ML20134J745

Summary of 961104 Meeting W/Tva in Rockville,Md Re Status of Thermo-Lag Fire Barrier Upgrades at Plant.List of Attendees & Copies of Handouts Encl

ML20134J745
Person / Time
Site:	Sequoyah
Issue date:	11/08/1996
From:	Hernan R NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9611180023
Download: ML20134J745 (41)

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< B NUCLEAR REGULATORY COMMISSION f WASHINGTON, D.C. 20665-0001

\...../ November 8, 1996 LICENSEE: Tennessee Valley Authority FACILITY: Sequoyah Nuclear Plant, Units 1 and 2

SUBJECT:

SUtEARY - NOVEMBER 4, 1996, MEETING WITH TVA TO BRIEF THE STAFF ON THE STATUS OF THERM 0-LAG FIRE BARRIER UPGRADES AT SEQUOYAH On November 4,1996, representatives of the Tennessee Valley Authority (TVA) met with members of the NRC staff in Rockville, Maryland. The staff requested this meeting to discuss with TVA the status of the Thermo-Lag fire barrier corrective action program at the Sequoyah Nuclear Plant (SQN) and the three-year slippage in the schedule for completion of the program. A list of attendees is given in Enclosure 1. Copies of the handouts provided by TVA are given in Enclosure 2.

TVA representativer discussed the Thermo-Lag testing program they conducted in order to gain the necessary confidence that use of additional Thermo-Lag material in the upgrades would be prudent. This testing included fire endurance testing, material property and composition testing, ampacity (current carrying capacity) derate testing, and seismic testing.

There are approximately 4,400 linear feet of single conduit configurations and 1,650 square feet of special configurations that utilize Thermo-Lag at SQN.

On the basis of its test results, TVA believes that approximately 2,100 feet of the linear configuration Thermo-Lag can be qualified as is. The remainder of the fire barriers will need to be upgraded by addition of material.

Standard designs have been developed and detailed walkdowns will be required to verify the qualification of the 2,100 feet of linear barrier and to apply the standard designs to the remaining configurations. TVA stated that most of these walkdowns (as well as during the installation of the additional material) would require erection of temporary scaffolding and much of this work would be in proximity to sensitive equipment. The sensitive equipment is mostly electrical and instrumentation. During the meeting, the TVA representatives could not characterize how many of the barriers were in close proximity to sensitive equipment.

TVA plans to train and use a number of relatively small installation teams to ensure quality work and to minimize risk of plant upsets while the plar ts are operating, which will be throughout most of the walkdowns and installation of the upgrades. There is also concern regarding this work jeopardizing required system / component availability during outage periods. TVA noted the l

differences beteeen performing Thermo-Lag upgrades at Watts Bar (single unit)  !

! prior to the plant receiving its operating license and performing the upgrades  !

I at SQN with at least one unit operating (most of the time with both units '

operating).

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d Tm . i 9611100023 961108 PDR ADOCK 05000327 F PDR L

1' The installation effort is expected to require approximately 110,000 person-l hours of direct rapport and approximately 11,000 person-hours of engineering support. The walkdowns are scheduled to start within the next several months and finish in late 1999. Total cost over the next three fiscal years is

estimated at about $9 million. The staff had requested, in advance of the l meeting, that TVA be prepared to discuss other planned / budgeted capital and '

0&M projects with which the Thermo-Lag upgrade is competing. This information can be found in Enclosure 2.

The staff requested specific information from TVA regarding documentation of l the integrated program plan / schedule that could be reviewed by NRC inspectors at the plant site to determine whether or not TVA had complied with 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requiring prompt corrective

action of conditions adverse to quality. TVA agreed to make this information I available to the staff. The staff informed TVA that it is still concerned about the length of the Sequoyah Thermo-Lag corrective action program and the significant delay in TVA's previously proposed completion schedule (i.e.,

l October 1999 vs. October 1996).

! The staff questioned TVA's decision to resolve the Thermo-Lag issues at it's i Watts Bar Nuclear Plant, at that time a Near-Term Operating License plant, prior to resolving them at Sequoyah, an operating plant. There was l speculation by some staff members that more preliminary work could have been l performed at Sequoyah during the past few years in parallel with the testing program. The staff requested an historical breakdown of resources expended by TVAonThermjLagresolutionsbysite(BrownsFerry,WattsBar,andSequoyah) l and year since the identification of the technical concerns by the staff in 1992 and a breakdown of the projected resources to be expended until all Thermo-Lag issues are resolved. The staff requested the breakdown by site because TVA made its presentation in the context of the TVA-wide program.

l Finally, the staff requested a comprehensive accounting of the amounts of installed Thermo-Lag in relation to the sensitive equipment that TVA is concerned about disrupting during this project.

l Original signed by Ronald W. Hernan, Senior Project Manager l

Project Directorate II-3 i Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-327 and 50-328 l

Enclosures:

1. Attendance List i 2. TVA Handout

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[ F. Miraglia (FJM)

! R. Zimmerman (RPZ) l A. Thadani (ACT)

S. Varga (SAV)  ;

B. Sheron (BWS) ,

l G. Holahan (GMH)-

J. Zwolinski (JAZ) '

E. Jordan (JKR)

T. Marsh.(LBM) l S. West (KSW)

F. Hebdon'(FJH)

R.'Jenkins (RVJ)

L. Tran (LN1)

L. Whitney (LEW1) >

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R. Hernan (RWH) l B. Clayton l

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Mr. Oliver D. Kingsley, Jr. SEQUOYAH NUCLEAR PLANT l Tennessee Valley Authority cc: '

