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| number = ML13038A144
| number = ML13038A144
| issue date = 02/20/2013
| issue date = 02/20/2013
| title = Browns Ferry Nuclear Plant, Unit 2, Request for Additional Information Regarding Relief Request No. 2-ISI-29 (TAC No. ME8854)
| title = Request for Additional Information Regarding Relief Request No. 2-ISI-29
| author name = Saba F E
| author name = Saba F
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Shea J W
| addressee name = Shea J
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000260
| docket = 05000260
Line 14: Line 14:
| page count = 4
| page count = 4
| project = TAC:ME8854
| project = TAC:ME8854
| stage = Other
| stage = RAI
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 February 20, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street LP 3D-C Chattanooga, TN 37402-2801 SUBJECT: BROWNS FERRY NUCLEAR PLANT, UNIT 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. 2-ISI-29 (TAC NO. ME8854) Dear Mr. Shea: By letter dated May 25,2012 (Agencywide Documents Access and Management System Accession No. ML 12150A368), the Tennessee Valley Authority (TVA or the licensee), submitted Relief Request 2-ISI-29. Pursuent to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Section 50.55a(g)(5)(iii), the licensee requested a relief from the weld examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, 1995 Edition with the 1996 Addenda, as amended by 10 CFR 50.55a(b )(2)(xv)(A)(2), for obtaining essentially 100 percent coverage for four welds. This relief was requested for the Browns Ferry Nuclear Plant, Unit 2, third 10-year Inspection Interval, which began on May 25,2001, and ended on May 24,2011. Pursuant to 10 CFR 50.55a(g)(5)(iii), the licensee should have notified the U.S. Nuclear Regulatory Commission (NRC) prior to May 24, 2012, of its inability to meet the ASME Code requirements for these examinations that are required to be completed in the third 10-year inspection cycle. By letter dated July 18, 2012, the NRC informed the licensee that because of the failure to request relief consistent with the 10 CFR 50.55a requirements, the NRC staff's review will be limited to a determination of the adequacy of the achieved coverage as it relates to the functionality and structural integrity of the affected piping and associated systems. A response to the enclosed request for additional information is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. Tom Hess of your staff on February 8, 2013, and it was agreed that TVA would respond within 30 days of issuance of this letter.
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street LP 3D-C Chattanooga, TN 37402-2801
J. Shea -If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov. Sincerely, Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc: Distribution via Listserv REQUEST FOR ADDITIONAL BY THE OFFICE OF NUCLEAR REACTOR REGARDING RELIEF REQUEST NO. TENNESSEE VALLEY BROWNS FERRY NUCLEAR PLANT, UNIT DOCKET NO. For All Welds: The piping and components are described as being constructed from "Stainless" or "Carbon" steel, but the alloys are not identified. For each weld, provide the materials of construction for the pipes, weld metals, and welded components. These welds are covered by a risk-informed inservice inspection program. Address whether any additional welds in the same segments were examined to compensate for the missed volume. For Weld RCRD-2-50: Provide the operating temperature at the dissimilar metal weld RCRD-2-50. Address whether any of the stress corrosion cracking mitigation methods, such as Mechanical Stress Improvement, have been applied to RCRD-2-50. For Welds RCRD-2-50 and GR-2-09: The provided coverage map does not clearly show where coverage is being claimed for the inspection and where coverage was missed. Please provide a coverage map showing the regions that were not inspected. For weld DRHR-2-03 The exact inspection process proposed for this weld is unclear to the NRC staff. Please confirm or correct the following: a. The weld was inspected using 45° shear waves b. The weld was inspected from both sides c. Only coverage on the flued side of the weld is counted Enclosure J.Shea -2 If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov. Sincerely, IRA by Siva Lingam fori Farideh E. Saba, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. Request for Additional cc: Distribution via Listserv DISTRIBUTION: Public LPL2-2 RlF RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry RidsOgcRp RidsRgn2MailCenter RidsNrrLABClayton RidsNrrDeEpnb FKeith, NRR SCumbridge, NRR Lingam for FSaba 119/13 LPL2-2/LA(IT) FKeith 19113 LPL2*2/LA DEIEPNB/BC BClayton Lupoid 2120113 LPL2*2/BC JQuichocho 120/13 OFFICIAL RECORD COpy
 
