ML111680272

2010 Palisades Nuclear Plant Initial Examination Outline Submittal

ML111680272
Person / Time
Site:	Palisades  (DPR-020)
Issue date:	08/16/2010
From:	Entergy Nuclear Operations
To:	NRC/RGN-III
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ML102070536	List: ML111460118 ML111680272
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Download: ML111680272 (8)

Text

2010 PALISADES NUCLEAR PLANT INITIAL EXAMINATION OUTLINE SUBMITTAL

Form ES-D-1 Appendix D Scenario Outline Facility: Palisades Scenario No.: QNJ Op-Test No.: 1 Examiners:

Opera tors:

Initial Conditions: 87% power with P-66B, HPSI Pump, tagged out.

Turnover:

P-666 HPSI Pump is tagged out for a coupling alignment and will be restored to operable in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. Shift orders are to maintain current power level.

Event Walf.

Event Event Description No.

No.

Type*

SRO (C, T)

BOP (C) t SRO (C)

RO (R)

BOP (C)

I 5

I SGOlA I ALL(M)

I 6

I ED13B I RO(C)

Cooling Tower Pump P-39A trips (ONP-14) and rapid downpower (ONP-26)

Main Generator Voltage Regulator failure with concurrent change in grid voltage Cold Leg #1 RTD fails high

'A' S/G tube leak that rises to require a reactor trip. (1 0.4 gpm requires reactor trip)

SGTR on 'A' S/G Failure of Right Train SlAS to automatically actuate Page 1 of 1

Appendix D Scenario Outline Form ES-D-1 Op-Test No.: 1 Facility: Palisades Scenario No.: TWO-A Examiners:

Operators:

Initial Conditions: 100% power. P-8C, Auxiliary Feedwater Pump, is out of service.

Turnover:

Shift orders are to alternate running Service Water pumps and then reduce power in to approximately 87% at 4% per hour to perform Turbine valve testing on the next shift.

Event No.

1 2

3 Maw.

Event Type*

Event No.

Description SWO4A RO (N)

Alternate Running Service Water Pumps SRO (N)

N/A RO (R)

Power de-escalation BOP (N)

SRO (I)

PZR Level Control Channel downscale demand Rxo8B I RO(I) I SRO (C, T)

BOP (C) 5 OVRD Dilution Water Pump P-40A trip/breaker failed I

6 I MS03B I ALL(M)

I ESDE Insidecontainment ED0 1 SRO (C)

ED14A RO (C) 7 8

RD16 RO (C)

Two stuck Control Rods Loss of Offsite Power with failure of D/G 1-1 to start I * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)ech Spec Page 1 of 1

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: TWO-B Op-Test No.: 1 I

Examiners:

Operators:

Initial Conditions: 100% power. P-8C, Auxiliary Feedwater Pump, is out of service.

Turnover:

Shift orders are to alternate running Service Water pumps and then reduce power in to approximately 87% at 4% per hour to perform Turbine valve testing on the next shift.

I Power de-escalation I

6 I MS03B I ALL(M) I ESDE InsideContainment ED0 1 SRO (C) 7 Loss of Offsite Power with failure of D/G 1-1 to start ED14A RO (C)

Page 1 of 1

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: THREE-A Op-Test No.: 1 Examiners:

Operators:

I Initial Conditions: 25% power.

Turnover:

The Plant is at approximately 25% power MOL following a startup from a forced outage.

The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications. GCL-5.1, Power Escalation in MODE 1, has been completed through Step 2.13a. Shift orders are to then commence a power escalation to 4

5 6

7 8

full power at 6% per hour.

Malf. No. 1 Event Type*

SRO (N)

NIA SRO (C, T)

RP1lA I

BOP(C)

NIA I SRO (T)

I RC04 I ALL(M)

TC02 BOP (I)

CH05A 1 RO(I)

CH05B Event DescriDtion Power escalation Power Range Detector NI-5 fails low Channel B Pressurizer Pressure Controller failure T-1OA Diesel Fuel Oil Inventory Low PCP P-50A High Vibration (requires pump trip)

LOCA Failure of Turbine to auto trip CHP Channels Auto Initiate Failure

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)ech Spec Page 1 of 1

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: THREE-B Op-Test No.: 1 I

Examiners:

Operators:

I I Initial Conditions: 25% power.

