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| issue date = 11/08/2012
| issue date = 11/08/2012
| title = 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification.
| title = 2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification.
| author name = Piplica N C
| author name = Piplica N
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Reactor Protection Setpoint Verification Instruction No: 2-PTI-099-06 Revision No: 0000 PREPARED BY: Nicholas C. Piplica I 4. 4L -DATE:.___./o_/
{{#Wiki_filter:WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE:                   Reactor Protection Setpoint Verification Instruction No:                     2-PTI-099-06 Revision No:                           0000 PREPARED BY:             Nicholas C.Piplica I PRINT NAME / SIGNATURE
__PRINT NAME / SIGNATURE REVIEWED BY: Mark D. Runion / /*A-J A), .- DATE: L PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No: / -- -JTG CHAIRMAN:
: 4.       4L   -       DATE:.___./o_/     __
A-DATE: APPROVED BY: DATE: di -'PREOFIOAL TARU'PMANAGEý TEST RESULTS APPROVAL JTG MEETING No: JTG CHAIRMAN:
REVIEWED BY:             Mark D. Runion / /*A-J A),               .-         DATE: J*L#/'      L PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No: / -- -
DATE: APPROVED BY: DATE: PREOPERATIONAL STARTUP MANAGER SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010 WBN REACTOR PROTECTION SETPOINT 2-PTI-99-06.
JTG CHAIRMAN:                         A-DATE:
Unit 2 VERIFICATION Rev. 0000 Page 2 of 148 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange 0000 -I f I/ I ALL Initial issue based on PTI-099-06 for Unit 1.
APPROVED BY:                                                           DATE: di       -'
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 3 of 148 Table of Contents
PREOFIOAL TARU'PMANAGEý TEST RESULTS APPROVAL JTG MEETING No:
JTG CHAIRMAN:                                                           DATE:
APPROVED BY:                                                           DATE:
PREOPERATIONAL STARTUP MANAGER SMP-8.0, Administration of Preoperational Test instructions, Appendix B                   12/07/2010


==1.0 INTRODUCTION==
WBN          REACTOR PROTECTION SETPOINT            2-PTI-99-06.
Unit 2                VERIFICATION                  Rev. 0000 Page 2 of 148 Revision Log Revision                Affected or Change      Effective    Page Number          Date    Numbers              Description of RevisionlChange 0000    -  f I I/    I  ALL        Initial issue based on PTI-099-06 for Unit 1.


......................................................................................................
WBN                    REACTOR PROTECTION SETPOINT                                              2-PTI-099-06 Unit 2                                     VERIFICATION                                          Rev. 0000 Page 3 of 148 Table of Contents
6 1.1 Test Objectives
........................................................................................................
6 1 .2 S co p e ............................................................................................................................
6


==2.0 REFERENCES==
==1.0   INTRODUCTION==
......................................................................................................                    6 1.1  Test Objectives ........................................................................................................              6 1.2  S co p e ............................................................................................................................ 6


........................................................................................................
==2.0  REFERENCES==
6 2.1 Performance References  
........................................................................................................                    6 2.1   Performance References ........................................................................................                       6 2.2   Developmental References ....................................................................................                         12 3.0   PRECAUTIONS AND LIMITATIONS ....................................................................                                     14 4.0   PREREQUISITE ACTIONS ....................................................................................                             15 4.1   Preliminary Actions .................................................................................................                 15 4.2   Special Tools, Measuring and Test Equipment, Parts, and Supplies ...................... 16 4.3   Field Preparations ..................................................................................................                 16 4.4   Approvals and Notifications ...................................................................................                       16 5.0   ACCEPTANCE CRITERIA ....................................................................................                             17 5.1   Reactor Trips ..............................................................................................................         17 5.2   Engineered Safety Features Actuations ..................................................................                             18 6.0   PERFORMANCE ....................................................................................................                     19 6.1   Reactor Trips ..............................................................................................................         19 6.2   Engineered Safety Features Actuations ..................................................................                             27 7.0   POST PERFORMANCE ACTIVITY ......................................................................                                     31 8.0   RECORDS ..................................................................................................................           31 Appendix A:         Test Procedures / Instructions Reference Review ............................                                           32 Table 1:             Plant Instruction and PTI Verification of JTG Concurrence ........................................................................................                   33 Data Sheet 1:       Power Range High Neutron Flux Trip Setpoint Verification ...........................................................................................               38 Data Sheet 2:       Intermediate Range High Neutron Flux Trip Setpoint Verification ..........................................................................................               40 Data Sheet 3:       Source Range High Neutron Flux Trip Setpoint Verification ..........................................................................................               41
........................................................................................
6 2.2 Developmental References  
....................................................................................
12 3.0 PRECAUTIONS AND LIMITATIONS  
....................................................................
14 4.0 PREREQUISITE ACTIONS ....................................................................................
15 4.1 Preliminary Actions .................................................................................................
15 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ......................
16 4.3 Field Preparations  
..................................................................................................
16 4.4 Approvals and Notifications  
...................................................................................
16 5.0 ACCEPTANCE CRITERIA ....................................................................................
17 5.1 Reactor Trips ..............................................................................................................
17 5.2 Engineered Safety Features Actuations  
..................................................................
18 6.0 PERFORMANCE  
....................................................................................................
19 6.1 Reactor Trips ..............................................................................................................
19 6.2 Engineered Safety Features Actuations  
..................................................................
27 7.0 POST PERFORMANCE ACTIVITY ......................................................................
31 8.0 RECORDS ..................................................................................................................
31 Appendix A: Test Procedures  
/ Instructions Reference Review ............................
32 Table 1: Plant Instruction and PTI Verification of JTG Concurrence  
........................................................................................
33 Data Sheet 1: Power Range High Neutron Flux Trip Setpoint Verification  
...........................................................................................
38 Data Sheet 2: Intermediate Range High Neutron Flux Trip Setpoint Verification  
..........................................................................................
40 Data Sheet 3: Source Range High Neutron Flux Trip Setpoint Verification  
..........................................................................................
41 WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 4 of 148 Data Sheet 4: Data Sheet 5: Data Sheet 6: Data Sheet 7: Data Sheet 8: Data Sheet 9: Data Sheet 10: Data Sheet 11: Data Sheet 12: Data Sheet 13: Data Sheet 14: Data Sheet 15: Data Sheet 16: Data Sheet 17: Data Sheet 18: Data Sheet 19: Data Sheet 20: Table of Contents (continued)
Power Range High Positive Neutron Flux Rate Trip Setpoint Verification
.............................................................................
42 Overtemperature/Overpower Delta T Trip Setpoint Verification
..........................................................................................
44 Pressurizer Low Pressure Trip Setpoint Verification
........................
74 Pressurizer High Pressure Trip Setpoint Verification
.......................
77 Pressurizer High Water Level Trip Setpoint Verification
...................
78 Low Reactor Coolant Flow Trip Setpoint Verification
.......................
79 Reactor Coolant Pump Undervoltage Trip Setpoint Verification
.............................................................................................
83 Reactor Coolant Pump Underfrequency Trip Setpoint Verification
.............................................................................................
85 Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification
.............................................................................
87 Reactor Trip on Turbine Trip Setpoint Verification
..............................
100 Reactor Trip System Permissive and Interlock Setpoint V erification
..............................................................................................
102 Low Pressurizer Pressure Safety Injection Setpoint V erification
..............................................................................................
117 Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification
...............................................................
118 Containment High Pressure Safety Injection Setpoint V erification
..............................................................................................
127 Safety Injection Manual Reset Time Delay Setpoint V erification
..............................................................................................
128 High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification
...............................................................
130 High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation Setpoint Verification
...............................................................................
137 Miscellaneous ESFAS Setpoint Verification
.........................................
139 Data Sheet 21:
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 5 of 148 Table of Contents (continued)
Attachment Index ....................................................................................
148 Table 2:
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 6 of 148


==1.0 INTRODUCTION==
WBN            REACTOR PROTECTION SETPOINT                                        2-PTI-099-06 Unit 2                      VERIFICATION                                          Rev. 0000 Page 4 of 148 Table of Contents (continued)
Data Sheet 4:  Power Range High Positive Neutron Flux Rate Trip Setpoint Verification .............................................................................          42 Data Sheet 5:  Overtemperature/Overpower Delta T Trip Setpoint Verification ..........................................................................................      44 Data Sheet 6:  Pressurizer Low Pressure Trip Setpoint Verification ........................ 74 Data Sheet 7:  Pressurizer High Pressure Trip Setpoint Verification .......................                                  77 Data Sheet 8:  Pressurizer High Water Level Trip Setpoint Verification ...................                                  78 Data Sheet 9:  Low Reactor Coolant Flow Trip Setpoint Verification .......................                                  79 Data Sheet 10: Reactor Coolant Pump Undervoltage Trip Setpoint Verification ............................................................................................. 83 Data Sheet 11: Reactor Coolant Pump Underfrequency Trip Setpoint Verification ............................................................................................. 85 Data Sheet 12: Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification .............................................................................          87 Data Sheet 13: Reactor Trip on Turbine Trip Setpoint Verification ..............................                            100 Data Sheet 14: Reactor Trip System Permissive and Interlock Setpoint V erification .............................................................................................. 102 Data Sheet 15: Low Pressurizer Pressure Safety Injection Setpoint V erification .............................................................................................. 117 Data Sheet 16: Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification ...............................................................              118 Data Sheet 17: Containment High Pressure Safety Injection Setpoint V erification .............................................................................................. 127 Data Sheet 18: Safety Injection Manual Reset Time Delay Setpoint V erification .............................................................................................. 128 Data Sheet 19: High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification ...............................................................              130 Data Sheet 20: High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation Setpoint Verification ...............................................................................        137 Data Sheet 21: Miscellaneous ESFAS Setpoint Verification .........................................                          139


1.1 Test Objectives Verify initial setpoint adjustments have been made prior to plant startup and are in agreement with Watts Bar Nuclear Plant design requirements.
WBN        REACTOR PROTECTION SETPOINT                                  2-PTI-099-06 Unit 2              VERIFICATION                                        Rev. 0000 Page 5 of 148 Table of Contents (continued)
1.2 Scope The scope of this instruction verifies setpoints associated with Reactor Trips and the Engineered Safety Features Actuations.
Table 2:    Attachment Index .................................................................................... 148


==2.0 REFERENCES==
WBN              REACTOR PROTECTION SETPOINT              2-PTI-099-06 Unit 2                      VERIFICATION                  Rev. 0000 Page 6 of 148


2.1 Performance References
==1.0  INTRODUCTION==
: 1. SMP-9.0, Watts Bar Nuclear Plant Unit 2 -Conduct of Test 2. 2-SI-1-1, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel I Loop 2-LPP-1-2A (P-514)3. 2-SI-1-2, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel II Loop 2-LPP-1-2B (P-515)4. 2-SI-1-3, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel IV Loop 2-LPP-1-5 (P-516)5. 2-SI-1-4, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel I Loop 2-LPP-1-9A (P-524)6. 2-SI-1-5, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel II Loop 2-LPP-1-9B (P-525)7. 2-SI-1-6, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel III Loop 2-LPP-1-12 (P-526)8. 2-SI-1-7, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel I Loop 2-LPP-1-20A (P-534)9. 2-SI-1-8, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel II Loop 2-LPP-1-20B (P-535)10. 2-SI-1-9, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel III Loop 2-LPP-1-23 (P-536)11. 2-SI-1-10, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel I Loop 2-LPP-1-27A (P-544)
 
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 7 of 148 2.1 Performance References (continued)
1.1  Test Objectives Verify initial setpoint adjustments have been made prior to plant startup and are in agreement with Watts Bar Nuclear Plant design requirements.
: 12. 2-SI-1-11, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel II Loop 2-LPP-1-27B (P-545)13. 2-S1-1-12, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel IV Loop 2-LPP-1-30 (P-546)14. 2-SI-1-72, 18 Month Channel Calibration Turbine Impulse Chamber Pressure Channel II, Loop 2-LPP-1-72 (P-506)15. 2-SI-1-73, 18 Month Channel Calibration Turbine Impulse-Chamber Pressure Channel I, Loop 2-LPP-1-73 (P-505)16. 2-SI-3-1, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel II Loop 2-LPL-3-38 (L-519)17. 2-SI-3-2, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel III Loop 2-LPL-3-39 (L-518)18. 2-SI-3-3, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel IV Loop 2-LPL-3-42 (L-517)19. 2-SI-3-4, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel II Loop 2-LPL-3-51 (L-529)20. 2-SI-3-5, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel III Loop 2-LPL-3-52 (L-528)21. 2-SI-3-6, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel IV Loop 2-LPL-3-55 (L-527)22. 2-SI-3-7, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel II Loop 2-LPL-3-93 (L-539)23. 2-SI-3-8, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel III Loop 2-LPL-3-94 (L-538)24. 2-SI-3-9, 18 Month Channel Calibration.Steam Generator 3 Narrow Range Level Channel IV Loop 2-LPL-3-97 (L-537)25. 2-SI-3-10, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel II Loop 2-LPL-3-106 (L-549)26. 2-SI-3-11, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel III Loop 2-LPL-3-107 (L-548)27. 2-SI-3-12, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel IV Loop 2-LPL-3-1 10 (L-547)
1.2  Scope The scope of this instruction verifies setpoints associated with Reactor Trips and the Engineered Safety Features Actuations.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 8 of 148 2.1 Performance References (continued)
 
==2.0  REFERENCES==
 
2.1   Performance References
: 1. SMP-9.0, Watts Bar Nuclear Plant Unit 2 - Conduct of Test
: 2. 2-SI-1-1, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel I Loop 2-LPP-1-2A (P-514)
: 3. 2-SI-1-2, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel II Loop 2-LPP-1-2B (P-515)
: 4. 2-SI-1-3, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel IV Loop 2-LPP-1-5 (P-516)
: 5. 2-SI-1-4, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel I Loop 2-LPP-1-9A (P-524)
: 6. 2-SI-1-5, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel II Loop 2-LPP-1-9B (P-525)
: 7. 2-SI-1-6, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel III Loop 2-LPP-1-12 (P-526)
: 8. 2-SI-1-7, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel I Loop 2-LPP-1-20A (P-534)
: 9. 2-SI-1-8, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel II Loop 2-LPP-1-20B (P-535)
: 10. 2-SI-1-9, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel III Loop 2-LPP-1-23 (P-536)
: 11. 2-SI-1-10, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel I Loop 2-LPP-1-27A (P-544)
 
WBN           REACTOR PROTECTION SETPOINT             2-PTI-099-06 Unit 2                   VERIFICATION                 Rev. 0000 Page 7 of 148 2.1   Performance References (continued)
: 12. 2-SI-1-11, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel II Loop 2-LPP-1-27B (P-545)
: 13. 2-S1-1-12, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel IV Loop 2-LPP-1-30 (P-546)
: 14. 2-SI-1-72, 18 Month Channel Calibration Turbine Impulse Chamber Pressure Channel II, Loop 2-LPP-1-72 (P-506)
: 15. 2-SI-1-73, 18 Month Channel Calibration Turbine Impulse-Chamber Pressure Channel I, Loop 2-LPP-1-73 (P-505)
: 16. 2-SI-3-1, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel II Loop 2-LPL-3-38 (L-519)
: 17. 2-SI-3-2, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel III Loop 2-LPL-3-39 (L-518)
: 18. 2-SI-3-3, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel IV Loop 2-LPL-3-42 (L-517)
: 19. 2-SI-3-4, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel II Loop 2-LPL-3-51 (L-529)
: 20. 2-SI-3-5, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel III Loop 2-LPL-3-52 (L-528)
: 21. 2-SI-3-6, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel IV Loop 2-LPL-3-55 (L-527)
: 22. 2-SI-3-7, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel II Loop 2-LPL-3-93 (L-539)
: 23. 2-SI-3-8, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel III Loop 2-LPL-3-94 (L-538)
: 24. 2-SI-3-9, 18 Month Channel Calibration.Steam Generator 3 Narrow Range Level Channel IV Loop 2-LPL-3-97 (L-537)
: 25. 2-SI-3-10, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel II Loop 2-LPL-3-106 (L-549)
: 26. 2-SI-3-11, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel III Loop 2-LPL-3-107 (L-548)
: 27. 2-SI-3-12, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel IV Loop 2-LPL-3-1 10 (L-547)
 
WBN             REACTOR PROTECTION SETPOINT           2-PTI-099-06 Unit 2                   VERIFICATION                 Rev. 0000 Page 8 of 148 2.1   Performance References (continued)
: 28. 2-SI-3-13, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel II, Loop 2-LPL-3-38T (L-519-549)
: 28. 2-SI-3-13, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel II, Loop 2-LPL-3-38T (L-519-549)
: 29. 2-SI-3-14, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel III, Loop 2-LPL-3-39T (L-518-548)
: 29. 2-SI-3-14, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel III, Loop 2-LPL-3-39T (L-518-548)
: 30. 2-SI-3-15, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel IV, Loop 2-LPL-3-42T (L-517-547)
: 30. 2-SI-3-15, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel IV, Loop 2-LPL-3-42T (L-517-547)
: 31. 2-SI-3-21, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2A-A Suction Header Pressure Switches 32. 2-SI-3-22, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2B-B Suction Header Pressure Switches 33. 2-SI-3-25, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2A Trip 34. 2-SI-3-26, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2B Trip 35. 2-SI-3-402, 18 Month Channel Calibration South Valve Vault Level Switch Channel I Loop 2-LPL-3-402
: 31. 2-SI-3-21, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2A-A Suction Header Pressure Switches
: 32. 2-SI-3-22, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2B-B Suction Header Pressure Switches
: 33. 2-SI-3-25, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2A Trip
: 34. 2-SI-3-26, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2B Trip
: 35. 2-SI-3-402, 18 Month Channel Calibration South Valve Vault Level Switch Channel I Loop 2-LPL-3-402
: 36. 2-SI-3-403, 18 Month Channel Calibration South Valve Vault Level Switch Channel III Loop 2-LPL-3-403
: 36. 2-SI-3-403, 18 Month Channel Calibration South Valve Vault Level Switch Channel III Loop 2-LPL-3-403
: 37. 2-SI-3-404, 18 Month Channel Calibration South Valve Vault Level Switch Channel IV Loop 2-LPL-3-404
: 37. 2-SI-3-404, 18 Month Channel Calibration South Valve Vault Level Switch Channel IV Loop 2-LPL-3-404
: 38. 2-SI-3-405, 18 Month Channel Calibration North Valve Vault Level Switch Channel I Loop 2-LPL-3-405
: 38. 2-SI-3-405, 18 Month Channel Calibration North Valve Vault Level Switch Channel I Loop 2-LPL-3-405
: 39. 2-SI-3-406, 18 Month Channel Calibration North Valve Vault Level Switch Channel Ill Loop 2-LPL-3-406
: 39. 2-SI-3-406, 18 Month Channel Calibration North Valve Vault Level Switch Channel Ill Loop 2-LPL-3-406
: 40. 2-SI-3-407, 18 Month Channel Calibration North Valve Vault Level Switch Channel IV Loop 2-LPL 407 41. 2-SI-30-42, 18 Month Channel Calibration Containment Pressure Channel IV Loop 2-LPP-30-42 (P-934)42. 2-SI-30-43, 18 Month Channel Calibration Containment Pressure Channel III Loop 2-LPP-30-43 (P-935)
: 40. 2-SI-3-407, 18 Month Channel Calibration North Valve Vault Level Switch Channel IV Loop 2-LPL 407
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 9 of 148 2.1 Performance References (continued)
: 41. 2-SI-30-42, 18 Month Channel Calibration Containment Pressure Channel IV Loop 2-LPP-30-42 (P-934)
: 43. 2-SI-30-44, 18 Month Channel Calibration Containment Pressure Channel II Loop 2-LPP-30-44 (P-936)44. 2-SI-30-45, 18 Month Channel Calibration Containment Pressure Channel I Loop 2-LPP-30-45 (P-937)45. 2-SI-63-1, 18 Month Channel Calibration Containment Sump Level Channel I Loop 2-LPL-63-180 (L-920)46. 2-SI-63-2, 18 Month Channel Calibration Containment Sump Level Channel II Loop 2-LPL-63-181 (L-921)47. 2-SI-63-3, 18 Month Channel Calibration Containment Sump Level Channel Ill Loop 2-LPL-63-182 (L-940)48. 2-SI-63-4, 18 Month Channel Calibration Containment Sump Level Channel IV Loop 2-LPL-63-183 (L-941)49. 2-SI-63-50, 18 Month Channel Calibration RWST Level Channel I Loop 2-LPL-63-50 (L-913)50. 2-SI-63-51, 18 Month Channel Calibration RWST Level Channel II Loop 2-LPL-63-51 (L-914)51. 2-SI-63-52, 18 Month Channel Calibration RWST Level Channel III Loop 2-LPL-63-52 (L-915)52. 2-SI-63-53, 18 Month Channel Calibration RWST Level Channel IV Loop 2-LPL-63-53 (L-916)53. 2-SI-68-1, 18 Month Channel Calibration RCS Loop 1 Delta T/Tavg Channel I. Loop 2-LPT-68-2 (T-411/412)
: 42. 2-SI-30-43, 18 Month Channel Calibration Containment Pressure Channel III Loop 2-LPP-30-43 (P-935)
 