}}
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. 2-ISI-29 (TAC NO. ME8854)
 
==Dear Mr. Shea:==
 
By letter dated May 25,2012 (Agencywide Documents Access and Management System Accession No. ML12150A368), the Tennessee Valley Authority (TVA or the licensee), submitted Relief Request 2-ISI-29. Pursuent to Title 10 of the Code of Federal Regulations (10 CFR),
Part 50, Section 50.55a(g)(5)(iii), the licensee requested a relief from the weld examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code), Section XI, 1995 Edition with the 1996 Addenda, as amended by 10 CFR 50.55a(b )(2)(xv)(A)(2), for obtaining essentially 100 percent coverage for four welds. This relief was requested for the Browns Ferry Nuclear Plant, Unit 2, third 10-year Inspection Interval, which began on May 25,2001, and ended on May 24,2011.
Pursuant to 10 CFR 50.55a(g)(5)(iii), the licensee should have notified the U.S. Nuclear Regulatory Commission (NRC) prior to May 24, 2012, of its inability to meet the ASME Code requirements for these examinations that are required to be completed in the third 10-year inspection cycle. By letter dated July 18, 2012, the NRC informed the licensee that because of the failure to request relief consistent with the 10 CFR 50.55a requirements, the NRC staff's review will be limited to a determination of the adequacy of the achieved coverage as it relates to the functionality and structural integrity of the affected piping and associated systems.
A response to the enclosed request for additional information is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. Tom Hess of your staff on February 8, 2013, and it was agreed that TVA would respond within 30 days of issuance of this letter.
 
J. Shea                                   - 2 If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov.
Sincerely,
                                              ~(t.~                            ~r Farideh E. Saba, 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: Distribution via Listserv
 
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST NO. 2-ISI-29 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 For All Welds:
: 1. The piping and components are described as being constructed from "Stainless" or "Carbon" steel, but the alloys are not identified. For each weld, provide the materials of construction for the pipes, weld metals, and welded components.
: 2. These welds are covered by a risk-informed inservice inspection program. Address whether any additional welds in the same segments were examined to compensate for the missed volume.
For Weld RCRD-2-50:
: 3. Provide the operating temperature at the dissimilar metal weld RCRD-2-50.
: 4. Address whether any of the stress corrosion cracking mitigation methods, such as Mechanical Stress Improvement, have been applied to RCRD-2-50.
For Welds RCRD-2-50 and GR-2-09:
: 5. The provided coverage map does not clearly show where coverage is being claimed for the inspection and where coverage was missed. Please provide a coverage map showing the regions that were not inspected.
For weld DRHR-2-03
: 6. The exact inspection process proposed for this weld is unclear to the NRC staff. Please confirm or correct the following:
: a.     The weld was inspected using 45° shear waves
: b.     The weld was inspected from both sides
: c.     Only coverage on the flued side of the weld is counted Enclosure
 
J.Shea                                           -2 If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov.
Sincerely, IRA by Siva Lingam fori Farideh E. Saba, 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: Distribution via Listserv DISTRIBUTION:
Public                     LPL2-2 RlF             RidsAcrsAcnwMailCenter       RidsNrrDorlDpr RidsNrrDorlLpl2-2         RidsNrrPMBrownsFerry   RidsOgcRp                   RidsRgn2MailCenter RidsNrrLABClayton         RidsNrrDeEpnb           FKeith, NRR                 SCumbridge, NRR LPL2-2/LA(IT)     LPL2*2/LA           DEIEPNB/BC     LPL2*2/BC Lingam for FSaba    FKeith            BClayton              Lupoid        JQuichocho 119/13                19113            2120113                              120/13 OFFICIAL RECORD COpy}}

