ND-20-0174, ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03 (Index Number 179)

ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03 (Index Number 179)

ML20132A103
Person / Time
Site:	Vogtle
Issue date:	05/11/2020
From:	Yox M Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ND-20-0174
Download: ML20132A103 (7)

Text

Michael J. Vox 7825 River Road Southern Nuclear Regulatory Affairs Director Waynesboro, GA 30830 Vogtie 3 & 4 706-848-6459 tel MAY 1 1 2020 Docket Nos.: 52-025 ND-20-0174 10CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03 [Index Number 1791 Ladies and Gentlemen:

In accordance with 10 CFR 52.99(c)(1), the purpose of this letter is to notify the Nuclear Regulatory Commission (NRC) of the completion of Vogtie Electric Generating Plant(VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.2.03.08c.1.03

[Index Number 179], for verifying the In-containment Refueling Water Storage Tank injection line flow resistance values. The closure process for this ITAAC is based on the guidance described in NEI 08-01, "Industry Guideline for the ITAAC Closure Process under 10 CFR Part 52", which is endorsed by the NRC in Regulatory Guide 1.215.

This letter contains no new NRC regulatory commitments. Southern Nuclear Operating Company(SNC) requests NRC staff confirmation of this determination and publication of the required notice in the Federal Register per 10 CFR 52.99.

If there are any questions, please contact Tom Petrak at 706-848-1575.

Respectfully submitted.

Michael J. Vox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.i.03[Index Number 179]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-20-0174 Page 2 of 3 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. P. Martino Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. T. G. Petrak Mr. C. T. Defnall Mr. C. E. Morrow Mr. R. L. Beiike Mr. S. Leighty 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. 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 M . C. Welch M . J. Gaslevic M V. Hall M G. Armstrong Ms. T. Lamb M M. Webb M T. Fredette M C. Weber M S. Smith M C. Santos M s. M. Bailey M S. Rose M B. Davis M J. Vasquez M J. Eargle Ms. K. Carrington

U.S. Nuclear Regulatory Commission ND-20-0174 Page 3 of 3 Mr. P. Heher Mr. M. King Mr. E. Davidson Qqlethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authoritv of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Daiton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani (w/o enclosures)

Mr. D. C. Durham (w/o enclosures)

Mr. M. M. Corletti Mr. Z. 8. Harper 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. Kernizan, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-20-0174 Enclosure Page 1 of 4 Southern Nuclear Operating Company ND-20-0174 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.2.03.08c.l.03[Index Number 179]

U.S. Nuclear Regulatory Commission ND-20-0174 Enclosure Page 2 of 4 ITAAC Statement Design Commitment 8.c) The PXS provides RCS makeup, boration, and safety injection during design basis events.

I nspections/Tests/Analvses i) A low-pressure injection test and analysis for each CMT, each accumulator, each IRWST injection line, and each containment recirculation line will be conducted. Each test is initiated by opening isolation valve(s) in the line being tested. Test fixtures may be used to simulate squib valves.

3. IRWST Injection:

The IRWST will be partially filled with water. All valves in these lines will be open during the test.

Sufficient flow will be provided to open the check valves.

Acceptance Criteria i) The injection line flow resistance from each source is as follows:

3. IRWST Injection:

The calculated flow resistance for each IRWST injection line between the IRWST and the reactor vessel is:

Line A: > 5.35 x 10 ft/gpm^ and s 9.09 x 10 ft/gpm^ and Line B: s 6.15 x 10 ft/gpm^ and 2 1.05 x 10 ft/gpm^.

ITAAC Determination Basis Multiple ITAAC are performed to verify that the Passive Core Cooling System (PXS) provides Reactor Coolant System (RCS) makeup, boration, and safety injection during design basis events. This ITAAC performs a low pressure injection test and analysis for each In-containment Refueling Water Storage Tank (IRWST) by testing and calculating the flow resistance of each injection line.

Performance tests were conducted in accordance with the Unit 3 preoperational test procedure 3-PXS-ITPP-507(Reference 1 and 2) which demonstrated that the flow path from each Unit 3 IRWST injection line to the reactor vessel has a flow resistance s 5.35 x 10 ft/gpm2 and ^ 9.09 X 10 ft/gpm^ for line A and a flow resistance s 6.15 x 10" ft/gpm^ and ^ 1.05 x 10 ft/gpm^ for line B.

The test installed flow test fixtures for the squib valves in the IRWST injection lines, isolated the containment sump recirculation lines, filled the IRWST with demineralized water to act as a temporary water supply, and initiated flow between the IRWST injection line A and the reactor vessel. All valves in these lines were opened during the test and sufficient flow was provided to open the check valves. The flow rate between the IRWST and injection line A to the reactor vessel, differential pressure, and IRWST level were measured. This test was repeated for the IRWST injection line B to the reactor vessel. The constant value for flow resistance was

U.S. Nuclear Regulatory Commission ND-20-0174 Enclosure Page 3 of 4 calculated based on measured tank level, differential pressure, discharge flow, adjusted for measurement uncertainty, and compared to the acceptance criteria.

The flow resistance for Unit 3 was calculated to be 7.33 x 10 ft/gpm^ for the IRWST injection line A flow path and 9.37 x 10'ft/gpm^ for the IRWST injection line B flow path (References 4 and 5). The Unit 3 test results were documented in Reference 3 and confirm that the calculated flow resistance between each IRWST injection line flow path and the reactor vessel meet the ITAAC acceptance criteria.

References 1 through 5 are available for NRC inspection as well as the ITAAC 2.2.03.08c.i.03 Completion Package (Reference 6).

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 one (1) closed Notice of Nonconformance (NGN)associated with this ITAAC.

1. NGN 99900404/2011-201-02(Closed)- Contrary to the above, as of July 15, 2011, Westlnghouse failed to establish measures to assure that the design of the check valves, piping, and related components located in-between the IRWST and the Direct Vessel Injection Line appropriately considered the potentially large hydrodynamic forces that could occur due to a spurious actuation of the IRWST squib valves while the reactor is at operating pressure.

a. The ITAAC completion review determined that all corrective actions associated with this NGN were completed and closed. NRC closure of this NGN was documented in NRC Safety Evaluation dated November 22, 2017 and closure letter dated December 18, 2017.

The ITAAC findings review is documented in the ITAAC Completion Package for ITAAC 2.2.03.08c.i.03(Reference 6)and available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.2.03.08c.i.03 was performed for VEGP Unit 3 and that the prescribed acceptance criteria were met.

Systems, structures, and components verified as part of this ITAAC are being maintained in their as-designed, ITAAC compliant condition in accordance with approved plant programs and procedures.

References favallable for NRC inspection)

1. 3-PXS-ITPP-507, Rev. 3,"IRWST Flow Tests"

2. Work Grder 1071722,"(ITAAC) Perform Preop Test 3-PXS-ITPP-507"

3. SV3-PXS-ITR-800179, Rev. 0, IT/\AC Technical Report,"Unit 3 Recorded Results of PXS IRWST Injection Line Flow Resistance: IT/\AC 2.2.03.08c.i.03"

4. SV3-PXS-T1R-001, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.2 IRWST Injection to DVI Nozzle Flow Resistance Test Engineering Report"

U.S. Nuclear Regulatory Commission ND-20-0174 Enclosure Page 4 of 4

5. SV3-PXS-T2C-001, Rev. 0,"Vogtle Unit 3 3-PXS-ITPP-507 Section 4.2 IRWST Injection to DVI Nozzle Flow Resistance Test Calculation"

6. 2.2.03.08c.i.03-U3-CP-Rev0, ITAAC Completion Package

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