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| number = ML110820353
| number = ML110820353
| issue date = 03/28/2011
| issue date = 03/28/2011
| title = Browns Ferry Unit 2 - Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program (TAC No. ME3720)
| title = Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program
| author name = Gratton C
| author name = Gratton C
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Krich R M
| addressee name = Krich R
| addressee affiliation = Tennessee Valley Authority
| addressee affiliation = Tennessee Valley Authority
| docket = 05000260
| docket = 05000260
Line 13: Line 13:
| document type = Letter, Request for Additional Information (RAI)
| document type = Letter, Request for Additional Information (RAI)
| page count = 3
| page count = 3
| project = TAC:ME3720
| stage = RAI
}}
}}
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT:      BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)
==Dear Mr. Krich:==
In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.
Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.
This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).
If you have any questions, please contact me at (301) 415-1055.
Christopher Gratton, 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/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF 2-IS1-1 UPDATED RISK INFORMED INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 (TAC NO. ME3720)
: 1. The March 31,2010, submittal (Agencywide Documents Access and Management System Accession No. ML100920542) states that the revised risk-informed inservice inspection (RI-ISI) program represents a reduction in risk with regard to core damage frequency (CDF) and large early release fraction (LERF). There are other risk criteria in Section 4.4.2 of WCAP-14572, Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," February 1999 (WCAP), that must also be met. Please provide the results of your evaluation that will allow you to state that the risk/safety evaluation criteria in 4.4.2 of the WCAP are met.
: 2. Attachment 10, page 6, of the submittal clearly lists 51 previous RI-ISI examinations for R1.16. The value(s) provided for the revised program are unclear. Please clarify how many examinations are listed as R1.16 for the revised RI-ISI program.
: 3. Attachment 10, page 3, of the submittal states:
itA new Delta Risk Evaluation was performed, and the revised RI-ISI program continues to represent a risk reduction when compared to the last deterministic ASME Section XI inspection program. The revised RI-ISI program represents a reduction of 1.869E-05 in regards to CDF and 1.596E-07 in regards to LERF."
A) Per letter dated October 16,2000, the Tennessee Valley Authority reported an increase in CDF and LERF for the previous RI-ISI program when compared to the last deterministic American Society of Mechanical Engineers (ASME), Section XI inspection program. The estimated change in risk was in the third and fourth significant digits for the estimated LERF and CDF; therefore, the RI-ISI program was considered risk neutral. Please clarify the above statement to properly reflect the change in risk of the previous RI-ISI program B) Please provide additional information and clarification for how a decrease in volumetric examinations associated with thermal fatigue and intergranular stress corrosion cracking, when compared to the last RI-ISI program, can produce a very significant risk decrease when compared to the last deterministic ASME, Section XI inspection program. In addition, please provide a table comparing CDF and LERF for "without lSI," "Section XI," and "Risk-Informed" programs.
Enclosure
March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801
==SUBJECT:==
BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)
==Dear Mr. Krich:==
In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.
Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.
This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).
If you have any questions, please contact me at (301) 415-1055.
Sincerely, IRA!
Christopher Gratton, 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/encl: Distribution via Listserv Distribution:
PUBLIC                    LPLlI-2 R/F  RidsNrrDorlLpl2-2        RidsNrrDraApla RidsNrrPMBrownsFerry RidsNrrLABClayton          RidsOgcRp    RidsRgn2MailCenter        RidsNrrDorlDpr RidsNrrAcrsAcnwMailCenter ADAMS Accession No'.. ML110820353 OFFICE          LPL2-2/PM            LPL2-2/LA              APLNBC                LPL2-2/BC NAME            CGratton            BClayton                DHarrison              DBroaddus DATE            03/24/11            03/23/11                03/28/11              03/28/11 OFFICIAL RECORD COpy}}

Latest revision as of 01:48, 13 November 2019

Request for Additional Information Regarding 2-ISI-1, Updated Risk-Informed Inservice Inspection Program
ML110820353
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 03/28/2011
From: Gratton C
Plant Licensing Branch II
To: Krich R
Tennessee Valley Authority
Gratton C, NRR, DORL, 415-1055
References
TAC ME3720
Download: ML110820353 (3)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 SUB~IECT: BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)

Dear Mr. Krich:

In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.

Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.

This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).

If you have any questions, please contact me at (301) 415-1055.

Christopher Gratton, 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/encl: Distribution via Listserv

REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR RELIEF 2-IS1-1 UPDATED RISK INFORMED INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNIT 2 DOCKET NO. 50-260 (TAC NO. ME3720)

1. The March 31,2010, submittal (Agencywide Documents Access and Management System Accession No. ML100920542) states that the revised risk-informed inservice inspection (RI-ISI) program represents a reduction in risk with regard to core damage frequency (CDF) and large early release fraction (LERF). There are other risk criteria in Section 4.4.2 of WCAP-14572, Revision 1-NP-A, "Westinghouse Owners Group Application of Risk-Informed Methods to Piping Inservice Inspection Topical Report," February 1999 (WCAP), that must also be met. Please provide the results of your evaluation that will allow you to state that the risk/safety evaluation criteria in 4.4.2 of the WCAP are met.
2. Attachment 10, page 6, of the submittal clearly lists 51 previous RI-ISI examinations for R1.16. The value(s) provided for the revised program are unclear. Please clarify how many examinations are listed as R1.16 for the revised RI-ISI program.
3. Attachment 10, page 3, of the submittal states:

itA new Delta Risk Evaluation was performed, and the revised RI-ISI program continues to represent a risk reduction when compared to the last deterministic ASME Section XI inspection program. The revised RI-ISI program represents a reduction of 1.869E-05 in regards to CDF and 1.596E-07 in regards to LERF."

A) Per letter dated October 16,2000, the Tennessee Valley Authority reported an increase in CDF and LERF for the previous RI-ISI program when compared to the last deterministic American Society of Mechanical Engineers (ASME),Section XI inspection program. The estimated change in risk was in the third and fourth significant digits for the estimated LERF and CDF; therefore, the RI-ISI program was considered risk neutral. Please clarify the above statement to properly reflect the change in risk of the previous RI-ISI program B) Please provide additional information and clarification for how a decrease in volumetric examinations associated with thermal fatigue and intergranular stress corrosion cracking, when compared to the last RI-ISI program, can produce a very significant risk decrease when compared to the last deterministic ASME,Section XI inspection program. In addition, please provide a table comparing CDF and LERF for "without lSI," "Section XI," and "Risk-Informed" programs.

Enclosure

March 28, 2011 Mr. R. M. Krich Vice President, Nuclear Licensing Tennessee Valley Authority 3R Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNIT 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING 2-ISI-1, UPDATED RISK-INFORMED INSERVICE INSPECTION PROGRAM (TAC NO. ME3720)

Dear Mr. Krich:

In Attachment 10 of letter dated March 31, 2010 (Agencywide Documents Access and Management System Accession No. ML100920542), Tennessee Valley Authority requested authorization to use a risk-informed process as an alternative for the selection of Class 1 and Class 2 piping welds for examination.

Based on our review of your submittal, the U. S. Nuclear Regulatory Commission staff finds that a response to the enclosed request for additional information is needed before we can complete the review.

This request was discussed with Mr. Thomas Mathews of your staff on March 7, 2011, and it was agreed that a response would be provided by May 6,2011 (60 days).

If you have any questions, please contact me at (301) 415-1055.

Sincerely, IRA!

Christopher Gratton, 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/encl: Distribution via Listserv Distribution:

PUBLIC LPLlI-2 R/F RidsNrrDorlLpl2-2 RidsNrrDraApla RidsNrrPMBrownsFerry RidsNrrLABClayton RidsOgcRp RidsRgn2MailCenter RidsNrrDorlDpr RidsNrrAcrsAcnwMailCenter ADAMS Accession No'.. ML110820353 OFFICE LPL2-2/PM LPL2-2/LA APLNBC LPL2-2/BC NAME CGratton BClayton DHarrison DBroaddus DATE 03/24/11 03/23/11 03/28/11 03/28/11 OFFICIAL RECORD COpy

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