ND-18-0212, Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item E.3.9.06.00.02 (Index Number 860)

Vogtie, Unit 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item E.3.9.06.00.02 (Index Number 860)

ML18068A072
Person / Time
Site:	Vogtle
Issue date:	03/08/2018
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-18-0212
Download: ML18068A072 (7)

Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830

^ Southern Nuclear Vogtie 3 & 4 708-848-6459 tei 410-474-8587 ceii myox@souttiernco.com MAK 0 8 2018 Docket Nos.: 52-025 52-026 ND-18-0212 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 E.3.9.06.00.02 [Index Number 860]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 6, 2018, Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item E.3.9.06.00.02 [Index Number 860] 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 submittedto 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

Enclosure:

Vogtie Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC E.3.9.06.00.02 [Index Number 860]

MJY/LBP/amw

U.S. Nuclear Regulatory Commission ND-18-0212 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. Yox Mr. D. L. Fulton Mr. J. 8. Klecha Mr. F. H. Willis Ms. A. L. Pugh Mr. A. 8. Parton Mr. W. A. Sparkman Mr. 0. E. Morrow Ms. K. M. Stacy Mr. M. K. Washington Mr. J. P. Redd Ms. A. 0. Chamberlain Mr. D. R. Culver Mr. T. G. Petrak Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Reouiatorv 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. N. D. Karlovich Mr. A. J. Lerch Mr. C. J. Even Mr. F. D. Brown Mr. B. J. Kemker Ms. A. E. Rivera-Varona Ms. L. A. Kent Mr. P. B. Donnelly Qqiethorpe Power Corporation Mr. R. B. Brinkman Municipal Eiectric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-18-0212 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinqhouse 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. J. Monahan 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, Balch Bingham

U.S. Nuclear Regulatory Commission ND-18-0212 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-18-0212 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC E.3.9.06.00.02 [Index Number 860]

U.S. Nuclear Regulatory Commission ND-18-0212 Enclosure Page 2 of 4 ITAAC Statement Program Commitment 6.2 The means exists to determine the source term of releases of radioactive material within plant systems, and the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors. [1.3]

Inspections/Tests/Analvses 6.2 A test will be performed to demonstrate that the means exist to determine the source term of releases of radioactive material within plant systems, and the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors.

Acceptance Criteria 6.2 EIPs, through use in training and a drill, provided direction to accurately calculate the source terms and the magnitude of release of postulated accident scenarios.

ITAAC Completion Description A test (drill) is performed to demonstrate that the means exist to determine the source term of releases of radioactive material within plant systems, and the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors. Emergency Implementing Procedures (EIPs) are confirmed, through use in training and a drill, to provide direction to accurately calculate the source terms and the magnitude of release of postulated accident scenarios.

Response personnel who are required to determine the source term of releases of radioactive material within plant systems, and the magnitude of the release of radioactive materials based on plant system parameters and effluent monitors, are trained per the requirements of procedure NMP-TR-480, Emergency Response Organization (ERG) Training and Qualifications (Reference 1). The training includes a review of the position-specific EIPs used to provide direction to accurately calculate the source terms and the magnitude of release of radioactive materials for postulated accident scenarios.

A drill scenario, simulating a radiological material release within a plant system, is developed and conducted using procedure NMP-EP-303, Drill and Exercise Standards (Reference 2).

Evaluation of the drill performance confirms that the methodology contained in the EIPs provides direction to accurately calculate the source terms and the magnitude of release of a postulated accident scenario.

Personnel respond to the Technical Support Center (TSC) and the Operations Support Center (OSC) based on a scenario involving the release of radioactive materials within a plant system.

The TSC staff uses EIP procedures NMP-EP-146, Emergency Response Organization (Reference 3) and NMP-EP-143, FacilityActivation (Reference 4), and their applicable sub-tier documents, to review plant system and equipment parameter and effluent monitor data available to the TSC from the Data Display and Processing System, Post-Accident Monitoring System, and Emergency Response Data System to calculate the source term and establish the

U.S. Nuclear Regulatory Commission ND-18-0212 Enclosure Page 3 of 4 release pathway of the radioactive materials within plant system(s). In-plantteam(s) are dispatched from the 080 per EIP NMP-EP-146, and its applicable sub-tier documents, to obtain radiological survey data and chemistry sample data to provide additional information to supplement the plant system and equipment parameter and effluent monitor data used to calculate the source term and establish the release pathway of radioactive materials within plant system(s).

The ISC staff also utilizes EIP procedures NMP-EP-146 and NMP-EP-143, and their applicable sub-tier documents, to monitor the plant system and equipment parameter and effluent monitor data available to the JSC from the Data Display and Processing System, Post-Accident Monitoring System, and Emergency Response Data System to determine the magnitude of the release of radioactive materials.

Scenario-specific drill objectives are generated using the guidance provided in procedure NMP-EP-303 to evaluate that EIPs provide direction to accurately calculate the source terms and the magnitude of release of a postulated accident scenario. An evaluation of drill performance is conducted per procedure NMP-EP-303 to confirm that the drill objectives, associated with EIPs providing direction to accurately calculate the source terms and the magnitude of release of a postulated accident scenario, are met.

The NMP-TR-480 emergency response personnel lesson plans, which cover the EIPs used to provide direction to accurately calculate the source terms and the magnitude of release of radioactive materials for postulated accident scenarios, are documented in the Lesson Plan Summary Report (Reference 5).

The drill performance (test) results are documented in Drill/Exercise Report XXX (Reference 6) per procedure NMP-EP-303. The Drill/Exercise Report documents and confirms that EIPs provide direction to accurately calculate the source terms and the magnitude of release of a postulated accident scenario.

References 5 and 6 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC E.3.9.06.00.02 Completion Packages (References 7 and 8).

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 (available for NRC inspection)

1. Procedure NMP-TR-480, Emergency Response Organization (ERO) Training and Qualifications

2. Procedure NMP-EP-303, Drill and Exercise Standards

3. Procedure NMP-EP-146, Emergency Response Organization

4. Procedure NMP-EP-143, Facility Activation

5. Lesson Plan Summary Report

6. Drill/Exercise Report XXX

U.S. Nuclear Regulatory Commission ND-18-0212 Enclosure Page 4 of 4

7. ITAAC E.3.9.06.00.02 Completion Package (Unit 3)

8. ITAAC E.3.9.06.00.02 Completion Package (Unit 4)

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