ML20216D923
| ML20216D923 | |
| Person / Time | |
|---|---|
| Issue date: | 09/02/1997 |
| From: | Birmingham J NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| IEIN-97-049, IEIN-97-49, NUDOCS 9709100015 | |
| Download: ML20216D923 (92) | |
Text
' ,
September 2.-1997~
MEMORANDUM TO: David B. Matthews. Chief Generic Issues and Environmental Projects Branch i Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Joseph L. Birmingham Project Manager Original Signed By:
Generic issues and Environmental ProjectsBranch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF AUGUST 27, 1997. MEETING WITH B&W OWNERS GROUP AND FRAMATOME TECHNOLOGIES ON NRC INFORMATION NOTICE 97-49 AND PLANS-FOR STEAM GENERATOR TUBE ALTERNATE REPAIR CRITERIA On August 27, 1997, representatives of the B&W Owners Group (B&WOG) and Framatome Technologies (Framatome) met with U.S. Nuclear Regulatory Commission staff to present information about the status of'B&WOG activities to better resolve steam generator tube integrity and plans for alternate repair criteria (ARC) in once through steam generators (OTSG). The Owners Group and Framatome presented an overview of activities to date, current status, and actions planned for the near future. The overview included a discussion of emerging issues and new degradation mechanisms related to OTSG tubes and B&WOG actions taken to include the new issues and mechantsnis in their resolution program.
Details of the above ',opics are in Attachment I which is the slides presented by B&WOG during the meeting. Also, a list of meeting attendees is provided in Attachment 2.
Attachments: As stated cc w/atts: See next page Distribution:
Central File.(w/atts 1&2)
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% * * . . + /) September 2, 1997 l
l MEMORANDUM T0: David B. Matthews. Chief t
! Generic issues and Environmental '
Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Joseph L. Birmingham Project Manager .
Generic issues and Environmenta Projects Branch .
dd W9 Division of Reactor Program Ma agement Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF AUGUST 27. 1997 MEETING WITH B&W OWNERS GROUP AND FRAMATOME TECHNOLOGIES ON NRC INFORMATION NOTICE 97-49 AND PLANS FOR STEAM GENERATOR TUBE ALTERNATE REPAIR CRITERIA On August 27. 1997, representatives of the B&W Owners Group (B&WOG) and Framatome Technologies (Framatome) met with U.S. Nuclear Regulatory Commission staff to present information about the status of B&WOG activities to better resolve steam generator tube integrity and plans for alternate repair criteria (ARC) in once through steam generators (OTSG). The Owners Group and Framatome presented an overview of activities to date, current status, and actions planned for the near future. The overview included a discussion of emerging issues and new degradation mechanisms related to OTSG tubes and B&WOG actions taken to include the new issues and mechanisms in their resolution program.
Details of the above topics are in Attachment 1 which is the slides presented by B&WOG during the meeting. Also, a list of meeting attendees is provided in Attachment 2.
Attachments: As stated cc w/atts: See next page
== s
.k TUBE DEGRADATION IN ONCE THROUGH STEAM GENERATORS CURRENT STATUS AND UTILITY ACTIONS AUGUST 1997 l
B&WOG SG Committee / NRC Meeting
^"# '
Rockville, Md. whi
\* .
Attachment 1
MEETING OBJECTIVES Continue Communication With NRC on OTSG Tube ;
Degradation
- Previous Meetings in I1/94 and 3/96
- Identifv Emerging Issues / New Degradation Mechanisms
- Information Notic 47-49
- Discuss B&WOG Actions to Address Emerging Issues of Concern
- Get NRC Feedback on B&WOG Actions B&WOG SG Committee / NRC Meeting, i ^"S# * '
Rochille, Md. 6 i
e AGENDA
- Meeting Objectives
- Plant Operation Summary
- Update on ECT Results & Tube Pull Analyses
- Emerging Areas of Concern .
- Applicable B&WOG Projects
- Summary i
B&WOG SG Committee / NRC Meeting, August 27,1997 Rockville, Md. g 3
PLA3 T OPERATING
SUMMARY
COM OP CHEM CLNG CURRENT PLANT DATE DATE EFPY Thot ONS-1 7/73 9/87 17.5 602 ONS-2 9/74 2/88 17.I 602 ONS-3 12/74 Planned 9/98 16.6 602 ANO-1 12/74 10/90 15.5 602 TMI-1 9/74 9/91 13.5 604 CR-3 1/77 -
12.2 603 DB-1 7/78 Planned 4/00 11.7 605 -
1 B&WOG SG Committee / NRC Meeting
^"E# ui
'I Rockville, Md.
