ND-22-0520, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.02 (Index Number 178)
| ML22244A145 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/01/2022 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-22-0520 | |
| Download: ML22244A145 (5) | |
Text
A Southern Nuclear SEP O 1 2022 Docket No.:
52-026 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 4 7825 River Road Waynesboro, GA 30830 706-848-6926 tel ND-22-0520 1 O CFR 52.99(c)(1)
ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.02 [Index Number 1781 Ladies and Gentlemen:
In accordance with 1 O CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtle Electric Generating Plant (VEGP)
Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c. i.02
[Index Number 1781, for verifying the accumulator tank injection line flow resistance values. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is endorsed by the NRC in Regulatory Guide 1.215.
This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company (SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 1 O CFR 52.99.
If there are any questions, please contact Kelli Roberts at 706-848-6991.
Respectfully submitted,
~(ov,W-Mv Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
JMC/DLW/sfr Vogtle Electric Generating Plant (VEGP) Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.02 [Index Number 1781
U.S. Nuclear Regulatory Commission ND-22-0520 Page 2 of 2 cc:
Regional Administrator, Region II Director, Office of Nuclear Reactor Regulation (NRR)
Director, Vogtle Project Office NRR Senior Resident Inspector - Vogtle 3 & 4
U.S. Nuclear Regulatory Commission ND-22-0520 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-22-0520 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 IT AAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.02 [Index Number 178]
U.S. Nuclear Regulatory Commission ND-22-0520 Enclosure Page 2 of 3 IT AAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.
Inspections/Tests/ Analyses i) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve(s) in the line being tested. Test fixtures may be used to 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.
Acceptance Criteria i) The injection line flow resistance from each source is as follows:
- 2. Accumulators:
The calculated flow resistance between each accumulator and the reactor vessel is~ 1.47 x 10-5 ft/gpm 2 and::; 1.83 x 10-5 ft/gpm 2.
ITAAC Determination Basis Multiple ITAAC were performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This ITAAC performed a low pressure injection test and analysis on the injection lines between each accumulator (PXS-MT-01 A/B) and the reactor vessel to calculate the flow resistance on each line.
Performance tests were conducted in accordance with the Unit 4 preoperational test procedure 4-PXS-ITPP-502 (Reference 1) to demonstrate that the flow path from each accumulator to the reactor vessel has a flow resistance ~ 1.47 x 10-5 ft/gpm 2 and ::; 1.83 x 10-5 ft/gpm 2.
Each accumulator was initially filled with water while measuring the volume of water added and tank level to establish a volume verses level correlation. The test was accomplished by partially filling each accumulator with water and pressurizing with nitrogen, opening the associated accumulator discharge isolation valve, and blowing down each tank through the Direct Vessel Injection (DVI) flow path with all valves in these lines open, while measuring accumulator tank level and pressure during the test period. Sufficient flow was provided to fully open the check valves. The constant value for flow resistance was calculated based on the test duration, total head loss, and total volume change from the change in measured tank level, adjusted for measurement uncertainty, and compared to the acceptance criteria. The accumulator design and flow resistance calculation required the check valves to be fully open as was demonstrated by a flow rate of~ 1614 gpm. The flow rates for each accumulator were 2367 gpm for Accumulator A and 2269 gpm for Accumulator B (reference 2).
U.S. Nuclear Regulatory Commission ND-22-0520 Enclosure Page 3 of 3 The Unit 4 flow resistance was calculated to be 1.63 x 10-5 ft/gpm 2 for Accumulator A, PXS-MT-01 A, flow path and was 1.72 x 10-5 ft/gpm 2 for Accumulator B, PXS-MT-01 B, flow path. The Unit 4 test results were documented in reference 2 and confirmed that the calculated injection line flow resistance between each Accumulator and the reactor vessel was 2: 1.47 x 10-5 ft/gpm2 and :s: 1.83 x 10-5 ft/gpm 2.
References 1 and 2 are available for NRC inspection as part of the ITAAC 2.2.03.08c.i.02 Completion Package (Reference 3).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there were no relevant ITAAC findings associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.i.02 (Reference 3) and is available for NRC review.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.i.02 was performed for VEGP Unit 4 and that the prescribed acceptance criteria were met.
Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.
References (available for NRC inspection)
- 1. 4-PXS-ITPP-502, Rev 0, "PXS Accumulator Mapping and Line Resistance Test"
- 2. SV4-PXS-ITR-800178, Rev 0, ITAAC Technical Report, "Unit 4 Recorded Results of PXS Accumulator Injection Line Flow Resistance: ITAAC 2.2.03.0Sc.i.02"
- 3. 2.2.03.08c.i.02-U4-CP-Rev0, "ITAAC Completion Package"