The DAB Safety Team Agrees With Newly Released MHI Data:
Plug All Of SONGS Unsafe Tubes, Not Just Some
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The DAB
Safety Team along with the support of an ever-growing number of SONGS
Concerned Insiders and Whistleblowers, prepared the
following analysis, which is consistent with the conclusions presented
in the publicly available reports provided earlier on this subject by:
1. Fairewinds Associates Internationally Known Nuclear
Consultant Arnie Gundersen and his team of Anonymous Industry insiders, who
have had lengthy careers in the design, fabrication, and operation of nuclear
steam generators.
2.
Professor Daniel Hirsch and Internationally Known Nuclear
Consultant Dale Bridenbaugh.
3.
Publicly available posted documentation by Dr. Joram
Hopenfeld, a retired engineer from the Office of Nuclear Regulatory Research
and NRC's Advisory Committee on Reactor Safeguards (ACRS) report issued in
February 2001, which substantiated many of Dr. Hopenfeld's concerns,
4.
David A. Lochbaum, Director of the Nuclear Safety Project
for the Union of Concerned Scientists (UCS).
MHI Part 21 (10/05/2012) - Steam Generator Tube Wear Adjacent To
Retainer Bars:
The following information was received via email: "Mitsubishi Heavy
Industries, LTD (MHI) has identified steam generator tube wear for San Onofre
Nuclear Generating Station. "The Steam Generator tube wear adjacent
to the retainer bars was identified as creating a potential safety hazard. The
maximum wear depth is 90% of the tube thickness. The cause of the tube wear has
been determined to be the retainer bars' random flow-induced vibration caused
by the secondary fluid exiting the tube bundle. Since the retainer bar has a
low natural frequency, the bar vibrates with large amplitudes. This type tube
wear could have an adverse effect on the structural integrity of the tubes, which
are part of the pressure boundary. The plugging of the tubes that are adjacent
to the retainer bars was performed. MHI has recommended to the purchaser to
remove the retainer bars that would have the possibility of vibration with
large amplitude or to perform the plugging and stabilizing for the associated
tubes."
SCE Unit 2 Restart Plan, Attachment 4, Page 9, Line 13, MHI
States,
"In order to ensure the structural integrity of the tubes after restarting
the plant, all tubes which have a potential for losing their integrity
during the next operating period should be plugged and thermal power
output of the plant should be decreased. Plugging for the Type 1
wear should include not only the tubes with the Type 1 (tube-to-tube) wear
but also tubes which are susceptible to the Type 1 wear, for preventative
reasons." Attachment 4, Page 82, Section 8.1.3, MHI states, “ Tubes with wear indications
adjacent to the retainer bars should be plugged regardless of the wear depth.
Furthermore, all tubes that have a possibility to come in contact with the
retainer bars should be preventatively plugged.” SONGS Technical Specification states, “Structural integrity
performance criterion: All in-service steam generator tubes shall retain
structural integrity over the full range of normal operating conditions
(including startup, operation in the power range, hot standby, and cool down
and all anticipated transients included in the design specification) and design
basis accidents.”
General design criteria (GDC) 14, “Reactor Coolant Pressure Boundary (RCPB)” of
Appendix A to United States Code of Federal Regulations 10 CFR
Part 50, “Domestic Licensing of Production and Utilization Facilities,”
states “The RCPB shall have “an extremely low probability of abnormal leakage…and
gross rupture.”
Even at 70% power operations, if a steam line break outside
containment were to occur in Unit 2, the depressurization of the steam
generators with the failure of a main steam isolation valve to close would
result in 100% void fraction in the entire U-Tube bundle. This condition
of ZERO Water in the steam generators would cause fluid elastic instability
(FEI) and flow-induced random vibrations.
This adverse condition, in turn would result in hundreds of SG tube
failures/ruptures due to tubes hitting each other because of extremely low tube
clearances, NO in-plane support protection, and movement of retainer bars with large amplitudes
due to low natural frequencies. With an undetermined amount of tube leaks/ruptures,
approximately 60 tons of very hot high-pressure radioactive reactor coolant
would leak into the secondary system. The release of this amount of
radioactive primary coolant, along with an additional approximately 200 tons of
steam in the first five minutes from a broken steam line would EXCEED the SONGS
NRC approved safety margins and result in a nuclear meltdown like Fukushima in Southern California.
Many steam generator tube ruptures and steam line break events
have occurred in the last 30 years at nuclear power plants throughout the world
(See DAB Safety Team’s SONGS
MSLB Analysis). In
light of the Unit 3 Replacement Steam Generators (RSGs) unprecedented eight
tube failures due to 99.6% steam voiding, narrow tube pitch to tube diameter
ratio, low tube clearances and NO
Designed "In-plane Fluid Elastic Instability support protection" and
other tube ruptures/steam line break events, the DAB Safety Team agrees with
MHI that all the Unit 2 Tubes would be susceptible to the Type 1
(tube-to-tube) failures/ruptures due to 100% steam voiding of the entire U-Tube
Bundle in case of a Main Steam Line Break (MSLB). Therefore, to meet the
SONGS Technical
Specifications and GDC
14 of Appendix A to 10 CFR Part 50 for a MSLB and prevent a nuclear accident and reactor
meltdown in California from cascading tube ruptures, all Unit 2 RSG’s Tubes should be preventatively plugged before
Unit 2 Restarts. In other
words, the Unit 2 RSG’s in the “As Designed and Degraded Configuration” cannot
be OPERATED at any “Power Levels” due to the substantial risk of nuclear
meltdown described above.
PRESS RELEASE
The DAB Safety Team: November 21, 2012
Media Contact: Don Leichtling (619) 296-9928 or Ace Hoffman (760) 720-7261
Copyright November 21,
2012 by The DAB Safety Team. All rights reserved. This material may not be
published, broadcast or redistributed without crediting the DAB Safety Team.
The contents cannot be altered without the Written Permission of the DAB Safety
Team Leader and or the DAB Safety Team’s Attorneys.
The background information regarding the condition of Unit 2's RSG tubing and what the Experts have to say about it is listed under the DAB Safety Team TAB above as SCE's NRC Package ML122850320 About Unit 2 Tube Degradation or here: https://docs.google.com/folder/d/0BweZ3c0aFXcFZGpvRlo4aXJCT2s/edit?docId=0BweZ3c0aFXcFR3YwR0sxM1pDczg
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