ML17219A524

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Forwards Safety Evaluation of Licensee Conformance W/ Guidelines Re Seismic Analysis of Safety Injection Piping. Reasonable Assurance Shown That Appropriate Load & Stress Limits Will Not Be Exceeded Using More Accurate Techniques
ML17219A524
Person / Time
Site: Saint Lucie NextEra Energy icon.png
Issue date: 04/06/1987
From: Miraglia F
Office of Nuclear Reactor Regulation
To: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17219A526 List:
References
TIA-83-54, NUDOCS 8704150155
Download: ML17219A524 (2)


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P, Docket No. 50-389 0

APR 06 lgy FROM:

Frank J. Miraglia, Director Division of PWR Licensing-B Office of Nuclear Reactor Regulation MEMORANDUM FOR:

Luis A. Reyes, Director Division of Reactor Projects Region II oc et e

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SUBJECT:

SEISMIC ANALYSIS OF SAFETY INJECTION PIPING AT, ST.

LUCIE UNIT 2 (TIA 83-54)

By memorandum dated May 2, 1983 (J.

A. Olshinski to D.

G. Eisenhut),

Region II requested that NRR evaluate the modelling used for the St. Lucie Unit 2 safety injection piping and determine the acceptability of the St. Lucie Unit 2 seismic piping analysis that used this modelling method.

The enclosure to the Region II letter had a more definitive description of the Region II concerns.

The concerns centered on the modelling techniques used in the seismic analysis of the piping, and the verification that the refueling water tank nozzle design includes all appropriate piping loads.

We have completed our review.

We conclude that although the licensee did not conform fully with the guidelines for choosing the interface point in the piping calculations, there is reasonable assurance that the appropriate load and stress limits will not be exceeded if more accurate techniques are used in the seismic analysis of these piping systems.

We also conclude that the RWT nozzle has been shown to have been evaluated based on the combined loading determined from both piping analyses.

I We apologize for our delayed response to the Region II request for assistance.

This completes our work under TIA 83-54.

Our detailed Safety Evaluation is enclosed.

Original signe'Q bp,'rank J. Hiragana Frank J. Miraglia, Director Division of PWR Licensing-8 Office of Nuclear Reactor Regulation i*

Enclosure:

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