ML061520098

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Draft RAI Cook Proposed Amendment, P-7 to P-8
ML061520098
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 06/01/2006
From: Tam P
Plant Licensing Branch III-2
To: Scarpello M, Steinmeyer K
Indiana Michigan Power Co
References
TAC MD0496, TAC MD0497
Download: ML061520098 (3)


Text

From: Peter Tam To: Scarpello, Michael; Steinmetz, Keith Start: 06/01/2006 Due: 06/01/2006

Subject:

Draft RAI re. Cook Proposed Amendment, P-7 to P-8 (TAC MD0496, 7)

Mike, Keith:

This is in response to your application for amendment dated 3/7/06. Our reviewer Sam Miranda developed the following draft questions that we would like to discuss with you in a conference call, to take place in the week of 6/5/06. Please propose options of day and time for that week.

1. Please provide copies of all Westinghouse Nuclear Safety Advisory Letters (NSALs) that allude to permissives P-7 and P-8. You may simply reference them if they are already docketed in NRC's ADAMS.
2. If applicable, describe how these NSALs have been used in preparing the proposal to shift the reactor trip on turbine trip interlock from P-7 to P-8.
3. Please provide a safety analysis or evaluation to show that tripping one reactor coolant pump, when the plant is at 31% power, will satisfy all ANS Condition II acceptance criteria without crediting the low flow reactor trip.
4. Please provide a safety analysis or evaluation to show that the seizure of one reactor coolant pump rotor or the shearing of one reactor coolant pump shaft, when the plant is at 31%

power, will satisfy all ANS Condition IV acceptance criteria without crediting the low flow reactor trip.

5. The Cook UFSARs state, ANS Condition II occurrences are faults that may occur with moderate frequency during the life of the plant. They are accommodated with, at most, a reactor shutdown with the plant being capable of returning to operation after a corrective action.

In addition, no ANS Condition II occurrence shall cause consequential loss of function of fuel cladding and reactor coolant system barriers. Show that inadvertent actuation of the emergency core cooling system would not cause a consequential loss of the reactor coolant system barrier (by filling the pressurizer; causing the pressurizer power-operated relief valves to open, to discharge water, and consequently, to fail to reseat properly). See RIS 2005-29 for more information.

This e-mail aims solely to prepare you and others for the proposed conference call. It does not formally request for additional information, nor does it convey a formal NRC staff position.

Peter S. Tam, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation e-mail: pst@nrc.gov Tel.: 301-415-1451 CC: Miranda, Samuel

Task Properties (447ECE7F.503 : 12 : 35330)

Subject:

Draft RAI re. Cook Proposed Amendment, P-7 to P-8 (TAC MD0946, 7)

Scheduled Date: 06/01/2006 From: Peter Tam Created By: PST@nrc.gov Creation Date 06/01/2006 7:24:47 AM Recipients Action Date & Time aep.com Transferred 06/01/2006 7:25:28 AM kasteinmetz (Keith Steinmetz) mkscarpello (Michael Scarpello) nrc.gov TWGWPO01.HQGWDO01 Delivered 06/01/2006 7:24:53 AM SXM1 CC (Samuel Miranda) Opened 06/01/2006 8:01:14 AM Accepted 06/01/2006 8:32:59 AM Post Office Delivered Route aep.com TWGWPO01.HQGWDO01 06/01/2006 7:24:53 AM nrc.gov Files Size Date & Time MESSAGE 3373 06/01/2006 7:24:47 AM Options Auto Delete: No Expiration Date: None Notify Recipients: Yes Priority: Standard ReplyRequested: No Return Notification: None Concealed

Subject:

No Security: Standard To Be Delivered: Immediate Status Tracking: All Information