ML18289A746

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Attachment - Vogtle Unit 3 LAR-17-043 Containment Pressure Analysis
ML18289A746
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 11/07/2018
From: Gleaves B C
NRC/NRO/DLSE/LB4
To:
Southern Nuclear Operating Co
gleaves b/415-5848
Shared Package
ML18289A742 List:
References
EPID L-2018-LLA-0005, LAR-17-043
Download: ML18289A746 (7)


Text

ATTACHMENT TO LICENSE AMENDMENT NO. 147 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 A to Facility Combined License Nos. NPF-91 and NPF-92 REMOVE INSERT 5.5-8 5.5-8 Appendix C to Facility Combined License No. NPF-91 REMOVE INSERT C-111 C-111 C-111a C-111a C-111b C-111b C-409 C-409 C-426 C-426 (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, 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. 147, 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. 147

C-111 Amendment No. 147 Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 138 2.2.02.07b.i 7.a) The PCS delivers water from the PCCWST to the outside, top of the containment vessel. i) Testing will be performed to measure the PCCWST delivery rate from each one of the three parallel flow paths. i) When tested, each one of the three flow paths delivers water at greater than or equal to: 469.1 gpm at a PCCWST water level of 27.4 ft + 0.2, - 0.0 ft above the tank floor 226.6 gpm when the PCCWST water level uncovers the first (i.e. tallest) standpipe 176.3 gpm when the PCCWST water level uncovers the second tallest standpipe 144.2 gpm when the PCCWST water level uncovers the third tallest standpipe or a report exists and concludes that the as-measured flow rates delivered by the PCCWST to the containment vessel provides sufficient heat removal capability such that the limiting containment pressure and temperature values are not affected and the PCS is able to perform its safety function to remove heat from containment to maintain plant safety. ii) Testing and or analysis will be performed to demonstrate the PCCWST inventory provides 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of adequate water flow. ii) When tested and/or analyzed with all flow paths delivering and an initial water level at 27.4 + 0.2, - 0.00 ft, the PCCWST water inventory provides greater than or equal to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of flow, and the flow rate at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is greater than or equal to 100.7 gpm or a report exists and concludes that the as-measured flow rates delivered by the PCCWST to the containment vessel provides sufficient heat removal capability such that the limiting containment pressure and temperature values are not affected and the PCS is able to perform its safety function to remove heat from containment to maintain plant safety.

C-111a Amendment No. 147 Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria ii) Inspection of the containment vessel exterior coating will be conducted. ii) A report exists and concludes that the containment vessel exterior surface is coated with an inorganic zinc coating above elevation 135'-3". iii) Inspection of the containment vessel interior coating will be conducted. iii) A report exists and concludes that the containment vessel interior surface is coated with an inorganic zinc coating above the operating deck. 7.c) The PCS provides air flow over the outside of the containment vessel by a natural circulation air flow path from the air inlets to the air discharge structure. Inspections of the air flow path segments will be performed. Flow paths exist at each of the following locations: Air inlets Base of the outer annulus Base of the inner annulus 7.d) The PCS drains the excess water from the outside of the containment vessel through the two upper annulus drains. Testing will be performed to verify the upper annulus drain flow performance. With a water level within the upper annulus 10" +/- 1" above the annulus drain inlet, the flow rate through each drain is greater than or equal to 525 gpm. 7.e) The PCS provides a flow path for long-term water makeup to the PCCWST. ii) Testing will be performed to measure the delivery rate from the long-term makeup connection to the PCCWST. ii) With a water supply connected to the PCS long-term makeup connection, each PCS recirculation pump delivers greater than or equal to 100 gpm when tested separately.

C-111b Amendment No. 147 Table 2.2.2-3 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 9. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the MCR. Inspection will be performed for retrievability of the safety-related displays in the MCR. Safety-related displays identified in Table 2.2.2-1 can be retrieved in the MCR. 10.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.2.2-1 to perform active functions. Stroke testing will be performed on the remotely operated valves identified in Table 2.2.2-1 using the controls in the MCR. Controls in the MCR operate to cause remotely operated valves identified in Table 2.2.2-1 to perform active functions. 10.b) The valves identified in Table 2.2.2-1 as having PMS control perform an active safety function after receiving a signal from the PMS. Testing will be performed on the remotely operated valves in Table 2.2.2-1 using real or simulated signals into the PMS. The remotely operated valves identified in Table 2.2.2-1 as having PMS control perform the active function identified in the table after receiving a signal from the PMS. 11.a) The motor-operated valves identified in Table 2.2.2-1 perform an active safety-related function to change position as indicated in the table. iii) Tests of the motor-operated valves will be performed under preoperational flow, differential pressure, and temperature conditions. iii) Each motor-operated valve changes position as indicated in Table 2.2.2-1 under preoperational test conditions. 11.b) After loss of motive power, the remotely operated valves identified in Table 2.2.2-1 assume the indicated loss of motive power position. Testing of the remotely operated valves will be performed under the conditions of loss of motive power. After loss of motive power, each remotely operated valve identified in Table 2.2.2-1 assumes the indicated loss of motive power position. 139 2.2.02.07b.ii 140 2.2.02.07b.iii 141 2.2.02.07c 142 2.2.02.07d C-409 Amendment No. 147 1. b) c) 1 d) e) f) g) h) b) 1. Containment isolation devices are addressed in subsection 2.2.1, Containment System.

C-426 Amendment No. 147 Table 3.3-6 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 772 3.3.00.02d 773 3.3.00.02e 774 3.3.00.02f 775 3.3.00.02g 776 3.3.00.02h