ML063340006

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SNC Farley Meeting Slides
ML063340006
Person / Time
Site: Farley  
Issue date: 11/29/2006
From:
Division of Nuclear Materials Safety II
To:
Southern Nuclear Operating Co
References
Download: ML063340006 (72)


Text

11 SNC Farley Units 1 & 2 SNC Farley Units 1 & 2 Status Status November 29, 2006 November 29, 2006 NRC Region II Status Meeting NRC Region II Status Meeting

22 Agenda Agenda 3/4 3/4 Introduction Introduction 3/4 3/4 Farley Project Overview Farley Project Overview -- Lewis Sumner Lewis Sumner 3/4 3/4 Farley Site Status Farley Site Status -- Randy Johnson Randy Johnson 3/4 3/4 Licensing Status Licensing Status -- Doug McKinney Doug McKinney 3/4 3/4 Problem Identification and Resolution Problem Identification and Resolution --

Paul Hayes Paul Hayes 3/4 3/4 Major Focus Areas Major Focus Areas-- Sonny Sonny Bargeron Bargeron 3/4 3/4 Open Discussion Open Discussion -- ALL ALL

33 Farley Project Overview Farley Project Overview Lewis Sumner Lewis Sumner

44 FNP Unit 1 FNP Unit 1 Average Daily Power Level Average Daily Power Level November 17, 2004 November 17, 2004 -- October 31, 2006 October 31, 2006 0

100 200 300 400 500 600 700 800 900 Nov-04 Dec-04 Jan-05 Feb-05 Mar-05 Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Equip HU

55 FNP Unit 2 FNP Unit 2 Average Daily Power Level Average Daily Power Level April 14, 2004 April 14, 2004 -- October 31, 2006 October 31, 2006 0

100 200 300 400 500 600 700 800 900 Apr-04 May-04 Jun-04 Jul-04 Aug-04 Sep-04 Oct-04 Nov-04 Dec-04 Jan-05 Feb-05 Mar-05 Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Equipment HU

66 INPO Index INPO Index INPO Performance Indicator Index 65 70 75 80 85 90 95 100 Apr05 M ay05 Jun05 Jul05 Aug05 Sep05 Oct05 Nov05 Dec05 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 Monthly Index Values Percent Unit 1 - Index Value Unit 2 - Index Value Plant - Index Value Year End Target

77 Forced Loss Rate 0.0 1.0 2.0 3.0 4.0 5.0 6.0 7.0 8.0 9.0 10.0 11.0 12.0 Apr05 M ay05 Jun05 Jul05 Aug05 Sep05 Oct05 Nov05 Dec05 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 Cycle Based Averages (18 or 24 Months)

Percent INPO 100% Performance Level Unit 1 - Monthly Cycle Avg Unit 2 - Monthly Cycle Avg Year End Goal Level Action Level

88 Industrial Safety Accident Rate - Plant Value 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 Apr05 M ay05 Jun05 Jul05 Aug05 Sep05 Oct05 Nov05 Dec05 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 Cycle Based Averages (18 or 24 Months)

Industrial Safety Accident Rate per 200,000 Hours Worked INPO 100% Performance Level Industrial Safety Accident Rate (Cycle Based)

Action Level

99 NRC PI - Safety System Functional Failures Green 5 0

1 2

3 4

5 6

7 8

Safety System Functional Failures Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 12 Month Rolling Sum White > 5 Green 5 Unit 1 Data Unit 2 Data Action Level Note: Yellow/Red No Threshold

10 10 NRC PI - Mitigating System Performance Index, Cooling Water System Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 1.0E-07 1.0E-06 1.0E-05 1.0E-04 1.0E-03 Mitigating System Performance Index (MSPI) Value Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Rolling 36 Month Values Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 Unit 1 Data Unit 2 Data Action Level

