ND-21-0300, ITAAC Closure Notification on Completion of ITAAC 2.3.06.11a (Index Number 382)

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ITAAC Closure Notification on Completion of ITAAC 2.3.06.11a (Index Number 382)
ML21148A020
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 05/28/2021
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
ITAAC 2.3.06.11a, ND-21-0300
Download: ML21148A020 (15)
v • d • e


Text

L Michael J. Yox 7325 River Road SOUtuBrn Nucl63r Regulatory Affairs Director Waynesboro, GA 30830 Vogtle 3 & 4 706-848-6459 tel MAY 2 8 2021 Docket Nos.: 52-025 ND-21-0300 10 CFR 52.99(c)(1)

U.S. Nuclear Regulatory Commission Document Control Desk Washiington, DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant Unit 3 ITAAC Closure Notification on Completion of ITAAC 2.3.06.1 la [Index Number 3821 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 Vogtle Electric Generating Plant (VEGP)

Unit 3 Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.3.06.1 la [Index Number 382], to verify that the valves/pumps identified in Combined License (COL) Appendix C Tables 2.3.6-1 and 2.3.6-3 respond per the Acceptance Criteria specified per ITAAC 2.3.06.1 la.

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 Kelli Roberts at 706-848-6991.

Respectfully submitted.

Michael J. Yox' Regulatory Affairs Director Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.06.1 la [Index Number 382]

MJY/GRS/sfr

U.S. Nuclear Regulatory Commission ND-21-0300 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. Peter P. Sena III Mr. D. L. McKinney Mr. M. D. Meier Mr. G. Chick Mr. S. Stimac Mr. P. Martino Mr. M. J. Vox Mr. A. S. Parton Ms. K. A. Roberts Mr. C. T. Defnall Mr. C. E. Morrow Mr. J. M. Fisher Mr. R. L. Belike 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 Ms. M. Bailey Mr. M. King Mr. G. Bowman Ms. A. Veil M

M M

M Ms. N. C. Coovert M

M M

M M

M M

M M

M M

M M

M

. C. P. Patel

. G. J. Khourl

. C. J. Even B. J. Kemker

. C. Welch

. J. Gaslevic

. O. Lopez-Santiago G. Armstrong M. Webb T. Fredette C. Santos B. Davis

. J. Vasquez

. J. Eargle E. Davidson

. T. Fanelll Ms. K. McCurry

. J. Parent

. B. Griman

U.S. Nuclear Regulatory Commission ND-21-0300 Page 3 of 3 Oalethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinqhouse Electric Company. LLC Dr. L. Oriani Mr. D. 0. Durham Mr. M. M. Corletti Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. 8. W. Kline, Bechtel Power Corporation Ms. L. Matis, Tetra Tech NUS, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., CDS Associates, Inc.

Mr. 8. Roetger, Georgia Public Service Commission Mr. R. L. Trokey, Georgia Public Service Commission Mr. K. C. Greene, Troutman Sanders Mr. 8. Blanton, Balch Bingham

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 1 of 12 Southern Nuclear Operating Company ND-21-0300 Enclosure Vogtle Electric Generating Plant (VEGP) Unit 3 Completion of ITAAC 2.3.06.11a [Index Number 382]

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 2 of 12 ITAAC Statement Desion Commitment

10. Safety-related displays identified in Table 2.3.6-1 can be retrieved in the MCR.

11.a) Controls exist in the MCR to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.

11.b) The valves identified in Table 2.3.6-1 as having RMS control perform active safety functions after receiving a signal from the RMS.

12.b) After loss of motive power, the remotely operated valves identified in Table 2.3.6-1 assume the indicated loss of motive power position.

13. Controls exist in the MCR to cause the pumps identified in Table 2.3.6-3 to perform the control function.
14. Displays of the RNS parameters identified in Table 2.3.6-3 can be retrieved in the MCR.

I nspections/T ests/Analvses Inspection will be performed for retrievability of the safety-related displays in the MCR.

Stroke testing will be performed on the remotely operated valves identified in Table 2.3.6-1 using the controls in the MCR.

Testing will be performed using real or simulated signals into the RMS.

Testing of the remotely operated valves will be performed under the conditions of loss of motive power.

Testing will be performed to actuate the pumps identified in Table 2.3.6-3 using controls in the MCR.

Inspection will be performed for retrievability in the MCR of the displays identified in Table 2.3.6-3.

Acceptance Criteria Safety-related displays identified in Table 2.3.6-1 can be retrieved in the MCR.

Controls in the MCR operate to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.

The valves identified in Table 2.3.6-1 as having RMS control perform the active function identified in the table after receiving a signal from the RMS.

