ML073310008

Request for Additional Information, Amendment to Revise TS Surveillance Requirement 13.3.33.2, Frequency of Cycles of High-Pressure and Low-Pressure Turbine Stop Control Valves

ML073310008
Person / Time
Site:	Comanche Peak
Issue date:	12/03/2007
From:	Balwant Singal NRC/NRR/ADRO/DORL/LPLIV
To:	Blevins M Luminant Generation Co
Singal, Balwant, 415-3016, NRR/DORL/LPL4
References
TAC MD5639, TAC MD5640
Download: ML073310008 (5)

Text

December 3, 2007 Mr. M. R. Blevins Executive Vice President

& Chief Nuclear Officer Luminant Generation Company LLC ATTN: Regulatory Affairs P. O. Box 1002 6322 North FM 56 Glen Rose, TX 76043

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION, LICENSE AMENDMENT REQUEST 07-001 TO REVISE SURVEILLANCE FREQUENCY FOR THE TURBINE STOP AND CONTROL VALVES SPECIFIED BY THE TECHNICAL REQUIREMENTS MANUAL (TAC NOS. MD5639 AND MD5640)

Dear Mr. Blevins:

By letter to the U.S. Nuclear Regulatory Commission (NRC) dated May 22, 2007, TXU Generation Company LP (subsequently renamed Luminant Generation Company LLC) submitted Technical Requirements Manual changes to revise the surveillance frequency for the turbine stop and control valves for Comanche Peak Steam Electric Station, Units 1 and 2, for NRC review in accordance with Section 50.90 of Title 10 of the Code of Federal Regulations.

The NRC staff has determined that additional information is required to complete the review of the application. The specific information requested is addressed in the enclosure to this letter.

You are requested to respond to the request for additional information (RAI) within 30 days from the issuance of this letter.

The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for NRC staff to complete its review and contribute toward the NRCs goal of efficient and effective use of staff resources.

M. R. Blevins If you have any questions, please contact me at (301) 415-3016.

Sincerely,

/RA/

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:

Request for Additional Information cc w/encl: See next page

M. R. Blevins If you have any questions, please contact me at (301) 415-3016.

Sincerely,

/RA/

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:

Request for Additional Information cc w/encl: See next page DISTRIBUTION:

PUBLIC RidsNrrDorlLpl4 RidsRgn4MailCenter LPL4 R/F RidsNrrLAJBurkhardt SSheng, NRR/DCI/CVIB RidsAcrsAcnwMailCenter RidsNrrPMBSingal BMarcus, NRR/DE/EICB RidsNrrDciCvib RidsNrrDorlDpr RidsNrrDeEicb RidsOgcRp ADAMS Accession Number: ML073310008 *email dated OFFICE LPL4/PM LPL4/LA CVIB/BC LPL4/BC NAME BSingal JBurkhardt MMitchell* THiltz DATE 12/3/07 12/3/07 11/26/07 12/3/07 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION RELATED TO REVIEW ASSOCIATED WITH REVISION OF TECHNICAL REQUIREMENTS SURVEILLANCE FREQUENCY FOR THE TURBINE STOP AND CONTROL VALVES LUMINANT GENERATION COMPANY LLC COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446

1. It was stated on Page 6 of the submittal that, the upgraded Turbine Overspeed Protection System is redundant and diverse and most of the devices are tested on line at least once a day. Confirm whether this upgrade was considered in the P10 (probability of a runaway due to a failure of the Overspeed Protection System) calculation. Provide sufficient details for staff review if this upgrade is considered quantitatively.

2. It was stated on Page 14 of the submittal that, [except for the 26-week testing interval,] all other variables remain the same as in the previous analysis on which the current testing interval of 12 weeks is based. Confirm that both the previous and the proposed analyses are based on the plant-specific turbine information reflecting all turbine modifications (retrofits) made in the Comanche Peak Steam Electric Station, Units 1 and 2. List all deviations of the current methodology, if they exist, from the methodology approved by the staff on July 22, 2003, regarding Siemens Westinghouse Power Corporations missile analysis methodology for General Electric nuclear steam turbine rotors and justify their adequacy.

Comanche Peak Steam Electric Station cc:

Senior Resident Inspector Mr. Richard A. Ratliff, Chief U.S. Nuclear Regulatory Commission Bureau of Radiation Control P.O. Box 2159 Texas Department of Health Glen Rose, TX 76403-2159 1100 West 49th Street Austin, TX 78756-3189 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Mr. Brian Almon 611 Ryan Plaza Drive, Suite 400 Public Utility Commission Arlington, TX 76011 William B. Travis Building P.O. Box 13326 Mr. Fred W. Madden, Director 1701 North Congress Avenue Regulatory Affairs Austin, TX 78701-3326 Luminant Generation Company LLC P.O. Box 1002 Ms. Susan M. Jablonski Glen Rose, TX 76043 Office of Permitting, Remediation and Registration Timothy P. Matthews, Esq. Texas Commission on Environmental Morgan Lewis Quality 1111 Pennsylvania Avenue, NW MC-122 Washington, DC 20004 P.O. Box 13087 Austin, TX 78711-3087 County Judge P.O. Box 851 Mr. Anthony P. Jones Glen Rose, TX 76043 Chief Boiler Inspector Texas Department of Licensing Environmental and Natural and Regulation Resources Policy Director Boiler Division Office of the Governor E.O. Thompson State Office Building P.O. Box 12428 P.O. Box 12157 Austin, TX 78711-3189 Austin, TX 78711 October 2007