Latest revision as of 22:37, 4 November 2019

Request for Additional Information Regarding Relief Request No. 2-ISI-29
ML13038A144
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 02/20/2013
From: Farideh Saba
Plant Licensing Branch II
To: James Shea
Tennessee Valley Authority
Saba, Farideh
References
TAC ME8854
Download: ML13038A144 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 20, 2013 Mr. Joseph W. Shea Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street LP 3D-C Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. 2-ISI-29 (TAC NO. ME8854)

Dear Mr. Shea:

By letter dated May 25,2012 (Agencywide Documents Access and Management System Accession No. ML12150A368), the Tennessee Valley Authority (TVA or the licensee), submitted Relief Request 2-ISI-29. Pursuent to Title 10 of the Code of Federal Regulations (10 CFR),

Part 50, Section 50.55a(g)(5)(iii), the licensee requested a relief from the weld examination coverage requirements specified in American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI, 1995 Edition with the 1996 Addenda, as amended by 10 CFR 50.55a(b )(2)(xv)(A)(2), for obtaining essentially 100 percent coverage for four welds. This relief was requested for the Browns Ferry Nuclear Plant, Unit 2, third 10-year Inspection Interval, which began on May 25,2001, and ended on May 24,2011.

Pursuant to 10 CFR 50.55a(g)(5)(iii), the licensee should have notified the U.S. Nuclear Regulatory Commission (NRC) prior to May 24, 2012, of its inability to meet the ASME Code requirements for these examinations that are required to be completed in the third 10-year inspection cycle. By letter dated July 18, 2012, the NRC informed the licensee that because of the failure to request relief consistent with the 10 CFR 50.55a requirements, the NRC staff's review will be limited to a determination of the adequacy of the achieved coverage as it relates to the functionality and structural integrity of the affected piping and associated systems.

A response to the enclosed request for additional information is needed before the Nuclear Regulatory Commission staff can complete the review. This request was discussed with Mr. Tom Hess of your staff on February 8, 2013, and it was agreed that TVA would respond within 30 days of issuance of this letter.

J. Shea - 2 If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov.

Sincerely,

~(t.~ ~r Farideh E. Saba, 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: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REGARDING RELIEF REQUEST NO. 2-ISI-29 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 For All Welds:

1. The piping and components are described as being constructed from "Stainless" or "Carbon" steel, but the alloys are not identified. For each weld, provide the materials of construction for the pipes, weld metals, and welded components.
2. These welds are covered by a risk-informed inservice inspection program. Address whether any additional welds in the same segments were examined to compensate for the missed volume.

For Weld RCRD-2-50:

3. Provide the operating temperature at the dissimilar metal weld RCRD-2-50.
4. Address whether any of the stress corrosion cracking mitigation methods, such as Mechanical Stress Improvement, have been applied to RCRD-2-50.

For Welds RCRD-2-50 and GR-2-09:

5. The provided coverage map does not clearly show where coverage is being claimed for the inspection and where coverage was missed. Please provide a coverage map showing the regions that were not inspected.

For weld DRHR-2-03

6. The exact inspection process proposed for this weld is unclear to the NRC staff. Please confirm or correct the following:
a. The weld was inspected using 45° shear waves
b. The weld was inspected from both sides
c. Only coverage on the flued side of the weld is counted Enclosure

J.Shea -2 If you have any questions, please contact me by phone at (301) 415-1447 or e-mail at Farideh.Saba@nrc.gov.

Sincerely, IRA by Siva Lingam fori Farideh E. Saba, 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: Distribution via Listserv DISTRIBUTION:

Public LPL2-2 RlF RidsAcrsAcnwMailCenter RidsNrrDorlDpr RidsNrrDorlLpl2-2 RidsNrrPMBrownsFerry RidsOgcRp RidsRgn2MailCenter RidsNrrLABClayton RidsNrrDeEpnb FKeith, NRR SCumbridge, NRR LPL2-2/LA(IT) LPL2*2/LA DEIEPNB/BC LPL2*2/BC Lingam for FSaba FKeith BClayton Lupoid JQuichocho 119/13 19113 2120113 120/13 OFFICIAL RECORD COpy

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