11 11 NRC PI - Reactor Coolant System Specific Activity White > 50%

Green 50%

0%

10%

20%

30%

40%

50%

60%

70%

80%

90%

100%

% of Technical Specifications Limits Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Monthly Maximum Yellow >100%

White > 50%

Green 50%

Unit 1 Data Unit 2 Data Action Level Note: Red No Threshold

12 12 NRC PI - Emergency Response Organization Drill/Exercise Performance Green 90%

White <90%

Yellow <70%

50%

55%

60%

65%

70%

75%

80%

85%

90%

95%

100%

Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 24 Month Rolling Values

% Of Opportunities Green 90%

White <90%

Yellow <70%

Plant Data Action Level Note: Red No Threshold

13 13 NRC PI - Alert and Notification Reliability Green 94%

White <94%

90%

91%

92%

93%

94%

95%

96%

97%

98%

99%

100%

Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 12 Month Rolling Values

% Of Opportunities Green 94%

White <94%

Yellow <90%

Plant Data Action Level Note: Red No Threshold

14 14 Collective Radiation Exposure - Unit Values 0

20 40 60 80 100 120 140 160 180 200 Apr05 M ay05 Jun05 Jul05 Aug05 Sep05 Oct05 Nov05 Dec05 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 12 Month Normalized Unit Values*

Rem INPO 100% Performance Level Unit 1 - Actuals Unit 2 - Actuals Action Level

15 15 NRC PI - PA Security Equipment Performance Index White > 0.08 Green 0.08 0.00 0.02 0.04 0.06 0.08 0.10 0.12 0.14 0.16 Index Value Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 12 Months Rolling Averages White > 0.08 Green 0.08 Plant Data Action Level Note: Yellow/Red No Threshold

16 16 NRC PI - FFD/Personnel Reliability Program White > 2 Green 2 0

1 2

3 4

5 Reportable Events Caused By Programmatic Failures Apr-05 May-05 Jun-05 Jul-05 Aug-05 Sep-05 Oct-05 Nov-05 Dec-05 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 12 Months Rolling Sum Yellow > 5 White > 2 Green 2 Plant Data Action Level Note: Red No Threshold

17 17 Engineering Realignment 2006 Engineering Realignment 2006

18 18 Organizational Chart: Technical Organizational Chart: Technical Support Support Technical Support Engineering Fuels Licensing

19 19 Organizational Chart:

Organizational Chart: Licensing Licensing Nuclear Licensing Vogtle Licensing Farley Licensing Hatch Licensing PRA Services License Renewal

20 20 Organizational Chart:

Organizational Chart: Engineering Engineering Engineering VP Plant Support Engin. Services Engin. Admin. Serv.

Config. Mgmt.

Common QA Prog.

21 21 Organizational Chart: Plant Support Organizational Chart: Plant Support Plant Suppt. Mgr.

Farley Support Hatch Support Vogtle Support Design Change Team RER Team Elec./I & C RER Team Mech/Civil Proj/Planning Team Design Change Team RER Team Elec./I & C RER Team Mech/Civil Proj/Planning Team Design Change Team RER Team Elec./I & C RER Team Mech/Civil Proj/Planning Team

22 22 Organizational Chart:

Organizational Chart: Configuration Configuration Management Management Config. Manager Design. Config. -

DCP /Design.

Config. As Found Minor Mods.

Hatch E Fin Farley E Fin Vogtle E Fin Admin. Asst.

23 23 Organizational Chart:

Organizational Chart: Engineering Engineering Services Services Engin. Serv. Mgr.

M & IS Equip. Reliab.

Engin. Prog. Mgr.

  • Seismic
  • Stress
  • Fire Protection
  • Dry Cask Storage
  • Security
  • Environmental Qualification

24 24 Organizational Chart:

Organizational Chart: Engineering Engineering Programs Programs Engin. Prog. Mgr.

Stress Fire Protection Dry Cask Storage Security Seismic/

Environ. Qualif.

Admin. Asst.

