ND-19-1122, Unit 4 Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08b.ii (Index Number 543)

From kanterella
Jump to navigation Jump to search
Unit 4 Notice of Uncompleted ITAAC 225-days Prior to Initial Fuel Load Item 2.5.02.08b.ii (Index Number 543)
ML19267A213
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 09/24/2019
From: Yox M
Southern Nuclear Operating Co
To:
Document Control Desk, Office of New Reactors
References
ITAAC 2.5.02.08b.ii, ND-19-1122
Download: ML19267A213 (14)
v • d • e


Text

Michael J. Vox 7825 River Road

^Southern Nuclear Regulatory Affairs Director Vogtle 3 & 4 Waynesboro, GA 30830 706-848-6459 tel SEP 2 4 2019 Docket Nos.: 52-025 52-026 ND-19-1122 10 CFR 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 2.5.02.08b.ii [Index Number 5431 Ladies and Gentlemen:

Pursuant to 10 CFR 52.99(c)(3), Southern Nuclear Operating Company hereby notifies the NRC that as of September 18, 2019, Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Uncompleted Inspections, Tests, Analyses, and Acceptance Criteria (ITAAC) Item 2.5.02.08b.ii

[Index Number 543] 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.

Michael J. Vox Regulatory Affairs Dire'ctor Vogtle 3 & 4

Enclosure:

Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.08b.ii [Index Number 543]

MJY/CWM/sfr

U.S. Nuclear Regulatory Commission ND-19-1122 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. 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 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 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. T. Fredette Mr. C. Weber Mr. S. Smith Oglethorpe Power Corporation Mr. R. B. Brinkman Mr. E. Rasmussen Municipal Electric Authority of Georgia Mr. J. E. Fuller Mr. S. M. Jackson

U.S. Nuclear Regulatory Commission ND-19-1122 Page 3 of 3 Dalton Utilities Mr. T. Bundros Westinghouse Eiectric Company, LLC Dr. L. Oriani (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. 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-19-1122 Enclosure Page 1 of 11 Southern Nuclear Operating Company ND-19-1122 Enclosure Vogtle Electric Generating Plant(VEGP) Unit 3 and Unit 4 Completion Plan for Uncompleted ITAAC 2.5.02.08b.ii [Index Number 543]

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 2 of 11 ITAAC Statement Design Commitment 8.b) The RMS provides for the transfer of control capability from the MCR to the RSW using multiple transfer switches. Each individual transfer switch is associated with only a single safety-related group or with nonsafety-related control capability.

Insoections/Tests/Analvses ii) An operational test of the as-built system will be performed to demonstrate the transfer of control capability from the MCR to the RSW.

Acceptance Criteria ii) Actuation of each transfer switch results in an alarm in the MCR and RSW,the activation of operator control capability from the RSW, and the deactivation of operator control capability from the MCR for the associated safety-related division and nonsafety-related control capability.

ITAAC Completion Description Multiple ITAAC are performed to ensure that the Protection and Safety Monitoring System (PMS) provides for the transfer of control capability from the Main Control Room (MCR)to the Remote Shutdown Workstation(RSW)using multiple transfer switches. Each individual transfer switch is associated with only a single safety-related group or with non-safety-related control capability. The subject ITAAC requires that an operational test of the as-built system will be performed to demonstrate the transfer of control capability from the MCR to the RSW.

This ITAAC is performed to verify, by testing, that activation of each PMS transfer switch from the MCR to the RSW results in an alarm in the MCR and RSW. This ITAAC also verifies the activation of the operator control capability from the RSW and the deactivation of the operator control capability from the MCR for the associated safety-related division and nonsafety-related control capability.

