ND-18-0691, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08c.viii (Index Number 193)
| ML18149A395 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 05/25/2018 |
| From: | Yox M Southern Nuclear Operating Co |
| To: | Document Control Desk, Office of New Reactors |
| References | |
| ND-18-0691 | |
| Download: ML18149A395 (7) | |
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I MichaelJ. Yox 7825 River Road jOUtn0rn iNUCl03r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle3 &4 706-848-6459 tel MAY 2 5 2018 Docket Nos.:
52-025 52-026 410-474-8587 cell myox@southernco.com ND-18-0691 10CFR 52.99(c)(3)
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.03.08c.viii [Index Number 1931 Ladies and Gentlemen:
Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of May 10, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.viii [Index Number 193] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan for completing this ITAAC. Southern Nuclear Operating Company will, at a later date, provide additional notifications for ITAACthat have not been completed 225-days prior to initial fuel load.
This notification is informed by 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. In accordance with NEI 08-01, this notification includes ITAAC for which required inspections, tests, or analyses have not been performed or have been only partially completed. All ITAAC will be fully completed and all Section 52.99(c)(1) ITAAC Closure Notifications will be submitted to NRC to support the Commission finding that all acceptance criteria are met prior to plant operation, as required by 10 CFR 52.103(g).
This letter contains no new NRC regulatory commitments.
Ifthere are any questions, please contact Tom Petrak at 706-848-1575.
Respectfully submitted.
Michael J. Yox Regulatory Affairs l^rector Vogtle 3 &4
Enclosure:
Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.viii [Index Number 193]
MJY/KJD/amw
U.S. Nuclear Regulatory Commission ND-18-0691 Page 2 of 3 To:
Southern Nuclear Operating Company/ Georgia Power Company M
M M
M M
M M
M M
M D. A. Bost (w/o enclosures)
M. D. Rauckhorst (w/o enclosures)
M. D. Meier
. D. H. Jones (w/o enclosures)
D. L. McKinney M. J. Vox D. L. Fulton J. B. Klecha G. Chick F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. C. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. C. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.LOG File AR.01.02.06 cc:
Nuclear Reaulatorv Commission Mr. W. Jones (w/o enclosures)
Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Ernstes Mr. G. J. Khouri Mr. T. E. Chandler Ms. S. E. Temple Ms. P. Braxton Mr. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Ms. N. C. Coovert Oolethoroe Power Corporation Mr. R. B. Brinkman
U.S. Nuclear Regulatory Commission ND-18-0691 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton 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. D. Hawkins Ms. J. Monahan Mr. J. L. Coward Ms. N. E. Deangelis Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.
Dr. W. R. Jacobs, Jr., Ph.D., CDS 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, Balch Bingham
U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0691 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08c.viii [Index Number 193]
U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment:
B.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.
Insoections/Tests/Analvses:
viii) Inspections of the IRWST and containment recirculation screens will be conducted. The inspections will include measurements of the pockets and the number of pockets used ineach screen. The pocket frontal face area is based on a widthtimes a height. The width is the distance between pocket centerlines for pockets located beside each other. The height is the distance between pocket centerlines for pockets located above each other. The pocket screen area is the total area of perforated plate inside each pocket; this area will be determined by inspection of the screen manufacturing drawings.
Acceptance Criteria:
viii) The screens utilize pocketswith a frontal face area ofs 6.2 in^ and a screen surface area ^
140 in^ per pocket. IRWST Screens Aand Beach have a sufficient number of pockets to provide a frontal face area s 25 ft^, a screen surface area ^ 575 ft^, and a screen mesh size of 2 0.0625 inch. IRWST Screen C has a sufficient number of pockets to provide a frontal face area s 50 ft^, a screen surface area s 1150 ft^, and a screen mesh size ^ 0.0625 inch. Each containment recirculation screen has a sufficient number of pockets to provide a frontal face area s 105 ft^, a screen surface area ^ 2500 ft^, and a screen mesh size ^ 0.0625 inch.
A debris curb exists in front of the containment recirculation screens which is s 2 ft above the loop compartment floor.
The bottoms of the IRWST screens are located > 6 in above the bottom of the IRWST.
ITAAC Completion Description Multiple ITAAC are performed to demonstratethat the Passive Core Cooling System (PXS) provides ReactorCoolant System (RCS) makeup, boration, and safety injection during design basis events. The subject ITAAC requires an inspectionof the In Containment Refueling Water StorageTank (IRWST) screens and containment recirculation screens to verify the frontal face area, screen surface area, and screen mesh size meet the acceptance criteria as shown in Attachment A. Inaddition, inspections are performed to verify the debris curb infront of the containment recirculation screens is s 2 ft above the loop compartment floor, and the bottoms of the IRWST screens are located > 6 in above the bottom of the IRWST.