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 3 of 12 Upon loss of motive power, each remotely operated valve identified in Table 2.3.6-1 assumes the indicated loss of motive power position.

Controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Displays of the RNS parameters identified in Table 2.3.6-3 are retrieved in the MCR.

ITAAC Determination Basis Testing or inspections were performed to verify that the Normal Residual Heat Removal System (RNS) provides the following functions:

Inspections performed demonstrate the safety-related displays identified in Combined License (COL) Appendix C Table 2.3.6-1 (Attachment A) can be retrieved in the Main Control f^oom (MCR).

Testing performed demonstrates that controls in the MCR operate to cause those remotely operated valves identified in Table 2.3.6-1 (Attachment B) to perform active functions.

Testing performed demonstrates that the valves identified in table 2.3.6-1 (Attachment C) as having Protection and Monitoring System (PMS) control perform the active function identified in the table after receiving a signal from the PMS.

Testing performed demonstrates that after a loss of motive power, the remotely operated valves identified in Table 2.3.6-1 (Attachment D) assumes the indicated loss of motive power position.

Testing performed demonstrates that controls in the MCR cause pumps identified in Table 2.3.6-3 (Attachment E) to perform the control function.

Inspections performed demonstrate the displays of the RNS parameters identified in Table 2.3.6-3 (Attachment F) are retrieved in the MCR.

Safetv-related displavs identified in Table 2.3.6-1 can be retrieved in the MCR.

An inspection was performed in accordance with Unit 3 component test work package SNC922091 (Reference 1) to verify the safety-related displays identified in Attachment A can be retrieved in the MCR.

The inspection was performed using reference 1 and was conducted at the MCR PMS Visual Display Units (VDUs) and verified the safety-related displays in Attachment A can be retrieved in the MCR. Each valve and indication listed in Attachment A is located on the VDUs and verified to display.

The completed Unit 3 component inspection results (Reference 1), as documented in SV3-RNS-ITR-800382 (Reference 16), confirmed that the safety-related displays identified in Table 2.3.6-1 can be retrieved in Unit 3 MCR.

Controls in the MCR operate to cause those remotelv operated valves identified in Table 2.3.6-1 to perform active functions.

Testing was performed in accordance with Unit 3 component test work packages listed in SV3-RNS-ITR-801382 (Reference 17) to verify that controls in the MCR operate to cause those

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 4 of 12 remotely operated valves identified in Attachment B to perform active functions. Testing was conducted at an operator work station, and Division B and D RMS VDUs in Unit 3 MGR to verify the valves identified in Attachment B as being remotely operated and having active functions are stroked open and ciosed from the MGR. The valve positions were verified locally and in the MGR. This confirmed that controls in Unit 3 MGR operate to cause the remotely operated valves to perform active safety functions.

The completed Unit 3 testing results (References 4 through 10 and 21), as documented in SV3-RNS-ITR-801382 (Reference 17), confirmed that controls in the MGR operate to cause those remotely operated valves identified in Table 2.3.6-1 to perform active functions.

The valves identified in Table 2.3.6-1 as having RMS control perform the active function identified in the table after receivino a sional from the RMS.

Testing was performed in accordance with Unit 3 component test packages and procedures listed in SV3-RNS-ITR-802382 (Reference 18). These component test packages utilize B-GEN-ITRGI-039 (Reference 2) and 3-GEN-0TS-10-002 (Reference 3) to verify that the valves identified in Attachment G as having RMS control perform the active function identified in the Attachment after receiving a signal from the RMS.

Unit 3 component test packages and procedures listed in SV3-RNS-ITR-802382 (Reference 18) established initial conditions with each valve verified locally and in the MGR to be in the Open position. An actuation signal was generated by RMS using the RMS Maintenance and Test Panel (MTR) to generate a signal to Glose the valves in Attachment G. Each valve was verified locally and in the MGR to be Glosed.

The completed Unit 3 testing results (References 4 through 10 and 15), as documented in SV3-RNS-ITR-802382 (Reference 18), confirmed that the valves identified in Table 2.3.6-1 as having RMS control perform the active function identified in the table after receiving a signal from the RMS.

Upon loss of motive power, each remotelv operated valve identified in Table 2.3.6-1 assumes the indicated loss of motive power position.

Testing was performed in accordance with Unit 3 work packages listed in SV3-RNS-ITR-803382 (Reference 19) to verify that upon loss of motive power, each remotely operated valve identified in Attachment D assumes the indicated loss of motive power position.

