NRC Region IIIFebruary 21, 2001

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Presentation AgendaNMC Commitment to SGR

Plant Ownership of SGR

Project Overview

SG Design Change

RSG Safety Analysis

RSG Supply and Safe End Weld

RSG Installation

RP and OSG Disposal

Quality Assurance

Closing Remarks

Questions and Discussion

Mark Reddemann, Site VP

Kyle Hoops, Plant Manager

Jeff Jensen, Project Manager

George Bieberbach, SG Design

John Holly, Engineering

Guy Holmes, Fabrication

Kim Hull, Installation Manager

Brad Gauger, Radiation Protection

Brian Koehler, QA Manager

Mark Reddemann, Site VP

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", Key Lesson Learned

"* Success Built on Uniform Site Purpose

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m SGR Team Reports to PlantManager

m Integrated SGR Outage Schedulem Dedicated KNPP Shift Manager to

SGR Planningm Integrated KNPP and Bechtel

Processes

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KNPP

Project Management

Contract Management

Safety Analysis

OSG Disposal

Radiation Protection

Design Change Process

Quality Programs

Industry SGR Experts

RSG Design

RSG Fabrication

RSG Installation

Quality Programs

Welding Oversight

Licensing

8 Comittd toNucerEceln•8

Westinghouse

Ansaldo

Bechtel

Duratek

RSG Design,Licensing & Safety Analysis

RSG Fabrication

RSG Installation

OSG Disposal

Project Management Design Change Process Non-LOCA Analysis Contract Mgmt Radiation Protection Licensing QA & QC Resolution of Non-Conformances

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KNPP

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. Maximize Personnel Safety

. First Time Quality

m Minimize Radiation Exposure

. Minimize SGR Outage Duration

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"m Use Industry Lessons Learned

"m Ensure KNPP Retains Knowledge of SGRP

11 Commi tEyce

* Readiness is the assurance that the strategy can be followed to achieve SGRP goals & objectives - Team Development - Employ Industry Expertise - Independent Assessment

- Site Access Plan

12 Committed to Nucl e 0"

* Configuration Control

"* Receipt Inspection

"* Questioning Attitude

13 CommnItte d to Nuctea r,6 ceý , c. ' lI

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Key Improvements

Refurbished Upper Package

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Replaced Lower Package

Replacement SG Model 54F

Steam Flow Limiter Separator Mods Feedwater Ring

Alloy 690 Tubes Stainless Support Plates Hydraulic Tube Expansion 3 Sets of U-bend Supports

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Plant Change ImpactStakeholders

KNPP %4 Acceptability Basis

Licensing Report

Acceptability Basis Changes to USAR Certified Design Report Changes to USA c Thermal/Hydraulic Report Changes to Tech Specs Moisture Carry-Over Report USQ for Analysis Methods

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1ImpactPrimary Loop Flow Rate Increase (+6%) None, remains below MDFPrimary Volume/Mass Change(+3%)

Secondary Volume/Mass Change (-2%)

Circulation Ratio(2.71 to 4.28)

Constant Water Level Program

Only minor changes during load changes

Minor simplification

These changes have been fully evaluated and all results are within acceptance criteria

17 ~~Commith.ted to NuclearExclec

Change

Plant Operation Impacts are Minimal

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10 Safety Evaluations were Completed for Mod 1 to Assure Sufficient Evaluation Detail -Overall

-Materials -Design Feature -Thermal Hydraulic -Component/Structural -Analysis Methods -Non LOCA -LOCA -Radiological -Systems/Components 1eNu a18 1

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m Tech Spec Changes- TS 3.1 .d.2 - RCS Min Flow Rate 0- Returned to Zero Plugging Value

- TS 3.10.m - Primary to SecondaryLeak Rate Reduced from 500gpd to 150gpd

- TS 5.1 -Site Previous Owner, deleted

- Steam Generator Tube Repair- Support

Crevice- Voltage

Criteria

Plate and Tubesheet Plugging Criteria Based TSP Repair

Eliminated, not applicableto RSG Design

0 USQ- RETRAN3D- GOTHIC 19 Commtted toNuclearExcIe j,

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I Summary/Conclusions

* In terms of plant operations, there are only minor impacts

+ All changes and their impact on the plant have beenreviewed and assessed

+ Mod 1 was divided into 10 Safety Evaluations to assurethoroughness and completeness.