Mr. O. J. Zoringue, Sr. Vice President Mr. J. T. Herron, Plant Manager Nuclear Operations Sequoyah Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority 6A Lookout Place P.O. Box 2000 1101 Market Street Soddy Daisy, TN 37379 Chattanooga, TN 37402-2801 Regional Administrator Mr. Mark 0. Medford, Vice President U.S. Nuclear Regulatory Commission Engineering & Technical Services Region II Tennessee Valley Authority 101 Marietta Street, NW., Suite 2900 6A Lookout Place Atlanta, GA 30323 1101 Market Street Chattanooga, TN 37402-2801 Mr. Mel C. Shannon Senior Resident Inspector Mr. R. J. Adney, Site Vice President Sequoyah Nuclear Plant Sequoyah Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 2600 Igou Ferry Road P.O. Box 2000 Soddy Daisy, TN 37379 Soddy Daisy, TN 37379 Mr. Michael H. Mobley, Director General Counsel Division of Radiological Health Tennessee Valley Authority 3rd Floor, L and C Annex l ET 10H 401 Church Street 400 West Summit Hill Drive Nashville, TN 37243-1532 Knoxville, TN 37902 County Executive Mr. Raul R. Baron, General Manager Hamilton County Courthouse Nuclear Assurance and Licensing Chattanooga, TN 37402-2801 Tennessee Valley Authority 4J Blue Ridge l 1101 Market Street Chattanooga, TN 37402-2801 Mr. Pedro Salas, Manager Licensing and Industry Affairs Tennessee Valley Authority 4J Blue Ridge 1101 Market Street  !

Chattanooga, TN 37402-2801 Mr. Ralph H. Shell, Manager Licensing and Industry Affairs Sequoyah Nuclear Plant Tennessee Valley Authority l P.O. Lox 2000 l Soddy Daisy, TN 37379 i l

1

ATTENDEES NRC/TVA MEETING ON NOVEMBER 4, 1996 REGARDING THERM 0-LAG HAmg Affiliation Ron Hernan NRC/NRR/DRPE/PD II-3 Kent W. Brown TVA - Sr. Elect. Engr., Corp Mark Henry Salley TVA - Sr. Engr., Corp Craig Butcher TVA - Elect. Engr. Mgr., SQN l

l James K. Rochelle TVA - Civil Engr., Corp  !

l John K. Gates TVA - Project Manager l l

l Michael J. Lorek TVA - Mech. Engr. Mgr., SQN Mark J. Burzynsky TVA - Engr. & Matls Mgr. - SQN Jon R. Rupert TVA - Engr. & Tech. Supp., SQN l

Raul R. Baron TVA - Gen. Mgr. NA&L, TVAN Ralph H. Shell TVA - Mgr., Lic & Ind Affairs Ronaldo V. Jenkins NRC/NRR/EELB - Elect. Engr.

Linh N. Tran NRC/NRR/DRP, Lead Proj. Mgr.

l Fred Hebdon NRC/NRR/DRP, PD 2-3 1

! Jim Smith TVA - SQN Licensing Supervisor Patrick Madden NRC/NRR/DSSA, Fire Prot. Engr. i K. Steven West NRC/NRR/DSSA, Fire Prot. SL 1 L. B. Marsh NRC/NRR/DSSA, Chief, SPLB Brian Sheron NRC/NRR, Acting Assoc. Dir.

Theresa Sutter Bechtel, Licensing Engr.

Mike Schoppman Florida Power & Light, Beth.

E. A. Thompson Florida Power & Light, PE ENCLOSURE 1 l

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Tennessee Valley Authority Sequoyah Nuclear Plant  ;

TVA/NRC Thermo-Lag Meeting i November 4,1996 1 l

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Sequoyah Nuclear Plant TVA/NRC Thermo-Lag Management Meeting November 4,1996 t Agenda ,

Introduction M. J. Burzynsk TVA The.rmo-Lag Testing Plan ,

- FireProtection M. H. Salley

- Ampacity K. W. Brown j - Seismic J. K. Rochelle Thermo-Lag Application to SQN M. J. Lorek/C. R. Butcher Thermo-Lag Schedule L K. Gates i i Summary J. R. Rupert i

1 ENCLOSURE 2

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Sequoyah Nuclear Plant Introduction Sequoyah Nuclear Plant Introductioit

- TVA Strategy

- Ressarc'h to bound testing

- Testing

- Internal standards

- Design j - Implementation

• TVA Perspective

- Browns Ferry

- Watts Bar

- Sequoyah

+ Schedule

- Why we changed

- Where we will be in '97 2

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Sequoyah Nuclear Plant l

l Thermo-Lag Testing l

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Sequoyah Nuclear Plant TVA Thermo-Lag Testing Plan ,

! - TVA Integrated Thenno-Lag Program

- WBN Unit 1 TVA Nuclear (TVAN) lead plant

- BFN Units 2 and 3 l

• Cable rerouting

• Thermo-Lag. intake pumping station

- SQN Units I and 2 final TVAN plant

l.

• Prototype for TVA Nuclear testing

• Qualification and upgrade l + Multi-disciplined approach to resolve related issues

- Fire protection rating

- Ampacity derating

- Seismic adequacy 1

Sequoyah Nuclear Plant Thermo-Lag Testing Fire Protection

. TVA Nuclear Testing Position

- NRC/NRR meeting, October 7,1992

- NRC GL 86-10, Supplement 1. March 25,1994

- Regulatory Information Conference, May 4,1993

- ACRS Subcommittee meeting, November 9,1993

- ACRS Full Committee, December 9,1993

- ASME International Joint Power Generation Conference, October 1995

- TVA continues to share testing with industry (NEI)

Sequoyah Nuclear Plant Thermo-Lag Testing Fire Protection

• Fire Endurance Testing Phase I l

- Developed testing methodology and acceptance criteig

- Started construction, October 1992 l

- Conducted testing, December 1992 through April 1993  !

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• Fundamentalone-hourconfigurations

• Six M1-scale fue tests

• Basic conduits

• Basic air drops 1

• Basicjunctionboxes

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l Sequoyah Nuclear Plant Thermo-Lag Testing Fire Protection

- Fire Endurance Testing Phase II

- Started construction, June 1993 l

j - Conducted testing, September 1993 through October 1993 l

• Cable trays and advanced one-hour configurations l

• Seven full-scale fire tests

• Three cable tray tests  !

• Four SQN configurations

- Boxed and ganged conduits  !

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! - ImprovedJunction box design ,

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Thermo-Lag Testing l Fire Protection i t .

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l - Fire Endurance Testing Phase Ill .

