ND-21-0306, ITAAC Closure Notification on Completion of ITAAC 2.3.07.07c (Index Number 408)
| ML21286A779 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 10/13/2021 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-21-0306 | |
| Download: ML21286A779 (9) | |
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Southern Nuclear OCT 1 3 2021 Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel Docket Nos.: 52-025 ND-21-0306 10CFR 52.99(c)(1)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.07.07c findex Number 4081 Ladies and Gentlemen; In accordance with 10 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 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.07.07c [Index Number 408], for verifying check valve exercise testing requirements, pump flowrate, and controls and displays in the main control room (MCR) of the Spent Fuel Pool Cooling System.
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 10 CFR 52.99.
If there are any questions, please contact Kelli Roberts at 706-848-6991.
Respectfully submitted, Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.07.07c [Index Number 408]
MJY/DLW/sfr
U.S. Nuclear Regulatory Commission ND-21-0306 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKlnney Mr. H. Nieh Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Ms. J.M. Coleman Mr. C. T. Defnall Mr. C. E. Morrow Mr. K. J. Drudy Mr. J. M. Fisher Mr. R. L. Beiike Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 Nuclear Reoulatorv Commission Ms. M. Bailey M
M Ms. A. Veil M
M M
M Ms. N. C. Coovert M
M M
M M
M M
M M
M M
M M
M M
. M. King G. Bowman
. C. P. Patel G. J. Khouri
. C. J. Even
. B. J. Kemker C. Welch J. Gaslevic O. Lopez-Santiago G. Armstrong M. Webb T. Fredette C. Santos B. Davis
. J. Vasquez
. J. Eargle
. E. Davidson
. T. Fanelli Ms. K. McCurry
. J. Parent
. B. Griman
. V. Hall
U.S. Nuclear Regulatory Commission ND-21-0306 Page 3 of 3 Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)
Mr. D. C. Durham (w/o enclosures)
Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.
Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Batch BIngham
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 1 of 6 Southern Nuclear Operating Company ND-21-0306 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.07.07c [Index Number 408]
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 2 of 6 ITAAC Statement Design Commitment 7c) The SFS provides check valves in the drain line from the refueling cavity to prevent flooding of the refueling cavity during containment flooding.
- 8. The SFS provides the nonsafety-related function of removing spent fuel decay heat using pumped flow through a heat exchanger.
- 9. Safety-related displays identified in Table 2.3.7-1 can be retrieved in the MCR.
- 10. Controls exist in the MCR to cause the pumps identified in Table 2.3.7-3 to perform their listed functions.
I nspections/Tests/Analvses Exercise testing of the check valves with active safety-functions identified in Table 2.3.7-1 will be performed under pre-operational test pressure, temperature and flow conditions.
ii) Testing will be performed to confirm that each SFS pump provides flow through its heat exchanger when taking suction from the SFP and returning flow to the SFP.
Inspection will be performed for retrievabillty of the safety-related displays in the MCR.
Testing will be performed to actuate the pumps identified in Table 2.3.7-3 using controls in the MCR.
Inspection will be performed for retrievabillty in the MCR of the displays identified in Table 2.3.7-3.
Acceptance Criteria Each check valve changes position as indicated on Table 2.3.7-1.
ii) Each SFS pump produces at least 900 gpm through Its heat exchanger.
Safety-related displays identified in Table 2.3.7-1 can be retrieved in the MCR.
Controls in the MCR cause pumps identified in Table 2.3.7-3 to perform the listed functions.
Displays of the SFS parameters identified in Table 2.3.7-3 are retrieved in the MCR.
ITAAC Determination Basis Testing is performed to demonstrate that the Spent Fuel Pool Cooling System (SFS) provides check valves in the drain line from the refueling cavity to prevent flooding of the refueling cavity during containment flooding, verifies the SFS provides the nonsafety-related function of
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 3 of 6 removing spent fuel decay heat using pumped flow through a heat exchanger, and that controls exist in the Main Control Room (MCR) to cause the pumps identified in Table 2.3.7-3 to perform their listed functions. Inspections are performed to verify that safety-related displays identified in Table 2.3.7-1 can be retrieved in the MCR and that displays of the SFS parameters identified in Table 2.3.7-3 can be retrieved in the MCR.