WBN           REACTOR PROTECTION SETPOINT           2-PTI-099-06 Unit 2                   VERIFICATION                 Rev. 0000 Page 9 of 148 2.1   Performance References (continued)
: 43. 2-SI-30-44, 18 Month Channel Calibration Containment Pressure Channel II Loop 2-LPP-30-44 (P-936)
: 44. 2-SI-30-45, 18 Month Channel Calibration Containment Pressure Channel I Loop 2-LPP-30-45 (P-937)
: 45. 2-SI-63-1, 18 Month Channel Calibration Containment Sump Level Channel I Loop 2-LPL-63-180 (L-920)
: 46. 2-SI-63-2, 18 Month Channel Calibration Containment Sump Level Channel II Loop 2-LPL-63-181 (L-921)
: 47. 2-SI-63-3, 18 Month Channel Calibration Containment Sump Level Channel Ill Loop 2-LPL-63-182 (L-940)
: 48. 2-SI-63-4, 18 Month Channel Calibration Containment Sump Level Channel IV Loop 2-LPL-63-183 (L-941)
: 49. 2-SI-63-50, 18 Month Channel Calibration RWST Level Channel I Loop 2-LPL-63-50 (L-913)
: 50. 2-SI-63-51, 18 Month Channel Calibration RWST Level Channel II Loop 2-LPL-63-51 (L-914)
: 51. 2-SI-63-52, 18 Month Channel Calibration RWST Level Channel III Loop 2-LPL-63-52 (L-915)
: 52. 2-SI-63-53, 18 Month Channel Calibration RWST Level Channel IV Loop 2-LPL-63-53 (L-916)
: 53. 2-SI-68-1, 18 Month Channel Calibration RCS Loop 1 Delta T/Tavg Channel I.Loop 2-LPT-68-2 (T-411/412)
: 54. 2-81-68-2, 18 Month Channel Calibration RCS Loop 2 Delta T/Tavg Channel II Loop 2-LPT-68-25 (T-421/422)
: 54. 2-81-68-2, 18 Month Channel Calibration RCS Loop 2 Delta T/Tavg Channel II Loop 2-LPT-68-25 (T-421/422)
: 55. 2-SI-68-3, 18 Month Channel Calibration RCS Loop 3 Delta T/Tavg Channel Ill Loop 2-LPT-68-44 (T-431/432)
: 55. 2-SI-68-3, 18 Month Channel Calibration RCS Loop 3 Delta T/Tavg Channel Ill Loop 2-LPT-68-44 (T-431/432)
: 56. 2-SI-68-4, 18 Month Channel Calibration RCS Loop 4 Delta T/Tavg Channel IV Loop 2-LPT-68-67 (T-441/442)
: 56. 2-SI-68-4, 18 Month Channel Calibration RCS Loop 4 Delta T/Tavg Channel IV Loop 2-LPT-68-67 (T-441/442)
: 57. 2-SI-68-5, 18 Month Channel Calibration Pressurizer Pressure Channel I Loop 2-LPP-68-340 (P-455)58. 2-SI-68-6, 18 Month Channel Calibration Pressurizer Pressure Channel II Loop 2-LPP-68-334 (P-456)
: 57. 2-SI-68-5, 18 Month Channel Calibration Pressurizer Pressure Channel I Loop 2-LPP-68-340 (P-455)
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 10 of 148 2.1 Performance References (continued)
: 58. 2-SI-68-6, 18 Month Channel Calibration Pressurizer Pressure Channel II Loop 2-LPP-68-334 (P-456)
: 59. 2-SI-68-7, 18 Month Channel Calibration Pressurizer Pressure Channel Ill Loop 2-LPP-68-323 (P-457)60. 2-SI-68-8, 18 Month Channel Calibration Pressurizer Pressure Channel IV Loop 2-LPP-68-322 (P-458)61. 2-SI-68-9, 18 Month Channel Calibration Pressurizer Level Channel I Loop 2-LPL-68-339 (L-459)62. 2-SI-68-10, 18 Month Channel Calibration Pressurizer Level Channel II Loop 2-LPL-68-335 (L-460)63. 2-SI-68-11, 18 Month Channel Calibration Pressurizer Level Channel III Loop 2-LPL-68-320 (L-461)64. 2-SI-68-12, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel I Loop 2-LPF-68-6A (F-414)65. 2-SI-68-13, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel II Loop 2-LPF-68-6B (F-415)66. 2-SI-68-14, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel III Loop 2-LPF-68-6D (F-416)67. 2-SI-68-15, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel I Loop 2-LPF-68-29A (F-424)68. 2-SI-68-16, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel II Loop 2-LPF-68-29B (F-425)69. 2-SI-68-17, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel III Loop 2-LPF-68-29D (F-426)70. 2-SI-68-18, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel I Loop 2-LPF-68-48A (F-434)71. 2-SI-68-19, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel II Loop 2-LPF-68-48B (F-435)72. 2-SI-68-20, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel III Loop 2-LPF-68-48D (F-436)73. 2-SI-68-21, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel I Loop 2-LPF-68-71A (F-444)74. 2-SI-68-22, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel II Loop 2-LPF-68-71B (F-445)
 
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 11 of 148 2.1 Performance References (continued)
WBN           REACTOR PROTECTION SETPOINT             2-PTI-099-06 Unit 2                   VERIFICATION                 Rev. 0000 Page 10 of 148 2.1   Performance References (continued)
: 75. 2-SI-68-23, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel III Loop 2-LPF-68-71D (F-446)76. 2-SI-68-36, 18 Month Reactor Coolant Pump 1 Underfrequency Relay Calibration
: 59. 2-SI-68-7, 18 Month Channel Calibration Pressurizer Pressure Channel Ill Loop 2-LPP-68-323 (P-457)
: 60. 2-SI-68-8, 18 Month Channel Calibration Pressurizer Pressure Channel IV Loop 2-LPP-68-322 (P-458)
: 61. 2-SI-68-9, 18 Month Channel Calibration Pressurizer Level Channel I Loop 2-LPL-68-339 (L-459)
: 62. 2-SI-68-10, 18 Month Channel Calibration Pressurizer Level Channel II Loop 2-LPL-68-335 (L-460)
: 63. 2-SI-68-11, 18 Month Channel Calibration Pressurizer Level Channel III Loop 2-LPL-68-320 (L-461)
: 64. 2-SI-68-12, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel I Loop 2-LPF-68-6A (F-414)
: 65. 2-SI-68-13, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel II Loop 2-LPF-68-6B (F-415)
: 66. 2-SI-68-14, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel III Loop 2-LPF-68-6D (F-416)
: 67. 2-SI-68-15, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel I Loop 2-LPF-68-29A (F-424)
: 68. 2-SI-68-16, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel II Loop 2-LPF-68-29B (F-425)
: 69. 2-SI-68-17, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel III Loop 2-LPF-68-29D (F-426)
: 70. 2-SI-68-18, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel I Loop 2-LPF-68-48A (F-434)
: 71. 2-SI-68-19, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel II Loop 2-LPF-68-48B (F-435)
: 72. 2-SI-68-20, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel III Loop 2-LPF-68-48D (F-436)
: 73. 2-SI-68-21, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel I Loop 2-LPF-68-71A (F-444)
: 74. 2-SI-68-22, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel II Loop 2-LPF-68-71B (F-445)
 
WBN           REACTOR PROTECTION SETPOINT               2-PTI-099-06 Unit 2                   VERIFICATION                   Rev. 0000 Page 11 of 148 2.1   Performance References (continued)
: 75. 2-SI-68-23, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel III Loop 2-LPF-68-71D (F-446)
: 76. 2-SI-68-36, 18 Month Reactor Coolant Pump 1 Underfrequency Relay Calibration
: 77. 2-SI-68-37, 18 Month Reactor Coolant Pump 2 Underfrequency Relay Calibration
: 77. 2-SI-68-37, 18 Month Reactor Coolant Pump 2 Underfrequency Relay Calibration
: 78. 2-SI-68-38, 18 Month Reactor Coolant Pump 3 Underfrequency Relay Calibration
: 78. 2-SI-68-38, 18 Month Reactor Coolant Pump 3 Underfrequency Relay Calibration
Line 149: Line 146:
: 82. 2-SI-68-42, 18 Month Reactor Coolant Pump 3 Undervoltage Channel Calibration
: 82. 2-SI-68-42, 18 Month Reactor Coolant Pump 3 Undervoltage Channel Calibration
: 83. 2-SI-68-43, 18 Month Reactor Coolant Pump 4 Undervoltage Channel Calibration
: 83. 2-SI-68-43, 18 Month Reactor Coolant Pump 4 Undervoltage Channel Calibration
: 84. 2-SI-92-31, 18 Month Channel Calibration of Source Range, Intermediate Range, and Remote Shutdown Neutron Flux Channel I 85. 2-SI-92-32, 18 Month Channel Calibration of Source Range and Intermediate Range Channel II 86. 2-SI-92-41, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-41 87. 2-SI-92-42, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-42 88. 2-SI-92-43, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-43 89. 2-SI-92-44, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-44 90. 2-SI-47-28, 18 Month Channel Calibration Turbine Trip -Turbine Stop Valve Closure Channel I, (Channel 1, 11, 111, & IV) [2-ZS-47-28, 30, 32, & 34]
: 84. 2-SI-92-31, 18 Month Channel Calibration of Source Range, Intermediate Range, and Remote Shutdown Neutron Flux Channel I
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 12 of 148 2.1 Performance References (continued)
: 85. 2-SI-92-32, 18 Month Channel Calibration of Source Range and Intermediate Range Channel II
: 91. 2-SI-47-73, 18 Month Channel Calibration Turbine Trip -Low Fluid Oil Pressure Channel I Loop 2-PS-47-73-D
: 86. 2-SI-92-41, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-41
: 92. 2-SI-47-74, 18 Month Channel Calibration Turbine Trip -Low Fluid Oil Pressure Channel II Loop 2-PS-47-74-E
: 87. 2-SI-92-42, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-42
: 93. 2-SI-47-75, 18 Month Channel Calibration Turbine Trip -Low Fluid Oil Pressure Channel III Loop 2-PS-47-75-F
: 88. 2-SI-92-43, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-43
: 94. 2-SI-99-10-A, 62 Day Functional Test of SSPS Train A and Reactor Trip Breaker A 95. 2-SI-99-10-B, 62 Day Functional Test of SSPS Train B and Reactor Trip Breaker B 96. 2-PTI-099-05, NSSS Turbine Runback 97. 2-ATI-047A-02, Turbine Trips and Protections
: 89. 2-SI-92-44, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-44
: 98. SSD-2-LPP-2-1, Scaling and Setpoint Document Condenser Zone A Hotwell Narrow Range Pressure 99. SSD-2-LPP-2-7, Scaling and Setpoint Document Condenser Zone B Hotwell Narrow Range Pressure 100. Work Order 113725926, Unique one-time test for HP Turbine Impulse Chamber Pressure Control (C-7), CTN 2-001-12296-IU1-000 101. 2-47A630-98-205, Rev. 0 (ANT), DRA 56744-005, Rev. 0, DCS Software Control Block Parameters  
: 90. 2-SI-47-28, 18 Month Channel Calibration Turbine Trip - Turbine Stop Valve Closure Channel I, (Channel 1,11, 111, & IV) [2-ZS-47-28, 30, 32, & 34]
-Processor W205CP 2.2 Developmental References A. Final Safety Analysis Report (FSAR)- Amendment 109 1. Table 14.2.1, Sheet 57 of 89, Reactor Protection System Test Summary 2. Section 7.2, Reactor Trip System 3. Section 7.3, Engineered Safety Features Actuation System B. Documents 1. PTI-99-06, Rev. 0, Reactor Protection Setpoint Verification
 
: 2. 2-TSD-99-06, Rev. 1, Reactor Protection Setpoint Verification WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 13 of 148 2.2 Developmental References (continued)
WBN           REACTOR PROTECTION SETPOINT             2-PTI-099-06 Unit 2                     VERIFICATION                 Rev. 0000 Page 12 of 148 2.1   Performance References (continued)
: 3. WBN2-99-4003, Rev. 0, System Description For Reactor Protection System 4. WBN2-47-4002, Rev. 1, Turbogenerator System (Part 1) and Turbogenerator Control and Protection System (Part 2)
: 91. 2-SI-47-73, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel I Loop 2-PS-47-73-D
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 14 of 148 3.0 PRECAUTIONS AND LIMITATIONS A. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps must be re-verified and a Chronological Test Log (CTL) entry made.B. Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description is sufficient to identify the component.
: 92. 2-SI-47-74, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel II Loop 2-PS-47-74-E
If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14.
: 93. 2-SI-47-75, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel III Loop 2-PS-47-75-F
Make an entry in the CTL and continue testing.C. All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.
: 94. 2-SI-99-10-A, 62 Day Functional Test of SSPS Train A and Reactor Trip Breaker A
D. Problems identified during the test shall be annotated on the CTL from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.E. Data Sheets are to be completed by entering the data from the completed procedure shown on the Data Sheet or where indicated from the Eagle Surveillance Instruction printout.F. The Work Package number of the performance package will be entered on the Data Sheet and verified for each entry.G. On Data Sheet 1 through 21 the columns for REQUIRED SET PT ACTION and ACTUAL SET PT ACTION will have the setpoint action addressed for trip setpoints only. Parameters which do not have an action associated with them will not have an action indicated or required.H. On Data Sheets containing Eagle 21 trip setpoints the ACTUAL SET PT ACTION column will have two values recorded for Eagle 21 equipment trip setpoints.
: 95. 2-SI-99-10-B, 62 Day Functional Test of SSPS Train B and Reactor Trip Breaker B
These values are the actual minimum value and the actual maximum value. The Eagle 21 Surveillance Test Software presents the worst case minimum and the maximum trips based on multiple test passes through the setpoint.I. For Eagle 21 equipment parameters the least significant digit may deviate by one from the REQUIRED VALUES, i.e. 588.2 may be presented as 588.1999.J. Eagle 21 equipment parameters that are not trip setpoints may be obtained using the work order associated with the calibration procedure instead of the calibration procedure.
: 96. 2-PTI-099-05, NSSS Turbine Runback
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 15 of 148 Date 4.0 PREREQUISITE ACTIONS NOTE Prerequisite steps may be performed in any order unless otherwise stated and should be completed as close in time as practicable to the start of the instruction subsection to which they apply.4.1 Preliminary Actions[1] EVALUATE open items in Watts Bar Integrated Task Equipment List (WITEL), and ENSURE they will NOT adversely affect the test performance and results.[2] ENSURE changes to the references listed on Appendix A, have been reviewed, and determined NOT to adversely affect the test performance.
: 97. 2-ATI-047A-02, Turbine Trips and Protections
[3] VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.[4] ENSURE outstanding Design Change Notices (DCN's), Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.[5] OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the performance of this PTI.[6] VERIFY instructions listed in Table 1 have JTG concurrence that the instructions satisfy the requirements for this instruction.
: 98. SSD-2-LPP-2-1, Scaling and Setpoint Document Condenser Zone A Hotwell Narrow Range Pressure
[7] ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.
: 99. SSD-2-LPP-2-7, Scaling and Setpoint Document Condenser Zone B Hotwell Narrow Range Pressure 100. Work Order 113725926, Unique one-time test for HP Turbine Impulse Chamber Pressure Control (C-7), CTN 2-001-12296-IU1-000 101. 2-47A630-98-205, Rev. 0 (ANT), DRA 56744-005, Rev. 0, DCS Software Control Block Parameters - Processor W205CP 2.2   Developmental References A. Final Safety Analysis Report (FSAR)- Amendment 109
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 16 of 148 4.2 Date Special Tools, Measuring and Test Equipment, Parts, and Supplies This is a desktop performed instruction with no actual field testing. Measuring and Test Equipment or Permanent Plant Instrumentation Log is not required since the setpoint values obtained for this instruction are gathered from previously performed instructions listed in Table 1.Field Preparations None Approvals and Notifications
: 1. Table 14.2.1, Sheet 57 of 89, Reactor Protection System Test Summary
[1] OBTAIN permission of the Preoperational Startup Manager to start the test.4.3 4.4 Preoperational Startup Manager Signature Date[2] OBTAIN the Unit 2 Supervisor's (US/SRO) or Shift Manager's (SM) authorization.
: 2. Section 7.2, Reactor Trip System
US/SRO/SM Signature Date WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 17 of 148 5.0 ACCEPTANCE CRITERIA 5.1 Reactor Trips[1] The initial setpoints for Power Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[1]C, Data Sheet 1)[2] The initial setpoints for Intermediate Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[2]C, Data Sheet 2)[3] The initial setpoints for Source Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[3]C, Data Sheet 3)[4] The initial setpoints for Power Range High Positive Neutron Flux Rate Trip agree with the design requirements. (Step 6.1[4]C, Data Sheet 4)[5] The initial setpoints for Overtemperature/Overpower Delta T Trip agree with the design requirements. (Step 6.1[5]C, Data Sheet 5)[6] The initial setpoints for Pressurizer Low Pressure Trip agree with the design requirements. (Step 6.1 [6]C, Data Sheet 6)[7] The initial setpoints for Pressurizer High Pressure Trip agree with the design requirements. (Step 6.1[7]C, Data sheet 7)[8] The initial setpoints for Pressurizer High Water Level Trip agree with the design requirements. (Step 6.1[8]C, Data Sheet 8)[9] The initial setpoints for Low Reactor Coolant Flow Trip agree with the design requirements. (Step 6.1[9]C, Data Sheet 9)[10] The initial setpoints for Reactor Coolant Pump Undervoltage Trip agree with the design requirements. (Step 6.1 [10]C, Data Sheet 10)[11] The initial setpoints for Reactor Coolant Pump Underfrequency Trip agree with the design requirements. (Step 6.1 [11]C, Data Sheet 11)[12] The initial setpoints for Low-Low Steam Generator Water Level Trip, including TTDs, agree with the design requirements. (Step 6.1[12]C, Data Sheet 12)[13] The initial setpoints for Reactor Trip on Turbine Trip agree with the design requirements. (Step 6.1[13]C, Data Sheet 13)[14] The initial setpoints for Reactor Trip System Permissives and Interlocks agree with the design requirements. (Step 6.1[14]C, Data Sheet 14)
: 3. Section 7.3, Engineered Safety Features Actuation System B. Documents
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 18 of 148 5.2 Engineered Safety Features Actuations
: 1. PTI-99-06, Rev. 0, Reactor Protection Setpoint Verification
[1] The initial setpoints for Low Pressurizer Pressure Safety Injection agree with the design requirements. (Step 6.2[1]C, Data Sheet 15)[2] The initial setpoints for Low Steamline Pressure Safety Injection and Steamline Isolation agree with the design requirements. (Step 6.2[2]C, Data Sheet 16)[3] The initial setpoints for Containment High Pressure Safety Injection agree with the design requirements. (Step 6.2[3]C, Data Sheet 17)(4] The initial setpoints for Safety Injection Manual Reset Time Delay agree with the design requirements. (Step 6.2[4]C, Data Sheet 18)[5] The initial setpoints for High Negative Steamline Pressure Rate Steamline Isolation agree with the design requirements. (Step 6.2[5]C, Data Sheet 19)[6] The initial setpoints for High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation agree with the design requirements. (Step 6.2[6]C, Data Sheet 20)[7] The initial setpoints for the Miscellaneous ESFAS agree with the design requirements: (Step 6.2[7]C, Data Sheet 21)
: 2. 2-TSD-99-06, Rev. 1, Reactor Protection Setpoint Verification
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 19 of 148 Date 6.0 PERFORMANCE NOTES 1) This is a desktop performed instruction.
 
