ML20206Q339

Provides Update on Status of Resolution of follow-up Actions from Resolution of Dpv on Dynamic Testing of Instrumentation at Braidwood Station

ML20206Q339
Person / Time
Site:	Braidwood
Issue date:	01/05/1999
From:	Spessard R NRC (Affiliation Not Assigned)
To:	Sheron B NRC (Affiliation Not Assigned)
Shared Package
ML20206Q280	List: ML20206Q275 ML20206Q283 ML20206Q321 ML20206Q339 ML20206Q348 ML20206Q377 ML20206Q392 ML20206Q420 ML20206Q426 ML20206Q453 ML20206Q463 ML20206Q487 ML20206Q560 ML20206Q578 ML20206Q589 ML20206Q605 ML20206Q611 ML20206Q626 ML20206Q636 ML20206Q646
References
NUDOCS 9905190103
Download: ML20206Q339 (4)

Text

. _ _ -

1 4

.h g~g4 UNITED STATES 7 l S

NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 20555-0001

.....l January 5, 1998 MEMORANDUM TO: Brian Sheron, Acting Associate Director l l

for Technical Review j

FROM: R. Lee Spessard, Director

-i Division of Reactor Controls and Human Factors i

SUBJECT:

USE OF MESAC IN BRAIDWOOD The purpose of this memorandum is to provide you with an update on the status of the resolution of the follow-up actions from the resolution of the DPV on dynamic testing of instrumentation at Braidwood Station, in your memorandum to Bruce Boger, Director, Division of Reactor Controls and Human Factors, dated January 2,1997, you requested responses to three DPV panel recommendations on the acceptability of dynamic testing of instrumentacion channels. The staff was directed to evaluate the licensee's (Commonwealth Edison Company) method of accounting for dynamic component setpoint uncertainties in the Braidwood Station accident analyses and to verify that the licensee's use of dynamic testing and its acceptance criteria are bounded by the Braidwood Station accident analyses. In addition, the staff was to document its position including the technical basis for how much uncertainty is acceptable when setting dynamic components in instrumentation channels, and was to determine the acceptability of technical specifications that do not specify tolerances for dynamic component setpoints.

By letter dated May 5,1997, the NRC staff requested information from the licensee concerning the effect of dynamic component uncertainties on the Braidwood/ Byron updated final safety analysis report (UFSAR) analyses, technical specifications (TSs), and setpoint methodology. In this letter, the staff requested a list of all safety related 9905190103 990513 i PDR DRO NE TOP  ;

PDR i

.wy1iv n ~