ML20024J070

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Summary of 940406 & 14 Meetings W/Nei,Epri & Industry to Discuss SG Issues.Meeting Attendees Listed in Encls 1 and 2.Meeting Handouts Also Encl
ML20024J070
Person / Time
Issue date: 08/25/1994
From: Tim Reed
Office of Nuclear Reactor Regulation
To: Strosnider J
Office of Nuclear Reactor Regulation
References
NUDOCS 9409120260
Download: ML20024J070 (64)
v • d • e


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MEMORANDUM T0:

Jack Strosnider, Branch Chief Materials and Chemical Engineering Branch RECEP/en Division of Engineering Office of Nuclear Reactor Regulation 94 g FROM:

Timothy A. Reed, Project Manager Materials and Chemical Engineering Branchi"3 llc DocuMrs Division of Engineering Office of Nuclear Reactor Regulation

SUBJECT:

SUWlARY OF'THE APRIL 6 AND 14, 1994 MEETINGS WIT Q Qfl8.

ENERGY INSTITUTE AND INDUSTRY TO DISCUSS STEAM GEATE 133ULJ On April 6 and 14, 1994, the NRC staff met with representatives of. Nuclear Energy Institute (NEI, Electric Power Research Institute (EPRI) and industry to discuss issues asso)ciated with steam generator degradation specific management'(SGDSM) and ongoing work in the steam generator area. Meeting attendees for the April 6 and 14 meetings are listed in Enclosures I and 2

{

respectively. Meeting handouts are provided as Enclosure 3.

j If there are questions regarding this matter, contact Tim Reed at i

301-504-1462.

Enclosures:

1.

List of Attendees-April Technical Meeting i

2.

List of Attendees-April Management Meeting 3.

Meeting Handouts (for both sessions)

~

cc w/ enclosures:

i See next page i

DISTRIBUTION:

See next page 0FFICIAL RECORD COPY DOCUMENT NAME: APRNTG. MIN To receive a copy of this document, indicate in the box:

"C" - Copy without attachmentfenclosure

- E" - Copy with attar.hment/ enclosure "N" = No copy Office DE:EMCl u E

DE:EMCB:Sdk DE:EMCB:BCk Name TRe dk ESullivan hv JStrosnid[

Date B/h6/94 g /2T'/ 94 6 / 2f '94

/

(PDR-RENSP"ERONUPRC 94095202 940825 A

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,' August fO.994 l I.

V iU MEMORANDUM T0:

Jack Strosnider, Branch Chief j

Materials and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation FROM:

Timothy A. Reed, Project Manager-Materials and Chemical Engineering Branch Division of Engineering Office of Nuclear Reactor Regulation j

SUBJECT:

SUMMARY

OF THE APRIL 6 AND 14, 1994 MEETINGS WITH NUCLEAR ENERGY INSTITUTE AND INDUSTRY TO DISCUSS STEAM GENERATOR 1

ISSUES l

i On April 6 and 14, 1994, the NRC staff met with-representatives of Nuclear Energy Institute (NEI), Electric Power Research Institute (EPRI) and industry to discuss issues associated with steam generator degradation specific management (SGDSM) and ongoing work in the steam generator area. Meeting attendees for the April 6 and 14 meetings are listed in Attachments 1 and 2 respectively. Meeting handouts are provided as Attachments 3.

i If there are questions regarding this matter, contact Tim Reed at 301-504-1462.

t 2

Attachments:

l 1.

List of Attendees-April Technical Meeting l

2.

List of Attendees-April Management Meeting 3.

Meeting Handouts (for both sessions) i cc w/ attachments:

i See next page DISTRIBUTION:

i See next page I

4 OFFICIAL RECORD COPY j

DOCUMENT NAME: AFRKTG. MIN See previous concurrence page To receive a copy of this document, indicate in the box:

"C" - Copy without attachment / enclosure "E" - Copy with attachment / enclosure "N" - No copy Office DE:EMCB E

DE:EMCB:SC C

DE:EMCB:BC C

4 Name Treed

  • ESu111 van
  • JStrosnider*

Date 8/25/94 8/25/94 8/25/94 i

2.