- Started con:Tuction, October 1994 l

- Conducted testing, December 1994 through January 1995

• Conduit, cable tray, junction box (basic three-hour configurations)

• Two full-scale tests

• Four-hour, ten-minute rating l

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Sequoyah Nuclear Plant Thermo-Lag Testing Fire Protection

• Fire Endurance Testing Phase IV ,

- Started construction, November 1995

- Conducted test, January 1996

• SQN materialproperties

• 1hennogravimetric Analysis (TGA)  !

• Infrared (IR) Spectroscopy

• SQN/WBN June 15,1995 update to GL 92 08 RAI  ;

• Effecu of cable fillin conduit ,

• Effects of banding

• 1 i

Sequoyah Nuclear Plant l

Thermo-Lag Testing Fire Protection l

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• January 1996 Test Results

- OMEGA Point Laboratories Report issued March 20,1996

- Qualified SQN vintage material

- Qualified 3-inch conduit protected with a single layer of l nominal 5/8-inch Thermo-Lag 330-1

• Qualified existing bands on 3-inch and larger conduct l

• Developed relationship for ccaduit cable fill and thermal performance l-i l

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Thermo-Lag Testing Fire Protection r--

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- January 1996 Fire Test Results (cont.)

t Therme-tag 330-1 Cable Fia Conduit Surface Conduit Serface Conduit Sim. ERFBS (Ibs/ft.) Delts Teve (der F) Deits Taas (des,D A l* Min.1/2"TGA = ? 0.0 157 16i Noen. 3/8"TGA = V B 3" Nom. 5/8"TGA = ? 0.0 248 300 C 3" Min.1/2"TGA = ? 0.85 221 275 D 3" Min.1/2" TGA = ? 2.70 199 238 E 4" Min.1/2" TGA = ? 0.0 178 210 F 4" Min.1/2"TGA = V 0.0 189 230 ,

l Sequoyah Nuclear Plant ,

Thermo= Lag Testing l l Fire Protection l . summary j i

- Existing Thermo-Lag performance

• SQN original installation is high quality

• Limiting conduit (1-inch) approximately 40-minute rating ,

• Uniquecordigurauonsupgrading I

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l - TVA received approval for Thermo-Lag ERFBS, October 1995

• NRC NUREG-0847, Supplement 18 i

- Testing has been thorough and systematic

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Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity l

. TVA Test Program Overview

- Results andIssues i

I Sequoyah Nuclear Plant Thermo-Lag Testing  ;

Ampacity ,

i Thermo-Lag Test Program

- No original manufacturer deratings used

- TV derating applied to single open-top trays

- TVA test programs address

• Single conduits (single layer and upgrade)

• Boxed multiple conduits

• Coveredtrays

• Stacked trays ,

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Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity

• Thenno-Lag Test Program

- Testing based on IEEE P-848," Procedure for the Determination of the Ampacity Derating of Fire Protected Cables"

- TVA program led the industry on numerous issues

• Conduit

• ENectofconduitemissivity

• Effectofnumberofconductors

• Non-standard configwations

• Three-hoursystems

• Tray

• Non-standard configmations

• Three-howsystems Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity

• Thermo-Lag Test Program

- Final ampacity derating factors

• Single conduits (includes 5% margin to address emissivity)

• 5/8-inch,1-hour 7%

• 3/8-inch + 3/8-inch,1-how 7%

• 5/8-inch + 3/8-inch,1-how 8%

• 330-In701,2 inch and larger,3-how !8*'.

• Boxed conduits

• Unistrut frame,1-how 12%

• Directmounted,1-hour 26% j 9

Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity

• Thermo-Lag Test Program

- Final ampacity derating factors

• Tray

• Opentop,1-hour (RJtest) 32%

• Sheetsteclevered,1-hour-40%

• Stacked trays common enclosure,1-hour 41%

• 330-in70-1,3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 48%

Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity

• Four questions from August 29,19% WBN request foi additional information(RAI)

- Confirm absence of tray cover on specimen 7.1 baseline

- Cure time of wrapped specimen 7.3

- Simultaneous testing of two specimens

- Margin

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Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity Issue Number One Confirm absence of tray cover on specimen 7.1 baseline

. Testing of an open tray confirmed in four sections of the report

- Test plan

. Sequence and Procedure

• List of test configurations

- Description of test articles

- Photographs Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity Issue Number Two l l

Cure time of wrapped specimen 7.3 m ay l . Original spacing 8 inches (tray bottom-to-tray top)

. Altered spacing 6-1/2 inches (bottom tray-to-middle tray)

. Spacing restored and enclosure spliced ey j emiaana.y  ;

- Shortened splice cure has insignificant impact j

- Low percentage of the barrier affected by the splice

! (4%)

- Location of the splice next to non-power tray

- Elevated temperature exposure beginning October 4 l

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1 Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity Issue Number Two Cure time of wrapped specimen 7.3

- Assembly chronology

- August 30,1994 - Begin application of ERFBS with altered spacing between lower trays

- September 7,1994 Initialcompletion

- September 8,1994 - Altered spacing deemed unacceptable, spacing restored with " splice"

- September 9,1994 - Splice completed

- October 4,1994 - Assembly placed in test enclosure and energized

- October 6,1994 - Ampacity evaluation completed Sequoyah Nuclear Plant Thermo-Lag Testing Ampacity .

Issue Number Three Simultaneous testing of two specimens l

- simultaneous testing had no effect

- Hottest conduit in specimen 7.4 was awJLy from assembly 7.1

- Left- and right-side extemal temperatures within 0.2*C AnemWy u AsamWy M i.

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Issue Number Four Margin l

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+ Cables not reanalyzed with new multipliers l

. Minimalimpact expected

- No wrapped power cable trays

- Little change in conduit derating factors i

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TVA Design standard includes new multipliers i

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l Sequoyah Nuclear Plant l Thermo-Lag Testing i Ampacity ,

• Summuy 2 l

- Development of test standard

- Numerous configurations evaluated

- Intemal standards will ensure acceptable installation t  !

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Sequoyah Nuclear Plant  !

