ML072350546

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Public Meeting Summary - Enclosure 2
ML072350546
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 08/23/2007
From: Douglas S, Madison D
Southern Nuclear Operating Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML072350528 List:
References
FOIA/PA-2010-0209
Download: ML072350546 (43)


Text

Edwin I. Hatch Nuclear Plant Edwin I. Hatch Nuclear Plant NRC Region II Status Meeting NRC Region II Status Meeting August 15, 2007 August 15, 2007 Dennis Madison - Hatch Vice President Steve Douglas - Plant Manager Southern Nuclear Operating Company

Agenda

  • Introduction
  • Hatch Project Overview

- Plant Performance

- Site Vice President Reorganization

  • Topical Updates
  • Major Projects

- Major Projects Underway

- Recently Completed Projects

  • Open Discussion

Plant Performance

August 7, 2007 Unit 2 Reactor Trip

  • I&C technician inadvertently tripped an overcurrent relay on the normal incoming feeder breaker for D 4160 VAC bus during calibration
  • Loss of this bus resulted in a loss of 2 condensate pumps and 2 booster pumps, as well as a recirc runback
  • Plant scrammed on low reactor water level
  • All systems responded as designed; no actuation of HPCI or RCIC
  • Bus re-energized about 1.5 minutes from alternate source
  • Breakdown in risk assessment process

Forced Loss Rate - Hatch 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 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 Oct06 Nov06 Dec06 Jan07 Feb07 M ar07 Apr07 M ay07 Jun07 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

Industrial Safety - Hatch 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 Jan06 Feb06 M ar06 Apr06 M ay06 Jun06 Jul06 Aug06 Sep06 Oct06 Nov06 Dec06 Jan07 Feb07 M ar07 Apr07 M ay07 Jun07 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

NRC Performance Indicators - Hatch NRC PI - Safety System Functional Failures White > 6 Green 6 0

1 2

3 4

5 6

7 8

Safety System Functional Failures Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 12 Month Rolling Sum White > 6 Green 6 Unit 1 Data Unit 2 Data Action Level Note: Yellow/Red No Threshold

Unit 1 HPCI

Unit 1 RCIC

Unit 2 HPCI

Unit 2 RCIC

NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, Emergency AC Power 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 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 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

Emergency Diesel Generator

NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, High Pressure Injection 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 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 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

Site Vice President Reorganization

J. B. BEASLEY, JR.

Chairman, President & Chief Executive Officer K. S. KING CFO & Vice President Corporate Services M. M. CASTON General Counsel, VP External Affairs &

Corporate Secretary W. L. BARGERON Plant Manager J. D. WILLIAMS Site Support Manager W. D. DRINKARD Quality Assurance Manager M. J. AJLUNI Site Support Manager

  • SCS Employee Site Vice President Reorganization - January 2007 0407 R. A. BELL*

Human Res. Sr. VP Southern Company D. R. MADISON Vice President - Hatch J. R. JOHNSON Vice President - Farley T. E. TYNAN Vice President - Vogtle T. L. YOUNGBLOOD Site Support Manager C. R. DEDRICKSON Plant Manager S. M. DOUGLAS Plant Manager S. A. MITCHELL Asst. Corp. Sec./Exec.

Asst. to Pres./Asst. Treas.

P. R. BIZJAK Safety & Health Manager C. D. COLLINS Supply Chain General Manager VACANT

  • H. R. Director J. G. WOLFE Comptroller &

Treasurer J. T. GASSER Executive Vice President

& Chief Nuclear Officer A. F. THORNHILL Managing Atty. &

Compliance Manager C. H. PHILLIPS Public Affairs Manager J. M. GODFREY Environmental Affairs Manager W. H. LEE Emergency Planning Supervisor J. A. MILLER Senior Vice President Nuclear Development D. P. BURFORD Nuclear Fleet Security and Emergency Preparedness Manager Vogtle 3&4 Bellefonte D. H. JONES Engineering Vice President W. L.

BURMEISTER Plant Support Manager A. HARRIS Engineering Services Manager G. K. McELROY Engineering Admin.

