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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 />

Airborne Release Fraction and Respirable Fraction - As discussed in Section 5.2.1.1, the ARF for<br />

contaminated combustible materials which are subjected to impact and breach <strong>of</strong> the waste canister is<br />

0.001. This value represents a bounding ARF for packaged material in a canister which fails due to<br />

impact (<strong>DOE</strong>-HDBK-3010-94, subsection 5.2.3.2). 4 The bounding RF is 0.1 (<strong>DOE</strong>-HDBK-3010-94,<br />

subsection 5.2.3.2). 4<br />

The ARF for contaminated noncombustible materials which are subjected to impact and breach <strong>of</strong> the<br />

waste canister for solids that do not undergo brittle fracture is 0.001. This value represents a bounding<br />

ARF for packaged material in a canister which fails due to impact (<strong>DOE</strong>-HDBK-3010-94, subsection<br />

5.3.3.2.2). 4 The bounding RF is 1.0 (<strong>DOE</strong>-HDBK-3010-94, subsection 5.2.3.2). 4<br />

Leakpath Factor - Due to the accident scenario conditions and potential damage to both the RH canister<br />

and the facility cask, a conservative LPF from the facility cask to the underground <strong>of</strong> 1.0 is assigned.<br />

The amount <strong>of</strong> material removed from the air due to the HEPA filters is predicted based on DF. DF have<br />

been predicted for accident conditions in the handbook ERDA 76-21. 14 Based ERDA 76-21, the total<br />

DF used in this analysis for both stages <strong>of</strong> filtration is 1.0E+06. The LPF is 1.0E-06 for the mitigated<br />

case and 1.0 for the unmitigated case.<br />

Estimated noninvolved worker and MEI Consequences and Comparison to Risk Evaluation Guidelines -<br />

Based on the values for the source term variables as presented above, the worst-case, unmitigated MEI<br />

and noninvolved worker consequences (see Appendix E, Tables E-4, E-5, and E-6) <strong>of</strong> the LOC in the<br />

Underground (<strong>Waste</strong> Hoist Drop) (RH4-A) are well within the radiological and non-radiological risk<br />

evaluation guidelines for the extremely unlikely range.<br />

Assessment <strong>of</strong> Immediate Worker Consequences- No current risk evaluation guidelines exist for the<br />

assessment <strong>of</strong> accident consequences to immediate workers. Therefore, in the absence <strong>of</strong> guidelines, and<br />

for conservatism, the noninvolved worker radiological guidelines for the extremely unlikely range are<br />

used as a reference point for the assessment <strong>of</strong> consequences to immediate workers and the evaluation <strong>of</strong><br />

the adequacy <strong>of</strong> the WIPP defense-in-depth features. The worst-case consequences to the immediate<br />

worker from RH4A (Tables E-13 and E-16) exceed the risk evaluation guidelines. However, no specific<br />

additional worker protection engineering or administrative controls beyond those already qualitatively<br />

identified as providing defense-in-depth for the immediate worker, are needed based on the discussion<br />

provided in Section 5.2.4.2.<br />

Safety Structures, Systems, and Components - The brake system on the waste hoist has been designated<br />

as Safety Significant. The following input data and assumptions are used in the accident analysis:<br />

C<br />

Design <strong>of</strong> the facility cask transfer car, facility cask, and waste hoist and shaft<br />

C<br />

C<br />

C<br />

C<br />

The facility cask is in a horizontal position and positioned with the greatest moment <strong>of</strong> inertia.<br />

It is held in place by trunions and supports to keep it from moving.<br />

Maximum speed <strong>of</strong> the facility cask transfer car is 30 ft (9.1 m) per minute<br />

Maintain configuration <strong>of</strong> the waste hoist on which fault tree was based (for details see<br />

WIPP/WID-96 -2178 40 )<br />

Maintenance program including post-maintenance functional testing- stroke testing is assumed<br />

for all valves following a maintenance operation<br />

5.2-33 January 22, 2003

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