ML091880183: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
 
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB..OCONEE NUCLEAR STATION, UNIT 3 -REQUEST FOR ADDITIONAL INFORMATION (RAJ) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS. ME0752 AND ME0753)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB..IECT:        OCONEE NUCLEAR STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION (RAJ) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS.
ME0752 AND ME0753)


==Dear Mr. Baxter:==
==Dear Mr. Baxter:==
By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.
By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.
The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6,2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter. If you have any questions, please call me at 301-415-1345.
The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6,2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter.
Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287  
If you have any questions, please call me at 301-415-1345.
SinCereIY'~
                                              ~ng,          Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287


==Enclosure:==
==Enclosure:==


RAI cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL RELIEF REQUEST 08-0N-002 LIMITED WELD EXAMINATION DUKE ENERGY CAROLINAS, OCONEE NUCLEAR STATION, UNIT DOCKET NO. By letter dated December 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090050027), Duke Energy Carolinas, LLC (the licensee), submitted Relief Request 08-0N-002 for the U.S. Nuclear Regulatory Commission (NRC) staff's review and approval.
RAI cc w/encl: Distribution via Listserv
Pursuant to paragraph 50.55a(g)(5)(iii) of Title 10 of the Code of Federal Regulations, the licensee requested relief from the vOlumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 1 O-year inservice inspection interval scheduled to end on December 16,2014. The request pertains to volumetric examination of the reducer-to-valve 3LP-18 weld in the low pressure injection system and the tee-to-pipe weld in the high pressure injection system. The request contains the results of the ultrasonic testing performed during the 2006 outage on the subject welds where 100-percent coverage of the required examination volume could not be achieved because of interferences from existing piping and valve geometry.
 
The NRC staff has determined that the following information is needed in order to complete its review of the relief request. For weld 3HP-365-9C: Explain the angles used for shear wave examination.
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 08-0N-002 LIMITED WELD EXAMINATION COVERAGE DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287 By letter dated December 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090050027), Duke Energy Carolinas, LLC (the licensee), submitted Relief Request 08-0N-002 for the U.S. Nuclear Regulatory Commission (NRC) staff's review and approval. Pursuant to paragraph 50.55a(g)(5)(iii) of Title 10 of the Code of Federal Regulations, the licensee requested relief from the vOlumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 1O-year inservice inspection interval scheduled to end on December 16,2014. The request pertains to volumetric examination of the reducer-to-valve 3LP-18 weld in the low pressure injection system and the tee-to-pipe weld in the high pressure injection system. The request contains the results of the ultrasonic testing performed during the 2006 outage on the subject welds where 100-percent coverage of the required examination volume could not be achieved because of interferences from existing piping and valve geometry.
In particular, address the use of a 38-degree shear wave as shown on page 5 of Attachment A of the relief request. Clarify the discrepancies in regard to the shear wave examination between the text in paragraph IV on page 5, the contents of the table on page 5 of Attachment A, and the contents of the table on page 11 of Attachment A. Enclosure July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 OCONEE NUCLEAR STATION, UNIT 3 -REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS. ME0752 AND ME0753)  
The NRC staff has determined that the following information is needed in order to complete its review of the relief request.
For weld 3HP-365-9C:
: 1. Explain the angles used for shear wave examination. In particular, address the use of a 38-degree shear wave as shown on page 5 of Attachment A of the relief request.
: 2. Clarify the discrepancies in regard to the shear wave examination between the text in paragraph IV on page 5, the contents of the table on page 5 of Attachment A, and the contents of the table on page 11 of Attachment A.
Enclosure
 
July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672
 
==SUBJECT:==
OCONEE NUCLEAR STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS.
ME0752 AND ME0753)


==Dear Mr. Baxter:==
==Dear Mr. Baxter:==
By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.
By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code), Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.
The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6, 2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter. If you have any questions, please call me at 301-415-1345.
The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6, 2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter.
Sincerely, IRA! John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287  
If you have any questions, please call me at 301-415-1345.
Sincerely, IRA!
John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287


==Enclosure:==
==Enclosure:==


RAI cc w/encl: Distribution via Listserv Public LPLlI-1 RidsAcrsAcnw
RAI cc w/encl: Distribution via Listserv DISTRIBUTION:
_MailCtr Resource RidsNrrLAMOBrien Resource (hard RidsNrrDorlDpr Resource RidsNrrPMOconee Resource (hard RidsNrrDorlLp2-1 Resource RidsRgn2MailCenter RidsOgcRp Resource RidsNrrDciCpnb (TChan, JAdams, EDO ADAMS A ccesslon N o. ML091880183  
Public                                           LPLlI-1 R1F RidsAcrsAcnw_ MailCtr Resource                   RidsNrrLAMOBrien Resource (hard copy)
" transml'tt e db lY memo d t d NRR-088ae OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCPNB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME IJStanQ: prb MO'Brien rrChan" MWonQ IJStanQ DATE 17/9/09 7/15/09 06/25/09 7/15/09 17/15/09 OFFICIAL RECORD COpy}}
RidsNrrDorlDpr Resource                         RidsNrrPMOconee Resource (hard copy)
RidsNrrDorlLp2-1 Resource                       RidsRgn2MailCenter Resource RidsOgcRp Resource                               RidsNrrDciCpnb (TChan, ARezac)
JAdams, EDO R-II ADAMS A ccesslon No. ML091880183       "transml' ttedblY memo d ated              -
NRR 088 OFFICE     NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCPNB/BC         NRRlLPL2-1/BC NRRlLPL2-1/PM NAME       IJStanQ: prb   MO'Brien     rrChan"           MWonQ         IJStanQ DATE       17/9/09         7/15/09     06/25/09           7/15/09       17/15/09 OFFICIAL RECORD COpy}}

