ND-19-0010, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.4.02.02b (Index Number 498)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.4.02.02b (Index Number 498)

ML19011A196
Person / Time
Site:	Vogtle
Issue date:	01/10/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.4.02.02b, ND-19-0010
Download: ML19011A196 (6)

Text

~ Southern Nuclear Michael J. Yox 7825 River Road Regu latory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell JAN 10 2019 myox @southernco.com Docket Nos.: 52-025 52-026 ND-19-0010 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 2.4.02.02b [Index Number 498]

Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 11 , 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses , and Acceptance Criteria (ITAAC) Item 2.4.02.02b

[Index Number 498] 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,

Enclosure:

Vogtle lectric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.4.02.02b [Index Number 498]

MJY/LBP/sfr

U.S. Nuclear Regulatory Commission ND-19-0010 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. A. L. Pugh 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. B. 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-19-0010 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-19-001 O Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0010 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.4.02.02b [Index Number 498]

U.S. Nuclear Regulatory Commission ND-19-001 O Enclosure Page 2 of 3 ITAAC Statement Design Commitment 2b) The main turbine-generator trips after receiving a signal from the PMS.

Inspections. Tests. Analyses Testing will be performed using real or simulated signals into the PMS.

Acceptance Criteria The main turbine-generator trips after receving a signal from the PMS.

ITAAC Completion Description Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3(4)-

TOS-ITPP-501 (References 1 and 2, respectively) and 3(4)-PMS-ITPP-504 (References 3 and 4, respectively), to confirm the main turbine-generator trips after receiving a signal from the Protection and Safety Monitoring System (PMS).

Test procedure 3(4)-TOS-ITPP-501 performs a trip solenoid valve functional test by verifying when master trip pilot solenoids (TOS-V174A1/A2, TOS-V174B1/B2) are de-ernergized, the spool moves to the tripped position and the main turbine and extraction non-return valves close thereby tripping the main turbine. Procedure 3(4)-PMS-ITPP-504 verifies the master trip pilot solenoids denergize due to opening PXS-V108A PRHR heat exchanger outlet valve resulting in a signal from PMS to the reactor trip logic, causing a reactor trip and subsequent main turbine-generator trip.

Results of the preoperational testing are documented on data sheets included in the Unit 3 and Unit 4 preoperational test procedures (References 1, 2, 3, and 4), and confirm that the main turbine-generator trips after receiving a signal from the PMS.

References 1, 2, 3, and 4 are available for NRC inspection as part of the Unit 3 and Unit 4 ITAAC 2.4.02.02b Completion Packages (References 5 and 6, respectively).

List of ITAAC Findings In accordance with plant procedures for ITAAC completion, Southern Nuclear Operating Company (SNC) 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-19-001 o Enclosure Page 3 of 3 References (available for NRC inspection)

1. 3-TOS-ITPP-501, "Main Turbine Control and Diagnostics System Preoperational Test Procedure"

2. 4-TOS-ITPP-501, "Main Turbine Control and Diagnostics System Preoperational Test Procedure"

3. 3-PMS-ITPP-504, "PMS Reactor Trip Breakers"

4. 4-PMS-ITPP-504, "PMS Reactor Trip Breakers"

5. 2.4.02.02b-U3-CP-Rev 0, ITAAC Completion Package

6. 2.4.02.02b-U4-CP-Rev 0, ITAAC Completion Package

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