ML12319A179

From kanterella
Jump to navigation Jump to search

NRR E-mail Capture - Monticello Nuclear Generating Plant - Draft Requests for Additional Information Mellla+ License Amendment Request Review
ML12319A179
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 11/08/2012
From: Beltz T
Plant Licensing Branch III
To: Fields J
Northern States Power Co
References
TAC ME3145
Download: ML12319A179 (5)


Text

NRR-PMDAPEm Resource From: Beltz, Terry Sent: Thursday, November 08, 2012 3:22 PM To: 'Fields, John S.'

Cc: Huang, Tai; Jackson, Christopher

Subject:

Monticello Nuclear Generating Plant - Draft Requests for Additional Information re: MELLLA+

License Amendment Request Review (TAC No. ME3145)

Attachments: image001.gif; Monticello MELLLA+ RAIs_After GEH Audit.docx

Dear Mr. Fields:

By letter dated January 21, 2010 (Agencywide Documents Access and Management System Accession No. ML1002805580), Northern States Power Company - Minnesota (NSPM, the licensee), submitted a license amendment request (LAR) for the Monticello Nuclear Generating Plant (MNGP). The proposed LAR would allow plant operation in the expanded Maximum Extended Load Line Limit Analysis Plus (MELLLA+) domain.

MNGP is currently licensed to operate in the Maximum Extended Load Line Limit Analysis (MELLLA) domain with thermal-hydraulic stability Option III.

The U.S. Nuclear Regulatory Commission (NRC) staff in the Reactor Systems Branch of the Office of Nuclear Reactor Regulation has reviewed the LAR and performed an audit at GE-Hitachi Nuclear Energy America (GEH) on October 24-25, 2012, with respect to Tmin and quenching methodologies used for the MNGP MELLLA+ LAR.

The NRC staff has identified areas where additional information is needed to complete its review. The draft requests for additional information (RAIs) are attached.

You may accept these as formal Requests for Additional Information and respond to the questions by December 12, 2012. Alternatively, you may request to discuss the contents of these RAIs with the NRC staff in a conference call, including any change to the proposed response date.

Please let me know if you have any questions or concerns.

Sincerely, Terry A. Beltz, Senior Project Manager Plant Licensing Branch III-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov 1

Hearing Identifier: NRR_PMDA Email Number: 532 Mail Envelope Properties (87B1F1BDFE5A554CA9DC5EAA75EB6D0DBF4A8B0376)

Subject:

Monticello Nuclear Generating Plant - Draft Requests for Additional Information re: MELLLA+ License Amendment Request Review (TAC No. ME3145)

Sent Date: 11/8/2012 3:21:51 PM Received Date: 11/8/2012 3:21:00 PM From: Beltz, Terry Created By: Terry.Beltz@nrc.gov Recipients:

"Huang, Tai" <Tai.Huang@nrc.gov>

Tracking Status: None "Jackson, Christopher" <Christopher.Jackson@nrc.gov>

Tracking Status: None

"'Fields, John S.'" <John.Fields@xenuclear.com>

Tracking Status: None Post Office: HQCLSTR01.nrc.gov Files Size Date & Time MESSAGE 1708 11/8/2012 3:21:00 PM image001.gif 3939 Monticello MELLLA+ RAIs_After GEH Audit.docx 23414 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received:

Page 1 of 1 file://c:\EMailCapture\NRR_PMDA\532\attch1.gif 11/14/2012

REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE LICENSE AMENDMENT REQUEST FOR MAXIMUM LOAD LINE LIMIT ANALYSIS PLUS (MELLLA+)

NORTHERN STATES POWER COMPANY - MINNESOTA (NSPM)

MONTICELLO NUCLEAR GENERATING PLANT (MNGP)

DOCKET NO. 50-263 TAC NO. ME3145 On October 24-25, 2012, the U.S. Nuclear Regulatory Commission (NRC) staff performed an audit at GE-Hitachi Nuclear Americas (GEH) with respect to Tmin and quenching methodologies, and identified that additional information is needed for the staff to complete its review of the MNGP MELLLA+ license amendment request. The requests for additional information are provided below.

RAI 1

For a typical quench front calculated by TRACG04 for representative ATWSI [anticipated transients without scram with instability] conditions, provide the heat rate to the liquid and vapor state and the quench component of the heat rate. Compare with the measured heat rate values published by Thompson in NED 1974, On the Process of Rewetting a Hot Surface by a Falling Liquid.

RAI 2

Provide a detailed description of the TRACG implementation of the quench front model.

Provide a numerical comparison of the heat transfer coefficients used by TRACG downstream of the front and normal coefficients in nucleate boiling.

RAI 3

Generate TRACG quench model inputs for a number of Halden dryout experiments and provide a comparison of the results to validate the quench front velocity model at high power and pressures.

RAI 4

Provide the TRACG input decks for the Halden experiments including the digitized data from the experiments used to compare the results. In addition, please provide the TRACG output file and CEDAR file (in ascii if possible).

RAI 5

Reproduce the ATWSI calculations for MNGP with and without applying the void and the Zr credit in the Shumway Tmin correlation using the latest version of the TRACG code.

Provide a comparison of results.

Provide a plot that shows the hot rod clad temperature on the same plot as the calculated Tmin as function of time.

Provide a comparison for the variables shown in Figs 9-12 through 9-14 of NEDC-3435P/Rev1.