ML20210B711

Provides Summary of 990701 Meeting with Sce&G in Atlanta, Georgia Re Recent Virgil C Summer Refueling Outage & Other Items of Interest.List of Meeting Attendees & Licensee Presentation Handouts Encl

ML20210B711
Person / Time
Site:	Summer
Issue date:	07/06/1999
From:	Haag R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
References
NUDOCS 9907230207
Download: ML20210B711 (13)

Text

• .

July 6,1999 i

South Carolina Electric & Gas Company ATTN: Mr. Gary J. Taylor Vice President, Nuclear Operations Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 29065

SUBJECT:

VIRGIL C. SUMMER NUCLEAR STATION REFUELING OUTAGE REVIEW MEETING

Dear Mr. Taylor:

This refers to the meeting conducted at your request at this office in Atlanta, Georgia on July 1,1999. The purpose of the meeting was to discuss the recent Virgil C. Summer refueling l outage and other items of interest. A list of attendees and presentation handouts are enclosed.

l At the meeting, South Carolina Electric & Gas (SCE&G) personnel presented an informational overview of activities conducted during Refueling Outage 11. SCE&G also discussed the evaluation and corrective actions for issues associated with Magne-Blast breakers and fuel assembly top nozzle failures.

l l In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10 Code of ,

! Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public l l Document Room. j l

l Should you have any questions concerning this meeting, please contact me at (404) 562-4500.

]

Sincerely,  !

Orig signed by Robert C. Haag Robert C. Haag, Chief j Reactor Projects Branch 5  !

Division of Reactor Projects

]

Docket No. 50-395 License No. NPF-12 l

Enclosures:

1. List of Meeting Attendees l

2. Licensee Presentation Handouts

\

cc w/encts: Continued see page 2 l 9907230207 990706 0FFICIAL C0PY DR ADOCK 0 g5

. 9 +s

SCE&G 2

' cc w/encls:

R. J. White Nuclear Coordinator Mail Code 802 S.C. Public Service Authority Virgil C. Summer Nuclear Station P. O. Box 88 -

Jenkinsville, SC 20065 1

J. B. Knotts, Jr., Esq.

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

and Environmental Control 2600 Bull Street Columbia, SC 29201 1

R. M. Fowlkes, Manager Operations (Mail Code 303)

South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station P. O. Box 88 Jenkinsville, SC 20065 April Rice, Manager

' Nuclear Licensing & Operating Experience (Mail Code 830) -

Virgil C. Summer Nuclear Station P. O. Box 88 -

Jenkinsville, SC 20065

=

I~ SCE&G 3 .

l Distribution w/ encl:

L. Plisco, Ril K. Cotton, NRR R. Alello, Ril .

P. Fillion, Ril -

l R. Gibbs, Ril L. Hayes, Rll G. Kuzo, Ril PUBLIC NRC Resident inspector U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville,'SC 29065 OFFICE p.,Ii '. O g p slGNATURE g ,

NAME 'KCoyne /

DATE 7/ Z. /99 7/ /99 7/ /99 7/ /99 7/ /99 7/ /99 7/ /99 COPY? N S) NO YES NO YES w3 YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\ summer mtg_0799.wpd 1

l i

LIST OF MEETING ATTENDEES Topic VIRGIL C. SUMMER NUCLEAR STATION REFUELING OUTAGE REVIEW Location: US Nuclear Regulatory Commission, Region 11 Office, Atlanta, Georgia Qgitt July 1,1999 NBC Luis Reyes Regional Administrator Loren Plisco Director, Division of Reactor Projects Bruce Mallett Director, Division of Reactor Safety Robert Haag Chief, Reactor Projects Branch 5 Kerry Landis Chief, Reactor Safety Engineering Branch Kevin Coyne Project Engineer Mark King Resident inspector Paul Fillion Reactor inspector South Carolina Electric 8, Gas Steve Byrne Plant Manager Alan Torres Outage Manager Jim Proper Supervisor, Nuclear Licensing and Operating Experience Sam Skidmore Engineer, Plant Support Engineering Richard Slone Engineer, Plant Support Engineering Enclosure 1

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_ ina IIn trh tfas Participants

\ Rs R, xmn 11 l'irsc%' + Steve Ilyrne Plant Manager

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j + Alan Torres OutageManager

+ Richard Slone PSE Engineer

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'G l '. F + Sam Skidmore PSE Engineer M -

v- + Jim Proper Supervisor, NL&OE lulu I.

j' . _ ' *

"=au m aa Agenda

+ Introduction and Overview

+ RecuelingOutage1, Refueling Outage 11

+ Magne-Illast llreakers

+ Fuel Assembly Top Nozzle issue Alan Torres

+ ClosingComments Outage Manager v .. a ..