PLANT OPERATING
SUMMARY
CONT'D.
Pri-Sec Fuel Cycle # Sleeves Leak Limit, GPD Length % Plugged In Service PLANT Tech Spec / Admin. (Months) Per SG (A/B) Per SG (A/B)
ONS-1 504/150 16 2.8 / 8.7 236/ 193 ONS-2 504/150 16 2.4 / 3.3 277/260 ONS-3 504/150 16 3.5 / 3.3 286/253 ANO-1 500/144 16 4.1 / 2.0 476/484 TMI-l 144 /NA 24 8.1 / 2.6 248/253 CR-3 150 /NA 24 1.1 / 4.2 163 / 162 DB-1 1440/ 100 22 2.6 / 0.6 199/212 Note: % Plugged Includes Effect ofIn-Service Sleeves B&WOG SG Committee / NRC Meeting, August 27,1997 Rockville, Md. :
i
EDDY CURRENT INSPECTION SCOPE Bobbin Coil MRPC Upper Rolls RPC Sleeves
- PLANT (A / B) (A / B) A (A / B)
ONS-1 100 % /100 % 20% /20% 100% /100%
11/95 Planned 9/97 11/95 ONS-2 100 % / 100 % 20% /20% 20 % / 21 %
4/96 Planned 4/98 4/96 ONS-3 100% /100% 20% /100% 59 % / 51 %
10/96 10/96 10/96 ANO-1 100% /100% 21 % / 21 % 100% /100%
9/96 9/96 9/96 T M I-I 23% / 23% m 21 % / 21 % 52 % / 51 %
9/95 Planned 9/97 9/95 CR-3 100% /100% 100% /100% 40% / 0%
6/97 6/97 6/97 DB-1 20% /20% 10% / 3% 20% /31%
3/96 3/96 3/96
- 1. TMI-I Plans 100% Bobbin Exam for 9/97
- 2. Where Planned Inspection is Given, Previous Inspections Consisted Only of Re-rolled Locations
= OWNER $GROUF B&WOG SG Committee / NRC Meeting' August 27,1997 6 R&lk Mi i
PREVIOUSLY IDENTIFIED MECHANISMS
- VOLUMETRIC IGA
- HIGH CYCLE FATIGUE PARTICLE IMPINGEMENT AND EROSION l
- FRETTING WEAR
" ## "E' 7 August 27,1997 ;
...-.2 . - - . _ - _ _ _ . _ _ _ _
VOLUMETRIC IGA
- Increasing Number of Small Amplitude Indications in Freespan
- May Be Due to Improved Inspection and Analvsis Techniques
- Growth Rates Are Low
- Alternate Repair Criteria Being Pursued
- Has Been Discussed Previously With NRC
- First Partial Submittal Has Been Made
- ANO-1 Is Lead Plant B&WOG SG Committee / NRC Meeting,
^"# '
Rockville, Md. m d
HIGH CYCLE FATIGUE
- Circumferential Cracking Near Open Tube Lane Due to High Secondary Side Cross Flow I
All Plants Have Preventively Sleeved Susceptible Area No Identified Failures (Tube Leaks) Since 1994
- Plants Inspected Border Around Preventive Sleeving Area in Response to GL 95-03 Plants Continue to Monitor Susceptible Area (Lane / Wedge)
B&WOG SG Committee / NRC Meeting,
^" 'I Rockville, Md. M i
PARTICLE IMPINGEMENT / EROSION
- Continues to be Observed at Oconee Units Only
- Located Within 2" of TSP's, Typically Upper Bundle
- Significant Contributor to Total Tubes Plugged at Oconee
- Not Observed in Other Plants
- Tubes Repaired Based on App. H Qualified Depth Measurement
- AdditionalIndications Repaired Based on Location & History
- "E' August 27,1997 ," 10
FRETTING WEAR
- Continues at a Loiv Level in All Plants Has Been Confirmed at Lower TSP Elevations in Tube Pulls from CR-3 in 1994
- Tubes Repaired Based on App. H Qualified Depth Measurement
- Loiv Growth Rates B&WOG SG Committee / NRC Meetin*a August 27,1997 g g 11
9 XEWLY IDENTIFIED DEGRADATION MECHANISMS /
EMERGING AREAS OF INTEREST
- Degradation at Dented Locations
- Freespan, TSP, & Tubesheet
- PWSCC at Tube-TS Roll Transitions
- Freespan AxialIGSCC Indications in Sleeve Roll Joints (Sleeve and Tube)
- OD Degradation in Sludge Pile Region
- SG Internals Degradation
- Following NEI Industry Program U " # "E' 12 August 27,1997 1
DEGRADATION AT DENTED LOCATIONS
- Inspection History
- ANO-1 1993: 6 Tubes with Indications at UTS Sec. Face
- Two Circumferential, Four Volumetric
- Detected with Bobbin, Confirmed with MRPC
- Other Dented Locations Examined, No Additional Indications Detected 1996: 2 Tubes with Axial Indications in Freespan Dents