ITAAC 2.5.02.08b.ii is completed as a combination of:

  • Factory Accepta nee Test
  • Testing of switches in the MCR, RSW, and MCR/RSW Transfer Panel to verify proper wiring and correct digital output is received
  • Site software installation and regression test- Hardware and software integration verification and testing of post system delivery changes The Factory Acceptance Testing (FAT)follows the guidance of NEI 08-01 Section 9.4 for the as-built tests to be performed at other than the final installed location. The FAT was performed in accordance with PMS Software Program Manual WCAP-16096(Reference 1), PMS Test Plan APP-PMS-T5-001 (Reference 2) and applicable Codes and Standards described in Vogtle 3 and 4 Update Final Safety Analysis Report(UFSAR)Section 7.4. Test results are documented

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 3 of 11 in AP1000 Protection and Safety Monitoring System Qualified Data Processing System Channel Integration Test Reports (References 5 and 6 and 13 through 18).

The FAT included testing of PMS inputs and outputs, logic, and functionality. During this test, the initial conditions for the test scenarios are established and process parameters are simulated to get the expected outputs.

The test initially confirms that an alarm actuates in the MCR and RSW when process parameters are simulated for each transfer switch placed in the Remote Shutdown Room (RSR)

ENABLE position. The test procedure used for this testing is PMS Miscellaneous Test Procedure SV3/4-PMS-T1P-034 (References 3 and 4). The results of the testing are documented in the FAT Test Report SV3/4-PMS-T2R-034 (References 5 and 6). Attachment A provides a listing of the test cases to confirm the alarm actuation.

The test continues with all transfer switches simulated in the RSR ENABLED position. During this portion of the test, the process parameters are simulated to confirm the operator control capability is transferred from the MCR to the RSW and all MCR operator control capability is deactivated. The multiple test procedures that are used for this testing are PMS Channel Integration Test Procedures SV3/4-PMS-T1P-007(References 7 and 8), SV3/4-PMS-T1P-008 (References 9 and 10), and SV3/4-PMS-T1P-018 (References 11 and 12). The results of the testing are documented in the FAT Test Reports SV3/4-PMS-T2R-007(References 13 and 14),

SV3/4-PMS-T2R-008 (References 15 and 16), and SV3/4-PMS-T2R-018 (References 17 and 18). Attachment B provides a listing of the test cases to confirm the activation of RSW controls and the deactivation of MCR controls.

Site testing of each switch is performed to verify the switch is properly wired and the correct digital output is received. This test places each switch in the MCR, RSW, and MCR/RSW Transfer Panel in all switch positions and verifies proper indicating lights are received in computer cabinets. Unit 3 component test package work orders 1051893, 1054772,1058836, and 1060105 (References 19, 20, 21, and 22) and Unit 4 component test package work orders SNCWWWWWW,SNCXXXXXX, SNCYYYYYY, and SNCZZZZZZ (References 23, 24, 25, and

26) document completion of switch position testing portion of this ITAAC. Attachment C provides a listing switches that are tested in each test package work order.

Additional hardware and software installation and associated inspections and testing are performed on-site to verify that the cabinets are intact and functional in accordance with Units 3 and 4 for applicable Field Change Notifications(FGNs) API000 Vogtle Unit 3 PMS Initial Software Installation - Software Release 8.7.0.1 and API000 Vogtle Unit 4 PMS Initial Software Installation - Software Release 8.7.0.1 (References 27 and 28). Reference 27 and 28 also include steps that confirm and document successful software load and further confirm the physical properties of the as-built PMS. The Field Change Notification are implemented using Unit 3 component test package work order SNCAAAAAA and Unit 4 component test package work order SNCBBBBBB (References 29 and 30). A regression analysis (i.e., change evaluation) is performed post-delivery and installation for hardware changes (references 31 and

32) and software changes (Reference 33)to determine if additional testing is needed for the as-built system.

The completed Unit 3 and Unit 4 FAT (References 5,6, and 13 through 18), switch testing (References 19 through 26), FCNs (References 27 and 30), and regression test results (References 31 through 33) confirm actuation of each transfer switch results in an alarm in the

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 4 of 11 MCR and RSW,the activation of operator control capability from the RSW,and the deactivation of operator control capability from the MCR for the associated safety-related division and nonsafety-related control capability.

References 1 through 33 are available for NRC inspection as part of the ITAAC 2.5.02.08b.ii Unit 3 and 4 Completion Packages (References 34 and 35).