Outline Outage Summary No Safety Significant Goal Met

+ RF-11 Goals Events No Lost Time 1LTA

+ 0utage Compan. son gec;a,ni,

+ Outage Success Outage Dose less than Actual Dose 115 Mr a Run zwi .un piume-y

+ Outage Challenges Planned Duration less Actual Duration 38

+ Major Activities Completed than 30 days days,10.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

'~'~ ~"""'" " *"'

+ Summa 7 Budget Met Budget Goal Lowed in plant heetary Enclosure 2

m .- n ..

V. C. Summer Outage History scn ona, .

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12. . ,,. 6 .

,,, - 97 D 80 5 I73 l,l,iIS ,,

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19841985198719881990 lbd119931994199619971999

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Odues S AG T.seu Outage Summary Outage Summary

+ 0utage Successes + 0utage Successes

- Use of Administrative Group for Safety, - Response to Challenges Fire Watche~ Confine Space, and FME - Control of Dose and Use of ALARA Plan Watches . RIIR single Train Cool Down

- Use of Training Staffs in Shop and + Use of Iq uipment I otators,151, snubbers Specific Project Tasks + Res Drain Down Plan

- Use of Other Graups Such as Licensing, - Outage Work Scope Control Chemistry, llR, E P, CDSV to Supplement Craft and ilP Activities

- cs . - cr a REFllEL OUTAGE TOTAL ACTIVITIES IDENTIFIED wg"m" ca"" -- Outage Summary MS + 0utage Successes

- Cor 4 ml of RCS Crud Burst sono ' /j e Chemistry Controls Change RCS pH 4000 < -

e**e--*~~

Hold Hydrogen Concentration Higher Longer for Increased $olubility se Followed FPRI Guidelinee 3000 Pump oper.:ssn Following Hydrogen Peroside Add 0, , , , , , , , , , , , , , , , ,

asuntiemuswnacuinas etant l- - RF.7 -+- RF-8 --.- RF RF -- RF 11 l

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, -. _ . _ . Outage Summary

+ Major Issues and Emergent Work

=-- - -

- TuelTransfer System Modifications-60 hrs

... . . . _ delay

- Fuel Top Nonle issues - 68 hrs delays

. . - 7,2 kV Breaker Issue - 18 hrs delay

)

_________ a A

l l

l m .. m .. :

Outage Summary Outage Summary

+MajorWork Activities + Modifications Completed

- 40". Eddy Current of 2 S/C'S - IIP Rotor Replacement

- 'A' RC1' Seal Replacement and Motor Swap - 10th Stage Extraction Check Valve

- Replacement of both 1E Batteries Replacement

. Inspection and Testing of 116 Snubbers - Removal of S/C Snubbers

- 49 LLRTs and 29 Movats Tests '

- A' D/G lleat Exchanger Replacement

- 154 ISI Examinations and 39 Erosion - FuelTransfer System

/ Corrosion Inspections m i. m_

Outage Summary Outage Summary

+ Modifications Completed + Challenges for the Future

- Amertap Upgrade

- Control Cost Through Increased Use of

- Cate Valve Pressure Locking Plant Staff and CDSV

- MSR Digital Controls Contractor Resources

- Main Transformer SupplementalCooling - Continue to Improve Schedule Review System Process

- Continue Improvements Such as llP ALARA Plan, Drain Down Plan

t m &a m .a Outage Summary Magne-Blast

+ Our Measuring Stick of Success Brggkgrs

. Safety Conscience Primary Focus

- No Nuclear Safety Fvents

. Conservative Decision Making Richard Slone

. l uel Top Nonte luue PSE Engineer

.7.2 kV Hreaker laue

- ALARA Awareness M aa G ka Overview VCS Medium Voltage

+ Ureakers recently overhauled by GE BregkgrS

+" Tripped free" on close attempt

+ Ceneral Electric Magne-Blast

+ Cotter pin not properly bent

+ Air Circuit Breakers

+ Latch check switch bracket hit by pin

+ Bracket interfered with switch paddle

+ ertical Wt on trip shaft +7.2kV

+ 500 MVA mha M ka Q ChargingPump Breaker m#

3

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2 j

+ Overhauled in May/ June '98

+ Site Tested and Installed June '98

+ Failed to close February'99

+ Various factory attempts to fix failed

+ Back to Atlanta Service Shop 0

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1 a .. m ..

Second BreakerFailure Second BreakerFailure

+ Post overhaul testing April 99 + Root cause of interference not clear

+ Same failure to close symptom + liigh speed photography

+ Latch Check Switch paddle + Cotter pin observed striking back of interference found latch check switch plate Re-inspection of1st Root Cause Breaker

+ Cotter pin on trip shaft not bent fully

+ Gap was also changing

+ Tab strikes back of switch, .

