ML20137X934

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Summary of 970403 Meeting W/Licensee to Discuss plant-specific Thermo-Lag Corrective Action Programs. List of Attendees & Handouts Encl
ML20137X934
Person / Time
Site: Davis Besse 
Issue date: 04/16/1997
From: Hansen A
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
NUDOCS 9704220256
Download: ML20137X934 (26)


Text

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UNITED STATES s

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j NUCLEAR REGULATORY COMMISSION g

WASHINGTON, D.C. 20056 0001 o% *****,/

& J'fS April 16, 1997

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LICENSEE:

Toledo Edison Company j

FACILITY:

Davis-Besse Nuclear Power Station

SUBJECT:

SUMMARY

OF APRIL 3, 1997, MEETING ON THERMO-LAG RESOLUTION PROGRESS I

In its semiannual report on the status of the Thermo-Lag Action Plan of October 31, 1996, the staff indicated that it would conduct management 3

meetings to discuss plant-specific Thermo-Lag corrective action programs with licensees with protracted schedules. On April 3, 1997, the staff met with representatives of the Toledo Edison Company, one of the three licensees for i

the Davis-Besse Nuclear Power Station, to discuss the overall status of corrective action and the potential for schedule improvements. A list of the 1

meeting participants is included as Enclosure 1, and a copy of the meeting handouts is provided as Enclosure 2.

The licensee has installed a substantial quantity of Thermo-Lag at Davis-Besse:

740 linear feet of 1-hour material on conduits; 1,000 square feet of i

1-hour material over condulets, junction boxes, fire dampers, etc.; 170 linear feet. of 3-hour material on conduits; 860 square feet of 3-hour material over condulets, junction boxes, fire dampers, etc.; 2,200 square feet of 3-hour 1

material over structural steel; and 170 linear feet of material as radiant 3

i energy heat shield.

I 4

Upon completion of their evaluation, the licensee has determined to eliminate i

their reliance on Thermo-Lag as a fire barrier material.

This will be accomplished by circuit modifications, fire hazard reanalysis, and installation of alternate fire barrier materials.

The alternate materials will include 3M Interam E-54 Flexible Mat, Internit Promat - H Calcium j

Silicate Cement Board, and Manoval Fendolite or Carboline Pyrocrete coatings.

The licensee has a five-phase program.

Phase I consisted of removing the Thermo-Lag from circuits in three rooms and from fire dampers in five rooms, and is now complete.

Phase II is scheduled for all of 1997 and the first two quarters of 1998.

Phase II removes the Thermo-Lag from containment and installs new radiant energy heat shields.

Phase III is scheduled for the second and third quarter of 1997.

Phase III installs the new fire barrier material for circuits that had their Thermo-Lag removed in Phase I.

Phase III also removes additional Thermo-lag from structural steel and installs the new fire barrier material.

Phase IV is tied to the next refueling outage, which is scheduled for the second quarter 1998.

Phase IV will remove the Thermo-Lag radiant energy heat shields from the annulus and will install new 3-hour fire barrier material.

Phase V is scheduled for the third quarter 1997 through all of 1998. This phase completes the installations on circuits where Thermo-Lag will be removed in Phase III.

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ggJ l The current schedule shows Davis-Besse completing their program by the end of the fourth quarter 1998. The licensee is considering accelerating its schedule to be complete by the end of the second quarter 1998.

Based upon this meeting, the staff concluded that the licensee is applying appropriate management attention to the Thermo-Lag issues at Davis-Best.e, making progress towards the overall resolution of the issues, and has established an acceptable schedule.

Original signed by:

Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosures:

1.

List of Meeting Participants 2.

Meeting Handouts cc w/encls:

See next page lSTRIBf10N w/encls:

  1. )ocket**

' e '(50:346)

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PUBLIC PD3-3 R/F OGC ACRS E-fLAll S. Collins /F. Miraglia S. West, NRR R. Zimmerman

-M. Salley, NRR J. Roe R. Jenkins, NRR i

E. Adensam i[

G. Marcus

[h jl D. Ross (SAM)

B. McCabe J. Caldwell, RIII DOC'UMENT NAME:

G:\\DAVISBES\\DB85542.MTS To receive a copy of ttus document, indicate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy 0FFICE LA:PD3-3., l 6 PM:PD3-3 f

BC:SPLB (m

(A)tD:PD3-3l l

NAME CBoyle d @

AHansen Aft)

TMarsh II

CCarjhinter DATE 04/ /I/97 0 04//(/9F 04/16 /97 047 /37 0FFICIAL RECORD COPY 220022

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. I 4

The current' schedule shows Davis-Besse completing their program by the end of the fourth quarter 1998.

