ML032810137

Presentation Slides for Post-Refueling Outage Meeting

ML032810137
Person / Time
Site:	Summer
Issue date:	10/06/2003
From:	Landis K NRC/RGN-II/DRP/RPB5
To:	Byrne S South Carolina Electric & Gas Co
Shared Package
ML032810121	List: ML032810129 ML032810137
References
Download: ML032810137 (43)

Text

teve Byrne Senior VP, Nuclear Operations eff Archie General Manager, Nuclear Plant Operations Mike Fowlkes General Manager, Engineering Services on Clary Manager, Nuclear Licensing lan Torres Outage Manager erry Weatherford RHR Retrofit Project Lead

• VCS Organization Changes Steve Byrne

• RF-14 Alan Torres

• Reactor Vessel ISI Ron Clary

• RHR Pump Jerry Weatherford

V. C. Summer Nuclear Station Management Organizational Changes Steve Byrne Sr. Vice President Nuclear Operations Division Jeff Archie Dave Lavigne Mike Fowlkes Ken Nettles Bob Waselus General Manager General Manager General Manager General Manager Manager uclear Plant Operations Org. Effectiveness Engineering Services Nuclear Support Services Stragetic Plan. & Dev.

Dan Gatlin Terry Matlosz John Nesbitt Ron Clary Manager Manager Manager Manager Operations Org. Dev. & Perf. Materials & Procurement Nuclear Licensing Frank Bacon Chris Caston Wayne Stuart Steve Furstenberg Manager Team Leader Manager Manager Chemistry Document Control & Records Plant Support Engineering Nuclear Training Shaun Zarandi TBD Mel Browne Manager Manager Manager Maintenance Services Design Engineering Quality Systems L. A. Blue Mark Findlay Manager Manager Health Physics Nuclear Protection Services Alan Torres Manager Planning / Outage

• Human Performance

• Corrective Action Program

• Root Cause Analysis

• Operating Experience

• Trend Analysis

• Self Assessments

• Benchmarking

General Overview

• Our Number 1 Goal

- Safety

• Nuclear

• Radiological

• Industrial

• Duration - 36 days

• Dose goal - To be determined after source term

• Emphasize human performance

• Modifications

- RHR pump seal

- Complete RHR miniflow switch relocation

- RHR vent addition

- CW pump trip circuitry

- Feedwater heater level transmitter logic change

- Gravity boration flow path

• PRA review indicates no change in CDF

• Reactor Vessel

- Ten Year ISI

- Bare metal visual inspections - Head/BMI

• Low pressure turbine maintenance

• ILRT of the Reactor Building

• A Train electrical maintenance

• B CCW heat exchanger repair and coating

• C RCP

- Seal replacement

- Motor replacement

teve Byrne Senior VP, Nuclear Operations eff Archie General Manager, Nuclear Plant Operations Mike Fowlkes General Manager, Engineering Services on Clary Manager, Nuclear Licensing lan Torres Outage Manager erry Weatherford RHR Retrofit Project Lead

• VCS Organization Changes Steve Byrne

• RF-14 Alan Torres

• Reactor Vessel ISI Ron Clary

• RHR Pump Jerry Weatherford

V. C. Summer Nuclear Station Management Organizational Changes Steve Byrne Sr. Vice President Nuclear Operations Division Jeff Archie Dave Lavigne Mike Fowlkes Ken Nettles Bob Waselus General Manager General Manager General Manager General Manager Manager uclear Plant Operations Org. Effectiveness Engineering Services Nuclear Support Services Stragetic Plan. & Dev.

