ML20212A905

Forwards AEOD/T610, Automatic Depressurization Sys (Ads)/ RCIC Sys Interaction Events at River Bend-1. Unavailability of RCIC Sys Insignificant.Licensee Corrective Actions Adequate to Prevent Future Ads/Rcic Sys Interaction

ML20212A905
Person / Time
Site:	River Bend
Issue date:	12/19/1986
From:	Leeds E NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
To:	Rubin S NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD)
Shared Package
ML20212A911	List: ML20212A905 ML20212A940
References
AEOD-T610, NUDOCS 8612290079
Download: ML20212A905 (1)

Text

r' fo December 19, 1986 AE0D/T610 Distribution:

sESSEA.

MEMORANDUM FOR: Stuart D. Rubin, Chief ROAB CF Reactor Operations Analysis Branch AE0D SF Office for Analysis and Evaluation E. Leeds of Operational Data P. Baranowsky S. Rubin THRU:

Patrick Baranowsky, Chief F. Hebdon Reactor Systems Section 1 C. Heltemes 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:

ADS /RCIC SYSTEM INTERACTION EVENTS AT RIVER BEND-1 The enclosed technical review report is forwarded for your information and consideration. The study found that the events at River Bend-1 involving the ADS /RCIC system interaction appear to have limited safety significance. Each event resulted in the RCIC system being unavailable for less than an hour until the system was returned to the standby condition. The resultant unavailability of the RCIC system was estimated to be nearly insignificant compared to the system's expected yearly total unavailability. The study also found that the ADS /RCIC system interaction events at River Bend-1 were plant-specific events and are not a generic concern.

Finally, it appears that the licensee's corrective actions are adequate to prevent recurrence of an ADS /RCIC system interaction. Therefore, it is suggested that no further AE0D action concerning this subject be taken at this time.

A

~

Eric J.

eds, Reactor Systems Engineer Reactor Systems Section 1 Reactor Operations Analysis Branch Office for Analysis and Evaluation of Operational Data

Enclosure:

8612290079 861219 As stated PDR ADOCK 05000458 S

PDR cc w/ enclosure:

S. Stern, NRR M. Beaumont, W R. Borsum, B&W D. Ch berlain, IV C. Brinkman, UE L. Gifford, GE OfC

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C AE0D

.f/.__.:_/ROAB NAME :Elee s:rm

PBa nowsky :SRubin

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