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Five Additional TMI-2 Related Requirements - Erata Sheets to 5/7/80 Letter (Generic Letter 80-52)
GL80052 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TO: ALL OPERATING REACTOR LICENSEES By letter dated May 7, 1980, we transmitted five additional TMI-2 related requirements to operating reactors. Attached is a set of errata sheets which correct errors in our designation of applicability of certain items. The item involved are II.K.3.25, II.K.3.29 and II.K.3.44. A corrected table of the Implementation Schedule and Summary is also attached. Sincerely, Darrell G. Eisenhut, Director Division of Licensing Enclosures: Errata Sheets cc: Service Lists . EFFECT OF LOSS OF AC POWER ON PUMP SEALS (II.K.3.25) POSITION The licensees should determine by analysis or experiment, on a plant- specific basis, the consequences of a loss of cooling water to the reactor recirculation pump seal coolers. The pump seals should be designed to withstand a complete loss of alternating current power for at least two hours. Adequacy of the seal design should be demonstrated. CLARIFICATION This item is applicable to BWRs. DISCUSSION NUREG-0626, Section A-2.14 SCHEDULE January 1, 1982 ACTION: (Class I) Licensee to provide results of evaluation to staff by scheduled date. . STUDY TO DEMONSTRATE PERFORMANCE OF ISOLATION CONDENSERS WITH NON-CONDENSIBLES (II.K.3.29) POSITION If natural circulation plays an important role in depressurizing the system (e.g., in the use of isolation condensers), then the various modes of two- phase flow natural circulation, including non-condensibles, which may play a significant role in plant response following a small-break LOCA should be demonstrated. CLARIFICATION This item is applicable to all BWRs. DISCUSSION NUREG-0626, Section F-4.5 SCHEDULE April 1, 1981 ACTION: (Class I) (1) Licensee to provide, results of evaluation to staff by scheduled date. . EVALUATION OF ANTICIPATED TRANSIENTS WITH SINGLE FAILURE TO VERIFY NO FUEL FAILURE (II.K.3.44) POSITION For anticipated transients combined with the worst single failure and assuming proper operator actions, licensees should demonstrate that the core remains covered or provide analysis to show that no significant fuel damage results from core uncovery. Transients which result in a stuck-open relief valve should be included in this category. CLARIFICATION This item is applicable to BWRs. DISCUSSION NUREG-0626, Section F-4.3 SCHEDULE 1/1/81 ACTION: (Class 1) (1) Licensee to provide results of evaluation to staff by scheduled date.
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