25 25 Organizational Chart:

Organizational Chart: Equipment Equipment Reliability Reliability Equip. Reliab. Mgr.

Components - Mech.

Components - Mech.

Equipment Reliab.

Components - Elec.

Admin. Asst.

Turbine Gen.

26 26 Farley Project Overview:

Farley Project Overview:

2006 TIP Award 2006 TIP Award

27 27

28 28 Pandemic Plans Pandemic Plans Human Flu Pandemic Threats to Business Continuity Avian Flu H5N1 Avian Flu H5N1 Panic or Pandemic ?

29 29 What are we trying to do here?

What are we trying to do here?

3/4 3/4 Agree that our SNC focus is to Agree that our SNC focus is to keep nuclear units on keep nuclear units on--line line 3/4 3/4 Acknowledge the uncertainty of a Acknowledge the uncertainty of a widespread pandemic widespread pandemic 3/4 3/4 In response, In response, create a flexible plan create a flexible plan that accommodates an uncertain that accommodates an uncertain event event 3/4 3/4 When the pandemic does happen, When the pandemic does happen, zz Focus resources where they will Focus resources where they will do the most good; with frugality do the most good; with frugality zz Put forces and resources in reserve Put forces and resources in reserve as much you can as much you can SNC Decision Matrix Pandemic Progression - Example - SRO Decision Cycle Low Guarded Elevated High Severe SNC Pandemic Threat Level Gradually Progresses Reaches SNC Threshold Reaches SNC Threshold Plan ahead:

  • Vaccinate SROs Implement the plan:
  • Vaccinate SROs Plan ahead:
  • Establish site quarters Implement the plan:
  • Establish site quarters Plan ahead:
  • Unit shutdown
  • Consolidate SROs at site
  • Prioritize unit shutdowns
  • Consider outside assistance Implement initial preparations:
  • Acquire vaccination meds
  • Buy hand sanitizer

30 30 SNCs Mission in the face of a pandemic threat To continue the uninterrupted maximum generation and delivery of electrical energy from the nuclear reactors at all three sites, considering mandated minimal staffing levels that are on-hand for an extended period of time and that there are no allowable compromise of the public health, public safety or violations of then-in-effect regulations in doing so.

Implementation The specified task would be to keep electricity flowing uninterrupted at maximum loads for all six nuclear units.

  • Implied in that is the suggested establishment of minimum manning documents for not only numbers of employees present for duty but minimums assigned in several duty functions.
  • Falling below these pre-established minimums at any location might necessitate voluntary derate or even shutdown of selected nuclear units, in a logical, stepwise manner.
  • Likewise, there may be a hierarchy of necessary plant services and necessary Corporate services beyond which nuclear unit operations would not be prudent, regulatorily allowable or even possible SNC Mission and Implementation Statement in the event of a pandemic Pandemic Plans Pandemic Plans

31 31 SNC Decision Matrix Pandemic Progression - Gradual versus Rapid Low Guarded Elevated High Severe Implement Plan Implement Plan Implement Plan Implement Plan Implement Plan Implement Plan Low Pandemic explodes SNC Pandemic Threat Level Gradually Progresses Reaches SNC Threshold Reaches SNC Threshold Reaches SNC Threshold Reaches SNC Threshold Reaches SNC Threshold Reaches SNC Threshold High Severe Implement Plan Implement Plan Event-driven Decision Matrix

-- Example --

Pandemic Plans Pandemic Plans

32 32 Farley Site Status Farley Site Status Randy Johnson Randy Johnson

33 33 Positioned for the Future Positioned for the Future 3/4 3/4 Both unit's steam generators replaced in 2000 & 2001 Both unit's steam generators replaced in 2000 & 2001 3/4 3/4 Completed construction and placed in service new mechanical draf Completed construction and placed in service new mechanical draft t cooling towers in 2003 & 2004 cooling towers in 2003 & 2004 3/4 3/4 Replaced both unit's reactor vessel heads in 2004 & 2005 Replaced both unit's reactor vessel heads in 2004 & 2005 3/4 3/4 Completed Dry Cask Storage facility and completed first campaign Completed Dry Cask Storage facility and completed first campaign in 2005.

in 2005.

