ML20129K379

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Summary of 961016 Meeting W/Dpc at Plant Re Ongoing Current Licensing Issues & Safety Initiatives at Three Nuclear Stations.Meeting Attendees,Agenda & Handouts Encl
ML20129K379
Person / Time
Site: Oconee, Mcguire, Catawba, McGuire  Duke Energy icon.png
Issue date: 11/21/1996
From: Nerses V
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9611220142
Download: ML20129K379 (45)
v • d • e


Text

.-.

November 21, 1996 l

l LICENSEE:

Duke Power Company FACILITIES:

Oconee Nuclear Station, Units 1, 2, and 3 McGuire Nuclear Station, Units 1 & 2 l

Catawba Nuclear Station, Units 1 & 2

SUBJECT:

SUMMARY

OF MEETING WITH DUKE POWER COMPANY ON LICENSING ISSUES AND SAFETY INITIATIVES I

On October 16, 1996, the NRC staff (NRR Projects, Region II and resident inspectors) met with representatives of Duke Power Company (DPC) at the McGuire Nuclear Station to discuss ongoing current licensing issues and safety initiatives at the three DPC nuclear stations. Meeting attendees are listed in Enclosure 1.

The meeting agenda is included in Enclosure 2 and meeting handouts are provided in Enclosure 3.

Original signed by:

Victor Nerses, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation 4

Docket Nos. 50-269, 50-270, 50-287, 50-369, 50-370, 50-413, 50-414

-cc w/ enc 1:

See next page Distribution w/ enclosures 1. 2. 3:

Distribution w/ enclosure 1 only HARD COPY E-MAIL

, Docket File,

FMiraglia/AThadani DLaBarge PUBLIC RZimmerman PTam PD 11-2 Rdg.

SVarga LBerry OGC JZwolinski EJordan (JKR)

ACRS HBerkow SRudisail s

VNerses LWert GTracy, RII EMerschoff, RII

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l To receive a copy of this document, indicate in the box:

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attachment /encloture "E" = Copy yith attachment / enclosure "N" = Pg copy l

OFFICE PM:Pff M,

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NUCLEAR REGULATORY COMMISSION o

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November 21, 1996 d

I LICENSEE:

Duke Power Company FACILITIES:

Oconee Nuclear Station, Units 1, 2, and 3 McGuire Nuclear Station, Units 1 & 2 Catawba Nuclear Station, Units 1 & 2

SUBJECT:

SUMMARY

OF MEETING WITH DUKE POWER COMPANY ON LICENSING i

ISSUES AND SAFETY INITIATIVES On October 16, 1996, the NRC staff (NRR Projects, Region II and resident inspectors) met with representatives of Duke Power Company (DPC) at the McGuire Nuclear Station to discuss ongoing current licensing issues and safety initiatives at the three DPC nuclear stations. Meeting attendees are listed in Enclosure 1.

The meeting agenda is included in Enclosure 2 and meeting handouts are provided in Enclosure 3.

s Victor Nerses, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Decket Nos. 50-269, 50-270, 50-287, 50-369, 50-370, 50-413, 50-414 cc w/ enc 1: See next page t

4 4

I t

ATTENDEE LIST DCTOBER 16. 1996. DUKE POWER COMPANY & NRC INTERFACE MEETING M8lE ORGANIZATION V. Nerses NRC/NRR/PD II-2/ Project Mgr-McGuire H. Berkow NRC/NRR/PD II-2 Director i

l D. LaBarge NRC/NRR/PD II-2/ Project Manager-Oconee i

P. Tam NRC/NRR/PD II-2/ Project Manager-Catawba S. Rudisail NRC/RII/DRP l

R. Freudenberger NRC/ SRI / Catawba l

L. Wert NRC/RII/ Acting Branch Chief /DRP Jim Snyder MNS/ Reg. Compliance Manager l

Mano Nazar MNS/ Maintenance Superintendent Jack Boyle MNS/CE&N Engr. Mgr.

l T. C. McHeekin VP/MNS l

M. S. Kitlan, Jr.

CNS/ Reg. Compl. Manager l

Bruce Anderson Information Management l

Jeff Forbes CNS/ Engr. Mgr.

Ernie Hite NG0/ Acting Engineering Support Mgr.

l Dennis Murdock ESS/ Manager, Major Projects l

Ed Burchfield ONS/ Reg. Comp. Mgr.

Scott Shaeffer NRC/RII/McGuire SRI Marvin Sykes NRC-McGuire Pete Herran DPCo - McGuire Mgr. Eng.

John Thrasher DPC-McGuire Maint. Engr. Mgr.

l Keith Thomas DPC-McGuire - Work Control Supt.

Skip Copp DPC-Mgr. Muc. Reg. Affairs - G0 Mike Tuckman DPC-Sr. VP Bill Pitesa DPC-McGuire - SRG Mgr.

I Mac Gerrie DPC-Station Mgr.

