NL-24-0045, Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-02: Difference between revisions

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{{#Wiki_filter:A                                     Southern                                       Nuclear                                                                                                                                                                                                                                                                                                                                             Regulatory                         Affairs                                                                                                                                                                                             3535 Colonnade                                   Park w      ay Birmingham           , AL           35243
{{#Wiki_filter:A Southern Nuclear Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 February 8, 2024 Docket Nos.: 50-424 50-425 NL-24-0045 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Units 1 and 2 Supplement to Response to Requests for Additional Information for Proposed Alternative AL T-VR-02 Ladies and Gentlemen:
By {{letter dated|date=May 1, 2023|text=letter dated May 1, 2023}} (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML23121A267), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) and a proposed alternative request for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2 regarding revisions to Technical Specification (TS) 3.4.14, "RCS Pressure Isolation Valve (PIV) Leakage", and an alternative to ASME OM Code for applicable Vogtle Pressure Isolation Valves to allow testing to be conducted at a performance-based frequency, as specified in Nuclear Engineering Institute 94-01, Revision 3-A.
By {{letter dated|date=November 17, 2023|text=letter dated November 17, 2023}} (ADAMS Accession No. ML23321A242), SNC responded to an NRC request for additional information. A clarification call was held on Thursday, January 11, 2024, between SNC and the NRC regarding RAI response #3 for AL T-VR-02. Based on the results of the clarification call, SNC is issuing a supplement to clarify that SNC's request does not modify the requirement to meet 1 0CFR50.55a(b)(3)(iv), which states:
3 OM condition: Check valves (Appendix II). Appendix II of the ASME OM Code, 2003 Addenda through the 2012 Edition, is acceptable for use with the following requirements.
Trending and evaluation must support the determination that the valve or group of valves is capable of performing its intended function(s) over the entire interval. At least one of the Appendix II condition monitoring activities for a valve group must be performed on each valve of the group at approximate equal intervals not to exceed the maximum interval shown in the following table:
Group size Table 3 to Paragraph (b)(3)(iv)-Maximum Intervals For Use When Applying Internal Extensions Maximum interval between activities of member valves in the groups (years) 4.5 4.5 6
Not applicable Maximum interval between activities of each valve in the group (years) 16 12 12 10


205  992  5000
U. S. Nuclear Regulatory Commission NL-24-0045 Page 2 Subsequent to AL T-VR-02 approval, SNC will continue to meet this condition.
 
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
February                                    8,    2024
Respectfully submitted,  
 
Docket      Nos.:                                50-424                                                                                                                                            NL-24-0045 50-425
 
U.                       S.     Nuclear           Regulatory                   Commission ATTN:              Document                                          Control      Desk Washington,                                          D.      C.                20555-0001
 
Vogtle      Electric Generating      Plant -                      Units      1 and                        2 Supplement            to    Response                        to  Requests for Additional Information                        for Proposed              Alternative AL T-VR-02
 
Ladies and                        Gentlemen:
 
By          letter dated May                          1,  2023 (Agencywide                          Documents                                    Access          and                      Management                                              System          (ADAMS)
Accession                                              No.                                ML23121A267),                        Southern                                    Nuclear                              Operating              Company                                                                            (SNC)                      submitted a                              license amendment                                                      request  (LAR)            and                                a                    proposed                      alternative request for            Vogtle              Electric Generating              Plant      (Vogtle),              Units            1        and                                2        regarding      revisions to          Technical                    Specification (TS) 3.4.14,  "RCS      Pressure Isolation      Valve                (PIV)                  Leakage",                          and                            an                        alternative to  ASME    OM    Code            for applicable      Vogtle        Pressure Isolation        Valves                  to      allow        testing to      be                conducted                                              at    a              performance based                                frequency,                              as          specified in  Nuclear            Engineering    Institute 94-01,    Revision 3-A.
 