No actual field testing is required.
WBN         REACTOR PROTECTION SETPOINT             2-PTI-099-06 Unit 2                 VERIFICATION                 Rev. 0000 Page 13 of 148 2.2   Developmental References (continued)
Subsections may be performed in any order. Steps within a subsection are not required to be performed in the order written.2) Table 1 (Step 4.1[6]) does not have to be fully completed prior to the performance of each step in this subsection.
: 3. WBN2-99-4003, Rev. 0, System Description For Reactor Protection System
Only the Table 1 instructions applicable to the step, to be performed, must have JTG approval.
: 4. WBN2-47-4002, Rev. 1, Turbogenerator System (Part 1) and Turbogenerator Control and Protection System (Part 2)
As an example, JTG concurrence of 2-SI-68-9, 10, and 11 must be obtained in Table 1 (Step 4.1[6]) prior to performance of Step 6.1 [8] and Data Sheet 8. Table 1 (Step 4.1 [6]) should be fully completed prior to completing Section 6.0.6.1 Reactor Trips[1] Power Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
WBN             REACTOR PROTECTION SETPOINT               2-PTI-099-06 Unit 2                     VERIFICATION                   Rev. 0000 Page 14 of 148 3.0   PRECAUTIONS AND LIMITATIONS A. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps must be re-verified and a Chronological Test Log (CTL) entry made.
B. Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description is sufficient to identify the component. If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.
C. All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.
D. Problems identified during the test shall be annotated on the CTL from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.
E. Data Sheets are to be completed by entering the data from the completed procedure shown on the Data Sheet or where indicated from the Eagle Surveillance Instruction printout.
F. The Work Package number of the performance package will be entered on the Data Sheet and verified for each entry.
G. On Data Sheet 1 through 21 the columns for REQUIRED SET PT ACTION and ACTUAL SET PT ACTION will have the setpoint action addressed for trip setpoints only. Parameters which do not have an action associated with them will not have an action indicated or required.
H. On Data Sheets containing Eagle 21 trip setpoints the ACTUAL SET PT ACTION column will have two values recorded for Eagle 21 equipment trip setpoints. These values are the actual minimum value and the actual maximum value. The Eagle 21 Surveillance Test Software presents the worst case minimum and the maximum trips based on multiple test passes through the setpoint.
I. For Eagle 21 equipment parameters the least significant digit may deviate by one from the REQUIRED VALUES, i.e. 588.2 may be presented as 588.1999.
J. Eagle 21 equipment parameters that are not trip setpoints may be obtained using the work order associated with the calibration procedure instead of the calibration procedure.
 
WBN             REACTOR PROTECTION SETPOINT                 2-PTI-099-06 Unit 2                     VERIFICATION                   Rev. 0000 Page 15 of 148 Date 4.0     PREREQUISITE ACTIONS NOTE Prerequisite steps may be performed in any order unless otherwise stated and should be completed as close in time as practicable to the start of the instruction subsection to which they apply.
4.1     Preliminary Actions
[1]   EVALUATE open items in Watts Bar Integrated Task Equipment List (WITEL), and ENSURE they will NOT adversely affect the test performance and results.
[2]   ENSURE changes to the references listed on Appendix A, have been reviewed, and determined NOT to adversely affect the test performance.
[3]   VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.
[4]   ENSURE outstanding Design Change Notices (DCN's),
Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.
[5]   OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the performance of this PTI.
[6]   VERIFY instructions listed in Table 1 have JTG concurrence that the instructions satisfy the requirements for this instruction.
[7]     ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.
 
WBN             REACTOR PROTECTION SETPOINT               2-PTI-099-06 Unit 2                     VERIFICATION                   Rev. 0000 Page 16 of 148 Date 4.2   Special Tools, Measuring and Test Equipment, Parts, and Supplies This is a desktop performed instruction with no actual field testing. Measuring and Test Equipment or Permanent Plant Instrumentation Log is not required since the setpoint values obtained for this instruction are gathered from previously performed instructions listed in Table 1.
4.3  Field Preparations None 4.4  Approvals and Notifications
[1]     OBTAIN permission of the Preoperational Startup Manager to start the test.
Preoperational Startup Manager Signature                   Date
[2]     OBTAIN the Unit 2 Supervisor's (US/SRO) or Shift Manager's (SM) authorization.
US/SRO/SM Signature                               Date
 
WBN           REACTOR PROTECTION SETPOINT               2-PTI-099-06 Unit 2                     VERIFICATION                   Rev. 0000 Page 17 of 148 5.0   ACCEPTANCE CRITERIA 5.1   Reactor Trips
[1]   The initial setpoints for Power Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[1]C, Data Sheet 1)
[2]   The initial setpoints for Intermediate Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[2]C, Data Sheet 2)
[3]   The initial setpoints for Source Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[3]C, Data Sheet 3)
[4]   The initial setpoints for Power Range High Positive Neutron Flux Rate Trip agree with the design requirements. (Step 6.1[4]C, Data Sheet 4)
[5]   The initial setpoints for Overtemperature/Overpower Delta T Trip agree with the design requirements. (Step 6.1[5]C, Data Sheet 5)
[6]   The initial setpoints for Pressurizer Low Pressure Trip agree with the design requirements. (Step 6.1 [6]C, Data Sheet 6)
[7]   The initial setpoints for Pressurizer High Pressure Trip agree with the design requirements. (Step 6.1[7]C, Data sheet 7)
[8]   The initial setpoints for Pressurizer High Water Level Trip agree with the design requirements. (Step 6.1[8]C, Data Sheet 8)
[9]   The initial setpoints for Low Reactor Coolant Flow Trip agree with the design requirements. (Step 6.1[9]C, Data Sheet 9)
[10] The initial setpoints for Reactor Coolant Pump Undervoltage Trip agree with the design requirements. (Step 6.1 [10]C, Data Sheet 10)
[11] The initial setpoints for Reactor Coolant Pump Underfrequency Trip agree with the design requirements. (Step 6.1 [11]C, Data Sheet 11)
[12] The initial setpoints for Low-Low Steam Generator Water Level Trip, including TTDs, agree with the design requirements. (Step 6.1[12]C, Data Sheet 12)
[13] The initial setpoints for Reactor Trip on Turbine Trip agree with the design requirements. (Step 6.1[13]C, Data Sheet 13)
[14] The initial setpoints for Reactor Trip System Permissives and Interlocks agree with the design requirements. (Step 6.1[14]C, Data Sheet 14)
 
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[1] The initial setpoints for Low Pressurizer Pressure Safety Injection agree with the design requirements. (Step 6.2[1]C, Data Sheet 15)
[2]   The initial setpoints for Low Steamline Pressure Safety Injection and Steamline Isolation agree with the design requirements. (Step 6.2[2]C, Data Sheet 16)
[3]   The initial setpoints for Containment High Pressure Safety Injection agree with the design requirements. (Step 6.2[3]C, Data Sheet 17)
(4] The initial setpoints for Safety Injection Manual Reset Time Delay agree with the design requirements. (Step 6.2[4]C, Data Sheet 18)
[5]   The initial setpoints for High Negative Steamline Pressure Rate Steamline Isolation agree with the design requirements. (Step 6.2[5]C, Data Sheet 19)
[6] The initial setpoints for High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation agree with the design requirements. (Step 6.2[6]C, Data Sheet 20)
[7] The initial setpoints for the Miscellaneous ESFAS agree with the design requirements: (Step 6.2[7]C, Data Sheet 21)
 
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: 1) This is a desktop performed instruction. No actual field testing is required. Subsections may be performed in any order. Steps within a subsection are not required to be performed in the order written.
: 2) Table 1 (Step 4.1[6]) does not have to be fully completed prior to the performance of each step in this subsection. Only the Table 1 instructions applicable to the step, to be performed, must have JTG approval. As an example, JTG concurrence of 2-SI-68-9, 10, and 11 must be obtained in Table 1 (Step 4.1[6]) prior to performance of Step 6.1 [8] and Data Sheet 8. Table 1 (Step 4.1 [6]) should be fully completed prior to completing Section 6.0.
6.1     Reactor Trips
[1]   Power Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the "Actual" setpoints from the instructions listed on Data Sheet 1, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the "Actual" setpoints from the instructions listed on Data Sheet 1, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY "Actual" setpoints recorded on Data Sheet 1 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[11])
C. VERIFY "Actual" setpoints recorded on Data Sheet 1 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 20 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[11])
[2] Intermediate Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[2]   Intermediate Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 2, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 2, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 2 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[2])[3] Source Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 2 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1[2])
[3]   Source Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 3, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 3, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 3 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[3])
C. VERIFY Actual setpoints recorded on Data Sheet 3 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 21 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[3])
[4] Power Range High Positive Neutron Flux Rate Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[4]   Power Range High Positive Neutron Flux Rate Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 4, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 4, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 4 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[4])[5] Overtemperature/Overpower Delta T Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 4 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1[4])
[5]   Overtemperature/Overpower Delta T Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 5, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 5, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 5 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[5])
C. VERIFY Actual setpoints recorded on Data Sheet 5 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 22 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[5])
[6] Pressurizer Low Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[6]   Pressurizer Low Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 6, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 6, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 6 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[6])[7] Pressurizer High Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 6 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1[6])
[7]   Pressurizer High Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 7, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 7, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 7 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[7])
C. VERIFY Actual setpoints recorded on Data Sheet 7 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 23 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[7])
[8] Pressurizer High Water Level Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[8]   Pressurizer High Water Level Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 8, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 8, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 8 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[8])[9] Low Reactor Coolant Flow Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 8 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1[8])
[9]   Low Reactor Coolant Flow Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 9, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 9, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 9 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[9])
C. VERIFY Actual setpoints recorded on Data Sheet 9 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 24 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[9])
[10] Reactor Coolant Pump Undervoltage Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[10] Reactor Coolant Pump Undervoltage Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 10, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 10, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 10 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1 10])[11] Reactor Coolant Pump Underfrequency Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 10 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1 10])
[11] Reactor Coolant Pump Underfrequency Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 11, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 11, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 11 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1 [11])
C. VERIFY Actual setpoints recorded on Data Sheet 11 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 25 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1 [11])
[12] Low-Low Steam Generator Water Level Trip (Including TTDs)A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[12] Low-Low Steam Generator Water Level Trip (Including TTDs)
A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 12, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 12, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 12 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[12])[13] Reactor Trip On Turbine Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 12 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.1[12])
[13] Reactor Trip On Turbine Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 13, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 13, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 13 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[13])
C. VERIFY Actual setpoints recorded on Data Sheet 13 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 26 of 148 Date 6.1 Reactor Trips (continued)
(Acc Crit 5.1[13])
[14] Reactor Trip System Permissives and Interlocks A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[14] Reactor Trip System Permissives and Interlocks A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 14, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 14, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 14 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.1[14])
C. VERIFY Actual setpoints recorded on Data Sheet 14 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 27 of 148 Date 6.2 Engineered Safety Features Actuations
(Acc Crit 5.1[14])
[1] Low Pressurizer Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[1] Low Pressurizer Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 15, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 15, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 15 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[1])[2] Low Steamline Pressure Safety Injection and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 15 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.2[1])
[2] Low Steamline Pressure Safety Injection and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 16, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 16, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 16 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[2])
C. VERIFY Actual setpoints recorded on Data Sheet 16 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 28 of 148 Date 6.2 Engineered Safety Features Actuations (continued)
(Acc Crit 5.2[2])
[3] Containment High Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[3]   Containment High Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 17, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 17, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 17 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[3])[4] Safety Injection Manual Reset Time Delay A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 17 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.2[3])
[4] Safety Injection Manual Reset Time Delay A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 18, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 18, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 18 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[4])
C. VERIFY Actual setpoints recorded on Data Sheet 18 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 29 of 148 Date 6.2 Engineered Safety Features Actuations (continued)
(Acc Crit 5.2[4])
[5] High Negative Steamline Pressure Rate Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[5]   High Negative Steamline Pressure Rate Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 19, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 19, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 19 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[5])[6] High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
C. VERIFY Actual setpoints recorded on Data Sheet 19 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
(Acc Crit 5.2[5])
[6]   High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 20, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 20, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 20 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[6])
C. VERIFY Actual setpoints recorded on Data Sheet 20 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 30 of 148 Date 6.2 Engineered Safety Features Actuations (continued)
(Acc Crit 5.2[6])
[7] Miscellaneous ESFAS Setpoints A. VERIFY prerequisites listed in Section 4.0 have been completed.
 
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[7]   Miscellaneous ESFAS Setpoints A. VERIFY prerequisites listed in Section 4.0 have been completed.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 21, AND RECORD the values and work documents utilized in the spaces allocated.
B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 21, AND RECORD the values and work documents utilized in the spaces allocated.
C. VERIFY Actual setpoints recorded on Data Sheet 21 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.(Acc Crit 5.2[7])
C. VERIFY Actual setpoints recorded on Data Sheet 21 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.
WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 31 of 148 Date 7.0 POST PERFORMANCE ACTIVITY[1] VERIFY copies of the Eagle Surveillance Instruction printouts and applicable data sheets from completed SIs/lMIs/WOs used to verify setpoints have been attached to this instruction and logged in Table 2.[2] NOTIFY the US/SRO of the test completion.
(Acc Crit 5.2[7])
RECORDS A. QA Records Completed Test Package (PTI)B. Non-QA Records 8.0 None WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 32 of 148 Appendix A (Page 1 of 1)Test Procedures
 
/ Instructions Reference Review Date NOTES 1) Additional copies of this table may be made as necessary.
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: 2) Initial and date indicates review has been completed for impact.PROCEDURE/
[1]  VERIFY copies of the Eagle Surveillance Instruction printouts and applicable data sheets from completed SIs/lMIs/WOs used to verify setpoints have been attached to this instruction and logged in Table 2.
REVISION/CHANGES IMPACT INITIAL AND INSTRUCTION Yes/No DATE. (N/A for no change)U2 FSAR Table 14.2.1 Section 7.2 Section 7.3 PTI-99-06 2-TSD-99-06 WBN2-99-4003 WBN2-47-4002
[2]    NOTIFY the US/SRO of the test completion.
* 4 4 4 t .~ 4 4 4 4 WBN REACTOR PROTECTION SETPOINT 2-PTI-
8.0  RECORDS A. QA Records Completed Test Package (PTI)
B. Non-QA Records None
 
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Test Procedures / Instructions Reference Review Date NOTES
: 1)  Additional copies of this table may be made as necessary.
: 2)  Initial and date indicates review has been completed for impact.
PROCEDURE/                  REVISION/CHANGES                IMPACT        INITIAL AND INSTRUCTION                                                  Yes/No      DATE. (N/A for no change)
U2 FSAR Table 14.2.1 Section 7.2 Section 7.3 PTI-99-06 2-TSD-99-06 WBN2-99-4003 WBN2-47-4002
* 4 4                                  4 t                                    .~            4 4                                    4              4
 
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Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI          JTG Meeting Number                    Initial 2-SI-1-1 2-SI-1-2 2-SI-1-3 2-SI-1-4 2-SI-1-5 2-SI-1-6 2-SI-1-7 2-S1-1-8 2-SI-1-9 2-SI-1-10 2-SI-1-11 2-SI-1-12 2-SI-1-72 2-SI-1-73 2-Sl-3-1 2-SI-3-2 2-Sl-3-3 2-SI-3-4 2-SI-3-5 2-SI-3-6
 
WBN            REACTOR PROTECTION SETPOINT            2-PTI-099-06 Unit 2                    VERIFICATION                Rev. 0000 Page 34 of 148 Table I (Page 2 of 5)
Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI          JTG Meeting Number                    Initial 2-SI-3-7 2-SI-3-8 2-SI-3-9 2-S1-3-10 2-SI-3-11 2-SI-3-12 2-SI-3

Latest revision as of 17:40, 4 November 2019

2-PTI-099-06, Revision 0, Reactor Protection Setpoint Verification.
ML13175A136
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 11/08/2012
From: Piplica N
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
References
2-PTI-085-06, Rev 0
Download: ML13175A136 (148)


Text

WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Reactor Protection Setpoint Verification Instruction No: 2-PTI-099-06 Revision No: 0000 PREPARED BY: Nicholas C.Piplica I PRINT NAME / SIGNATURE

4. 4L - DATE:.___./o_/ __

REVIEWED BY: Mark D. Runion / /*A-J A), .- DATE: J*L#/' L PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No: / -- -

JTG CHAIRMAN: A-DATE:

APPROVED BY: DATE: di -'

PREOFIOAL TARU'PMANAGEý TEST RESULTS APPROVAL JTG MEETING No:

JTG CHAIRMAN: DATE:

APPROVED BY: DATE:

PREOPERATIONAL STARTUP MANAGER SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010

WBN REACTOR PROTECTION SETPOINT 2-PTI-99-06.

Unit 2 VERIFICATION Rev. 0000 Page 2 of 148 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange 0000 - f I I/ I ALL Initial issue based on PTI-099-06 for Unit 1.

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 3 of 148 Table of Contents

1.0 INTRODUCTION

...................................................................................................... 6 1.1 Test Objectives ........................................................................................................ 6 1.2 S co p e ............................................................................................................................ 6

2.0 REFERENCES

........................................................................................................ 6 2.1 Performance References ........................................................................................ 6 2.2 Developmental References .................................................................................... 12 3.0 PRECAUTIONS AND LIMITATIONS .................................................................... 14 4.0 PREREQUISITE ACTIONS .................................................................................... 15 4.1 Preliminary Actions ................................................................................................. 15 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies ...................... 16 4.3 Field Preparations .................................................................................................. 16 4.4 Approvals and Notifications ................................................................................... 16 5.0 ACCEPTANCE CRITERIA .................................................................................... 17 5.1 Reactor Trips .............................................................................................................. 17 5.2 Engineered Safety Features Actuations .................................................................. 18 6.0 PERFORMANCE .................................................................................................... 19 6.1 Reactor Trips .............................................................................................................. 19 6.2 Engineered Safety Features Actuations .................................................................. 27 7.0 POST PERFORMANCE ACTIVITY ...................................................................... 31 8.0 RECORDS .................................................................................................................. 31 Appendix A: Test Procedures / Instructions Reference Review ............................ 32 Table 1: Plant Instruction and PTI Verification of JTG Concurrence ........................................................................................ 33 Data Sheet 1: Power Range High Neutron Flux Trip Setpoint Verification ........................................................................................... 38 Data Sheet 2: Intermediate Range High Neutron Flux Trip Setpoint Verification .......................................................................................... 40 Data Sheet 3: Source Range High Neutron Flux Trip Setpoint Verification .......................................................................................... 41

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 4 of 148 Table of Contents (continued)

Data Sheet 4: Power Range High Positive Neutron Flux Rate Trip Setpoint Verification ............................................................................. 42 Data Sheet 5: Overtemperature/Overpower Delta T Trip Setpoint Verification .......................................................................................... 44 Data Sheet 6: Pressurizer Low Pressure Trip Setpoint Verification ........................ 74 Data Sheet 7: Pressurizer High Pressure Trip Setpoint Verification ....................... 77 Data Sheet 8: Pressurizer High Water Level Trip Setpoint Verification ................... 78 Data Sheet 9: Low Reactor Coolant Flow Trip Setpoint Verification ....................... 79 Data Sheet 10: Reactor Coolant Pump Undervoltage Trip Setpoint Verification ............................................................................................. 83 Data Sheet 11: Reactor Coolant Pump Underfrequency Trip Setpoint Verification ............................................................................................. 85 Data Sheet 12: Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification ............................................................................. 87 Data Sheet 13: Reactor Trip on Turbine Trip Setpoint Verification .............................. 100 Data Sheet 14: Reactor Trip System Permissive and Interlock Setpoint V erification .............................................................................................. 102 Data Sheet 15: Low Pressurizer Pressure Safety Injection Setpoint V erification .............................................................................................. 117 Data Sheet 16: Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification ............................................................... 118 Data Sheet 17: Containment High Pressure Safety Injection Setpoint V erification .............................................................................................. 127 Data Sheet 18: Safety Injection Manual Reset Time Delay Setpoint V erification .............................................................................................. 128 Data Sheet 19: High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification ............................................................... 130 Data Sheet 20: High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation Setpoint Verification ............................................................................... 137 Data Sheet 21: Miscellaneous ESFAS Setpoint Verification ......................................... 139

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 5 of 148 Table of Contents (continued)

Table 2: Attachment Index .................................................................................... 148

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 6 of 148

1.0 INTRODUCTION

1.1 Test Objectives Verify initial setpoint adjustments have been made prior to plant startup and are in agreement with Watts Bar Nuclear Plant design requirements.

