ND-19-0861, Vogtie, Units 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.14 (Index Number 700)

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Vogtie, Units 3 and Unit 4, Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.7.01.14 (Index Number 700)
ML19198A175
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 07/17/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ND-19-0861
Download: ML19198A175 (16)
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Text

Michael J. Yox 7825 River Road Regulatory Affairs Director Southern Nuclear Vogtie 3 & 4 Waynesboro, GA 30830 706-848-6459 tei JUL 1 7 2019 Docket Nos.: 52-025 52-026 ND-19-0861 10 CFR 52.99(c)(3)

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555-0001 Southern Nuclear Operating Company Vogtie Electric Generating Plant Unit 3 and Unit 4 Notice of Uncompleted ITAAC 225-davs Prior to Initial Fuel Load Item 2.7.01.14 [Index Number 7001 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of July 12, 2019, Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.7.01.14 [Index Number 700] 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 MichaelJ. Yox Regulatory Affairs Director Vogtie 3 & 4

Enclosure:

Vogtie Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.14 [Index Number 700]

MJY/DLW/sfr

U.S. Nuclear Regulatory Commission ND-19-0861 Page 2 of 3 To:

Southern Nuclear Operating Company/ Georgia Power Company Mr. R.G. West(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. 8. Ration 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 go:

Nuclear Regulatory 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. B. 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. P. O'Bryan Mr. T. Fredette Mr. C. Weber Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen

U.S. Nuclear Regulatory Commission ND-19-0861 Page 3 of 3 Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. 8. M. Jackson Dalton Utilities Mr. T. Bundros Westinghouse Electric Company, LLC Dr. L. OrlanI (w/o enclosures)

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

Mr. M. M. Corletti Ms. L. G. Iller Mr. Z. 8. Harper Mr. J. L. Coward Other Mr. J. E. Hosier, Bechtel Power Corporation Ms. L. Matis, TetraTech NU8, Inc.

Dr. W. R. Jacobs, Jr., Ph.D., GD8 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-19-0861 Enclosure Page 1 of 13 Southern Nuclear Operating Company ND-19-0861 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.7.01.14[Index Number 700]

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 2 of 13 ITAAC Statement Desian Commitment B.d) The VBS provides ventilation cooling via the ancliiary equipment in Table 2.7.1-3 to the MCR and the division B&C Class 1E i&C rooms.

9. Safety-related displays identified in Table 2.7.1-1 can be retrieved in the MCR.

10.a) Controls exist in the MCR to cause the remotely operated valves identified in Table 2.7.1-1 to perform their active functions.

10.b) The valves identified in Table 2.7.1-1 as having RMS control perform their active safety function after receiving a signal from the RMS.

11. After loss of motive power, the remotely operated valves identified in Table 2.7.1-1 assume the indicated loss of motive power position.
12. Controls exist in the MCR to cause the components identified in Table 2.7.1-3 to perform the listed function.
13. Displays of the parameters identified in Table 2.7.1-3 can be retrieved in the MCR.
14. The background noise level in the MCR and RSR does not exceed 65 dB(A) when the VBS is operating.

I nsoections/Tests/Analvses Testing will be performed on the components in Table 2.7.1-3.

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 2.7.1-1 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 on the components in Table 2.7.1-3 using controls in the MCR.

Inspection will be performed for retrievability of the parameters in the MCR.

The as-built VBS will be operated, and background noise levels in the MCR and RSR will be measured.

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 3 of 13 Acceptance Criteria The fans start and run.

Safety-related displays identified in Table 2.7.1-1 can be retrieved in the MCR.

Controls in the MCR operate to cause the remotely operated valves identified in Table 2.7.1-1 to perform their active functions.

The valves identified in Table 2.7.1-1 as having RMS control perform their active safety function after receiving a signal from RMS.

Upon loss of motive power, each remotely operated valves identified in Table 2.7.1-1 assumes the indicated loss of motive power position.

Controls in the MCR operate to cause the components listed in Table 2.7.1 -3 to perform the listed functions.

The displays identified in Table 2.7.1-3 can be retrieved in the MCR.

The background noise level in the MCR and RSR does not exceed 65 dB(A) when the VBS is operating.