3/4 3/4 License renewal approved License renewal approved-- Spring 2005. Unit 1 Spring 2005. Unit 1-- 2038. Unit 2 2038. Unit 2-- 2041 2041 3/4 3/4 New 20,000 sq. ft. Maintenance Training facility opened in summe New 20,000 sq. ft. Maintenance Training facility opened in summer r 2006.

2006.

3/4 3/4 In 2006, completed extensive repair effort on fire protection In 2006, completed extensive repair effort on fire protection impairments related to Kaowool & large penetration seals impairments related to Kaowool & large penetration seals

34 34 Licensing Status Licensing Status Doug McKinney Doug McKinney

35 35 Licensing Status Licensing Status 3/4 3/4 1 LER in 2006 (MSIV failure to close) 1 LER in 2006 (MSIV failure to close) 3/4 3/4 CDBI, ISFSI, EP, MSIV Special Inspection CDBI, ISFSI, EP, MSIV Special Inspection are completed NRC inspections are completed NRC inspections 3/4 3/4 MSPI Verification, Initial Exam, Outage are MSPI Verification, Initial Exam, Outage are future NRC inspections future NRC inspections 3/4 3/4 NRC approval requests NRC approval requests -- snubber relief snubber relief request, room cooler TS, SSPS TS, Weld request, room cooler TS, SSPS TS, Weld Overlay Alternative, 10 year ISI /IST, Overlay Alternative, 10 year ISI /IST, Personnel Access Hatch Personnel Access Hatch

36 36 Triennial Fire Inspection Actions Triennial Fire Inspection Actions 3/4 3/4 Re Re--validate safe shutdown analysis and validate safe shutdown analysis and develop database develop database 3/4 3/4 Manual operator actions review Manual operator actions review 3/4 3/4 Circuit analysis review Circuit analysis review 3/4 3/4 Communications, emergency lights, Communications, emergency lights, diagnostic instruments diagnostic instruments 3/4 3/4 Complete by end of 2007 Complete by end of 2007 3/4 3/4 Next Farley Triennial Fire Audit 3/2008 Next Farley Triennial Fire Audit 3/2008

37 37 Problem Identification Problem Identification and Resolution and Resolution Paul Hayes Paul Hayes

38 38 Problem Identification & Resolution Problem Identification & Resolution Problems Identified Through Problems Identified Through --

3/4 3/4 Corrective Action Program Corrective Action Program 3/4 3/4 System Health Reports System Health Reports 3/4 3/4 Equipment Reliability Board (ERB)

Equipment Reliability Board (ERB) 3/4 3/4 Major Issues List Major Issues List 3/4 3/4 Long Range Plans Long Range Plans 3/4 3/4 Life Cycle Plan Life Cycle Plan

39 39 Life Cycle Plan Life Cycle Plan 3/4 3/4 Provides overview of plant projects Provides overview of plant projects 3/4 3/4 Integrates planned improvements and Integrates planned improvements and outage durations outage durations 3/4 3/4 Ensure budget review and assessment Ensure budget review and assessment against other plant needs against other plant needs

40 40 Major Issue List Major Issue List 3/4 3/4 30 Issues 30 Issues 3/4 3/4 Directs Problem Resolution Focus for Directs Problem Resolution Focus for Primarily Short/Medium Primarily Short/Medium--Term Issues Term Issues 3/4 3/4 Monthly Meetings Ensure Management Monthly Meetings Ensure Management Visibility Visibility

41 41 Focus Areas Focus Areas 3/4 3/4 HHSI HHSI 3/4 3/4 4KV Breakers 4KV Breakers 3/4 3/4 ECCS Sump ECCS Sump 3/4 3/4 Service Water Issues Service Water Issues 3/4 3/4 Alloy 600 Alloy 600 3/4 3/4 Plant Computer Replacement Plant Computer Replacement 3/4 3/4 MSIVs MSIVs 3/4 3/4 Main Steam Line Vibration Main Steam Line Vibration

42 42 HHSI HHSI Pump Casings Pump Casings Replacing all 6 casings. First replacement planned for March 200 Replacing all 6 casings. First replacement planned for March 2007.