I Turnover:

The Plant is at approximately 25% power MOL following a startup from a forced outage.

The Turbine Drain Valves are closed per SOP-8. A Chemistry hold has just been lifted with S/G chemistry within specifications. GCL-5.1, Power Escalation in MODE 1, has been completed through Step 2.13a. Shift orders are to then commence a power escalation to full power at 6% per hour.

5 1

RC16 I 6 I RCO4 CH05A CH05B Event Type*

SRO (N)

RO (R)

SRO (C, T)

BOP (C)

SRO (I)

RO (1)

SRO (T)

ALL (M)

Event Description Power escalation Power Range Detector NI-5 fails low Channel 'B' Pressurizer Pressure Controller failure T-1OA Diesel Fuel Oil Inventory Low PCP P-50A High Vibration (requires pump trip)

LOCA CHP Channels Auto Initiate Failure I

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor (T)ech Spec Page 1 of 1

Appendix D Scenario Outline Form ES-D-1 Facility: Palisades Scenario No.: SPARE Op-Test No.: 1 Examiners:

Operators:

Initial Conditions:

100% power. P-8A, Auxiliary Feedwater Pump is out of service for pump seal replacement.

Turnover:

Shift orders to rotate Instrument Air Compressors and then lower power at 4% per hour to 87% to perform Turbine Valve Testing.

Event Event No.

Malf. No.

Event Type*

Description 1

I N/A I

RO (N)

I Rotate Instrument Air Compressors 2

1 N/A 1

SRo(N)

RO (R)

Power de-escalation 3

CHO6B SRo (I, Loss of 'B' Control Room HVAC Train BOP (I)

SRO (I, T)

RO (I) 4 ED08B Loss of Preferred AC Bus Y-20 I

I BOP (I)

SRO (C, T)

I RC03 I RO(C) 6 FWOBB BOP (C)

MSO6B I MS15B I ALL(M) 7 PCS Leak Failure of Steam Driven AFW Pump P-8B to Auto Start Main Steam Relief RV-0711 partially open (initiates at time of trip)

Failure of P-66B, HPSl Pump, to Auto start Page 1 of 1

Proposed Monitored Parameters List for Palisades 201 0 NRC Operatinn Exam I

1. Core output by heat balance

2. Nuclear Instrument power channels 5/6

4. Nuclear Instrument power source range 113 5, PCS boron concentration

6. PCS Loop 1 Tave

7. PCS Loop 2 Tave

8. Cold Leg Loop 1A temperature

9. Cold Leg Loop 1B temperature

10. Cold Leg Loop 2A temperature

11. Cold Leg Loop 28 temperature

12. HPSl flow Loop 1A

13. HPSl flow Loop 1 B

14. HPSl flow Loop 2A

15. HPSl flow Loop 2B

16. PCP P-50A amps

17. PCP P-5OB amps

18. PCP P-50C amps

19. PCP P-50D amps

20. PZR pressure actual

21. PZR pressure indicated C-02

22. PZR level Channel A

23. PZR level wide range

24. PCS letdown flow

25. Charging line flow

26. Containment wide range pressure

27. Containment dome temperature

28. Containment sump water level 29, Containment floor water level

30. Hot Leg Loop 1 temperature

31. Hot Leg Loop 2 temperature

32. Feed flow to A S/G

33. Feed flow to B SIG

34. Steam flow from A SIG

35. Steam flow from B S/G

36. A S/G level wide range

37. A S/G level narrow range

38. B S/G level wide range

39. B S/G level narrow range

40. A SIG pressure

41. B SIG pressure

42. AFW flow to S/G A from P-8A/B

43. AFW flow to S/G A from P-8C

44. AFW flow to S/G B from P-8AIB

45. AFW flow to S/G B from P-8C

46. Main Generator terminal voltage

47. Generator gross output mw

48. Condenser vacuum

49. Control Room pressure

50. Critical SW pressure

@ 3. Nuclear Instrument power wide range 1/3 e

1)

51. CCW pressure

52. D/G 1-1 Output kW

53. D/G 1-2 Output kW