[DNFSB
LETTERHEAD]
February 4, 2005
The Honorable Linton Brooks
Administrator
National Nuclear Security
Administration
U.S. Department of Energy
1000 Independence Avenue, SW
Washington, DC 20585-0701
Dear Ambassador Brooks:
Enclosed for your information
and use is a report prepared by the staff of the Defense Nuclear Facilities
Safety Board (Board) on the Preliminary Documented Safety Analysis (PDSA) for
the Pit Disassembly and Conversion Facility.
The report notes that overall, the PDSA is comprehensive. However, it presents several comments for
your consideration to improve the PDSA and the facility design.
The Board and its staff will
continue to follow the issues noted in the report as the facility design
progresses.
Sincerely,
John T. Conway
Chairman
c: Mr. Mark B. Whitaker, Jr.
Enclosure
DEFENSE
NUCLEAR FACILITIES SAFETY BOARD
Staff
Issue Report
January
14, 2005
MEMORANDUM FOR: J. K. Fortenberry, Technical Director
COPIES: Board Members
FROM: H. W. Massie
SUBJECT: Summary Status Report on the
Preliminary Documented Safety Analysis for the Pit Disassembly and Conversion
Facility
This report summarizes the
status of issues associated with the Preliminary Documented Safety Analysis
(PDSA) for the Pit Disassembly and Conversion Facility (PDCF), which is undergoing
Title II design by Washington Group International (WGI). These issues were identified in reviews
conducted by the staff of the Defense Nuclear Facilities Safety Board (Board). The safety analysis is being performed by
Battelle Memorial Institute (Battelle), a major subcontractor to WGI. Los Alamos National Laboratory (LANL) is
providing design support on the plutonium and uranium processing modules and is
the design authority for this work.
Westinghouse Savannah River Company is the design authority for all
other design work and has responsibility for accepting the design and safety
analysis.
Background. The Board and its staff have been reviewing the safety
aspects of the PDCF design. The PDCF is
one of two plutonium disposition facilities to be constructed at the Savannah
River Site (SRS). It is part of a joint
U.S./Russian agreement under which each country will dispose of 34
metric tons of
weapons-grade plutonium. The mission of
the facility is to process 25.6 metric tons of plutonium pits and metal to make
oxide feed for the Mixed-Oxide Fuel Fabrication Facility, also to be located at
the SRS.
Early in the design phase (i.e.,
Title I), the Board’s goal was to identify basic design issues that could have
major safety impacts on the PDCF. The
Board and its staff worked with the National Nuclear Security Administration NNSA
to effect the
following changes in the PDCF design:
Review of Safety
Analysis. The staff reviewed Revision B of
the PDSA and provided an initial list of questions to WGI and NNSA. Based on WGI’s responses to these questions
and a conference call held on October 20, 2004, the staff has resolved many of
the issues raised, but several remain open.
The following discussion summarizes the current status of these issues.
Seismically Induced
Facility Fire―The Board sent a letter to NNSA on May 13, 2003, regarding the
need to address a seismically induced full-facility fire that was originally
proposed by Battelle as a possible design basis accident. The staff report enclosed to the Board’s
letter stated:
During discussions
held in November 1999, the Board’s staff strongly encouraged NNSA to use
properly designed fire barriers, coupled with a sand filter, to provide sufficient
design margin against large fires. More
recently, the Board’s staff reviewed the Title I design of the PDCF and
commented that it is essential for fire barriers, irrespective of their fire
rating, to survive the design basis earthquake to mitigate the full-facility
fire scenario.
The Board also noted that not
all of the fire barriers within the plutonium processing building were rated as
3-hour barriers. Had this been the case,
the potential for this accident scenario would have been eliminated. In response to the Board’s letter, however,
NNSA opted to have WGI and Battelle conduct a fire risk analysis to determine
the probability of a full-facility fire occurring as the result of a design
basis earthquake. The conclusion of the
fire risk analysis was that a seismically induced full-facility fire (resulting
in a heat release rate of 170 megawatts) is a beyond-design-basis
accident. WGI and Battelle then
developed a more reasonable design basis accident for the PDSA. The revised accident scenario is a
seismically induced three-room fire (with a heat release rate of 12 megawatts),
which results in a calculated offsite dose of 0.8 rem. The staff reviewed the basis for the analysis
and found the results to be reasonable.