7.

Charging Pump Gassing Charging Pump Gassing 3/4 3/4 Significant Event and LER 12/05 Significant Event and LER 12/05 3/4 3/4 Attributed to large swing in VCT pressure Attributed to large swing in VCT pressure 3/4 3/4 Ops procedures enhance to monitor for VCT pressure fluctuations Ops procedures enhance to monitor for VCT pressure fluctuations 3/4 3/4 Participating in WOG program to study gas void formation/behavio Participating in WOG program to study gas void formation/behaviorr 3/4 3/4 INPO assist visit investigated events and made recommendations INPO assist visit investigated events and made recommendations regarding automatic pressure control, checking system for additi regarding automatic pressure control, checking system for additional onal high points, adding charging pump discharge vents, etc high points, adding charging pump discharge vents, etc 3/4 3/4 Restoration of automatic VCT pressure control under investigatio Restoration of automatic VCT pressure control under investigation.

n.

43 43 4 KV Breakers 4 KV Breakers 3/4 3/4 Expediting replacement with C Expediting replacement with C--H.

H.

3/4 3/4 Unit 1 & 2 SW breaker design issued and Unit 1 & 2 SW breaker design issued and breakers procured.

breakers procured.

3/4 3/4 Implementation begins in Dec 06 Implementation begins in Dec 06 3/4 3/4 Other Safety Related bus breaker DCP Other Safety Related bus breaker DCP preparation in preparation in--progress.

progress.

3/4 3/4 P.O. for additional breakers to be issued in P.O. for additional breakers to be issued in Dec 06 Dec 06

44 44 ECCS Sump ECCS Sump 3/4 3/4 Modifications scheduled for U2R18 and Modifications scheduled for U2R18 and U1R20 (2007)

U1R20 (2007) 3/4 3/4 Continue to respond to emerging criteria Continue to respond to emerging criteria such as chemical effects such as chemical effects

45 45 Service Water Issues Service Water Issues 3/4 3/4 Replacement of all 10 SW pumps starting Replacement of all 10 SW pumps starting with 2E.

with 2E.

3/4 3/4 No reliance on booster pumps for lube and No reliance on booster pumps for lube and cooling.

cooling.

46 46 Alloy 600 Alloy 600 3/4 3/4 Inspection planned for U2R18 (Spring 07)

Inspection planned for U2R18 (Spring 07) 3/4 3/4 Weld overlays planned for U1R20 (Fall 07)

Weld overlays planned for U1R20 (Fall 07) 3/4 3/4 Unit 2 overlays planned for 2010 Unit 2 overlays planned for 2010

47 47 Plant Computer Replacement Plant Computer Replacement 3/4 3/4 Replacement completed for Unit 1 and the Replacement completed for Unit 1 and the simulator simulator 3/4 3/4 Unit 2 complete by February 2007 Unit 2 complete by February 2007

48 48 MSIVs MSIVs 3/4 3/4 Component refurbishment and Component refurbishment and enhancements scheduled for upcoming enhancements scheduled for upcoming outages outages 3/4 3/4 Computational Fluid Dynamics (CFD)

Computational Fluid Dynamics (CFD) assessment to be performed by Weir assessment to be performed by Weir Valve. Should be complete in early 2007.

Valve. Should be complete in early 2007.