- Located in Upper Bundle
- Detected with Bobbin, Confirmed with MRPC OD Initiated
- In-situ Pressure Tested Largest Indications, Confirmed Thru-Wall
- Shown by Analysis to Satisfy Reg. Guide B -ILeak Requirements
= own ns enove B&WOG SG Committee / NRC Meeting, -
g' g Rockville, Md. =
13
1 DEGRADATION AT DENTS, CONT'D.
Inspection History, Cont'd.
- oconee-1 1995: 1 Volumetric and 1 Circumferential Indication at 15th TSP Circumferential Indication Had Volumetric Characteristics
~
- Drilled Hole Locations -o
! - CR-3 1996: Volumetric Indication in Freespan Dent above 13th TSP 1997: Two Volumetric and Four Circumferential Indications l - Volumetric Indications in Freespan Dents Circumferential Indications Near UTS Secondary Face Similar to ANO-1 Indications
- OWNdERS GROUP B&WOG SG Committee / NRC Meeting, -'
g
- 997 Rockville, Md. m
~
o CURRENT INSPECTION PRACTICES FOR DENTED LOCATIONS
- InitialInspection with Bobbin Coil
- All Plants Continue to Inspect a Sample of Dented Locations with Rotating Coil Techniques l
i B&WOG SG Committee / NRC Meeting
^"E#
- Rockville, Md. bd
e TUBE-TO-TUBESHEET ROLL TRANSITIONS
- Background
- Tube-to-Tubesheet Joint Formed by One-Inch Expansion l Additional Seal Weld n All Joints Stress Relieved During Full Bundle Stress Relief After Vessel Fabrication Decreases Susceptibility to PWSCC at Roll Transitions
- Some Joints Re-rolled During Fabrication After Stress Relief Considered More Susceptible to PWSCC, Therefore Have Been Inspected as " Leading Indicators"
- Roll Transition is Contained Inside Tubesheet Tube Can Not Burst - Degradation is a Leakage Concern Only B&WOG SG Committee / NRC Meeting' August 27,1997 16 gg
DEGRADATION IN TUBE-TS ROLL REGIONS OUTAGE # TUBES WITH # TUBES WITH INS PECTION PLANT DATE VOL INDIC'S. AXIAL INDIC'S. SCOPE COM M ENTS D B-1 3/96 0 1 A-SG 10% A-SG Tube Pulled, Concluded 3% B-SG to be Re-rolled C R-3 3/96 0 1 B-SG 4 A-SG Indication in Re-Rolled 55 B-SG Location 6/97 46 A-SG 5 A-SG 100% A-SG 8 B-S G 45 B-SG (1 Circ) 100% B-SG 48 of 51 B-SG Axials in l Previously Repaired Locations ANO-1 9/96 3 A-SG 11 A-SG 21% A-SG 1 Tube Pulled.
l 1 B-SG 9 B-SG 21% B-SG ON S-3 10/96 1 A-SG 0 A-SG 2% A-SG 1 Tube Pulled.
10 B-SG 18 B-SG 100% B-S G
= ownsas amour B&WOG SG Committee / NRC Meeting' August 27,1997 I Rockville, Md.
-._._..._..____m_._.__.__ _ _
TUBE PULL DATA FOR TUBESHEET ROLLS
- Davis Besse-1
- One Tube Pulled in 3/96
- Lab Exam Confirmed PWSCC 5 Axial Cracks in Roll Transition, Largest Was 0.092" long and 78%
Max TW
- ANO-1
- One Tube Pulled 9/96, Confirmed PWSCC
- Largest Crack Was 0.082" Long,65% Max TW C
l
- Oconee-3 q l - One Tube Pulled 10/96 (Lab Results Not Yet Available)