By            letter dated    November                                  17,  2023  (ADAMS  Accession                          No.              ML23321A242),      SNC    responded                    to an                          NRC    request for additional information.                        A  clarification call was                      held on                        Thursday,                          January                                                            11, 2024,        between                            SNC        and                            the NRC          regarding    RAI            response                  #3      for AL T-VR-02.                                      Based                  on                              the results of the clarification call, SNC  is issuing a          supplement          to  clarify that SNC's  request does            not modify          the requirement to  meet    1 0CFR50.55a(b)(3)(iv),                which      states:
 
OM condition:                  Check        valves (Appendix                II). Appendix                II    of the ASME    OM    Code,              2003 Addenda                        through        the 2012    Edition, is acceptable                      for use        with the following requirements.
Trending        and                        evaluation                      must          support    the determination    that the valve or    group                of valves is capable                          of performing its intended function(s)                over    the entire interval. At least one                      of the Appendix                  II        condition                    monitoring                activities for a            valve  group                    must              be                performed    on                            each valve      of    the group                        at      approximate                                  equal                intervals not                  to        exceed                          the maximum                                                            interval shown                                    in  the following table:
 
Table    3 to  Paragraph              (b)(3)(    iv)-Maximum                                Intervals For    Use          When            Applying    Internal    Extensions
 
Group          size      Maximum                        interval between          activities of member              valves in the groups Maximum                        interval between          activities of each            va        lve  in the group            (years)
(years)
 
4.5                                                                                                                    16
 
3                                                                                                                                4.5                                                                                                                    12
 
6                                                                                                                    12
 
Not applicable                                                                                                                        10 U.                        S.      Nuclear          Regulatory                  Commission NL-24-0045 Page             2
 
Subsequent                                     to AL T-VR-02                     approval,                 SNC will continue                                 to     meet this condition.
 
This letter contains                             no                         NRC   commitments.                           If you                                     have           any                                 questions,       please contact                           Ryan                                   Joyce at   205.992.6468.
 
Respectfully submitted,
~~
~~
Jamie           Coleman Regulatory               Affairs Director
Jamie Coleman Regulatory Affairs Director JMC/dsp/cbg cc:
 
Regional Administrator, Region II NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 RType: CVC?000}}
JMC/dsp/cbg
 
cc:                                                   Regional         Administrator, Region                 II NRR       Project Manager                           -                     Vogtle       1 & 2 Senior     Resident Inspector         -                     Vogtle       1 & 2 RType:                         CVC?000}}

Latest revision as of 20:26, 24 November 2024

Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-02
ML24039A175
Person / Time
Site: Vogtle  
Issue date: 02/08/2024
From: Coleman J
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation, Document Control Desk
References
NL-24-0045
Download: ML24039A175 (1)
v • d • e


Text

A Southern Nuclear Regulatory Affairs 3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 February 8, 2024 Docket Nos.: 50-424 50-425 NL-24-0045 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant - Units 1 and 2 Supplement to Response to Requests for Additional Information for Proposed Alternative AL T-VR-02 Ladies and Gentlemen:

By letter dated May 1, 2023 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML23121A267), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) and a proposed alternative request for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2 regarding revisions to Technical Specification (TS) 3.4.14, "RCS Pressure Isolation Valve (PIV) Leakage", and an alternative to ASME OM Code for applicable Vogtle Pressure Isolation Valves to allow testing to be conducted at a performance-based frequency, as specified in Nuclear Engineering Institute 94-01, Revision 3-A.

By letter dated November 17, 2023 (ADAMS Accession No. ML23321A242), SNC responded to an NRC request for additional information. A clarification call was held on Thursday, January 11, 2024, between SNC and the NRC regarding RAI response #3 for AL T-VR-02. Based on the results of the clarification call, SNC is issuing a supplement to clarify that SNC's request does not modify the requirement to meet 1 0CFR50.55a(b)(3)(iv), which states:

3 OM condition: Check valves (Appendix II). Appendix II of the ASME OM Code, 2003 Addenda through the 2012 Edition, is acceptable for use with the following requirements.

Trending and evaluation must support the determination that the valve or group of valves is capable of performing its intended function(s) over the entire interval. At least one of the Appendix II condition monitoring activities for a valve group must be performed on each valve of the group at approximate equal intervals not to exceed the maximum interval shown in the following table:

Group size Table 3 to Paragraph (b)(3)(iv)-Maximum Intervals For Use When Applying Internal Extensions Maximum interval between activities of member valves in the groups (years) 4.5 4.5 6

Not applicable Maximum interval between activities of each valve in the group (years) 16 12 12 10

U. S. Nuclear Regulatory Commission NL-24-0045 Page 2 Subsequent to AL T-VR-02 approval, SNC will continue to meet this condition.

This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.

Respectfully submitted,

~~

Jamie Coleman Regulatory Affairs Director JMC/dsp/cbg cc:

Regional Administrator, Region II NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 RType: CVC?000

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