ND-18-0116, Vogtie, Unit 4, ITAAC Closure Notification on Completion of ITAAC 2.2.04.08a.ii (Index Number 236)

Vogtie, Unit 4, ITAAC Closure Notification on Completion of ITAAC 2.2.04.08a.ii (Index Number 236)

ML18037A885
Person / Time
Site:	Vogtle
Issue date:	01/31/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0116
Download: ML18037A885 (7)

Text

Michael J. Yox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tei 410-474-8587 cell myox@southernco.com JAN 3 12018 Docket No.: 52-026 ND-18-0116 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 4 ITAAC Closure Notification on Completion of ITAAC 2.2.04.08a.ii [Index Number 2361 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 Vogtie Electric Generating Plant (VEGP)

Unit 4 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.04.08a.ii [Index Number 236] for verifying that the steam generator system safety valves set pressure is less than 1305 psig. 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.

HP'/UOA/lA^V.^

Michael J. Yox Regulatory Affairs Director Vogtie 3&4

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.08a.ii [Index Number 236]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0116 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. Vox Mr. D. L. Fulton Mr. J. D. Williams 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. R. L. Belike Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reoulatorv 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. T. C. Brimfield Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Qqiethoroe Power Corporation Mr. R. B. Brinkman Munlcioai Eiectric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0116 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinahouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Mr. D. Hawkins Ms. 8. DITommaso 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-18-0116 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0116 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 4 Completion of ITAAC 2.2.04.08a.il [Index Number 236]

U.S. Nuclear Regulatory Commission ND-18-0116 Enclosure Page 2 of 4 ITAAC Statement Design Commitment:

8.a) The SGS provides a heat sink for the PCS and provides overpressure protection in accordance with Section III of the ASME Boiler and Pressure Vessel Code.

Inspections. Tests. Analvses:

ii) Testing and analyses in accordance with ASME Code Section III will be performed to determine set pressure.

Acceptance Criteria:

ii) A report exists to indicate the set pressure of the valves is less than 1305 psig.

ITAAC Determination Basis Multiple ITAAC are performed to demonstrate that the Steam Generator System (SGS) provides a heat sink for the Reactor Coolant System (PCS) and provides overpressure protection in accordance with Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC) (Reference 1). This ITAAC requires testing and analysis in accordance with Section III of the ASME Code be performed to ensure the set pressure of the SGS Safety Valves is less than 1305 psig.

Testing was performed on the SGS safety valves listed in combined license (COL) Appendix C, Table 2.2.4-1 (Attachment A). ASME B&PVC,Section III, NC-7400, "Set Pressures of Pressure Relief Devices," requires that at least one pressure relief device shall have a set pressure not greater than any ofthe components within the system, and NC-7512.2, "Safety Valve Operating Requirements - Set Pressure Tolerance," requires a maximum of 1% set pressure tolerance for pressures over 1000 psig. Three lift check tests were performed by the manufacturer for each SGS safety valve and the values were recorded on a valve test report.

The test results are documented in the valve test report included in Reference 2 and noted in Attachment A which shows the set pressure for each valve is less than 1305 psig and meets the ITAAC acceptance criteria.

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 included in the Vogtle Unit 4 ITAAC Completion Package for ITAAC 2.2.04.08a.ii (Reference 3) and available for NRC inspection.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.04.08a.ii was performedfor VEGP Unit 4 and that the prescribed acceptance criteriaare met.

U.S. Nuclear Regulatory Commission ND-18-0116 Enclosure Page 3 of 4 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. American Society of Mechanical Engineers Boiler& Pressure Vessel Code, Section 111,1998 Edition with 2000 Addenda

2. SV4-PV65-VQQ-001 Rev 1, "Quality Release and Certificate of Conformance for PV65 MSSV's"

3. 2.2.04.08a.ii-U4-CP-Rev 0, Completion Package for Unit 4 ITAAC 2.2.04.08a.ii [COL Index 236] (SGS Safety Valves Set Pressure)

U.S. Nuclear Regulatory Commission ND-18-0116 Enclosure Page 4 of 4 Attachment A Steam Generator System Steam Safety Valves Quality Set Release and Test Test Test

""Equipment Name *Tag No. Serial No. Pressure 1 2 3 Certificate of Conformance (psig)

Main Steam Safety SGS-PL-V030A Valve SG01 JX-16-CN0023 SV4-PV65-VQQ- 1175 1182 1176 1185 Main Steam Safety JX-16-CN0029 001 1181 1184 1174 SGS-PL-V030B Valve SG02 Main Steam Safety SGS-PL-V031A Valve SG01 JX-16-CN0024 SV4-PV65-VQQ- 1188 1187 1189 1197 Main Steam Safety JX-16-CN003G 001 1197 1193 1193 SGS-PL-V031B Valve SG02 Main Steam Safety SGS-PL-V032A Valve SG01 JX-16-CN0025 SV4-PV65-VQQ- 1210 1196 1212 1209 Main Steam Safety JX-16-CN0031 001 1198 1198 1205 SGS-PL-V032B Valve SG02 Main Steam Safety SGS-PL-V033A Valve SG01 JX-16-CN0026 SV4-PV65-VQQ- 1213 1213 1211 1221 Main Steam Safety JX-16-CN0032 001 1229 1223 1222 SGS-PL-V033B Valve SG02 Main Steam Safety SGS-PL-V034A Valve SG01 Main Steam Safety SGS-PL-V034B JX-16-CN0027 1228 1229 1223 Valve SG02 JX-16-CN0028 SV4-PV65-VQQ- 1220 1226 1226 1232 JX-16-CN0033 001 1223 1225 1224 Main Steam Safety SGS-PL-V035A JX-16-CN0034 1229 1232 1230 Valve SG01 Main Steam Safety SGS-PL-V035B Valve SG02 All set point and test values <1305 "Excerpt from COL Appendix C Table 2.2.4-1