Information Notice No. 91-63: Natural Gas Hazards at Fort St. Vrain Nuclear Generating Station
UNITED STATES
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
October 3, 1991
NRC INFORMATION NOTICE 91-63: NATURAL GAS HAZARDS AT FORT ST. VRAIN
NUCLEAR GENERATING STATION
Addressees
All holders of operating licenses or construction permits for nuclear power
reactors.
Purpose
The U.S. Nuclear Regulatory Commission (NRC) is issuing this information
notice to alert addressees to problems that could result from the presence
of natural gas at nuclear facilities. It is expected that recipients will
review the information for applicability to their facilities and consider
actions, as appropriate, to avoid similar problems. Although this notice
specifically describes hazards associated with natural gas, licensees should
note that similar hazards may be imposed by other toxic, flammable, or
explosive materials which may be brought into close proximity to licensee's
facilities. However, suggestions contained in this information notice are
not new NRC requirements; therefore, no specific action or written response
is required.
Background
When the Fort St. Vrain facility was licensed in 1973, no natural gas
pipelines were located nearby; thus, neither the licensee's final safety
analysis report nor the NRC staff's safety evaluation report addressed the
hazards associated with natural gas present in geological formations in the
area. In 1974, a 16-inch low pressure natural gas collection pipeline was
constructed nearby by a natural gas company. This pipeline crossed a corner
of the licensee's property about 0.9 mile from the reactor building. At its
closest point, this pipeline came within 0.85 mile of the reactor building.
Although the pipeline was not constructed by the Public Service Company of
Colorado (PSC), the Fort St. Vrain licensee, PSC was informed of its
construction.
Between 1981 and 1983, 12 natural gas wells were installed within about one
mile of the Fort St. Vrain reactor building. Seven of these wells were
drilled on land owned by the Fort St. Vrain licensee by a company that had
acquired the mineral rights from the licensee. Some of these wells were
located within the Exclusion Area Boundary, but all were outside of the
protected area. Nine of these wells were connected to the 16-inch
collection pipeline by a 6-inch pipeline. The closest well was located 1524
feet from the reactor building, and the 6-inch pipe passed within 1340 feet
of the reactor building. Personnel involved in the drilling of these wells
and the licensee's manager of nuclear production concluded that possible
accidents at the well sites would not
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October 3, 1991
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produce adverse effects further than 300 feet from the wellheads. The
licensee did not prepare any written analyses for any of the wells or
pipelines.
Late in 1987, PSC allowed the drilling of a gas well within 1184 feet of the
Fort St. Vrain reactor building, which was within the Exclusion Area
Boundary and 300 feet from the protected area fence. The pipeline
associated with this well passed within 560 feet of the Fort St. Vrain
switchyard. PSC prepared a 10 CFR 50.59 safety evaluation that concluded
that in the event of a well fire caused by a blow out, the area affected
both by the fire and the equipment needed to control it would not be larger
than the existing drillsite location. The licensee also concluded that the
air temperature beyond a radius of 200 feet would not be elevated above the
ambient temperature and therefore, the construction and operation of the
closest well did not create the possibility of a new type of reactor plant
accident or constitute an unreviewed safety question. The safety analysis
did not evaluate the consequences of a rupture of either the 6-inch or
16-inch pipeline and did not postulate the release of a cloud of natural gas
which might drift toward safety-related structures or equipment and ignite
and either burn or detonate.
Description of Circumstances
On August 18, 1989, the licensee shut down the Fort St. Vrain facility and,
by letter of August 29, 1989, informed the NRC that the plant would be shut
down permanently. In November 1990, the licensee submitted a proposed
decommissioning plan. While reviewing the proposed decommissioning plan,
the NRC became concerned that plans to introduce natural gas at Fort St.
Vrain as part of a proposed repowering of the facility could lead to an
accident that had not been reviewed. During this review, the NRC further
determined that the licensee had not adequately addressed the natural gas
already on site. The licensee responded by preparing analyses that
addressed the limiting failures of all natural gas pipelines existing on
site. Before completing these analyses, the licensee took prompt corrective
actions to limit the amount of natural gas that could be released from a
large rupture of the 6-inch collection pipeline. These actions consisted of
closing a 6-inch valve and opening a 1 1/2-inch bypass valve in the line
that carried gas from the wells to the 16-inch collection pipeline. This
configuration would reduce the gas leakage from a rupture in the 6-inch
pipeline by reducing the flow of gas back from the 16-inch pipeline.
The NRC staff reviewed the licensee's analyses including those regarding
flammability and explosive hazards associated with the gas cloud that could
be released by a postulated worst-case rupture of a wellhead or pipelines.
Both the licensee and the NRC determined that, with the compensatory
measures taken, postulated accidents associated with the natural gas on site
would not affect the safe storage of spent fuel or other radioactive
components in the reactor building. After reaching this conclusion, the NRC
issued the Fort St. Vrain possession only license (POL) amendment on May 21,
1991. The POL amendment included a license condition that requires the
licensee to obtain the NRC's approval before making changes to the
collection system that would involve permanently opening the 6-inch valve.
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In August 1991, the licensee completed additional analyses which indicated
that postulated explosions or deflagrations resulting from natural gas line
ruptures with the 6-inch line open would not have resulted in unacceptable
consequences at the Fort St. Vrain reactor building or at the switchyard.
Nevertheless, PSC indicated that redundant check valves would be installed
in the 6-inch pipeline to reduce the possibility that natural gas could flow
back from the 16-inch pipeline, if the 6-inch line ruptured.
Discussion of Safety Significance
The natural gas pipelines and wells completed between 1973 and 1983
introduced additional unanalyzed external hazards that could have affected
the safe operation of the Fort St. Vrain facility. These additional hazards
were not evaluated by the licensee prior to their introduction to the site
to determine the impacts on the safe operation of the plant and whether
these hazards exceeded those evaluated during the initial licensing of the
facility. For the gas well drilled in 1987, the licensee's 10 CFR 50.59
evaluation was too narrowly focused and did not consider additional possible
malfunctions before concluding that an unreviewed safety question was not
involved.
This information notice requires no specific action or written response. If
you have any questions about the information in this notice, please contact
one of the technical contacts listed below or the appropriate Office of
Nuclear Reactor Regulation project manager.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical contacts: Richard Dudley, Jr., NRR
(301) 492-1116
Stephen Koscielny, NRR
(301) 492-0726
Attachment:
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