ND-19-0043, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.5.05.04 (Index Number 572)

Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.5.05.04 (Index Number 572)

ML19024A431
Person / Time
Site:	Vogtle
Issue date:	01/23/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.5.05.04, ND-19-0043
Download: ML19024A431 (7)

Text

>-. Southern Nuclear Michael J. Yox Regu latory Affa irs Director Vogtle 3 & 4 7825 River Road Waynes boro, GA 30830 706-848-6459 te l 410-474-8 587 cell JAN 2 3 2019 myox@southernco.com Docket Nos.: 52-025 52-026 ND-19-0043 10 CFR 52 .99(c)(3)

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 Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.05.04 [Index Number 5721 Ladies and Gentlemen:

Pursuant to 10 CFR 52 .99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 18, 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests , Analyses , and Acceptance Criteria (ITAAC) Item 2.5.05.04 [Index Number 5721 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 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, Regulatory Affairs Dire tor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.05.04 [Index Number 5721 MJY/LBP/sfr

U.S. Nuclear Regulatory Commission ND-19-0043 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. D. A Bost (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 S. 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 Ms. J. M. Heisserer Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A Lerch Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-19-0043 Page 3 of 3 Westinghouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller 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., GOS Associates, Inc.

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

U.S. Nuclear Regulatory Commission ND-19-0043 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0043 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.05.04 [Index Number 572]

U.S. Nuclear Regulatory Commission ND-19-0043 Enclosure Page2of 4 ITAAC Statement Design Commitment

4. Safety-related displays of the parameters identified in Table 2.5.5-1 can be retrieved in the MCA.

Inspections, Tests, Analyses Inspection will be performed for retrievability of the safety-related displays in the MCA.

Acceptance Criteria Safety-related displays identified in Table 2.5.5-1 can be retrieved in the MCA.

ITAAC Completion Description An inspection is performed to verify the safety-related displays of the parameters identified in the Combined License (COL) Appendix C Table 2.5.5-1 (Attachment A) can be retrieved in the MCA.

The inspection is performed in accordance with the Unit 3 and Unit 4 preoperational test procedures 3(4)-PMS-ITPP-503 (References 1 and 2, respectively) for In-Core Instrumentation System component indication verifications. The test procedures inject a test signal for core exit temperature (CET) and visually confirms that when each of the safety-related displays for core exit temperature is summoned at the MCA Protection and Safety Monitoring System (PMS)

Visual Display Units (VDUs), the summoned core exit temperature appears on the PMS VDU.

The Unit 3 and Unit 4 preoperational test results (References 1 and 2, respectively) confirm that the VEGP Unit 3 and Unit 4 plant parameter safety-related displays listed in Attachment A can be retrieved in the MCA.

References 1 and 2 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC 2.5.05.04 Completion Packages (References 3 and 4, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company performed a review of all ITAAC findings pertaining to the subject ITAAC and associated corrective actions. This review found there are no relevant ITAAC findings associated with the ITAAC.

U.S. Nuclear Regulatory Commission ND-19-0043 Enclosure Page 3 of 4 References (available for NRC inspection)

1. 3-PMS-ITPP-503, "PMS Qualified Data Processing System Preoperational Test Procedure"

2. 4-PMS-ITPP-503, "PMS Qualified Data Processing System Preoperational Test Procedure"

3. 2.5.05.04-U3-CP-Rev0, ITAAC Completion Package

4. 2.5.05.04-U4-CP-Rev0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0043 Enclosure Page 4 of 4 Attachment A IIS Safety-Related Displays in the MCR*

Table 2.5.5-1 Equipment Name Safety-Related Display lncore Thimble Assemblies (at least three Core Exit T emperature<1>

assemblies in each core quadrant)

1. Only applies to the safety-related assemblies. There are at least two safety-related assemblies in each core quadrant.

• Excerpt from COL Table 2.5.5-1