Mark Leyse and PRM-50-84 at ACRS, December 15, 2011

Here is the reference:

http://pbadupws.nrc.gov/docs/ML1202/ML120200495.pdf

Mark Leyse is referred to as Mark Lacey

The Members wanted to see Statements of Consideration if possible.
There was a petition from Mr. Lacey concerning the effects of crud. 132-133, 161

Official Transcript of Proceedings
NUCLEAR REGULATORY COMMISSION
Title: Advisory Committee on Reactor Safeguards
Materials, Metallurgy and Reactor Fuels
Docket Number: (n/a)
Location: Rockville, Maryland
Date: Thursday, December 15, 2011

MEMBER SHACK: There was a statement that
19 the new rule was going to address Mr. Lacey's
20 petition, and I haven't seen anything that really does
21 that. Is it something in the Statement of
22 Considerations?
23 MR. CLIFFORD: There was an analytical
24 requirement added to the rule itself that said the
25 effects of crud have to be accounted for.

MEMBER SHACK: I missed it. I missed it.
2 MR. CLIFFORD: So, any new LOCA model we
3 review they would have to say how are they accounting
4 for crud.
5 MEMBER SHACK: I missed it.
6 CHAIR ARMIJO: Paul, don't most of them
7 already do that?
8 MR. CLIFFORD: A lot of them. I can't say
9 -- there are a lot of LOCA models dating back decades
10 some of them. A lot of them do.
11 CHAIR ARMIJO: Yes.
12 MR. CLIFFORD: I can't say that they all
13 do.
14 CHAIR ARMIJO: Okay.
15 MR. CLIFFORD: But they may not
16 specifically account for it, but the way you measure
17 oxidation layers, sometimes you get the tenacious crud
18 that's mixed in with the oxide when you do your eddy
19 current testing.
20 CHAIR ARMIJO: Yes.
21 MR. CLIFFORD: You get a combination of the
22 two, so when you adjust your oxidation model you're
23 kind of getting the inherent -- some inherent effects
24 of tenacious crud.
25 CHAIR ARMIJO: Yes. Yes. Is that it?

 Slide by  Tara Inverso
Rulemaking Purpose
• Revise ECCS acceptance criteria to
reflect recent research findings
• SECY-02-0057
– Replace prescriptive analytical
requirements with performance-based
requirements
– Expand applicability to all fuel designs
and cladding materials
• Address concerns raised in two
PRMs: PRM-50-71 and PRM-50-84

Here is the link to PRM-50-84:

http://pbadupws.nrc.gov/docs/ML0708/ML070871368.pdf

Here is the biography of ACRS Member William Shack at the time of his appointment to ACRS on October 19,1993:

No. 93-154 FOR IMMEDIATE RELEASE
Tel. 301/504-2240 (Tuesday, October 19, 1993)
 
NRC NAMES DR. WILLIAM J. SHACK
TO ADVISORY COMMITTEE ON REACTOR SAFEGUARDS
 
The Nuclear Regulatory Commission has appointed Dr. William
J. Shack, Associate Director of the Energy Technology Division,
Argonne National Laboratory in Chicago, Illinois, to the
independent Advisory Committee on Reactor Safeguards (ACRS).
The ACRS was established in 1957 by the Congress to advise
the former Atomic Energy Commission, and subsequently the Nuclear
Regulatory Commission, with regard to the safety aspects of
proposed and existing nuclear facilities and the adequacy of
related safety standards. The ACRS also performs such other
special assignments as the Commission may request, including the
review of related research programs.
 
Dr. Shack was born in 1943, in Pittsburgh, Pennsylvania. He
received his B.S. degree in civil engineering from the
Massachusetts Institute of Technology (MIT) in 1964, and his M.S.
and Ph.D. degrees in applied mechanics from the University of
California-Berkeley in 1965 and 1968, respectively.
In 1968, Dr. Shack joined the Mechanical Engineering
Department at MIT as an assistant professor. He taught there
until 1975.
 
He joined Argonne National Laboratory in 1975. His work has
included measurement and modeling of residual stresses, fracture
mechanics analyses of stress corrosion crack growth, assessment
of leak-before-break behavior in piping systems, and fatigue of
reactor materials.
 
Dr. Shack is the author or coauthor of more than 75
publications on a variety of topics in applied mechanics and
materials behavior. He has served on the NRC Piping Review
Committee and various ad hoc NRC committees to assess the impact
of environmentally enhanced material degradation on reactor
safety and operation. He has also been involved in research on
corrosion and stress corrosion cracking of candidate materials
for the Yucca Mountain, Nevada, high-level waste repository
project.