ND-18-0314, ITAAC Closure Notification on Completion of ITAAC 2.3.06.09a.ii (Index Number 373)

ITAAC Closure Notification on Completion of ITAAC 2.3.06.09a.ii (Index Number 373)

ML18117A424
Person / Time
Site:	Vogtle
Issue date:	04/26/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0314
Download: ML18117A424 (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 myox@southernco.com APR 7 6 2018 Docket Nos.: 52-025 52-026 ND-18-0314 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.ii [Index Number 3731 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.ii [Index Number 373] 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.ii [Index Number 373]

MJY/RAS/amw

U.S. Nuclear Regulatory Commission ND-18-0314 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. McKinney Mr. M. J. Yox 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 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 Oalethoroe Power Corporation Mr. R. B. Brinkman

U.S. Nuclear Regulatory Commission ND-18-0314 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse 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. 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-0314 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0314 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion of ITAAC 2.3.06.09a.ii [Index Number 373]

U.S. Nuclear Regulatory Commission ND-18-0314 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment:

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

Inspections. Tests. Analyses:

II) Testing and analysis In accordance with the ASME Code Section III will be performed to determine set pressure.

Acceptance Criteria:

II) A report exists and concludes that the reliefvalves open at a pressure not greater than the set pressures 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 testing and analysis to confirm that the relief valves open at a pressure not greater than the set pressures required to provide low-temperature overpressure protection for the RCS.

The Unit 3 and 4 RNS Suction Pressure Relief Valves, RNS-PL-V020 and RNS-PL-V021 (hereafter, RNS reliefvalves) are arranged per Figure 2.3.6-1 of Appendix C of the Vogtle Combined Licenses. The nominal set pressures for the RNS relief valves are based on the reactor vessel low-temperature pressure limit (I.e., 621 pounds per square Inch gauge/pslg)

(Reference 1). The reactor vessel pressure and temperature limits are based on API 000 generic pressure temperature limits report and plant-specific reactor baseline test reports.

Updated Final Safety Analysis Report (UFSAR) Table 5.4-17 and valve datasheets (Reference

1) document the set pressure for the RNS reliefvalves. These values were analyzed In an LTOPS evaluation and confirm the RNS relief valves satisfy the bounding UFSAR shutdown pressure and temperature limits.

As documented In Inspection report SVO-RNS-ITR-001 (Reference 1), testing of the RNS relief valves was performed In accordance with American Society of Mechanical Engineers (ASME)

Boilerand Pressure Vessel (B&PV) Code,Section III, Subsection NC-7400, "Set Pressures of Pressure Relief Devices," and NC-7512.2, "Safety Valve Operating Requirements - Set Pressure Tolerance." Testing Included three lift check tests performed by the manufacturer for each RNS relief valve and the values were recorded In valve test reports. Comparison of the lift check test results to the LTOPS evaluation confirm the RNS relief valves meet the required set pressure acceptance criteria and confirm the set pressures will provide LTOPfor the RCS. The Attachment to this Enclosure contains the set pressure and lift check test results for each RNS relief valve.

U.S. Nuclear Regulatory Commission ND-18-0314 Enclosure Page 3 of 4 In accordance with vendor quality assurance program and ASME requirements, testing was conducted to determine the pressures at which the RNS relief valves open. These tests were recorded in valve test reports and the set pressures are recorded on the valves' vendor code plates. An inspection report exists and concludes the test results were visually inspected and compared to the LTOPS evaluation (which was based on the pressure-temperature curves developed for the as-procured reactor vessel material) to verify the relief valves open at a pressure not greater than the set pressures required to provide low temperature overpressure protection for the RCS.

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 finding review is included in the Vogtle Units 3 and 4 ITAAC Completion Packages for ITAAC 2.3.06.09a.ii (References 2 and 3, respectively) and available for NRC inspection.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.06.09a.ii was performedfor Vogtle Units 3 and 4 and that the prescribed acceptance criteria are met.

Systems, structures, and components verified as part ofthis ITAAC are being maintained in their as-designed, ITAAC compliant condition inaccordance with approved plant programsand procedures.

References (available for NRC inspection)

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

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

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

U.S. Nuclear Regulatory Commission ND-18-0314 Enclosure Page 4 of 4 ATTACHMENT The following table documents the set pressure and test results for each relief valve; RNS Relief Valve Name Piate Set Test 1* Test 2* Test 3*

Equipment No. Pressure*

Unit 3 RNS-PL-V020 470 474 474 474 Unit 3 RNS-PL-V021 500 504 505 505 Unit 4 RNS-PL-V020 470 473 473 473 Unit 4 RNS-PL-V021 500 505 505 506

• all values are pounds per square inch gage (psig)