1.2 Scope The scope of this instruction verifies setpoints associated with Reactor Trips and the Engineered Safety Features Actuations.

2.0 REFERENCES

2.1 Performance References

1. SMP-9.0, Watts Bar Nuclear Plant Unit 2 - Conduct of Test
2. 2-SI-1-1, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel I Loop 2-LPP-1-2A (P-514)
3. 2-SI-1-2, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel II Loop 2-LPP-1-2B (P-515)
4. 2-SI-1-3, 18 Month Channel Calibration SG 1 Main Steam Header Pressure Channel IV Loop 2-LPP-1-5 (P-516)
5. 2-SI-1-4, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel I Loop 2-LPP-1-9A (P-524)
6. 2-SI-1-5, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel II Loop 2-LPP-1-9B (P-525)
7. 2-SI-1-6, 18 Month Channel Calibration SG 2 Main Steam Header Pressure Channel III Loop 2-LPP-1-12 (P-526)
8. 2-SI-1-7, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel I Loop 2-LPP-1-20A (P-534)
9. 2-SI-1-8, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel II Loop 2-LPP-1-20B (P-535)
10. 2-SI-1-9, 18 Month Channel Calibration SG 3 Main Steam Header Pressure Channel III Loop 2-LPP-1-23 (P-536)
11. 2-SI-1-10, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel I Loop 2-LPP-1-27A (P-544)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 7 of 148 2.1 Performance References (continued)

12. 2-SI-1-11, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel II Loop 2-LPP-1-27B (P-545)
13. 2-S1-1-12, 18 Month Channel Calibration SG 4 Main Steam Header Pressure Channel IV Loop 2-LPP-1-30 (P-546)
14. 2-SI-1-72, 18 Month Channel Calibration Turbine Impulse Chamber Pressure Channel II, Loop 2-LPP-1-72 (P-506)
15. 2-SI-1-73, 18 Month Channel Calibration Turbine Impulse-Chamber Pressure Channel I, Loop 2-LPP-1-73 (P-505)
16. 2-SI-3-1, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel II Loop 2-LPL-3-38 (L-519)
17. 2-SI-3-2, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel III Loop 2-LPL-3-39 (L-518)
18. 2-SI-3-3, 18 Month Channel Calibration Steam Generator 1 Narrow Range Level Channel IV Loop 2-LPL-3-42 (L-517)
19. 2-SI-3-4, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel II Loop 2-LPL-3-51 (L-529)
20. 2-SI-3-5, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel III Loop 2-LPL-3-52 (L-528)
21. 2-SI-3-6, 18 Month Channel Calibration Steam Generator 2 Narrow Range Level Channel IV Loop 2-LPL-3-55 (L-527)
22. 2-SI-3-7, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel II Loop 2-LPL-3-93 (L-539)
23. 2-SI-3-8, 18 Month Channel Calibration Steam Generator 3 Narrow Range Level Channel III Loop 2-LPL-3-94 (L-538)
24. 2-SI-3-9, 18 Month Channel Calibration.Steam Generator 3 Narrow Range Level Channel IV Loop 2-LPL-3-97 (L-537)
25. 2-SI-3-10, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel II Loop 2-LPL-3-106 (L-549)
26. 2-SI-3-11, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel III Loop 2-LPL-3-107 (L-548)
27. 2-SI-3-12, 18 Month Channel Calibration Steam Generator 4 Narrow Range Level Channel IV Loop 2-LPL-3-1 10 (L-547)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 8 of 148 2.1 Performance References (continued)

28. 2-SI-3-13, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel II, Loop 2-LPL-3-38T (L-519-549)
29. 2-SI-3-14, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel III, Loop 2-LPL-3-39T (L-518-548)
30. 2-SI-3-15, 184 Day Channel Operational Test And 18 Month Channel Calibration Steam Generator Level Trip Time Delay Channel IV, Loop 2-LPL-3-42T (L-517-547)
31. 2-SI-3-21, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2A-A Suction Header Pressure Switches
32. 2-SI-3-22, 18 Month Channel Calibration, Auxiliary Feedwater Pump 2B-B Suction Header Pressure Switches
33. 2-SI-3-25, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2A Trip
34. 2-SI-3-26, 18 Month Channel Calibration, TADOT and Response Time Test AFW Initiation From Main Feedpump Turbine 2B Trip
35. 2-SI-3-402, 18 Month Channel Calibration South Valve Vault Level Switch Channel I Loop 2-LPL-3-402
36. 2-SI-3-403, 18 Month Channel Calibration South Valve Vault Level Switch Channel III Loop 2-LPL-3-403
37. 2-SI-3-404, 18 Month Channel Calibration South Valve Vault Level Switch Channel IV Loop 2-LPL-3-404
38. 2-SI-3-405, 18 Month Channel Calibration North Valve Vault Level Switch Channel I Loop 2-LPL-3-405
39. 2-SI-3-406, 18 Month Channel Calibration North Valve Vault Level Switch Channel Ill Loop 2-LPL-3-406
40. 2-SI-3-407, 18 Month Channel Calibration North Valve Vault Level Switch Channel IV Loop 2-LPL 407
41. 2-SI-30-42, 18 Month Channel Calibration Containment Pressure Channel IV Loop 2-LPP-30-42 (P-934)
42. 2-SI-30-43, 18 Month Channel Calibration Containment Pressure Channel III Loop 2-LPP-30-43 (P-935)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 9 of 148 2.1 Performance References (continued)

43. 2-SI-30-44, 18 Month Channel Calibration Containment Pressure Channel II Loop 2-LPP-30-44 (P-936)
44. 2-SI-30-45, 18 Month Channel Calibration Containment Pressure Channel I Loop 2-LPP-30-45 (P-937)
45. 2-SI-63-1, 18 Month Channel Calibration Containment Sump Level Channel I Loop 2-LPL-63-180 (L-920)
46. 2-SI-63-2, 18 Month Channel Calibration Containment Sump Level Channel II Loop 2-LPL-63-181 (L-921)
47. 2-SI-63-3, 18 Month Channel Calibration Containment Sump Level Channel Ill Loop 2-LPL-63-182 (L-940)
48. 2-SI-63-4, 18 Month Channel Calibration Containment Sump Level Channel IV Loop 2-LPL-63-183 (L-941)
49. 2-SI-63-50, 18 Month Channel Calibration RWST Level Channel I Loop 2-LPL-63-50 (L-913)
50. 2-SI-63-51, 18 Month Channel Calibration RWST Level Channel II Loop 2-LPL-63-51 (L-914)
51. 2-SI-63-52, 18 Month Channel Calibration RWST Level Channel III Loop 2-LPL-63-52 (L-915)
52. 2-SI-63-53, 18 Month Channel Calibration RWST Level Channel IV Loop 2-LPL-63-53 (L-916)
53. 2-SI-68-1, 18 Month Channel Calibration RCS Loop 1 Delta T/Tavg Channel I.Loop 2-LPT-68-2 (T-411/412)
54. 2-81-68-2, 18 Month Channel Calibration RCS Loop 2 Delta T/Tavg Channel II Loop 2-LPT-68-25 (T-421/422)
55. 2-SI-68-3, 18 Month Channel Calibration RCS Loop 3 Delta T/Tavg Channel Ill Loop 2-LPT-68-44 (T-431/432)
56. 2-SI-68-4, 18 Month Channel Calibration RCS Loop 4 Delta T/Tavg Channel IV Loop 2-LPT-68-67 (T-441/442)
57. 2-SI-68-5, 18 Month Channel Calibration Pressurizer Pressure Channel I Loop 2-LPP-68-340 (P-455)
58. 2-SI-68-6, 18 Month Channel Calibration Pressurizer Pressure Channel II Loop 2-LPP-68-334 (P-456)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 10 of 148 2.1 Performance References (continued)

59. 2-SI-68-7, 18 Month Channel Calibration Pressurizer Pressure Channel Ill Loop 2-LPP-68-323 (P-457)
60. 2-SI-68-8, 18 Month Channel Calibration Pressurizer Pressure Channel IV Loop 2-LPP-68-322 (P-458)
61. 2-SI-68-9, 18 Month Channel Calibration Pressurizer Level Channel I Loop 2-LPL-68-339 (L-459)
62. 2-SI-68-10, 18 Month Channel Calibration Pressurizer Level Channel II Loop 2-LPL-68-335 (L-460)
63. 2-SI-68-11, 18 Month Channel Calibration Pressurizer Level Channel III Loop 2-LPL-68-320 (L-461)
64. 2-SI-68-12, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel I Loop 2-LPF-68-6A (F-414)
65. 2-SI-68-13, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel II Loop 2-LPF-68-6B (F-415)
66. 2-SI-68-14, 18 Month Channel Calibration Reactor Coolant Flow Loop 1 Channel III Loop 2-LPF-68-6D (F-416)
67. 2-SI-68-15, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel I Loop 2-LPF-68-29A (F-424)
68. 2-SI-68-16, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel II Loop 2-LPF-68-29B (F-425)
69. 2-SI-68-17, 18 Month Channel Calibration Reactor Coolant Flow Loop 2 Channel III Loop 2-LPF-68-29D (F-426)
70. 2-SI-68-18, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel I Loop 2-LPF-68-48A (F-434)
71. 2-SI-68-19, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel II Loop 2-LPF-68-48B (F-435)
72. 2-SI-68-20, 18 Month Channel Calibration Reactor Coolant Flow Loop 3 Channel III Loop 2-LPF-68-48D (F-436)
73. 2-SI-68-21, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel I Loop 2-LPF-68-71A (F-444)
74. 2-SI-68-22, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel II Loop 2-LPF-68-71B (F-445)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 11 of 148 2.1 Performance References (continued)

75. 2-SI-68-23, 18 Month Channel Calibration Reactor Coolant Flow Loop 4 Channel III Loop 2-LPF-68-71D (F-446)
76. 2-SI-68-36, 18 Month Reactor Coolant Pump 1 Underfrequency Relay Calibration
77. 2-SI-68-37, 18 Month Reactor Coolant Pump 2 Underfrequency Relay Calibration
78. 2-SI-68-38, 18 Month Reactor Coolant Pump 3 Underfrequency Relay Calibration
79. 2-SI-68-39, 18 Month Reactor Coolant Pump 4 Underfrequency Relay Calibration
80. 2-SI-68-40, 18 Month Reactor Coolant Pump 1 Undervoltage Channel Calibration
81. 2-SI-68-41, 18 Month Reactor Coolant Pump 2 Undervoltage Channel Calibration
82. 2-SI-68-42, 18 Month Reactor Coolant Pump 3 Undervoltage Channel Calibration
83. 2-SI-68-43, 18 Month Reactor Coolant Pump 4 Undervoltage Channel Calibration
84. 2-SI-92-31, 18 Month Channel Calibration of Source Range, Intermediate Range, and Remote Shutdown Neutron Flux Channel I
85. 2-SI-92-32, 18 Month Channel Calibration of Source Range and Intermediate Range Channel II
86. 2-SI-92-41, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-41
87. 2-SI-92-42, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-42
88. 2-SI-92-43, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-43
89. 2-SI-92-44, 18 Month Channel Calibration of Power Range Nuclear Instrumentation System Channel N-44
90. 2-SI-47-28, 18 Month Channel Calibration Turbine Trip - Turbine Stop Valve Closure Channel I, (Channel 1,11, 111, & IV) [2-ZS-47-28, 30, 32, & 34]

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 12 of 148 2.1 Performance References (continued)

91. 2-SI-47-73, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel I Loop 2-PS-47-73-D
92. 2-SI-47-74, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel II Loop 2-PS-47-74-E
93. 2-SI-47-75, 18 Month Channel Calibration Turbine Trip - Low Fluid Oil Pressure Channel III Loop 2-PS-47-75-F
94. 2-SI-99-10-A, 62 Day Functional Test of SSPS Train A and Reactor Trip Breaker A
95. 2-SI-99-10-B, 62 Day Functional Test of SSPS Train B and Reactor Trip Breaker B
96. 2-PTI-099-05, NSSS Turbine Runback
97. 2-ATI-047A-02, Turbine Trips and Protections
98. SSD-2-LPP-2-1, Scaling and Setpoint Document Condenser Zone A Hotwell Narrow Range Pressure
99. SSD-2-LPP-2-7, Scaling and Setpoint Document Condenser Zone B Hotwell Narrow Range Pressure 100. Work Order 113725926, Unique one-time test for HP Turbine Impulse Chamber Pressure Control (C-7), CTN 2-001-12296-IU1-000 101. 2-47A630-98-205, Rev. 0 (ANT), DRA 56744-005, Rev. 0, DCS Software Control Block Parameters - Processor W205CP 2.2 Developmental References A. Final Safety Analysis Report (FSAR)- Amendment 109
1. Table 14.2.1, Sheet 57 of 89, Reactor Protection System Test Summary
2. Section 7.2, Reactor Trip System
3. Section 7.3, Engineered Safety Features Actuation System B. Documents
1. PTI-99-06, Rev. 0, Reactor Protection Setpoint Verification
2. 2-TSD-99-06, Rev. 1, Reactor Protection Setpoint Verification

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 13 of 148 2.2 Developmental References (continued)

3. WBN2-99-4003, Rev. 0, System Description For Reactor Protection System
4. WBN2-47-4002, Rev. 1, Turbogenerator System (Part 1) and Turbogenerator Control and Protection System (Part 2)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 14 of 148 3.0 PRECAUTIONS AND LIMITATIONS A. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps must be re-verified and a Chronological Test Log (CTL) entry made.

B. Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description is sufficient to identify the component. If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.

C. All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.

D. Problems identified during the test shall be annotated on the CTL from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.

E. Data Sheets are to be completed by entering the data from the completed procedure shown on the Data Sheet or where indicated from the Eagle Surveillance Instruction printout.

F. The Work Package number of the performance package will be entered on the Data Sheet and verified for each entry.

G. On Data Sheet 1 through 21 the columns for REQUIRED SET PT ACTION and ACTUAL SET PT ACTION will have the setpoint action addressed for trip setpoints only. Parameters which do not have an action associated with them will not have an action indicated or required.

H. On Data Sheets containing Eagle 21 trip setpoints the ACTUAL SET PT ACTION column will have two values recorded for Eagle 21 equipment trip setpoints. These values are the actual minimum value and the actual maximum value. The Eagle 21 Surveillance Test Software presents the worst case minimum and the maximum trips based on multiple test passes through the setpoint.

I. For Eagle 21 equipment parameters the least significant digit may deviate by one from the REQUIRED VALUES, i.e. 588.2 may be presented as 588.1999.

J. Eagle 21 equipment parameters that are not trip setpoints may be obtained using the work order associated with the calibration procedure instead of the calibration procedure.

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 15 of 148 Date 4.0 PREREQUISITE ACTIONS NOTE Prerequisite steps may be performed in any order unless otherwise stated and should be completed as close in time as practicable to the start of the instruction subsection to which they apply.

4.1 Preliminary Actions

[1] EVALUATE open items in Watts Bar Integrated Task Equipment List (WITEL), and ENSURE they will NOT adversely affect the test performance and results.

[2] ENSURE changes to the references listed on Appendix A, have been reviewed, and determined NOT to adversely affect the test performance.

[3] VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.

[4] ENSURE outstanding Design Change Notices (DCN's),

Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.

[5] OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the performance of this PTI.

[6] VERIFY instructions listed in Table 1 have JTG concurrence that the instructions satisfy the requirements for this instruction.

[7] ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 16 of 148 Date 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies This is a desktop performed instruction with no actual field testing. Measuring and Test Equipment or Permanent Plant Instrumentation Log is not required since the setpoint values obtained for this instruction are gathered from previously performed instructions listed in Table 1.

4.3 Field Preparations None 4.4 Approvals and Notifications

[1] OBTAIN permission of the Preoperational Startup Manager to start the test.

Preoperational Startup Manager Signature Date

[2] OBTAIN the Unit 2 Supervisor's (US/SRO) or Shift Manager's (SM) authorization.

US/SRO/SM Signature Date

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 17 of 148 5.0 ACCEPTANCE CRITERIA 5.1 Reactor Trips

[1] The initial setpoints for Power Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[1]C, Data Sheet 1)

[2] The initial setpoints for Intermediate Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[2]C, Data Sheet 2)

[3] The initial setpoints for Source Range High Neutron Flux Trip agree with the design requirements. (Step 6.1[3]C, Data Sheet 3)

[4] The initial setpoints for Power Range High Positive Neutron Flux Rate Trip agree with the design requirements. (Step 6.1[4]C, Data Sheet 4)

[5] The initial setpoints for Overtemperature/Overpower Delta T Trip agree with the design requirements. (Step 6.1[5]C, Data Sheet 5)

[6] The initial setpoints for Pressurizer Low Pressure Trip agree with the design requirements. (Step 6.1 [6]C, Data Sheet 6)

[7] The initial setpoints for Pressurizer High Pressure Trip agree with the design requirements. (Step 6.1[7]C, Data sheet 7)

[8] The initial setpoints for Pressurizer High Water Level Trip agree with the design requirements. (Step 6.1[8]C, Data Sheet 8)

[9] The initial setpoints for Low Reactor Coolant Flow Trip agree with the design requirements. (Step 6.1[9]C, Data Sheet 9)

[10] The initial setpoints for Reactor Coolant Pump Undervoltage Trip agree with the design requirements. (Step 6.1 [10]C, Data Sheet 10)

[11] The initial setpoints for Reactor Coolant Pump Underfrequency Trip agree with the design requirements. (Step 6.1 [11]C, Data Sheet 11)

[12] The initial setpoints for Low-Low Steam Generator Water Level Trip, including TTDs, agree with the design requirements. (Step 6.1[12]C, Data Sheet 12)

[13] The initial setpoints for Reactor Trip on Turbine Trip agree with the design requirements. (Step 6.1[13]C, Data Sheet 13)

[14] The initial setpoints for Reactor Trip System Permissives and Interlocks agree with the design requirements. (Step 6.1[14]C, Data Sheet 14)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 18 of 148 5.2 Engineered Safety Features Actuations

[1] The initial setpoints for Low Pressurizer Pressure Safety Injection agree with the design requirements. (Step 6.2[1]C, Data Sheet 15)

[2] The initial setpoints for Low Steamline Pressure Safety Injection and Steamline Isolation agree with the design requirements. (Step 6.2[2]C, Data Sheet 16)

[3] The initial setpoints for Containment High Pressure Safety Injection agree with the design requirements. (Step 6.2[3]C, Data Sheet 17)

(4] The initial setpoints for Safety Injection Manual Reset Time Delay agree with the design requirements. (Step 6.2[4]C, Data Sheet 18)

[5] The initial setpoints for High Negative Steamline Pressure Rate Steamline Isolation agree with the design requirements. (Step 6.2[5]C, Data Sheet 19)

[6] The initial setpoints for High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation agree with the design requirements. (Step 6.2[6]C, Data Sheet 20)

[7] The initial setpoints for the Miscellaneous ESFAS agree with the design requirements: (Step 6.2[7]C, Data Sheet 21)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 19 of 148 Date 6.0 PERFORMANCE NOTES

1) This is a desktop performed instruction. No actual field testing is required. Subsections may be performed in any order. Steps within a subsection are not required to be performed in the order written.
2) Table 1 (Step 4.1[6]) does not have to be fully completed prior to the performance of each step in this subsection. Only the Table 1 instructions applicable to the step, to be performed, must have JTG approval. As an example, JTG concurrence of 2-SI-68-9, 10, and 11 must be obtained in Table 1 (Step 4.1[6]) prior to performance of Step 6.1 [8] and Data Sheet 8. Table 1 (Step 4.1 [6]) should be fully completed prior to completing Section 6.0.