Following fabrication of the IRWST and containment recirculation screens, the vendor determined the pocket screen area based upon the screen manufacturing drawings. The screen mesh size, which is the hole diameters in the perforated plates, are measured during production ofthe plates. The results are documented inthe quality data package forthe screens (References 2 and 3) and shown in Attachment A.
U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 3 of 4 Following installation of the IRWSTscreens, containment recirculation screens, and debris curb, inspections are performed in accordance with inspection procedure XYZ (Reference 1) to determine the pocket frontal face area and number of pockets in order to calculate the frontal face area of each screen. The inspection procedure utilizes guidance provided in Electric Power Research Institute (EPRI) Report TR-017218-R1 (Reference 4) to determine the number of pockets to measure. The inspection procedure also specifies required inspections and measurement locations to determine the distance from the bottom of the IRWST screens to the IRWST floor, the distance fromthe top of the containment recirculation screen debris curb to the loop compartmentfloor, and verification that the debris curb in front ofthe containment recirculation screens is installed in its proper locationand final configuration in accordance with design specifications. Measurements are taken using survey equipment in accordance with site survey and measurement procedures (Reference 7).
The total frontal face area of each screen and total screen surface area is calculated based on the width and height centerline measurements between pockets,the numberofpockets installed in each screen, and the screen area inside each pocket. The width and height measurement is the distance between pocketcenterlinesfor pockets located beside each other and above each other, respectively. Thescreen area inside each pocket isdetermined based on the screen manufacturing drawings.
The results are documented inthe Unit 3 and Unit 4 Principal Closure Documents XXX and YYY (References 5and 6, respectively) and shown in Attachment A, which meets the ITAAC acceptance criteria.
References 1,2, 3, 5 and 6 are available for NRG inspection as partofthe Unit 3 and Unit 4 ITAAC 2.2.03.08c.viii Completion Packages (References 8 and 9, respectively).
List of ITAAC Findings In accordance with plant procedures for ITAAC completion. Southern Nuclear Operating Company (SNC) performed a review of all ITAAC findings and associated corrective actions.
This reviewfound there are no relevant ITAAC findings associated with this ITAAC.
References ^available for NRG inspection)
- 1. Inspection Procedure XYZ
- 2. SV3-MY03-VQQ-001, Rev. X, "Quality Release and Data PackageVogtle 3 IRWST &
Containment Recirculation Screeens"
- 3. SV4-MY03-VQQ-001, Rev. X, "Quality Release and Data PackageVogtle 4 IRWST &
Containment Recirculation Screeens"
- 4. EPRI Report TR-017218-R1, "Guideline for Sampling in theCommercial-Grade Item Acceptance Process," January 1999
- 5. XXX Principal Closure Document (Unit 3) 6.
YYY Principal Closure Document (Unit 4) 7.
26139-000-4MP-T81C-N3201, "Construction Surveying" 8.
2.2.03.08c.viii-U3-CP-Rev 0, ITAACCompletion Package 9.
2.2.03.08c.viii-U4-CP-Rev 0, ITAAC Completion Package
- 10. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10CFR Part 52"
U.S. Nuclear Regulatory Commission ND-18-0691 Enclosure Page 4 of 4 Attachment A IRWST and Containment Recirculation Screen Areas and Measured Clearances +
Component Name*
Tag No.*
Pocket Frontal Face Area (AC > 6.2 in^)
Screen Surface Area per Pocket (AC > 140 in^)
Screen Mesh size (AC < 0.0625 inch)
Total Calculated Frontal Face Area Total Calculated Screen Surface Area IRWST Screen A PXS-MY-Y01A X.X in^
X.X in^
X.X inch X.Xft2 (AC>25ft2) x.xft^
(AC>575ft2)
IRWST Screen B PXS-MY-Y01B X.X in^
X.X in^
X.X inch X.Xft2 (ACs25ft2) x.xft2 (AC>575ft2)
IRWST Screen C PXS-MY-Y01C X.Xin^
X.X in^
X.X inch x.xft^
(AC>50ft2) x.xft^
(ACSllSOft^)
Containment Recriculation Screen A PXS-MY-Y02A X.X in^
X.X in^
X.X inch x.xft^
(AC> 105ft2) x.xft^
(ACS 2500 ft2)
Containment Recricuiation Screen B PXS-MY-Y02B X.X in^
X.X in^
X.X inch x.xft^
(ACS lOSft^)
x.xft^
(ACS 2500 ft2)
Minimum measured distance from the top of the debris curb infront of the containment recirculationscreens to the loopcompartment floor is X.X ft. (AC s 2 ft)
Minimum measured distance from the bottoms of the IRWST screens to the floor of the IRWST (AC s 6 in).
IRWST Screen A bottom is X.X inch above the fioor iRWST Screen B bottom is X.X inch above the floor IRWST Screen C bottom is X.X inch above the floor
- Excerpt from COL Appendix C, Table 2.2.3-1
+ Results are Unit specific