Each check valve changes position as indicated on Table 2.3.7-1.
Testing was performed in accordance with 3-SFS-ITPP-502 (Reference 2) using Unit 3 Work Order 1071755 (Reference 1) with the initial conditions of the refueling cavity drain isolation valve closed, with water level in the refueling cavity at a level of approximately 107 ft. elevation (approximately 3 inches below the reactor vessel flange), temporary drain hose attached to the cavity drain with a valve attached and routed to a floor drain, and non-intrusive valve disk monitoring installed on SFS-PL-V071 and SFS-PL-V072. The original testing was to be performed at approximately 28 ft. above the reactor vessel flange. Performing the test with water level 3 inches below the reactor vessel flange is conservative because the head of water is much less. The refueling cavity drain isolation valve and the temporary valve on the drain hose were opened to initiate flow and both check valves were verified to open by flow and the non-intrusive monitoring instruments. The temporary valve on the drain hose was closed to stop flow and both check valves were verified to close using the non-intrusive monitoring instruments. This was documented in ITAAC Technical Report SV3-SFS-ITR-800408 (Reference 3). This flow path is depicted on Piping and Instrument Drawing SV3-SFS-M6-001.
This testing verified that for Unit 3, each check valve changed position as indicated on Combined Operating License (COL) Appendix C Table 2.3.7-1 (Attachment A).
ii) Each SFS pump produces at least 900 oom through its heat exchanger.
Testing was performed in accordance with 3-SFS-ITPP-502 (Reference 2) using Unit 3 Work Order 1071755 (Reference 1). The test was conducted by running each of the SFS pumps individually, taking suction from and returning flow to the Spent Fuel Pool (SFP). Once steady flow was established, instrument readings were taken at the respective SFS pump discharge flow sensor, recorded in the test procedure and corrected for measurement uncertainty. The test was performed using multiple system alignments with the demineralizers in/out of service and single and dual pump configurations.
The Unit 3 A SFS pump (SFS-MP-01A) produced a minimum flow of 1397 gallons per minute (gpm) for all alignments and the B SFS pump (SFS-MP-01B) produced a minimum flow of 1418 gpm for all alignments during testing. This was documented in ITAAC Technical Report SV3-SFS-ITR-801408 (Reference 4).
The Unit 3 test results (Reference 4) confirmed that each SFS pump produced at least 900 gpm through its heat exchanger when taking suction from and returning flow to the SFP.
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 4 of 6 Safety-related displays identified in Table 2.3.7-1 can be retrieved in the MGR.
The inspection was performed in accordance with Unit 3 component test package SNC922101 (Reference 5) to confirm that safety-related displays identified in COL Appendix C Table 2.3.7-1 (Attachment B) can be retrieved in the MGR.
The inspection visually confirmed that when each of the safety-related displays identified in Attachment B was summoned at the MGR Protection and Safety Monitoring System (PMS)
Visual Display Units (VDUs), the summoned safety-related display appears on the PMS VDU.
This was documented in ITAAG Technical Report SV3-SFS-ITR-802408 (Reference 6).
This confirmed that the safety-related displays identified in Table 2.3.7-1 can be retrieved in the Unit 3 MGR.
Controls in the MGR cause pumps identified in Table 2.3.7-3 to perform the listed functions.
Testing was performed in accordance with Unit 3 component test package SNG922101 (Reference 5) to verify controls in the MGR caused the pumps identified in GOL Appendix G Table 2.3.7-3 (Attachment G) to perform the listed functions.
Testing was performed by ensuring the SFS A Train was filled and vented and then it was started per the operating procedure in the MGR. The pump start was verified locally and documented in the test package. The test then ensured the SFS B Train was filled and vented and then it was started per the operating procedure in the MGR. The pump start was verified locally and documented in the test package. This was documented in ITAAG Technical Report SV3-SFS-ITR-803408 (Reference 7).
This confirmed that controls in the MGR cause pumps identified in Table 2.3.7-3 to perform the listed functions.
Displays of the SFS parameters identified in Table 2.3.7-3 were retrieved in the MGR.
