ND-19-0680, Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.09a.ii (Index Number 241)

Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.04.09a.ii (Index Number 241)

ML19162A231
Person / Time
Site:	Vogtle
Issue date:	06/11/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0680
Download: ML19162A231 (7)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynestwro, GA 30830 706-848-6459 tei JUN M 2019 Docket Nos.: 52-025 52-026 ND-19-0680 10CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.2.04.09a.ii fIndex Number 2411 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 10, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.04.09a.ii

[Index Number 241] 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 ITAAC that have not been completed 225-days prior to initial fuel load.

This notification is informed by the guidance described in NEI-OB-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.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Yox' Regulatory Affairs D)fector Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.09a.ii [Index Number 241]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0680 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(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. J. B. Klecha Mr. G. Chick Mr. M. J. Yox Mr. A. 8. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. W. A. Sparkman Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Ms. K. M. Stacy Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Regulatory 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 Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Mr. T. Lamb Mr. M. Webb Mr. P. O'Bryan Mr. T. Fredette Mr. C. Weber Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0680 Page 3 of 3 Municipal Eiectric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. Oriani (w/o enclosures)

Mr. D. 0. Durham (w/o enclosures)

Mr. M. M. Corletti Ms. L. G. Iller Ms. J. Monahan Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUB, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Ms. 8. W. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-19-0680 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0680 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.04.09a.ii [Index Number 241]

U.S. Nuclear Regulatory Commission ND-19-0680 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment 9.a) Components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the SGS to limit steam generator blowdown and feedwater flow to the steam generator.

I nspections/Tests/Analvses ii) Testing will be performed to confirm the trip of the pumps identified in Table 2.2.4-3.

Acceptance Criteria ii) The pumps identified in Table 2.2.4-3 trip after a signal is generated by the RMS.

ITAAC Completion Description Multiple ITAAC are performed to verify components within the main steam system, main and startup feedwater system, and the main turbine system identified in Table 2.2.4-3 provide backup isolation of the Steam Generator System (SGS)to limit steam generator blowdown and feedwater flow to the steam generator. The subject ITAAC performs testing to confirm the trip of the pumps identified in Combined License(COL)Appendix C Table 2.2.4-3(Attachment A)after a trip is generated by the Protection and Safety Monitoring System (PMS).

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNCXXXXXX and SNCYYYYYY (References 1 and 2). These component test packages utilize B-GEN-ITPCI-039(Reference 3) to direct the performance of test procedures 3/4-PMS-OTS 001 (References 4 and 5) to verify that the pumps in Attachment A trip after a signal is generated by the PMS.

References 4 and 5 establish initial conditions with each pump breaker in the test position and closed. An actuation signal is generated by PMS using the PMS Maintenance and Test Panel (MTP)to trip the pump breakers. Each breaker is verified locally to be open (trip position) after the receipt of the trip signal.

The completed Unit 3 and Unit 4 component test results (references 1 and 2)confirm that the pumps identified in Table 2.2.4-3 trip after a signal is generated by the PMS.

References 1 and 2 are available for NRC inspection as part of ITAAC 2.2.04.09a.ii Unit 3 and 4 Completion Packages (Reference 6 and 7).

U.S. Nuclear Regulatory Commission ND-19-0680 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company(SNC) performed a review of all findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with this ITAAC.

References favaiiabie for NRG inspection)

1. SNCXXXXXX

2. SNCYYYYYY

3. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure"

4. 3-PMS-OTS-18-001,"Engineered Safeguards Actuation System 24-Month Actuation Device Tesf

5. 4-PMS-0TS-18-001,"Engineered Safeguards Actuation System 24-Month Actuation Device Tesf

6. 2.2.04.09a.ii-U3-CP-Rev 0, ITAAC Completion Package

7. 2.2.04.09a.ii-U4-CP-Rev 0, ITAAC Completion Package

8. NEI 08-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-0680 Enclosure Page 4 of 4 Attachment A "Excerpt from COL Appendix 0 Table 2.2.4-3 Table 2.2.4-3 "Equipment Name "Tag No. "Control Function Main Feedwater Pump FWS-MP-02A Trip Main Feedwater Pump FWS-MP-02B Trip Main Feedwater Pump FWS-MP-02C Trip Startup Feedwater Pump FWS-MP-03A Trip Startup Feedwater Pump FWS-MP-03B Trip