+ Cotter p.in also not properly bent moving it forward I

+ Ding marks where pin tabs hit

+ Closes required gap between bracket switch plate and trip shaft paddle j l

v m ..

Root Cause (cont.) Root Cause (cont.)

1

+ Result of no gap: + Breakers operated properly every

- Switch bracket bounces against paddle time with:

when attempting to close

- Paddle removed

- Paddle movement rotates trip shaf t

- Switch bracket removed

- Trip latch bounces off trip latch roller when breaker attempts to close

- Breaker" trips free" l

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= .. v ..

CorrectiveActions CorrectiveActions j

+ Latch Check Switches, brackets,

+ Electrical Maintenance procedures and paddles removed from VCS revised to re-verify switch breakers removal

- In-service as well as spare breakers i

. Nss no voit substauen fe,ans remain + Procurement documents / databases  !

- LCS function not required for VCs will be revised to address LCS I desig" I

+ Part 21 notification sent to NRC

• ""*'""'""P'"P'"

. Removes an unneccesary component from by VCS on 5-5-99 closing circuit - increased reliability

2. c a.

Summary

+ All NSR breakers reworked to a safer, more reliable condition Fuel Assembly Top

+ In-depth root cause NozzleIssue

+ Conservative decision making Sam Skidmore

- protected both trains PSE Engineer

+ Shared industry experience v .a m ..

Outline Problem Discovery

+ Problem Discovery + Simultaneously,on Offload Steps  !

. 23 A and 24 (4-13-99/2309):

+ Actions (Core Offload) - Difficulty Latching in Fuel Handling

+ Actions (Core Load) stag.

+ Safety Assessment - ["j"" I" "'"i " I" "' '

+ Vendor Root Cause - Visual Inspection in RB

+ Summay . One or More Gripper f ingers Disengaged

. Non-essential Personnel I cave RB e Recovery Ifforts Begin

. Suspend Attempts to Latth f uelin lilB l

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Gu Ga Problem Discovery Problem Discovery

+ Springs field Dowa With inc-600

+ Fuel Recovery: Screws

- Consult Manipulator Vendor Rep + Clamp (cover) Atta:hed by Separate

- Consult Additional Refueling Contractor Screw and Single 7 ack Weld resources

- Develop" Troubleshooting" Plan 5

- Plant Safety Review Comrnittee Approval .h

- Implement Plan. Fuel Safe (4-14-99/0810) l i

% ka %u Problem Discovery Actions: Core Offload 1

< j C:I / + Notifications:

m_ h:.

- NRC Resident (On site during discovery) 4*t .' - Other Affected Utilities

"*"""C*""*"

,,,: - Fuel Vendor 7)'i g - Refueling Services Vendor

- Manipulator Crane Vendor

- INPO Network ann ==w conman

- LER

a. m ..

Actions: Core Offload Actions: Core Offload

+ Spent Fuelllandling Tool

+ Manipulator Crane

- Remove Reference and Dummy Pins

- Verify Proper engagement function

- Visually Verify Latching (UW Camera)

. Adjunt regage t.imit switih eettins

. Wrify Cam Travel Vendor Video lnspection

. Test with Dummy Assembly 4 Crew Briefing

- Visually Verify Engagement (UW camera)

+ Resume Offload 4-16-99/0351 Tau M .a Actions: Core Offload Actions: Core Load

+ Step 65 Partial Engagement + Replace Top Nozzle on 28

+ VisualInspection Results Assemblies

- Problem Limited to Region M (" Mikes") - Standard Vendor Tooling, N cts and

+ 35" Mikes" out. 29 Remaining Procedurn

+ Lower Slack Cable Setting + Verify No Loose Parts

+ Brief Crew + Verify No Damage to 'S' Ifoles

+ Offload Complete 4-18-99/0722

m. w Actions: Core Load SafetyAssessment

+ All Parts Remain on Top Nozzle

+ Replace Manipulator Crane Gripper Assembly + Assembly Remains Engaged in ,

Alignment Pins

+ Restore SFliT Pins

+ RCCA Movement Unaffected

+ Core Load Uneventful

+ Accident Conditions Acceptable i

L

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VendorRoot Cause Summary

+ Ongoing: + Deliberateand Conservative

- Data conection Decision Making for Safe Offload

- Material.Investigati "

+ Thorough Assessment and

- ManufacturingInvestigation Reconstitution Effort to Ensure Safety of Cycle 12 Core

+ Notifications to Industry m.

I ClosingComments Steve Byrne  ;

Plant Manager 1 1

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