The licensee is considering accelerating its

]

schedule to be complete by the end of the second quarter 1998.

Based upon this meeting, the staff concluded that the licensee is applying appropriate 2

management attention to the Thermo-Lag issues at Davis-Besse, making progress i

towards the overall resolution of the issues, and has established an

)

acceptable schedule.

i l

Original signed by:

Allen G. Hansen, Project Manager 3

Project Directorate III-3 Division of Reactor Projects III/IV 1

Office of Nuclear Reactor Regulation j

j r

l Docket No. 50-346

Enclosures:

1.

List of Meeting Participants 2.

Meeting Handouts cc w/encls:

See next page i

DISTRIBUTION w/encls:

4 Docket File (50-346)

PUBLIC

-PD3-3 R/F OGC j

.ACRS i

E-MAIL 1

S. Collins /F. Miraglia S. West, NRR j

R. Zimmerman M. Salley, NRR J. Roe R. Jenkins, NRR E. Adensam G. Marcus D. Ross (SAM)

B. McCabe J. Caldwell, RIII DOCUMENT NAME: G:\\DAVISBES\\DB85542.MTS Ta receive a copy of this document, indicate in the box: "C" = Copy without enclosures *E" = Copy with enclosures "N" = No copy 0FFICE LA:PD3-3

._l 4 PM:PD3-3

(

BC:SPLB

/

( A)itD:PD3-3 l

m NAME CBoyle U @

AHansen h 6 TMarsh iF CCarKnter DATE 04/ /I/97 0 04//(/9F 04/l6/97-047 /37 0FFICIAL RECORD COPY

The current schedule shows Davis-Besse completing their program by the end of the fourth quarter 1998. The licensee is considering accelerating its schedule to be complate by the end of the second quarter 1998.

Based upon this meeting, the staff concluded that the licensee is applying appropriate management attention to the Thermo-Lag issues at Davis-Besse, making progress towards the overall resolution of the issues, and has established an acceptable schedule.

N Allen G. Hansen, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket No. 50-346

Enclosures:

1.

List of Meeting Participants 2.

Meeting Handouts cc w/encls:

See next page l

Davis-Bess 6 Nuclear Power Station Toledo Edison Company Unit No. I cc:

Robert E. Owen, Chief Mary E. O'Reilly Bureau of Radiological Health Centerior Energy Corporation Service 300 Madison Avenue Ohio Department of Health Toledo, Ohio 43652 P. O. Box 118 Columbus, Ohio 43266-0118 Mr. James L. Freels Manager - Regulatory Affairs Attorney General Toledo Edison Company Department of Attorney Davis-Besse Nuclear Power Station General 5501 North State - Route 2 30 East Broad Street Oak Harbor, Ohio 43449-9760 Columbus, Ohio 43216 Gerald Charnoff, Esq.

Mr. James W. Harris, Director Shaw, Pittman, Potts Division of Power Generation

& Trowbridge Ohio Department of Industrial 2300 N Street, NW.

Regulations Washington, D.C.

20037 P. O. Box 825 Columbus, Ohio 43216 Regional Administrator U.S. NRC, Region III Ohio Environmental Protection Agency 801 Warrenville Road DERR--Compliance Unit Lisle, Illinois 60523-4351 ATTN:

Zack A. Clayton P. O. Box 1049 Mr. Robert B. Borsum Columbus, Ohio 43266-0149 Babcock & Wilcox Nuclear Power Generation Division State of Ohio 1700 Rockville Pike, Suite 525 Public Utilities Commission Rockville, Maryland 20852 180 East Broad Street Columbus, Ohio 43266-0573 Resident Inspector U.S. Nuclear Regulatory Commission Mr. James R. Williams 5503 North State Route 2 Chief of Staff Oak Harbor, Ohio 43449 Ohio Emergency Management Agency 2855 West Dublin Granville Road Mr. James H. Lash, Plant Manager Columbus, Ohio 43235-2206 Toledo Edison Company Davis-Besse Company Mr. John K. Wood 5501 North State Route 2 Vice President-Nuclear, Davis-Besse Oak Harbor, Ohio 43449-9760 Centerior Service Company c/o Toledo Edison Company President, Board of County Davis-Besse Nuclear Power Station Commissioners of Ottawa County 5501 North State Route 2 Port Clinton, Ohio 43452 Oak Harbor, Ohio 43449-9760 Roy P. Lessy, Jr., Esq.

