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Nuclear
Nuclear Industry Overview
Nuclear Power is our future and MLEA Inc. has always maintained a very strong presence in
the Nuclear Power Industry. MLEA Inc. is focused on solving complex technical problems for nuclear utilities. Our principal
engineers average more than 25 years of nuclear plant engineering and operations experience. Below is a list of some of our
recent projects.
Spent Fuel Pool Decay Heat Management
MLEA Inc. recently designed and supported the installation of an Alternate Decay Heat Removal (ADHR) system
at the Cooper Nuclear Station in Brownville, Nebraska. The ADHR system more than doubled the heat removal capacity of the existing spent
fuel cooling at Cooper and provides additional capacity for (1) early fuel movement during outages (2) early outage maintenance of normal
cooling systems and (3) back-up capacity for unexpected events or postulated accidents. [Continue Article]
New Reactor Licensing
Through a subcontract with NUMARK Associates of Washington, DC, MLEA Inc. is providing technical
evaluations of licensing submittals for the New Reactor Office of the US Nuclear Regulatory Commission. Under the NUMARK contract,
MLEA Inc. engineers are reviewing technical submittals for the design certification of the U.S. EPR (Evolutionary Power Reactor) by
AREVA, along with combined license applications for planned EPR units such as Calvert Cliffs 3 and Calloway. MLEA Inc. engineers
compare the design certification or combined license applications against federal regulations and related regulatory guidance (including
appropriate industry standards or topical reports) and prepare technical evaluation reports for the NRC Staff. MLEA Inc. engineers determine
whether or not the applications meet the regulatory requirements and provide conclusions and recommendations to the NRC Staff as appropriate.
The ultimate product of this work are NRC safety-evaluation reports which accept or reject the applications based on regulatory requirements.
Extended Power Uprate (EPU)
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Point Beach:
MLEA Inc. is providing mechanical design support for EPU including the review of calculations, Tech Specs,
Operating Procedures, EOPs and determining testing requirements in preparation for an integrated test program.
Hope Creek:
MLEA Inc. has provided extensive mechanical design support for EPU including the revision of
almost 100 calculations, Tech Specs, Operating Procedures, EOPs and the development of the test plan.
Susquehanna:
MLEA Inc. has provided mechanical design support for EPU including the revision of fuel pool
calculations and onsite support.
Design Support
MLEA Inc. engineers supported the PSEG Nuclear design project to install a closed loop cooling water system for
Salem Units 1 & 2 containment cooling system. This system replaces the service water supply, reduces diesel loading, and enhances reliability.
MLEA Inc. engineers are responsible for all calculations and specifications for the project as well as preparing the UFSAR changes.
Licensing Support
MLEA Inc. engineers excel at solving complex problems at nuclear utilities, recent issues resolved
at the Salem and Hope Creek Generating Stations are:
- Resolution of degraded and nonconforming conditions - CO2 Fire Suppression Systems Switchgear Rooms
and Lower Electrical Penetration Areas
- Calculation to demonstrate the ability of the RHR shutdown-cooling mode to achieve cold shutdown
(reactor outlet temperature below 200°F) within 24 hours using only one RHR heat exchanger and one SACS loop
- Calculations to document the effects on the Service Water System from the automatic response of plant
systems to a LOCA (loss-of coolant accident), LOOP (loss of offsite power), LOCA & LOOP or LOCA & single vital bus
undervoltage
SSFI
MLEA Inc. engineers conducted Safety System Functional Inspections (SSFI) of:
- Diesel Generator and Emergency AC Distribution for Peach Bottom Atomic Power Station
- Emergency Service Water and RHR Service Water for Limerick Generation Station
- 125 Vdc Distribution system for the James A. FitzPatrick Nuclear Power Plant
- Main Steam system for the Indian Point 3 plant
Design Basis
MLEA Inc. engineers supported the response to the USNRC "Request for Information Pursuant to
10CFR50.54(f) Regarding Adequacy of Design Bases Information" for PSE&G's Salem I & II and Hope Creek Generation Stations
and NYPA's James A. FitzPatrick Nuclear Power Plant.
MLEA Inc. engineers are providing guidance and oversight for
Hope Creek Generation Station Design Basis Document (DBD) Project.
Response Team Support
MLEA Inc. provided Response Team support for the PSE&G-sponsored Hope Creek Operational Performance
Inspection of the Service Water and Safety Auxiliaries Cooling System.
MLEA Inc. assisted the PSE&G Response Team
in support of the USNRC-sponsored SSFI of the Salem Component Cooling Water System. Significant issues resolved included
CCW Pump runout, single failure of a room cooler and Emergency Diesel Generator Loading.
MLEA Inc. assisted the NYPA
Response Team in support of the USNRC-sponsored SSFI of the Indian Point 3 Service Water System.
FSAR
MLEA Inc. engineers led the Salem FSAR Project. The FSAR project integrated a series of new initiatives
with several recently completed or ongoing Salem improvement programs related to the plant licensing and design basis. The
new initiatives implemented by the FSAR Project included UFSAR reviews, accident analysis input and assumption validations
and vertical slice reviews.
FMEA
MLEA Inc. identified several scenarios where adverse interactions could occur among safety systems due
to design modifications or plant conditions at Crystal River 3. Postulated failures of DC control circuits were common precursors
to these scenarios. MLEA Inc. performed Failure Modes and Effects Analysis (FMEA) to systematically identify other scenarios. MLEA Inc.
developed the FMEA methodology, coordinated electrical evaluations and assisted in the evaluation of system and plant effects.
50.59
MLEA Inc. engineers prepared and reviewed numerous 10CFR50.59 Safety Evaluations for Salem, Hope Creek
and James A. FitzPatrick.
MLEA Inc. designed and supplied a containment closure device that serves as an atmospheric
ventilation barrier to be installed during refueling outages at nuclear power stations. The containment closure device provides for
rapid isolation to restrict radioactive material released from the containment during a postulated refueling accident. The design allows
for equipment access to the containment building that normally would not be allowed until later in the refueling outage after all
the fuel has been removed from the reactor vessel. This device provides outage scheduling flexibility that can save considerable time
in returning stations to service when planning major equipment outages such as steam generator replacements.
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