49 49 Main Steam Line Vibration Main Steam Line Vibration 3/4 3/4 Initiated Engineering Study to assess Initiated Engineering Study to assess recent OE and technology to determine if recent OE and technology to determine if improved techniques available.

improved techniques available.

50 50 Major Focus Areas Major Focus Areas Sonny Sonny Bargeron Bargeron

51 51 2007 Overview 2007 Overview 3/4 3/4 Spring and Fall outage Spring and Fall outage 3/4 3/4 INPO Non INPO Non-- Operations Accreditation Operations Accreditation Renewal Renewal 3/4 3/4 INPO Evaluation INPO Evaluation 3/4 3/4 LO Initial Training Exams LO Initial Training Exams 3/4 3/4 MSPI Margin Recovery MSPI Margin Recovery

52 52 Reactor Coolant Pump Inspections:

Reactor Coolant Pump Inspections:

    • 18 month motor inspection on A & B 18 month motor inspection on A & B
    • Shaft cracking UT Inspection on all pumps Shaft cracking UT Inspection on all pumps
    • Seal inspection on B Seal inspection on B
    • 10 10--year motor change year motor change--out on C out on C Alloy 600 Inspections:

Alloy 600 Inspections:

    • UT of 4 UT of 4 Pressurizer Pressurizer nozzles nozzles Unit 2 Spring Outage Plans Unit 2 Spring Outage Plans Outage Plans Outage Plans

53 53 Unit 2 Spring Outage Plans Unit 2 Spring Outage Plans 3/4 3/4 Containment Sump Screen Modification Containment Sump Screen Modification 3/4 3/4 Secondary Secondary--side Inspections of all Steam side Inspections of all Steam Generators including Upper Internals and Generators including Upper Internals and Feedring Feedring 3/4 3/4 Inspection and Refurbishment of all 6 Main Steam Inspection and Refurbishment of all 6 Main Steam Isolation Valves Isolation Valves 3/4 3/4 Main Power Transformer Replacement (#1 & #3)

Main Power Transformer Replacement (#1 & #3)

Outage Plans Outage Plans

54 54 Unit 1 Fall Outage Plans Unit 1 Fall Outage Plans 10 year Reactor Vessel ISI 10 year Reactor Vessel ISI 3/4 3/4 Rx vessel inspection Rx vessel inspection 3/4 3/4 RCS loop to vessel alloy 600 weld UT ( HL & CL)

RCS loop to vessel alloy 600 weld UT ( HL & CL) 3/4 3/4 Rx Vessel bottom mounted Rx Vessel bottom mounted incore incore penetration weld UT (alloy penetration weld UT (alloy 600) 600)

Pressurizer Pressurizer Alloy 600 weld mitigation Alloy 600 weld mitigation 3/4 3/4 Surge line Surge line 3/4 3/4 Spray line Spray line 3/4 3/4 3 safety lines 3 safety lines Outage Plans Outage Plans

55 55 Unit 1 Fall Outage Plans Unit 1 Fall Outage Plans 3/4 3/4 Containment Sump modification Containment Sump modification 3/4 3/4 Replace two Main Power Transformers Replace two Main Power Transformers 3/4 3/4 High Pressure Turbine Rotor Out inspection with a High Pressure Turbine Rotor Out inspection with a Rotor Swap Rotor Swap 3/4 3/4 Secondary Secondary--side Inspections of all Steam Generators side Inspections of all Steam Generators including Upper Internals and including Upper Internals and Feedring Feedring 3/4 3/4 MSIV inspection / refurbishment MSIV inspection / refurbishment Outage Plans Outage Plans

56 56 INPO Non INPO Non-- Operations Operations Accreditation Renewal Accreditation Renewal 3/4 3/4 Engineering, Maintenance & Chemistry Engineering, Maintenance & Chemistry pipelines pipelines 3/4 3/4 January Evaluation January Evaluation 3/4 3/4 Maintenance training facility Maintenance training facility zz Lab mockups Lab mockups 3/4 3/4 Flow loop simulator Flow loop simulator zz Practical factor training Practical factor training zz Dynamic learning activities Dynamic learning activities

