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DOE 2000. - Waste Isolation Pilot Plant - U.S. Department of Energy

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WIPP RH PSAR <strong>DOE</strong>/WIPP-03-3174 CHAPTER 5<br />

Source Term Development - The maximum temperature <strong>of</strong> the waste canister will be #500 EF (260 EC)<br />

from a potential hydraulic oil fire (event 7-10) as evaluated by the scoping Thermal Analysis. 33 The<br />

waste canister has a carbon composite filter held in place by AREMCO 503 Ceramabond. 34 The<br />

maximum temperature <strong>of</strong> the Ceramabond is 3000 EF (1649 EC). There will be no appreciable increase<br />

in the internal pressure <strong>of</strong> the waste canister because the filter would stay in place during and after the fire<br />

event. There will be no release <strong>of</strong> radioactivity.<br />

Safety Structures, Systems, and Components - Based on the lack <strong>of</strong> release <strong>of</strong> radioactivity as supported<br />

by the scoping Thermal Analysis, 33 Safety Class or Safety significant SSCs are not required. The<br />

following data and assumptions are used in the thermal analysis:<br />

C<br />

Design and Location (>6 ft [1.8 m]) from the catch pans provided for the hydraulic unit <strong>of</strong><br />

facility cask rotating device) <strong>of</strong> the facility cask transfer car<br />

C<br />

C<br />

Maximum volume <strong>of</strong> hydraulic oil in the facility cask rotating device is # 40 gal (151.4 L).<br />

Capacity <strong>of</strong> the catch pans in the facility cask rotating device is > 45 gals (170.3 L).<br />

The defense-in-depth SSCs which are applicable to this scenario, per the criteria in Chapter 3, Section<br />

3.1.3 are assigned as follows:<br />

C<br />

Vented DOT Type A (or equivalent) RH Canister - Primary confinement<br />

C<br />

C<br />

C<br />

C<br />

WHB Structure - Secondary confinement<br />

WHB RH HVAC System - Secondary confinement<br />

WHB HEPA Filters - Secondary confinement<br />

Design <strong>of</strong> Hydraulic Oil Reservoir - Designed to minimize leaks<br />

Section 5.2.4.1, Evaluation <strong>of</strong> the Design Basis, discusses in greater detail: (1) the evaluation <strong>of</strong> safety<br />

SSCs and (2) the applicability <strong>of</strong> functional and performance requirements (system evaluation) and<br />

controls (TSRs). Detailed design descriptions for the above defense-in-depth SSCs may be found in<br />

Chapter 4 and the applicable SDDs.<br />

Due to the importance <strong>of</strong> the WIPP Emergency Management Program, 36 TSR ACs are derived in Chapter<br />

6 and required in the WIPP TSR document.<br />

5.2.3.3 RH3 Loss <strong>of</strong> Confinement in the WHB<br />

Scenario Description - The HAZOP 28 postulated a LOC <strong>of</strong> the waste material in the WHB. The HAZOP<br />

postulated three hazardous events (7-1, 7-2, and 7-6) that could result in a LOC <strong>of</strong> the waste material in<br />

the WHB. The LOC events could cause a significant release <strong>of</strong> radioactivity.<br />

Hazardous event 7-1 postulates a movement <strong>of</strong> shuttle car while grapple hoist is lifting the waste canister.<br />

The causes <strong>of</strong> this event are mechanical failure or control loop failure during lifting <strong>of</strong> the waste canister.<br />

The potential consequences <strong>of</strong> this event are: breach <strong>of</strong> a waste canister, damage to shuttle car, spread <strong>of</strong><br />

contamination, direct radiological exposure, radiological impact <strong>of</strong>fsite, and worker fatality. The<br />

potential breach <strong>of</strong> a waste canister could cause a significant release <strong>of</strong> radioactivity to the environment.<br />

5.2-25 January 22, 2003

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