6.1 Reactor Trips

[1] Power Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the "Actual" setpoints from the instructions listed on Data Sheet 1, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY "Actual" setpoints recorded on Data Sheet 1 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[11])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 20 of 148 Date 6.1 Reactor Trips (continued)

[2] Intermediate Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 2, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 2 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[2])

[3] Source Range High Neutron Flux Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 3, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 3 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[3])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 21 of 148 Date 6.1 Reactor Trips (continued)

[4] Power Range High Positive Neutron Flux Rate Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 4, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 4 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[4])

[5] Overtemperature/Overpower Delta T Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 5, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 5 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[5])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 22 of 148 Date 6.1 Reactor Trips (continued)

[6] Pressurizer Low Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 6, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 6 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[6])

[7] Pressurizer High Pressure Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 7, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 7 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[7])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 23 of 148 Date 6.1 Reactor Trips (continued)

[8] Pressurizer High Water Level Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 8, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 8 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[8])

[9] Low Reactor Coolant Flow Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 9, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 9 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[9])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 24 of 148 Date 6.1 Reactor Trips (continued)

[10] Reactor Coolant Pump Undervoltage Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 10, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 10 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1 10])

[11] Reactor Coolant Pump Underfrequency Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 11, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 11 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1 [11])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 25 of 148 Date 6.1 Reactor Trips (continued)

[12] Low-Low Steam Generator Water Level Trip (Including TTDs)

A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 12, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 12 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[12])

[13] Reactor Trip On Turbine Trip A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 13, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 13 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[13])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 26 of 148 Date 6.1 Reactor Trips (continued)

[14] Reactor Trip System Permissives and Interlocks A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 14, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 14 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.1[14])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 27 of 148 Date 6.2 Engineered Safety Features Actuations

[1] Low Pressurizer Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 15, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 15 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[1])

[2] Low Steamline Pressure Safety Injection and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 16, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 16 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[2])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 28 of 148 Date 6.2 Engineered Safety Features Actuations (continued)

[3] Containment High Pressure Safety Injection A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 17, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 17 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[3])

[4] Safety Injection Manual Reset Time Delay A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 18, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 18 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[4])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 29 of 148 Date 6.2 Engineered Safety Features Actuations (continued)

[5] High Negative Steamline Pressure Rate Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 19, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 19 are within the Required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[5])

[6] High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 20, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 20 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[6])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 30 of 148 Date 6.2 Engineered Safety Features Actuations (continued)

[7] Miscellaneous ESFAS Setpoints A. VERIFY prerequisites listed in Section 4.0 have been completed.

B. OBTAIN the Actual setpoints from the instructions listed on Data Sheet 21, AND RECORD the values and work documents utilized in the spaces allocated.

C. VERIFY Actual setpoints recorded on Data Sheet 21 are within the required setpoint tolerance specified, AND INITIAL and DATE in the spaces allocated.

(Acc Crit 5.2[7])

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 31 of 148 Date 7.0 POST PERFORMANCE ACTIVITY

[1] VERIFY copies of the Eagle Surveillance Instruction printouts and applicable data sheets from completed SIs/lMIs/WOs used to verify setpoints have been attached to this instruction and logged in Table 2.

[2] NOTIFY the US/SRO of the test completion.

8.0 RECORDS A. QA Records Completed Test Package (PTI)

B. Non-QA Records None

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 32 of 148 Appendix A (Page 1 of 1)

Test Procedures / Instructions Reference Review Date NOTES

1) Additional copies of this table may be made as necessary.
2) Initial and date indicates review has been completed for impact.

PROCEDURE/ REVISION/CHANGES IMPACT INITIAL AND INSTRUCTION Yes/No DATE. (N/A for no change)

U2 FSAR Table 14.2.1 Section 7.2 Section 7.3 PTI-99-06 2-TSD-99-06 WBN2-99-4003 WBN2-47-4002

  • 4 4 4 t .~ 4 4 4 4

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 33 of 148 Table 1 (Page 1 of 5)

Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI JTG Meeting Number Initial 2-SI-1-1 2-SI-1-2 2-SI-1-3 2-SI-1-4 2-SI-1-5 2-SI-1-6 2-SI-1-7 2-S1-1-8 2-SI-1-9 2-SI-1-10 2-SI-1-11 2-SI-1-12 2-SI-1-72 2-SI-1-73 2-Sl-3-1 2-SI-3-2 2-Sl-3-3 2-SI-3-4 2-SI-3-5 2-SI-3-6

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 34 of 148 Table I (Page 2 of 5)

Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI JTG Meeting Number Initial 2-SI-3-7 2-SI-3-8 2-SI-3-9 2-S1-3-10 2-SI-3-11 2-SI-3-12 2-SI-3-13 2-SI-3-14 2-SI-3-15 2-SI-3-21 2-SI-3-22 2-SI-3-25 2-SI-3-26 2-SI-3-402 2-SI-3-403 2-SI-3-404 2-SI-3-405 2-SI-3-406 2-SI-3-407 2-SI-30-42

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 35 of 148 Table I (Page 3 of 5)

Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI JTG Meeting Number Initial 2-SI-30-43 2-SI-30-44 2-SI-30-45 2-SI-63-1 2-SI-63-2 2-SI-63-3 2-SI-63-4 2-SI-63-50 2-SI-63-51 2-SI-63-52 2-SI-63-53 2-SI-68-1 2-SI-68-2 2-SI-68-3 2-SI-68-4 2-SI-68-5 2-SI-68-6 2-SI-68-7 2-SI-68-8 2-SI-68-9

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Paqe 36 of 148 Table 1 (Page 4 of 5)

Plant Instruction and PTI Verification of JTG Concurrence Date Plant InstructionlPTI JTG Meeting Number Initial 2-SI-68-10 2-SI-68-11 2-SI-68-12 2-SI-68-13 2-SI-68-14 2-SI-68-15 2-SI-68-16 2-SI-68-17 2-SI-68-18 2-SI-68-19 2-SI-68-20 2-SI-68-21 2-SI-68-22 2-SI-68-23 2-SI-68-36 2-SI-68-37 2-SI-68-38 2-SI-68-39 2-SI-68-40 2-SI-68-41

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 37 of 148 Table 1 (Page 5 of 5)

Plant Instruction and PTI Verification of JTG Concurrence Date Plant Instruction/PTI JTG Meeting Number Initial 2-SI-68-42 2-SI-68-43 2-SI-92-31 2-SI-92-32 2-SI-92-41 2-SI-92-42 2-SI-92-43 2-SI-92-44 2-SI-47-28 2-SI-47-73 2-SI-47-74 2-SI-47-75 2-S 1-99-1 0-A 2-SI-99-10-B 2-PTI-99-05 2-ATI-047A-02 SSD-2-LPP-2-1 SSD-2-LPP-2-7 WO 113725926 (CTN 2-001-12296-IU1-000) 2-47A630-98-205

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 38 of 148 Data Sheet 1 (Page 1 of 2)

Power Range High Neutron Flux Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[1] Power Range 2-INS 25% RTP 24.4 to 25.6% 2-SI-92-41 High Flux Low 1NC/305-D (2.083 VDC) RTP (2.033 to Setpoint (NC-41P) INCR 2.133 VDC) 6.1[1] 2-INS 25% RTP 24.4 to 25.6% 2-SI-92-42 2NC/305-E (2.083 VDC) RTP (2.033 to (NC-42P) INCR 2.133 VDC) 6.1[1] 2-INS 25% RTP 24.4 to 25.6% 2-SI-92-43 3NC/305-F (2.083 VDC) RTP (2.033 to (NC-43P) INCR 2.133 VDC) 6.1[1] 2-INS 25% RTP 24.4 to 25.6% 2-SI-92-44 4NC/305-G (2.083 VDC) RTP (2.033 to (NC-44P) INCR 2.133 VDC)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 39 of 148 Data Sheet I (Page 2 of 2)

Power Range High Neutron Flux Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[1] Power Range 2-INS 109% RTP 108.4 to 109.6 2-SI-92-41 High Flux 1NC/306-D (9.083 VDC)  % RTP (9.033 to High Setpoint (NC-41R) INCR 9.133 VDC) 6.111] 2-INS 109% RTP 108.4 to 109.6 2-SI-92-42 2NC/306-E (9.083 VDC)  % RTP (9.033 to (NC-42R) INCR 9.133 VDC) 6.1[1] 2-INS 109% RTP 108.4 to 109.6 2-SI-92-43 3NC/306-F (9.083 VDC)  % RTP (9.033 to (NC-43R) INCR 9.133 VDC) 6.1[1] 2-INS 109% RTP 108.4 to 109.6 2-SI-92-44 4NC/306-G (9.083 VDC)  % RTP (9.033 to (NC-44R) INCR 9.133 VDC)

Recorded By:

Verified By:

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 40 of 148 Data Sheet 2 (Page 1 of 1)

Intermediate Range High Neutron Flux Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[21 High Flux 2-NI-92-135-D 25% RTP 23.4 to 26.7% 2-SI-92-31 TRIP (9.398 VDC) RTP INCR (9.370 to 9.426 VDC) 6.1[2] High Flux 2-NI-92-136-E 25% RTP 23.4 to 26.7% 2-SI-92-32 TRIP (9.398 VDC) RTP INCR (9.370 to 9.426 VDC)

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 41 of 148 Data Sheet 3 (Page 1 of 1)

Source Range High Neutron Flux Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Set Tolerance Actual Set Instruction Work PKG Initial/Date Section Description TVA/W Point Action Point Action NO.

6.1[3] Source Range 2-NI-92-131-D 105 CPS 9.973 to 2-SI-92-31 High Flux (10.0 VDC) 10.027 VDC TRIP INCR 6.1[3] 2-NI-92-132-E 105 CPS 9.973 to 2-SI-92-32 (10.0 VDC) 10.027 VDC INCR Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 42 of 148 Data Sheet 4 (Page 1 of 2)

Power Range High Positive Neutron Flux Rate Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[4] Power Range 2-INS +5% RTP 4.4 to 5.6 % 2-SI-92-41 Positive Rate 1NC/303-D INCR RTP (NC-41U) 6.1[4] 2-INS +5% RTP 4.4 to 5.6 % 2-SI-92-42 2NC/303-E INCR RTP (NC-42U) 6.1 [4] 2-INS +5% RTP 4.4 to 5.6 % 2-SI-92-43 3NC/303-F INCR RTP (NC-43U) 6.1[4] 2-INS +5% RTP 4.4 to 5.6 % 2-SI-92-44 4NC/303-G INCR RTP (NC-44U)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 43 of 148 Data Sheet 4 (Page 2 of 2)

Power Range High Positive Neutron Flux Rate Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVAIW Setpoint Setpoint NO.

Action Action 6.1[4] Impulse Unit 2-INM 2.4 SEC 2.2 -2.6 SEC 2-SI-92-41 Time 1NM/311-D Constant (NM-41J) 6.1[4] 2-INM 2.4 SEC 2.2 -2.6 SEC 2-SI-92-42 2NM/311-E (NM-42J) 6.1[4] 2-INM 2.4 SEC 2.2 -2.6 SEC 2-SI-92-43 3NM/311-F (NM-43J) 6.1[4] 2-INM 2.4 SEC 2.2 -2.6 SEC 2-SI-92-44 4NM/311-G (NM-44J)

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 44 of 148 Data Sheet 5 (Page 1 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances if applicable.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoint Action recorded for Eagle outputs are actual minimum and maximum values.
4) Actual Setpoint Action recorded for Eagle may have co-processor floating point calculation roundoff (i.e., 588.2 F may be presented as 588.1999 which is acceptable).
5) The K5 and K6 gains are set to 0.0 at specific Tavg conditions by logic internal to the Eagle-21 system and are not user entered setpoints.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Delta T Tavg Delta TO 51 OF NO 2-SI-68-1 Channel I DEVIATION ALLOWED 6.1[5] Tavg 0 Full 588.2 OF NO 2-SI-68-1 OTSP DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 45 of 148 Data Sheet 5 (Page 2 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Tavg1 Full 588.2 OF NO 2-SI-68-1 OPSP DEVIATION ALLOWED 6.1[5] F2 (DI) W 0.0 NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F2 (DI) F 0.0 PU NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F2 (DI) I 0.0 PU NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F2 (DI) H 0.0 NO 2-SI-68-1 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 46 of 148 Data Sheet 5 (Page 3 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1 [5] F2 (DI) V -0.01 /PU NO 2-S1-68-1 DEVIATION ALLOWED 6.1[5] F2 (DI) J 0.01 /PU NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F1 (DI) Q 0.7336 NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F1 (DI) A -22.0 PU NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F1 (DI) D 10.0 PU NO 2-SI-68-1 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 47 of 148 Data Sheet 5 (Page 4 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVAIW Setpoint Setpoint NO.

Action Action 6.1[5] F1 (DI) C 0.49 NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] F1 (DI) B -0.0262/PU NO 2-S1-68-1 DEVIATION ALLOWED 6.1[5] F1 (DI) N 0.0196/PU NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] Tau 1 Lead 33.0 SEC 32.67 to 33.33 2-SI-68-1 Tavg SEC 6.1[5] Tau 2 Lag 4.0 SEC 3.96 to 4.04 2-SI-68-1 Tavg SEC 6.1[5] Tau 3 Rate 5.0 SEC 4.95 to 5.05 2-SI-68-1 Tavg SEC

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 48 of 148 Data Sheet 5 (Page 5 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Tau 4 Lead 3.0 SEC 2.97 to 3.03 2-SI-68-1 Delta T SEC 6.1[5] Tau 5 Lag 3.0 SEC 2.97 to 3.03 2-SI-68-1 Delta T SEC 6.1[5] Tau 6 Lag T 0.0 SEC NO 2-SI-68-1 Hot DEVIATION ALLOWED 6.1[5] Tau 7 Lag T 0.0 SEC NO 2-SI-68-1 Cold DEVIATION ALLOWED 6.1[5] Tau 8 Lag 300.0 SEC 297.0 to 303.0 2-SI-68-1 Stream SEC 6.1[5] K1 OTSP 1.16 NO 2-SI-68-1 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 49 of 148 Data Sheet 5 (Page 6 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] K2 OTSP 0.0183/OF NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] K3 OTSP 0.0009/ PSIG NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] K4OPSP 1.10 NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] K5 OPSP 0.02 /OF NO 2-SI-68-1 (Note 5) DEVIATION ALLOWED 6.1[5] K6 OPSP 0.00162/OF NO 2-SI-68-1 (Note 5) DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 50 of 148 Data Sheet 5 (Page 7 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVAW Setpoint Setpoint NO.

Action Action 6.1[5] P0 OTSP 2235.0 PSIG NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] DELTAH RSA 8.0 OF NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] DELTAC RSA 2.5 OF NO 2-SI-68-1 DEVIATION ALLOWED 6.115] S1 Streaming 0.0 OF NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] S2 Streaming 0.0 OF NO 2-SI-68-1 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 51 of 148 Data Sheet 5 (Page 8 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] S3 Streaming 0.0 OF NO 2-SI-68-1 DEVIATION ALLOWED 6.1[5] SCAL FLUX 1.8 NO 2-SI-68-1 CALIB DEVIATION ALLOWED 6.1[5] PLOW STRM 0.5 NO 2-SI-68-1 CAL THR DEVIATION ALLOWED 6.1[5] Lo Tavg 2-TS-68-2K 564.0 OF 563.77 to 2-SI-68-1 (FW Isol) (TB-412G) DEEN DECR 564.23 OF 6.1 [5] Delta T Tavg 2-TS-68-2D 0.00 PU -0.84 to 0.84 2-SI-68-1 OTDT Trip (TB-41 lC) DEEN INCR PU 6.1[5] Delta T Tavg TS-68-2G 0.00 PU -0.54 to 0.54 2-SI-68-1 OPDT Trip (TB-411G) DEENINCR PU

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 52 of 148 Data Sheet 5 (Page 9 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Delta T Tavg Delta TO 51 OF NO 2-SI-68-2 Channel II DEVIATION ALLOWED 6.1151 Tavg 0 Full 588.2 OF NO 2-SI-68-2 OTSP DEVIATION ALLOWED 6.1[5] Tavg 1 Full 588.2 OF NO 2-SI-68-2 OPSP DEVIATION ALLOWED 6.1[5] F2 (DI) W 0.0 NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F2 (DI) F 0.0 PU NO 2-SI-68-2 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 53 of 148 Data Sheet 5 (Page 10 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] F2 (DI) I 0.0 PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F2 (DI) H 0.0 NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F2 (DI) V - 0.01 /PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F2 (DI) J 0.01 /PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F1 (DI) Q 0.7336 NO 2-SI-68-2 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 54 of 148 Data Sheet 5 (Page 11 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1 [5] F1 (DI) A - 22.0 PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F1 (DI) D 10.0 PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F1 (DI) C 0.49 NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F1 (DI) B -0.0262/PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] F1 (DI) N 0.0196/PU NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] Tau 1 Lead 33.0 SEC 32.67 to 33.33 2-SI-68-2 Tavg SEC

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 55 of 148 Data Sheet 5 (Page 12 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Tau 2 Lag 4.0 SEC 3.96 to 4.04 2-SI-68-2 Tavg SEC 6.1[5] Tau 3 Rate 5.0 SEC 4.95 to 5.05 2-SI-68-2 Tavg SEC 6.1[5] Tau 4 Lead 3.0 SEC 2.97 to 3.03 2-SI-68-2 Delta T SEC 6.1[5] Tau 5 Lag 3.0 SEC 2.97 to 3.03 2-SI-68-2 Delta T SEC 6.1[5] Tau 6 Lag T 0.0 SEC NO 2-SI-68-2 Hot DEVIATION ALLOWED 6.1[5] Tau 7 Lag T 0.0 SEC NO 2-SI-68-2 Cold DEVIATION ALLOWED 6.1[5] Tau 8 Lag 300.0 SEC 297.0 to 303.0 2-SI-68-2 Stream SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 56 of 148 Data Sheet 5 (Page 13 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -I-VA/W Setpoint Setpoint NO.