Thermo-Lag Testing  :

Seismic j i

- Objective l-l - Describe TVA static, dynamic, and acceptance tests and i application of test results for seismic / structural qualification of i Thermo-Lag 330-1 ERFBS l

- Requirements  ;

- Seismic II/I protection for safety-related equipment, components,  !

I and electrical cables

! - Account for Thermo-Lag mass and stiffness effects in qualification

!' of enclosed electrical raceway systems

. Testing j

- Static (mechanicalproperty) l

- Dynamic (shaketabic) i

- Lot acceptance (receipt inspection)  ;

1 Sequoyah Nuclear Plant >

Thermo-Lag Testing j Seismic l

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. TVA Milestones

- Nov 94 Submitted static (mechanical property) and dynamic (shake tabic) test reports to NRC

- Mar 95 Responded to Dec 94 RAls describing plans for:

• New WBN enclosures and replacement of BFN enclosures

• Evaluation and upgrade of SQN enclosures

• Thermo-Lag enclosure design standards based on TVA tests

• Acceptance testing for density and shear strength

• Installation per TVA General Specification (G-Spec) and plant-specific design output

- Apr 95 NRC WBN site audit of Thermo-Lag Seismic Adequacy l

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l Sequoyah Nuclear Plant l Thermo-Lag Testing l Se:Smic i

. TVA Milestones

- Oct 95 Completed WBN Thermo-Lag installation (DCN closed)

- Oct 95 NRC IN 95 Thermo-Lag seismic adequacy and TVA test results

- Dec 95 Completed BfN Thermo-Lag replacement (DCN closed) l

- Sep 96 Submitted revised response to Dec 94 RAI for SQN i

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l Sequoyah Nuclear Plant Thermo-Lag Testing Seismic l

. Static (Mechanical Property) Tests at Singleton Laboratory (SL),

f September 1994

- Specimens fabricated by TVA; joints cured 30 days l'

- Procedures per ASTM standards to extent possible; special fixtures developed ,

j - Tested worst case conditions (125'F and minimum curing time)  !

- Submitted SL Report, November 11,1994 i

- Strength / stiffness properties needed for analysis

! - Compartson te TSI data (IN 95-49) i 4

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Sequoyah Nuclear Plant j i Thermo-Lag Testing- l l Seismic i l

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. Dynamic (Shake Table) Tests (Wyle Laboratory, September 1994) {

- Cable tray, conduit, air drop fixtures and enclosures fabricated by TVA'

• cured 30 days l

- Required Response Spectra (RRS) enveloped WBN requirements l

- Simulated two OBEs followed by one SSE - triaxial input

- Resonance search tests before and after proof tests (to assess changes)

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j - Tested at 125'F and minimum (30-day) cure time i

- Submitted Wyle Report, November 11,1994  !

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- Video reviewed during WBN audit l - Test Response Spectra enveloped RRS in axes and frequency ranges

- Specimens performed very well (no significant damage) t l  :

1 Sequoyah Nuclear Plant )

l Thermo-Lag Testing ,

l Seismic i

. Material Lot Acceptance Tests (Singleton laboratory, March - .

l August 1995) '

L - Tests for cada lot ofmaterial used at WBN and BFN

- Board specimens tested for density and in-plane shear strength

- Pre-formed (curved) panel specimens tested for density

( - Shear strength tests at 125'F l

- _ First tests provided basis for acceptance criteria in G-Spec (includui material from lots used in TVA-sponsored fire, ampacity, and seismic tests)

- SL Report, September 26,1995 (Over 200 tots tested)(One 1-1/4 inch thick board tot rejected for low density)

- Additionallot ==5E{ tests planned for SQN upgrade material t

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Sequoyah Nuclear Plant Thermo-Lag Testing Seismic

- TVA Civil Design standard

- Scope: Thermo-Lag 330-1 enclosures installed or upgraded per TVA O-Spec

- Qualification by attribute comparison to dynamic test specimens and spectra

- Allowable stresses based on static test minimum strength values

- Modulus of elasticity and shear modulus values based on average test values

- Density for boards (72 pcf) and pre-formed curved panels (84 pcf) based on mean plus one standard deviation of phase I acceptance test data

- Stress checks for enclosure qualification by analysis and analytical methods (correlated)

Sequoyah Nuclear Plant Thermo-Lag Testing Seismic

. TVA Civil Design standard

- Methods for qualifying enclosed racew:ys for added mass and stiffness

- Reviewed during WBN Scismic Adequacy Audit, April 1995

- Used to qualify WBN and BFN enclosures

- Resulted in minor structural enhancements and span '.' knits for Thermo-Lag enclosures qualified by TVA fire tests j

- To be applied for SQN Thermo-Lag designs

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j Sequoyah Nuclear Plant I Thermo-Lag Testing i Seismic

- summary

- TVA static, dynamie, and acceptance tests provided basis for wismic/ structural qualification of Thermo-Lag enclosures and enclosed raceways at WBN and BFN

- Mechanical property / density values from TVA tests more specific than TSI data

- Mechanical properties from TVA tests lower than TSI properties (IN 95-49)

- WBN and BFN enclosures installed per TVA G-Spec and plant-specific l design output f - Conservative tests: at maximum operating temperature (125'F) arid minimum curing time (30 days)

- Application of TVA Civil DS resulted in minor structural enhancements and spen limits for Thermo-Lag enclosures qualified by TVA fire tests (minor impact on enclosure design)(no significant impact on fire or ampacity -

qualification)

- TVA Civil DS and G-Spx to be applied for SQN designs Sequoyah Nuclear Plant

[ Thermo-Lag Application to Sequoyah i

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l Sequc ahNuclearPlant Thenno-Lag Testing Application

. Current wrapped configurations ,

- 4374 linear feet of single conduit (1 inch,1 1/2 inch,2 inch,2-1/2 inch, 3 inch, and 4 inch)

- 1646 square feet of special configurations

• Four boxed conduit configuratic:4 (three 4 inch, one 2 inch)

• Twentyjunction boxes

• Three cable trays

. Reduction allowed by test results j - 2132 linear feet of 3 inch and 4 inch conduit will be qualified as is

- 2242 linear feet of 1 inch,1 1/2 inch,2 inch, and 2-1/2 inch conduit will require upgrade l

- 1646 square feet of special configurations will require upgrade 1

i Sequoyah Nuclear Plant Thermo-Lag Testing Application ,

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. Upgrade implementation plan

- Walkdowns ofinstalled Thermo-Lag will be required to verify acceptability

• Verification of design attributes (32 required by RAI)

• Installation constructibility

• Civil support considerations

- A significant percentage ofinstalled Thermo-Lag is on conduit runs near the ceiling of each elevation of the auxiliary building which will require a significant amount of scaffolding to access 4

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Sequoyah Nuclear Plant Thermo-Lag Testing  ;

Application i

- Scaffolding will have to be constructed around sensitive equipment

• RCP undervoltage and underfrequency relays

• S/G pressure transmitters

• 120V AC vitalinstrument power boards  !

