ML083110833: Difference between revisions

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| number = ML083110833
| number = ML083110833
| issue date = 11/14/2008
| issue date = 11/14/2008
| title = Columbia Generating Station, Request for Additional Information Related to Request for Relief 3ISI-09
| title = Request for Additional Information Related to Request for Relief 3ISI-09
| author name = Lyon C F
| author name = Lyon C F
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV

Revision as of 06:20, 17 April 2019

Request for Additional Information Related to Request for Relief 3ISI-09
ML083110833
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 11/14/2008
From: Lyon C F
Plant Licensing Branch IV
To: Parrish J V
Entergy Northwest
Lyon, C F, NRR/DLPM, 415-2296
References
TAC MD9850
Download: ML083110833 (3)


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555.0001 November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968

SUBJECT:

COLUMBIA GENERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850)

Dear Mr. Parrish:

By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for NRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19,2008, to this request for additional information.

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 NRC's 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) 415-2296.

Sincerely, Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

As stated cc w/encl: Distribution via ListServ REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 ENERGY NORTHWEST COLUMBIA GENERATING STATION DOCKET NUMBER 50-397 By letter dated October 9, 2008 to the U.S. Nuclear Regulatory Commission

(!\IRC), Energy Northwest (the licensee) submitted Relief Request (RR) 31SI-09 for the Columbia Generating Station. The licensee proposes to use an alternative examination which provides less inspection coverage of the weld volume than the volume required by the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI requirements.

The alternative examination is applicable to the welds in the reactor pressure vessel nozzle-to-vessel welds and the nozzle inner radius sections.

The NRC staff requests that the licensee confirm the following related to the welds that are addressed in the RR 3ISI-09. A. Previous ultrasonic testing results of the subject welds did not reveal any service induced indications.

B. The type of weld metal used in the subject welds is carbon/low alloy steel.

November 14, 2008 Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023) Richland, WA 99352-0968 COLUMBIA GEI\IERATING STATION -REQUEST FOR ADDITIONAL INFORMATION RELATED TO REQUEST FOR RELIEF 31SI-09 (TAC NO. MD9850)

Dear Mr. Parrish:

By letter dated October 9, 2008, to the U.S. Nuclear Regulatory Commission (NRC), Energy Northwest submitted Inservice Inspection (lSI) Program Request 31SI-09 for Columbia Generating Station. The request was for I\IRC approval of the alternative to ASME Section XI, Subarticle IWB-2500, to allow reduced percentage requirements for nozzle to vessel weld and inner radius examinations for the 3rd ten-year interval lSI program. The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosure to this letter. Please provide a response by December 19, 2008, to this request for additional information.

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 NRC's 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) 415-2296.

Sincerely, IRAI Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-397

Enclosure:

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