To determine the amount of
safety margin provided in the design, WGI/Battelle calculated the size of a
fire needed to reach the evaluation guideline of 25 rem. In response to a question posed by the
Board’s staff. WGI/Battelle stated that
the confinement ventilation design provides significant safety margin, with the
ability to mitigate fires with a heat release rate in excess of 100
megawatts. The staff determined that
this statement is true only if the safe haven doors are closed; otherwise, the
leak path factor increases. However, the
safe haven doors may be open during a fire to allow for employee egress. WGI/Battelle noted that the effect of having both
the safe haven doors and the shipping bay outer doors open is to double the
leak path factor, which should double the calculated dose to the public. Controls on the safe haven doors (e.g., interlocks)
might provide defense in depth for large fires.
In summary, the staff agrees
that a seismically induced full-facility fire is a beyond-
design-basis accident. However, important assumptions behind this
conclusion and the basis for the design basis fire scenarios are not adequately
captured in the safety basis documentation. The staff will continue to review additional
design details related to the amount of combustibles in the facility, including
cables; the placement of fire walls with dampers that isolate the material transfer
system; safe haven airlock procedures; and other assumptions related to fire
initiation and growth.
Integrity
of 3023 Cans―The staff questioned the basis
for the conclusion that a 3013 can would provide one level of safety-class
confinement (i.e., be considered a safety-class component) during an accident
involving a loss of ventilation/cooling in the main vault. The 3013 cans store only pure plutonium oxide
or uranium oxide in the main vault.
WGI/Battelle personnel responded that SRS sponsored fire tests (conducted
by Southwest Research Institute) that demonstrated the robustness of the 3013
cans. The test cans were loaded with
cerium oxide to simulate plutonium oxide, and were fully engulfed in flame
within a propane-fired oven. While some
container deformation occurred, no ruptures were experienced at a temperature approaching
2000°F, which is
much greater than the maximum temperature that would be reached in an accident
involving a loss of ventilation/cooling.
The test results were recently documented in a report for the K-Area
Material Storage Project. The staff
finds that the loss of cooling issue is closed for PDCF; however, the fire
testing was not sufficient to demonstrate that 3013 containers holding impure
plutonium oxide or plutonium metal would survive a fire in the K-Area Materials
Storage facility without the protection of a Type B shipping container.
Redesign
of Milk Bottles―Calcined material (oxide) will
be stored in the interim storage area in steel containers called “milk bottles”.
The current milk bottle design has a
sealed lid, which could fail and lead to a release of material as a result of
heatup and overpressurization during a loss of ventilation/cooling in the
interim storage area. The Board’s staff
questioned the project’s position that this failure would be a gradual venting
condition as the lid retainer yielded.
No test data on bottle failure are available. Additional testing will be performed at LANL
to determine whether moisture in a sample of oxide material is a sufficient
pressurization source to cause the bottles to fail below 200°F. This temperature is in excess of the maximum
calculated oxide temperature (160°F) during the postulated loss-of-cooling
accident.
If the testing shows that sealed
milk bottles can overpressurize as a result of moisture in the material, a
design feature (a porous sintered metal plug) may be added to allow filtered venting
of the bottles during heatup. However,
an operational consideration is that if the bottles have a filter, the material
they contain may adsorb moisture from the air and have to be recalcined to
remove that moisture before being packaged into 3013 containers. The staff will review the results of the LANL
tests when they are available.
Explosions
and Worker Safety Issues―The staff questioned the potential for a steam explosion in
the Sanitization Module. Protection of
the onsite workers from such an event would require safety-significant controls
in the furnace. According to the design
contractor, a redesign of the furnace is in progress. No cooling water will be used internal to the
furnace cavity, precluding the possibility of an energetic reaction.
Safety
Controls to Prevent Melting of Plutonium Metal―In July 2004, the staff inquired
about the need for safety-significant controls to prevent melting of plutonium
metal in the Direct Metal Oxidation processing module. The Direct Metal Oxidation module will heat
pits and plutonium metal to about 600°C to produce plutonium oxide. An over-temperature transient could produce
molten plutonium that could melt through the glovebox and produce significant hazards
to workers. WGI responded that the
design for the PDCF includes a high-high temperature switch to provide defense
in depth against a melt accident.
However, the safety-significant control is a ceramic tray under the
furnace to confine the postulated melt-through, and hence is a mitigative
control. Crediting a mitigative control
instead of a preventive control is inconsistent with the design hierarchy which
prefers preventive instead of mitigative controls. Hence, a preventive safety-significant
control, such as the high-high temperature control, appears appropriate.
Source
Term Calculations―The
staff reviewed several of the assumptions for the source term values in the
PDSA, including the material at risk, the airborne release fractions, and the respirable
fractions. The presentation of the
material at risk in several tables of the PDSA (e.g., Tables 3.4-3 and 3.4-37)
is confusing and difficult to review. A
more logical approach would be to either prepare tables for incorporation into
the PDSA or provide the material at risk for each of the accident scenarios in
a separate calculation (i.e., a roadmap).