ML18030A675
| ML18030A675 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/28/2018 |
| From: | Office of New Reactors |
| To: | Southern Nuclear Operating Co |
| patel c/415-3025 | |
| References | |
| EPID L-2017-LLA-0126, LAR 17-009 | |
| Download: ML18030A675 (7) | |
Text
ATTACHMENT TO LICENSE AMENDMENT NO. 110 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-64 C-64
--- C-64a C-132 C-132 C-133 C-133 C-138 C-138
(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, 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. 110, 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. 110
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 33 2.1.02.08d.ii 8.d) The RCS provides automatic ii) Inspections and associated ii) The calculated flow depressurization during design basis analysis of each fourth-stage resistance for each group of events. ADS sub-loop (four valves fourth-stage ADS valves and and associated piping piping with all valves open connected to each hot leg) is:
will be conducted to verify Loop 1:
the line routing is consistent Sub-loop A: < 5.91x10-7 ft/gpm2 with the line routing used for Sub-loop C: < 6.21x10-7 ft/gpm2 design flow resistance Loop 2:
calculations. Sub-loop B: < 4.65x10-7 ft/gpm2 Sub-loop D: < 6.20x10-7ft/gpm2 34 2.1.02.08d.iii 8.d) The RCS provides automatic iii) Inspections of each iii) The as-manufactured depressurization during design basis fourth-stage ADS valve will flow area through each events. be conducted to determine the fourth-stage ADS valve is >
as-manufactured flow area 67 in2.
through each valve.
35 2.1.02.08d.iv 8.d) The RCS provides automatic iv) Type tests and analysis iv) A report exists and depressurization during design basis will be performed to concludes that the effective events. determine the effective flow flow area through each stage area through each stage 1,2,3 1 ADS valve > 4.6 in2 and ADS valve. each stage 2,3 ADS valve is
> 19 in2.
36 2.1.02.08d.v 8.d) The RCS provides automatic v) Inspections of the v) The minimum elevation depressurization during design basis elevation of the ADS stage 4 of the bottom inside surface events. valve discharge will be of the outlet of these valves conducted. is greater than plant elevation 110 feet.
37 2.1.02.08d.vi 8.d) The RCS provides automatic vi) Inspections of the ADS vi) The discharge of the depressurization during design basis stage 4 valve discharge will ADS stage 4 valves is events. be conducted. directed into the steam generator compartments.
38 2.1.02.08d.vii 8.d) The RCS provides automatic vii) Inspection of each ADS vii) The flow area through depressurization during design basis sparger will be conducted to the holes in each ADS events. determine the flow area sparger is > 274 in2.
through the sparger holes.
C-64 Amendment No. 110
Table 2.1.2-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 39 2.1.02.08d.viii 8.d) The RCS provides automatic viii) Inspection of the viii) The centerline of the depressurization during design basis elevation of each ADS sparger connection of the sparger events. will be conducted. arms to the sparger hub is
< 11.5 feet below the IRWST overflow level.
40 2.1.02.08e 8.e) The RCS provides emergency letdown Inspections of the reactor A report exists and during design basis events. vessel head vent valves and concludes that the capacity inlet and outlet piping will be of the reactor vessel head conducted. vent is sufficient to pass not less than 8.2 lbm/sec at 1250 psia in the RCS.
C-64a Amendment No. 110
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 178 2.2.03.08c.i.02 8.c) The PXS provides RCS makeup, i) A low-pressure injection test i) The injection line flow boration, and safety injection during and analysis for each CMT, each resistance from each source is design basis events. accumulator, each IRWST as follows:
injection line, and each 2. Accumulators:
containment recirculation line The calculated flow resistance will be conducted. Each test is between each accumulator and initiated by opening isolation the reactor vessel is valve(s) in the line being tested. 1.47 x 10-5 ft/gpm2 and Test fixtures may be used to 1.83 x 10-5 ft/gpm2.
simulate squib valves.
- 2. Accumulators:
Each accumulator will be partially filled with water and pressurized with nitrogen. All valves in these lines will be open during the test. Sufficient flow will be provided to fully open the check valves.
179 2.2.03.08c.i.03 8.c) The PXS provides RCS makeup, i) A low-pressure injection test i) The injection line flow boration, and safety injection during and analysis for each CMT, each resistance from each source is design basis events. accumulator, each IRWST as follows:
injection line, and each 3. IRWST Injection:
containment recirculation line The calculated flow resistance will be conducted. Each test is for each IRWST injection line initiated by opening isolation between the IRWST and the valve(s) in the line being tested. reactor vessel is:
Test fixtures may be used to Line A: 5.35 x 10-6 ft/gpm2 simulate squib valves. and 9.09 x 10-6 ft/gpm2 and
- 3. IRWST Injection: Line B: 6.15 x 10-6 ft/gpm2 The IRWST will be partially and 1.05 x 10-5 ft/gpm2.
filled with water. All valves in these lines will be open during the test. Sufficient flow will be provided to open the check valves.