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 NRC inspection)

1. WCAP-16096 "Software Program Manual for Common Q Systems"
2. APP-PMS-T5-001 "AP1000 Protection and Safety Monitoring System Test Plan"
3. SV3-PMS-T1P-034,"AP1000 Protection and Safety Monitoring System Maintenance and Test Panel Miscellaneous Test Procedure"
4. SV4-PMS-T1 P-034,"AP1000 Protection and Safety Monitoring System Maintenance and Test Panel Miscellaneous Test Procedure"
5. SV3-PMS-T2R-034,"AP1000 Protection and Safety Monitoring System Maintenance and Test Panel Miscellaneous Test Report"
6. SV4-PMS-T2R-034,"AP1000 Protection and Safety Monitoring System Maintenance and Test Panel Miscellaneous Test Report"
7. SV3-PMS-T1P-007,"AP1000 Protection and Safety Monitoring System Reactor Trip Channel Integration Test Procedure"
8. SV4-PMS-T1 P-007,"AP1000 Protection and Safety Monitoring System Reactor Trip Channel Integration Test Procedure"
9. SV3-PMS-T1P-008 "AP1000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Procedure"
10. SV4-PMS-T1P-008 "API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Procedure"
11. SV3-PMS-T1P-018 "API000 Protection and Safety Monitoring I/O Channel Accuracy Channel Integration Test Procedure" 12."SV4-PMS-T1P-018 "API000 Protection and Safety Monitoring I/O Channel Accuracy Channel Integration Test Procedure"
13. SV3-PMS-T2R-007,"AP1000 Protection and Safety Monitoring System Reactor Trip Channel Integration Test Report"
14. SV4-PMS-T2R-007,"API000 Protection and Safety Monitoring System Reactor Trip Channel Integration Test Report"
15. S\/3-PMS-T2R-008 "API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Report"
16. SV4-PMS-T2R-008 "API000 Protection and Safety Monitoring System System-Level Engineered Safety Features Channel Integration Test Report"
17. SV3-PMS-T2R-018 "API000 Protection and Safety Monitoring I/O Channel Accuracy Channel Integration Test Report"
18. SV4-PMS-T2R-018 "API000 Protection and Safety Monitoring I/O Channel Accuracy Channel Integration Test Report"

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 5 of 11

19. 1051893, "Perform Component I/O Testing on Listed PMS Components"
20. 1054772, "Perform B-GEN-ITPCI-006 for the Main Control Room & Remote Shutdown Room" 21.1058836,"MCR/RSR Transfer Panel"
22. 1060105, "Perform component test B-GEN-ITPCI-006 for DOS"
23. SNCWWWWWW
24. SNCXXXXXX
25. SNCYYYYYY
26. SNCZZZZZZ
27. Unit 3 Field Change Notice "API000 Vogtle Unit 3 PMS Initial Software Installation -

Software Release 8.7.0.1"

28. Unit 4 Field Change Notice "API000 Vogtle Unit 4 PMS Initial Software Installation -

Software Release 8.7.0.1"

29. SNCAAAAAA
30. SNCBBBBBB
31. GIC-AP1000-HEDS-19-001, Rev. 0 "Regression Testing Analysis for Vogtle Unit 3 Protection and Safety Monitoring System (PMS)Baseline 8.2 to 8.4 Hardware Modifications Performed at Site"(Unit 3)
32. GIC-AP1000-HEDS-19-001, Rev. 0 "Regression Testing Analysis for Vogtle Unit 4 Protection and Safety Monitoring System (PMS) Baseline 8.2 to 8.4 Hardware Modifications Performed at Site"(Unit 4)
33. APP-PMS-T2R-050,"API000 Protection and Safety Monitoring System Channel Integration Test Integrated System Validation Test Report"
34. ITAAC 2.5.02.08b.ii-U3-CP-Rev0, "ITAAC Completion Package"
35. ITAAC 2.5.02.08b.ii-U4-CP-Rev0, "ITAAC Completion Package"
36. NEI 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52"