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• 125V DC vital banery boards

• 6SkVshutdownboards  ;

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• Componentcoolingwnierpumps

• 480V MOV boards

• 6900V/480V shutdown transformers 1

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Sequoyah Nuclear Plant j Thermo-Lag Testing i Application )

- Engineering effort required to resolve Thermo-Lag

- Estimated 13,000 man-hours for Fiscal Year '97

- Scoping walkdowns account for 10% of this estimate

- Approximately 90 cables require ampacity review

- Civil Engineering required to evaluate ERFBS supports I

I - Efforts best accomplished by dedicated teams of reasonable size j to ensure consistency and high quality a

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Sequoyah Nuclear Plant Therma-Lag Testing Application.

• Walkdown attributes

- Thermo. Lag installations will be walked down

• Dedicated, specially-trained team consisting of fire protection engineers, electrical engineers, civil engineers, modifications engineers, and operations

- Snecial scaffolding required, some in close proximity to sensitive equipment

- Team will perform detailed documented inspections of existing installation for attributes such as:

• Correctthickness

• Correct surface texture

• Cracks or shrinkage in material

• Visible gaps or separation from adjacent materials

• Compliance with requirements to cover intervening items Sequoyah Nuclear Plant Thermo-Lag Testing Application Walkdown attributes (continued)

• Presence of mechanical fasteners and compliance with space rules

• Presence of surface voids (unacceptable) . ,

• Presence of surface delsminations (unacceptable)

• Adequacy of civil support systems j

• Protection of mechanical fasteners and civil supports ]

• Water damage and the need to use a protective coatmg i

• Need for weep holes (junction boxes) l

• Document the acceptability of single conduits > 3 inches

• Initiate minor maintenance documents *o correct minor deficiencies

• Document required upgrades to be en.de

• Verify constructabill:y of upgrade configurations 21

l Sequoyah Nuclear Plant Thermo-Lag Testing Application Engineering analysis to support upgrade configurations l

- Existing configurations will be evaluated and those found compliant to requirements will be returned to service l

• Currently estimated that approximately 2l00 feet of conduit l will be acceptable as-is and returned to service following documentation from walkdowns

- Ampacity evaluations of approximately 90 power cables

- Civil evaluations of structural support sys* ems

- Fire protection evaluations of fire barriers to conform to requirements (GL 86-10 evaluations)

- Creation of entire new drawing series to document installation details

- Potential cable rerouting

- Two design change notices per nc planned

- One for removal of material no longer required

- One for upgrade of fire barriers l

l l Sequoyah Nuclear Plant l Thermo-Lag Testing Application l

t

- Thermo Lag reduction

- Installations identified by evaluations as not required can be removed

- Material will be retained to evaluate acceptability of past installations I

• Verify presence of stress skin material I

• Verify assembly was pre-buttered at time ofinitial insta!!ation 22

Sequoyah Nuclear Plant Thermo-Lag Testing Application

• Training ef team members

- Improved training based on lessons learned from WBN

- Extensive training of engineering and modifications individuals

• Requirements forinspections

• Requirements forinstallations

• Clear understanding ofrequirements

• Consistent direction from engineering staff

• Promotes a strong and effective team Highest quality can be achieved through smaller installation

< teams

• Consistency ofinstallations and retention oflessons learned Sequoyah Nuclear Plant Thermo-Lag Testing Application

• Implementation of fire barrier upgrades

- Additional 11,000 man-hours estimated for engineering support

- Modification estimates near 111,000 man-hours for implementation

- Scaffolding will be required in the same sensitive areas previously described

- Installation is very labor intensive

- To ensure quality construction, a crew of 10-12 insulators with

{

previous Thermo-Lag installation experience will be utilized with close supervision

)

- Most locations will be difficult to work m  ;

- Final document closure following installation and verification j

- Integration of resources with other site projects j

- Balance Thermo-Lag upgrades with other reliability issues

- Multi-year business plans i

/

23

Sequoyah Nuclear Plant Thermo-Lag Schedule Sequoyah Nuclear Plant Thermo-Lag Schedule

. Majority ofimplementation nonoutage

. Spring and Fall outages in '97 dictate Engineering resources i

. Application is specialized work I

- Management concerns j

- CapitalProjectsThree-YearPlan

- O&M Projects Three-Year Plan

- Implementation L auxiliary building 24

i L

1

.i Sequoyah Nuclear Plant ,

I Summary i

i Sequoyah Nuclear Plant ,

Summary I i

. OverallTVA systematic approach i

l

. Thermo-Lag installation details .