C-132 Amendment No. 110
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 180 2.2.03.08c.i.04 8.c) The PXS provides RCS makeup, i) A low-pressure injection test i) The injection line flow boration, and safety injection during and analysis for each CMT, each resistance from each source is design basis events. accumulator, each IRWST as follows:
injection line, and each 4. Containment Recirculation:
containment recirculation line The calculated flow resistance will be conducted. Each test is for each containment initiated by opening isolation recirculation line between the valve(s) in the line being tested. containment and the reactor Test fixtures may be used to vessel is:
simulate squib valves. Line A: 1.33 x 10-5 ft/gpm2
- 4. Containment Recirculation: and A temporary water supply will Line B: 1.21 x 10-5 ft/gpm2.
be connected to the recirculation lines. All valves in these lines will be open during the test.
Sufficient flow will be provided to open the check valves.
181 2.2.03.08c.ii 8.c) The PXS provides RCS makeup, ii) A low-pressure test and ii) The flow resistance from boration, and safety injection during analysis will be conducted for the cold leg to the CMT is design basis events. each CMT to determine piping 7.21 x 10-6 ft/gpm2.
flow resistance from the cold leg to the CMT. The test will be performed by filling the CMT via the cold leg balance line by operating the normal residual heat removal pumps.
182 2.2.03.08c.iii 8.c) The PXS provides RCS makeup, iii) Inspections of the routing of iii) These lines have no boration, and safety injection during the following pipe lines will be downward sloping sections design basis events. conducted: between the connection to the
- CMT inlet line, cold leg to RCS and the high point of the high point line.
- PRHR HX inlet line, hot leg to high point 183 2.2.03.08c.iv.01 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the
- 1. IRWST injection lines; elevation of:
IRWST connection to DVI 1. IRWST bottom inside nozzles surface 184 2.2.03.08c.iv.02 8.c) The PXS provides RCS makeup, iv) Inspections of the elevation iv) The maximum elevation boration, and safety injection during of the following pipe lines will of the top inside surface of design basis events. be conducted: these lines is less than the
- 2. Containment recirculation elevation of:
lines; containment to IRWST 2. IRWST bottom inside lines surface C-133 Amendment No. 110
Table 2.2.3-4 Inspections, Tests, Analyses, and Acceptance Criteria No. ITAAC No. Design Commitment Inspections, Tests, Analyses Acceptance Criteria 197 2.2.03.08c.xii 8.c) The PXS provides RCS makeup, xii) Inspections will be xii) Each upper level tap line boration, and safety injection during conducted of the CMT level has a downward slope of 2.4 design basis events. sensors (PXS-11A/B/D/C, - degrees from the centerline of 12A/B/C/D, - 13A/B/C/D, - the connection to the CMT to 14A/B/C/D) upper level tap the centerline of the lines. connection to the standpipe.
198 2.2.03.08c.xiii 8.c) The PXS provides RCS makeup, xiii) Inspections will be xiii) These surfaces are boration, and safety injection during conducted of the surfaces in the stainless steel.
design basis events. vicinity of the containment recirculation screens. The surfaces in the vicinity of the containment recirculation screens are the surfaces located above the bottom of the recirculation screens up to and including the bottom surface of the plate discussed in Table 2.2.3-4, item 8.c.vii, out at least 8 ft, 3 in perpendicular to the front and at least 7 feet to the side of the face of the screens.
199 2.2.03.08c.xiv 8.c) The PXS provides RCS makeup, xiv) Inspection will be xiv) A report exists and boration, and safety injection during conducted of the excore (source concludes that the aluminum design basis events. range, intermediate range, and surfaces of the excore power range) detectors. detectors are encased in a watertight stainless steel or titanium housing.
200 2.2.03.08d 8.d) The PXS provides pH adjustment Inspections of the pH adjustment pH adjustment baskets exist, of water flooding the containment baskets will be conducted. with a total calculated volume following design basis accidents. 560 ft3.
The pH baskets are located below plant elevation 107 ft, 2 in.
201 2.2.03.09a.i 9.a) The PXS provides a function to i) A flow test and analysis for i) The calculated flow cool the outside of the reactor vessel each IRWST drain line to the resistance for each IRWST during a severe accident. containment will be conducted. drain line between the IRWST The test is initiated by opening and the containment is isolation valves in each line. 4.44 x 10-6 ft/gpm2.
Test fixtures may be used to simulate squib valves.
C-138 Amendment No. 110