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 6 of 11 Attachment A Factory Acceptance Test - Test Cases MGR/RSR Transfer Panel(OCS-JW-001)Switches Alarm Switch Description Switch Tag PMS-T2R-034 Test Cases PLS 1 PLS-HS402A PLS II PLS-HS402B MGR/RSR Xfr Panel PMS Div A PMS-HS401 TPS34-03.5 MGR/RSR Xfr Panel PMS Div 8 PMS-HS402 Divisions A, B, G, D MGR/RSR Xfr Panel PMS Div G PMS-HS403 MGR/RSR Xfr Panel PMS Div D PMS-HS404 Attachment B Factory Acceptance Test - Test Cases RSW Activation / MCR Deactivation Test(PM S-T2R-007)

Switch Description MCR Switch RSW Switch PMS-T2R-007 Tag Tag Test Case Safeguards Actuation PMS-HS033 DDS-HS318 TPS01A-19.1 TPS01B-19.1 TPS01G-19.1 TPS01D-19.1 Safeguards Actuation PMS-HS034 TPS01A-19.1 TPS01B-19.1 TPS01G-19.1 TPS01D-19.1 RSW Activation / MCR Deactivation Test(PM S-T2R-008)

Switch Description MCR Switch RSW Switch PMS-T2R-008 Tag Tag Test Cases ADS Stages 1-3 Actuation PMS-HS001 DDS-HS301 TPS02A-05.1 PMS-HS101 TPS02B-05.1 TPS02G-05.1 TPS02D-05.1 ADS Stages 1-3 Actuation PMS-HS002 DDS-HS302 TPS02A-05.1 PMS-HS102 TPS02B-05.1 TPS02G-05.1 TPS02D-05.1 ADS Stage 4 Actuation PMS-HS003 DDS-HS303 TPS02A-05.4 PMS-HS103 TPS02B-05.4 TPS02G-05.4 TPS02D-05.4 ADS Stage 4 Actuation PMS-HS004 DDS-HS304 TPS02A-05.4 PMS-HS104 TPS02B-05.4 TPS02G-05.4 TPS02D-05.4

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 7 of 11 RSW Activation / MGR Deactivation Test(PMS-T2R-008)(con't)

Switch Description MGR Switch RSW Switch PMS-T2R-008 Tag Tag Test Cases Containment Recirculation PMS-HS005 DDS-HS305 TPS02A-10.1 PMS-HS105 TPS02B-10.1 TPS02C-10.1 TPS02D-10.1 Containment Recirculation PMS-HS006 DDS-HS306 TPS02A-10.1 PMS-HS106 TPS02B-10.1 TPS02C-10.1 TPS02D-10.1 IRWST Injection PMS-HS007 DDS-HS307 TPS02A-03 PMS-HS107 TPS02B-03 TPS02C-03 TPS02D-03 IRWST Injection PMS-HS008 DDS-HS308 TPS02A-03 PMS-HS108 TPS02B-03 TPS02C-03 TPS02D-03 RMS Isolation PMS-HS013 DDS-HS313 TPS02A-21.1 PMS-HS113 TPS02B-21.1 TPS02D-21.1 RNS Isolation PMS-HS014 DDS-HS314 TPS02A-21.1 PMS-HS114 TPS02B-21.1 TPS02D-21.1 CMT Actuation PMS-HS015 DDS-HS315 TPS02A-04.1 TPS02B-04.1 TPS02C-04.1 TPS02D-04.1 CMT Actuation PMS-HS016 TPS02A-04.1 TPS02B-04.1 TPS02C-04.1 TPS02D-04.1 Containment Cooling PMS-HS017 DDS-HS317 TPS02A-13 TPS02B-13 TPS02C-13 Containment Cooling PMS-HS018 TPS02A-13 TPS02B-13 TPS02C-13 Main Steamline Isolation PMS-HS021 DDS-HS321 TPS02B-11.1 TPS02D-11.1 Main Steamline Isolation PMS-HS022 TPS02B-11.1 TPS02D-11.1 SG Relief Isolation PMS-HS041 DDS-HS322 TPS02B-25.1 TPS02D-25.1 SG Relief Isolation PMS-HS042 TPS02B-25.1 TPS02D-25.1

