ND-18-0042, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.1.00.03 (Index Number 735)

Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 3.1.00.03 (Index Number 735)

ML18032A222
Person / Time
Site:	Vogtle
Issue date:	01/25/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0042
Download: ML18032A222 (8)

Text

7825 River Road Michael J. Yox Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 706-848-6459 tel Vogtle 3 & 4 410-474-8587 cell myox@southernco.com JAN 2 5 Docket Nos.: 52-025 52-026 ND-18-0042 10CFR 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-davs Prior to Initial Fuel Load Item 3.1.00.03 (Index Number 7351 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 17, 2018, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 3.1.00.03 [Index Number 735] 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 Companywill, 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.

Michael J. Yox Regulatory Affairs Director Vogtle 3 &4

U.S. Nuclear Regulatory Commission ND-18-0042 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted 1TAAC 3.1.00.03 [Index Number 735]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0042 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company M -D. A.* -Bost (w/o

• enclosures)

M M. D. Rauckhorst (w/o enclosures)

M M. D. Meier M D. H. Jones (w/o enclosures)

M D. L. McKinney M M. J. Yox M D. L. Fulton M J. D. Williams M 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. 0. Chamberlain Mr. D. R. Culver Mr. R. L. Beiike Mr. T. G. Petrak Document Services RTYPE: VND.Li.L06 File AR.01.02.06 cc; Nuclear Regulatory 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 Oolethoroe Power Corporation Mr. R. B. Brinkman Munfcipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0042 Page 4 of 4 Dalton Utmties 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. 8. DiTommaso 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., 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, Baich Bingham

U.S. Nuclear Regulatory Commission ND-18-0042 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0042 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 3.1.00.03 [Index Number 735]

U.S. Nuclear Regulatory Commission ND-18-0042 Enclosure Page 2 of 4 ITAAC Statement Desion Commitment

3. The plant parameters listed In Table 2.5.4-1, minimum Inventory table, In subsection 2.5.4, DOS, with a "Yes" In the "Display" column, can be retrieved In the TSC.

Insoectlons/Tests/Analvses An Inspection will be performed for retrlevablllty of the plant parameters In the TSC.

Acceotance Criteria The plant parameters listed In Table 2.5.4-1, minimum Inventory table. In subsection 2.5.4, DOS, with a "Yes" In the "Display" column, can be retrieved In the TSC.

ITAAC Completion Description An Inspection Is performed to verify the retrlevablllty of the VEGP Unit 3 and Unit 4 plant parameters In the Technical Support Center(TSC). The Inspection for retrlevablllty confirms that the plant parameters listed In COL Appendix C Table 2.5.4-1, Minimum Inventory of Controls, Displays, and Alerts at the RSW, with a "Yes" In the "Display" column (Attachment A) can be retrieved In the TSC.

The Inspection Is performed using Procedure AAA, TSC Data Display and Processing System (DDS) Display Inspection - Unit 3 (Reference 1)and Procedure BBS, TSC Data Display and Processing System (DDS) Display Inspection - Unit 4 (Reference 2), and visually confirms that when each of the plant parameters Identified In Attachment A Is summoned at a workstation connected to the TSC Local Area Network the summoned plant parameter appears on a display monitor at that TSC workstation.

The Inspection results are documented In Procedure XXX, TSC Data Display and Processing System (DDS) Display Inspection Report - Unit 3 (Reference 3)and Procedure YYY, TSC Data Display and Processing System (DDS) Display Inspection Report - Unit 4 (Reference 4) and confirmsthat the VEGP Unit 3 and Unit 4 plant parameters listed In AttachmentA can be retrieved In the TSC.

References 3 and 4 are available for NRC Inspection as part of the Unit 3 and Unit 4 ITAAC 3.1.00.03 Completion Packages (References 5 and 6).

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

U.S. Nuclear Regulatory Commission ND-18-0042 Enclosure Page 3 of 4 References (available for NRG inspection)

1. Procedure AM, TSC Data Display and Processing System (DDS) Display Inspection-Unit 3

2. Procedure BBB, TSC Data Display and Processing System (DDS) Display Inspection-Unit 4

3. Procedure XXX, TSC Data Display and Processing System (DDS) Display Inspection Report

- Unit 3

4. Procedure YYY, TSC Data Display and Processing System (DDS) Display Inspection Report

- Unit 4

5. ITMC 3.1.00.03 Completion Package (Unit 3)

6. ITMC 3.1.00.03 Completion Package (Unit 4)

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

U.S. Nuclear Regulatory Commission ND-18-0042 Enclosure Page 4 of 4 Attachment A Minimum Inventory of Controls, Displays, and Alerts at the RSW*

Description

• Display

• Neutron Flux Yes Startup Rate Yes Reactor Coolant System (RCS) Pressure Yes Wide-range Hot Leg Temperature Yes Wide-range Cold Leg Temperature Yes RCS Cooldown Rate Compared to the Limit Based on RCS Pressure Yes Wide-range Cold Leg Temperature Compared to the Limit Based on Yes RCS Pressure Containment Water Level Yes Containment Pressure Yes Pressurizer Water Level Yes Pressurizer Water Level Trend Yes Pressurizer Reference Leg Temperature Yes Reactor Vessel-Hot Leg Water Level Yes Pressurizer Pressure Yes Core Exit Temperature Yes RCS Subcooling Yes RCS Cold Overpressure Limit Yes In-containment Refueling Water Storage Tank (IRWST) Water Level Yes Passive Residual Heat Removal (PRHR) Flow Yes PRHR Outlet Temperature Yes Passive Containment Cooling System (PCS) Storage Tank Water Yes Level PCS Cooling Flow Yes IRWST to Normal Residual Heat Removal System (RNS) Suction Yes Valve Status Remotely Operated Containment IsolationValve Status Yes Containment Area High-range Radiation Level Yes Containment Pressure (Extended Range) Yes Core Makeup Tank (CMT) Level Yes

• Excerpt from COL Table 2.5.4-1