The inspection was performed in accordance with Unit 3 component test package SNG922101 (Reference 5) to confirm that the displays identified in GOL Appendix G Table 2.3.7-3 (Attachment D) can be retrieved in the MGR.
The inspection visually confirmed that when each of the displays of parameters identified in Attachment D was summoned at a MGR workstation, the summoned plant parameter appeared on a display monitor at that MGR workstation. This was documented in ITAAG Technical Report SV3-SFS-ITR-804408 (Reference 8).
References 1 through 8 are available for NRG inspection along with Unit 3 ITAAG Gompletion Package (Reference 9).
List of ITAAC Findings In accordance with plant procedures for ITAAG completion, Southern Nuclear Operating Gompany (SNG) performed a review of all findings pertaining to the subject ITAAG and associated corrective actions. This review found there were no relevant ITAAG findings
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 5 of 6 associated with this ITAAC. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.07.07c (Reference 9) and is available for NRC review.
ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.07.07c was performed for VEGP Unit 3 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. Work Order 1071755, Rev. 0, "(ITAAC) Perform Preop Test 3-SFS-ITPP-502"
- 2. 3-SFS-ITPP-502, Rev 3.1, "Spent Fuel Pool Cooling System Flow Path Preoperational Test Procedure"
- 3. SV3-SFS-ITR-800408, Rev 0, ITAAC Technical Report, "Unit 3 Recorded Results of SFS Check Valves Position: ITAAC 2.3.07.07c Item 7c"
- 4. SV3-SFS-ITR-801408, Rev 0, ITAAC Technical Report, "Unit 3 Recorded Results of SFS Pump Flow: ITAAC 2.3.07.07c Item 8.ii"
- 6. SV3-SFS-ITR-802408, Rev 0, ITAAC Technical Report, "Unit 3 Recorded Results of MCR Safety-Related Displays: ITAAC 2.3.07.07c Item 9"
- 7. SV3-SFS-ITR-803408, Rev 0, ITAAC Technical Report, "Unit 3 Recorded Results of MCR Controls Start SFS Pumps: ITAAC 2.3.07.07c Item 10"
- 8. SV3-SFS-ITR-804408, Rev 0, ITAAC Technical Report, "Unit 3 Recorded Results of MCR SFS Parameter Displays: ITAAC 2.3.07.07c Item 11"
- 9. 2.3.07.07c-U3-CP-Rev0, "ITAAC Completion Package"
- 10. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"
U.S. Nuclear Regulatory Commission ND-21-0306 Enclosure Page 6 of 6 Attachment A
'Excerpt from COL Appendix 0 Table 2.3.7-1
'Component Name
'Tag No.
'Active Function Refueling Cavity Drain Line Check Valve SFS-PL-V071 T
ransfer Open Transfer Closed Refueling Cavity Drain Line Check Valve SFS-PL-V072 Transfer Open Transfer Closed Attachment B
'Excerpt from COL Appendix C Table 2.3.7-1
'Component Name
'Tag No.
'Safety-Related Display Spent Fuel Pool Level Sensor SFS-019A Yes Spent Fuel Pool Level Sensor SFS-019B Yes Spent Fuel Pool Level Sensor SFS-019C Yes Refueling Cavity Drain to SGS Compartment Isolation Valve SFS-PL-V031 Yes Refueling Cavity Drain to Containment Sump Isolation Valve SFS-PL-V033 Yes SFS Containment Floodup Isolation Valve SFS-PL-V075 Yes Attachment C
'Excerpt from COL Appendix C Table 2.3.7-3
'Component Name
'Tag No.
'Control Function SFS Pump A SFS-MP-01A Start SFS Pump B SFS-MP-01B Start Attachment D
'Excerpt from COL Appendix C Table 2.3.7-3
'Component Name
'Tag No.
'Display SFS Pump A SFS-MP-01A Yes (Run Status)
SFS Pump B SFS-MP-01B Yes (Run Status)
SFS Flow Sensor SFS-13A Yes SFS Flow Sensor SFS-13B Yes Spent Fuel Pool Temperature Sensor SFS-018 Yes Cask Loading Pit Level Sensor SFS-022 Yes