Andrew G. Berg, Esq.

Akin, Gump, Strauss, Hauer & Feld, L.L.P.

1333 New Hampshire Avenue, NW., Ste. 400 Washington, D.C.

20036

i MEETING ATTENDEES NRC AND TOLEDO EDISON CO.

DISCUSSION OF PROGRESS ON THERMO-LAG ISSUE RESOLUTION APRIL 3, 1997 NRC Allen Hansen Cindi Carpenter K. Steven West Mark Henry Salley i

L.B. Marsh Ronaldo Jenkins TOLED0 EDIS0N C0.

Dale R. Wuokko Craig Hengge Michael K. Leisure 3

Andrew G. Migas j

Bob Donnellon NUS LIS Edward C. Wenzinger NIRS Paul Gunter

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Davis-Besse Nuclear Power Station i

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l Thermo-Lag Resolution Progress Presentation to the U.S. Nuclear Regulatory Commission April 3,1997 i

f GNTERIOR I

I Cc m^ cE. -

ENERGY l

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W EffE M Pagel l

N DAVIS-BESSE NUCLEAR POWER STATION l

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DISCUSSION TOPICS eScope and Approach P

1 e Resolution Strategy i

e Ampacity Issue o Summary

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-CENTERf0R

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Page 2 I

ENE N DAVIS 4 ESSE NUCLEAR POWER STATION I

Scope and Approach Initial Installed Thermo-Lag at DBNPS

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e One Hour Appendix R Fire Barriers e Three Hour Appendix R Fire Barriers o Radiant Energy Shields t

o Structural Steel Fireproofing 4

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-GNTERNHE i

Page3 D

8"EN DAVIS-BESSE NUCLEAR POWER STATION

I Scope and Approach 2)

DBNPS Initia? Strategy e Evaluation of Best Approach for DBNPS

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Upgrade / Qualify Existing Barriers Perform Additional Testing Replace Thermo-Lag With Alternate Material Relocate or Modify Circuits

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Obtain Regulatory Relief (Exemption Request)

Modify / Add Fire Suppression Isolate Barrier / Circuit With An Enclosure j

i Replace Cable With Fire-Resistive Cable j

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DAVIS 4 ESSE NUCM POWER STATION 2

Scope and Approach

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DBNPSInitial Strategy

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e Participation in Industry Initiatives NUMARC/NEl Generic Fire Endurance Test Program l

NEl Chemical Composition Test Program e Detailed Plant Walkdowns/ Verifications e NEl Industry Application Guideline i

Assessment O"""Wekv g,y s

~e Scope and Approach Compensatory Measures t

l e Containment

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When Containment is accessible during outages, a fire watch is established j

n to inspect affected fire barriers at least once per eight hours At other times, containment air temperature is monitored at least once per n

I hour o Annulus i

During Modes 3,4,5, or 6, a fire watch is established to inspect affected fire barriers at least once per eight hours l

During Modes 1 or 2, due to ALARA concems, a video camera and l

supplemental lighting is being utilized to inspected affected fire barriers at

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least once per hour j

e Outside Containment / Annulus Hourly Fire Watches established for affected plant rooms n

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-CENTER 00R Page 6

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ENE N

Resolution Strategy i

ua an. -

o Eliminate Reliance on Thermo-Lag Circuit Modifications

.i Fire Hazards Reanalysis Replacement With Alternate Materials l

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E RGY Page 7 DAVIS-BESSE NUCLEAR POWER STATION I

Resolution Strategy 1-and 3-Hour Fire Barriers i

e Circuit Modifications Component Cooling Water Pump Control Circuitry l

e Fire Hazards Reanalysis n Valve HP31 De-powered

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Eliminate Protaction for CAC-3 (Swing Train)

Structural Steel Reevaluation e Replacement With Alternate Material n 3M Interam E-54 Flexible Mat Internit Promat-H Calcium Silicate Cement Board Manoval Fendolite or Carboline Pyrocrete Trowelable Fireproofing (Structural Steel) i E

Page 8 I

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c Resolution Strategy

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RadiantEnergy ShieMs e Containment Replace With Alternate Material During Next Outage of i