B&WOG SG Committee / NRC Meeting August 27,1997 Rockville, Md. >
___.--__-._________m.__.
ACTIONS TAKEN TO ADDRESS TUBE-TS ROLLS
- Inspection
- All Plants Sampling Hot Leg Transitions with MRPC
- Non-Stress Relieved Cold Leg Transitions Sampled with MRPC
- Appendix H Sizing Work in Progress
- Repair Options Considered
- - Tube Re-roll (B&WOG has Prepared Qualification Report)
Similar to Process Applied in RSGs Topical Report to be Submitted This Year Some Plants May Require Tech Spec Change
- Shot Peening
- Alternate Repair Criteria (Being Considered by B&WOG)
B&WOG SG Committee / NRC Meeting' I
August 27,1997 Rockville, Md. i i
- First Identified at ONS-1 in 1994 Via Tube Pull
- Since Identified at ONS-2, ONS-3, ANO-1, and CR-3
- Discussed with NRC on Several Occasions
- Believed to be Associated with Axial Grooves Believed to Resulting from Tube Insertion During Fabrication l
- Inspection Results Indicate an Active Mechanism eedag, August 27,1997 fg g n[ 20
4 IGSCC IN FREESPAXS -INSPECTION RESULTS OUTAGE # TUBES INSPECTION PLANT DATE AFFECTED SCOPE (Bobbin) COMMENTS ONS-1 5/94 7 61% A,64% B 7 Tubes Pulled 11/95 40 100 %
ONS-2 10/94 9 61%A,64% B 4/96 173 100 % 4 Tubes Pulled ONS-3 6/95 22 100%
10/96 67 100 % 4 Tubes Pulled,1 For FS Axial ANO-1 9/96 14 100 %
CR-3 6/97 1 100 %
TMI-l 9/95 0 23% A&B 100% Planned 9/97 l
DB-1 3/96 0 20% A&B l
Total = 333
= ownses saour B&WOG SG Committee / NRC Meeting, 21
^"E# *I Rockville, Md.
I 9
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035 043 055- 065 073 085- 093- 105- 11S- 125- 135- 143- 153-04S OSS OSS 07S 085 OSS 10S 115 123 133 145 153 UTS FREESPAN ELEVATION
= ownses amour B&WOG SG Committee / NRC Meeting
^"S#
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IGSCC IN FREESPANS - CURRENT ACTIONS Inspection / Disposition
- Inspect with Bobbin, Confirm with MRPC l Lab Analysis of Tube Pull Results Confirm Adequate Bobbin Detection
- Plug on RPC Confirmation Tube Integrity
- Burst Testing of Tube Pull Samples (Oconee Plants) & In-Situ l
Pressure Testing (ANO-1) Indicates Adequate Structural Margin l
- No Leakir.g Tubes
- Preliminary Probabilistic Analysis Demonstrates Current Planned Cycles Acceptable B&WOG SG Committee / NRC Meeting' August 27,1997 Rockville, Md. -
i
IGSCC IN FREESPANS - CURRENT ACTIONS, CONT'D.
- Investigating Causes and Mitigation Options
- Formed B&WOG Chemistry Committee
- Titanium Injection at Oconee and TMI-l
- B&WOG Tube Pull Program Lab Sample Analysis Burst & Leak Testing NDE Correlation with Met Results Chemistry Analysis
- Additional Duke Power Efforts SIMS Analysis (Additional Causal Factors Data)
- Investigating Repair Options l
B&WOG SG Committee / NRC Meeting'
^"E"#
- Rockville, Md. > d
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TUBE PULL RESULTS: ANO-1 SLUDGE PILE REGION
- 2 Tubes Pulled for Lab Exam
- Confirmed OD Initiated Attack
- Some Indications Confirmed to be Through-Wall
- Axial Cracks Originated at the Bottom of Shallow Areas of Wastage B&WOG SG Committee / NRC Meeting'
^"E#
- Rockville, Md. hi 27
- Background
- Sleeves First Installed at ANO-1 in 10/84
- Two Lengths 80" Sleeve Extends to Below 15th TSP 3 31" Sleeve Extends to Below UTS
- Reason forInstallation l
Preventive Measure to Mitigate High Cycle Fatigue Near Open Tube Lee All Plants Span Areas of Degradation B&WOG SG Committee / NRC Meeting,
^"E#
- Rockville, Md. :
jg 28
,,N,,,,,,/,i/er""'y, 3 4 ss N
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B&WOG SG Committee / NRC Meeting, ,OWNEI8##ouP August 27,1997 e Rockvine. - f[JgL,t s
. - - - - - . . _ _ . . . . . . . . . . . . . . . . ------1 p.-..;..r-. ._ . .. . .-. , . . . - -.
- Background, Cont'd.
- Two Materials n Alloy 600 Sleeves Installed from 1984 to 1990 921 TotalInstalled ANO-1, ONS-1, ONS-3 n Alloy 690 Sleeves Installed 1990 to 1995 2867 Total Installed All Piants Except ONS-1 1
B&WOG SG Committee / NRC Meeting' 0
^"E
- Rockville, Md. .