]

l

. Implementation considerations for quality of work l

. Schedule reflects a balanced approach to address reliability and regulatoryissues l

23 l _ - . _ _ , _

PROJECT TITLE 5

@$ k O

3 C

2 0

i IE l 8 OE D L i Tech Spec Upgrade (includes Procedure Upgrade) $696 $1.407 $1,441 Werk Man 9Jemer,t System Data Bases $802 $518 $416 ISI Support U1C8 Jun-97 $165 l

Erosion / Corrosion U1C8 Jun-97 $187 Coatings Sep-97 $214 Raw Waterinspection Sep-97 $140 Erosion / Corrosion U2C8 $144 ISI Support U2C8 $85 Drawing Backlogs $735 $1,110 Thermolag Enhancements $748 $3,076 $2,996 l il SO960654PER Resolution (Partial Mods) Sep-97 $449 DCN Closecut U1C8 $426 $200 l

Relief Valve issue U2C8 $193 $303 U1 & Common Relief Valve issue U1C9 $250 $500 l

1 Loss of Voltage Relay, Annunciator Main Bus U1C8 Apr-97 $3 U1 Replace Flow Switches $12 TBD TBD j Control Air for ABGTS Jul-97 $180 Thermal Barrier Isolation Vivs U1C8 Apr-97 $41 Ecolochem $516 10/31/9611:22 AM Om97-99a 1

SEQUOYAH O&M PROJECTS Ll3T ,

FISCAL YEARS 1997-1999 ,

w cz ~ = g b b PROJECT TITLE fo I$

OE D D O

D PROJECTS TO IMPROVE RELIABillTY MCR Annunciator Jul-97 $81 Power Circuit Breakers U2C8 $11 $20 Replace Doors C49 and C50 $104 SCWS Pump Discharge Iso Valves U1C8 Apr-97 $13 SCWS Pump Discharge Iso Valves U2C8 $11 $10 Con Demin Waste Sep-97 $85 NASH Relief Valve Drain Pipe U2C8 $51 $26 '

No. 7 HDT Optimization $24 $133 U1 Upgrade Rad Monitor Software Jul-97 $55 U2 Upgrade Rad Monitor Software Sep-97 $55 Sight Glass Raplacement U2C8 $45 $39 No. 7 Heater Drain Tank Flow in MCR U1C8 Apr-97 $23 No. 7 Heater Drain Tank Flowin MCR U2C8 $23 $5 U1 No. 3 HDTP Sealinjection Low Delta P Alarm Jul-97 $15 ERCW Traveling Screens $19 TBD Various Reach Rod Operated Valves $11 TBD TBD Press Control Vivs77-430,431 U1C9 $20 TBD TBD Press Control Vivs77-430,431 U2C8 $20 TBD Positioner for 2-PCV-47-189 U2C8 $12 $8 Interlock Gen Output Breaker to MOD U2C8 $14 $12 Add T-Drains to 35 MOVs U2C8 $30 TBD TBD 10/31/3611:22 AM Om97-99a 2

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nMM1M SEQUOYQH CAPITAL PROJECTS LIST FISCAL YEARS 1997 - 1999 1

l

$ OW E E E

( PROJECT TITLE * $E E E E Nd $ $ $

OPERATOR WORK AROUNDS REPL MOTOR OPERATORS 1-FCV-47-180 & 181 UIC9 TBD TBD REPL MOTOR OPERATORS 2-FCV-47-180 & 18! U2C8 60 TBD FLOW MODIFIER l-FM-142A TERRY TURBINE CNTRL UIC8 Apr-97 68 FLOW MODIFIER 2-FM-142A TERRY TURBINE CNTRL U2C8 53 TBD REPLACE ICE CONDENSER GLYCOL CillLLERS 3,297 485 POST UIC7 ARROW-fiART ISSUES Nov-96 36 IIEAT TRACE RECORDERS FOR FREEZE PROTECTION Jan-97 28 UIC8 ARROW-ilARTISSUES UIC8 Apr-97 2,224 U2C8 ARROW-ilARTISSUES iU2C8 211 CVCS VENTING UIC9 615 248 CVCS VENTING U2C9 125 738 GLYCOL C111LLERS INSTRUMENTATION 249 INSTALL NEW MFP MINIFLOW VALVE NEW ORFICE AND NEW CONTROLLERS UIC9 350 300 INSTALL NEW MFP MINIFLOW VALVE NEW ORFICE AND NEW CONTROLLERS U2C8 200 400 50 RIIR SYSTEM DISCIIARGE PIPING WATER 11 AMMER (GAS ENTRAINMENT) UIC8 Apr-97 350 RilR SYSTEM DISCilARGE PIPING WATER 11AMMER (GAS ENTRAINMENT) U2C8 191 159 POST U2C7 ARROW-ilART ISSUES Nov-96 355 REPL ARROWilART CONTACTORS (FY97 MONEY IN PCN'S 2048,2158,2159, & 3031) ABOVE 1.150 1.400 SUBTOTAL OPERATOR WORK AROUND3 3,776 6,345 3,221 l REPLACEMENT OF OBSOLETE EOUIPMENT MAIN TURBINE SUPERVISORY INSTR UI UIC9 TBD TBD MAIN TURBINE SUPERVISORY INSTR U2 U2C9 TBD TBD l OBSOLETE RECORDERS U2C8 165 TBD REPLACE AUX AIR COMPRESSORS TBD POWER SUPPLY l-PX-3-142 UICR Apr-97 14 l REPLACE CRD COOLER COtrFROLLERS UI Jun-97 98 l

REPLACE CRD COOLER CONTROLLERS Ul Jul-97 94 1

10:3i % Page I of 7 Nre_3y

SEQUO'NH CAPITAL PROJECTS LIST MC ' VEARS 1997 - 1999 ~

O bk b h h PROJECT TITLE

{o  ::: E ME REPLACE DUNilAM BUSH TlhER TMR-103 Jun-97 63 REPLACE S&K FLOW INDICATING XMITTERS UI UIC8 Apr-97 245 REPLACE S&K FLOW INDICATING XMITTERS U2 U2C8 200 TBD OBSOLETE EQUIPhENT DETAIL 1,000 1,000 AUXILIARY POII,ER RECORDER AND CONTROLS UPGRADE 300 OBSOLETE RECORDERS UIC8 May-97 405 REPLACE MICRO R 100 RECORDERS 200 REPLACE MICRO R 100 RECORDERS 200 SUBTOTAL REPLACEMENT OF OBSOLETE EQUIPMENT 1,284 1,700 1,000