DISTRIBUTION:

w/o attachments:

Russell /Miraglia 12-G-18 R. Zimmerman 12-G-18 OGC E. Jordan w/ attachments:

E. Murphy J. Donoghue R. Jones S. Long J. Craig A. Buslik J. Hopenfeld J. Muscara P. Kadambi A. Thadani G. Holohan T. Speis J. Cunningham ACRS (10)

L. Plisco, EDO 17G21 PUBLIC

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ATTACHMENT 1-f EPRI/NEI STEAM GENERATOR ON DEGRADATION SPECIFIC MANAGEMENT TECHNICAL WORKING GROUP MEETING April 6, 1994 LIST OF ATTENDEES M

ORG/ POSITION Tim Reed NRR/EMCB/SG PM Robert C. Jones NRR/DSSA John W. Craig RES/DE L. J. Cunningham NRR/DRSS David Steininger EPRI Richard Pearson NSP David Modeen NEI John Blomgren Commonwealth Edison Medhi Sarram NEI Rick Mullins Southern Nuclear-Farley Greg Kammerdeiner Dusquesne Light i

Brain Sheron NRR/DE Ron Gamble Sartrex Larry Steinert EPRI Dan Mayes Duke Power Lynn Conner STS, Inc.

Roger Huston TVA i

Joe Hopenfeld NRC l

Ken Karwoski NRR/DE/EMCB Steve Long NRR/DSSA/SPSB l

Emmett Murphy NRR/DE/EMCB l

Ted Sullivan NRR/DE/EMCB i

Theresa Sutter Bechtel Joe Donoghue NRR/DSSA/SRXB Tom Essig NRR/DRSS/PRPB l

Ken Eccleston NRR/DRSS/PRPB j

N. P. Kadambi RES/DSIR/EIB i

l l

l l

ATTACHMENT 2 EPRI/NEI STEAM GENERATOR ON DEGRADATION SPECIFIC MANAGEMENT MEETING EXECUTIVE STEERING COMMITTEE MEETING April 14, 1994 LIST OF ATTENDEES l

i N_AjiE ORG/ POSITION A

Tim Reed NRR/DE/EMCB Themis Speis RES l

Chuck Welty EPRI Marty Virgilio NRR Robert C~ Jones NRR John W. Craig RES Ashok Thadani NRR i

Brian Sheron NRR W.G. Smith Jr.

Am.Elec.Pwr.Syc. Corp j

Larry Shao RES Jack Woodard Southern Nuclear Mike Tuckman Duke Power c

Bill Rasin NEI Bob Smith Rochester Gas & Electric John Blomgren Commonwealth Edison N.P. Kadambi RES/DSIR Arthur Buslik RES/PRAB Kevin Graney SERCH Licensing /Bechtel Bob Borsum B&W Nuclear Technologies Lynn Conner STS, Inc.

George Wunder NRR/PD21 Joe Donoghue NRR/DSSA/SRXB Medhi Sarram NEI Ed Butcher NRR/DRSS Dave Modeen NEI Greg Kammerdeiner Dusquesne Light Co.

Ron Gamble Sartrex Steve Katradis Halliburton NUS Corp Ken Eccleston.

NRR/DRSS/PRPB Steve Long NRR/DRSS/SPSB Emmett Murphy NRR/DE/EMCB Rick Mullins Southern Nuclear Brad Moore Southern Nuclear l

i

t a

b MEETING FOCUS

[

e Presentation of industry status on:

- Leakage monitoring

- Integrated tube pull program

- Validity of data Discussion.of how these items are being addressed, if at all, in the draft generic letter on interim plugging criteria t

SUMMARY

PROGRESS IS BEING MADE WITH THE NRC ON SGDSM & THE STEAM GENERATOR RULE

- WE BELIEVE WE HAVE MATCHED THE EXPECTATIONS OF THE TWO TECHNICAL STEERING COMMITTEES

- AGREEMENT ON THE PROCESS FOR DEFINITION AND RESOLUTION 1

OFISSUES

  • NO TECHNICAL ISSUES REQUIRING RESOLUTION BEFORE GENERIC LETTER IS DRAFTED REVIEW OF SGDSM DDCUMENTS IS BEGINNING, BUT NOT COMPLETE MAJOR CONCERNS -

- MEETING THE SCHEDULE

- OTHER UTILITY SUBMITTALS DEPLETING RESOURCES r

l

5 W

SGDSMISSUE RESOLUTIONPROCESS SUBMIT SGDSM DOCUMENTS

^

COMPLETE TO NRC FOR REVIEW SUBMIT COMMENTS ON 1477 COMPLETE i

I NRC OUTLINES SYSTEMS &

COMPLETE NRC OUTLINES OPERATION ISSUES MATERIALS & OTHER ISSUES INDUSTRY PRESENTS WORK COMPLETED ON 50% COMPLETE NRC SYSTEMS & OPERATIONS ISSUES STEERING COMMITTEES AGREE ON REMAINING ISSUES & SCOPE REQUIRING RESOLUTION STAFF & INDUSTRY DEVELOP RESPONSES ON REMAINING ISSUES ISSUES RESOLVED j

f NRC COMMENTS / ISSUES OPERATIONAL LEAKAGE 1

t

  • SGTR SUPPOSED TO BE INCREDIBLE EVENT YET 1/100EFPY

- REDUCE RUPTURE FREQUENCY BY SHUTDOWN ON EXCEEDING LEAKAGE THRESHOLD l

- HOW MUCH DELAY IS FEASIBLE ?

