ML20196K977

Refers to Open Meeting Conducted at Licensee Request at NRC Region II Offices in Atlanta,Ga on 990315 Re Upcoming April 1999 Refueling Outage,Back Leakage Into Residual Heat Removal Sys & Licensee Position on Hazard Barriers

ML20196K977
Person / Time
Site:	Summer
Issue date:	03/25/1999
From:	Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 9904130225
Download: ML20196K977 (14)

Text

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March 25, 1999 South Carolina Electric & Gas Company ATTN: Mr. Gary J. Taylor.

Vice President, Nuclear Operations Virgil C. Suminer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065

SUBJECT:

MEETING

SUMMARY

- VIRGIL C. SUMMER NUCLEAR STATION

Dear Mr. Taylor:

This letter refers to the open meeting conducted at your request at the NRC Region ll office in Atlanta on March 15,1999. The meeting included discussions of the upcoming April 1999 refueling outage, the back leakage into the residual heat removal system, your position on hazard barriers (steam propagation barriers), the management rotation program, and recent performance observations. It is our opinion that this meeting was beneficial and provided a better understanding of the areas discussed.

In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questions conceming this letter, please let us knov..

i Sincerely, Orig signed by Robert 'C.

Haag Robert C. Haag, Chief Reactor Projects Branch 5 Division of Reactor Projects Docket No. 50-395 License No. NPF-12

Enclosures:

1. Presentation Slides

2. List of attendees I

0FFICIAL COPY

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l 9904130225 990325 PDR-ADOCK 05000395 P

PDR k

SCE&G cc:

R. J. White Nuclear Coordinator Mail Code 802 S.C. Public Service Authority Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 J. B. Knotts, Jr., Esq.

Winston and Strawn 1400 L Street, NW Washington, D. C. 20005-3502 Chairman Fairfield County Council P. O. Box 60 Winnsboro.' SC 29180 Virgil R. Autry, Director Radioactive Waste Management Bureau of Solid and Hazardous Waste Management-

. S. C. Department of Health and Environmental Control 2600 Bull Street Columbia, SC 29201 R. M. Fowikes, Manager Operations (Mail Code 303)-

Both Carolina Electric & Gas Company Virgil C Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 April Rice, Manager Nuclear Licensing & Operating Experience (Mail Code 830)

Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065 j

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SCE&G l

Diskibution:

M. Padovan, NRR P. Fillion, Ril R. Gibbs, Ril

' R. Alello, Ril G. Kuzo, Ril i

W. Stansberry, Ril

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Public.-

t NRC Resident !nspector, V. C. Summer Nuclear Station l

U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, SC 29065 I

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f Participants l

+ Steve Byrne Plant Manager

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+ Gary Williams Asoc. Mgr. Ops.

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+ Alan Torres OutageManager t'

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+ Brad Stokes Supervisor, PSE so rit ti (

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+ Tom Keckeisen PSE Engineer

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+ Don Jones NL&OE Engineer w,n i o -

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Agenda Refueling Outage 11 l

+ Introduction and Overview

+ RefuelingOutagell

+ RHR SystemIssues NN O # 08 i

+ Steam Propagation Barriers

+ Manager Rotation Program Ontage Manager

+ 19980verview

+ Summary and Closing Statements i

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^YoB SG Outline RF11 Objectives

+ 0utage Start

+ RF-11 Objectives

_ 3p,ii3,,gogi

+ Outage Process & Implementation

+ Maintain Continued Excellence in Enhancements

- Nuclear safety

+ Significant Work Scope

- Indu9rialSafety

+ Summary

- RadialogicalSafety

+ Business Objectives

- Durationy_30 Days

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Safety Safety

+ Nuclear Safety

+IndustrialSafety

- No Safety Significant Events

- No lost Time Accidents

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- Maintain Nuclear Safety Focus Increase Safety involvement in Planning Process

- No Reduced inventory Operations

-. Maintain Safety Over Schcdule Philosophy

- Stress Safety focus in All Meetings

- unphasise the Use of STAR i

2.

ma Outage Exposure Shutdown Chemistry

+ Projection of 90 Man Rem

+ Plan Developed

+ Contingency Plans

- Change RCS pil During Cycle

- Single Train RHRCool Down

- Hold H2 Concentration Higher Ionger for

- Flushing of System Hot Spots increased Solubility

- Follow Modified EPRIGuidelines

- Increase Use of Locator System

• slow Lrly Boratmn

- ISI tagging System

- Purnp Operation following Hydrogen

- Snubber Locator Maps Peroxide Shock T ao nEFUEL OUTAGE TOTAL ACTIVmES IDENTIFIED ' "***

