ML20030C096

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RO 335-81-19:on 810410,NSSS Vendor Found to Have Failed to Perform Licensing Type Analyses Using Licensing Assumptions for Certain Postulated Accidents Assuming Reactor Coolant Pump Trip Upon Safety Injection Activation
ML20030C096
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/10/1981
From: Wethy C
FLORIDA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-335-81-19, NUDOCS 8108250391
Download: ML20030C096 (1)


Text

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APR l'61981

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B AS, NGR, RRJ Offsite: ADS, JRB, COW, PLP, REU, KNH FLORIDA POM.R & LIGHT COMPANY To:

Mr. J. P. O'Reilly, Director, Region II April 10, 1981 Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission

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Atlanta, GA 30303 s

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Mr. C. M. Wethy, Plant Manager s

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St. Lucie Plant - DPR167 D

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Florida Power & Light. Company

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7 ej y Miami, Florida

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Subject:

MEMO FOR FACSIMILE TRANSMISSION TO CONFIRM P T

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REPORTABLE OCCURRENCE 335-81-19 e,

4 Accident Analyses without RCP - Trip.

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This confirms the telephone notification to Mr. Dance of your office at 4:25 PM, 4/10/81.

Event In review of analyses planned and in progress for the cycle 5 refueling safety evaluation it came to our attention that our NSSS vendor (C.E.)

has not performed the licensing type analyses using licensing assumptions for certain postulated accidents (MSLB, S/G Tube Rupture, Excess load) using the assumption that the RCP's are tripped as mandated by the NRC upon receipt of a Safety Injection Actuation Signal. As the NRC knows, licensing type analysis of automatic auxiliary feedwater initiation on MSLB has not been performed with the assumption of lack of procedurally required operator action to isolate feed flow to the affected S/G.

This is-reportable per T.S. 6.9.1.9.h.

The vendor has informed us this is not generic.

1.r Action Analysis of RC. trip for LOCA has been performed (CEN-ll5).

Best estimate engineering analyses for these events have been performed. Additionally licensing analyses for similar vendor plants have been satisfactorily performed. Based on the above the vendor has stated they are confident no significant safety question exists and continu(d operation is easily justified while such analyses are done. The FP&L Nuclear Analysis group has concurred with the vendor statements and recommendations for continued operation. We do not know exactly how this situation came about at this time.

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K M. Wethy Plant Manager St. Lucie Plant CMW/RRJ:cc

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