ML20045D399
| ML20045D399 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/09/1993 |
| From: | Boger B Office of Nuclear Reactor Regulation |
| To: | Robare D GENERAL ELECTRIC CO. |
| Shared Package | |
| ML20044B612 | List: |
| References | |
| NUDOCS 9306280327 | |
| Download: ML20045D399 (2) | |
Text
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UNRED STATES 3
,1 NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20505 February 9, 1993 Mr. David J. Robare, Manager Plant Licensing Services General Electric Nuclear Energy 175 Curtner Avenue San Jose, California 95125
Dear Mr. Robare:
SUBJECT:
GENERAL ELECTRIC COMPANY (GE) TOPICAL REPORT NEDC-31336 " GENERA ELECTRIC INSTRUMENTATION SETPOINT METHODOLOGY" We have completed our review of the subject topical report submitted by General Electric in October 1986. provides our Safety Evaluation Report (SER) in which we conclude that:
1.
Although NEDC-31336 is an importaat reference for understanding how GE selects instrumentation setpoints, the topical report is not to be used by any plant to validate their individual setpoints.
That is, each plant must provide its own plant unique analysis for the setpoints.
The examples given in the topical report are used by GE only to show the safety margins and typical channel errors that might be expected.
Since plants have different instruments, environments, seismic and other l
requirements, only examples have been provided by GE in this report.
2.
Where instruments are used that are different from those presented in NEDC-31336, the licensee must demonstrate that drift is, or is not random, it is normally distributed and can be quantified.
3.
The general methods used by GE in selecting instrumentation setpoints are acceptable.
4.
The use of single-sided confidence tests is only acceptable for those channels that provide trips in one ' direction.
9306280327 930623 PDR ADOCK 05000410 p
a Mr. David J. Robare, Manager February.9, 1993 5.
NEDC-31336 is only acceptable for determining instrumentation trip.
setpoints (not evaluating indicators) using equipment that is not in a harsh (e.g. accident) environment.
In accordance with procedures established in NUREG-0390 " Topical Report Review Status," we request that the BWR Owners Group publish NEDC-31336 within 3 months of receipt of this letter. The accepted proprietary version should (1) incorporate this letter and the enclosed Safety Evaluation Report between l
the title page and the abstract and (2) include an -A (designated accepted) following the report identification symbol.
Should our acceptance criteria or regulations change so that our conclusions as to the acceptability of the-report are no longer valid, the BWR Owners Group and/or the applicants referencing this topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued applicability of the topical report without revision of its documentation.
l, Sincerely, Ori:!r.21ST ?d By:
%:::1.0;er Bruce A. Boger, Director l
Division of Reactor Controls and Human Factors Office of Nuclear Reactor Regulation 1
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