ML080660224

Request for Additional Information Relief Request B-2

ML080660224
Person / Time
Site:	Comanche Peak
Issue date:	03/12/2008
From:	Balwant Singal NRC/NRR/ADRO/DORL/LPLIV
To:	Blevins M Luminant Generation Co
Singal, Balwant, 415-3016, NRR/DORL/LPL4
References
TAC MD7527
Download: ML080660224 (3)

Text

March 12, 2008 Mr. M. R. Blevins Executive Vice President

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

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST NO. B-2 (TAC NO. MD7527)

Dear Mr. Blevins:

By application dated December 19, 2007, Luminant Generation Company LLC (the licensee) requested that the U.S. Nuclear Regulatory Commission (NRC) staff authorize an alternative to certain inservice inspection (ISI) code requirements for the Comanche Peak Steam Electric Station, Unit 2. Specifically, Relief Request No. B-2 proposed an alternative to the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for certain risk-informed ISI piping welds.

The NRC staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. Please provide a response to the enclosed questions by June 2, 2008.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3016.

Sincerely,

/RA by Carl F. Lyon for/

Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-446

Enclosure:

As stated cc w/encl: See next page

March 12, 2008 Mr. M. R. Blevins Executive Vice President

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

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION RE: RELIEF REQUEST NO. B-2 (TAC NO. MD7527)

Dear Mr. Blevins:

By application dated December 19, 2007, Luminant Generation Company LLC (the licensee) requested that the U.S. Nuclear Regulatory Commission (NRC) staff authorize an alternative to certain inservice inspection (ISI) code requirements for the Comanche Peak Steam Electric Station, Unit 2. Specifically, Relief Request No. B-2 proposed an alternative to the examination requirements of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code for certain risk-informed ISI piping welds.

The NRC staff has reviewed the information provided in your submittal and determined that additional information is required in order to complete its review. Please provide a response to the enclosed questions by June 2, 2008.

The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3016.

Sincerely,

/RA by Carl F. Lyon for/

Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-446

Enclosure:

As stated cc w/encl: See next page DISTRIBUTION:

PUBLIC RidsNrrPMBSingal RidsNrrDciCpnb LPLIV Reading RidsNrrLAJBurkhardt CNove, NRR/DCI/CPNB RidsAcrsAcnw&mMailCenter RidsOgcRp RidsNrrDorlLpl4 RidsRgn4MailCenter ADAMS Accession No: ML080660224 *email dated OFFICE NRR/LPL4/PM NRR/LPL4/LA CPNB/BC NRR/LPL4/BC NAME BSingal, CFL for JBurkhardt TChan* THiltz DATE 3/12/08 3/12/08 3/4/08 3/12/08 OFFICIAL AGENCY RECORD

Comanche Peak Steam Electric Station (10/2007) 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 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

OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST B-2 LUMINANT GENERATION COMPANY LLC COMANCHE PEAK STEAM ELECTRIC STATION, UNIT 2 DOCKET NO. 50-446 The Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's Relief Request No. B-2 for the Comanche Peak Steam Electric Station, Unit 2, and has determined that additional information is necessary to complete the review of its request for relief. Based on the staff=s review, please provide a response which addresses the following request for additional information (RAI) questions.

1. For weld no. TCX-1-4105, please:

a. Discuss the inspection history (including methods and results);

b. Indicate what system this weld is located in; and

c. Discuss the potential degradation mechanism that may occur in this weld.

Also include in your discussion the (1) most likely crack-initiation location resulting from this potential degradation mechanism and (2) industry-wide service experience for welds such as this one.

2. Why was this weld rather than a different weld selected for this examination?

3. In light of the fact that manual-phased array ultrasonics are capable of being qualified on tapered surfaces of austenitic materials, please describe your efforts in improving the area of coverage at the far side of the weld.

4. During what period of the second inservice inspection interval were the inspections performed?