T
DEGRADATION HISTORY OF SLEEVED TUBES PLUGGED DUE TO SLEEVE PLUGGED TOTAL TOTAL RELATED FOR OTHER REMAINING MATERIAL INSTALLED DEGRADATION REASONS IN SERVICE ALLOY 600 921 4 SERVICE 34 883 INDUCED ALLOY 690 2867 6 SERVICE 42 2819 INDUCED I
B&WOG SG Committee / NRC Meeting' August 27,199i Rockville, Md. di 31
SERVICE INDUCED DEGRADATION OTSG ROLLED SLEEVES NO. TUBE /
PLANT DATE MAT:L. SLEEVES LOCATION SLEEVE W IND.
ONS-3 10/96 A-690 1 FS ROLL SLEEVE SCI ,
ANO-1 9/96 A-600 4 3 - UTS ROLL TUBE SCI 1 - FS ROLL SLEEVE SCI A-690 5 4 - UTS ROLL TUBE MAI/ SCI 1 - FS ROLL TUBE SCI
- 1. Indicates Whether the Indication is in the Sleeve or the Parent Tube.
B&WOG SG Committee / NRC Meeting' Aups 27, M7 Rockville, Md. %
- - _ - - _ - _ - _ _ - - _ - - - . - _ _ _ . _ - _ ~ . _ _ _ - _ . . . . . .
UTILITY ACTIONS - SLEEVE DEGRADATION Inspection
- Inspect Sample of Sleeve Joints (A-600 & A-690) With Plus Point Each Outage
- Disposition
- Plug Indications of Pressure Boundary Degradation on Detection
- Future Plans
- B&WOG Investigating NDE Sizing Capabilities for Sleeve Rolls l
- Develop Method to Remove Sleeve for Laboratory Analysis Difficult Due to Freespan Expansions
- Continue to Monitor Installed Sleeves
- Sleeving Still Considered Future Repair Option B&WOG sG Committee / NRC Meeting' 33 August 27,1997 Rockville, Md. -
Et
DEGRADATION MECHAXISMS
SUMMARY
OF AFFECTED PLANTS PRI SEC ROLL OD SLUDGE SIDE SIDE TRANS EROSION- FRET / GROOVE PILE PLANT EFPY IGA IGA PWSCC CORR WEAR IGA / SCC AXIALS ONS-1 17.5 X X X X ONS-2 17.1 X X X X ONS-3 16.6 X X X X X ANO-1 15.5 X X X X X TMI-1 13.5 X X X CR-3 12.2 X X X X DB-1 11.7 X X X B&WOG SG Committee / NRC Meeting' 34 August 27,1997 Rockville, Md.
B&WOG STEAM GENERATOR RELATED PROJECTS
- Tube Pull
- Objectives Correlate Lab Results with Field NDE Determine Degradation Mechanisms Evaluate Structural / Leakage Integrity
- All Tube Pulls Jointly Funded Since 1994 Ensures Participation in Planning and Communication of Results by All Utilities
- 88 Total Tubes Pulled to Date B&WOG SG Committee / NRC Meeting' August 27,1997 Rockville, Md. . d
TUBE PULL HISTORY AT B&WOG PLANTS PLANT YEARS DAMAGE MECHANISMS FOUND ONS-1 77,78,81,94 HCF, IMPINGE, IGA PIT, FREESPAN IGSCC, WEAR ONS-2 76,88,96 EROS-CORR, HCF, WEAR, FREESPAN IGSCC ONS-3 81,82,96 IMPINGE, WEAR, HCF, FREESPAN IGSCC, OD IGA, ROLL TRANSITION PWSCC ANO-1 78,82,84,96 OD IGA (UTSF), ROLL TRANSITION PWSCC, LTS SLUDGE PILE CR-3 92,94 OD IGA PIT, WEAR f
TMI-I 82,86 ID IGSAC, OD IGA l
97 (PLANNED)
DB-1 96 ROLL TRANSITION PWSCC 98 (PROPOSED)
= ownsas amour ng' August 27,1997 36 R M
=
B&WOG PROJECTS, CO3T'D.
- Alternate Repair Criteria for OD IGA
- Started Fall 1996
- First Submittal Expected 9/97 (Tubesheet Only)
- Final Submittal Expected January 1998
- Tube Integrity
- Objective: Determine Degradation-Specific Effect on Tube Structural Integrity
- Burst Testing of Simulated Flaws (Completed)
- Cycle Length Analysis for AxialIGSCC (In Progress)
- Hideout / Return Studies (Completed)
B&WOG sG Committee / NRC Meeting'
^"E" "
Rockville, Md. hi
1 B&WOG PROJECTS, CO3 T'D.
- Tube Integrity, Cont'd.
