ML072350546

08/15/2007 Public Meeting Summary - Enclosure 2

ML072350546
Person / Time
Site:	Hatch
Issue date:	08/23/2007
From:	Douglas S, Madison D Southern Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML072350528	List: ML072350536 ML072350546
References
FOIA/PA-2010-0209
Download: ML072350546 (43)

Text

Edwin I. Hatch Nuclear Plant NRC Region II Status Meeting August 15, 2007 Dennis Madison - Hatch Vice President Steve Douglas - Plant Manager Southern Nuclear Operating Company Enclosure 2

Agenda

• Introduction

• Hatch Project Overview

- Plant Performance

- Site Vice President Reorganization

• Topical Updates

• Major Projects

- Major Projects Underway

- Recently Completed Projects

• Open Discussion Enclosure 2

Plant Performance Enclosure 2

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 Enclosure 2

Forced Loss Rate - Hatch Forced Loss Rate 12.0 11.0 10.0 9.0 8.0 7.0 Percent 6.0 5.0 4.0 3.0 2.0 1.0 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months)

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

Industrial Safety - Hatch Industrial Safety Accident Rate - Plant Value Industrial Safety Accident Rate per 2.0 1.8 1.6 1.4 1.2 1.0 200,000 Hours Worked 0.8 0.6 0.4 0.2 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months)

INPO 100% Performance Level Industrial Safety Accident Rate (Cycle Based)

Action Level Enclosure 2

NRC Performance Indicators - Hatch NRC PI - Safety System Functional Failures 0

1 Safety System Functional Failures 2

3 Green 6 4

5 6

7 White > 6 8

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 Note: Yellow/Red No Threshold White > 6 Green 6 Unit 1 Data Unit 2 Data Action Level Enclosure 2

Unit 1 HPCI Enclosure 2

Unit 1 RCIC Enclosure 2

Unit 2 HPCI Enclosure 2

Unit 2 RCIC Enclosure 2

NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, Emergency AC Power System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 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 Enclosure 2

Emergency Diesel Generator Enclosure 2

NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, High Pressure Injection System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 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 Enclosure 2

Site Vice President Reorganization Enclosure 2

Site Vice President Reorganization - January 2007 J. B. BEASLEY, JR.

Chairman, President & Chief Executive Officer S. A. MITCHELL Asst. Corp. Sec./Exec.

Asst. to Pres./Asst. Treas.

K. S. KING D. H. JONES M. M. CASTON J. T. GASSER R. A. BELL* J. A. MILLER CFO & Vice President Engineering General Counsel, Executive Vice President Human Res. Sr. VP Senior Vice President VP External Affairs &

Corporate Services Vice President Corporate Secretary & Chief Nuclear Officer Southern Company Nuclear Development J. G. WOLFE B. J. GEORGE A. F. THORNHILL W. D. DRINKARD Vogtle 3&4 Comptroller & Managing Atty. & Quality Assurance L. M. STINSON Nuclear Licensing Treasurer Manager Compliance Manager Manager Fleet Operations Support Bellefonte Vice President C. D. COLLINS B. E. HUNT C. H. PHILLIPS Supply Chain Nuclear Fuels Public Affairs Manager General Manager Manager P. R. BIZJAK J. M. GODFREY D. P. BURFORD W. L. Nuclear Fleet Security Safety & Health BURMEISTER Environmental Affairs Manager Manager and Emergency Plant Support Preparedness Manager Manager VACANT

• P. A. HURST H. R. Director A. HARRIS Corporate Concerns W. B. THIGPEN W. H. LEE Engineering Supervisor Security Emergency Planning Services Manager Supervisor/Access Supervisor Authorization G. K. McELROY Engineering Admin.

Services Manager J. R. JOHNSON T. E. TYNAN D. R. MADISON J. B. PAPPAS Vice President - Farley Vice President - Vogtle Vice President - Hatch Configuration Management Manager W. L. BARGERON T. L. YOUNGBLOOD S. M. DOUGLAS M. J. AJLUNI Plant Manager Site Support Plant Manager Site Support Manager Manager C. R. DEDRICKSON J. D. WILLIAMS Plant Manager Site Support Manager 0407

• SCS Employee Enclosure 2

Fleet Operations Support (proposed)

Fleet Ops VP Assistant Fleet Fleet Fleet Outage Fleet Chem / Fleet Security & Fleet Training &

Operations Maintenance /

Manager HP Manager EP Manager PI Manager Manager WC Manager Operations Maintenance/ NFS Outage Staff HP Staff *** Admin Asst Admin Asst

• CAPCO Staff WC Staff Coordinator Security EP Training Chem Staff

• PI Staff Supervisor Supervisor Supervisor *

• Transfer from Engineering

• • Transfer from Supply Chain

• • • Transfer from Environmental Security Staff EP Staff Instructors /

Staff * / **

Enclosure 2

Site Engineering (proposed)

New or Modified Org.

Site VP Plant Mgr. Engineering Mgr. *** Site Suppt. Mgr.

• • • Dotted line reporting to Chief Performance Admin. Asst Engineer Improvement

• EFIN

• Design Chg. (Corp)

• Mech/Civil (Corp) Principal Engineer -

• Elec/I &C (Corp)

Design Engineering Support Licensing **

• • Dotted line Modifications PMMS Nuc. Systems Programs reporting to Corporate Licensing

• Mech & Civil BOP Systems Elec./I & C Design

• Elec/I & C Equipment Reliability Design Enclosure 2

Topical Updates Enclosure 2

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 Enclosure 2

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 Enclosure 2

H3 pCi / L Fe b-03 1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 M

ay

-0 3

Au g-0 3 No v-03 M

ar

-0 4

Ju n-04 Se p-Tritium Sampling 04 Ja n-05 Ap r- 0 T12 5 Ju SAMPLE WELL T12 l- 0 5

O ct

-0 5

Fe b-06 M

ay

-0 6

Au g-0 6 De c-06 M

ar

-0 7

Ju n-07

Tritium Sampling Tritium Outfall Sample (Subsurface drain N008A) 1.00E+05 H3 pCi / L 1.00E+04 1.00E+03

/0 6 /0 6 /0 6 /0 6 /0 7 /0 7 /0 7 /0 7

/0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 05 07 09 11 01 03 05 07 1Y22N008A Enclosure 2

Tritium Sampling SAMPLE WELL (NW10) 1.70E+05 1.50E+05 1.30E+05 H3 pCi/ L 1.10E+05 9.00E+04 7.00E+04 5.00E+04 3.00E+04 1.00E+04 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 NW10 Enclosure 2

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 Enclosure 2

Alternative Source Term

• Full scope AST analysis submitted to NRC 8/29/2006

• Addresses control room inleakage concerns of Generic Letter 2003-01

• 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 Enclosure 2

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.)

Enclosure 2

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 Enclosure 2

Tool Box Enclosure 2

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 Enclosure 2

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 Enclosure 2

Planned Major Projects Enclosure 2

Unit 1 Main Transformer Replacement

• Unit 1 Main transformer replacement (2008)

- 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 Enclosure 2

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 Enclosure 2

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)

Enclosure 2

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 Enclosure 2

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 Enclosure 2

Completed Major Projects Enclosure 2

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 Enclosure 2

Unit 2 Generator Exciter Controls

• 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 Enclosure 2

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 Enclosure 2

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 Enclosure 2

Open Discussion Enclosure 2