57 57 INPO Evaluation INPO Evaluation 3/4 3/4 Next evaluation July 2007 Next evaluation July 2007 3/4 3/4 Accomplishments Accomplishments zz Focus on equipment replacements Focus on equipment replacements zz Material condition Material condition zz Workforce ownership Workforce ownership zz Conservative decision making Conservative decision making zz Low Low rad rad exposure exposure zz Timely resolution of equipment problems Timely resolution of equipment problems

58 58 INPO Evaluation INPO Evaluation 3/4 3/4 Improvement Needed Improvement Needed zz Operations planning input Operations planning input zz Recognition of error likely situations Recognition of error likely situations zz Component Component mis mis--positioning positioning zz Lifting & Rigging Lifting & Rigging

59 59 LO Initial Training Exams LO Initial Training Exams 3/4 3/4 HL HL -- 30 (10/06 Exam) 30 (10/06 Exam) -- 1 RO & 3 SRO 1 RO & 3 SRO 3/4 3/4 HL HL -- 31 ( 10/07 Exam) 31 ( 10/07 Exam) -- 7 RO & 7 SRO 7 RO & 7 SRO 3/4 3/4 HL HL -- 32 ( 10/08 Exam) 32 ( 10/08 Exam) -- 8 RO & 8 SRO 8 RO & 8 SRO

60 60 MSPI Margin Recovery MSPI Margin Recovery 3/4 3/4 All NRC indicators currently All NRC indicators currently green green 3/4 3/4 Two indicators with zero margin to white Two indicators with zero margin to white zz U1 CCW U1 CCW zz U2 MDAFW U2 MDAFW Developed action plan to recover margin Developed action plan to recover margin

61 61 U1 CCW Margin Recovery U1 CCW Margin Recovery 3/4 3/4 1 failure to start in 2006 (

1 failure to start in 2006 ( handswitch handswitch contacts) contacts) 3/4 3/4 Fail to start or Run will result in white Fail to start or Run will result in white MSPI MSPI 3/4 3/4 Recovery focused on Recovery focused on handswitch handswitch &

breaker replacements breaker replacements

62 62 U2 MDAFW Margin Recovery U2 MDAFW Margin Recovery 3/4 3/4 1 failure to run in 2004 due to oil leak 1 failure to run in 2004 due to oil leak requiring pump stop requiring pump stop 3/4 3/4 1 fail to start will result in white MSPI 1 fail to start will result in white MSPI 3/4 3/4 Recovery focused on breaker Recovery focused on breaker replacement, replacement, handswitch handswitch replacement, replacement, and gasket improvement and gasket improvement

63 63 Questions Questions

64 64 4kV Safety Related 4kV Safety Related Breakers Breakers Overview and Planning Overview and Planning

65 65 Most Recent Issues By Year Most Recent Issues By Year 3/4 3/4 2000 (2 issues) 2000 (2 issues) zz Dirty hand switch contacts Dirty hand switch contacts zz unknown unknown 3/4 3/4 2002 (1 issue) 2002 (1 issue) zz Dirty hand switch contacts Dirty hand switch contacts 3/4 3/4 2004 (4 issues) 2004 (4 issues) zz Dirty hand switch contacts Dirty hand switch contacts zz Four bar linkage damaged Four bar linkage damaged 3/4 3/4 2005 (3 issues) 2005 (3 issues) zz Dirty hand switch contacts Dirty hand switch contacts zz Loose stop bolt Loose stop bolt zz Unknown Unknown 3/4 3/4 2006 (6 issues) 2006 (6 issues) zz Charging motor (2 issues were out Charging motor (2 issues were out--of of--spec spec -- not failures) not failures) zz Guide rail notch too narrow (2 Guide rail notch too narrow (2--DL03)