- Develop Database to Allow Condition Monitoring and Operational Assessment
- OTSG Re-roll Procedure
- Qualification Report Complete
- Topical Report To Be Completed in 1997
- Increased Tube Plugging Limit
- Objective: Increase Tube Plugging Limit to 20% for All Plants
- Current Limits Vary Plant to Plant l B&WOG SG Committee / NRC Meeting'
^"E
- Rockville, Md. d l
~
B&WOG PROJECTS, CO3 T'D.
- OTSG Trending Report
- Yearly Compilation ofInspection Results for All OTSGs~
- Used to Identify Emerging Trends, Focus Resources on Most Important Issues
- SG Internals
- Following NEI Program
- Repair Process for AxialIGSCC
- Planned for 1998
- Being Considered for 1998
- ARC for Roll Transition PWSCC
- Feasibility Study for OTSG Sleeve ARC B&WOG sG Committee / NRC Meeting August 27,1997 Rockville, Md. d '
l B&WOG PROJECTS, CONT'D.
- Appendix H Qualification Projects
- Improve Detection and Sizing Techniques Sleeve Roll Joints Tubesheet Roll Transitions .
Tubesheet Crevice (Complete for Detection)
- Probe Wear
- Quantify Bobbin Probe Wear in OTSGs
- Characterization ofIGA
- Optimize ECT Techniques for Detection and Sizing ofIGA in OTSGs B&WOG SG Committee / NRC Meeting, 40 3997 Rockville, Md. .
i
e B&WOG PROJECTS, CONT'D.
- Probability of Detection / Human Factors
- Quantify Bobbin POD for Most Prevalent OTSG Damage Mechanisms
- Supports IGA ARC Project
~
- In Final Reporting Stage
- Analysis Guidelines Update
- Objective is to Develop Generic NDE Guidelines for OTSG Inspections
- OTSG Site Specific Testing
- Develop ECT Database of OTSG Tube Indications to be Used in l
Site Training for Analysts B&WOG SG Committee / NRC Meeting,
^"E
- Rockville, Md. 6
i SUM MARY
- Several New Areas of Degradation Observed in Last 3 Years at B&W Plants
- Tube Condition Continues to Satisfy Reg. Guide 1.121 Requirements
- B&W Utilities Continue to Communicate and Share Information on Steam Generator Issues
- B&WOG Actively Involved in Managing SG Degradation 42 August 27,199'1 R 1
_ - . - . . _ - - . _ _ - _ - . _ - - - _ n
O B&W ("!NERS GROUP HEETING ATTEi4 DEES e AUGUST 27, 1997 l ((td ORGAN 17A110jf l
DEWEY ROCHESTER DUKE POWER RICHARD FREEMAN GPU NUCLEAR JOHN HATHCOTE ENTERGY/ANO l RICH ACKERMAN TOLEDO EDISON l JOHN MAYAR FLORIDA POWER JEFF BROWN FRAMATOME 1 GLENN MCINTYRE TOLEDO EDISON J0E BIRMINGHAM NRC\NRR\PGEB PHIL RUSH NRC\NRR\EMCB TED SULLIVAN NRC\NRR\EMCB JOHN TSA0 NRC\NRR\EMCB STEPHANIE C0FFIN NRC\NRR\EMCB CHERYL BEARDSLEE NRC\NRR\EMCB JENNY WEll MCGRAW HILL Attachment 2
9 B&W Owners Group Project No. 693 Mr. Robert W. Keaten, Chairman Mr. W. W. Foster, Chairman B&WDG Executive Committee B&WDG Steering Committee Vice President & Director of Director of Safety Assurance Technical Functions Duke Power Company GPU Nuclear Cor> oration Oconee Nuclear Station One Upper Pond Road PO Box 1439 Parsippany, NJ 0705f Seneca. SC 29679 Mr. R. B. Borsum, Manager Mr. J. H. Taylor, Manager Rockville Licensing Operations Licensing Services Framatome Technologies, Inc. Framatome Technologies. Inc.
1700 Rockville Pike Suite 525 P.O. Box 10935 Rockville, MD 20852 1631 Lynchburg, VA 24506-0935
\ -
Septomber 2. 1997' MEMORANDUM 10: David B. Matthews Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM: Joseph L. Birmingham Project Manager Original Signed By:
Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF AUGUST 27, 1997. MEETING WITH B&W OWNERS GROUP AND FRAMATOME TECHNOLOGIES ON NRC INFORMATION NOTICE 97 49 AND PLANS FOR STEAM GENERATOR TUBE ALTERNATE REPAIR CRITERIA On August 27. 1997. representatives of the B&W Owners Group (B&WOG) and Framatome Technologies (Framatome) met with U.S. Nuclear Regulatory Commission staff to present information about the status of B&WOG activities to better resolve steam generator tube integrity and plans for alternate repair criteria (ARC) in once through steam generators (OTSG). The M ers Group and Framatome presented an overview of activities to date, current status, and actions planned for the near future. The overview included a discussion of emerging issues and new degradation meche11sms related to OTSG tubes and B&WOG actions taken to include the new issues und mechanisms in their resolution program.