Sufficient Duration Following Design Work Completion j

- 3M Interam (Stainless Steel Backing)

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- Reevaluation of Need for Circuit Protection (CAC-3) e Annulus Eliminate Use of Radiant Energy Shields During Next Outage of Sufficient Duration Following Design Work Completion j

- Installation of 3-Hour Rated Fire Barriers Using Alternate Material e 3M Interam (Aluminum Backing)-

l Additional Testing Required e

- Circuit Relocation (PORV)

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-GN1EREOR o4vi e wuct.rm s now I

Resolution Strategy ReplacementActivities e Contract Awarded e Phased Approach Commenced 3Q1996 Completion 4Q1998 (February 20,1996 Letter)

Proposed Schedule 2Q1998 (Under Review) j f

/A V """. h Page10 DAVIS-BESSE NUCLEAR POWER STATION l

Resolution Strategy

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ReplacementActivities e Remove Existing Thermo-Lag and Obtain Detailed Measurements e Determine the Configuration e Develop Detailed Drawings e Determine the Resultant Change in Support Loading and Identify Any Required Support Modifications /

Additions e Process and Implement Modification Packages for j

installation of New Materials A-m i

DAVIS-BESSE NUCLEAR POWER STATION I

Resolution Strategy

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PhasedApproach o Thermo-Lag Replacement

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t Implementation Schedule l

-l 1996 l

1997 l

1998 1Q 2Q 3Q 4Q 1Q 2Q 3Q 4Q 1Q 2Q 3Q 4Q t

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ase Se se l

se se l

l PROPOSED SCHEDULE l

CUPsRENT SCHEDULE l

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^ CENTERf0R I

b ENERGY i

Pagd 2 DAVIS-BESSE NUCLEAR POWER STATION

Resolution Strategy

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PhasedApproach j

i e Phase I (Completed 4Q1996}

Removed Thermo-Lag from Circuits in 3 Rooms i

Removed Thermo-Lag from Fire Dampers in 5 Rooms and Replaced With New Material j

w """ER"nor Page13 1

DAVIS-8 ESSE NUCLEAR POWER STATION t

Resolution Strategy

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PhasedApproach l

o Phase ll { Potential Mid-Cycle C'utage}

Remove Thermo-Lag from Containment j

1 Radiant Energy Shields and Install New i

Materials k

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_GNTERf0R Page14 l

D 8"8 N 1

DAVIS-BESSE NUCLEAR POWER STATION

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Resolution Strategy Phased Approach (cont'd) i e Phase Ill {3Q1997}

Install New Material for Circuits Which Had Thermo-Lag Removed in Phase i I

i Remove Thermo-Lag from Remaining Circuits (Except Containment and Annulus) l Remove Thermo-Lag from Structural Steel and Install New Materials i

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Resolution Strategy Phased Approach (cont'd)

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e Phase IV (11RFC',2Q1998}

Remove Thermo-Lag From Radiant Energy Shields in Annulus, and Install 3-Hour Rated Barriers Using New Materials l

l Remove Thermo-Lag from Remaining Structural Steel and Install New Materials Phase 11 Scope (If Not Completed) l O

D E

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l Resolution Strategy Phased Approach (cont'd) o Phase V (2Q1998}

Install New Material for Remaining Circuits Which Had Thermo-Lag Removed in i

Phase Ill l

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[n^ GNTERMNr Page17 f

ENEN DAVIS 4 ESSE NUCLEAR POWWER STATION l

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Ampacity Issue J

e Resolving Cable Ampacity Derating Issue in Parallel with Resolving the j

Overall Thermo-Lag issue o Ampacity Derating Factors for Replacement Materials will be Determined using IEEE-848 (Draft 16 or Later)

O"""."M"nov

" 8 Y

Ampacity Issue l

l e Evaluation of Ampacity Issues Related to Thermo-Lag was Provided to the j

NRC in June and November,1996 o Preparing Response to Additional NRC Questions Base Ampacity for Triplex Cable with Ground Voltage Tolerances Conduit Grouping Factors L

Aw-

.w-i age w omis.assa nuct.amowan sroon

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i Summary e Success Path in Place I

i e Current Schedule Well-Planned Management Commitment

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e Compensatory Measures Maintained Until Resolution Plan is Implemented t

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N Page 20 f

DAVIS 4 ESSE NUCLEAR POWER STATION t