ML20207Q204

Forwards Technical Review Rept AEOD/T609, Foreign Matl & Debris in Safety-Related Fluid Sys. Procedures Used to Minimize Addition of Foreign Matl Into Sys During Maint & Mod Effective.Draft Case Study Rept Re Air Sys Also Encl

ML20207Q204
Person / Time
Issue date:	12/16/1986
From:	Leed E NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Rubin S NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20207Q205	List: ML20207Q204 ML20207Q209 ML20207Q210
References
AEOD-T609, NUDOCS 8701270010
Download: ML20207Q204 (1)

Text

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. December 16, 1986

. MEMORANDUM FOR: Stuart D. Rubin, Chiof

, Reactor Operations Analysis Branch Office for Analysis and Evaluation AE0D/T609 of Operational Data THRU: Patrick Baranowsky, Chief Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data FROM: Eric J. Leeds, Reactor Systems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data

SUBJECT:

FOREIGN MATERIAL AND DEBRIS IN SAFETY.RELATED FLUID SYSTEMS The enclosed technical review report is forwarded for your information and consideration. The study found that formal written procedures are commonly used at nuclear power plants to minimize the introduction of foreign material and debris into safety-related fluid systems during system maintenance and modification activities and that these procedures appear to be generally effective. The study also found that a limited number of operating events have been attributed to foreign material and debris contamination during maintenance or modification and that there is relatively minor safety significance associated with these events. The study concludes there is limited risk significance which can be associated with the effect of foreign material and debris on safety.related fluid systems. Therefore, it is suggested that no further AE0D review on this subject be taken at this time, pf Eric J. Leeds, Reactor Systems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data Erclosure: '

As stated DISTRIBUTION:

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