ML23159A099: Difference between revisions

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{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 192 TO FACILITY COMBINED LICENSE NO. NPF-91 DOCKET NO. 52-025 Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 192
Facility Combined License No. NPF-91 REMOVE                              INSERT 5                                  5 7                                  7 Appendix C to Facility Combined License No. NPF-91 REMOVE                              INSERT C-1                                C-1 C-2 through C-494                      ---


(c)      SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the design-specific pre-operational tests identified in Section 2.D.(2)(a) of this license; and (d)      (Removed by Amendment No. 192)
TO FACILITY COMBINED LICENSE NO. NPF-91
(3) Nuclear Fuel Loading and Pre-critical Testing (a)      Until the submission of the notification required by Section 2.D.(2)(c) of this license, SNC shall not load fuel into the reactor vessel; (b)      (Removed by Amendment No. 192)
(c)      SNC shall perform the pre-critical tests identified in UFSAR Section 14.2.10.1; (d)      SNC shall review and evaluate the results of the tests identified in Section 2.D.(3)(c) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified functions in accordance with UFSAR Section 14.2.10; and (e)      SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the pre-critical tests identified in Section 2.D.(3)(c) of this license.
(4) Initial Criticality and Low-Power Testing (a)      Upon submission of the notification required by Section 2.D.(3)(e) of this license, SNC is authorized to operate the facility at reactor steady-state core power levels not to exceed 5-percent thermal power in accordance with the conditions specified herein; (b)      SNC shall perform the initial criticality and low-power tests identified in UFSAR Sections 14.2.10.2 and 14.2.10.3, respectively; 5                          Amendment No. 192


(7)   Reporting Requirements (a)   Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
DOCKET NO. 52-025
(b)   SNC shall report any violation of a requirement in Section 2.D.(3),
 
Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
 
Facility Combined License No. NPF-91 REMOVE INSERT 5 5 7 7
 
Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-1 C-1 C-2 through C-494 ---
 
(c) SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the design-specific pre-operational tests identified in Section 2.D.(2)(a) of this license; and
 
(d) (Removed by Amendment No. 192)
 
(3) Nuclear Fuel Loading and Pre-critical Testing
 
(a) Until the submission of the notification required by Section 2.D.(2)(c) of this license, SNC shall not load fuel into the reactor vessel;
 
(b) (Removed by Amendment No. 192)
 
(c) SNC shall perform the pre-critical tests identified in UFSAR Section 14.2.10.1;
 
(d) SNC shall review and evaluate the results of the tests identified in Section 2.D.(3)(c) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified functions in accordance with UFSAR Section 14.2.10; and
 
(e) SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the pre-critical tests identified in Section 2.D.(3)(c) of this license.
 
(4) Initial Criticality and Low-Power Testing
 
(a) Upon submission of the notification required by Section 2.D.(3)(e) of this license, SNC is authorized to operate the facility at reactor steady-state core power levels not to exceed 5-percent thermal power in accordance with the conditions specified herein;
 
(b) SNC shall perform the initial criticality and low-power tests identified in UFSAR Sections 14.2.10.2 and 14.2.10.3, respectively;
 
5 Amendment No. 192 (7) Reporting Requirements
 
(a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).
 
(b) SNC shall report any violation of a requirement in Section 2.D.(3),
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.
(8)  Incorporation The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 192, are hereby incorporated into this license.
(9)  Technical Specifications The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).
(10)  Operational Program Implementation SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:
(a)      Environmental Qualification Program implemented before initial fuel load; (b)      Reactor Vessel Material Surveillance Program implemented before initial criticality; (c)      Preservice Testing Program implemented before initial fuel load; (d)      Containment Leakage Rate Testing Program implemented before initial fuel load; (e)      Fire Protection Program
: 1.        The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt 7                                Amendment No. 192


APPENDIX C VOGTLE ELECTRIC GENERATING PLANT UNIT 3 INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA (Removed by Amendment No. 192)
(8) Incorporation
C-1                 Amendment No. 192}}
 
The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 192, are hereby incorporated into this license.
 
(9) Technical Specifications
 
The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).
 