Durtilon s

courAnisoncasen IWATED DW!/ap py

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+ Breaker to 13reaker Work Window

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2 Da} s

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- Mode 5 Decreasing to Mode 51nereasing Approximately 20 Days

- Turbine Work Window 26 Days C

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- Planned Duration Consistent with Workload u

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cm thatHb autas.gfre cutaet.Tattf

]-=- RF 7 -e RF4 -a-RF.4 ---RF 10 -RF-11 l

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RF-11 Enhancements SignificantWork

+1mproved Communication dChdU f is

+1ncrease Use of Window Managers i

+ Twelve Modifications Planned

+ Improved Control on Outage Scope

+ Eddy Current Testing of Two

+ Use of Formal Pre-outage Work S/G's Schedule

+ Seal Maintenance on 'A' RCP

, Improved Resource Sharing Within NSBU j

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Ss.gnsfs.cantWork

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Activities M=--

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+ Removal / Replacement of'A' D/G yygggg g [+g gggg Heat Exchangers

+ Replacement of High Pressure Turbine Rotor E E E,TJ *

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+ SnubberTesting EiaEEE5

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Summary

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+ Maintain Primary Focus j

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+ Do What is Right 3

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RHR SystemIssues Issue Description s s : a fi -

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Pi :.. - Fahd Ei n

n_n 0 0 Bcad Stokes

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Supervisor, Plant

-g Support Engineering

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InstalledEquipment RER ReliefValves ActionItems XVR-8864A,B and XVR8865

+ RHR Relief Valves

+ ECCS Check Valves

+ RF-11 Actions: none required

+ 0ther piping / valves

+ RF-12 Actions: Setpoint and leak rate testing of all three valves ECCS Check Valves ECCS Check Valves (cont)

+ RF-11 actions: Collect baseline data

+ Beyond RF-11:

on SI/RHR cold leg check valves.

1) T/S change for RCS boundary valve leakage to be consistent with ASME Section XI.

2) Investigate feasibility of a plant modification to account for RCS back leakage into the RHR header

ECCS Check Valves

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(cont.)

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I RF-11 actions do not include valve maintenance

+ RF-10 P1V testing indicated SAT results

+ Leakage rates have not increased 2.

m.

OtherPipingl Valves Design FlagIssues l

+ Improve Plant Personnel Knowledge

+ Action Regtured-None as piping g.,,;

analysis bottnds 600 pst operating j

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pressure & components rated for 2

.w i unii 600 psi

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+ Plant Design Basis j

- Address RiiR/S1 flow diagram l

- AddressCauseand Corrective Action i

G aa m ka SteamPropagation Outline BarrierDoors

+ Program History j

+ Region II Issues Tom Keckelsen,

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+ NRC / Industry Positions

• N RC ^'ti ""

PSE Engineer

+ SCE&G Position 1.w

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Program History Program History

+ No Current Established Regulatory

+ 1996 to 1998: Established AIT Based LCO or AIT for SPBs.

PSA Insights. Level of Control

+ Prior to 1988: No Specific S/B Based on Risk Significance.

Controls.

+ Current: SPBs not Allowed to be

+ 1988 to 1996: SPBs not Allowed to Removed from Service Without be Removed from Service Without Prior Approval. Doors Shall Only Prior Approval.5PB Doors allowed be Opened for Routine Ingress and to be Blocked Open for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Egress and to Perform Minor Door Maintenance.

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RegionIIIssues NRCPosition TIA 98-004 j

+ URI 50-365/98006-01

+ Lack of NRC Guidance Relating to an

- Unreviewed Safety Question acceptable AOT

- Acceptabihty of PSA

+ AOTs for SPUs Specified by the LCO

- Adequacy of Controls for Equipment the Barrieri'rotects.

+1f the SPB Protects Redundant Trains Perform an Operability Determination including a 50.50 Lyaluation.

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IndustryPosition IndustryPosition

+ An AIT for Non-TS whichisITS

+ SPBs are Design Features and Not TS and being removed from service Support Equipment. As such TS LCOs should be consistent with the Should Not Apply.

importance of the equipment to

+ Regulatory Guidance is Provided in:

safety.

_ ct 91 1s

+ Safety Evaluations per 50.59 are not

- NRC Insp. ManualChapter 9900

- NE19647 required for these activities if _

- RG 1.160 & NUM ARC 93-01 completed within the AIT.

