ML20132A076

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Attachment - Vogtle Electric Generating Plant Unit 3 (LAR 20-001)
ML20132A076
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 08/04/2020
From: Cayetano Santos
NRC/NRR/VPOB
To:
Tanny Santos Ex 7270
References
EPID L-2020-LLE-0009, LAR 20-001
Download: ML20132A076 (3)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 182 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-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 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. 182, 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. 182

C-440 Amendment No. 182 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. 113

11. Deleted 818 3.3.00.12
12. The extended turbine generator axis intersects the shield building.

An inspection of the as-built turbine generator will be performed.

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

819 3.3.00.13

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 the safe shutdown earthquake without impact between structural elements of the buildings.

An inspection of the separation of the nuclear island from the annex and turbine building structures will be performed.

The inspection will verify the specified horizontal clearance between structural elements of the adjacent buildings, consisting of the reinforced concrete walls and slabs, structural steel columns and floor beams.

The minimum horizontal clearance above floor elevation 100-0 between the structural elements of the annex building and the nuclear island is 3 inches; except that the minimum north-south horizontal clearance between elevations 141-0 and 154-0 between structural elements of the annex building and the nuclear island west of column line I is 2-1/16 inches. The minimum horizontal clearance above floor elevation 100-0 between the structural elements of the turbine building and the nuclear island is 3 inches.

820 3.3.00.14

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.

Type test, analysis, or a combination of type test and analysis will be performed for the external walls, doors, ceilings, and floors in the main control room, the central alarm station, and the secondary alarm station.

A report exists and concludes that the external walls, doors, ceilings, 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