- LOTS OF RUPTURES AVOIDED BY TAKING ACTION FIRST PALO VERDE 2 RESTART CONTINGENT ON ON-LINE LEAKAGE MONITORING

- LEAKAGE MONITORING AVOIDED 6 WEEK SHUTDOWNS ISSUEAREAS;

1. LEAKAGEDURING OPERATIONLEADING TO TUBE RUPTURE AT NORMAL OPERATING CONDITIONS
2. OPERATOR RESPONSE TO OPERATIONAL LEAKAGE --- AOP's l

RESOLUTIONS;

1. LEAKAGEPRESENTATION & CANRUPTUREFREQUENCYBE REDUCED---GETRUPTURE FREQUENCY &LEAKRATEDATA
2. LEAKAGEMONITORING GUIDELINE

NRC COMMENTS / ISSUES ACCIDENT LEAKAGE

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  • BEST APPROACH FOR DETERMINING ALLOWABLE LEAKAGE IS TO WORK BACKWARD FOR ALLOWABLE DOSE AT SITE BOUNDARY
  • l-131 ACCIDENT OF CONCERN IS SLB WITH ARC CAUSED LEAKAGE - NOT CLASSICAL MSLB
  • PROBABILITY OF LEAKAGE PER VOLTAGE INCLUDES NON-THROUGH WALL CRACKS OPENING DURING TRANSIENT TEST GOODNESS OF FITS
  • EVALUATE ALTERNATE MODELS FOR EOC VOLTAGE DISTRIBUTIONS
  • HOW DO WE TREAT INDICATIONS NOT CONFIRMED BY RPC ?

VOLTAGE LIMITS SHOULD CONTINUE TO USE CONSERVATIVE CONFIDENCE LIMITS i

  • USE GENERIC ANALYSIS FOR SLB PROBABILITY OF BURST APPROPRIATE LEAKRATE vs. VOLTAGE RELATIONSHIP ?

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1. BOUNDARYDOSE CALCULATIONFOR ACCIDENT CONDITIONS
2. FITMETHODOLOGYFORLEAKAGE DATABASE
3. EOC VOLTAGE DISTRIBUTION
4. RPC ODSCC CONFIRMATION & SENSITIVITY t

RESOLUTIONS;

1. BOUNDARYDOSEAPPROACHINCLUDEDEXPLICITLYINSGDSMMETHODOLOGY

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2. AGREE ONSTATISTICAL & UNCERTA1NTYANALYSIS APPROACHES FOR ARC
3. AGREE ONDATA USEDINALLMODELS 4 AGREE ON& EVALUATEIMPACTOF VARIOUS RPC NON-CONFIRMATIONASSUMPTIONS.

i NRC COMMENTS / ISSUES i

IODINE SPIKING I RELEASE SOURCE TERM t

DATABASES MAY NOT APPLY TO ACCIDENTS OF INTEREST (i.e., MSLB)

- RATE & MAGNITUDE OF PRESSURE & TEMPERATURE TRANSIENTS AFFECT SPIKE

  • POTENTIAL FOR SIGNIFICANT FISSION PRODUCT CARRYOVER

- RELAP NOT FOR STEAM GENERATOR SECONDARY ANALYSIS ISSUEAREAS;

1. DATABASEAPPLICABILITY
2. FISSIONPRODUCTCARRYOVER s

RESOLUTIONS;

1. TECHNICAL DISCUSSION TO AGREE ONDATABASEAPPLICATION
2. TECHNICAL DISCUSSION TO AGREE ON CARRYOVER

NRC COMMENTS / ISSUES SEVERE ACCIDENT CREEP RUPTURE OF TUBING

  • DEMONSTRATE TUBE TEMPERATURE < 1000 F LEAKAGE FLOW TH:+iOUGH CRACKS AT 1000 F OR HIGHER FRACTURE MECHANICS ANALYSIS INDICATED PRIMARY PIPING FAILURE BEFORE S/G TUBE FAILURE DURING TMLB' SEVERE ACCIDENT ISSUEAREAS;
1. SEVERE ACCIDENT TUBE TEMPERATURE
2. CONSEQUENCES OFHIGH TUBE TEMPERATURE
3. PRIMARYPIPING FAILURE BEFORE TUBE FAILURE RESOLUTIONS; 1.SIG TUBESREMAINBELOWABOUT1000F 2.SIG TUBESREMAINBELOWABOUT1000F
3. SEVERE ACCIDENTISSUE NOTA SGDSM ISSUE BUT TO BE ASSESSED FROMA RISK PERSPECTIVE i