(10) Operational Program Implementation
 
SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:
 
(a) Environmental Qualification Program implemented before initial fuel load;
 
(b) Reactor Vessel Material Surveillance Program implemented before initial criticality;
 
(c) Preservice Testing Program implemented before initial fuel load;
 
(d) Containment Leakage Rate Testing Program implemented before initial fuel load;
 
(e) Fire Protection Program
: 1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt
 
7 Amendment No. 192 APPENDIX C
 
VOGTLE ELECTRIC GENERATING PLANT UNIT 3
 
INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA
 
(Removed by Amendment No. 192)
 
C-1 Amendment No. 192}}

Latest revision as of 20:37, 13 November 2024

Attachment - Vogtle Electric Generating Plant, Unit 3 Amendment No. 192 (LAR 23-001)
ML23159A099
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 07/31/2023
From: Cayetano Santos
NRC/NRR/VPOB
To:
References
LAR-23-001, EPID L-2023-LLA-0050
Download: ML23159A099 (1)
v • d • e


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 192

TO FACILITY COMBINED LICENSE NO. NPF-91

DOCKET NO.52-025

Replace the following pages of the Facility Combined License No. NPF-91 with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Facility Combined License No. NPF-91 REMOVE INSERT 5 5 7 7

Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-1 C-1 C-2 through C-494 ---

(c) SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the design-specific pre-operational tests identified in Section 2.D.(2)(a) of this license; and

(d) (Removed by Amendment No. 192)

(3) Nuclear Fuel Loading and Pre-critical Testing

(a) Until the submission of the notification required by Section 2.D.(2)(c) of this license, SNC shall not load fuel into the reactor vessel;

(b) (Removed by Amendment No. 192)

(c) SNC shall perform the pre-critical tests identified in UFSAR Section 14.2.10.1;

(d) SNC shall review and evaluate the results of the tests identified in Section 2.D.(3)(c) of this license and confirm that these test results are within the range of acceptable values predicted or otherwise confirm that the tested systems perform their specified functions in accordance with UFSAR Section 14.2.10; and

(e) SNC shall notify the Director of NRO, or the Directors designee, in writing, upon successful completion of the pre-critical tests identified in Section 2.D.(3)(c) of this license.

(4) Initial Criticality and Low-Power Testing

(a) Upon submission of the notification required by Section 2.D.(3)(e) of this license, SNC is authorized to operate the facility at reactor steady-state core power levels not to exceed 5-percent thermal power in accordance with the conditions specified herein;

(b) SNC shall perform the initial criticality and low-power tests identified in UFSAR Sections 14.2.10.2 and 14.2.10.3, respectively;

5 Amendment No. 192 (7) Reporting Requirements

(a) Within 30 days of a change to the initial test program described in UFSAR Section 14, Initial Test Program, made in accordance with 10 CFR 50.59 or in accordance with 10 CFR Part 52, Appendix D, Section VIII, Processes for Changes and Departures, SNC shall report the change to the Director of NRO, or the Directors designee, in accordance with 10 CFR 50.59(d).

(b) SNC shall report any violation of a requirement in Section 2.D.(3),

Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Initial notification shall be made to the NRC Operations Center in accordance with 10 CFR 50.72, with written follow up in accordance with 10 CFR 50.73.

(8) Incorporation

The Technical Specifications and Environmental Protection Plan in Appendices A and B, respectively, of this license, as revised through Amendment No. 192, are hereby incorporated into this license.

(9) Technical Specifications

The technical specifications in Appendix A to this license become effective upon a Commission finding that the acceptance criteria in this license (ITAAC) are met in accordance with 10 CFR 52.103(g).

(10) Operational Program Implementation

SNC shall implement the programs or portions of programs identified below, on or before the date SNC achieves the following milestones:

(a) Environmental Qualification Program implemented before initial fuel load;

(b) Reactor Vessel Material Surveillance Program implemented before initial criticality;

(c) Preservice Testing Program implemented before initial fuel load;

(d) Containment Leakage Rate Testing Program implemented before initial fuel load;

(e) Fire Protection Program

1. The fire protection measures in accordance with Regulatory Guide (RG) 1.189 for designated storage building areas (including adjacent fire areas that could affect the storage area) implemented before initial receipt

7 Amendment No. 192 APPENDIX C

VOGTLE ELECTRIC GENERATING PLANT UNIT 3

INSPECTIONS, TESTS, ANALYSES, AND ACCEPTANCE CRITERIA

(Removed by Amendment No. 192)

C-1 Amendment No. 192

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