References 4 through 12 verified each Motor Operated Valve (MOV) locally and in the MGR to be in the Open position. Each MOV was stroked Glosed by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Glosed position was reached. This loss of power caused by valve control circuit demonstrated that each MOV failed "As-ls" (Glosed) when motive power was removed. Actual valve position was verified locally and in the MGR. Each MOV was also stroked Open by using the valve control circuit to de-energize the contactors, which removed motive power from the valve when the Open position was reached. This loss of power caused by the valve control circuit demonstrated the MOV failed "As-ls" (Open) when motive power was removed. Actual valve position was verified locally and in the MGR.

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 5 of 12 RNS-PL-V061 (RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve) testing was performed using Work Order 1109884 (Reference 15). The valve was Opened and verified to be Open locally and in the MCR. Power was removed from the solenoid valve supplying air to the valve actuator which removed motive power to the valve.

RNS-PL-V061 was verified to Close locally and in the MCR.

RNS-PL-V057A and -V057B (RNS Pump Miniflow Air-Operated Isolation Valves) testing was performed using Work Orders 1040464 and 1040466 (References 13 and 14). The valves were Closed, and power was removed from the solenoid valves supplying air to the valve actuators, which removed motive power to the valves. RNS-PL-V057A and -V057B were verified to be Open locally and in the MCR.

The completed Unit 3 testing results (References 4 through 15), as documented in SV3-RNS-ITR-803382 (Reference 19), confirmed that upon loss of motive power, each remotely operated valve identified in Table 2.3.6-1 assumed the indicated loss of motive power position.

Controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Testing was performed in accordance with Unit 3 component test work package, SNC922091 (Reference 1) to verify that controls in the MCR cause pumps identified in Attachment E to perform the control function.

Reference 1 established the initial conditions with both RNS pumps stopped. The pumps were started using Plant Control System (PLS) controls in the MCR per 3-RNS-ITPP-501 (Reference 20). Both RNS pumps were verified to start locally.

The completed Unit 3 component test results (Reference 1), as documented in SV3-RNS-ITR-800382 (Reference 16) confirmed that controls in the MCR cause pumps identified in Table 2.3.6-3 to perform the control function.

Displavs of the RNS parameters identified in Table 2.3.6-3 are retrieved in the MCR.

An inspection was performed in accordance with Unit 3 component test work package, SNC922091 (Reference 1) to verify displays of the RNS parameters identified in Attachment F are retrieved in the MCR.

Reference 1 directed performance of the inspection at an MCR operator workstation and visually confirmed that when each of the displays of parameters identified in Attachment F is summoned at an MCR workstation, the summoned plant parameter appears on a display monitor at the MCR workstation.

The completed Unit 3 component test results (Reference 1), as documented in SV3-RNS-ITR-800382 (Reference 16), confirmed that displays of the RNS parameters identified in Table 2.3.6-3 were retrieved in the MCR.

References 1 through 21 are available for NRC inspection as part of ITAAC 2.3.06.1 la Unit 3 Completion Package (Reference 22).

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 6 of 12 ITAAC Finding Review 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. The ITAAC completion review is documented in the ITAAC Completion Package for ITAAC 2.3.06.11 a (Reference 22) and is available for NRC review.

ITAAC Completion Statement Based on the above information, SNC hereby notifies the NRC that ITAAC 2.3.06.1 la 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.

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 7 of 12 References ^available for NRG inspection)

1.

SNC922091, Rev. 2, "RNS Component Testing - ITAAC: SV#-2.3.06.11a, Items 10,14, 13"

2.

B-GEN-ITPCI-039, Rev 7.0, "PMS CIM Component Test Procedure"

3.

3-GEN-0TS-10-002, Rev B, "Division B Quarterly Valve Stroke Tesf

4.

Work Order 1241546, "PMS CIM Component Retest - RNS-V001 A"

5.

Work Order 1241547, "PMS CIM Component Retest - RNS-V001B"

6.

Work Order 1241549, "PMS CIM Component Retest -

RNS-V002A"

7.

Work Order 1241550, "PMS CIM Component Retest -

RNS-V002B"

8.

Work Order 1241551, "PMS CIM Component Retest -

RNS-V0011"

9.

Work Order 1241736, "PMS CIM Component Retest -

RNS-PL-V022"

10.

Work Order 1241552, "PMS CIM Component Retest -

RNS-PL-V023"

11.

Work Order 1079934, "Static Diagnostic Testing Of MOV SV3-RNS-PL-V024"

12.

Work Order 1079933, "Static Diagnostic Testing Of MOV SV3-RNS-PL-V055"

13.

Work Order 1040464, "Perform initial Setup and Testing on AOV SV3-RNS-PL-V057A"

14.

Work Order 1040466, "Perform initial Setup and Testing on AOV SV3-RNS-PL-V057B"

15.

Work Order 1109884, "PMS CIM Component Testing Using GEN-OTS-10-002 (RNS)

(ITAAC)"

16.

