Operation of BWR primary system pressure relief valves can result in hydrodynamic loads on the suppression pool retaining structures or those structures located within the pool. These loads result from initial vent clearing of relief valve piping and steam quenching due to high local pool temperatures. The item addresses GE MARK I,
II, and III containments and was originally identified in NUREG-0371[1] but was later determined to be a USI.
This USI was RESOLVED[2] with the issuance of SRP[3] Section 6.2.1.1.C. NUREG-0763,[4] NUREG-0783,[5] and NUREG-0802[6] were also issued for Mark I, II, and III containments, respectively.
[1] NUREG-0371, "Task Action Plans for Generic Activities (Category A)," U.S. Nuclear Regulatory Commission, November 1978.
[2] NUREG-0606, "Unresolved Safety Issues Summary," U.S. Nuclear Regulatory Commission, Vol. 7 No. 3, August 1985.
[3] NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, (1st Ed.) November 1975, (2nd Ed.) March 1980, (3rd Ed.) July 1981.
[4] NUREG-0763, "Guidelines for Confirmatory Inplant Tests of Safety Relief Valve Discharges for BWR Plants," U.S. Nuclear Regulatory Commission, May 1981.
[5] NUREG-0783, "Suppression Pool Temperature Limits for BWR Containments," U.S. Nuclear Regulatory Commission, November 1981.
[6] NUREG-0802, "Safety/Relief Valve Quencher Loads: Evaluation for BWR Mark II and III Containments," U.S. Nuclear Regulatory Commission, October 1982.
Page Last Reviewed/Updated 08/28/2025
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