* There are only a few required Tech Spec changescaused by the RSG

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m Design Basis Accidents, NSSSm Split between Westinghouse and

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. KNPP Scope- USAR Chapter 14 Non-LOCA

Accidents

- MSLB Accident inside and outsidecontainment

- LTOP Analysis Comm-tted to u Exc" "-n" •22

* Westinghouse Scope - USAR Chapter 14 LOCA

+ Large Break LOCA

+ Small Break LOCA + LOCA containment response

+ LOCA hydraulic forces

- NSSS components/systems/controls

- RCS Loop piping & support systems - Radiological - RSG Component T/H and Structural

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"* Consistent Methods for Analyses "* Upgrade to Methodology

- RETRAN 3D and GOTHIC

"* KNPP Experts Used SEnsured accurate analysis inputs

- Reviewed results/licensing report

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"- Reactor Core Physics Parameters "* Reactor Power Level "* Reactor Temperature

"* Fuel Design "* Engineered Safeguards Systems

"- Plant Setpoints

25 ComItted.to.Nuclar •

m RSG Component Design andPerformance

, NSSS Thermal Hydraulics+e.g., RCS flow, 10% SGTP

. SG Programmed Level vs. Power- Constant at 44%

. SG Outlet Nozzle Flow Restrictor

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m SGR Change was Analyzed- Design Basis Accidents/Transients

and NSSS

- All Acceptance Criteria are Satisfied- Verified plant operation withindesign

m KNPPand licensing basis

is Positioned for the Future

m Plant Change was Minimized27 Con imltted to Nuclear ExceIIe���

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"* Westinghouse- Design and Engineering - Model 54F

"* Ansaldo - Manufacturing and Procurement

"* KNPP - Configuration Control, Surveillance of Manufacturing

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m Welds on RSG- Passed ASME III RT- One Weld required repair, ASME Xl UT

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m Weld will be performed on site by PCI

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Tube End Welds

-ITube End Welding

36 ~Comm itted to Nuclear Excetiencte P36l

TBs Inssalled. End Caps ready to Weld to Retaining Rings; NMC 37 Committed to Nuclear Excellence

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Channel Head to

Tube Sheet Weld

Post Weld Heat Treatment

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m Welding in RSGs- Lessons Learned- Welder training & certification- Weld material and process control

m KNPP Control of Welding- Ownership

- Review

- OversightCommitted to Nuclear Excell eni~e45

* Summary - Replacement Similar to Original

- Rigorous Control of Welding

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NMC 47 Committed to Nuclear Excellence

- KNPP Control of Radiation Protection - Expanded Organization under KNPP - Rad Pro Plan & Interface Plan - Using KNPP Procedures - Detailed ALARA Plans for critical work

48 Committed to Nuclear Excellenciz

"* Augmented Access Control Facility - CAF (containment access facility)

"* New Decontamination Facility

49 Committed to Nuclear Exelldnoe

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"- Approximately 57,000 lbs of Lead Shielding

"* Closed Circuit TV "* Pipe End Decon and Shielding "* SG Secondary Water Level "* RP Training with Mockups

50 Committed to Nuclear Exellenc6 .

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m Radiography m RCS Pipe Cut and Decon m Moving Original Steam Generators m Increase in Personnel - Doubling

of Site Staff

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m Duratek- Performs work under contract

m Move OSGs- KNPP to Port by Transporter- Kewaunee to Memphis by Barge- Port to Duratek by Transporter

NMC Committed to Nuclear Excelene 1.52

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Nmc 53 ComminItted tO Nuclear Excienc*0~

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m KNPP Similar to Maine Yankee - NRC Generic Letter 96-07 -49 CFR 173.403 Exemption

+ surface contamination demonstration

49 CFR 173.427(b)(1) Exemption + packaging requirements

NMC 55 Committed to Nuclear Exc'ellencim ~

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m Duratek will:- Decontaminate

+ SIVAblast Grit

- Divide OSG into Sections- Metal Melt

. Shielding Blocks

- Free Release of Clean Metal

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57 Committed to Nuclear Excellence~P

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"m Quality Oversight - Early in project - Dedicated QA staff

"* Specific QA Plan for SGRP

58 Committed to Nuclear Excellence •W

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m Vendor Evaluation

m Audits & Surveillances - Pensacola - RSG Design - Monroeville - Licensing and Safety Analysis - Waltz Mills - Steam Dome Design

m Technical Specialists Used

59 Committed to Nuclear ExceIlncL.

m Vendor Selection

m Supplier Qualification - 1996- Joint Utility Audit (APS and BG&E)

m Re-Evaluation Audit - 1999- APS lead

m Fabrication at Ansaldo- Including major sub-suppliers

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m Supplier Audit Evaluation (initial)m NUPIC Audit- 1999

- KNPP Lead on Joint Utility Effort

m Surveillances- Bechtel and Sub-suppliers

.:Westinghouse, Colonial Machine

61 ~Committed to Nuclear Excellenc ~

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m Internal Audit of SGRPm Document Control Auditm ECT Surveillance

m Safe-End Surveillance at PCIm Readiness Review (Planned). SGRP Surveillances (on-going)

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"- NMC Committed to SGRP

"* Operating Plant Integrated with SGR

"* SGR Project Focused on Excellence

"* Questions and Discussion

63 Committed to Nuclear* Exc 4eften~P