ND-19-0279, Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.5.01.03a (Index Number 511)

Notice of Uncompleted ITAAC 225-Days Prior to Initial Fuel Load Item 2.5.01.03a (Index Number 511)

ML19095B550
Person / Time
Site:	Vogtle
Issue date:	04/05/2019
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of New Reactors
References
ITAAC 2.5.01.03a, ND-19-0279
Download: ML19095B550 (6)

Text

Michael J. Yox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tei APR 0 5 Z019 myox@southernco.com Docket Nos.52-025 52-026 ND-19-0279 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 2.5.01.03a [Index Number 5111 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of April 1, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.01.03a [Index Number 511]

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, (UlT/,

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 2.5.01.03a [Index Number 511]

MJY/LBP/sfr

U.S. Nuclear Regulatory Commission ND-19-0279 Page 2of 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. Vox 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 Reoulatorv 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 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authorltv of Georgia Mr. J. E. Fuller Mr. S. M. Jackson Dalton Utilities Mr. T. Bundros

U.S. Nuclear Regulatory Commission ND-19-0279 Page 3of 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 Pubiic Service Commission Ms. 8. W. Kernizan, Georgia Pubiic Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Baich Bingham

U.S. Nuclear Regulatory Commission ND-19-0279 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-0279 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.01.03a [Index Number 511]

U.S. Nuclear Regulatory Commission ND-19-0279 Enclosure Page 2 of 3 ITAAC Statement Design Commitment S.a) The signal processing hardware of the DAS uses input modules, output modules, and microprocessor or special purpose logic processor boards that are different than those used in the RMS.

Inspections. Tests. Analyses Inspection of the as-built DAS and RMS signal processing hardware will be performed.

Acceptance Criteria The DAS signal processing equipment uses input modules, output modules, and micro processor or special purpose logic processor boards that are different than those used in the RMS. The difference may be a different design, use of different component types, or different manufacturers.

ITAAC Completion Description Inspections are performed to confirm that the as-built signal processing hardware of the Diverse Actuation System (DAS) uses input modules, output modules, and microprocessor or special purpose logic processor boards that are different from those used in the Rrotection and Safety Monitoring System (RMS). The results of the inspections verify that the DAS utilizes both a different design and different component types of signal processing hardware than that used in the RMS.

Inspection of the DAS and RMS design specifications and topical reports verifies that the DAS and RMS utilize both a different design and different component types of signal processing hardware. The design of the DAS, documented in the DAS Design Specification (Reference 1),

utilizes an Advanced Logic System (ALS) hardware configuration with input, output, core logic, and communications boards. The ALS is a logic-based platform that does not utilize a microprocessor or software for operation, but instead relies on simple hardware architecture.

The logic is implemented using field-programmable gate array tectinology. The ALS design is further described in the ALS Topical Report (Reference 2). This is different from the design of the RMS,documented in the RMS Design Specification (Reference 3), which utilizes the Common Qualified (0) platform with the AC160 controller with multiprocessing capability for signal processing. The Common 0 platform is a computer system consisting of a set of commercial-grade hardware and software components dedicated and qualified for use in nuclear power plants. This design is further described in the Common Q RIatform Topical Report(Reference 4).

Inspections of the as-built DAS and RMS cabinets (References 5 and 6)are performed at Westinghouse prior to shipment to the plant site in accordance with NEI 08-01 Section 9.5 (Reference 17) because it is impractical to inspect the signal processing hardware within the cabinets after the cabinets are installed on site. The inspections use the system cabinet configuration drawings(References 7 and 8)and confirm that the as-built configuration of the DAS equipment uses different component types of signal processing hardware than that of the RMS. The as-built drawings for the cabinet configuration for the DAS and RMS document that

U.S. Nuclear Regulatory Commission ND-19-0279 Enclosure Page 3of 3 the as-built cabinets conform to the design, thereby utilizing different design and component types of signal processing hardware.

Upon arrival at the plant site, receipt inspections of the DAS and RMS cabinets are performed and documented in Material Receiving Reports(References 9 through 12) and confirm each cabinet was received and arrived in an acceptable condition with no opens items or corrective actions required. The cabinets are subsequently installed in their final as-built location and Installation Records(References 13 and 14) confirm the cabinets contain no evidence to indicate that the signal processing hardware was adversely impacted during installation.

References 1 through 14 confirm that the DAS signal processing equipment uses input modules, output modules, and micro-processor or special purpose logic processor boards that are different than those used in the RMS.

References 1 through 14 are available for NRC inspection as part of Unit 3 and Unit 4 ITAAC 2.5.01.03a Completion Packages(References 15 and 16, 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 ITAAC findings associated with the ITAAC.

References favailabie for NRC review)

1. SV3(4)-DAS-J4-001,"API000 Diverse Actuation System System Design Specification"

2. 6002-00301-NP,"Advanced Logic System Topical Report"

3. SV3(4)-PMS-J4-020,"API000 System Design Specification for the Protection and Safety Monitoring System"

4. WCAP-16097-P-A,"Common Qualified Platform Topical Report"

5. SV3(4)-DAS-VQQ-001,"Quality Release & Certificate of Conformance"

6. SV3(4)-PMS-VQQ-001,"Quality Release & Certificate of Conformance"

7. SV3(4)-DAS-J8Y-001,"Vogtle Unit 3(4) API000 Diverse Actuation System Cabinet Configuration Drawing Package"

8. SV3(4)-PMS-J8Y-001,"Vogtle Unit 3(4) API000 Protection and Safety Monitoring System Cabinet Configuration Drawing Package"

9. J132175-MRR-15-01219, Unit 3 DAS Material Receiving Report

10. XXXXXX-MRR-XX-XXXX, Unit 4 DAS Material Receiving Report

11. J132175-MRR-16-02318, Unit 3 PMS Material Receiving Report

12. XXXXXX-MRR-XX-XXXX, Unit 4 PMS Material Receiving Report

13. Unit 3(4)-DAS-XXX Installation Records

14. Unit 3(4)-PMS-XXX Installation Records 15.2.5.01.03a-U3-CP-Rev 0, Completion Package 16.2.5.01.03a-U4-CP-Rev 0, Completion Package

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