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NRCActions Meetingwith NRR from 2/26/99 NRR Meeting NRC Attendees:

Tad Marsh Plant Systems Branc h Chief g

Tim l'ohch CI'SES Project Manager i "" "*""""

P"'""D""'""

+ Provide Guidance on the George H ubbard Plant Systems Branch Applicability of Tech Specs, Jim Tatum Plant Systems Branc h SeWeng Wong PSA Branch 10CFR50.65, and GL 91-18 to John Knom Electncal Engmeermg Branch BarrierImpairments.

Tom nergman Cen. issues and Env Branch Richard Bachmann OCC Bob Latta

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Meetingwith NRR SCE&GPosition thenwes and Othee Reprewnted.

+ SPBs Are Not Addressed in Tech.

South Carnhna Electric aad Ca*

S eCs.

P Tem Utihtie Electnc SYhItnYuIil$r'

+ SPBs Are Not Considered to be Tech.

Nebra ka Pubhc Power Distnct Spec. Support Equipment.

l'acific Cas and Dectric Southern Cahfornia Edison

+ SPUs A_rg Design Features.

["r$Tnc,gy

+ Existing Regulatory Guidance V

NE!

Sunnorts Ottr Previous Program.

Winvon and Strawn Bec htel General PhyWcs SCE&G Position SCE&G Position

+ NormalIngress & Egress through

+The TIA has imposed Undue and l

Plant Doors is witlun the Design inappropriate Constraints on the and Licensing Basis of the Plant.

Plant. Requires VCSNS to enter

+ Use of Doors for the Transportation Tech. Spec. 3.0.3, Defer of Material and/or Equipment in Maintenance Activities, or Request support of other Maintenance Prior NRC Approval for Norma!

Activities is not a Change to the RoutineMaintenance Activities.

Facility and Should Not Require a 50.59 Evaluation.

2.

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SCE&G Position ManagerRotation

+ This is a GenericIndustry issue Program and Needs to be Addressed by the Industry and the NRC in Order to Provide a Consistent and Clear StCUC 8,1frne, Approach.

+ An Acceptable AIT can be Plant Manager Established Consistent with the Importance of the Equipment to Safety.

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ManagerRotation 1998in Overview Program

((Mgr.

.preent PositLon I%w Position rugry IMgr Matenalsand John Newbiet t-r-,

Garu Williams P

u mm,., rat,..

Ron Clary Mgr. Quahey Mgr. 6%nt Life v

system.

E cen um AbOOCiNtO MONNhO Curta helde Mgr Maienal.and Mgr. Quahty System, Prwur ement Operatr.

weve Fur $tentwrg Mgr. Mamtenanse INl'O liwn-Ons

% rvken Gary W ilhams Aw. Mgr Mgr Mamtenance Operae nms Sert ves m.

1998in Overview 1998in Overview

+SALP1

<. Annual Exposure 12.5 Rem

+ 1NPO 1

- Ibsed on SRD (TLD Lower)

+ Safety Record

- 5th Best in Country 1998

- Reactor

+ Lowest Milicurie Discharge

. No Challenges

+ Opening of New VCS Wellness

- Industrial Cenier

. Completed 1998 with no Lost Time Accident

. Certificate from Department of Labor"one Million sale Work flours" Longest Run l

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OperatingPerformance Continuous oays on une s.

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+ Dr.ys on Line -432 (Cycle 11)

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tre 350

+ Capacity Factor YTD - 98%

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+ Electrical production - 11,424,170 E

2 mu hrs d

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i Ga ma Unplanned Capability Loss Factor CinemistryIndex

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I T as Summary and Closing Comments Steve Byrne 1

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p LIST OF ATTENDEES Nuclear Reaulatorv Commission L. Reyes, Regional Administrator, Ril L. Plisco, Director, Division of Reactor Projects (DRP), Ril R. Haag, Chief, Branch 5, DRP, Ril G. Belisle, Chief, Maintenance Bra't.ch, Division Reactor Safety (DRS), Ril M. Widmann, Senior Resident inspector, V. C. Summer Nuclear Statlan M. King, Resident inspector, V. C. Summer Nuclear Station W. Rogers, Senior Reactor Analysis, Ril L. Gamer, Senior Project Engincer, Branch 5, DRP, Ril P. Hopkins, Project Engineer, Branch 5, DRP, Rll J. Coley, Reactor inspector, Maintenance Branch, DRS, Rll South Carolina Electric and Gas Comoany S. Byrne, Plant Manager G. Williams, Associate Manager, Operations B. Stokes, Supervisor, Plant Support Engincering T. Keckelsen, Engineer, Plant Support Engineering D. Jones, Ucensing Engineer A. Torres, Outage Manager

,