ND-19-0223, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.12 (Index Number 879)

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Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.3.10.12 (Index Number 879)
ML19063B582
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/04/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-19-0223
Download: ML19063B582 (7)


Text

Michael J. Yox 7825 River Road Sk Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tei MAR 0 4 2019 Docket Nos.52-025 52-026 ND-19-0223 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 2.3.10.12 [Index Number 8791 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of March 1, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.10.12 [Index Number 879]

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.

Michael J. Yox Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.12 [Index Number 879]

MJY/LBP/sfr

U.S. Nuclear Regulatory Commission ND-19-0223 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. 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 Reaulatorv 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. B. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. I. Cozens Mr. J. Gaslevic Mr. V. Hall Oalethoroe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-19-0223 Page 3 of 3 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 Ms. J. Monahan Mr. J. L. Coward Other Mr. J. E. Hosier, 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. Kemizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0223 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0223 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.3.10.12[Index Number 879]

U.S. Nuclear Regulatory Commission ND-19-0223 Enclosure Page 2of 4 ITAAC Statement Desion Commitment

12. Safety-related displays identified in Table 2.3.10-1 can be retrieved in tfie main control room (MCR).

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

Acceptance Criteria Safety-related displays identified in Table 2.3.10-1 can be retrieved in the MCR.

ITAAC Completion Description An inspection is performed to verify the retrievability of the Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 safety-related displays in the MCR.The inspection for retrievability confirms that the safety-related displays of the parameters identified in COL Appendix C Table 2.3.10-1 (Attachment A)can be retrieved in the MCR.

The inspection is performed in accordance the Unit 3 and Unit 4 component test package work orders(References 1 and 2, respectively)for Liquid Radwaste System (WLS)component indication verifications, and visually confirms that when each of the safety-related displays identified in Attachment A is summoned at the MCR Protection and Safety Monitoring System (PMS) Visual Display Units(VDUs),the summoned safety-related display appears on the PMS VDU.

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

References 1 and 2 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.3.10.12 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 findings associated with the ITAAC.

U.S. Nuclear Regulatory Commission ND-19-0223 Enclosure Page 3of 4 References(available for NRC inspection)

1. SNC922147,"WLS Verifications - ITAAC: SV3-2.3.10.07a.ii Items 7.a.i, 8, 10 and SV3-2.3.10.12"
2. SNOXXXXX,"WLS Verifications- ITAAC: SV4-2.3.10.07a.ii Items 7.a.i, 8,10 and SV4-2.3.10.12"
3. 2.3.10.12-U3-CP-Rev 0, ITAAC Completion Package
4. 2.3.10.12-U4-CP-Rev 0, 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-19-0223 Enclosure Page 4 of 4 Attachment A Table 2.3.10-1 Safety-Related Equipment Name Tag No.

Display WLS Auxiliary Building Radiologically Controlled Area(RCA) Floodup Level WLS-400A Yes Sensor WLS Auxiliary Building RCA Floodup WLS-400B Yes Level Sensor