ML18011A893: Difference between revisions

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| issue date = 02/01/2018
| issue date = 02/01/2018
| title = Attachment to License Amendment No. 107 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 4
| title = Attachment to License Amendment No. 107 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 4
| author name = Patel C P
| author name = Patel C
| author affiliation = NRC/NRO/DNRL/LB4
| author affiliation = NRC/NRO/DNRL/LB4
| addressee name = Whitley B H
| addressee name = Whitley B
| addressee affiliation = Southern Nuclear Operating Co, Inc
| addressee affiliation = Southern Nuclear Operating Co, Inc
| docket = 05200026
| docket = 05200026

Revision as of 06:12, 18 June 2019

Attachment to License Amendment No. 107 for the Main Control Room Emergency Habitability System Changes to Satisfy Post Actuation Performance Requirements (LAR 17-001) for Vogtle Electric Generating Plant Unit 4
ML18011A893
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 02/01/2018
From: Chandu Patel
NRC/NRO/DNRL/LB4
To: Whitley B
Southern Nuclear Operating Co
PATEL C/415-3025
Shared Package
ML18011A885 List:
References
CAC RP9639, EPID L-2017-LLA-0145, LAR 17-001
Download: ML18011A893 (15)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 107 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 A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 3.3.13-1 3.3.13-1 3.3.16-1 3.3.16-1 3.7.6-1 3.7.6-1 3.7.6-2 3.7.6-2 3.7.6-3 3.7.6-3 3.7.6-4 3.7.6-4 --- 3.7.6-5 Appendix C to Facility Combined License No. NPF-92 REMOVE INSERT C-168 C-168 C-169 C-169 C-172 C-172 C-175 C-175 C-178 C-178 C-294 C-294 (7) Reporting Requirements (a) Within 30 days of a change to the initial test program described in FSAR 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, for Changes and SNC shall report the change to the Director of NRO, or the 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. 107, 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. 107

C-168 Amendment No. 107 b) c) d) c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.

C-169 Amendment No. 107 MCR Load Shed Panel 1 VES-EP-01 No Yes - Yes/No Yes Yes De-energize MCR Loads - MCR Load Shed Panel 2 VES-EP-02 No Yes - Yes/No Yes Yes De-energize MCR Loads - Note: Dash (-) indicates not applicable.

C-172 Amendment No. 107 Temporary Instrument Isolation Valve A VES-PL-V018 Yes Yes No -/- No No Transfer Open - Temporary Instrument Isolation Valve B VES-PL-V019 Yes Yes No -/- No No Transfer Open -

C-175 Amendment No. 107 23.5 (hour 0 to 0.5) 14.5 (hour 0.5 to 3.5) 4.75 (hour 3.5 through 24) 3.95 Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 252 2.2.05.01 C-178 Amendment No. 107 Table 2.2.5-5 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 270 2.2.05.07c 271 2.2.05.07d 272 2.2.05.08 273 2.2.05.09a 274 2.2.05.09b 877 2.2.05.09c 9.c) The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS. Testing will be performed on the MCR Load Shed Panels listed in Table 2.2.5-1 using real or simulated signals into the PMS. The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.

C-294 Amendment No. 107