ND-19-0001, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.05.09c (Index Number 877)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.05.09c (Index Number 877)

ML19172A241
Person / Time
Site:	Vogtle
Issue date:	06/21/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0001
Download: ML19172A241 (8)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUN 2 1 2019 Docket Nos.: 52-025 52-026 ND-19-0001 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 2.2.05.09c findex Number 8771 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of June 20, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) 2.2.05.09c [Index Number 877]

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, later, 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-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.

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

Respectfully submitted.

Michael J. Yox Regulatory Affairs Director Vogtie 3 & 4

U.S. Nuclear Regulatory Commission ND-19-0001 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.05.09c [Index Number 877]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0001 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Companv 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 Reoulatorv 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 Ms. T. Lamb Mr. M. Webb Mr. P. O'Bryan Mr. T. Fredette Mr. C. Weber Qqiethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0001 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Eiectric Company. LLC Dr. L. Oriani(w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. lller Ms. J. Monahan Mr. J. L. Coward 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-19-0001 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0001 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.05.09c [Index Number 877]

U.S. Nuclear Regulatory Commission ND-19-0001 Enclosure Page 2 of 4 ITAAC Statement Design Commitment:

9.c) The MCR Load Shed Panels Identified in Table 2.2.5-1 perform their active safety function after receiving a signal from the PMS.

Inspection. Tests. Analvses:

Testing will be performed on the MCR Load Shed Panels listed in Table 2.2.5-1 using real or simulated signals into the PMS.

Acceptance Criteria:

The MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.

ITAAC Completion Description Testing is performed to demonstrate the Main Control Room (MCR) Load Shed Panels Identified in Combined License(COL) Appendix C Table 2.2.5-1 (Attachment A) perform their active safety function after receiving a signal from 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 confirm that the MCR Load Shed Panels identified in Attachment A perform their active safety function to de-energize MCR loads after receiving a signal from the PMS.

References 4 and 5 generate an actuation signal from PMS using the PMS Maintenance and Test Panel(MTP)to actuate the MCR Load Shed Panel 1 Division A. The MCR Load Shed Panel is verified locally to be actuated after the receipt of the actuation signal and the stage 1 and stage 2 loads are verified to be de-energized. The MCR Load Shed Panel 1 Division A is reset and the loads are verified to be energized. This methodology is repeated for MCR Load Shed Panel 2 Division A, MCR Load Shed Panel 1 Division C, and MCR Load Shed Panel 2 Division C.

The completed Unit 3 and Unit 4 component test results (references 1 and 2) confirm that the MCR Load Shed Panels identified in Table 2.2.5-1 perform their active safety function identified in the table after receiving a signal from the PMS.

References 1 through 5 are available for NRC Inspection as part of the ITAAC 2.2.05.09c Completion Packages(Reference 6 and 7).

U.S. Nuclear Regulatory Commission ND-19-0001 Enclosure Page 3 of 4 List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company 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-0TS-18-001,"Engineered Safeguards Actuation System 24-Month Actuation Device Test"

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

6. 2.2.05.09c-U3-CP-Rev 0, ITAAC Completion Package

7. 2.2.05.09c-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-19-0001 Enclosure Page 4 of 4 Attachment A "Excerpt from Combined License Appendix C Table 2.2.5-1

^Equipment Name *Tag No. ^Active Function MCR Load Shed Panel 1 VES-EP-01 De-energize MCR Loads MCR Load Shed Panel 2 VES-EP-02 De-energize MCR Loads