ML102240637

Draft RAIs Extended Power Uprate (TAC Nos. ME1044 & ME1045

ML102240637
Person / Time
Site:	Point Beach
Issue date:	08/11/2010
From:	Beltz T Plant Licensing Branch III
To:	Point Beach
Beltz, T A, NRR/DORL/LPLIII-1, 415-3049
Shared Package
ML102240636	List: ML102240637
References
TAC ME1044, TAC ME1045
Download: ML102240637 (2)

Text

REQUESTS FOR ADDITIONAL INFORMATION Point Beach Nuclear Plant (PBNP), Units 1 and 2 License Amendment Request (LAR-261) dated April 7, 2009 Extended Power Uprate (TAC Nos. ME1044 and ME1045)

The following requests for additional information are associated with the NRC staff review of LAR-261 associated with the extended power uprate for the PBNP, Units 1 and 2.

IHPB-1 Please verify that motor control centers (MCCs) 1B32, 2B32, 1B42 and 2B42 are being replaced, or have been replaced, with models that auto load following start of the emergency diesel generator such that resetting these MCCs is no longer considered a vital action as defined in NUREG 0737, item II.B.2.

IHPB-2 Please verify that resetting MCCs 1B42 and 2B42 was the only vital action needed at panel C59 so that replacing these MCCs, as described in the response to IHPB-1 above, eliminates the need to access panel C59 during the course of the accident (i.e., C59 would no longer be considered a vital area as defined in NUREG 0737, item II.B.2).

IHPB-3 Please provide the technical basis for originally concluding that accessing panel C59 to manually isolate the spray additive (NaOH) tank discharge valves was needed during the course of a Design Basis Accident, including any calculations and/or technical rationale for subsequently concluding that this action is not needed to mitigate the consequences of the accident.

IHPB-4 Please provide documentation of the NRC staffs acceptance for allowing TSC evacuation as a compensatory measure in lieu of meeting the habitability criteria in NUREG 0737, item II.B.2.

IHPB-5 In response to the discussion related to the Waste Gas Decay Tank (WGDT) release/rupture event, please demonstrate how the licensee is maintaining dose acceptance criteria consistent with Branch Technical Position (BTP) 11-5 in NUREG 0800 by either,

1. Demonstrating that the consequences of this postulated release are within the dose limits of the current 10 CFR Part 20, or

2. Demonstrating that the consequences of this postulated release are within a small fraction (i.e., 10 percent) of the 10 CFR Part 100 limits for whole body dose if the gaseous radwaste system is designed to withstand the effects of a hydrogen explosion and earthquakes for gaseous wastes produced during normal operation and anticipated operational occurrences.