ML18158A310

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Attachment - Vogtle Electric Generating Plant, Unit 3 LAR-17-039
ML18158A310
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 07/10/2018
From:
Office of New Reactors
To:
Southern Nuclear Operating Co
gleaves b/415-5848
Shared Package
ML18158A305 List:
References
EPID L-2017-LLA-0376, LAR-17-039
Download: ML18158A310 (3)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 131 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-137 C-137

(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. 131, 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. 131

Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 195 2.2.03.08c.x 8.c) The PXS provides RCS makeup, x) Inspections will be conducted x) A report exists and boration, and safety injection during of the as-built nonsafety-related concludes that the coatings design basis events. coatings or of plant records of used on these surfaces have a the nonsafety-related coatings dry film density of used inside containment on 100 lb/ft3. If a coating is walls, floors, ceilings, and used that has a lower dry film structural steel except in the density, a report must exist CVS room. Inspections will be and conclude that the coating conducted of the as-built non- will not transport. A report safety-related coatings or of exists and concludes that plant records of the non-safety- inorganic zinc coatings used related coatings used on on these surfaces are Safety -

components below the maximum Service Level I or have been flood level of a design basis quantified and justified in a LOCA or located above the program for management of maximum flood level and not unqualified coatings to inside cabinets or enclosures. demonstrate the unqualified coatings are acceptable for use.

Inspections will be conducted on A report exists and concludes caulking, tags, and signs used that tags and signs used in inside containment below the these locations are made of maximum flood level of a design steel or another metal with a basis LOCA or located above the density 100 lb/ft3. In maximum flood level and not addition, a report exists and inside cabinets or enclosures. concludes that caulking used in these locations or coatings used on these signs or tags have a dry film density of 100 lb/ft3. If a material is used that has a lower density, a report must exist and conclude that there is insufficient water flow to transport lightweight caulking, signs, or tags.

Inspections will be conducted of A report exists and concludes ventilation filters and fiber- that the ventilation filters and producing fire barriers used fire barriers in these locations inside containment within the have a density of 100 lb/ft3.

ZOI or below the maximum flood level of a design basis LOCA.

196 2.2.03.08c.xi 8.c) The PXS provides RCS makeup, xi) Inspection of the as-built xi) The CMT inlet diffuser boration, and safety injection during CMT inlet diffuser will be has a flow area 165 in2.

design basis events. conducted.

C-137 Amendment No. 131