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DUKE POWER - NRC 10/16/96 INTERFACE MEETING AGENDA Time Topic Speaker 0800 Opening Remarks /DPC Mike Tuckman Ted McMeekin i

Opening Remarks /NRC Herb Berkow 4

0810 SG Replacement Project Wayne Hallman Robert Sharpe 0840 UFSAR Activities Skip Copp John Thrasher 0920 Identification of UFSAR Compliance Herb Berkow Changes in Proposed Amendments (Sensitivity in Identifying USQ) i 0955 P!:an Issues List (Clarifications)

Scott Shaeffer 1020 BREAK 1035 Self-assessment Process Mac Geddie i105 EP/ Implementing Procedures Peter Tam Handling Privacy Issues 1115 ISTS Status Skip Copp 1145 OEDB Database Demo Bill Matthews 1215 Closing Remarks Duke Power Mike Tuckman Ted McMeekin NRC Herb Berkow 1230 Lunch ENCLOSURE 2

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ENCLOSURE 3

EDEIll Duke Power Company i

McGuire Nuclear Station t

Steam Generator Replacement Project i

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Duke Power / NRC Interface Meeting l

l October 16,1996 l

Steam GeneratorReplacementProject i

EDEIll Duke Power Company

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Agenda Project Overview Wayne Hallman j

Catawba Outage Video Robert Sharpe Catawba Outage Robert Sharpe j

McGuire Status Robert Sharpe i

l Steam GeneratorReplacementProject j

WM51 Catawba Outage Successes June 12 - October 4 = 113.35 days Breaker to Breaker Outage Exposure (168 REM) Lowest Ever (per S/G) in U. d.

i S/G Fitup and Narrow Groove Welding l

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Containment Purge Necessary for Heatup No LER's i

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7 Recordable Injuries, None Serious l

i Housekeeping i

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On-Site Manufacturing Activities l

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M Mill RSG OPERATING PERFORMANCE

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. Responsive Level Control

. Less Shrink and Swell During Transients j

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. Operations and Engineering Very Pleased with RSG's I

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i EDER Operating Parameters Preliminary System Operating Parameters MNS CNS1 Old (expected)

(actual)

(W S/Gs)

  • T-Hot (F) 614 613 619
  • T-Cold (F) 557 554 559
  • RCS Flow (GPM) 400k 399k 386k SG Oper Lyl(%)

39 - 65 39 - 65 38 - 66.5 i

  • Pzr Lvl(%)

25 - 55 25 - 55 25 - 60 f

  • Fdw Temp (F) 440 440 435 - 440

. Steam Flow (Mlbm/hr) 3.79 3.79 3.79 l

  • Steam Press (psia) 1020 997 930 - 990 i

i SG Moisture Carryover j

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0.1 0.1 0.25 l

Steam GeneratorReplacementProject i

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EDER McGuire Status i

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. Five RSG's on Site; Last Three to Ship in December

. RSG Nozzle Preps Underway j

. Unit 1 Outage to Start January 31,1997

. Unit 2 Outage to Start September 16,1997

. Engineering Work for Both Outages Nearing Completion

. Retired S/G Storage Facility Complete

. Crane Erection Has Begun l

Steam GeneratorReplacementProject

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i-UFSARINITIATIVES 1

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+ Process Improvement 4

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+ Accuracy Review 1

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+ UFSAR Working Group l

NGD UFSAR Working Group Formed i

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Existing Guidance / Directives

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Interfacing Directives Reviewed l

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i Feedback From UFSAR Contributors

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+ Results Nuclear System Directive (NSD) Written for UFSAR Update Process l

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Interfacing NSDs to be Revised

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Self-Assessments Planned

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UFSAR ACCURACY REVIEW i

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+ COMPLETED:

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+ UFSAR " Read Through" by SG Replacement Staff (MNS/CNS) j l

+ Chapter 15, Accident Analysis, Review to Support SGRP l

+ Accuracy Review for Current Updates (ONS/MNS)

+ Radiation Protection Accuracy Review (CNS)

+ PLANNED:

+ NEIInitiative i

+ Engineering Pilot UFSAR Review of Systems (MNS/CNS/ONS) 4 Nb Nnt Slide 6 I

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ENGINEERING PILOT UFSAR REVIEW I

+ NEI 96-05 Guidelines

+ Two (2) Catawba Safety Systems

+ FW (Refueling Water) and VE (Annulus Ventilation) i

+ Two (2) McGuire Safety Systems j

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+ KC (Component Cooling) and NS (Containment Spray) j l

+ Two (2) Catawba Non-Safety Systems

+ EHM (Hydrogen Mitigation) and EPA (SATA /SATB)

+ Two (2) McGuire Non-Safety Systems l

+ EHM (Hydrogen Mitigation) and RC (Condenser Cooling -Turbine j

Flood) i

+ Pilot Results Expected First Quarter of 1997 ENEm"wr Slide 7

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McGUIRE SELF ASSESSMENT PROGRAM l

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+ We believe that a key to contmuous improvement is a l

strong Self Assessment Program. Therefore, we are i

attacking self assessment on multiple levels.