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NRC COMMENTS / ISSUES INCORPORATION OF NON-U.S. DATA INTO

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DATABASE CONFIRMATION OF BELGIAN CROSS CAL!N ATION FACTOR OF 1.7 USE OF EDM NOTCHES vs. FIELD CROSS t.,wd3 RATION DATA BETWEEN BELGIAN & E STANDARDS MAGNITUDE OF THE CORRECTION NOT UNDERSTOOD ISSUEAREAS;

1. METHODOLOGY
2. STANDARDDESIGNDETAILS
3. MAGNITUDE OF CORRECTION RESOLUTIONS;
1. REVIEW & ACCEPT CROSS CALIBRATIONMETHODOLOGY& RESULTS FOR BELGIAN &

OTHER EUROPEANDATA.

2. ACCEPTCROSS CALIBRATIONMETHODOLOGY
3. CLEARLYIDENTIFYDATA INARCDATABASE WIHCHIS NON-U.S.

4 NRC COMMENTS / ISSUES INSPECTION

  • 20% ANALYST VARIABILITY
  • ODSCC VOLTAGE CALIBRATION METHODOLOGY 20% HOLES vs. 4-100% HOLES
  • PROBE VARIABILITY CONTROL
  • PROBE WEAR CONTROL
  • ECT SIGNAL-TO-NOISE CRITERIA
  • SHOULD PERFORM RPC BASED MlX RESIDUAL THRESHOLD

+ BOBBIN COIL PROBE SIZE ACCEPTANCE

  • POD DATABASE AND ACCEPTANCE ISSUEAREAS;
1. UNCERTAINTYOFINSPECTIONMETHODOLOGYDETAILS
2. UNCERTAINTYOFEQUIPMENTQUALIFICATIONREQUIREMENTS
3. UNCERTAINTYOFANALYSTQUALIFICATIONREQUIREMENTS
4. QUALIFICATION OF SMALL DIAMETER PROBES RESOLUTIONS;
1. REVIEWINDUSTRYPROPOSED NDE GUIDELINE AND ARC DOCUMENTS
2. IMPLEMENTPERFORMANCE DEMONSTRATIONPROGRAMAND EVALUATE DATA
3. UNDERSTAND RELATIONSHIP OF NDE GUIDELINES, ECTPERFORMANCE DEMONSTRATION & ARCINSPECTION REQUIREMENTS
4. PERFORMAND DOCUMENTPROBE PERFORMANCE QUALIFICATION

NRC COMMENTS / ISSUES SGDSM DATABASE

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l NEED MORE PULLED TUBE DATA

  • TUBE PULLS ARE EXPENSIVE
  • NEED EXPLICIT REASONS FOR TUBE PULLTO ASSURE APPROPRIATE TUBES ARE PULLED ISSUEAREAS;
1. SGDSMDATABASENEEDS TOBEMAINTAINED
2. MORE TUBE PULL DATA REQUIRED RESOLUTIONS;
1. DEFINEANDIMPLEMENTSGDSMDATABASEMANAGEMENT& REPORT UPDATE MECHANISM
2. DEVELOPINDUSTRYAPPROACH TO TUBE PULLS WITHSPECIFIC SELECTION CRITERIA

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SUMMARY

- WE BELIEVE WE HAVE MATCHED THE EXPECTATIONS OF THE TWO TECHNICAL STEERING COMMITTEES t

- AGREEMENT ON TtlE PROCESS FOR DEFINITION AND RESOLUTION OFISSUES NO TECHNICAL ISSUES REQUIRING RESOLUTION BEFORE GENERIC LETTER IS DRAFTED

  • REVIEW OF SGDSM DOCUMENTS IS BEGINNING, BUT NOT COMPLETE MAJOR CONCERNS.

- MEETING THE SCHEDULE

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- OTHER UTILi1Y SUBMITTALS DEPLETING RESOURCES

INDUSTRYSTEAM GENERATOR TUBEPULL PROGRAM DEVELOPED BY THE Ad-Hoc STEAM GENERATOR ALTERNATE REPAIR CRITERIA COMMITTEE INMEETING MARCH 4,1994 NEl/EPRl/NRC SGDSM TECHNICAL STEERING COMMl1 TEE APRIL 6,1994 WASHINGTON, D.C.

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PROGRAM OBJECTIVES 1.

IMPLEMENT THE MISSION OF THE 'SGDSM' INDUSTRY IMPLEMENTATION INITIATIVE r

2.

ENHANCE & VALIDATE ARC STEAM GENERATOR TUBE LEAK AND BURST CORRELATIONS 3.

