ML21286A222

Amendment 29 to Updated Final Safety Analysis Report, Appendix G - BWR Operating States

ML21286A222
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Download: ML21286A222 (3)

Text

MATRIX 1 BWR OPERATING STATES STATES CONDITIONS A B C D E F Reactor vessel head off X X Reactor vessel head on X X X X Shutdown X X X Not shutdown X X X Pressure <825 psig(2) X(1) X(1) X X Pressure >825 psig X X Definition Shutdown: keff sufficiently less than 1.0 that the full withdrawal of any one control rod could not produce criticality under the most restrictive potential conditions of temperature, pressure, core age, and fission product concentrations.

NOTES:

(1) Because the reactor vessel head is off in States A and B, pressure is atmospheric pressure.

(2) At less than 825 psig, the main steam line isolation valves are interlocked closed when the mode switch is in RUN.

MATRIX 2 Sheet 1 TYPES OF OPERATIONS AND EVENTS APPLICABLE IN EACH BWR OPERATING STATE TYPES OF OPERATION BWR OPERATING STATE AND EVENTS A B C D E F PLANNED OPERATION

1. Refueling Outage X X

2. Achieving Criticality X X X X X X

3. Heatup X X

4. Power Operation X

5. Achieving Shutdown X X X

6. Cooldown X X X

7. (Open)

8. (Open)

9. (Open)

10. (Open)

11. (Open)

ABNORMAL OPERATIONAL TRANSIENTS Nuclear System Pressure Increase

12. Generator trip X X

13. Turbine trip (with bypass) X X

14. Isolation of all main steam lines X X X X

15. Isolation of one main steam line X X X X 16 Loss of vacuum (turbine trip without bypass) X X X X Moderator Temperature Decrease

17. (Open)

18. Loss of feedwater heating X

19. Shutdown cooling (RHRS) malfunction (temperature decrease) X X X X

20. Inadvertent Pump Start (temperature decrease) X X X X X X Reactivity Insertion

21. Control rod withdrawal error X X X X X X

22. Fuel assembly insertion X

23. Control rod removal X

24. (Open)

Loss of Coolant Inventory

25. Pressure regulator failure X X X X

26. Inadvertent opening of a relief or safety valve X X X X X X

MATRIX 2 (Continued) Sheet 2 TYPES OF OPERATION BWR OPERATING STATE AND EVENTS A B C D E F

27. Loss of feedwater flow X X X X

28. Total loss of off-site power X X X X X X Core Coolant Flow Decrease

29. Recirculation flow control failure decreasing flow X X X X

30. Trip of one recirculation pump X X X X

31. Trip of two recirculation pumps X X X X

32. Recirculation pump seizure X X X X Core Coolant Flow Increase

33. Recirculation flow control failure increasing flow X X X X

34. Startup of idle recirculation pump X X X X X X Core Coolant Temperature Increase

35. Loss of shutdown cooling X X X X Excess of Coolant Inventory

36. Feedwater Controller failure-maximum demand X X X X ACCIDENTS

37. (Open)

38. Control rod drop accident X X X X

39. Pipe breaks inside primary containment X X X X

40. Fuel-handling accident X X X X X X

41. Pipe breaks outside primary containment X X X X

42. (Open)

43. (Open)

SPECIAL EVENT

44. Loss of habitability of the control room X X X X X X SPECIAL EVENT

45. Ability to shut down reactor without control rods X X X

46. (Open)

47. (Open)