ND-19-0022, Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.06c.i (Index Number 532)

Unit 4 - Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.06c.i (Index Number 532)

ML19017A282
Person / Time
Site:	Vogtle
Issue date:	01/15/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ND-19-0022
Download: ML19017A282 (7)

Text

~ Southern Nuclear Michael J. Yox 7825 River Road Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel 410-474-8587 cell JAN 1 5 2019 myox@southernco.com Docket Nos. : 52-025 52-026 ND-19-0022 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 2.5.02.06c.i [Index Number 5321 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of January 14, 2019, Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses , and Acceptance Criteria (ITAAC) Item 2.5.02.06c.i

[Index Number 532] has not been completed greater than 225-days prior to initial fuel load. The Enclosure describes the plan fo r 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,

?#4}

Michael J. Yox I Regulatory Affairs Dir~ctor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.06c.i [Index Number 532]

MJY/LBP/sfr

U.S. Nuclear Regulatory Commission ND-19-0022 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. 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-19-0022 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-19-0022 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-19-0022 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 and Unit 4

-Completion Plan for Uncompleted ITAAC 2.5.02.06c.i [Index Number 532]

U.S. Nuclear Regulatory Commission ND-19-0022 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 6.c) The PMS provides manual initiation of reactor trip and selected engineered safety features as identified in Table 2.5.2-4.

Inspections, Tests, Analyses An operational test of the as-built PMS will be performed using the PMS manual actuation controls.

Acceptance Criteria i) The reactor trip switchgear opens after manual reactor trip controls are actuated.

ITAAC Completion Description Multiple ITAAC are performed to verify that the Protection and Safety Monitoring System (PMS) provides manual initiation of reactor trip and selected engineered safety features as identified in Combined License (COL) Appendix C, Table 2.5.2-4, (Attachment A). The subject ITAAC performs an operational test of the reactor trip function using the PMS manual actuation control$.

Operational testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures 3(4)-PMS-ITPP-504 (References 1 and 2 respectively), and 3(4)-DDS-ITPP-520 (References 3 and 4 respectively), to confirm that the reactor trip switchgear opens after manual reactor trip controls are actuated.

Preoperational test procedure 3(4)-PMS-ITPP-504 verifies the Reactor Trip Circuit Breakers (RTCBs) are closed. The reactor trip is then manually actuated at the Primary Dedicated Safety Panel (PDSP) by placing hand switch 3(4)-PMS-HS025, reactor trip, in the trip position. Each RTCB is verified to be open locally at the Reactor Trip Switchgear Cabinet, at the Maintenance and Test Panel, and on the Main Control Room displays. Testing is repeated for reactor trip hand switch 3(4)-PMS-HS026. Test procedure 3(4)-DDS-ITPP-520 transfers control from the main control room to the remote shutdown workstation, ensures all RTCBs are closed, then places the same reactor trip hand switch, 3(4)-PMS-HS025, in the trip position. The RTCBs are then verified open, and the process is repeated for reactor trip hand switch 3(4)-PMS-HS026.

Results of the preoperational testing are documented in Unit 3 and Unit 4 preoperational test procedures (References 1, 2, 3, and 4), and confirm that the reactor trip switchgear opens after manual reactor trip controls are actuated.

References 1 through 4 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC 2.5.02.06c.i Completion Packages (Reference 5 and 6, 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

U.S. Nuclear Regulatory Commission ND-19-0022 Enclosure Page 3 of 4 associated corrective actions. This review found there are no relevant ITAAC findings associated with the ITAAC.

References (available for NRC inspection)

1. 3-PMS-ITPP-504, "PMS Reactor Trip Breakers"

2. 4-PMS-ITPP-504, "PMS Reactor Trip Breakers

3. 3-DDS-ITPP-520, "Data and Display Processing System Remote Shutdown Room Preoperational Test Procedure"

4. 4-DDS-ITPP-520, "Data and Display Processing System Remote Shutdown Room Preoperational Test Procedure"

5. 2.5.02.06c.i-U3-CP-Rev 0, ITAAC Completion Package

6. 2.5.02.06c.i-U4-CP-Rev 0, ITAAC Completion Package

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

U.S. Nuclear Regulatory Commission ND-19-0022 Enclosure Page 4 of 4 Attachment A Table 2.5.2-4 PMS Manually Actuated Functions Reactor Trip Safeguards Actuation Containment Isolation Depressurization System Stages 1, 2, and 3 Actuation Depressurization System Stage 4 Actuation Feedwater Isolation Core Makeup Tank Injection Actuation Steam Line Isolation Passive Containment Cooling Actuation Passive Residual Heat Removal Heat Exchanger Alignment IRWST Injection .

Containment Recirculation Actuation Main Control Room Isolation, Air Supply Initiation, and Electrical Load De-energization Steam Generator Relief Isolation Chemical and Volume Control System Isolation Normal Residual Heat Removal System Isolation Containment Vacuum Relief