Services Manager J. B. PAPPAS Configuration Management Manager B. E. HUNT Nuclear Fuels Manager B. J. GEORGE Nuclear Licensing Manager W. B. THIGPEN Security Supervisor/Access Authorization P. A. HURST Corporate Concerns Supervisor L. M. STINSON Fleet Operations Support Vice President

Fleet Operations Support (proposed)

Fleet Ops VP Fleet Operations Manager Fleet Maintenance /

WC Manager Fleet Outage Manager Assistant Fleet Chem /

HP Manager Fleet Security &

EP Manager Fleet Training &

PI Manager Operations Staff Maintenance/

WC Staff Outage Staff HP Staff ***

Chem Staff

  • Security Supervisor EP Supervisor Security Staff EP Staff NFS Coordinator Admin Asst Admin Asst
  • Training Supervisor
  • Instructors /

Staff * / **

PI Staff CAPCO

  • Transfer from Engineering
    • Transfer from Supply Chain
      • Transfer from Environmental

Site Engineering (proposed)

Site VP Plant Mgr.

Engineering Mgr. ***

Site Suppt. Mgr.

Design Engineering Support Modifications PMMS

  • Mech & Civil Design
  • Elec/I & C Design Nuc. Systems Programs BOP Systems Elec./I & C Admin. Asst Performance Improvement Principal Engineer -

Licensing **

Equipment Reliability New or Modified Org.

  • EFIN
  • Design Chg. (Corp)
  • Mech/Civil (Corp)
  • Elec/I &C (Corp)
    • Dotted line reporting to Corporate Licensing
      • Dotted line reporting to Chief Engineer

Topical Updates

SNM Update

  • Procedure revisions implemented to upgrade SNM accountability practices for in-core detectors following conclusion of SNM retrieval activities last year
  • Initial results indicated that 4 in-core detectors were not at the location specified
  • All 4 detectors were subsequently located and accounted for
  • Fuel pool legacy cleanup scheduled 3rd/4th quarter 2007

Tritium Sampling

  • Update on tritium graphs (T12, NW10, N008A)
  • Mactec Status

- Phase 2 Report (2007)

- Complete hydrology study (determine need)

  • Unit 2 CST pipe Replacement Update

Tritium Sampling SAMPLE WELL T12 1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 Feb-03 May-03 Aug-03 Nov-03 Mar-04 Jun-04 Sep-04 Jan-05 Apr-05 Jul-05 Oct-05 Feb-06 May-06 Aug-06 Dec-06 Mar-07 Jun-07 H3 pCi / L T12

Tritium Sampling Tritium Outfall Sample (Subsurface drain N008A) 1.00E+03 1.00E+04 1.00E+05 05/01 /06 07/01 /06 09/01 /06 11/01 /06 01/01 /07 03/01 /07 05/01 /07 07/01 /07 H 3 p C i / L 1Y22N008A

Tritium Sampling SAMPLE WELL (NW10) 1.00E+04 3.00E+04 5.00E+04 7.00E+04 9.00E+04 1.10E+05 1.30E+05 1.50E+05 1.70E+05 10/9/2006 11/9/2006 12/9/2006 1/9/2007 2/9/2007 3/9/2007 4/9/2007 5/9/2007 6/9/2007 7/9/2007 8/9/2007 H3 pCi/ L NW10

1A RHR Pump Vibration

  • Vibration observed on 1A RHR pump only during two pump flow in Division 1 (Pumps A & C)
  • Occurs only in loop flow range of 4000 - 6000 gpm
  • Cause of vibration has not been determined
  • Conceptual design being developed to increase natural frequency of the loop

Alternative Source Term

  • Full scope AST analysis submitted to NRC 8/29/2006
  • Control room inleakage testing showed good results, well within interim licensing basis limits
  • Approval of AST submittal required by 5/31/2010
  • Significant interdisciplinary review at NRR is in progress
  • Planned and potential modifications to support AST are scheduled to complete by spring 2010

Staffing

  • Pipeline Replenishment

- Strategies for hiring entry level workers and engineers

- License classes

  • 8 candidates to finish this December
  • 10 SRO candidates started June 2007
  • 16 candidates to start March 2008
  • 16 candidates to start March 2009
  • Average class size of 16

- All other initial programs up and running (Chemistry, HP, Maintenance, etc.)