Dan Gatlin Terry Matlosz John Nesbitt Ron Clary Manager Manager Manager Manager Operations Org. Dev. & Perf. Materials & Procurement Nuclear Licensing Frank Bacon Chris Caston Wayne Stuart Steve Furstenberg Manager Team Leader Manager Manager Chemistry Document Control & Records Plant Support Engineering Nuclear Training Shaun Zarandi TBD Mel Browne Manager Manager Manager Maintenance Services Design Engineering Quality Systems L. A. Blue Mark Findlay Manager Manager Health Physics Nuclear Protection Services Alan Torres Manager Planning / Outage

• Human Performance

• Corrective Action Program

• Root Cause Analysis

• Operating Experience

• Trend Analysis

• Self Assessments

• Benchmarking

• Reactor Vessel

- Ten Year ISI

- Bare metal visual inspections - Head/BMI

• Low pressure turbine maintenance

• ILRT of the Reactor Building

• A Train electrical maintenance

• B CCW heat exchanger repair and coating

• C RCP

- Seal replacement

- Motor replacement

• ILRT

• Finding the fuel leak

• Coating the B CCW heat exchanger

• Timing of inspection of bottom of Reactor Vessel

• V. C. Summer currently in 2nd ISI Interval

- January 1, 1994 through December 31, 2003

- RF-14 scheduled October 11 through November 15, 2003

• 10 year ISI

• Reactor Vessel *

• Cold Legs*

• Hot Legs

• Core barrel must be removed to perform

• Fully qualified for detection and length sizing of circumferential flaws

• Procedure limitation in the detection of axial flaws

• Limited qualifications for depth sizing of flaws

- Demonstrated to size within 7.38 % RMSP of the wall thickness at the location of the flaw

• UT

- Circumferential and axial directions

• ET

• Remote Enhanced Visual

• Surface Profile Mapping

Detected Circ Flaw Detected Axial Flaw Length Size - UT Length Size - ET Depth Size - UT Difference between actual First Option - UT vendor RMS sizing error and Difference between actual vendor 0.125 RMS will be added to the RMS sizing error and 0.125 RMS through-wall size before will be added to the through-wall assessment. size before assessment.

Second Option -

Conservative depth assumption based on ET measured length if not detected by UT.

RF-12 RF-13 RF-13 UT RF-12 Circ.

Length Length Length /

Loop Leg Location/

(Eddy (Eddy Depth Orientation Current) Current)

A Cold 326/circ. 0.5 (N335)

B Hot 35/circ. 0.6 0.5 (N265) 200.8/axial** 0.25 0.5

• 0.625 /

0.317 348/axial 0.25 0.25 B Cold No (N215) Indications C Hot 309/circ.** 0.5 0.5 0.375 /

(N145) 0.11 C Cold 200/circ. 0.5 (N95)

• Attributed to improved detection and sizing capability

• • Indications also defined by UT examination. Evaluated and accepted to IWB 3600.

• Identify and characterize the previously identified indications

• If all previously identified indications are not found - then supplemental NDE must be performed

• Discuss actual inspection results with NRR

• If the results demonstrate no crack growth:

- Restart without the need for further (beyond RF-14)

NRC staff approval

- Complete three successive examinations of the welds in accordance with ASME Code requirements

- Provide highlighted reference in cover letter of 90 day ISI report on Hot Leg exam results

Results of RF-14 examinations will drive NRC staffs expectations for future NDE

- Demonstration that current examination methods accurately characterize indications (may not need supplemental NDE)

- Surface indication results show not a flaw (may not need supplement NDE)

- Inconclusive surface indication results (may need supplement NDE)

Staff evaluation is required If the condition is safe for the duration of the next outage, then the licensee will be allowed to restart for one cycle, subject to new inspection requirements

• VC Summer and NRR agreed at the 9-10-03 meeting that the direction being taken by VC Summer in RF-14 is appropriate.

F-14 RHR Retro Fit Modification VC SUMMER Westinghouse FlowServe

• Scope of modification A RHR Pump

- Support stand

- Spacer coupling

- Upper & lower hub Assembly

• Project duration 5 days

• ALARA estimate 2.75 REM

Motor 47 inches Approximately 6000 lbs Seal cooler Seal cooler Stuffing Box 12 inches X 41 inches Impeller 10 inches

Bearing Housing 18 by 18 seal opening Support stand with an 18 X 18 opening

Upper (Driver)

Hub Assembly Lower (Pump)

Hub Assembly