COLLECT & EVALUATE TUBE PULL DATA OVER THE FULL RANGE OF ARC APPLICABILITY 4.

SHARE THE RESPONSIBILITY OF S/G TUBE PULLS 5.

COLLECT & USE TUBE PULL DATA IN THE QUALIFIED DATA ANALYST (QDA) PROGRAM

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6.

TEST USING STANDARD INDUSTRY GUIDELINES i

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PROGRAMIMPERATIVES I

1. REMOVE 3 INTERSECTIONS WITH EACH TUBE PULLED 2.

1 TUBE PULL MINIMUM REQUIRED FOR EACH ARC IMPLEMENTED AT A PLANT

3. MORPHOLOGYIS MINIMUM ANALYSIS REQUIRED 4.

LOW LEVEL OF ONGOING TUBE PULLS & ANALYSES TO IMPROVE INDUSTRY DATABASES l

5. ALL TUBE PULL ANALYSIS AVAIL.ABLE TO INDUSTRY DATABASE

PROGRAM OUTLINE I

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1. PLANT SPECIFIC REQUIREMENTS TO IMPLEMENT ARC
a. OBJECTIVE: Assure morphologyis within the Requirements for the ARC Applied on a Plant Specific Basis.

1

b. Minimum Pull 1 Tube with 3 Intersections
c. Pull Accessible Tube with the Largest Indication
d. Focus on ODSCC Voltages > 2 Volts
e. Evaluate NDE Parameter & Metalography
f. AII Data Provided to the Industry SGDSM Database 1

1 t

PROGRAM OUTLINE 2.

PULL 1 TUBE EVERY OTHER OUTAGE UNTIL A MINIMUM OF 1 INTERSECTION IS ADDED TO EACH OF 3 NDE PARAMETER BINS

a. OBJECTIVE: Enhance the Industry SGDSM Database l
b. Remove Tube with the Largest Accessible Indication
c. Remove 3 Intersections for each tube pulled
d. ODSCC Bins Defined by Voltage Ranges of; 2-4 voits, 4-8 volts & 8-15 volts
e. Evaluate for Operational Leakage, MSLB Leakage &

Burst Capability

f. All Data Provided to the Industry SGDSM Database

PROGRAM OUTLINE

3. INDUSTRY DATABASE ENHANCEMENTS FOR OPERATIONAL & ACCIDENT LEAKAGE AND BURST CORRELATIONS I
a. OBJECTIVES: a) Enhance and Validate Leakage and Burst Correlations, b) Inspection Reliability improvement
b. Remove Tube with Largest Accessible Indication
c. Evaluate for Operational Leakage, MSLB Leakage &

Burst Capability

d. Input Data for Sizing & POD Evaluations
e. Focus on Extending the Database Range &

Correlations l

i

1 Monitoring '

of Small Steam Generator Tube Leakage i

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(< Technical Specification Limit)

Presentation to the NRC by the SGDSM Technical Steering Committee April 6,1994

  • Survey
  • Industry Guidelines Proposal Richard P. Pearson Northern States Power, Prairie Island Nuclear Plant o...

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Review of Site Specific Abnormal Operating Procedures for Steam Generator Tube Leaks i

Outstanding Response: Procedures reviewed from 26 sites shof 26 Procedures met my criteria for "SMALL LEAKS" e18 of 26 Procedures required actions based on "above normal"or

" increasing trends".

  • 12 of 26 Procedures provided detailed guidance for sampling and trending as a function of leak rate value and/or rate of change.

Procedures are from U.S. Utilities Only NROnek.944 2

Telephone Survey of Steam Generator Tube Leak Monitors Excellent Response: 43 sites / units responded

1. Do You Have N-16 Monitors?

Installed 18 Planning to Install

....................................5

2. Is the N-16 Instrument Monitored in Control Room?

14

3. What type of Air Ejector Monitor do you have?

Geiger-Mueller 1 5 Scintillation Counter 3 2 (4 had both)

OffMN.ek.944 3

STEAM GENERATOR TUBE LEAKAGE 0

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I Outline for Steam Generator Tube Leakage Monitoring Guidelines I

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1. Background Information i

e Purpose Acknowledge Current Plant Expertise Capture the Historical Experience Address NRC Concernd-i e Types of Tube Degradation which have resulted in Tube Leak Outages Fatigue U-Bend PWSCC Free Span Cracks Loose Parts Wear Wayward Plug Tops Roll Transition Zone PWSCC t

Etc.!

e Examples of Actual Plant Leakage Trends.

