ML15040A269

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NRR E-mail Capture - Draft RAI for TAC No. MF5280
ML15040A269
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 02/09/2015
From: Lyon F
Plant Licensing Branch IV
To: Wideman S
Wolf Creek
References
TAC MF5280
Download: ML15040A269 (2)


Text

NRR-PMDAPEm Resource From: Lyon, Fred Sent: Monday, February 09, 2015 10:23 AM To: Wideman Steve G (stwidem@WCNOC.com)

Cc: Muilenburg William T (wimuile@WCNOC.com)

Subject:

Draft RAI for TAC No. MF5280 Heres an RAI that Im preparing to send you; 45 day response from date of letter. Please share it with your folks and let me know if you need a clarifying phoncon. Thanks, Fred P.S. these are due to the deviations from the TSTF you requested.

By letter dated November 20, 2014 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14330A247), Wolf Creek Nuclear Operating Corporation (the licensee) submitted to the U.S. Nuclear Regulatory Commission (NRC) a license amendment request to revise the Wolf Creek Generating Station (WCGS) Technical Specifications (TS) requirements to address NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, as described in Technical Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation.

The NRC staff requests the following additional information in order to complete its review of the request.

Reactor Systems Branch (SRXB) Questions:

1. What were the historic void volumes found that are applicable to performance of TS surveillance requirements (SRs) 3.5.2.3 and 3.6.6.9, and how did these compare to the acceptance criteria? How do those void volumes compare to follow-up calculations that were performed if the original criteria were not met?
2. Is the WCGS design basis no gas? If not, please provide the documentation that established the design basis.
3. Please provide a description of the process used to restore the plant to the design basis condition at the earliest practical time following discovery of a gas volume that exceeds the design basis.
4. Please describe the methodology used to determine gas volumes that do not jeopardize operability that are applicable to SRs 3.5.2.3 and 3.6.6.9.
5. How is potential leakage from the reactor coolant system addressed?

1

Hearing Identifier: NRR_PMDA Email Number: 1865 Mail Envelope Properties (Fred.Lyon@nrc.gov20150209102300)

Subject:

Draft RAI for TAC No. MF5280 Sent Date: 2/9/2015 10:23:25 AM Received Date: 2/9/2015 10:23:00 AM From: Lyon, Fred Created By: Fred.Lyon@nrc.gov Recipients:

"Muilenburg William T (wimuile@WCNOC.com)" <wimuile@WCNOC.com>

Tracking Status: None "Wideman Steve G (stwidem@WCNOC.com)" <stwidem@WCNOC.com>

Tracking Status: None Post Office:

Files Size Date & Time MESSAGE 1992 2/9/2015 10:23:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: