ML092170275: 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)
 
(One intermediate revision by the same user not shown)
Line 3: Line 3:
| issue date = 08/21/2009
| issue date = 08/21/2009
| title = Request for Additional Information for Second 10-Year Interval Inservice Inspection Program Plan Relief Request 2-ISI-19 Revision 1
| title = Request for Additional Information for Second 10-Year Interval Inservice Inspection Program Plan Relief Request 2-ISI-19 Revision 1
| author name = Brown E A
| author name = Brown E
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Swafford P D
| addressee name = Swafford P
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000260
| docket = 05000260
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 August 21, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 BROWNS FERRY NUCLEAR PLANT, UI\JIT 2 -REQUEST FOR ADDITIONAL INFORMATION FOR SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2-ISI-19 REVISION 1 (TAC NO. ME0764)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 21, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
 
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UI\JIT 2 - REQUEST FOR ADDITIONAL INFORMATION FOR SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2-ISI-19 REVISION 1 (TAC NO. ME0764)


==Dear Mr. Swafford:==
==Dear Mr. Swafford:==


By letter dated March 2, 2009, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Browns Ferry Nuclear Plant, Unit 2. In accordance with Title 10 of the Code of Federal Regulations, Section 50.55a(g)(5)(iii), the licensee has submitted Relief Request (RR) 2-ISI-19, Rev. 1, for certain limited Class 1 component weld examinations.
By letter dated March 2, 2009, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code, Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Browns Ferry Nuclear Plant, Unit 2.
The ASME Code requires that 100 percent of the examination volumes or surface areas described in ASME Code, Section XI, be performed during each interval.
In accordance with Title 10 of the Code of Federal Regulations, Section 50.55a(g)(5)(iii), the licensee has submitted Relief Request (RR) 2-ISI-19, Rev. 1, for certain limited Class 1 component weld examinations. The ASME Code requires that 100 percent of the examination volumes or surface areas described in ASME Code, Section XI, be performed during each interval. The licensee determined that the required examination coverage of 100 percent was impractical to obtain.
The licensee determined that the required examination coverage of 100 percent was impractical to obtain. The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of RR 2-IS 1-19 Revision 1. A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. Dan Green of your staff on August 21,2009, and it was agreed that TVA would respond within 30 days from the date of this letter.
The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of RR 2-IS 1-19 Revision 1. A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. Dan Green of your staff on August 21,2009, and it was agreed that TVA would respond within 30 days from the date of this letter.
P. Swafford -2 If you have any questions, please contact me at (301) 415-2315.
 
Sincerely, If' Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260 Request for Additional cc w/enclosure:
P. Swafford                               -2 If you have any questions, please contact me at (301) 415-2315.
Distribution via REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 2-ISI-19, REVISION 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 Page E1-7 of the submittal is the beginning of a table that summarizes several (and different) ultrasonic angles and modes of propagation that were used to interrogate various reactor pressure vessel nozzle-to-vessel welds. Provide a description of any modeling performed in support of the varied angles and modes of ultrasonic propagation that were applied. The highest angle of ultrasonic examination employed is listed as 60-degrees, for both shear and refracted longitudinal waves. Based on the drawings provided for the subject welds, it appears that greater American Society of Mechanical Engineers Code volume examination coverage could be obtained if a higher probe-angle was used. Clarify why higher probe angles were not exercised to maximize coverage on these welds. Enclosure P. Swafford -If you have any questions, please contact me at (301) 415-2315.
Sincerely,
Sincerely, IRA SLingam fori Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
                                            ~ If' ~                    +tf\.
Request for Additional cc w/enclosure:
Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260
Distribution via DISTRIBUTION PUBLIC LPL2-2 RlF RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry RidsAcrsAcnw
 
_MailCenter RidsOgcRp RidsRgn2MailCenter RidsNrrDorl RidsNrrLABClayton (Hard Copy) TMcLelian RidsNrrDciCvib ADAMS Accession No*.. ML092170275 OFFICE LPL2-2/PM LPL-WB/LA CVIB\BC LPL2-2/BC NAME SLingam for EBrown BClayton MMitchell by memo TBoyce DATE 08/21/09 08/21/09 6/30/2009 08/21/09 OFFICIAL RECORD COpy}}
==Enclosure:==
 
Request for Additional Information cc w/enclosure: Distribution via Listserv
 
REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 2-ISI-19, REVISION 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260
: 1. Page E1-7 of the submittal is the beginning of a table that summarizes several (and different) ultrasonic angles and modes of propagation that were used to interrogate various reactor pressure vessel nozzle-to-vessel welds. Provide a description of any modeling performed in support of the varied angles and modes of ultrasonic propagation that were applied.
: 2. The highest angle of ultrasonic examination employed is listed as 60-degrees, for both shear and refracted longitudinal waves. Based on the drawings provided for the subject welds, it appears that greater American Society of Mechanical Engineers Code volume examination coverage could be obtained if a higher probe-angle was used. Clarify why higher probe angles were not exercised to maximize coverage on these welds.
Enclosure
 
P. Swafford                               - 2 If you have any questions, please contact me at (301) 415-2315.
Sincerely, IRA SLingam fori Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260
 
==Enclosure:==
 
Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION PUBLIC                       LPL2-2 RlF                   RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry         RidsAcrsAcnw_MailCenter      RidsOgcRp RidsRgn2MailCenter           RidsNrrDorl                   RidsNrrLABClayton (Hard Copy)
TMcLelian                     RidsNrrDciCvib ADAMS Accession No*.. ML092170275 OFFICE     LPL2-2/PM       LPL-WB/LA       CVIB\BC                   LPL2-2/BC NAME       SLingam for     BClayton       MMitchell by memo         TBoyce EBrown DATE       08/21/09         08/21/09       6/30/2009                 08/21/09 OFFICIAL RECORD COpy}}

Latest revision as of 04:32, 14 November 2019

Request for Additional Information for Second 10-Year Interval Inservice Inspection Program Plan Relief Request 2-ISI-19 Revision 1
ML092170275
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 08/21/2009
From: Ellen Brown
Plant Licensing Branch II
To: Swafford P
Tennessee Valley Authority
Brown E, NRR/DORL, 415-2315
References
TAC ME0764
Download: ML092170275 (4)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 21, 2009 Mr. Preston D. Swafford Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UI\JIT 2 - REQUEST FOR ADDITIONAL INFORMATION FOR SECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN RELIEF REQUEST 2-ISI-19 REVISION 1 (TAC NO. ME0764)

Dear Mr. Swafford:

By letter dated March 2, 2009, the Tennessee Valley Authority (TVA, the licensee) requested relief from the American Society of Mechanical Engineers (ASME) Code,Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components for Browns Ferry Nuclear Plant, Unit 2.

In accordance with Title 10 of the Code of Federal Regulations, Section 50.55a(g)(5)(iii), the licensee has submitted Relief Request (RR) 2-ISI-19, Rev. 1, for certain limited Class 1 component weld examinations. The ASME Code requires that 100 percent of the examination volumes or surface areas described in ASME Code,Section XI, be performed during each interval. The licensee determined that the required examination coverage of 100 percent was impractical to obtain.

The U.S. Nuclear Regulatory Commission (NRC) staff requires additional information in order to complete its evaluation of RR 2-IS 1-19 Revision 1. A response to the enclosed Request for Additional Information is needed before the NRC staff can complete the review. This request was discussed with Mr. Dan Green of your staff on August 21,2009, and it was agreed that TVA would respond within 30 days from the date of this letter.

P. Swafford -2 If you have any questions, please contact me at (301) 415-2315.

Sincerely,

~ If' ~ +tf\.

Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION RELIEF REQUEST 2-ISI-19, REVISION 1 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260

1. Page E1-7 of the submittal is the beginning of a table that summarizes several (and different) ultrasonic angles and modes of propagation that were used to interrogate various reactor pressure vessel nozzle-to-vessel welds. Provide a description of any modeling performed in support of the varied angles and modes of ultrasonic propagation that were applied.
2. The highest angle of ultrasonic examination employed is listed as 60-degrees, for both shear and refracted longitudinal waves. Based on the drawings provided for the subject welds, it appears that greater American Society of Mechanical Engineers Code volume examination coverage could be obtained if a higher probe-angle was used. Clarify why higher probe angles were not exercised to maximize coverage on these welds.

Enclosure

P. Swafford - 2 If you have any questions, please contact me at (301) 415-2315.

Sincerely, IRA SLingam fori Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-260

Enclosure:

Request for Additional Information cc w/enclosure: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-2 RlF RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry RidsAcrsAcnw_MailCenter RidsOgcRp RidsRgn2MailCenter RidsNrrDorl RidsNrrLABClayton (Hard Copy)

TMcLelian RidsNrrDciCvib ADAMS Accession No*.. ML092170275 OFFICE LPL2-2/PM LPL-WB/LA CVIB\BC LPL2-2/BC NAME SLingam for BClayton MMitchell by memo TBoyce EBrown DATE 08/21/09 08/21/09 6/30/2009 08/21/09 OFFICIAL RECORD COpy