ND-19-1244, Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08b.01 (Index Number 175)

Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.2.03.08b.01 (Index Number 175)

ML19305A232
Person / Time
Site:	Vogtle
Issue date:	10/31/2019
From:	Yox M Southern Nuclear Company
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-19-1244
Download: ML19305A232 (7)

Text

^Southern Nuclear Michael J. Yox Regulatory Affairs Director 7825 River Road Waynesboro, GA 30830 Vogtle 3 & 4 OCT 3 1 2019 706-848-6459 tel Docket Nos.: 52-025 52-026 ND-19-1244 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 2.2.03.08b.01 [Index Number 1751 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of October 31, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08b.01 [Index Number 175] 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).

SNC has proposed changes to ITAAC Item 2.2.03.08b.01 via license amendment request(LAR) and exemption request, LAR-19-017 (reference ML19249C739), which was submitted to NRC on September 6, 2019. Upon NRC issuance of the amendment and exemption for LAR-19-017, this uncompleted ITAAC notification will be updated to reflect the approved ITAAC changes.

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

U.S. Nuclear Regulatory Commission ND-19-1244 Page 2 of 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08b.01 [Index Number 175]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-1244 Page 3 of 4 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III (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. G. Chick Mr. M. Page Mr. M. J. Yox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. L. Hughes Mr. S. Leighty Ms. A. C. Chamberlain Mr. J. C. Haswell Document Services RTYPE: VND.LI.L06 File AR.01.02.06 cc:

Nuclear Requlatorv Commission Mr. W.Jones(w/o enclosures)

Mr. F. D. Brown Mr. C. P. Patel Mr. G. J. Khouri Ms. S. E. Temple Mr. N. D. Karlovich Mr. A. Lerch Mr. C. J. Even Mr. 8. J. Kemker Ms. N. C. Coovert Mr. C. Welch Mr. J. Gaslevic Mr. V. Hall Mr. G. Armstrong Ms. T. Lamb Mr. M. Webb Mr. T. Fredette Mr. C. Weber Mr. S. Smith Oqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-1244 Page 4 of 4 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinahouse 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. Z. 8. Harper 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., GDS 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-19-1244 Enclosure Page 1 of 3 Southern Nuclear Operating Company ND-19-1244 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.2.03.08b.01 [Index Number 175]

U.S. Nuclear Regulatory Commission ND-19-1244 Enclosure Page 2 of 3 ITAAC Statement Design Commitment:

8.b) The PXS provides core decay heat removal during design basis events.

Inspection. Tests. Analvses:

1. A heat removal performance test and analysis of the PRHR HX will be performed to determine the heat transfer from the HX. For the test, the reactor coolant hot leg temperature will be initially at > 540°F with the reactor coolant pumps stopped. The IRWST water level for the test will be above the top of the HX. The IRWST water temperature is not specified for the test. The test will continue until the hot leg temperature decreases below 420°F.

Acceptance Criteria:

1. A report exists and concludes that the PRHR HX heat transfer rate with the design basis number of PRHR HX tubes plugged is:

s 1.78 X 10 Btu/hr with 520°F HL Temp and 80°F IRWST temperatures.

> 1.11 X 10 Btu/hr with 420°F HL Temp and 80°F IRWST temperatures.

ITAAC Completion Description Multiple IT/\AC are performed to confirm the Passive Core Cooling System provides core decay heat removal during design basis events by testing and analysis of the Passive Residual Heat Removal(PRHR) Heat Exchanger(HX)to determine the heat transfer from the PRHR HX. The Reactor Coolant System (RCS) hot leg temperature will be initially > 540°F with the Reactor Coolant Pumps(RCPs)stopped. The In-containment Refueling Water Storage Tank(IRWST) water level for the test will be above the top of the PRHR HX and the test will continue until the hot leg temperature decreases below 420°F.

The testing is performed in accordance with Unit 3 and Unit 4 Preoperational test procedures (References 1 and 2) during Hot Functional Testing with the RCS at normal operating temperature and pressure and the IRWST level verified to be above the PRHR HX. The RCPs are stopped, and the test initiated by opening one of the PRHR HX outlet valves. RCS temperature is monitored and when temperature decreases below 420°F, the PRHR HX outlet valve is closed. PRHR HX inlet temperature, RCS hot leg and cold leg temperatures, IRWST temperature and PRHR HX flow are trended during the test and this information is provided to engineering to perform the heat transfer rate calculations.

The completed test results report (References 1 and 2) document the heat transfer rate for Unit 3 is A.AA X 10 Btu/hr with 520°F HL Temperature and 80°F IRWST temperatures and B.BB x 10 Btu/hr with 420°F HL Temperature and 80°F IRWST temperatures. The heat transfer rate for Unit 4 is C.CC x 10 Btu/hr with 520°F HL Temperature and 80°F IRWST temperatures and D.DD X 10 Btu/hr with 420°F HL Temperature and 80°F IRWST temperatures.

This demonstrates that a report exists and concludes that the PRHR HX heat transfer rate with the design basis number of PRHR HX tubes plugged is:

s 1.78 X 10 Btu/hr with 520°F HL Temp and 80°F IRWST temperatures, s 1.11 X 10 Btu/hr with 420°F HL Temp and 80°F IRWST temperatures.

U.S. Nuclear Regulatory Commission ND-19-1244 Enclosure Page 3 of 3 References 1 and 2 are available for NRG inspection as part of ITAAC 2.2.03.08b.01 Unit 3 and 4 Completion Packages(Reference 3 and 4).

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 NRG inspection)

1. 3-PXS-ITPP-XXX, PRHR heat transfer rate test

2. 4-PXS-ITPP-XXX, PRHR heat transfer rate test

3. 2.2.03.08b.01-U3-CP-RevO, ITAAC Completion Package

4. 2.2.03.08b.01-U4-CP-Rev0, ITAAC Completion Package

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