~

CHEMISTRY & RAD PROTECTION UPGRADES 3

RESOLVE PAS SYS PROBLEMS Jul-97 307

{ RESOLVE PAS SYS PROBLEMS Jul-97 294 INSTALL CABLE AND CONDUIT TO POWER PLASMA SPECTROMETER 200 SECONDARY SAMPLING AND INSTRUMENT Feb-97 1,019 SECONDARY SAMPLING AND INSTRUMENT 2,542 50 kNSTALL DATA ACQUISITION SYSTEM 703 REPLACE ERCW CHLORINATION SYS 1,063 50 REPLACE RCW CHLORINATION SYSTEM 981 LOWER COMPARThENT COOLER COILS 325 SUBTOTAL CHEMISTRY & RAD PROTECTION UPGRADES 5,928 1,606 0 FIRE PROTECTION ISSUES CSST A OIL RETAINING CURB Jan-97 176 UPGRADE FIRE PROTECTION SYS 2,562 200 FIRE DETECTION IN PASF Jul-97 332 SUBTOTAL FIRE PROTECTION ISSUES 3,070 200 0 VARIOUS BUILDING UPGRADES REACTOR BLDG ROOF UPGRADE 140 140 103iw Page 2 of 7 Nrc_3p

SEQUOYQII CAPITAL PROJECTS LIST FISCAL YEARS 1997 - 1999

$ Am E R R

• E E E PROJECT TITLE 5h ME $ $ D SOLAR BLDG ELEVATOR INSTALLATION Jul-97 75 ALPINE VILLAGE UPGRADE Jul-97 100 SOLAR BUILDING UPGRADE Jul-97 100 PLANT OFFICE BUILDING UPGRADE Jul-97 350 SUBTOTAL VARIOUS BUILDING UPGRADES 765 I40 0 ELECTRICAL PENETRATION CHANGEOUTS ELECTRICAL PENETRATIONS UIC8 May-97 2,005 EL'dcrRICAL PENETRATIONS U.1C8 U2C8 640 REPLACE ELECTRICAL PENETRATIONS (FY97 MONEY IN PCN'S 2174 & 3080) ABOVE 2.440 _3_00 SUBTOTAL ELECTRICAL PENETRATION CHANGEOUTS 2,645 2,440 300 ETEAM GENERATOR PRESERVATION RETUBE GLAND STEAM CONDENSER UIC8 Apr-97 122 CONDENSER RETUBE PROJECT UIC8 Jun-97 23,596 CONDENSER RETUBE PROJECT U2C7 Dec-96 200 ,

INSTALL S/G N16 MONITOR UIC9 175 75 INSTALL S/G N16 MONITOR U2C9 50 2pd SUBTOTAL STEAM GENERATOR PRESERVATION 23,918 225 275 UPGRADE / REBUILD OF PLANT EOUIPMENT REBUILD J-A ERCW PUMP & MOTOR Feb-97 487 REPLACE SCSA COMPRESSORS Jul-97 600 REPLACE WASTE GAS ANALYZER Jul-97 325 SUBTOTAL UPGRADE / REBUILD OF PLANT EQUIPMENT 1,412 0 0 OUTAGEIMPROVEMENT LOWER CONTAINMENT COOLING UIC9 26 85 LOWER CONTAINMENT COOLING U2C9 32 CRDM DUCT REPLACEMENT AT RPV HEAD UIC8 May-97 91 io 3:w Page 3 of 7 Nrc_3p

SEQUOYQII CAPITAL PROJECTS LIST

• FISCAL YEARS 1997 - 1999 '

E Am E R R PROJECT TITLE *

$0 E E E Mb $ $ $

PRESSURIZER SArt1 Y VALVES U1C9 1,399 TBD TBD PRESSURIZER SAFETY VALVES U2C8 701 699 SUBTOTAL OUTAGE IMPROVEMENT 2,191 725 117 ICE COND FLOOR MODIFICATIONS ICE COND FLOOR MODIFICATION IllC3 666 600 650 ICE COND FLOOR MODIFICATION U2C9 leQ0 1.350 SUBTOTAL ICE COND FLOOR MODIFICATIONS 666 2,050 2,000 PROJECTS TO IMPROVE RELIABILITY GENERATOR DIAGNOSTIC SYSTEM 200 l GENERATOR DIAGNOSTIC SYSTEM 200 REDUNDANT CUNO FILTER UIC8 Apr-97 142 l CilANGE MFP CONTROLS FROM MilC TO EllC 560 MOTOR DRIVEN AUX FEEDW ATFR WATER LEVEL CONTROL VALVES U2C9 250 355 INSTALL BEARING LUBE WATER UPGRADE SYSTEM (CCW) 502 CHANGE MFP CONTROLS FROM MiiC TO EllC U2C10 100 MOTOR DRIVEN AUX FEEDWATER WATER LEVEL CONTROL VALVES UIC9 545 60 STATION BA I itRY BANK REPLACEMENT Dec-96 42 l

STM. GEN. FEEDWATER INTERFACE PIPING UIC9 1,000 506 STM. GEN. FEEDWATER INTERFACE PIPING U2C9 1,737 PMP FLOODING ISSUE Jul-97 150 CABLE DRIVE FOR TRANSFER SYSTEM U2C9 300 620 UPGRADE AIRBORNE RAD MONITORS-(CAMS) 561 NO. 2 FEEDWATER IIEATER - AUTO BYPASS TO CONDENSER UIC9 200 92 NO. 2 FEEDWATER IIEATER - AUTO BYPASS TO CONDENSER U2C9 75 255 REPLACE RAD MONITOR 0-RE-090-122 Aug-97 298 480V BOARD ROOM SUPPLEMENTAL COOLING 285 185 I 480V BOARD ROOM SUPPLEMENTAL COOLING 250 185 l ROD POSITION INDICATING SYSTEM UIC9 125 550 I,

10 31s6 Page 4 of 7 Nrc 3 p

SEQUOYQH CAPITAL PROJECTS LIST '

. FISCAL YEARS 1997 - 1999 $

1 w

i a gg o ao m

)