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 8 of 11 RSW Activation IMGR Deactivation Test(PMS-T2R-008)(con't)

Switch Description MGR Switch RSW Switch PMS-T2R-008 Tag Tag Test Cases PRHR Actuation PMS-HS023 DDS-HS323 TPS02A-08.1 TPS02B-08.1 TPS02D-08.1 PRHR Actuation PMS-HS024 TPS02A-08.1 TPS02B-08.1 TPS02D-08.1 Containment Isolation PMS-HS027 DDS-HS327 TPS02A-02 TPS02B-02 TPS02C-02 TPS02D-02 Containment Isolation PMS-HS028 TPS02A-02 TPS02B-02 TPS02C-02 TPS02D-02 Makeup Isolation PMS-HS029 DDS-HS329 TPS02A-16.2 TPS02D-16.2 Makeup Isolation PMS-HS030 TPS02A-16.2 TPS02D-16.2 Feedwater Isolation PMS-HS031 DDS-HS331 TPS02B-07.1 TPS02D-07.1 Feedwater Isolation PMS-HS032 TPS02B-07.1 TPS02D-07.1 Steam Dump Mode Control PMS-HS035 DDS-HS335 TPS02B-17.1 TPS02D-17.1 Steam Dump Mode Control PMS-HS036 TPS02B-17.1 TPS02D-17.1 Steam Dump Stage 1 Cooldown PMS-HS037 DDS-HS337 TPS02B-17.2 TPS02D-17.21 Steam Dump Stage 1 Cooldown PMS-HS038 TPS02B-17.2 TPS02D-17.2 Steam Dump Stage 2 Cooldown PMS-HS039 DDS-HS339 TPS02B-17.3 TPS02D-17.3 Steam Dump Stage 2 Cooldown PMS-HS040 TPS02B-17.3 TPS02D-17.3 Containment Vacuum Relief PMS-HS044 DDS-HS344 TPS02A-27 TPS02C-27 Containment Vacuum Relief PMS-HS045 TPS02A-27 TPS02C-27

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 9 of 11 RSW Activation / MGR Deactivation Test(P MS-T2R-018)

Switch Description MGR Switch RSW Switch PMS-T2R-018 Tag Tag Test Gases Reactor Head Vent V150A PMS-HS009 DDS-HS309 TPS05A-01.006 PMS-HS109 DDS-HS340 Reactor Head Vent V150B PMS-HS010 DDS-HS310 TPS05B-01.010 PMS-HS110 DDS-HS341 Reactor Head Vent V150C PMS-HS011 DDS-HS311 TPS05C-01.010 PMS-HS111 DDS-HS342 Reactor Head Vent V1 SOD PMS-HS012 DDS-HS312 TPS05D-01.006 PMS-HS112 DDS-HS343 Attachment0 Test Package Work Orders Work Order 1051893(U3)/ SNGWWWrwww(U4)

Switch Description MGR Switch Tag ADS Stages 1-3 Actuation PMS-HS001 ADS Stages 1-3 Actuation PMS-HS002 ADS Stage 4 Actuation PMS-HS003 ADS Stage 4 Actuation PMS-HS004 Containment Recirculation PMS-HSOOS Containment Recirculation PMS-HS006 IRWST Injection PMS-HS007 IRWST Injection PMS-HSOOS Reactor Head Vent VI50A PMS-HS009 Reactor Head Vent VI SOB PMS-HS010 Reactor Head Vent VISOC PMS-HS011 Reactor Head Vent VISOD PMS-HS012 RNS Isolation PMS-HS013 RMS Isolation PMS-HS014 CMT Actuation PMS-HS01S CMT Actuation PMS-HS016 Containment Cooling PMS-HS017 Containment Cooling PMS-HS018 Main Steamline Isolation PMS-HS021 Main Steamline Isolation PMS-HS022 PRHR Actuation PMS-HS023 PRHR Actuation PMS-HS024 Containment Isolation PMS-HS027 Containment Isolation PMS-HS028 Makeup Isolation PMS-HS029 Makeup Isolation PMS-HS030 Feedwater Isolation PMS-HS031 Feedwater Isolation PMS-HS032 Safeguards Actuation PMS-HS033 Safeguards Actuation PMS-HS034

