ML18120A344

Attachment - Vogtle Electric Generating Plant, Unit 4 (LAR 18-002)

ML18120A344
Person / Time
Site:	Vogtle
Issue date:	06/15/2018
From:	Jordan Hoellman NRC/NRO/DNRL/LB4
To:	Southern Nuclear Operating Co
hoellman j/415-5481
Shared Package
ML18120a348	List: ML18120A344
References
EPID L-2018-LLA-0025, LAR 18-002
Download: ML18120A344 (4)

Text

ATTACHMENT TO LICENSE AMENDMENT NO. 126 TO FACILITY COMBINED LICENSE NO. NPF-92 DOCKET NO.52-026 Replace the following pages of the Facility Combined License No. NPF-92 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-92 REMOVE INSERT 7 7 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-411 C-411 C-440 C-440

(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 hours1 days <br />0.143 weeks <br />0.0329 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. 126, 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. 126

11. Deleted.

12. The extended turbine generator axis intersects the shield building.

13. Separation is provided between the structural elements of the turbine and annex buildings and the nuclear island structure. This separation permits horizontal motion of the buildings in a safe shutdown earthquake without impact between structural elements of the buildings.

14. The external walls, doors, ceiling, and floors in the main control room, the central alarm station, and the secondary alarm station are bullet-resistant to at least Underwriters Laboratory Ballistic Standard 752, level 4.

15. Deleted.

16. Secondary security power supply system for alarm annunciator equipment and non-portable communications equipment is located within a vital area.

17. Vital areas are locked and alarmed with active intrusion detection systems that annunciate in the central and secondary alarm stations upon intrusion into a vital area.

18. Deleted.

C-411 Amendment No. 126

Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 817 3.3.00.10.iii Not used per Amendment No. 112

11. Deleted 818 3.3.00.12 12. The extended turbine generator An inspection of the as-built The extended axis of the axis intersects the shield building. turbine generator will be turbine generator intersects performed. the shield building.

819 3.3.00.13 13. Separation is provided between An inspection of the separation The minimum horizontal the structural elements of the turbine of the nuclear island from the clearance above floor and annex buildings and the nuclear annex and turbine building elevation 100-0 between the island structure. This separation structures will be performed. structural elements of the permits horizontal motion of the The inspection will verify the annex building and the nuclear buildings in the safe shutdown specified horizontal clearance island is 3 inches. The earthquake without impact between between structural elements of minimum horizontal clearance structural elements of the buildings. the adjacent buildings, above floor elevation 100-0 consisting of the reinforced between the structural concrete walls and slabs, elements of the turbine structural steel columns and building and the nuclear island floor beams. is 3 inches.

820 3.3.00.14 14. The external walls, doors, ceiling, Type test, analysis, or a A report exists and concludes and floors in the main control room, combination of type test and that the external walls, doors, the central alarm station, and the analysis will be performed for ceilings, and floors in the secondary alarm station are the external walls, doors, main control room, the central bullet-resistant to at least Underwriters ceilings, and floors in the main alarm station, and the Laboratory Ballistic Standard 752, control room, the central alarm secondary alarm station are level 4. station, and the secondary alarm bullet-resistant to at least station. Underwriters Laboratory Ballistic Standard 752, level 4.

15. Deleted C-440 Amendment No. 126