ML20211C259

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Discusses New Work W/Structural Mechanics Assoc to Perform Detailed Leakage Model Analysis of Containment.Facility Has Robust Large Dry Containment & Simple Thershold Analysis Gives Exceptionally High Ultimate Strength Failure Pressure
ML20211C259
Person / Time
Site: Seabrook  NextEra Energy icon.png
Issue date: 12/09/1983
From: Bernero R
NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
To: Vollmer R
Office of Nuclear Reactor Regulation
Shared Package
ML20209C800 List:
References
FOIA-87-6 NUDOCS 8702200049
Download: ML20211C259 (29)
v • d • e


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.k NUCLE AR REGULATORY COMMisslON

{ .I was.uscros. o c. rosss December 9. 1983 k . . .,. . /

MEMORANDUM FOR: Richard Vollmer, Director Division of Engineering Office of Nuclear Reactor Regulation Guy A. Arlotto, Director Division of Engineering Technology Office of Nuclear Regulatory Research FROM: Robert M. Bernero, Director Accident Source Term Program Office Office of Nuclear Regulatory Research

SUBJECT:

CONTAINMENT CAPABILITY ANALYSIS I received a call from Fred Torre of Pickard, Lowe, and Garrick yesterday and he told me of some new work they have done. For the Seabrook PRA they have worked with Structural Mechanics Associates (R. Kennedy) to perform a detailed leakage model analysis of the containment. Seabrook has a particularly robust large dry containment and a simple threshold analysis gives an exceptionally high ultimate strength failure pressure.

Not only is this pressure so high that valves, seals, etc. are virtually .

certain to fail, but the associated strain displacements will certainly ,

lead to piping and Jenetration failures. PL&G and SMA have developed a probabilistic leakage model based on some detailed analysis of specific features of the containment.

This work could be extremely useful in advancing the state of this art.

I told Fred I would like to get it into the public domain as soon as possible. Fred expects it to be published in January. Bruce Beckley of Public Service of New Hampshire (603-669-4000) assured me that the January release is realistic. I told both Fred and Bruce that we would ask for it through NRR channels. I suggest that Vollmer/Noonan/Bagchi be the ones to seek it. Vic Nerses is the project manager for NRC.

Robert M. Bernero, Director Accident Source Term Program Office Office of Nuclear Regulatory Research cc: V. Noonan D. Eisenhut G. Bagchi M. Silberberg D. Ross M. Ernst R. Mattso 0. Bassett T. Speis /n P. K. Niyogi fo 3 A - 75 7 - 0 Blt S$S22S8?jv e6oan SHOLLYB7-6 PDR

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NORMAN C. RASMUSSEN 082./3 Professor of Nuclear Engineering Massachusetts Institute of Technology KI.T. ADDRESS /

El.T. Rm 24 205 i H ME FFICE Cambridge,MA 02139 & o 3' / 3 - AC s M 80 Winsor Road Sudbury, MA 01776 Tel. 417 268 3802 Tel. 617 443 6018 ,

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14 December 1983 ~

DE01519837 Frank R. Hubbard Pickard, Lowe & Garrick, Inc.

1200 18th Street NW, Suite 612 f[h Washington, D. C. 20036

Dear Frank,

Enclosed are my comments of each of the sections. I have read all sections completely except as noted (4 & 5), but not to a level that checked all results. To give you an idea, here are the times spent reading each section.

1. h hr
2. I hr 9. 3 hrs
3. hr 10. 3 hrs
4. 2 hrs only partially read 11, 5 hrs
5. 2 hrs only partially read 12. 2 hrs
6. 2 hrs 13. 4 hrs
7. 2 hrs
8. I hr I also spent 3 hrs reading sections of the appendices needed to understand the details that went into some of the main ceetions.

I believe I've spent enough time to understand in sufficient detail how the study has been carried out. In addition, I read it with enough care to judge its thoroughness and understandability.

I also spotted some things that didn't look correct,'as noted on the comment sheets.

I think it is an excellent job. It is the most understandable PRA I've yet read. The questions that I asked myself as I read along were usually answered by figures later in the text. As usual, PL & G did a good job of giving results in a lot of different ways in which I believe the reader is interested. I thought the source term discussion was the best I've seen in a PRA and reficcts what good.

I believe is the correct view at this time. Chapter 13 was My specific critical comments are given on attached sheets.

Sorry I did not have time to get the comments typed.

Best regards, fp;// . J '/ (.

fx Norman C. Rasmussen f /

RWim Bla .

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