ND-19-1396, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.xii (Index Number 197)
| ML19354A548 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 12/19/2019 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ND-19-1396 | |
| Download: ML19354A548 (7) | |
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Southern Nuclear DEC 1 9 2019 Docket No.:
52-025 Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4 7825 River Road Waynesboro, GA 30830 706-848-6459 tel ND-19-1396 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 2.2.03.08c.xii (Index Number 1971 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 ITAAC 2.2.03.08c.xii
[Index Number 197] for verifying that the downward slope of the CMT level sensors (PXS-11A/B/D/C, PXS -12A/B/C/D, PXS -13A/B/C/D, PXS -14A/B/C/D) upper level tap lines each have a downward slope of > 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe. 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 was 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 Tom Petrak at 706-848-1575.
Respectfully submitted, Michael J. Vox Regulatory Affairs Director Vogtle 3 & 4
Enclosure:
MJY/WLP/sfr Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.xii [Index Number 197]
U.S. Nuclear Regulatory Commission ND-19-1396 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (w/o enclosures)
Mr. D. L. McKinney (w/o enclosures)
Mr. M. D. Meier (w/o enclosures)
Mr. D. H. Jones (w/o enclosures)
Mr. G. Chick Mr. M. Page Mr. P. Martino Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:
Nuclear Requlatorv Commission Mr. W. Jones (w/o enclosures)
Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. B. J. Kemker Ms. N. C. Coovert M
M M
M M
M M
M M
. C. Welch J. Gaslevic
. V. Hall G. Armstrong Ms. T. Lamb M. Webb T. Fredette C. Weber S. Smith C. Santos Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen
U.S. Nuclear Regulatory Commission ND-19-1396 Page 3 of 3 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. 0. Durham (w/o enclosures)
Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hesler, 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 Ms. 8. W. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham
U.S. Nuclear Regulatory Commission ND-19-1396 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-1396 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.2.03.08c.xii [Index Number 197]
U.S. Nuclear Regulatory Commission ND-19-1396 Enclosure Page 2 of 4 ITAAC Statement Design Commitment:
8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.
Inspections. Tests. Analvses:
xii) Inspections will be conducted of the CMT level sensors (PXS-11A/B/D/C, - 12A/B/C/D, -
13A/B/C/D, - 14A/B/C/D) upper level tap lines.
Acceptance Criteria:
xii) Each upper level tap line has a downward slope of s 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe.
ITAAC Completion Description Multiple ITAAC are performed to demonstrate that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events.
This ITAAC requires inspections to be performed of each Core Makeup Tank (CMT) level sensors (PXS-11 A/B/D/C, PXS -12A/B/C/D, PXS -13A/B/C/D, PXS -14A/B/C/D) upper level tap lines to verify that each upper level tap line has a downward slope of s 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe.
An inspection of the installed CMT level sensors upper level tap lines was performed in accordance with the site walkdown inspection procedure (Reference 1). The inspection was performed to measure the slope of each upper level tap line from the centerline of the connection to the CMT to the centerline of the connection to the standpipe to ensure it meets the acceptance criteria. The slope measurements were obtained using Measurement and Test Equipment (M&TE) in accordance the site M&TE procedure (Reference 2).
The inspection results are shown in Attachment A and documented in the IT/\\AC Technical Report (ITR), Unit 3 Inspection of the PXS CMT Upper Level Tap Lines (Reference 3), which confirms that each upper level tap line has a downward slope of S; 2.4 degrees from the centerline of the connection to the CMT to the centerline of the connection to the standpipe and meets the IT/\\AC acceptance criteria.
References 1 through 3 are available for NRC inspection as part of the Unit 3 ITAAC 2.2.03.08c.xii Completion Package (Reference 4).
List of ITAAC Findings In accordance with plant procedures for IT/\\AC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found that there are no relevant ITAAC findings associated with this ITAAC.
U.S. Nuclear Regulatory Commission ND-19-1396 Enclosure Page 3 of 4 ITAAC Completion Statement Based on the above information, SNO hereby notifies the NRG that ITAAC 2.2.03.08c.xii 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 NRG inspection)
- 1. NCSP02-24, ITAAC Support Activities, Revision 3
- 2. 26139-000-4MP-T81C-N7102, Control of Measuring and Test Equipment, Revision 2
- 3. SV3-PXS-ITR-800197, Unit 3 Inspection of the PXS CMT Upper Level Tap Lines: ITAAC 2.2.03.08c.xii, Revision 0
- 4. 2.2.03.08c.xii-U3-CP-Rev0, Completion Package
- 5. SV3-PXS-M6-001, Piping and Instrumentation Diagram Passive Core Cooling System, Revision 5
U.S. Nuclear Regulatory Commission ND-19-1396 Enclosure Page 4 of 4 Attachment A GMT level sensors upper level tap line downward slope (Acceptance criteria s 2.4 degrees)
GMT GMT Level Sensor+
GMT Level Sensor Standpipe++
Upper Level Tap Line+
As-built downward slope (degrees)-i-++
PXS-MT-02A PXS-11A/C PXS-MY-Y11A PXS-PL-L082A 4.0 (max) - 2.5 (min)
PXS-11B/D PXS-MY-Y12A PXS-PL-L086A 5.2 (max) - 2.7 (min)
PXS-13A/C PXS-MY-Y13A PXS-PL-L092A 4.9 (max) - 2.5 (min)
PXS-13B/D PXS-MY-Y14A PXS-PL-L096A 4.3 (max) - 2.6 (min)
PXS-MT-02B PXS-12A/C PXS-MY-Y12B PXS-PL-L082B 5.7 (max) - 2.8 (min)
PXS-12B/D PXS-MY-Y11B PXS-PL-L086B 3.9 (max) - 2.6 (min)
PXS-14A/C PXS-MY-Y14B PXS-PL-L092B 5.0 (max) - 2.5 (min)
PXS-14B/D PXS-MY-Y13B PXS-PL-L096B 6.5 (max) - 2.6 (min)
- Excerpt from COL Appendix C Table 2.2.3-1
+ Reference 5, Piping & Instrumentation Drawing SV3-PXS-M6-001 (available for NRC inspection)
++ Excerpt from UFSAR Table 3.2-3
+++ Reference 3, PCD, SV3-PXS-ITR-800197, Attachment A