Action Action 6.1[5] K1 OTSP 1.16 NO 2-SI-68-2 DEVIATION ALLOWED 6.1 [51 K2 OTSP 0.0183 /OF NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] K3 OTSP 0.0009/ PSIG NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] K4 OPSP 1.10 NO 2-SI-68-2 DEVIATION ALLOWED 6.1 [5] K5 OPSP 0.02 /OF NO 2-SI-68-2 (Note 5) DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 57 of 148 Data Sheet 5 (Page 14 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] K6 OPSP 0.00162/0 F NO 2-SI-68-2 (Note 5) DEVIATION ALLOWED 6.1[5] P0 OTSP 2235.0 PSIG NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] DELTAH RSA 8.0 OF NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] DELTAC RSA 2.5 OF NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] S1 Streaming 0.0 OF NO 2-SI-68-2 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 58 of 148 Data Sheet 5 (Page 15 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -IVA/W Setpoint Setpoint NO.

Action Action 6.1[5] S2 Streaming 0.0 OF NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] S3 Streaming 0.0 OF NO 2-SI-68-2 DEVIATION ALLOWED 6.1[5] SCAL FLUX 1.80 NO 2-SI-68-2 CALIB DEVIATION ALLOWED 6.1[5] PLOW STRM 0.5 NO 2-SI-68-2 CALTHR DEVIATION ALLOWED 6.1 [5] Lo Tavg 2-TS-68-25K 564.0 OF 563.77 to 2-SI-68-2 (FW Isol) (TB-422G) DEEN DECR 564.23 OF 6.1[5] Delta T Tavg 2-TS-68-25D 0.00 PU -0.84 to 0.84 2-SI-68-2 OTDT Trip (TB-421C) DEEN INCR PU

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 59 of 148 Data Sheet 5 (Page 16 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Delta TTavg 2-TS-68-25G 0.00 PU -0.54 to 0.54 2-SI-68-2 OPDT Trip (TB-421G) DEENINCR PU 6.1[5] Delta T Tavg Delta TO 51 OF NO 2-SI-68-3 Channel III DEVIATION ALLOWED 6.1[5] Tavg 0 Full 588.2 OF NO 2-SI-68-3 OTSP DEVIATION ALLOWED 6.1[5] Tavg 1 Full 588.2 OF NO 2-SI-68-3 OPSP DEVIATION ALLOWED 6.1[5] F2 (DI) W 0.0 NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F2 (DI) F 0.0 PU NO 2-SI-68-3 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 60 of 148 Data Sheet 5 (Page 17 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] F2 (DI) I 0.0 PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F2 (DI) H 0.0 NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F2 (DI)V -0.01/PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F2 (DI) J 0.01 /PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F1 (DI) Q 0.7336 NO 2-SI-68-3 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 61 of 148 Data Sheet 5 (Page 18 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] F1 (DI) A - 22.0 PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F1 (DI) D 10.0 PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F1 (DI) C 0.49 NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F1 (DI) B -0.0262/PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] F1 (DI) N 0.0196/PU NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] Tau 1 Lead 33.0 SEC 32.67 to 33.33 2-SI-68-3 Tavg SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 62 of 148 Data Sheet 5 (Page 19 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description IVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Tau 2 Lag 4.0 SEC 3.96 to 4.04 2-SI-68-3 Tavg SEC 6.1[5] Tau 3 Rate 5.0 SEC 4.95 to 5.05 2-SI-68-3 Tavg SEC 6.1[5] Tau 4 Lead 3.0 SEC 2.97 to 3.03 2-SI-68-3 Delta T SEC 6.1[5] Tau 5 Lag 3.0 SEC 2.97 to 3.03 2-SI-68-3 Delta T SEC 6.1[5] Tau 6 Lag T 0.0 SEC NO 2-SI-68-3 Hot DEVIATION ALLOWED 6.1[5] Tau 7 Lag T 0.0 SEC NO 2-SI-68-3 Cold DEVIATION ALLOWED 6.1[5] Tau 8 Lag 300.0 SEC 297.0 to 303.0 2-SI-68-3 Stream SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 63 of 148 Data Sheet 5 (Page 20 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -I-VAW Setpoint Setpoint NO.

Action Action 6.1[5] K1 OTSP 1.16 NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] K2OTSP 0.0183/OF NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] K3 OTSP 0.0009/ PSIG NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] K4 OPSP 1.10 NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] K5 OPSP 0.02 /OF NO 2-SI-68-3 (Note 5) DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 64 of 148 Data Sheet 5 (Page 21 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] K6 OPSP 0.00162/°F NO 2-SI-68-3 (Note 5) DEVIATION ALLOWED 6.1[5] P0 OTSP 2235.0 PSIG NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] DELTAH RSA 8.0 OF NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] DELTAC RSA 2.5 OF NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] S1 Streaming 0.0 OF NO 2-SI-68-3 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 65 of 148 Data Sheet 5 (Page 22 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/ Setpoint Setpoint NO.

Action Action 6.1[5] S2 Streaming 0.0 OF NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] S3 Streaming 0.0 OF NO 2-SI-68-3 DEVIATION ALLOWED 6.1[5] SCAL FLUX 1.8 NO 2-SI-68-3 CALIB DEVIATION ALLOWED 6.1[5] PLOW STRM 0.5 NO 2-SI-68-3 CAL THR DEVIATION ALLOWED 6.1 [5] Lo Tavg 2-TS-68-44K 564.0 OF 563.77 to 2-SI-68-3 (FW Isol) (TB-432G) DEEN DECR 564.23 OF 6.1 [5] Delta T Tavg 2-TS-68-44D 0.00 PU -0.84 to 0.84 2-SI-68-3 OTDT Trip (TB-431C) DEEN INCR PU

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 66 of 148 Data Sheet 5 (Page 23 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Delta T Tav 2-TS-68-44G 0.00 PU -0.54 to 0.54 2-SI-68-3 OPDT Trip (TB-431G) DEENINCR PU 6.1[5] Delta T Tavg Delta TO 51 OF NO 2-SI-68-4 Channel IV DEVIATION ALLOWED 6.1[5] Tavg 0 Full 588.2 OF NO 2-SI-68-4 OTSP DEVIATION ALLOWED 6.1[5] Tavg 1 Full 588.2 OF NO 2-SI-68-4 OPSP DEVIATION ALLOWED 6.1[5] F2 (DI) W 0.0000 NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F2 (DI) F 0.0 PU NO 2-SI-68-4 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 22-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 67 of 148 Data Sheet 5 (Page 24 of 30).

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] F2 (DI) I 0.0 PU NO 2-SI-68-4 DEVIATION ALLOWED 6.115] F2 (DI) H 0.0 NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F2 (DI) V - 0.01 /PU NO 2-SI-68-4 DEVIATION ALLOWED 6.115] F2 (DI) J 0.01 /PU NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F1 (DI) Q 0.7336 NO 2-SI-68-4 DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 68 of 148 Data Sheet 5 (Page 25 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] F1 (DI) A - 22.0 PU NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F1 (DI) D 10.0 PU NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F1 (DI) C 0.49 NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F1 (DI) B -0.0262/PU NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] F1 (DI) N 0.0196/PU NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] Tau 1 Lead 33.0 SEC 32.67 to 33.33 2-SI-68-4 Tavg SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 69 of 148 Data Sheet 5 (Page 26 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Tau 2 Lag 4.0 SEC 3.96 to 4.04 2-SI-68-4 Tavg SEC 6.1[5] Tau 3 Rate 5.0 SEC 4.95 to 5.05 2-SI-68-4 Tavg SEC 6.1[5] Tau 4 Lead 3.0 SEC 2.97 to 3.03 2-SI-68-4 Delta T SEC 6.115] Tau 5 Lag 3.0 SEC 2.97 to 3.03 2-SI-68-4 Delta T SEC 6.1[5] Tau 6 Lag T 0.0 SEC NO 2-SI-68-4 Hot DEVIATION ALLOWED 6.1[5] Tau 7 Lag T 0.0 SEC NO 2-SI-68-4 Cold DEVIATION ALLOWED 6.1[5] Tau 8 Lag 300.0 SEC 297.0 to 303.0 2-SI-68-4 Stream SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 70 of 148 Data Sheet 5 (Page 27 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] K1 OTSP 1.16 NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] K2 OTSP 0.0183 /OF NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] K3 OTSP 0.0009/ PSIG NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] K4 OPSP 1.10 NO 2-SI-68-4 DEVIATION ALLOWED 6.1 [5] K5 OPSP 0.02 /OF NO 2-SI-68-4 (Note 5) DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 22-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 71 of 148 Data Sheet 5 (Page 28 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] K6 OPSP 0.00162/OF NO 2-SI-68-4 (Note 5) DEVIATION ALLOWED 6.1[5] P0 OTSP 2235.0 PSIG NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] DELTAH RSA 8.0 OF NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] DELTAC RSA 2.5 OF NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] S1 Streaming 0.0 OF NO 2-SI-68-4 DEVIATION ALLOWED

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 72 of 148 Data Sheet 5 (Page 29 of 30)

Overtem perature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction *Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] S2 Streaming 0.0 OF NO 2-SI-68-4 DEVIATION ALLOWED 6.1[5] S3 Streaming 0.0 OF NO 2-SI-68-4 DEVIATION ALLOWED 6.1 [5] SCAL FLUX 1.80 NO 2-SI-68-4 CALIB DEVIATION ALLOWED 6.1[5] PLOW STRM 0.5 NO 2-SI-68-4 CALTHR DEVIATION ALLOWED 6.1[5] Lo Tavg 2-TS-68-67K 564.0 OF 563.77 to 2-SI-68-4 (FW Isol) (TB-442G) DEEN DECR 564.23 OF 6.1[5] Delta T Tavg 2-TS-68-67D 0.00 PU -0.84 to 0.84 2-SI-68-4 OTDT Trip (TB-441C) DEEN INCR PU

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 73 of 148 Data Sheet 5 (Page 30 of 30)

Overtemperature/Overpower Delta T Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[5] Delta T Tavg 2-TS-68-67G 0.00 PU -0.54 to 0.54 2-SI-68-4 OPDT Trip (TB-441G) DEEN INCR PU Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 74 of 148 Data Sheet 6 (Page 1 of 3)

Pressurizer Low Pressure Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVAW Setpoint Setpoint NO.

Action Action 6.1[6] Pressurizer 2-PS-68-340E 1970 PSIG 1968.4 to 2-SI-68-5 Low Pressure (PB-455C) DECR 1971.6 PSIG Trip 6.1 [6] 2-PS-68-334E 1970 PSIG 1968.4 to 2-SI-68-6 (PB-456C) DECR 1971.6 PSIG 6.1[6] 2-PS-68-323E 1970 PSIG 1968.4 to 2-SI-68-7 (PB-457C) DECR 1971.6 PSIG 6.1[6] 2-PS-68-322E 1970 PSIG 1968.4 to 2-SI-68-8 (PB-458C) DECR 1971.6 PSIG

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 75 of 148 Data Sheet 6 (Page 2 of 3)

Pressurizer Low Pressure Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[6] P-455 Lead Tau 1 Pzr 12 SEC 11.88 to 12.12 2-SI-68-5 Time Press Lead SEC Constant 6.1[6] P-455 Lag Tau 2 Pzr 2 SEC 1.98 to 2.02 2-SI-68-5 Time Press Lag SEC Constant 6.1[6] P-456 Lead Tau 1 Pzr 12 SEC 11.88 to 12.12 2-SI-68-6 Time Press Lead SEC Constant 6.1[6] P-456 Lag Tau 2 Pzr 2 SEC 1.98 to 2.02 2-SI-68-6 Time Press Lag SEC Constant 6.1[6] P-457 Lead Tau 1 Pzr 12 SEC 11.88 to 12.12 2-SI-68-7 Time Press Lead SEC Constant

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 76 of 148 Data Sheet 6 (Page 3 of 3)

Pressurizer Low Pressure Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[6] P-457 Lag Tau 2 Pzr 2 SEC 1.98 to 2.02 2-SI-68-7 Time Press Lag SEC Constant 6.1[6] P-458 Lead Tau 1 Pzr 12 SEC 11.88 to 12.12 2-SI-68-8 Time Press Lead SEC Constant 6.1[6] P-458 Lag Tau 2 Pzr 2 SEC 1.98 to 2.02 2-SI-68-8 Time Press Lag SEC Constant Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 77 of 148 Data Sheet 7 (Page 1 of 1)

Pressurizer High Pressure Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint Action Action 6.1[7] Pressurizer High 2-PS-68-340A 2385 PSIG 2383.4 to 2-SI-68-5 Pressure Trip (PB-455A) INCR 2386.6 PSIG 6.1[7] 2-PS-68-334A 2385 PSIG 2383.4 to 2-SI-68-6 (PB-456A) INCR 2386.6 PSIG 6.1[7] 2-PS-68-323A 2385 PSIG 2383.4 to 2-SI-68-7 (PB-457A) INCR 2386.6 PSIG 6.1[7] 2-PS-68-322A 2385 PSIG 2383.4 to 2-SI-68-8 (PB-458A) INCR 2386.6 PSIG Recorded By: /

Verified By: I

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 78 of 148 Data Sheet 8 (Page 1 of 1)

Pressurizer High Water Level Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be with the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint and/or Action Action RIMS NO.

6.1[8] Pressurizer 2-LS-68-339A 92% INCR 91.8 to 92.2 2-SI-68-9 High Level (LB-459A)  %

Trip 6.1 [8] 2-LS-68-335A 92% INCR 91.8 to 92.2 2-SI-68-10 (LB-460A)  %

6.1[8] .2-LS-68-320A 92% INCR 91.8 to 92.2 2-SI-68-11 (LB-461A)  %

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 79 of 148 Data Sheet 9 (Page 1 of 4)

Low Reactor Coolant Flow Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be with the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[9] Reactor 2-FS-68-6A 90% Flow 66.76 to 67.12 2-SI-68-12 Coolant (FB-414A) 66.94% DP  % DP System Low DECR Flow Loop 1 6.1[9] 2-FS-68-6B 90% Flow 66.76 to 67.12 2-SI-68-13 (FB-415A) 66.94% DP  % DP DECR 6.1[9] 2-FS-68-6D 90% Flow 66.76 to 67.12 2-SI-68-14 (FB-416A) 66.94% DP  % DP DECR

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 80 of 148 Data Sheet 9 (Page 2 of 4)

Low Reactor Coolant Flow Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[9] Reactor 2-FS-68-29A 90% Flow 66.76 to 67.12 2-SI-68-15 Coolant (FB-424A) 66.94% DP  % DP System Low DECR Flow Loop 2 6.1[9] 2-FS-68-29B 90% Flow 66.76 to 67.12 2-SI-68-16 (FB-425A) 66.94% DP  % DP DECR 6.1[9] 2-FS-68-29D 90% Flow 66.76 to 67.12 2-SI-68-17 (FB-426A) 66.94% DP  % DP DECR 6.1[9] Reactor 2-FS-068-48A 90% Flow 66.76 to 67.12 2-SI-68-18 Coolant (FB-434A) 66.94% DP  % DP System Low DECR Flow Loop 3

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 81 of 148 Data Sheet 9 (Page 3 of 4)

Low Reactor Coolant Flow Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -T-VA/W Setpoint Setpoint NO.

Action Action 6.1[9] 2-FS-068-48B 90% Flow 66.76 to 67.12 2-SI-68-19 (FB-435A) 66.94% DP  % DP DECR 6.1[9] 2-FS-068-48D 90% Flow 66.76 to 67.12 2-SI-68-20 (FB-436A) 66.94% DP  % DP DECR 6.119] Reactor 2-FS-068-71A 90% Flow 66.76 to 67.12 2-SI-68-21 Coolant (FB-444A) 66.94% DP  % DP System Low DECR Flow Loop 4 6.1[9] 2-FS-068-71B 90% Flow 66.76 to 67.12 2-SI-68-22 (FB-445A) 66.94% DP  % DP DECR 6.1[9] 2-FS-068-71D 90% Flow 66.76 to 67.12 2-SI-68-23 (FB-446A) 66.94% DP  % DP DECR

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 82 of 148 Data Sheet 9 (Page 4 of 4)

Low Reactor Coolant Flow Trip Setpoint Verification Date Recorded By:

Verified By: /

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 83 of 148 Data Sheet 10 (Page I of 2)

Reactor Coolant Pump Undervoltage Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[10] RCP 2-27-68-8A 90 VAC 89.0 to 91.0 2-SI-68-40 Undervoltage DECR VAC Trip Pump 1 6.1[10] Total Time 2-62-68-8 0.431 SEC 0.384 to 0.478 2-SI-68-40 Delay SEC 6.1[10] Pump 2 2-27-68-31A 90 VAC 89.0 to 91.0 2-SI-68-41 DECR VAC 6.1[10] 2-62-68-31 0.431 SEC 0.384 to 0.478 2-SI-68-41 SEC 6.1[10] Pump 3 2-27-68-50A 90 VAC 89.0 to 91.0 2-SI-68-42 DECR VAC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 84 of 148 Data Sheet 10 (Page 2 of 2)

Reactor Coolant Pump Undervoltage Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[10] 2-62-68-50 0.431 SEC 0.384 to 0.478 2-SI-68-42 SEC 6.1[10] Pump 4 2-27-68-73A 90 VAC 89.0 to 91.0 2-SI-68-43 DECR VAC 6.1[10] 2-62-68-73 0.431 SEC 0.384 to 0.478 2-SI-68-43 SEC Recorded By: /

Verified By: I

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 85 of 148 Data Sheet 11 (Page 1 of 2)

Reactor Coolant Pump Underfrequency Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[11] RCP Under- 2-81-68-8 57.5 Hertz 57.45 to 57.55 2-SI-68-36 frequency DECR Hertz TRIP Pump 1 6.1 [11] Time Delay 0.14 SEC 0.1 to 0.19 2-SI-68-36 (8 Cycles) SEC (6 to 11 Cycles) 6.1[11] Pump 2 2-81-68-31 57.5 Hertz 57.45 to 57.55 2-SI-68-37 DECR Hertz 6.1[11] Time Delay 0.14 SEC 0.1 to 0.19 2-SI-68-37 (8 Cycles) SEC (6 to 11 Cycles)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 86 of 148 Data Sheet 11 (Page 2 of 2)

Reactor Coolant Pump Underfrequency Trip Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVAIW Setpoint Setpoint NO.

Action Action 6.1 [11] Pump 3 2-81-68-50 57.5 Hertz 57.45 to 57.55 2-SI-68-38 DECR Hertz 6.1[11] Time Delay 0.14 SEC 0.1 to 0.19 2-SI-68-38 (8 Cycles) SEC (6 to 11 Cycles) 6.1[11] Pump 4 2-81-68-73 57.5 Hertz 57.45 to 57.55 2-SI-68-39 DECR Hertz 6.1[11] Time Delay 0.14 SEC 0.1 to 0.19 2-SI-68-39 (8 Cycles) SEC (6 to 11 Cycles)

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 87 of 148 Data Sheet 12 (Page 1 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances if applicable.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.
4) Actual Setpoint Action recorded for Eagle may have co-processor floating point calculation roundoff (i.e., 588.2 F may be presented as 588.1999 which is acceptable).
5) Delta TO is set to match Delta TO in the OTDT/OPDT trip functions and is also set conservatively.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] Lo-Lo SG 2-LS-3-38B 17% DECR 16.8 to 17.2% 2-SI-3-13 Water Level Trip &TTDs (LB-5i9B)

Channel II 6.1[12] Tau 6 Lag T 0.0 SEC NO 2-SI-3-13 Hot DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 88 of 148 Data Sheet 12 (Page 2 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] Tau 7 Lag T 0.0 SEC NO 2-SI-3-13 Cold DEVIATION ALLOWED 6.1[12] S1 Streaming 0.00 OF NO 2-SI-3-13 DEVIATION ALLOWED 6.1[12] S2 Streaming 0.00 OF NO 2-SI-3-13 DEVIATION ALLOWED 6.1[12] S3 Streaming 0.00 OF NO 2-SI-3-13 DEVIATION ALLOWED 6.1[12] DELTAH 8.0 OF NO 2-SI-3-13 RSA DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 89 of 148 Data Sheet 12 (Page 3 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -I-VA/W Setpoint Setpoint NO.