Details of the above topics are in Attachment I which is the slides presented by BAWOG during the meeting. Also, a list of meeting attendees is provided in Attachment 2.
Attachments: As stated cc w/atts: See next page -
PRLribution:
CentraFF11e (w/atts 1&2) PUBLIC PGEB r/f OGC ACRS JBirmingham E Mai' (w/att 2)
S. Co' lins F. Miraglia R. Zimmerman F. Gillespie J. Roe D. Matthews B. Sheron G. Holahan L. Spessard J. Mitchell DOCUMENT NAME: G:\JLB\8 27 MTG. M. , f) ~
OFFICE PGEB:DRPM9tj SC/[G$YPM' dN6[IDRh, NAME JBirmingha'm:sw Ntulewicz hatthew[
DATE f/2J/97 4/V/97 i / t/97 N OiFICIAL RECORD COPY a ,
uq
/^(* Rio k UNITED STATES s
.]r NUCLEAR REGULATORY COMMISSION waswiwatow, o.c. seen.cooi
%, * * .*++/ September 2. 1997 l
HEMORANDUM T0: David B. Matthews. Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation, FROM: Joseph L. Birmingham. Project Manager .
Yc YYan Y .
Division of Reactor Program Ha agement k != -
Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF AUGUST 27. 1997 MEETING WITH B&W OWNERS GROUP AND FRAMATOME TECHNOLOGIES ON NRC INFORMATION NOTICE 97-49 AND PLANS FOR STEAM GENERAIOR TUBE ALTERNATE REPAIR CRITERIA On August 27, 1997. representatives of the B&W Owners Group (B&WOG) and Framatome Technologies (Framatome) met with U.S. Nuclear Regulatory Commission staff to present information about the status of B&WOG activities to better resolve steam generator tube integrity and plans for alternate repair criteria (ARC) in once through steam generators (OTSG). The Owners Group and Framatome presented an overview of activities to date, current' status, and actions planned for the near future. The overview included a discussion of emerging issues and new degradation mechanisms related to OTSG tubes and B&WOG actions taken to include the new issues and mechanisms in their resolution program.
Details of the above topics are in Attachment I which is the slides presented by B&WOG durin Attachment 2. g the meeting. Also, a list of meeting attendees is provided in Attachments: As stated cc w/atts: See next page
O TUBE DEGRADATION IV ONCE THROUGH STEAM GENERATORS CURRENT STATUS AND UTILITY ACTIONS AUGUST 1997 .
- g. j August 27,1997 R I 2
~ ~
attach. n 1
MEETIVG OBJECTIVES
- Continue Communication With NRC on OTSG Tube Degradation
- Previous Meetings in 11/94 and 3/96
- Identify Emerging Issues / New Degradation Mechanisms
- Discuss B&WOG Actions to Address Emerging Issues of Concern
- GetNRC Feedback on B&WOG Actions H 8. 2 August 27,1997 R 1
. . . . . ..i
AGENDA
- Meeting O'ojectives
- Plant Operation Summary
- Update on ECT Results & Tube Pull Analyses
- Emerging Areas of Concern
- Applicable B&WOG Projects
- Summary l
B&WOG SG Committee / NRC Meeting"
^"E
- Rockville, Md. g 3 3
-r, , . . ..
l _ . . . _ - . _ . _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ .
PLANT OPERATING SLMMARY COM OP CHEM CLNG CURRENT PLANT DATE DATE EFPY Thot ONS-1 7/73 9/87 17.5 602 ONS-2 9/74 2/88 17.1 602 ONS-3 12/74 Planned 9/98 16.6 602 ANO-1 12/74 10/90 15.5 602 TMI-1 9/74 9/91 13.5 604 CR-3 1/77 - 12.2 603 DB-1 7/78 Planned 4/00 11.7 605 u 2 8. 4 August 27,1997 ;
PLATT OPERATING SLMMARY, CONT'D.