DL03) zz Roller/Trip latch gap out of spec high (Root Cause 1 Roller/Trip latch gap out of spec high (Root Cause 1--DL05)

DL05) zz 2 issues are in 2 issues are in--progress (1 progress (1--DH03, 1 DH03, 1--DK05)

DK05)

66 66 Bus Arrangement Bus Arrangement TO 230 KV SWITCHYARD UNIT 1 MAIN G ENERATO R UNIT AUX XFMR UNIT AUX FROM 230 KV SWITCHYARD STARTUP XFMR 1B SWITCHYARD 230 KV FROM STARTUP XFMR 1A 1A 1C 1E 1L 1F 1K 1H RIVER WATER RIVER WATER RIVER WATER SERVICE WATER CCW RHR AFW CTMT SPRAY CHARGING CCW CTMT SPRAY AFW RHR CCW SERVICE WATER SERVICE WATER RIVER WATER RIVER WATER RCP RCP RCP SERVICE WATER Charging Charging 1G 1D SERVICE WATER 1J 1A XFMR 1B 1B ESP Simplified Unit-1 4160v Normal Alignment (Unit 2 is similar)

67 67 Most Recent Root Cause (1 Most Recent Root Cause (1--DL05)

DL05) 3/4 3/4 During a routine train swap, the breaker for the During a routine train swap, the breaker for the 1C SW pump was momentarily closed but 1C SW pump was momentarily closed but tripped free (open) tripped free (open) 3/4 3/4 Root cause investigation attributed the failure to Root cause investigation attributed the failure to age and degradation of existing Allis age and degradation of existing Allis--Chalmers Chalmers breakers which exhibited:

breakers which exhibited:

zz Excessive gap distance between the latch roll and Excessive gap distance between the latch roll and the trip latch the trip latch zz Bending of the back plate. This is the mounting Bending of the back plate. This is the mounting plate for the stop bolt.

plate for the stop bolt.

68 68 Internal Operating Mechanism for Allis Internal Operating Mechanism for Allis Chalmers MA350 Chalmers MA350

69 69 Interim Action Plan Interim Action Plan 3/4 3/4 Analysis of high duty breakers on expedited Analysis of high duty breakers on expedited schedule schedule zz Complete with exception of 2 Complete with exception of 2--DK04 (scheduled DK04 (scheduled 11/28), 1 11/28), 1--DG02 (feeder breaker for 1R21)

DG02 (feeder breaker for 1R21) 3/4 3/4 Extend analysis to include all safety related Extend analysis to include all safety related breakers breakers 3/4 3/4 Replacement of SW breakers with new vacuum Replacement of SW breakers with new vacuum breakers breakers 3/4 3/4 Use the healthy breakers from SW Use the healthy breakers from SW replacements in F & G (after PM performed) replacements in F & G (after PM performed) 3/4 3/4 Expedite Expedite DCPs DCPs for Unit 1 & 2 F & G for Unit 1 & 2 F & G replacements replacements

70 70 Long Term Plan Long Term Plan 3/4 3/4 Total replacement of existing obsolete Total replacement of existing obsolete Allis Allis--Chalmers MA350 breakers with Chalmers MA350 breakers with Cutler Hammer vacuum breakers Cutler Hammer vacuum breakers zz Unit 2 Unit 2 DCPs DCPs (F &G) due by March, 2007 (F &G) due by March, 2007 zz Unit 2 replacements complete by Spring 2007 Unit 2 replacements complete by Spring 2007 zz Unit 1 Unit 1 DCPs DCPs (F &G) due by June, 2007 (F &G) due by June, 2007 zz Unit 1 replacements complete by end of 2007 Unit 1 replacements complete by end of 2007 3/4 3/4 Increased tracking by serial number of Increased tracking by serial number of breaker locations and number of cycles breaker locations and number of cycles

71 71 Breaker Operation Breaker Operation Trip Free Closed SAT

72 72 Questions Questions