ITAAC Completion Description Multiple ITAAC are performed to verify by testing and inspections that the Nuclear Island Nonradioactive Ventilation System (VBS) provides ventilation cooling via the ancillary equipment in Combined License(COL)Appendix C Table 2.7.1-3(Attachment A)to the Main Control Room (MCR)and the division B&C Class 1E l&C rooms. Testing is performed to demonstrate controls exist in the MCR to cause the remotely operated valves in COL Appendix C Table 2.7.1-1 (Attachment C)to perform their active functions, that the valves identified in Table 2.7.1-1 (Attachment D)as having Rrotection and Safety Monitoring System (RMS)control perform their active safety function after receiving a signal from RMS and that after a loss of motive power, the remotely operated valves identified in Table 2.7.1-1 (Attachment E)assume the indicated loss of motive power position. Testing is also performed to demonstrate that controls exist in the MCR to cause the components identified in Table 2.7.1-3(Attachment F)to perform the listed function and the VBS system will be operated and the background noise level will be verified to be 5 65 db(A) in the MCR and the Remote Shutdown Room (RSR).

Inspections are also performed to demonstrate the safety-related displays identified in Table 2.7.1-1 (Attachment B)can be retrieved in the MCR and that the displays of the parameters identified in Table 2.7.1-3(Attachment G)can be retrieved in the MCR.

The fans start and run.

Testing is performed in accordance with Unit 3 and Unit 4 component test work packages, SNC922115 and SNCYYYYYY (References 1 and 2)to verify the ancillary fans listed in Attachment A start and run. References 1 and 2 direct the performance of 3/4-VBS-OTS-20-001 (References 3 and 4) and 3/4-VBS-OTS-20-002(References 5 and 6) which local starts each fan in Attachment A, runs each fan for 15 minutes, and then stops each fan.

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 4 of 13 This testing confirms that the fans start and run.

Safety-related displays identified in Table 2.7.1-1 can be retrieved in the MGR.

An inspection is performed in accordance with Unit 3 and Unit 4 component test work packages, SNC922115 and SNCYYYYYY(References 1 and 2)for VBS component indication verifications, and visually confirms that when each of the safety-related displays identified in Attachment B is summoned at the MGR RMS Visual Display Units(VDUs), the summoned safety-related display appears on the RMS VDU.

The Unit 3 and Unit 4 component test results (References 1 and 2)confirm that the Unit 3 and Unit 4 safety-related displays listed in Table 2.7.1-1 can be retrieved in the MGR.

Controls in the MGR ooerate to cause the remotely operated valves identified in Table 2.7.1-1 to perform their active functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test work packages, SNG922115 and SNCYYYYYY(References 1 and 2)to verify controls in the MGR operate to cause the remotely operated valves identified in Attachment C to perform their active function.

At an MGR operator workstation, the valves in Attachment G are verified to be Open and verified locally. Then each valve is stroked Closed using the Riant Control System (RLS)at an operator work station and verified in the MGR and locally.

Unit 3 and Unit 4 component test results (References 1 and 2)confirm controls in the MGR operate to cause the remotely operated valves identified in Table 2.7.1-1 to perform their active function.

The valves identified in Table 2.7.1-1 as havina RMS control perform their active safety function after receivino a sional from RMS.

Testing is performed in accordance with Unit 3 and Unit 4 component test packages SNGXXXXXX and SNCYYYYYY (References 7 and 8). These component test packages utilize B-GEN-ITRGI-039(Reference 9)to direct the performance of test procedures 3/4-GEN-OTS 001 (References 10 and 11), 3/4-GEN-OTS-10-002(References 12 and 13), and 3/4-GEN-OTS-10-003(References 14 and 15)to verify that the valves in Attachment D perform their active function after a signal is generated by the RMS.

References 10 through 15 establish initial conditions with each valve verified locally to be in the Open position. An actuation signal is generated by RMS using the RMS Maintenance and Test Ranel(MTR)to cause each valve to Close. Each valve is verified locally and in the MGR to be Closed after the receipt of the actuation signal.

Unit 3 and Unit 4 component test package results(References 7 and 8)confirm the valves identified in Table 2.7.1-1 as having RMS control perform their active safety function after receiving a signal from RMS.

