ML13067A029

2/28/13 - Summary of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2

ML13067A029
Person / Time
Site:	Comanche Peak
Issue date:	03/15/2013
From:	Balwant Singal Plant Licensing Branch IV
To:	Luminant Generation Co
Singal B
References
TAC MC4676, TAC MC4677
Download: ML13067A029 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 15, 2013 LICENSEE:

Luminant Generation Company LLC FACILITY:

Comanche Peak Nuclear Power Plant, Units 1 and 2

SUMMARY

OF FEBRUARY 28, 2013, PRE-LICENSING CONFERENCE CALL PUBLIC MEETING WITH LUMINANT GENERATION COMPANY LLC TO DISCUSS THE GENERIC SAFETY ISSUE (GSI)-191 SUMP STRAINER TEST PROTOCOLS FOR BYPASS AND HEAD LOSS TESTING AND RELATED TOPICS (T AC NOS. MC4676 AND MC4677)

On February 28, 2013, a conference call public meeting was held between the U.S. Nuclear Regulatory Commission (NRC), and representatives of Luminant Generation Company LLC (Luminant, the licensee), at NRC Headquarters, Rockville, Maryland. The meeting notice and agenda, dated February 15, 2013, is located in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 13045A41 O. The purpose of the meeting was to discuss Generic Safety Issue (GSI)-191, "Assessment of Debris Accumulation on PWR

[Pressurized-Water Reactor] Sump Performance." The licensee discussed GSI-191 sump strainer test protocols for bypass and head loss testing and related topics for Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP).

A copy of the presentation slides used for the meeting discussions can be located at ADAMS Accession No. ML13059A180.

A list of meeting attendees is provided in the Enclosure to this meeting summary.

Meeting Summary The discussion was based on the presentation slides referenced above including the following areas of discussion:

Purpose and background Comparison of recent testing and types of fibrous debris included during tests Head loss test data Concern for Scotch 69 Glass Electrical Tape (glass 69 tape) not included in previous testing Options available for future testing with glass 69 tape Results of Discussions The licensee stated that it had discovered a potential additional source of debris installed within containment. The source is tape used to protect steel-jacketed electrical cables where they pass through clamp supports. The NRC staff stated that the tape appeared to be relatively robust and not likely to create fine fibrous

- 2 debris, but would be more likely to behave like cloth tape or lead blanket covers that had already been evaluated by the licensee.

The NRC staff stated that considering the already relatively large design basis fibrous debris load at CPNPP, it was unlikely that even if the glass tape became fiber that a change to strainer head loss would occur. The NRC staff stated that it may be more efficient for the licensee to treat the tape as miscellaneous debris and perform a transport test in a small flume to determine whether it may transport to the strainer, then evaluate its potential effects if required.

The licensee asked if the NRC staff would accept bypass testing performed in a tank or a flume. The NRC staff stated that it has accepted tank testing and agreed upon a flume testing protocol with Alden Labs and Performance Contracting, Inc. (PCI). The staff also stated that it has previously accepted flume testing for strainer head loss performed for CPNPP based on the observation that most of the test debris transported to the strainer. The NRC staff stated that performing bypass testing using a flume similar to the one used for head loss testing would be acceptable and would negate the need for the licensee to perform computational fluid dynamics (CFD) evaluations of a newly designed flume.

The licensee asked whether the NRC staff would accept an exponential curve fit of head loss data to extrapolate the results to the required mission time of the strainer. The NRC staff stated that the accepted guidance allows the use of exponential curve fits as long as the data used for the extrapolation represents the final part of the test and the head loss has remained relatively stable over that period. The NRC staff also stated that any data extrapolation should be adjusted to ensure that it bounds all of the data and is not based on average values and the staff will also accept linear extrapolations of the data.

No Public Meeting Feedback Forms were received for this meeting.

- 3 Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov.

Sincerely, c,~-1~\\~~

Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

LIST OF ATTENDEES FEBRUARY 28, 2013, MEETING WITH LUMINANT GENERATION COMPANY LLC REGARDING GSI-191 SUMP STRAINER TEST PROTOCOLS FOR BYPASS AND HEAD LOSS TESTING AND RELATED TOPICS COMANCHE PEAK NUCLEAR POWER PLANT, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446

_ _c_

NAME TITLE ORGANIZATION Reactor Systems Engineer U.S. Nuclear Regulatory Commission (NRC)

Stew Bailey Steve Smith Branch Chief NRC Balwant K. Singal NRC John Taylor*

Senior Project Manager Manager Technical Support Luminant Generation Company LLC (Luminant)

Jimmy Seawright*

Luminant Lee Windham*

Regulatory Affairs Design Engineering Analysis Manager Luminant Chuck Feist*

Luminant Andrea Lemons*

Design Engineering Analysis Engineer Design Engineering Analysis Engineer Luminant Lauren Neuburger*

Luminant David Klooster*

Design Engineering Analysis Engineer Luminant Ludwig Haber*

Design Engineering Analysis Engineer Alden Research Laboratory, Inc.

Jeffrey Brown*

Principal Engineer Arizona Public Service (APS) r-APS Fariba Gartland*

Senior Engineer Carl Stafford*

AREVA Inc.

I Philip Locke*

AREVA Inc.

I Kenny Davis*

AREVA Inc.

Tim Sande*

ENERCON Services, Inc.

Patrick Reyes*

Principal Mechanical Engineer Performance Contracting, Inc.

Mark Richter*

Product Manager

Senior Project Manager Nuclear Energy Institute Yuta Maruyama*

Mitsubishi Nuclear Energy Systems, Inc.

Greg QUitoria:no* ISenior Engineer Lead engineer Pacific Gas and Electric Company

• Participated via phone Enclosure

-3 Please direct any inquiries to me at (301) 415-3016, or balwant.singal@nrc.gov.

Docket Nos. 50-445 and 50-446

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC LPLIV r/f RidsAcrsAcnw _MaiICTR Resource RidsNrrDorlLpl4 Resource RidsNrrDssSsib Resource RidsNrrLAIBurkhardt Resource ADAMS Accession No. ML 130367 A029 Sincerely, IRA!

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