Action Action 6.1[12] DELTAC 2.5 OF NO 2-SI-3-13 RSA DEVIATION ALLOWED 6.1[12] Delta TO 51.0 OF NO 2-SI-3-13 (Note 5) DEVIATION ALLOWED 6.1[12] TTD Coef. A - 0.0085041 NO 2-SI-3-13 SEC/PU3 DEVIATION ALLOWED 6.1[12] TTD Coef. B 0.9266400 NO 2-SI-3-13 SEC/PU2 DEVIATION ALLOWED 6.1[12] TTD Coef. C - 33.85998 NO 2-SI-3-13 SEC/PU DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 90 of 148 Data Sheet 12 (Page 4 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Coef. D 474.6060 NO 2-SI-3-13 SEC DEVIATION ALLOWED 6.1[12] TTD Coef. E -0.0047421 NO 2-SI-3-13 SEC/PU3 DEVIATION ALLOWED 6.1[12] TTD Coef. F 0.5682600 NO 2-SI-3-13 SEC/PU 2 DEVIATION ALLOWED 6.1[12] TTD Coef. G - 23.70753 NO 2-SI-3-13 SEC/PU DEVIATION ALLOWED 6.11[12] TTD Coef. H 357.9840 NO 2-SI-3-13 SEC DEVIATION ALLOWED

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 91 of 148 Data Sheet 12 (Page 5 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Power 50.0 PU NO 2-SI-3-13 Hi Limit DEVIATION ALLOWED 6.1[12] 2-LS-3-51B 17% DECR 16.8 to 17.2% 2-SI-3-13 (LB-529B) 6.1[12] 2-LS-3-93B 17% DECR 16.8 to 17.2% 2-SI-3-13 (LB-539B) 6.1[12] 2-LS-3-106B 17% DECR 16.8 to 17.2% 2-SI-3-13 (LB-549B) 6.1[12] Lo-Lo SG 2-LS-3-39B 17% DECR 16.8 to 17.2% 2-SI-3-14 Water Level Trip & TTDs (LB-5i8B)

Channel III 6.1[12] Tau 6 Lag T 0.0 SEC NO 2-SI-3-14 Hot DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 92 of 148 Data Sheet 12 (Page 6 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] Tau 7 Lag T 0.0 SEC NO 2-SI-3-14 Cold DEVIATION ALLOWED 6.1[12] S1 Streaming 0.0 OF NO 2-SI-3-14 DEVIATION ALLOWED 6.1[12] S2 Streaming 0.0 OF NO 2-SI-3-14 DEVIATION ALLOWED 6.1[12] S3 Streaming 0.0 OF NO 2-SI-3-14 DEVIATION ALLOWED 6.1[12] DELTAH 8.0 OF NO 2-SI-3-14 RSA DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 93 of 148 Data Sheet 12 (Page 7 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Setpoint NO.

Action Action 6.1112] DELTAC 2.5 OF NO 2-SI-3-14 RSA DEVIATION ALLOWED 6.1[12] Delta TO 51.0 OF NO 2-SI-3-14 (Note 5) DEVIATION ALLOWED 6.1[12] TTD Coef. A - 0.0085041 NO 2-SI-3-14 SEC/PU3 DEVIATION ALLOWED 6.1[12] TTD Coef. B 0.9266400 NO 2-SI-3-14 SEC/PU2 DEVIATION ALLOWED 6.1[12] TTD Coef. C - 33.85998 NO 2-SI-3-14 SEC/PU DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 94 of 148 Data Sheet 12 (Page 8 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description IVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Coef. D 474.6060 NO 2-SI-3-14 SEC DEVIATION ALLOWED 6.1[12] TTD Coef. E - 0.0047421 NO 2-SI-3-14 SEC/PU 3 DEVIATION ALLOWED 6.1[12] TTD Coef. F 0.5682600 NO 2-SI-3-14 SEC/PU 2 DEVIATION ALLOWED 6.1[12] TTD Coef. G - 23.70753 NO 2-SI-3-14 SEC/PU DEVIATION ALLOWED 6.1[12] TTD Coef. H 357.9840 NO 2-SI-3-14 SEC DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 95 of 148 Data Sheet 12 (Page 9 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Power 50.0 PU NO 2-SI-3-14 Hi Limit DEVIATION ALLOWED 6.1[12] 2-LS-3-52B 17% DECR 16.8 to 17.2% 2-SI-3-14 (LB-528B) 6.1[12] 2-LS-3-94B 17% DECR 16.8 to 17.2% 2-SI-3-14 (LB-538B) 6.1[12] 2-LS-3-107B 17% DECR 16.8 to 17.2% 2-SI-3-14 (LB 548B) 6.1[12] Lo-Lo SG 2-LS-3-42B 17% DECR 16.8 to 17.2% 2-SI-3-15 Water Level Trip & TTDs (LB-5I7B)

Channel IV 6.1[12] Tau 6 Lag T 0.0 SEC NO 2-SI-3-15 Hot DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 96 of 148 Data Sheet 12 (Page 10 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] Tau 7 Lag T 0.0 SEC NO 2-SI-3-15 Cold DEVIATION ALLOWED 6.1[12] S1 Streaming 0.0 OF NO 2-SI-3-15 DEVIATION ALLOWED 6.1[12] S2 Streaming 0.0 OF NO 2-SI-3-15 DEVIATION ALLOWED 6.1[12] S3 Streaming 0.0 OF NO 2-SI-3-15 DEVIATION ALLOWED 6.1[12] DELTAH 8.0 OF NO 2-SI-3-15 RSA DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 97 of 148 Data Sheet 12 (Page 11 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] DELTAC 2.5 OF NO 2-SI-3-15 RSA DEVIATION ALLOWED 6.1[12] Delta TO 51.0 OF NO 2-SI-3-15 (Note 5) DEVIATION ALLOWED 6.1[12] TTD Coef. A - 0.0085041 NO 2-SI-3-15 SEC/PU 3 DEVIATION ALLOWED 6.1[12] TTD Coef. B 0.9266400 NO 2-SI-3-15 SEC/PU2 DEVIATION ALLOWED 6.1[12] TTD Coef. C - 33.85998 NO 2-SI-3-15 SEC/PU DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 98 of 148 Data Sheet 12 (Page 12 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Coef. D 474.6060 NO 2-SI-3-15 SEC DEVIATION ALLOWED 6.1[12] TTD Coef. E - 0.0047421 NO 2-SI-3-15 SEC/PU3 DEVIATION ALLOWED 6.1[12] TTD Coef. F 0.5682600 NO 2-SI-3-15 SEC/PU2 DEVIATION ALLOWED 6.1[12] TTD Coef. G - 23.70753 NO 2-SI-3-15 SEC/PU DEVIATION ALLOWED 6.1[12] TTD Coef. H 357.9840 NO 2-SI-3-15 SEC DEVIATION ALLOWED

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 99 of 148 Data Sheet 12 (Page 13 of 13)

Low-Low Steam Generator Water Level Trip and TTD Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[12] TTD Power 50.0 PU NO 2-SI-3-15 Hi Limit DEVIATION ALLOWED 6.1[12] 2-LS-3-55B 17% DECR 16.8 to 17.2% 2-SI-3-15 (LB-527B) 6.1[12] 2-LS-3-97B 17% DECR 16.8 to 17.2% 2-SI-3-15 (LB-537B) 6.1[12] 2-LS-3-110B 17% DECR 16.8 to 17.2% 2-SI-3-15 (LB-547B)

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 100 of 148 Data Sheet 13 (Page 1 of 2)

Reactor Trip on Turbine Trip Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[13] Turbine Stop 2-FCV-1-61 0.8 IN OPEN 0.55 to 1.05 2-SI-47-28 Valve 2-ZS-47-28D CLOSING IN 6.1[13] 2-FCV-1-64 0.8 IN OPEN 0.55 to 1.05 2-SI-47-28 2-ZS-47-30E CLOSING IN 6.1[13] 2-FCV-1-67 0.8 IN OPEN 0.55 to 1.05 2-SI-47-28 2-ZS-47-32 CLOSING IN 6.1[13] 2-FCV-1-70 0.8 IN OPEN 0.55 to 1.05 2-SI-47-28 2-ZS-47-34 CLOSING IN 6.1[13] Low Auto Stop 2-PS-47-73 45 PSIG 43 to 47 2-SI-47-73 Oil Pressure DECR PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 101 of 148 Data Sheet 13 (Page 2 of 2)

Reactor Trip on Turbine Trip Setpoint Verification Date Test Sub- Function/ UNID - Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.1[13] 2-PS-47-74 45 PSIG 43 to 47 2-SI-47-74 DECR PSIG 6.1[13] 2-PS-47-75 45 PSIG 43 to 47 2-SI-47-75 DECR PSIG Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 102 of 148 Data Sheet 14 (Page 1 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances if applicable.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.
4) P-7 Permissive is a logic combination output of either P-1 3 (impulse pressure) or P-1 0 (Power Range) greater than 10% power.

See P-13 and P-10 Data Sheets.

5) Actual turbine runback rate less than the provided Tolerance is also acceptable. See WBN2-47-4002.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TIVA/W Setpoint Action Setpoint NO.

Action 6.1[14] Permissive 2-NI-92-135-D 1.66 x 10.4 4.192 to 4.248 2-SI-92-31 P-6 %RTP VDC (4.22 VDC)

INCR 6.1[14] 2-NI-92-136-E 1.66 x 10.4 4.192 to 4.248 2-SI-92-32

%RTP VDC (4.22 VDC)

INCR

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 103 of 148 Data Sheet 14 (Page 2 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] Permissive 2-NI-92-135-D <150 mV below Max = 2-SI-92-31 P-6 Reset setpoint Setpoint Min = Setpoint

- 150 mV 6.1[14] 2-NI-92-136-E < 150 mV below Max = 2-SI-92-32 setpoint Setpoint Min = Setpoint

- 150 mV 6.1[14] P-7 N/A N/A N/A N/A N/A N/A N/A (Note 4) 6.1[14] P-8 2-INS 48% RTP INCR 47.4 to 48.6 % 2-SI-92-41 1NC/304-D (4.000 VDC) RTP (NC-41 N) (3.95 to 4.05 VDC)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 104 of 148 Data Sheet 14 (Page 3 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-INS 48% RTP INCR 47.4 to 48.6 % 2-SI-92-42 2NC/304-E RTP (N42N) ((3.95 to 4.05 VDC) 6.1[14] 2-INS 48% RTP INCR 47.4 to 48.6 % 2-SI-92-43 3NC/304-F (4.000 VDC) RTP (NC-43N) (3.95 to 4.05 VDC) 6.1[14] 2-INS 48% RTP INCR 47.4 to 48.6 % 2-SI-92-44 4NC/304-G RTP (NC-44N) (4.000 VDC) (3.95 to 4.05 VDC) 6.1[14] P-9 2-INS 50% RTP INCR 49.4 to 50.6 % 2-SI-92-41 1NC/307-D RTP (NC-41S) (4.167VDC) (4.117 to 4.217 VDC)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 105 of 148 Data Sheet 14 (Page 4 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-INS 50% RTP INCR 49.4 to 50.6 % 2-SI-92-42 2NC/307-E RTP (NC-42S) (4.167VDC) (4.117 to 4.217 VDC) 6.1[14] 2-INS 50% RTP INCR 49.4 to 50.6 % 2-SI-92-43 3NC/307-F RTP (NC-43S) (4.167VDC) (4.117 to 4.217 VDC) 6.1[14] 2-INS 50% RTP INCR 49.4 to 50.6 % 2-SI-92-44 4NC/307-G (4.167 VDC) RTP (NC-44S) (4.117 to 4.217 VDC) 6.1[14] P-10 2-INS 10% RTP INCR 9.4 to 10.6 2-SI-92-41 1NC/308-D (0.833 VDC) %RTP (NC-41 M) (0.783 to 0.883 VDC)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 106 of 148 Data Sheet 14 (Page 5 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -IVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-INS 10% RTP INCR 9.4 to 10.6 2-SI-92-42 2NC/308-E %RTP (NC-42M) (0.833 VDC)to 0.883 VDC) 6.1[14] 2-INS 10% RTP INCR 9.4 to 10.6 2-SI-92-43 3NC/308-F (0.833 VOC) %RTP (NC-43M) (0.783 to 0.883 VDC) 6.1[14] 2-INS 10% RTP INCR 9.4 to 10.6 2-SI-92-44 4NC/308-G (0.833 VOC) %RTP (NC-44M) (0.783 to 0.883 VDC) 6.1[14] P-11 2-PS-68-340B 1970 PSIG INCR 1968.4 to 2-SI-68-5 (PB-455B) 1971.6 PSIG UNBLOCK

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 107 of 148 Data Sheet 14 (Page 6 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-PS-68-340B 1962 PSIG 1960.4 to 2-SI-68-5 (PB-455B) DECR 1963.6 PSIG BLOCK 6.1[14] 2-PS-68-334B 1970 PSIG INCR 1968.4 to 2-SI-68-6 (PB-456B) 1971.6 PSIG UNBLOCK 6.1[14] 2-PS-68-334B 1962 PSIG 1960.4 to 2-SI-68-6 (PB-456B) DECR 1963.6 PSIG BLOCK 6.1[14] 2-PS-68-323B 1970 PSIG INCR 1968.4 to 2-SI-68-7 (PB-457B) 1971.6 PSIG UNBLOCK 6.1[14] 2-PS-68-323B 1962 PSIG 1960.4 to 2-SI-68-7 (PB-457B) DECR 1963.6 PSIG BLOCK

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 108 of 148 Data Sheet 14 (Page 7 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] P-12 Lo-Lo 2-TS-68-2J 550.0 OF DEEN 549.77 to 2-SI-68-1 Tavg (TB-412D) DECR 550.23 OF 6.1[14] 2-TS-68-25J 550.0 OF DEEN 549.77 to 2-SI-68-2 (TB-422D) DECR 550.23 OF 6.1[14] 2-TS-68-44J 550.0 OF DEEN 549.77 to 2-SI-68-3 (TB-432D) DECR 550.23 OF 6.1[14] 2-TS-68-67J 550.0 OF DEEN 549.77 to 2-SI-68-4 (TB-442D) DECR 550.23 OF 6.1[14] P-13 Impulse 2-PS-1-73A 10% Turbine 9.78 to 10.22 2-SI-1-73 Press (PB-505A) Power (TP)  % TP INCR 6.1[14] 2-PS-1-72A 10% TP INCR 9.78 to 10.22 2-SI-1-72 (PB-506A) %TP

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 109 of 148 Data Sheet 14 (Page 8 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] P-14 2-LS-3-38A 82.4% INCR 82.2 to 82.6 % 2-SI-3-1 (LB-519A) 6.1[14] 2-LS-3-51A 82.4% INCR 82.2 to 82.6 % 2-SI-3-4 (LB-529A) 6.1[14] 2-LS-3-93A 82.4% INCR 82.2 to 82.6 % 2-SI-3-7 (LB-539A) 6.1[14] 2-LS-3-106A 82.4% INCR 82.2 to 82.6 % 2-SI-3-10 (LB-549A) 6.1[14] 2-LS-3-39A 82.4% INCR 82.2 to 82.6 % 2-SI-3-2 (LB-518A) 6.1114] 2-LS-3-52A 82.4% INCR 82.2 to 82.6 % 2-SI-3-5 (LB-528A)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 110 of 148 Data Sheet 14 (Page 9 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-LS-3-94A 82.4% INCR 82.2 to 82.6 % 2-SI-3-8 (LB-538A) 6.11[14] 2-LS-3-107A 82.4% INCR 82.2 to 82.6 % 2-SI-3-11 (LB-548A) 6.1[14] 2-LS-3-42A 82.4% INCR 82.2 to 82.6 % 2-SI-3-3 (LB-517A) 6.1[14] 2-LS-3-55A 82.4% INCR 82.2 to 82.6 % 2-SI-3-6 (LB-527A) 6.1[14] 2-LS-3-97A 82.4% INCR 82.2 to 82.6 % 2-SI-3-9 (LB-537A) 6.1[14] 2-LS-3-11OA 82.4% INCR 82.2 to 82.6 % 2-SI-3-12 (LB-547A)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 111 of 148 Data Sheet 14 (Page 10 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Action Setpoint NO.

Action 6.1[14] C-1 2-NI-92-135-D 20% RTP INCR 18.75 to 2-SI-92-31 Interlock (9.301 VDC) 21.33% RTP (9.273 to 9.329 VDC) 6.1[14] 2-NI-92-136-E 20% RTP INCR 18.75 to 2-SI-92-32 (9.301 VDC) 21.33% RTP (9.273 to 9.329 VDC) 6.1[14] C-2 2-INS 103% RTP INCR 102.4 to 103.6 2-SI-92-41 1NC/302-D (8.583 VDC)  % RTP (NC-41 L) (8.533 to 8.633 VDC) 6.1[14] 2-INS 103% RTP INCR 102.4 to 103.6 2-SI-92-42 2NC/302-E (8.583 VOC)  % RTP (NC-42L) (8.533 to 8.633 VDC)

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 112 of 148 Data Sheet 14 (Page 11 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-INS 103% RTP INCR 102.4 to 103.6 2-SI-92-43 3NC/302-F (8.583 VDC)  % RTP (NC-43L) (8.533 to 8.633 VDC) 6.1[14] 2-INS 103% RTP INCR 102.4 to 103.6 2-SI-92-44 4NC/302-G (8.583 VDC)  % RTP (NC-44L) (8.533 to 8.633 VDC) 6.1[14] C-3 2-TS-68-2E -1.00 PU -1.84 to -0.16 2-SI-68-1 (TB-411D) DEEN INC PU 6.1[14] 2-TS-68-25E -1.00 PU -1.84 to -0.16 2-SI-68-2 (TB-421D) DEEN INC PU 6.1[14] 2-TS-68-44E -1.00 PU -1.84 to -0.16 2-SI-68-3 (TB-431D) DEEN INC PU

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 113 of 148 Data Sheet 14 (Page 12 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -IVA/W Setpoint Action Setpoint Action NO.

6.1[14] 2-TS-68-67E -1.00 PU -1.84 to -0.16 2-SI-68-4 (TB-441D) DEEN INC PU 6.1 [14] C-4 2-TS-68-2F -1.00 PU -1.54 to -0.46 2-SI-68-1 (TB-411H) DEEN INC PU 6.1[14] 2-TS-68-25F -1.00 PU -1.54 to -0.46 2-SI-68-2 (TB-421H) DEEN INC PU 6.1[14] 2-TS-68-44F -1.00 PU -1.54 to -0.46 2-SI-68-3 (TB-431H) DEEN INC PU 6.1[14] 2-TS-68-67F -1.00 PU -1.54 to -0.46' 2-SI-68-4 (TB-441 H) DEEN INC PU 6.1 [14] Turbine 2-RLY 1.5 SEC 1.35 to 1.65 2-PTI-99-05 Runback STDX SEC Time Delay ON

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 114 of 148 Data Sheet 14 (Page 13 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1 [14] Turbine 2-RLY 28.5 SEC 25.7 to 31.4 2-PTI-99-05 Runback STDX SEC Time Delay OFF 6.1[14] Turbine Load N/A 200% / MIN 195-205 2-ATI-047A-02 Reference  %/MIN Reduction (Note 5)

Rate 6.1[14] C-5 2-PS-1-73E 15% Turbine 14.78 to 15.22 2-SI-1-73 (PB-505C) Power (TP)  % TP DEEN DECR 6.1[14] C-7 2-PS-1-72E 10% TP INCR 9.78 to WO 113725926 (PB-506C) 10.22% TP (CTN 2-001-122 96-1 U1-000) 6.1[14] LAGTIM 2.00 Min NO WO 113725926 DEVIATION (CTN 2-001-122 ALLOWED 96-1 U1-000)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 115 of 148 Data Sheet 14 (Page 14 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.1[14] LGAIN 1.0 NO WO 113725926 DEVIATION (CTN 2-001-122 ALLOWED 96-1 U1-000) 6.1[14] LLOPT 2 NO 47A630-98-205 DEVIATION ALLOWED 6.1 [14] HSCI 1 110% NO 47A630-98-205 DEVIATION ALLOWED 6.1[14] LSCI1 0% NO 47A630-98-205 DEVIATION ALLOWED 6.1[14] C-9 2-PS-2-1B 13.454 mA DC 13.428 to SSD-2-LPP-2-1 (6.5 IN Hg Abs) 13.480 mA DC CL DECR

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 116 of 148 Data Sheet 14 (Page 15 of 15)

Reactor Trip System Permissive and Interlock Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "IVA/W Setpoint Action Setpoint NO.

