ND-18-0313, Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.3.06.09a.i (Index Number 372)

Unit 4 - ITAAC Closure Notification on Completion of ITAAC 2.3.06.09a.i (Index Number 372)

ML18120A270
Person / Time
Site:	Vogtle
Issue date:	04/27/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.3.06.09a.i, ND-18-0313
Download: ML18120A270 (7)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell APR 2 7 2018 myox@southernco.com Docket Nos.: 52-025 52-026 ND-18-0313 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 and Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.3.06.09a.i flndex Number 3721 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 and Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.09a.i [Index Number 372] for verifying that the Normal Residual Heat Removal System provides for temperature and overpressure protection during shutdown operations. The closure process for this ITAAC is based on the guidance described in Nuclear Energy Institute (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 G. Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox' Regulatory Affairs Director Vogtle 3 &4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 2.3.06.09a.i [Index Number 372]

MJY/RAS/amw

U.S. Nuclear Regulatory Commission ND-18-0313 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A. Bost (w/o enclosures)

Mr. M. D. Rauckhorst (w/o enclosures)

Mr. M. D. Meier Mr. D. H. Jones (w/o enclosures)

Mr. D. L. McKlnney Mr. M. J. Vox Mr. D. L. Fulton Mr. J. B. Klecha Mr. G. Chick Mr. 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.L06 File AR.01.02.06 cc:

Nuclear Regulatory Commission Mr. W. Jones (w/o enclosures)

Ms. J. M. Heisserer Mr. C. P. Patel Mr. M. E. Emstes 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 Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0313 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. OrlanI (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. Kernlzan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch BIngham

U.S. Nuclear Regulatory Commission ND-18-0313 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0313 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 2.3.06.09a.i [Index Number 372]

U.S. Nuclear Regulatory Commission ND-18-0313 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment:

9.a) The RNS provides LTOP for the RCS during shutdown operations.

Inspections. Tests. Analyses:

i) Inspections will be conducted on the lowtemperature overpressure protection relief valves to confirm that the capacities of the vendor code plate ratings are greater than or equal to system relief requirements.

Acceptance Criteria:

i) The rated capacities recorded on the valves' vendor code plates are not less than the flow required to provide low-temperature overpressure protection for the RCS, as determined by the LTOPS evaluation based on the pressure-temperature curves developed for the as-procured reactor vessel material.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Normal Residual Heat Removal System (RNS) provides Low Temperature Overpressure Protection (LTOP) for the Reactor Coolant System (RCS) during shutdown operations. This ITAAC performs inspections on the LTOP reliefvalves to confirm that the capacities of the vendor code plate ratings are greater than or equal to system relief requirements.

The Unit 3 and 4 RNS Suction Pressure Relief Valves, RNS-PL-V020 and RNS-PL-V021 (hereafter, RNS relief valves) are arranged per Figure 2.3.6-1 of Appendix C ofthe Vogtle Combined Licenses. Updated Final Safety Analysis Report (UFSAR) Table 5.4-17 and valve datasheets (Reference 1) document the nominal relieving capacity for the RNS relief valves. An LTOPS analysis (evaluation), which is based on the pressure-temperature curves developed for the as-procured reactor vessel material and considers worst case RCS mass or heat input, provides the basis for the RNS relief valves flow capacities.

As documented in inspection report SVO-RNS-ITR-001 (Reference 1), an inspection ofthe RNS relief valves' Quality Release &Certificate of Conformance documentation (CoC) was performed. The CoC documentation included photographs of the RNS relief valves' vendor code plates, demonstrating the valves meet the ITAAC acceptance criteria. The RNS relief valves' flow capacity recorded on each American Society of Mechanical Engineers (ASME)

Code plate was certified by ASME through the National Board of Boiler and Pressure Vessel (B&PV) Inspectors (NBBPVI). Subsection NC-7700 ofthe ASME B&PV Code,Section III describes the methods required to certify the relief device capacityand determine a coefficient used in determining capacity in subsequently manufactured valves. The flow capacity for each RNS LTOP reliefvalve was calculated by a set of equations using the coefficient found in Subsection NC-7700 and in NB-18, Pressure Relief Device Certification, from the NBBPVI.

Attachment A to this Enclosure documents the valves' vendor code plate capacity and combined total relief capacity.

U.S. Nuclear Regulatory Commission ND-18-0313 Enclosure Page 3 of 4 An Inspection report exists and concludes the rated capacities recorded on the valves' vendor code plates are not less than the flow required to provide low-temperature overpressure protection for the RGB, as determined by the LTOPS evaluation based on the pressure-temperature curves developed for the as-procured reactor vessel material.

ITAAC Finding Review In accordance with plant procedures for ITAAC 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. The ITAAC completion review is documented in the Unit 3 and Unit 4 ITAAC Completion Package for ITAAC 2.3.06.09a.i (References 2 and 3, respectively) and is available for NRC review.

ITAAC ComDietion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.06.09a.i was performed for Vogtle Units 3 and 4 and that the prescribed acceptance criteria are 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 mspection)

1. SVO-RNS-ITR-001, Revision 1, "Inspection Report of the Low Temperature Overpressure Protection (LTOP) Relief Valve Comparing Rated Capacity and Set Pressure to LTOPs Evaluation Requirements, ITAAC 2.3.06.09a.i & ITAAC 2.3.06.09a.ii"

2. 2.3.06.09a.i-U3-CP-Rev0, ITAAC Completion Package

3. 2.3.06.09a.i-U4-CP-Rev0, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-18-0313 Enclosure Page 4 of 4 Attachment A The following table documentsthe vendor code plate capacityand combined relief capacityfor each RNS relief valve:

RNS Relief Valve Equipment No. Vaive Capacity

• Total Capacity

• Unit3RNS-PL-V020 53 1266 Unit3RNS-PL-V021 1213 Unit4RNS-PL-V020 53 1266 Unit4RNS-PL-V021 1213

• all values are gallons per minute (gpm)