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 10 of 11 Work Order 1051893(U3)/ SNCWWWWVl/W(U4)(con't)

Switch Description MGR Switch Tag Steam Dump Mode Control PMS-HS035 Steam Dump Mode Control PMS-HS036 Steam Dump Stage 1 Cooldown PMS-HS037 Steam Dump Stage 1 Cooldown PMS-HS038 Steam Dump Stage 2 Cooldown PMS-HS039 Steam Dump Stage 2 Cooldown PMS-HS040 SG Relief Isolation PMS-HS041 SG Relief Isolation PMS-HS042 Containment Vacuum Relief PMS-HS044 Containment Vacuum Relief PMS-HS045 ADS Stages 1-3 Actuation PMS-HS101 ADS Stages 1-3 Actuation PMS-HS102 ADS Stage 4 Actuation PMS-HS103 ADS Stage 4 Actuation PMS-HS104 Containment Recirculation PMS-HS105 Containment Recirculation PMS-HS106 IRWST Injection PMS-HS107 IRWST Injection PMS-HS108 Reactor Head Vent VI50A PMS-HS109 Reactor Head Vent VI506 PMS-HS110 Reactor Head Vent VI50C PMS-HS111 Reactor Head Vent VI SOD PMS-HS112 RNS Isolation PMS-HS113 RNS Isolation PMS-HS114 Work Order 1054772(U3)/ SNCXXXXXX(U4)

Switch Description Switch Tag PLS 1 PLS-HS402A PLS II PLS-HS402B Work Order 1058836(U3)/ SNCYYYYYY(U4)

Switch Description Switch Tag MCR/RSR Xfr Panel PMS Div A PMS-HS401 MCR/RSR Xfr Panel PMS Div 8 PMS-HS402 MCR/RSR Xfr Panel PMS Div C PMS-HS403 MCR/RSR Xfr Panel PMS Div D PMS-HS404 Work Order 1060105(U3)/ SNCZZZZZZ(U4)

Switch Description RSW Switch Tag ADS Stages 1-3 Actuation DDS-HS301 ADS Stages 1-3 Actuation DDS-HS302 ADS Stage 4 Actuation DDS-HS303 ADS Stage 4 Actuation DDS-HS304 Containment Recirculation DDS-HS305 Containment Recirculation DDS-HS306

U.S. Nuclear Regulatory Commission ND-19-1122 Enclosure Page 11 of 11 Work Order 1060105(U3)/ SNCZZZZZZ(U4)(con't)

Switch Description RSW Switch Tag IRWST Injection DDS-HS307 IRWST Injection DDS-HS308 Reactor Head Vent VI50A DDS-HS309 Reactor Head Vent VISOB DDS-HS310 Reactor Head Vent VI SCO DDS-HS311 Reactor Head Vent VI SOD DDS-HS312 RNS Isolation DDS-HS313 RNS Isolation DDS-HS314 GMT Actuation DDS-HS31S Containment Cooling DDS-HS317 Safeguards Actuation DDS-HS318 Main Steamllne Isolation DDS-HS321 SG Relief Isolation DDS-HS322 PRHR Actuation DDS-HS323 Containment Isolation DDS-HS327 Makeup Isolation DDS-HS329 Feedwater Isolation DDS-HS331 Steam Dump Mode Control DDS-HS33S Steam Dump Stage 1 Cooldown DDS-HS337 Steam Dump Stage 2 Cooldown DDS-HS339 Reactor Head Vent VISOA DDS-HS340 Reactor Head Vent VI SOB DDS-HS341 Reactor Head Vent VISOC DDS-HS342 Reactor Head Vent VI SOD DDS-HS343 Containment Vacuum Relief DDS-HS344

Retrieved from "https://kanterella.com/w/index.php?title=ND-19-1122,_Unit_4_Notice_of_Uncompleted_ITAAC_225-days_Prior_to_Initial_Fuel_Load_Item_2.5.02.08b.ii_(Index_Number_543)&oldid=2522942"