NRO.ek.944 I

i

2. Monitoring Methods e Radiation Monitors Air Ejector Radiation Monitor Steam Line Radiation Monitor - N-16 Steam Generator Blowdown System Monitor e Steam Generator Blowdown Liquid Samples Tritium, Fission Products, Argon, Sodium o Air Ejector Gas Samples analyzed for Fission Products and Activation Products eBlowdown Sample Filters and lon Exchange Columns
3. Leak Rate Calculations Mathematics Sensitivities of Each Method Accuracy of Each Method Calibration of On-line Monitors to Known Leakage Effect of Primary Activity on Sensitivity Effect of Reactor Power Level and Power Changes NM 11 i

i 4, Operational Response to Indications of Primary to Secondary Leakage e Recommendations for Sampling when Monitors are out of service -

l Technical Specification versus Practical Needs

  • Recommendations for increased Trending and Sampling based on

- Leak Rate

- Change in Leak Rate

  • Use of Setpoint Changes for Process Radiation Monitor Alarms e Use of Action Levels
  • Use of Logic Diagrams NROeek.944 12

h EPRl/NP I

p SGDSM PRIMARY-TO-SECONDARY LEAKAGE GUIDELINES COMMil I EE 5

13

EPRl/NP AD-HOC COMMil I EE MEMBERS s

Bob Thomas (EPRI)-Chairman Gary Brobst (GEBCO)

Walter Lach (Maine Yankee)

Jim Stevens (Commanche Peak)

Pete Penseyres (SONGS)

Larry Wilson (Duke Power)

Ricky Espolt(ANO-2)

Bruce Luthanen Greg Interline (Se(CY) quoyah)

Jesse Davis (C. Cliffs)

Dwight Hostetter (S. Nuclear)

David Hughes (TVA)

Guy Holmes (Kewaunee)

Randy Lewis (CP&L)

Jeff F olland (STP)

David Worley (CR3)

John Stevens (GPU)

Vick Linnenbaum (Duquesne)

Matt Kearns (IP3)

Ray Burns (IP2) 0

/1

EPRl/NP SCHEDULn e

i March 1-8 Establish Committee April 11 Strawman Document to Committee April 27 First Committee Meeting - Chicago i

May 27 Second Draft to Committee June 15 Second Committee Meeting July 1 Written Comments from Committee July 15 Third Draft to Comm'ittee Aug.1 Final Committee Comments due Aug. 31 Final Draft to Committee and TAG Sept.1 Final Committe Mtg. - Resolve TAG Comments (if necessary)

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EPRl/NPD Steam Generator Degradation Specific Management (SGDSMT Exclusion of Test Data from SGDSM Database David A. Steininger Program Manager EPRI NRC Meeting - April 6,1994 Steam Generator

EPRl/NPD What criteria is followed to identify test data as inappropriate for correlation development?

Per NRC's response to draft NUREG-1477's industry comments (NRC/EPRl/NUMARC Meeting,2/8/94%

General Criteria Test point deletion or modification is appropriate if

1. Data is associated with an invalid test
2. Morphology related criteria is rigorously defined and applied to all data

- Criteria must be able to be unambiguously applied by an independent observer

3. Action results in conservatism I

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EPRl/NPD What are the specific reasons for test point \\'

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deletion using these generai criteria?

Application to test data for ODSCC at tube support plates Criterion 1. Invalid test 1

Eddy current signal corruption I

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- Exclude data from all correlations Inadequate burst test

- Exclude data from burst correlation Inadequate leak test

- Exclude data from leak correlation Tube damage from tube pull forces

- Exclude from leak test if supported by analysis Leak test not performed and destructive examination inadequate to verify leakage potential

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- Exclude data from probability of leak correlation Steam Generator a

EPRl/NPD What are the specific reasons for test point deletion using these generai criteria? (con't)

Application to test data for ODSCC at tube support plates Criterion 2. Morphology related criteria Atypical degradation with less than or equal to 2 ligaments and maximum penetration less than 60%

Exclude data from all correlations Note: Removal of these data,which can be classified as systematic errors, is conservative relative to correlation mean Systematic error incorrectly influences standard deviation of probability distribution associated with random effects Severe degradation with voltages greater than 20 volts larger than next data point Note: An isolated singular data point should not define distribution l

tail Steam Generator

i EPRl/NPD What are the specific reasons for test point deletion using these generai criteria? (con't)

Application to test data for ODSCC at tube support plates l

Criterion 3. Test measurement error (reasons not as obvious as criterion 1)

Leak rate inconsistent with measured thruwall crack length (i.e. leakage is too low)

SLB leak rate less than or close to normal operating leak rate Exclude data from leak rate correlation Note: Leak flow path plugs with foreign material is possible cause for these test measurement errors

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Steam Generator

EPRl/NPD Are all NRC's general criteria for allowance of data point removalmet?

