AREVA NP Inc.ANP-3203Revision 0<strong>Vermont</strong> Yankee Nuclear Power Station*s Overall Integrated <strong>Plan</strong> in Response <strong>to</strong> March 12, 2012Commission Order Modifying Licenses with Regard <strong>to</strong> Requirements <strong>for</strong> <strong>Reliable</strong> HardenedContainment Vents (Order Number EA-12-050)Page 23To ensure the functionality <strong>of</strong> instruments following a seismic evont the <strong>NRC</strong> staff considers any <strong>of</strong> thefollowing as acceptable methods:• Use <strong>of</strong> instruments and supporting components with known operating principles that are supplied bymanufacturers with commercial quality assurance programs. such as 1S09001, The procurementspecifications shall include the seismic requirements and/or instrument design requirements, andspecify the need <strong>for</strong> commercial design standards and testing under seismic loadings consistent withdesign basis values at the instrument locations.• Demonstration <strong>of</strong> the seismic reliability <strong>of</strong> the instrumentation through methods that predict per<strong>for</strong>manceby analysis, qualification testing under simulated seismic conditions, a combination <strong>of</strong> testing andanalysis or the use <strong>of</strong> experience data. Guidance <strong>for</strong> these is based on sections 7, 8 9, and 10 <strong>of</strong> IEEEStandard 344-2004, “IEEE• Recommended Practice <strong>for</strong> Seismic Qualification <strong>of</strong> Class IE Equipment <strong>for</strong> Nuclear Power GeneratingStations. “or a substantially similar industrial standard could be used.• Demonstration that the instrumentation is substantially similar in design <strong>to</strong> instrumentation that hasbeen previously tested <strong>to</strong> seismic loading levels in accordance with the plant design basis at thelocation where the instrument is <strong>to</strong> be installed (g.4evels and frequency ranges). Such testing andanalysis should be similar <strong>to</strong> that perlbrmed <strong>for</strong> the plant licensing basis.Response (ref. ISG Item 2.2):The HCVS components downstream <strong>of</strong> the second containment isolation valve and componentsthat interface with the HCVS will be routed in seismically qualified structures except <strong>for</strong> thepermanently installed nitrogen tubing and instrumentation located in the Turbine Buildingbetween the Diesel Genera<strong>to</strong>r Room and the Reac<strong>to</strong>r Building. For those components, thestructure will be analyzed <strong>for</strong> seismic ruggedness <strong>to</strong> ensure that any potential failure would notadversely impact the function <strong>of</strong> the HCVS or other safety related structures or components.The HCVS downstream <strong>of</strong> the second containment isolation valve, including piping andsupports, electrical power supply, valve actua<strong>to</strong>r pneumatic supply, and instrumentation (localand remote) components, will be designed/analyzed <strong>to</strong> con<strong>for</strong>m <strong>to</strong> the requirements consistentwith the applicable design codes (e.g., Non-safety, Cat 1, SS and 300#ASME or B31.1, NEMA4, etc.) <strong>for</strong> the plant and <strong>to</strong> ensure functionality following a design basis earthquake.The HCVS instruments, including valve position indication, process instrumentation, radiationmoni<strong>to</strong>ring, and support system moni<strong>to</strong>ring, will be qualified by using one <strong>of</strong> the three methodsdescribed in the ISG, which includes:1. Purchase <strong>of</strong> instruments and supporting components with known operating principles<strong>from</strong> manufacturers with commercial quality assurance programs (e.g., lSO900l) wherethe procurement specifications include the applicable seismic requirements, designrequirements, and applicable testing.2. Demonstration <strong>of</strong> seismic reliability via methods that predict per<strong>for</strong>mance described inIEEE 344-2004.3. Demonstration that instrumentation is substantially similar <strong>to</strong> the design <strong>of</strong>instrumentation previous4y qualified.
AREVA NP Inc.ANP-3203Revision 0<strong>Vermont</strong> Yankee Nuclear Power Station’s Overall integrated <strong>Plan</strong> in Response <strong>to</strong> March 12, 2012Commission Order Modifying Licenses with Regard <strong>to</strong> Requirements <strong>for</strong> <strong>Reliable</strong> HardenedContainment Vents (Order Number EA-12-050)instrumentHCVS Process TemperatureHCVS Process PressureHCVS Process Radiation Moni<strong>to</strong>rHCVS Process Valve PositionHCVS Pneumatic Supply PressureHCVS Electrical Power Supply AvailabilityDrywell pressureWetwell pressureWetwell levelReac<strong>to</strong>r PressureQualification Method*1S09001 / IEEE 344-2004 / Demonstration1509001 / IEEE 344-2004 I Demonstration1509001 / IEEE 344-2004 / Demonstration1509001 / IEEE 344-2004/ Demonstration1S09001 I IEEE 344-20041 Demonstration1509001 / IEEE 344-2004 I DemonstrationExisting instruments I pie-qualifiedExisting instruments / pre-qualifiedExisting instruments / pie-qualifiedExisting instruments I pie-qualified*The specific qualification method used <strong>for</strong> each required HCVS instrument will bereported in future 6 month status reports.Paae 24
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