract with ORNL to perfom research in the area of safety-related operator action.
ORNL proposes four phases of research(described in greater detail in ORNL prcposal)as follows:
Phase 1 Preliminary Assessment (ccmpleted}-Determination of the availability of field data and development of precedures to collect data Phase 2 Field data collection - Collect and analyze data frcm operating experience Phase 3 Simulator Calibraticn Experiments-Develop / Adapt methods for " calibrating" simulator results (e.g.,
correlate simulator data to actual operating data)
Phase 4 - Simulator Experiment Program-Perform simulator experiments and analyze simulator generated data The scope of the preliminary assessment was limited (e.g., cnly S sites were reviewed), thus a judgment concerning the validity of the quantitative values for time margins for operator respcnse discussed in the stancard was not possible.
Mcwever, a conclusion of the preliminary assessment is that while a large supply of actual operating 168 178 mssoo y37 y %L
b, To R. S. Minogue experience data is not available, there probably is sufficient data to provide a data base for conducting simulator experiments. Attached are copies of the draft final report on the preliminary assessment phase of the study and a program proposal for the remaining phases of the study.
This study will be discussed at a meeting of the Human Engineering Review Group cn May 2,1979.
This study is unique frem other studies utilizing simulators in that the results frcm the simulator experiments will be correlated to actual operating experience.
This shculd be useful in examining the criteria set forth in the Nf60 standard.
The results of the study should also be applicable in areas not directly related to the N660 criteria.
For example, the simulator experiment program could be used to determine the validity of present simulator training programs with respect to thei,rgity to model actual operating experience.
If, in the future,#sgulariens are developed in the area of nuclear pcwer plant simulators, the results of this study should also be use-ful in establishing acceptance criteria for simulator training programs for reactor operators.
As the safety-related cperator acticn study progresses, I will keep-you informed of its status and significant results.
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J. L. Milhoan SD Representative to the Human Engineering Research Group
Enclosures:
As Stated cc:
w/ enclosures:
R. G. Smith G. A. Arlotto W. M. Morrison D. F. Sullivan 168 179