Yes

-Invalid test or measurements eliminate data points

--Well defined, quantitative morphology associated criteria used to identify atypical degradation that produces systematic error to the correlation if used

-Morphology test point deletion criteria can be unambiguously applied by an independent observer

-Test points removed (not including bad test data'i add conservatism to correlation mean at i

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voltage range of interest 6

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SENIOR LEVEL MANAGEMENT MEETING NRC/EPRl/NEI/ INDUSTRY l

STEAM GENERATOR DEFECT SPECIFIC MANAGEMENT i

a APRIL 14,1994 h

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STATUS OF SG RULE l

  • NRR HAS DRAFTED ANPR--IN CONCURRENCE (CURRENTLY IN l

SYSTEMS DIV) e CURRENTLY DRAFTING A COMMISSION PAPER (ISSUE ANPR UNDER SECY SIGNATURE)

SCHEDULE IS TO ISSUE ANPR BY JUNE 30,1994 1

FOLLOWING ANPR ISSUANCE-- GREATER DETAILED TECHNICAL DISCUSSIONS W/ INDUSTRY CAN BEGIN OVERALL SCHEDULE IS TO ISSUE FINAL RULE BY THE END OF 1995 m

STATUS OF GENERIC LETTER

  • GENERIC LETTER CRGR PACKAGE IS COMPLETE i

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  • SG T5CHNICAL STEERING COMMITTEE HAS REV j

PACKAGE i

  • THE NEXT ACTION IS TO MEET WITH SG EXECUTIVE STEERING I

I COMMITTEE (NEXT WEEK)

  • FINALIZE THE PACKAGE
  • PACKAGE INTO LINE CONCURRENCE
  • BEST ESTIMATE IS FOR GL IS TO MEET WITH CRGR APPROX MID-MAY
  • DELAYS DUE TO CRYSTAL RIVER AND BRAIDWOOD ISSUE
  • POTENTIAL ADVERSE SCHEDULAR IMPACT FOR LICENSEES WANTING TO USE THE GL FOR FALL OUTAGES
  • SIGNIFICANT IMPACT FOR PLANT SPECIFIC REVIEW

OTHER AGENDA ITEMS -

elNDUSTRY WILL SUMMARIZE PRESENTATIONS MADE AT APRIL 6 TECH MTG l

elNDUSTRY WILL DISCUSS THElR PROBLEM / ISSUE LIST DISCUSSED AT APRIL 6 MTG

>NRC PROVIDED FEEDBACK FOR ADDITIONAL ITEMS DURING THE APRIL 6 MTG I

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i Steam Generator Defect Specific Management Industry - NRC Senior Management Interaction April 14,1994 Rockville, MD i

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i-l MEETING OBJECTIVES Review list of ic entified issues and 3

l potential resolution Discuss status of draft generic letter j

and ANPR i

Identify "uture actions NEl i

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SUMMARY

OF APRIL 6,1994 i

MEETING INTEGRATED TUBE PULL l

PROGRAM i

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Objectives

- Implement the mission of the 'SGDSM' l

industry implementation initiative

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- Enhance & validate ARC steam generator i

tube leak and burst correlations 1

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- Collect & evaluate tube pull data over the j

full range of ARC applicability

- Share the responsibility of S/G tube pulls

- Collect & use tube pull data in the qualified data analyst program i

- Test using standard industry guidelines 1

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SUMMARY

OF APRIL 6,1994 MEETING INTEGRATED TUBE PULL PROGRAM (cont'd?

<ey Aspects

- 1 tube pull minimum required for each ARC implemented at a plant

- 1 tube pull every other outage thereafter (until adequate data is obtained)

- Remove 3 intersections with each tube pulled

- Morphology is minimum analysis required

- All tube pull results available to inc :stry database NEl

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SUMMARY

OF APRIL 6,1994 l

i MEETING, EXCLUSION OF TEST DATA FROM SGDSM DATABASE

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l Tes: data point de etion or modification is appropriate if:

- Data is associated with an invalid test

- Morphology related criteria atypical degradation with less than or equal to 2% ligament and maximum penetration less than 60%

a severe degradation with voltages greater than 20 volts larger than the next data point j

- Test measurement error I

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SUMMARY

OF APRIL 6,1994 l

MEETING, LEAKAGE

- MONITORING & RESPONSE 1

Review of industry operating l

j experience l

Outline for steam generator :ube l

leakage monitoring guide ines 1

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- Background information i

- Purpose I

Types of tube degradation Examples of actual plant leakage l

trends t

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- Monitoring methods i

Radiation monitors l

SG blowdown liquid samples l

Air ejector gas samples l

Blowdown sample filters and ion l

exchange I

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SUMMARY

OF LEAKAGE l

MONITORING & RESPONSE l

(cont'd) l

- Leak rate calculations Mathematics 1

Sensitivity of each method & accuracy Calibration of on-line monitors Effect of primary activity on sensitivity i

a Effect of reactor power level NEl

SUMMARY

OF ISSUES

. PRIORITY OF RESOLUTION i

1) Inc us':ry tube pull program
2) Criteria for selection of valid data i

points

3) Primary to secondary leakage monitoring program
4) Probability of detection models
5) Leak rate correla': ion Other issues SGDSM database maintenance and review NDE guidelines and ARC document review Euro3ean database cross calibration locine spiking and source terms NEl

