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 Park w ay Birmingham, AL 35243


205 992 5000
205 992 5000


February                                     8,     2024
February 8, 2024


Docket     Nos.:                                 50-424                                                                                                                                           NL-24-0045 50-425
Docket Nos.: 50-424 NL-24-0045 50-425


U.                       S.     Nuclear           Regulatory                   Commission ATTN:               Document                                         Control       Desk Washington,                                         D.     C.                 20555-0001
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
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:
Ladies and Gentlemen:


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


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.
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:
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
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)
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)
(years)


4.5                                                                                                                   16
4.5 16


3                                                                                                                                 4.5                                                                                                                   12
3 4.5 12


6                                                                                                                   12
6 12


Not applicable                                                                                                                       10 U.                       S.     Nuclear           Regulatory                   Commission NL-24-0045 Page             2
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.
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.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.


Respectfully submitted,
Respectfully submitted,
~~
~~
Jamie           Coleman Regulatory               Affairs Director
Jamie Coleman Regulatory Affairs Director


JMC/dsp/cbg
JMC/dsp/cbg


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

Revision as of 15:21, 5 October 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 Park w ay Birmingham, AL 35243

205 992 5000

February 8, 2024

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

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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