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 5 of 13 Uoon loss of motive power, each remotely ooerated valves identified in Table 2.7.1-1 assumes tlie indicated loss of motive power position.

Testing is performed in accordance withi Unit 3 and Unit 4 component test work packages, SNC922115 and SNCYYYYYY (References 1 and 2)to verify upon loss of motive power, each remotely operated valves identified in Attachment E assumes the indicated loss of motive power position.

References 1 and 2 establish the initial conditions with the remotely operated valves listed in Attachment E verified in the Open position locally and in the MGR. The power supply breaker to each valve is Opened; the valve is locally verified to fail as-is; an attempt is made to stroke the valve Closed and it is verified to remain Open. Power is restored to the valve and testing continues until all valves in Attachment E have been tested.

The Unit 3 and Unit 4 component test results(References 1 and 2)confirm that upon loss of motive power, each remotely operated valve identified in Table 2.7.1-1 assumes the indicated loss of motive power position.

Controls in the MCR operate to cause the components listed in Table 2.7.1-3 to perform the listed functions.

Testing is performed in accordance with Unit 3 and Unit 4 component test work packages, SNC922115 and SNCYYYYYY (References 1 and 2)to verify controls in the MCR operate to cause the components listed in Attachment F to perform their listed function.

References 1 and 2 direct performance of the plant operating procedures for the VBS system at an MCR operator workstation. The VBS ventilation systems are started using the plant operating procedures and the components listed in Attachment F are verified to start.

Unit 3 and Unit 4 component test results (References 1 and 2)confirm that controls in the MCR operate to cause the components listed in Table 2.7.1-3 to perform the listed function.

The disolavs identified in Table 2.7.1-3 can be retrieved in the MCR.

An inspection is performed in accordance with Unit 3 and Unit 4 component test work packages, SNC922115 and SNCYYYYYY (References 1 and 2)to verify the displays identified in Attachment G can be retrieved in the MCR.

References 1 and 2 perform the VBS verifications and visually confirms that when each of the displays of the component status identified in Attachment G is summoned at an MCR workstation, the summoned plant component status appears on a display monitor at the MCR workstation.

Unit 3 and Unit 4 component test results(References 1 and 2)confirm that the displays identified in Table 2.7.1-3 can be retrieved in the MCR.

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 6 of 13 The backaround noise level in the MGR and RSR does not exceed 65 dB(A) when the VBS is operating.

Testing is performed in accordance with Unit 3 and Unit 4 preoperational test procedures, 3-VBS-ITPP-502 and 4-VBS-ITPP-502(References 16 and 17)to verify the background noise level in the MGR and the Remote Shutdown Room (RSR)does not exceed 65 db(A) when the VBS is operating.

Testing using references 16 and 17 is initiated by placing one train of VBS in operation with one train of Division A/C Class 1E Electrical Subsystem, and one train of the Division B/D Class 1E Electrical Subsystem in service. After the ventilation systems have been in sen/ice for more than 15 minutes, noise level readings are taken at 8 locations in the MCR and 1 location in the RSR.

Ten readings are taken at one minute intervals; the readings at each location are averaged and corrected for measurement uncertainty and verified to be ^ 65 db(A). Then both supplemental filtration units are also placed in service and after 15 minutes the noise level readings are taken again and verified to be ^ 65 db(A). This testing is repeated with the opposite VBS ventilation train in sen/ice. The maximum noise level obtained is XX db(A)for Unit 3 MCR and YY db(A)for Unit 3 RSR. The maximum noise level obtained is XX db(A)for Unit 4 MCR and YY db(A)for Unit 4 RSR.

The Unit 3 and Unit 4 preoperational test results(References 16 and 17)confirm that the background noise level in the MCR and RSR does not exceed 65 dB(A) when the VBS is operating.

References 1 through 17 are available for NRC inspection as part of ITAAC 2.7.01.14 Unit 3 and 4 Completion Packages(Reference 18 and 19).

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.