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+ Levels of self assessment

+ Individual

+ Group

+ Site (Safety Review Group)

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+ Business Excellence Steering Team (BEST) Sponsored (three j

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+ ManagementObservationProgram l

+ Corporate - Regulatory and Performance i

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i INDIVIDUAL i**

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+ LevelISafety Assessment Questioning Attitude and STAR

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+ Risk Assessment Pre-Job Briefings j

+

+ Field Involvement Post Job Critiques

+

Maintenance Job Delays i

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Work Window Manager Critiques

+

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GROUPASSESSMENTS i

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+ Self Assessments performed by site groups l

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+ NSD--607 " Self Assessments" provide a stmeture for:

. Planmng - provides guidance to assist in selecting assessment opportunities

. Preparation - develop clear objectives for the assessment

. Implementation - drive the assessment to look at "why" problems exist J

. Action Tracking - requires findings and recommendations to be documented in PIP i

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$8 SRGASSESSMENTS 1

The Safety Review Group (SRG) provides the site with an

+

independent review of programs and processes.

+ Assessments developed from:

. Management Requests

. Industry Concerns t

. Problem Investigation Process (PIP) Trending

+ Performed by:

+ Individuals j

. Teams

. Augmented by: Site, Corporate, Industry Experts l

+ Corrective Actions documented in PIP

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Quick Hitters" observe activities (instead of processes or programs) 4 i

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MANAGEMENTOBSERVATIONS l

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+ Site and Corporate Management involved

+ Managers observe activities outside normal working group t

+ Reinforces Management Expectations I

+ Feedback to Management of Observed Activity t

Benefits the observing manager and the observed work group

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+ Regulatory Audits - routine audits required by commitment i

+ CFR Requirements

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+ Performance Assessments

+ Assessments similar to site SRG but at a corporate level

+ Benefit of being multi-site

+ Teams have site or industry expert involvement

+ Corrective actions communicated weekly 3

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1996 ASSESSMENT PROGRESS i

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IN-PROGRESS YTD COMPLETE l

Inplant Reviews 11 35 l

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Group Assessments 62 121 Management Observation N/A 111 l

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Regulatory Audits 3

5 Performance Assessments 2

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comprehensive use of Self-Assessment, and i

strengthened use of Operating Experience to identify and achieve improvements "

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Airlock Door operation, maintenance a-d ownership

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+ Operations Test Group Training Program improvements Fuel Handling improvements to include PPE use, communication,

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and FME precautions

+ New and improved Work Around Process j

Contractor In-processing improvements

+

4 Improved Equipment Receipt Inspection Process i

+

Discontinued use of house keeping tags on Out of Service equipment

+

Improvements to Block Tag Out

+

Identified low level DBD, FSAR, and procedure discrepancies

+

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FOR CONTINUOUS IMPROVEMENT i

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+ McGuire and Catawba Standard Technical Specifications

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Integrated Review

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Submittal to NRC

+ Oconee

+ October,1997 l

+ McGuire and Catawba

+ March,1997 l

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i 1

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t i

n Submittal to NRC t

+ Oconee

+ November,1997 i

i

+ McGuire and Catawba 1

i

+ March,1997 l

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4

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_ -. _.. -. _ _ _ _ _ _. _. _ _ _ _ _... _ _ _ _. - - _. ~ - _ _ _ - _ _ _ - - _. - - - -. _ _ _ - - _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ - _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - - _ _ - _ - - _ _. _ _ - - -, _ _ _ _, _ _ _ _ _ _ _,

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)

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l OPERATING EXPERIENCE l

l DATABASE i

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E st Nr Slide 22 ow m

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i-OPERATINGEXPERIENCE DATABASE 7

i A " Windows" Based Client / Server Application that J

provides for the Identification, Evaluation, and Retrieval of Industry and Duke Power Internal

{

Operating Experience Information from the Desktop.

I I

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EEen m

Slide 23

- - - -l

i CONTAINS OVER 11,000 i

INDUSTRYDOCUMENTS 4

l

+ INPO Documents - OE, SER, SOER, etc.

+ NRC Documents - AL, GL, IN, etc.

+ Vendor Documents and Industry Good Practices.

Access to Duke's Internal Operating Information is 1

+

Available Through Any One or All Four PIP Databases.

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l mYdEmm Slide 24 l

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I OPERATINGEXPERIENCE i

CULTURE 7

i

+ Significant Information is Communicated Daily for Awareness.

+ Extensively Used in Resolution of Plant Challenges.

+ Routine Part of Training.

+ Internal Experiences Documented for Later Reference.

+ Internal Experiences are Shared With the Industry i

l i

rassNb Slide 25 wr

4 i

i SUCCESS STORIES i

Define High Risk Fire Areas Based on Industry j

+

Experience to Develop Drill Scenarios and Future-Training.

Identification of Replacement Surge Capacitors for

+

Reactor Coolant Pumps.

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+ Replacement of the Main Generator Fuse / Diode Assembly based on Industry Experience.

+ An Emergency Tech Spec Change Was Made at ONS i

based on Industry Experience.

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Slide 26 I

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