Latest revision as of 05:22, 14 November 2019

Request for Additional Information (RAI) Regarding Relief Request 08-ON-002 Concerning Limited Weld Examination Coverage
ML091880183
Person / Time
Site: Oconee Duke Energy icon.png
Issue date: 07/15/2009
From: Stang J
Plant Licensing Branch II
To: Baxter D
Duke Energy Carolinas
Stang J, NRR/DORL, 415-1345
References
TAC ME0752, TAC ME0753
Download: ML091880183 (2)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672 SUB..IECT: OCONEE NUCLEAR STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION (RAJ) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS.

ME0752 AND ME0753)

Dear Mr. Baxter:

By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.

The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6,2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter.

If you have any questions, please call me at 301-415-1345.

SinCereIY'~

~ng, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287

Enclosure:

RAI cc w/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 08-0N-002 LIMITED WELD EXAMINATION COVERAGE DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNIT 3 DOCKET NO. 50-287 By letter dated December 29, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090050027), Duke Energy Carolinas, LLC (the licensee), submitted Relief Request 08-0N-002 for the U.S. Nuclear Regulatory Commission (NRC) staff's review and approval. Pursuant to paragraph 50.55a(g)(5)(iii) of Title 10 of the Code of Federal Regulations, the licensee requested relief from the vOlumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 1O-year inservice inspection interval scheduled to end on December 16,2014. The request pertains to volumetric examination of the reducer-to-valve 3LP-18 weld in the low pressure injection system and the tee-to-pipe weld in the high pressure injection system. The request contains the results of the ultrasonic testing performed during the 2006 outage on the subject welds where 100-percent coverage of the required examination volume could not be achieved because of interferences from existing piping and valve geometry.

The NRC staff has determined that the following information is needed in order to complete its review of the relief request.

For weld 3HP-365-9C:

1. Explain the angles used for shear wave examination. In particular, address the use of a 38-degree shear wave as shown on page 5 of Attachment A of the relief request.
2. Clarify the discrepancies in regard to the shear wave examination between the text in paragraph IV on page 5, the contents of the table on page 5 of Attachment A, and the contents of the table on page 11 of Attachment A.

Enclosure

July 15, 2009 Mr. Dave Baxter Vice President, Oconee Site Duke Energy Carolinas, LLC 7800 Rochester Highway Seneca, SC 29672

SUBJECT:

OCONEE NUCLEAR STATION, UNIT 3 - REQUEST FOR ADDITIONAL INFORMATION (RAI) REGARDING RELIEF REQUEST 08-0N-002 CONCERNING LIMITED WELD EXAMINATION COVERAGE (TAC NOS.

ME0752 AND ME0753)

Dear Mr. Baxter:

By letter dated December 29,2008, Duke Energy Carolinas, LLC (the licensee), requested relief from the volumetric coverage requirement for weld examinations specified in the American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code (Code),Section XI, as modified by ASME Code Case N-460. The relief is requested for Oconee Nuclear Station, Unit 3 for the remainder of the fourth 10-year inservice inspection interval.

The U.S. Nuclear Regulatory Commission staff has reviewed and evaluated the information provided by the licensee and has determined that additional information is required to complete its review. In a phone conversation with members of your staff on July 6, 2009, to provide clarification of the requested information, your staff committed to provide the requested information 30 days from the date of this letter.

If you have any questions, please call me at 301-415-1345.

Sincerely, IRA!

John Stang, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-287

Enclosure:

RAI cc w/encl: Distribution via Listserv DISTRIBUTION:

Public LPLlI-1 R1F RidsAcrsAcnw_ MailCtr Resource RidsNrrLAMOBrien Resource (hard copy)

RidsNrrDorlDpr Resource RidsNrrPMOconee Resource (hard copy)

RidsNrrDorlLp2-1 Resource RidsRgn2MailCenter Resource RidsOgcRp Resource RidsNrrDciCpnb (TChan, ARezac)

JAdams, EDO R-II ADAMS A ccesslon No. ML091880183 "transml' ttedblY memo d ated -

NRR 088 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA NRRlCPNB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME IJStanQ: prb MO'Brien rrChan" MWonQ IJStanQ DATE 17/9/09 7/15/09 06/25/09 7/15/09 17/15/09 OFFICIAL RECORD COpy