ML19063A891: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot change)
(StriderTol Bot change)
 
Line 15: Line 15:
| page count = 5
| page count = 5
| project = EPID:L-2018-LLA-0225
| project = EPID:L-2018-LLA-0225
| stage = Acceptance Review
| stage = Approval
}}
}}


=Text=
=Text=
{{#Wiki_filter:ATTACHMENT TO LICENSE AMENDMENT NO. 159 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. 159 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 7                                   7 Appendix C to Facility Combined License No. NPF-91 REMOVE                               INSERT C-101                               C-101 C-164                               C-164 C-165                               C-165
Facility Combined License No. NPF-91 REMOVE INSERT 7
7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-101 C-101 C-164 C-164 C-165 C-165  


(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).
(7) Reporting Requirements (a)
(b)   SNC shall report any violation of a requirement in Section 2.D.(3),
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).
Section 2.D.(4), Section 2.D.(5), and Section 2.D.(6) of this license within [[estimated NRC review hours::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.
(b)
(8)   Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 159, are hereby incorporated into this license.
SNC shall report any violation of a requirement in Section 2.D.(3),
(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).
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.
(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:
(8) Incorporation The Technical Specifications, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 159, are hereby incorporated into this license.
(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
(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).
: 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. 159
(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. 159  


Figure 2.2.1-1 Containment System C-101 Amendment No. 159
C-101 Amendment No. 159 Figure 2.2.1-1 Containment System


Figure 2.2.4-1 (Sheet 1 of 3)
C-164 Amendment No. 159 Figure 2.2.4-1 (Sheet 1 of 3)
Steam Generator System C-164        Amendment No. 159
Steam Generator System  


Figure 2.2.4-1 (Sheet 2 of 3)
C-165 Amendment No. 159 Figure 2.2.4-1 (Sheet 2 of 3)
Steam Generator System C-165        Amendment No. 159}}
Steam Generator System}}

Latest revision as of 04:31, 5 January 2025

Attachment - Vogtle Electric Generating Plant (LAR-18-021) PORV Relief Valve Noise Mitigation Unit 3, Amendment 159
ML19063A891
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 04/18/2019
From:
Office of New Reactors
To:
Southern Nuclear Operating Co
gleaves b/415-5848
Shared Package
ML19063A886 List:
References
EPID: L-2018-LLA-0225
Download: ML19063A891 (5)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 159 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 7

7 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-101 C-101 C-164 C-164 C-165 C-165

(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, Environmental Protection Plan, and ITAAC in Appendices A, B, and C, respectively of this license, as revised through Amendment No. 159, 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. 159

C-101 Amendment No. 159 Figure 2.2.1-1 Containment System

C-164 Amendment No. 159 Figure 2.2.4-1 (Sheet 1 of 3)

Steam Generator System

C-165 Amendment No. 159 Figure 2.2.4-1 (Sheet 2 of 3)

Steam Generator System