Steam Chase Grating Analyses

  • Tool boxes were staged over grated vent openings between Reactor Building steam pipe chase and torus room
  • Hinged vent covers were strapped to vent grating on Unit 2
  • Tool boxes were removed from grating on both units and strap was removed on Unit 2

Tool Box

Steam Chase Grating Analyses

  • Unit 1 limiting parameter is differential pressure on wall between torus room and ECCS pump rooms
  • Unit 1 analysis demonstrated that as-found vent paths provided adequate opening to meet differential pressure limits
  • Unit 2 limiting parameter is differential pressure on wall between torus room and reactor building ground level floor
  • Unit 2 analysis is at the preliminary results stage (not checked)
  • Preliminary results indicate that correcting for mass flow conservatisms will result in differential pressures within the analyzed limits

TSC HVAC Availability

  • Event represents good incorporation of corrective actions from 2005 TSC white finding
  • EP and work planning personnel discussed work activity during planning phase
  • Work was placed on hold when first phase took longer than expected so issue could be discussed with NRC Region II personnel
  • Region II provided timely feedback regarding SNCs planned course of action

Planned Major Projects

Unit 1 Main Transformer Replacement

- Asset management/Life Cycle management

- Replaces leased Alabama Power transformer with permanent transformer

- Spare transformer delivered early 2008 for infant mortality issue

- New transformer good to end of plant life

Shroud Tie Rod Upper Restraints

  • Unit 1 Shroud tie rod upper restraint replacement (2008)
  • Unit 2 Shroud tie rod upper restraint replacement (2009)

- Equipment reliability/safety

- Replaces upper supports with larger components to remove susceptibility to IGSCC

- Restores to BWRVIP criteria for repaired shrouds

- Eliminates need to re-inspect shroud horizontal welds

- Licensing submittal for Unit 1 has been issued

Condenser Bypass Sparger Replacement

  • Unit 1 and Unit 2 Condenser bypass sparger replacements (Unit 1 in 2008. Unit 2 in 2009)

- Replaces degraded bypass spargers

- Spargers currently limit Operations use of bypass (i.e., length of time in Hot shutdown)

Adjustable Speed Drives

  • Adjustable speed drives (Unit 1 in 2010 and Unit 2 in 2011)

- Asset management/Life Cycle management

- Replaces the Recirculation M-G sets with Variable Frequency drives

- Eliminates Recirculation flow step changes from fluid coupling positioner

- Does not eliminate step changes from Bi-stable flow

- Equipment reliability

Feedwater Sparger End Pins

  • Feedwater sparger end pin replacement (Unit 1 in 2008, no Unit 2 installation)
  • Remote tooling will allow the installation of the Feedwater Sparger End Pins simultaneously with other work activities on the refueling floor

Completed Major Projects

Mark VI Turbine Controls

  • Unit 1 and Unit 2 Mark VI Turbine Controls

- Completed on both units

- Asset management/Life Cycle management

- Installs triple redundant digital controls

- Replaces obsolete Mark I control system

Unit 2 Generator Exciter Controls

- Completed on Unit 2 - Unit 1 to complete in 2008)

- Asset management/Life Cycle management

- Replaces obsolete exciter with EX 2100 alterex

Condenser Bellows Replacement

  • Unit 1 and Unit 2 Condenser Bellows Replacement

- Completed on both units

- Equipment reliability - Industry OE

- Replaced bellows that were beyond design life

Unit 1 Drywell Cooler Replacement

  • Unit 1 Drywell Cooler Replacement

- Equipment reliability

- 2005 shutdown due to drywell leakage and containment integrity issue (leak from drywell into cooler)

- Replaced all 16 Drywell cooler coils

Open Discussion