Action 6.1[14] 2-PS-2-7D 13.454 mA DC 13.428 to SSD-2-LPP-2-7 (6.5 IN Hg Abs) 13.480 mA DC CL DECR Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 117 of 148 Data Sheet 15 (Page 1 of 1)

Low Pressurizer Pressure Safety Injection Setpoint Verification Date NOTES

1) Actual setpoint MUST be with the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Setpoint NO.

Action Action 6.2[1] Low 2-PS-68-340D 1870 PSIG 1868.4 to 2-SI-68-5 Pressurizer DECR 1871.6 Pressure (PB-455D) PSIG 6.2[1] 2-PS-68-334D 1870 PSIG 1868.4 to 2-SI-68-6 (PB-456D) DECR 1871.6 PSIG 6.2[1] 2-PS-68-323D 1870 PSIG 1868.4 to 2-SI-68-7 (PB-457D) DECR 1871.6 PSIG Recorded By:

Verified By: /

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 118 of 148 Data Sheet 16 (Page 1 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Set Points recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline 2-PS-1-2A 675 PSIG 672.4 to 2-SI-1-1 Pressure DECR 677.6 (PB-514A) PSIG 6.2[2] 2-PS-1-2B 675 PSIG 672.4 to 2-SI-1-2 (PB-5I15A) DECR 677.6 PSIG 6.2[2] 2-PS-1-5A 675 PSIG 672.4 to 2-S1-1-3 DECR 677.6 (PB-516A) PSIG 6.2[2] Low Pressure 2-PS-1-5D 750 PSIG 747.4 to 2-SI-1-3 Alarm DECR 752.6 (PB-516B) PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 119 of 148 Data Sheet 16 (Page 2 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline 2-PS-1 -9A 675 PSIG 672.4 to 2-SI-1-4 Pressure (PB-524A) DECR 677.6 PSIG 6.2[2] 2-PS-1-9B 675 PSIG 672.4 to 2-SI-1-5 DECR 677.6 (PB-525A) PSIG 6.2[2] 2-PS-1-12A 675 PSIG 672.4 to 2-SI-1-6 DECR 677.6 (PB-526A) PSIG 6.2[2] Low Pressure 2-PS-1-12D 750 PSIG 747.4 to 2-SI-1-6 Alarm (PB-526B) DECR 752.6 PSIG 6.2[2] Low Steamline 2-PS-1-20A 675 PSIG 672.4 to 2-SI-1-7 Pressure (PB-534A) DECR 677.6 PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 120 of 148 Data Sheet 16 (Page 3 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description IVA[W Setpoint Setpoint NO.

Action Action 6.2[2] 2-PS-1-20B 675 PSIG 672.4 to 2-SI-1-8 (PB-535A) DECR 677.6 PSIG 6.2[2] 2-PS-1-23A 675 PSIG 672.4 to 2-S1-1-9 (PB-536A) DECR 677.6 PSIG 6.2[2] Low Pressure 2-PS-1 -23D 750 PSIG 747.4 to 2-SI-1-9 Alarm (PB-536B) DECR 752.6 PSIG 6.2[2] Low Steamline 2-PS-1-27A 675 PSIG 672.4 to 2-SI-1-10 Pressure DECR 677.6 (PB-544A) PSIG 6.2[2] 2-PS-1 -27B 675 PSIG 672.4 to 2-SI-1-11 DECR 677.6 (PB-545A) PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 121 of 148 Data Sheet 16 (Page 4 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[2] 2-PS-1-30A 675 PSIG 672.4 to 2-SI-1-12 (PB-546A) DECR 677.6 PSIG 6.2[2] Low Pressure 2-PS-1-30D 750 PSIG 747.4 to 2-SI-1-12 Alarm (PB-546B) DECR 752.6 PSIG 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-1 Pressure 50.5 SEC Lead/Lag Coefficients (P-514) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-1 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-2 Pressure 50.5 SEC Lead/Lag Coefficients (P-515)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 122 of 148 Data Sheet 16 (Page 5 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Setpoint NO.

Action Action 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-2 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-3 Pressure 50.5 SEC Lead/Lag Coefficients (P-516) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-3 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-4 Pressure 50.5 SEC Lead/Lag Coefficients (P-524) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-4 5.05 SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 123 of 148 Data Sheet 16 (Page 6 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-5 Pressure 50.5 SEC Lead/Lag Coefficients (P-525) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-5 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-6 Pressure 50.5 SEC Lead/Lag Coefficients (P-526) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-6 5.05 SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 124 of 148 Data Sheet 16 (Page 7 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description VA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-7 Pressure 50.5 SEC Lead/Lag Coefficients (P-534) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-7 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-8 Pressure 50.5 SEC Lead/Lag Coefficients (P-535) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-8 5.05 SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 125 of 148 Data Sheet 16 (Page 8 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-9 Pressure 50.5 SEC Lead/Lag Coefficients (P-536) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-9 5.05 SEC 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-10 Pressure 50.5 SEC Lead/Lag Coefficients (P-544) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-10 5.05 SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 126 of 148 Data Sheet 16 (Page 9 of 9)

Low Steamline Pressure Safety Injection and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -VA/W Setpoint Setpoint NO.

Action Action 6.2[2] Low Steamline Tau 1 Lead 50 SEC 49.5 to 2-SI-1-11 Pressure 50.5 SEC Lead/Lag Coefficients (P-545) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-11 5.05 SEC 6.2[2] Low Steamline Tau I Lead 50 SEC 49.5 to 2-SI-1-12 Pressure 50.5 SEC Lead/Lag Coefficients (P-546) 6.2[2] Tau 2 Lag 5 SEC 4.95 to 2-SI-1-12 5.05 SEC Recorded By:

Verified By:

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 127 of 148 Data Sheet 17 (Page 1 of 1)

Containment High Pressure Safety Injection Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[3] Containment 2-PDS-30-42B 1.5 PSIG 1.466 to 2-SI-30-42 High Pressure (PB-934B) INCR 1.534 PSIG 6.2[3] 2-PDS-30-43B 1.5 PSIG 1.466 to 2-SI-30-43 (PB-935B) INCR 1.534 PSIG 6.2[3] 2-PDS-30-44B 1.5 PSIG 1.466 to 2-SI-30-44 (PB-936B) INCR 1.534 PSIG Recorded By:

Verified By: I

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 128 of 148 Data Sheet 18 (Page 1 of 2)

Safety Injection Manual Reset Time Delay Setpoint Verification Date NOTES

1) Actual setpoint MUST be with the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[4] Time Delay TD-1 90 SEC 76.5 to 2-SI-99-10-A Block on SI 103.5 SEC Manual Reset Train A - ON 6.2[4] OFF TD-1 5 SEC 4.25 to 2-SI-99-10-A 5.75 SEC 6.2[4] Time Delay TD-1 90 SEC 76.5 to 2-SI-99-10-B Block on SI 103.5 SEC Manual Reset Train B - ON 6.214] OFF TD-1 5 SEC 4.25 to 2-SI-99-10-B 5.75 SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 129 of 148 Data Sheet 18 (Page 2 of 2)

Safety Injection Manual Reset Time Delay Setpoint Verification Date Recorded By: /

Verified By: /

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 130 of 148 Data Sheet 19 (Page 1 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[5] High Negative 2-PS-1-2D 100 97.4 to 2-SI-1-1 Rate Steamline PSIG/SEC 102.6 Pressure (PB-514C) INCR PSIG/SEC 6.2[5] 2-PS-1-2E 100 97.4 to 2-SI-1-2 (PB-515C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-5B 100 97.4 to 2-SI-1-3 (PB-516C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1 -9D 100 97.4 to 2-SI-1-4 (PB-524C) PSIG/SEC INCR 102.6 PSIG/SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 131 of 148 Data Sheet 19 (Page 2 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description -VA/W Setpoint Setpoint NO.

Action Action 6.2[5] 2-PS-1-9E 100 97.4 to 2-SI-1-5 (PB-525C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-12B 100 97.4 to 2-SI-1-6 PSIG/SEC 102.6 (PB-526C) INCR PSIG/SEC 6.2[5] 2-PS-1-20D 100 97.4 to 2-SI-1-7 (PB-534C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-20E 100 97.4 to 2-SI-1-8 (PB-535C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-23B 100 97.4 to 2-SI-1-9 (PB-536C) PSIG/SEC INCR 102.6 PSIG/SEC

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 132 of 148 Data Sheet 19 (Page 3 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[5] 2-PS-1-27D 100 97.4 to 2-SI-1-10 (PB-544C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-27E 100 97.4 to 2-SI-1-11 (PB-545C) PSIG/SEC INCR 102.6 PSIG/SEC 6.2[5] 2-PS-1-30B 100 97.4 to 2-SI-1-12 (PB-546C) PSIG/SEC 102.6 INCR PSIG/SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-1 Coefficients 50.5 SEC (P-514) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-1 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-2 Coefficients 50.5 SEC (P-515)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 133 of 148 Data Sheet 19 (Page 4 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description IVA/W Setpoint Setpoint NO.

Action Action 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-2 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-3 Coefficients 50.5 SEC (P-516) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-3 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-4 Coefficients 50.5 SEC (P-524) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-4 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-5 Coefficients 50.5 SEC (P-525)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 134 of 148 Data Sheet 19 (Page 5 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-5 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-6 Coefficients 50.5 SEC (P-526) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-6 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-7 Coefficients 50.5 SEC (P-534) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-7 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-8 Coefficients 50.5 SEC (P-535)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 135 of 148 Data Sheet 19 (Page 6 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-8 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-9 Coefficients 50.5 SEC (P-536) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-9 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-10 Coefficients 50.5 SEC (P-544) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-10 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-11 Coefficients 50.5 SEC (P-545)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 136 of 148 Data Sheet 19 (Page 7 of 7)

High Negative Steamline Pressure Rate Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description "VA/W Setpoint Setpoint NO.

Action Action 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-11 50.5 SEC 6.2[5] Rate/Lag Tau 3 Rate 50 SEC 49.5 to 2-SI-1-12 Coefficients 50.5 SEC (P-546) 6.2[5] Tau 4 Lag 50 SEC 49.5 to 2-SI-1-12 50.5 SEC Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 137 of 148 Data Sheet 20 (Page 1 of 2)

High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[6] High-High 2-PDS-30-42A 2.8 PSIG 2.766 to 2-SI-30-42 Containment (PB 934A) INCR 2.834 Pressure PSIG 6.2[6] 2-PDS-30-43A 2.8 PSIG 2.766 to 2-SI-30-43 (PB 935A) INCR 2.834 PSIG 6.2[6] 2-PDS-30-44A 2.8 PSIG 2.766 to 2-SI-30-44 (PB 936A) INCR 2.834 PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 138 of 148 Data Sheet 20 (Page 2 of 2)

High-High Containment Pressure Containment Isolation Phase B, Containment Spray, and Steamline Isolation Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Setpoint NO.

Action Action 6.2[6] 2-PDS-30-45A 2.8 PSIG 2.766 to 2-SI-30-45 (PB 937A) INCR 2.834 PSIG Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 139 of 148 Data Sheet 21 (Page 1 of 9)

Miscellaneous ESFAS Setpoint Verification Date NOTES

1) Actual setpoint MUST be within the required setpoint tolerances.
2) Required Setpoint Action and Actual Setpoint Action only applies to trip outputs.
3) Actual Setpoints recorded for Eagle outputs are actual minimum and maximum values.
4) Parameter is MFPT Governor Valve Positioner Oil Pressure.

Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] North MSV 2-LS-3-405 4" Above Floor 3.75 to 4.25 IN 2-SI-3-405 Vault Room INCR Water Level High 6.2[7] 2-LS-3-406 4" Above Floor 3.75 to 4.25 IN 2-SI-3-406 INCR 6.2[7] 2-LS-3-407 4" Above Floor 3.75 to 4.25 IN 2-SI-3-407 INCR

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 140 of 148 Data Sheet 21 (Page 2 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] South MSV 2-LS-3-402 4" Above Floor 3.75 to 4.25 IN 2-SI-3-402 Vault Room INCR Water Level High 6.2[7] 2-LS-3-403 4" Above Floor 3.75 to 4.25 IN 2-SI-3-403 INCR 6.2[7] 2-LS-3-404 4" Above Floor 3.75 to 4.25 IN 2-SI-3-404 INCR 6.2[7] RWST Level 2-LS-63-50A 158.0 INWC 157.128 to 2-SI-63-50 Auto Recirc & (LB-913A) (34.6%) DECR 158.676 Alarm INWC 34.4 to 34.8%

6.2[7] 2-LS-63-51A 158.0 INWC 157.128 to 2-SI-63-51 (LB-g14A) (34.6%) DECR 158.676 INWC 34.4 to 34.8%

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Paqe 141 of 148 Data Sheet 21 (Page 3 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] 2-LS-63-52A 158.0 INWC 157.128 to 2-SI-63-52 (LB-915A) (34.6%) DECR 158.676 INWC 34.4 to 34.8%

6.2[7] 2-LS-63-53A 158.0 INWC 157.128 to 2-SI-63-53 (LB-916A) (34.6%) DECR 158.676 INWC 34.4 to 34.8%

6.2[7] RWST Level 2-LS-63-50B 52.4 IN 7.34% 51.632 to 2-SI-63-50 RWST Alarm Lo-Lo 56C2DAlarm 2- (LB-913B) 5.17 DC mAdc 53.180 NW XA-55-6C-126D DECR INWC 7.14 to 7.54 %

5.142 mAdc to 5.206 mAdc

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 142 of 148 Data Sheet 21 (Page 4 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] 2-LS-63-51 B 52.4 IN 7.34% 51.632 to 2-SI-63-51 (LB-914B) 5.17 mAdc 53.180 DECR INWC 7.14 to 7.54 %

5.142 mAdc to 5.206 mAdc 6.2[7] 2-LS-63-52B 52.4 IN 7.34% 51.632 to 2-SI-63-52 5.17 mAdc 53.180 (LB-915B) DECR INWC 7.14 to 7.54 %

5.142 mAdc to 5.206 mAdc 6.2[7] 2-LS-63-53B 52.4 IN 7.34% 51.632 to 2-SI-63-53 (LB-916B) 5.17 mAdc DECR 53.180 INWC 7.14 to 7.54 %

5.142 mAdc to 5.206 mAdc

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 143 of 148 Data Sheet 21 (Page 5 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] Containment 2-LS-63-180 38.2 IN 16.1% 37.8 to 38.6 IN 2-SI-63-1 Sump Level (LB-920A) INCR 15.9 to 16.3%

High - RWST Swapover 6.2[7] 2-LS-63-181 38.2 IN 16.1% 37.8 to 38.6 IN 2-SI-63-2 (LB-921A) INCR 15.9 to 16.3%

6.2[7] 2-LS-63-182 38.2 IN 16.1% 37.8 to 38.6 IN 2-SI-63-3 (LB-940A) INCR 15.9 to 16.3%

6.2[7] 2-LS-63-183 38.2 IN 16.1% 37.8 to 38.6 IN 2-SI-63-4 (LB-941A) INCR 15.9 to 16.3%

6.2[7] Auxiliary 2-PS-46-13 47.7 PSIG 51.7 to 43.7 2-SI-3-25 Feedwater Closes on PSIG Pump DECR Actuation (Note 4)

REACTOR PROTECTION SETPOINT 2-PTI-099-06 VERIFICATION Rev. 0000 Page 144 of 148 Data Sheet 21 (Page 6 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] MFWP 2-PS-46-13 47.7 PSIG 51.7 to 43.7 2-SI-3-25 Turbine Trip Opens on PSIG DECR (Note 4) 6.2[7] Auxiliary 2-PS-046-40 47.7 PSIG 51.7 to 43.7 2-SI-3-26 Feedwater Closes on PSIG Pump DECR Actuation (Note 4) 6.2[7] MFWP 2-PS-046-40 47.7 PSIG 51.7 to 43.7 2-SI-3-26 Turbine Trip Opens on PSIG DECR (Note 4) 6.2[7] Auxiliary 2-PS-3-139A 3.42 PSIG CL 3.33 to 3.51 2-SI-3-21 Feedwater DECR PSIG Pump Suction Transfer Train A 6.2[7] 2-PS-3-139B 3.42 PSIG CL 3.33 to 3.51 2-SI-3-21 DECR PSIG

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 145 of 148 Data Sheet 21 (Page 7 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] 2-PS-3-139D 3.42 PSIG CL 3.33 to 3.51 2-SI-3-21 DECR PSIG 6.2[7] Auxiliary 2-PS-3-144A 4.16 PSIG CL 4.07 to 4.25- 2-SI-3-22 Feedwater DECR PSIG Pump Suction Transfer Train B 6.2[7] 2-PS-3-144B 4.95 PSIG CL 4.86 to 5.04 2-SI-3-22 DECR PSIG 6.2[7] 2-PS-3-144D 4.95 PSIG CL 4.86 to 5.04 2-SI-3-22 DECR PSIG 6.2[7] Turbine Trip / 2-LS-3-38A 82.4% INCR 82.2 to 82.6 % 2-SI-3-1 Feedwater (LB-519A)

Isolation-Steam Gen Water Level High 6.2[7] 2-LS-3-39A 82.4% INCR 82.2 to 82.6 % 2-SI-3-2 (LB-518A)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 146 of 148 Data Sheet 21 (Page 8 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] 2-LS-3-42A 82.4% INCR 82.2 to 82.6% 2-SI-3-3 (LB-517A) 6.2[7] 2-LS-3-51A 82.4% INCR 82.2 to 82.6 % 2-SI-3-4 (LB-529A) 6.2[7] 2-LS-3-52A 82.4% INCR 82.2 to 82.6 % 2-SI-3-5 (LB-528A) 6.2[7] 2-LS-3-55A 82.4% INCR 82.2 to 82.6% 2-SI-3-6 (LB-527A) 6.2[7] 2-PS-3-93A 82.4% INCR 82.2 to 82.6% 2-SI-3-7 (LB-539A) 6.2[7] 2-LS-3-94A 82.4% INCR 82.2 to 82.6 % 2-SI-3-8 (LB-538A) 6.2[7] 2-LS-3-97A 82.4% INCR 82.2 to 82.6 % 2-SI-3-9 (LB-537A)

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 147 of 148 Data Sheet 21 (Page 9 of 9)

Miscellaneous ESFAS Setpoint Verification Date Test Sub- Function/ UNID Required Tolerance Actual Instruction Work PKG Initial/Date Section Description TVA/W Setpoint Action Setpoint NO.

Action 6.2[7] 2-LS-3-106A 82.4% INCR 82.2 to 82.6% 2-SI-3-10 (LB-549A) 6.2[7] 2-LS-3-107A 82.4% INCR 82.2 to 82.6 % 2-SI-3-11 (LB-548A) 6.2[7] 2-LS-3-1 10A 82.4% INCR 82.2 to 82.6 % 2-SI-3-12 (LB-547A)

Recorded By:

Verified By:

WBN REACTOR PROTECTION SETPOINT 2-PTI-099-06 Unit 2 VERIFICATION Rev. 0000 Page 148 of 148 Table 2 (Page 1 of 1)

Attachment Index Attachment No. Attachment Description No.of Pages

_____ .1 1 ____

4 4 4 4