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STATUS OF GENERIC LETTER i

AND ANPR i

Higlest 3riority: Issuance of l

generic letter on lnterim Plugging Criteria

- Acceptance of SGDSM methodology

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- Coordinate / limit plant-specific submittals to avoid redirecting NRC staff resources

- Industry /NRC interactions to support l

resolution of technicalissues l

Seconc ary Priority: SG rulemaking

- Coordinate industry comments on the Advance Notice of Proposed Rulemaking (ANPR) and proposed rule l

- Screening, prioritization, scheduling, and funding of supportive industry activities l

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SUMMARY

OF ISSUES S

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.SGDSM METHODOLOGY i

  • Issues

- Define the acceptable approach for l

Probability of Detection (POD) development

- POD vs. indication size

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- Statistical correlation approaches for SGDSM

- Degradation growth incorporation methodology Resolution

- Agree on POb development approach

- SGDSM correlation agreement

- Degradation growth methodology agreement NEl

SUMMARY

OF ISSUES SGDSM DATABASE Issue

- SGDSM database needs to be maintained

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- More tube pull data required Resolution f

- Define and implement SGDSM database management and report update mechanism

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- Develop industry approach to tube pulls with

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specific selection criteria i

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SUMMARY

OF ISSUES j

. OPERATIONAL LEAKAGE l

I Issues j

- Leakage during operation leading to tube rupture at normal operating conditions

- Operator response to operational leakage -

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- AOP's 2

Resolution i

- Obtain operating experience data on tube j

leak rates and ruptures - can rupture i

frequency be reduced i

- Assess adequacy of current leakage i

monitoring systems / methods and response l

guidance l

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SUMMARY

OF ISSUES ACCIDENT LEAKAGE i

Issues

- Boundary dose calculation for accident conditions

- Fit methodology for leakage database

- End of Cycle (EOC) voltage distribution

- RPC ODSCC confirmation & sensitivity Resolution

- Include boundary dose approach explicitly in SGDSM methodology

- Agree on statistical & uncertainty analysis approaches for Alternate Repair Criteria (ARC)

- Agree on data used in all models

- Agree on & evaluate impact of various RPC non-confirmation assumptions

- Agree on crack growth rate estimates NEl

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SUMMARY

OF ISSUES IODINE SPIKING & RELEASE AND SOURCE TERM Issues

- l-131 database may not apply to accidents ofinterest

- Ability of RELAP5 code to model the potential for significant fission product carryover Resolution

- Technical discussion to agree on database applicability

- Technical discussion to agree on carryover modeling/ analysis method

- Revisit Standard Review Plan and SAR Chapter-15 Accident Analyses; reflect a more mechanistic approach NEl

SUMMA,RY OF ISSUES SEVERE ACCIDENT CREEP RUPTURE OF TUBING ISSUES

- S/G (steam generator) tube temperatures under severe accident conditions 1

- Consequences of high tube temperature:

primary piping fails before or after S/G tubes

- Radiological consequences of containment bypass Resolutioris:

- Demonstrate S/G tubes remain below about l

l 1000 F (creep failure unlikely)

- Assess risk significance (likelihood and/or l

consequences) relative to Safety Goal Policy l

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SUMMARY

OF ISSUES INCORPORATION OF NON-U.S.

DATA INTO DATABASE Issues

- Methodology for deriving cross calibration factors (e.g., Belgians and other Europeans)

- Details of Westinghouse and European standard designs

- Magnitude of correction (Belgian) not understood Resolution

- Review & accept cross calibration methodology & results for Belgian & other European data

- Achieve acceptance of cross calibration methodology

- Clearly identify data in ARC database which is non-U.S.

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l-SUM MARY OF ISSUES INSPECTION i

i ssues

- Uncertainty ofinspection methodology details

- Uncertainty of equipment qualification j

requirements s

- Uncertainty of analyst qualification i

requirements

- Qualification of small diameter probes Resolution l

- Review industry proposed NDE guideline and ARC documents l

- Implement performance demonstration program and evaluate data

- Understand relationship of NDE guidelines, ECT performance demonstration & ARC l

inspection requirements

- Perform and document probe performance qualification l

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