SV3-RNS-ITR-800382, Rev 0, "Unit 3 Inspection Results of: ITAAC 2.3.06.11.a (Items 10, 13, &14)

17.

SV3-RNS-ITR-801382, Rev 0, "Unit 3 Testing Results of; ITAAC 2.3.06.11.a (Item 11.a)

18.

SV3-RNS-ITR-802382, Rev 1, "Unit 3 Testing Results of: ITAAC 2.3.06.11.a (Item 11.b)

19.

SV3-RNS-ITR-803382, Rev 1, "Unit 3 Testing Results of: ITAAC 2.3.06.11.a (Item 12.b)

20.

3-RNS-ITPP-501, Rev 2.1, "Normal Residual Heat Removal System Preoperational Test Procedure"

21.

Work Order 1100160, "Perform Plant Interface Testing of SV3-RNS-PL-V061"

22.

2.3.06.11a-U3-CP-RevO, ITAAC Completion Package

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 8 of 12 Attachment A

^Excerpt from COL Appendix C Table 2.3.6-1 Table 2.3.6-1

  • Equlpment Name
  • Tag No.
  • Safety-Related Display RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes (Valve Position)

RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Yes (Valve Position)

RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes (Valve Position)

RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Yes (Valve Position)

RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Yes (Valve Position)

RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Yes (Valve Position)

RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Yes (Valve Position)

RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve RNS-PL-V061 Yes (Valve Position)

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 9 of 12 Attachment B "Excerpt from COL Appendix 0 Table 2.3.6-1 Table 2.3.6-1 "Equipment Name "Tag No.

"Remotely Operated Valve "Active Function RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes Transfer Closed RCS Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Yes Transfer Closed RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes Transfer Closed RCS Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Yes Transfer Closed RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Yes Transfer Closed RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Yes Transfer Closed RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Yes T

ransfer Closed RNS Return from Chemical and Volume Control System (CVS)

Containment Isolation Valve RNS-PL-V061 Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 10 of 12

^Excerpt from COL Appendix C Table 2.3.6-1 Table 2.3.6-1

  • Equipment Name
  • Tag No.
  • Actlve Function RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A Yes Transfer Closed RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B Yes Transfer Closed RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A Yes Transfer Closed RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B Yes T

ransfer Closed RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 Yes Transfer Closed RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 Yes Transfer Closed RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 Yes T

ransfer Closed RNS Return from Chemical and Volume Control System (CVS)

Containment Isolation Valve RNS-PL-V061 Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 11 of 12 Attachment D

Excerpt from COL Appendix 0 Table 2.3.6-1 Table 2.3.6-1

  • Equipment Name
  • Tag No.
  • Loss of Motive Power Position RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001A As Is RGB Inner Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V001B As Is RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002A As Is RGB Outer Hot Leg Suction Motor-operated Isolation Valve RNS-PL-V002B As Is RNS Discharge Motor-operated Containment Isolation Valve RNS-PL-V011 As Is RNS Suction Header Motor-operated Containment Isolation Valve RNS-PL-V022 As Is RNS Suction from IRWST Motor-operated Isolation Valve RNS-PL-V023 As Is RNS Discharge to IRWST Motor-operated Isolation Valve RNS-PL-V024 As Is RNS Suction from Cask Loading Pit Motor-operated Isolation Valve RNS-PL-V055 As Is RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057A Open RNS Pump Miniflow Air-Operated Isolation Valve RNS-PL-V057B Open RNS Return from Chemical and Volume Control System (CVS) Containment Isolation Valve RNS-PL-V061 Closed

U.S. Nuclear Regulatory Commission ND-21-0300 Enclosure Page 12 of 12 Attachment E

^Excerpt from COL Appendix C Table 2.3.6-3 Table 2.3.6-3 "Equipment Name "Tag No.

"Control Function RMS Pump 1A (Motor)

RNS-MP-01A Start RMS Pump 1B (Motor)

RNS-MP-01B Start Attachment F "Excerpt from COL Appendix C Table 2.3.6-3 Table 2.3.6-3 "Equipment Name "Tag No.

"Display RNS Pump 1A (Motor)

RNS-MP-01A Yes (Run Status)

RNS Pump 1B (Motor)

RNS-MP-01B Yes (Run Status)

RNS Flow Sensor RNS-01A Yes RNS Flow Sensor RNS-01B Yes RNS Suction from Cask Loading Pit Isolation Valve (Position Indicator)

RNS-PL-V055 Yes RNS Pump Miniflow Isolation Valve (Position Indicator)

RNS-PL-V057A Yes RNS Pump Miniflow Isolation Valve (Position Indicator)

RNS-PL-V057B Yes

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