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 7 of 13 References favaiiable for NRG inspection)

1. SNC922115,"Nuclear Island Nonradioactive Ventilation System Control and Indication Verifications - ITAAC: SV3-2.7.01.14 Items B.d, 9, lO.a, 11,12, and 13"
2. SNCYYYYYY,"Nuclear Island Nonradioactive Ventilation System Control and Indication Verifications - ITAAC: SV3-2.7.01.14 Items B.d, 9, lO.a, 11,12, and 13"
3. 3-VBS-OTS-20-001,"Main Control Room Ancillary Fan Quarterly Operational Tesf
4. 4-VBS-OTS-20-001,"Main Control Room Ancillary Fan Quarterly Operational Tesf
5. 3-VBS-OTS-20-002,"l&C Rooms Ancillary Fan Quarterly Operational Tesf
6. 4-VBS-QTS-20-002,"l&C Rooms Ancillary Fan Quarterly Operational Tesf
7. SNCXXXXXX B. SNCYYYYYY
9. B-GEN-ITPCI-039,"PMS CIM Component Test Procedure"
10. 3-GEN-0TS-10-001,"DIVISION A QUARTERLY VALVE STROKE TEST' 11.4-GEN-0TS-10-001,"DIVISION A QUARTERLY VALVE STROKE TEST'
12. 3-GEN-0TS-10-002,"DIVISION B QUARTERLY VALVE STROKE TEST'
13. 4-GEN-0TS-10-002,"DIVISION B QUARTERLY VALVE STROKE TEST'
14. 3-GEN-0TS-10-003,"DIVISION C QUARTERLY VALVE STROKE TEST'
15. 4-GEN-0TS-10-003,"DIVISION C QUARTERLY VALVE STROKE TEST' 16.3-VBS-ITPP-502,"Nuclear Island Nonradioactive Ventilation System Hot Functional Tesf 17.4-VBS-ITPP-502,"Nuclear Island Nonradioactive Ventilation System Hot Functional Tesf IB. 2.7.01.14-U3-CP-Rev 0, ITAAC Completion Package 19.2.7.01.14-U4-CP-Rev 0, ITAAC Completion Package
20. NEI OB-01,"Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 8 of 13 Attachment A COL Appendix C Table 2.7.1-3 Table 2.7.1-3 Equipment Tag No. Display Control Function MGR Ancillary Fans VBS-MA-10A No -

VBS-MA-10B Division B Room Ancillary Fan VBS-MA-11 No -

Division C Room Ancillary Fan VBS-MA-12 No -

Attachment B

'Excerpt from COL Appendix C Table 2.7.1-1 Table 2.7.1-1

  • Equlpment Name *Tag No. *Safety-Related Display MGR Supply Air Isolation Valve VBS-PL-V186 Yes (Valve Position)

MGR Supply Air Isolation Valve VBS-PL-V187 Yes (Valve Position)

MGR Return Air Isolation Valve VBS-PL-V188 Yes (Valve Position)

MGR Return Air Isolation Valve VBS-PL-V189 Yes (Valve Position)

MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes (Valve Position)

MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes (Valve Position)

MGR SDS (Vent) Isolation Valve SDS-PL-V001 Yes (Valve Position)

MGR SDS (Vent) Isolation Valve SDS-PL-V002 Yes (Valve Position)

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 9 of 13 Attachment C

'Excerpt from COL Appendix C Table 2.7.1-1 Table 2.7.1-1

'Equipment Name 'Tag No. 'Remotely Operated 'Active Valve Function MGR Supply Air Isolation Valve VBS-PL-V186 Yes Transfer Closed MGR Supply Air Isolation Valve VBS-PL-V187 Yes Transfer Closed MGR Return Air Isolation Valve VBS-PL-V188 Yes Transfer Closed MGR Return Air Isolation Valve VBS-PL-V189 Yes Transfer Closed MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes Transfer Closed MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes Transfer Closed MGR SDS(Vent) Isolation Valve SDS-PL-V001 Yes Transfer Closed MGR SDS (Vent) Isolation Valve SDS-PL-V002 Yes Transfer Closed