I PROJECT TITLE O wm E & R g - - - l

D E i o NE $ $ $ l ROD POSITION INDICATING SYdini U2C9 150 600 l I

YARWAY ARC VALVE REPLACEhENT UIC9 650 85 YARWAY ARC VALVE REPLACEMENT U2C9 200 550 l l

REPLACEMENT OF Tim 125V DC DIESEL GENERATOR BATTERIES 620 l

MAIN GENERATOR VOLTAGE REGULATOR REPLACEMENT UIC9 600 400 MAIN GENERATOR VOLTAGE REGULATOR REPLACEMENT U2C9 100 900 SUPER SHORT CYCLE MODIFICATION UlC8 Apr-97 450 FEEDWATERIEATER SHROUD UPGRADE UIC9 190 50 FEEDWATER IEATER SHROUD UPGRADE tJ2C9 260 DIGITAL MFW CONTROL SYSTEM UIC10 735 1,300 l DIGITAL MFW CONTROL SYSTEM U2C10 550 MANHOLE SUMP PUMPS 340 100 SUBTOTAL PROJECTS TO IMPROVE RELIABILITY I,884 7,896 9,380 CIVIIJSEISMIC ISSUES CIVIL ISSUE - LARGE BORE PIPING REVIEW Jan-97 406 CIVIL ISSUE - UNQUALIFIED PIPING IN AUX BLDG UI 90 CIVIL ISSUE - CCS TIERMAL OP MODE UI UIC9 1,499 CIVIL ISSUE- U2 CCS OP MODES U2C8 400 CIVIL ISSUES (FY97 MONEY IN PCN'S 167,2088,208J, & 2099) ABOVE 2.475 1.485 SUBTOTAL CIVIL > SEISMIC ISSUES 2,395 2,475 1,485 MINOR CAPITAL PROJECTS REPLACE CAT. 2 LIGilTS WITII CAT. I SYSTEM 3 TBD REPLACE TEMPERATURE SWITCIES Feb-97 43 CONTROL BLDG LOW LEAKAGE DAMPERS TBD REDUNDANT VAPOR EXTRACTOR - MAIN TURBINE OIL TAiE U1CIO TBD lilGil PRESSURE ALARM FOR SAFETY INJECTION UIC10 TBD REPLACE ITS ON EGTS & CONTAINMENT AIR RETURN FANS UIC10 TBD SPENT FUEL BRIDGE CRANE IlOIST TBD j

10.3196 Page 5 of 7 Nrc_3p

FISCAL YEARS 1997 - 1999 l

PROJECT TITLE U

g bk h

~

h

~

h

~

I:: E o ME 9 li EQUALIZATION VALVES ON llIGli PRESSURE FILTERS PDS-47-12,17-41 UIC9 TBD TBD EQUALIZATION VALVES ON lilGli PRESSURE FILTERS PDS-47-12,17-41 U2C9 TBD TBD AFWPT I A-S OIL DRAIN SAMPLE VALVE UIC8 Apr-97 15 ADD LOOP L-77-1 (RCDT LEVEL) TD PLANT COMPUTER TBD IIEAT TRACE & INSULATE l-RE-90-106/ll2 LINES Feb-97 84 IIEAT TRACE & INSULATE 2-RE-90-106/112 LINES Dec-96 84 FIRE DETECTION @ AUX BLDG HVAC ROOMS Jan-97 127 REPLACE LUNDELL ANNUNCIATOR UI Jul-97 150 REPLACE LUNDELL ANNUNCIA1DR U2 Jun-97 77 REPLACE SECURITY BACK-UP DIESEL FUEL TANK TBD TBD FIFTil DIESEL SECURITY PROTECTION Nov-96 44 EMERGENT PCN 0282 TBD 52 MINOR CAPITAL WORK DETAIL 1.000 1.000 SUBTOTAL MINOR CAPITAL PROJECTS 676 1,000 1,000 PURCHASE OF TAGGED EOUIPMENT TAGGED EQUIPMENT DETAIL 350 350 MANSEL LEVEL MONITOR SYSTEM 58 TORBO-TOC TURBINE OIL CONDITIONER 77 D/G DATA ACQUISITION SYSTEM 25 RCS VACUUM PUMP 50 X-RAY ANALYZER 130 PIPING VIBRATION MEASUREMENT TRANSDUCER 10 SUBTOTAL PURCHASE OF TAGGED EQUIPMENT 350 350 350 PLANT COMPUTER CHANGEOUT INTEGRATED COMPUTER SYSTEM (ICS) UIC8 Apr-97 4,689 INTEGRATED COMPUTER SYSTEM (ICS) U2C7 Nov-96 282 SUBTOTAL PLANT COMPUTER CllANGEOUT 4,971 0 0 io/3iw Page 6 of 7 Nrc_3p

SEQUOYQH CAPITAL PROJECTS LIST I

FISCAL YEARS 1997 - 1999 o

U DE R R R PROJECT T!TLE * $N E D E Nd D $ $

ENVIRONMENTAL COMPLIANCE PCB RISK REDUCTION 2.149 SUBTOTAL ENVIRONMENTAL COMPLIANCE O 2,149 0 .

MAINTENANCE IMPROVEMENT CVCS VALVE RELOCATION IN ACCUMULATOR ROOM UlC9 300 TBD CVCS VALVE RELOCATION IN ACCUMULATOR ROOM U2C9 300 TBD FOUR ADDITIONAL RCCA'S UIC9 275 150 FOUR ADDITIONALRCCA'S U2C9 250 175 i SUBTOTAL MAINTENANCE IMPROVEMENT 0 1,125 325 PERSONNEL SAFETY ADDITION OF PLANT ACCESS PLATFORMS FOR MSVV'S UIC9 500 100 ADDITION OF PLANT ACCESS PLATFORMS FOR MSVV'S 120 580 ,

SUBTOTAL PERSONNEL SAFETY 0 620 680 s

MANAGEMENT & MISCELLANEOUS EMERGENT WORK 1,000 1,500 - 1,500 CAPITAL SUPPORT 4,400 4,000 4,000 CAPITALIZED WORK REQUESTS 5@

500 500 SUBTOTAL MANAGEMENT & MISCELLANEOUS 5,900 6,000 6,000

' STOTAIR . C61,8% $3.7,046i j26,133t b

to'3:N Page 7 0f 7 Nre_3p ,

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