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 10 of 13 Attachment D "Excerpt from COL Appendix 0 Table 2.7.1-1 Table 2.7.1-1 "Equipment Name "Tag No. "Control "Active RMS/DAS Function MGR Supply Air Isolation Valve VBS-PL-V186 Yes/No Transfer Closed MGR Supply Air Isolation Valve VBS-PL-V187 Yes/No Transfer Closed MGR Return Air Isolation Valve VBS-PL-V188 Yes/No Transfer Closed MGR Return Air Isolation Valve VBS-PL-V189 Yes/No Transfer Closed MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes/No Transfer Closed MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes/No Transfer Closed MGR SDS (Vent) Isolation Valve SDS-PL-V001 Yes/No Transfer Closed MGR SDS (Vent) Isolation Valve SDS-PL-V002 Yes/No Transfer Closed

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 11 of 13 Attachment E

'Excerpt from COL Appendix C Table 2.7.1-1 Table 2.7.1-1

'Equipment Name *Tag No. 'Remotely 'Loss of Motive Operated Power Position Valve MGR Supply Air Isolation Valve VBS-PL-V186 Yes As Is MGR Supply Air Isolation Valve VBS-PL-V187 Yes As Is MGR Return Air Isolation Valve VBS-PL-V188 Yes As Is MGR Return Air Isolation Valve VBS-PL-V189 Yes As Is MGR Exhaust Air Isolation Valve VBS-PL-V190 Yes As Is MGR Exhaust Air Isolation Valve VBS-PL-V191 Yes As Is MGR SDS (Vent) Isolation Valve SDS-PL-V001 Yes As Is MGR SDS(Vent) Isolation Valve SDS-PL-V002 Yes As Is

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 12 of 13 Attachment F

'Excerpt from COL Appendix C Table 2.7.1-3 Table 2.7.1-3

'Equipment 'Tag No. 'Control Function Supplemental Air Filtration Unit Fan A VBS-MA-03A Start Supplemental Air Filtration Unit Fan B VBS-MA-03B Start MGR/OSA Supply Air Handling Units(AMU) A Fans VBS-MA-01A Start VBS-MA-02A MGR/CSA Supply AMU B Fans VBS-MA-01B Start VBS-MA-02B Division "A" and "G" Glass 1E Electrical Room AHU A Fans VBS-MA-05A Start VBS-MA-06A Division "A" and "G" Glass 1E Electrical Room AHU G Fans VBS-MA-05G Start VBS-MA-06G Division "B" and "D" Glass 1E Electrical Room AHU B Fans VBS-MA-05B Start VBS-MA-06B Division "B" and "D" Glass IE Electrical Room AHU D Fans VBS-MA-05D Start VBS-MA-06D Division "A" and "G" Glass 1E Battery Room Exhaust Fans VBS-MA-07A Start VBS-MA-07G Division "B" and "D" Glass 1E Battery Room Exhaust Fans VBS-MA-07B Start VBS-MA-07D

U.S. Nuclear Regulatory Commission ND-19-0861 Enclosure Page 13 of 13 Attachment G

'Excerpt from COL Appendix 0 Table 2.7.1-3 Table 2.7.1-3

'Equipment 'Tag No. ' Display Supplemental Air Filtration Unit Fan A VBS-MA-03A Yes (Run Status)

Supplemental Air Filtration Unit Fan B VBS-MA-03B Yes (Run Status)

MGR/CSA Supply Air Handling Units(AHU) A Fans VBS-MA-01A Yes VBS-MA-02A (Run Status)

MCR/CSA Supply AHU B Fans VBS-MA-01B Yes VBS-MA-02B (Run Status)

Division "A" and "0" Class 1E Electrical Room AHU A Fans VBS-MA-05A Yes VBS-MA-06A (Run Status)

Division "A" and "C" Class IE Electrical Room AHU C Fans VBS-MA-05C Yes VBS-MA-06C (Run Status)

Division "B" and "D" Class IE Electrical Room AHU B Fans VBS-MA-05B Yes VBS-MA-06B (Run Status)

Division "B" and "D" Class 1E Electrical Room AHU D Fans VBS-MA-05D Yes VBS-MA-06D (Run Status)

Division "A" and "C" Class 1E Battery Room Exhaust Fans VBS-MA-07A Yes VBS-MA-07C (Run Status)

Division "B" and "D" Class 1E Battery Room Exhaust Fans VBS-MA-07B Yes VBS-MA-07D (Run Status)

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