Pri-Sec Fuel Cycle # Sleeve's LeakLimit, GPD Length % Plugged In Service PLANT Tech Spec / Admin. (Months) Per SG (A/B) Per SG (A/B)
ONS-1 504/150 16 2.8 / 8.7 236 / 193 ONS-2 504/150 16 2.4 / 3.3 277/260 ONS-3 504/150 16 3.5 / 3.3 286/253 ANO-1 500/ 144 16 4.1/ 2.0 476/484 TMI-1 144 /NA 24 8.1/ 2.6 248/253 CR-3 150/NA 24 1.1/ 4.2 163 / 162 DB-1 1440/100 ?? ? 6 / 0.6 199/212 Note: % Plugged Includes Effect ofIn-Service Sleeves
" "E" August 27,1997 5
?. .
EDDY CURRENT INSPECTION SCOPE Bobbin Coil MRPC Upper Rolls RPC Sleeves")
PLANT (A / B) (A / B)G) (A / B)
ONS-1 100 % / 100 % 20% /20% 100% /100%
11/95 Planned 9/97 11/95 ONS-2 100 % / 100 % 20% /20% 20% '1%
4/96 Planned 4/98 4/96 ONS-3 100 % / 100 % 20 % / 100 % 59% /51%
10/96 10/96 10/96 ANO-1 100% /100% 21 % / 21 % 100 % /100 %
9/96 9/96 9/96 T M I-I 23 % / 23 % 0) 21% /21% 52 % / 51 %
9/95 Planned 9/97 9/95 CR-3 100% /100% 100 % / 100 % 40% / 0%
6/97 6/97 6/97 l
l DB-1 20% /20% 10% / 3% 20% /31%
l 3/96 3/96 3/96 l 1. TMI-l Plans 100% Bobbin Exam for 9/97
- 2. Where Planned Inspection is Given, Previous Inspections Consisted Only of Re-rolled Loc 4tions i
= omneses asour B&WOG SG Committee / NRC Meeting' g
^" 6 Rockville, Md.
PREVIOUSLY IDEN TIFIED MECHANISMS
- VOLUMETRIC IGA
- HIGH CYCLE FATIGUE
- PARTICLE IMPINGEkENT AND EROSION
- FRETTING WEAR August 27,1997 R lie Md
- o- .
VOLUMETRIC IGA
- Increasing Number of Small Amplitude Indications in Freespan
- May Be Due to Improved Inspection and Analysis Techniques
- Growth Rates Are Low
- Alternate Repair Criteria Being Pursued
- Has Been Discussed Previously With NRC
- First Partial Submittal Has Been Made
- ANO-1 Is Lead Plant B&WOG SG Committee / NRC Meeting,
^"E
- Rockville, Md. Lm , T
HIGH CYCLE FATIGUE
- Circumferential Cracking Near Open Tube Lane Due to High Secondary Side Cross Flow
- All Plants Have Preventively Sleeved Susceptible Area No Identified Failures (Tube Leaks) Since 1994
- Plants Inspected Border Around Preventive Sleeving Area in Response to GL 95-03
- Plants Continue to Monitor Susceptible Area (Lane / Wedge)
August 27,1997
" "N' 9
- e 66 ..
PARTICLE IMPINGEME3T / EROSION
- Continues to be Observed at Oconee Units Only
- Located Within 2" of TSP's, Typically Upper Bundle
- Significant Contributor to Total Tubes Plugged at Oconee
- Not Observed in Other Plants l
- Tubes Repaired Based on App. H Qualified Depth Measurement
- Additional Indications Repaired Based on Location & History l
B&WOG SG Committee / NRC Meeting
- August 27,1997 Rockville, Md. g 10
FRETTIVG WEAR
- Continues at a Low Levelin All Plants
- Has Been Confirmed at Lower TSP Elevations in Tube Pulls from CR-3 in 1994
- Tubes Repaired Based on App. H Qualified Depth Measurement
- Low Growth Rates I
I B&WOG SG Committee / NRC Meeting"
^"#
- Rockville, Md. bY II 1 _ ._ -_____-_ -___- -___- __ .
]
NEWLY IDE3 TIFIED DEGRADATION MECHANISMS /
EMERGING AREAS OF INTEREST
- Degradation at Dented Locations
- Freespan, TSP, & Tubesheet
- PWSCC at Tube-TS Roll Transitions
- Freespan AxialIGSCC Indications in Sleeve Roll Joints (Sleeve and Tube)
- OD Degradation in Sludge Pile Region
- SG Internals Degradation
- FollowingNEIIndustry Program l
B&WOG sG Committee / NRC Meeting'
^"
- Rockville, Md. a, 4p 12
DEGRADATION AT DENTED LOCATIONS
- Inspection History
- ANO-1 1993: 6 Tubes with Indications at UTS Sec. Face
- Two Circumferential, Four Volumetric Detected with Bobbin, Confirmed with MRPC
~
Other Dented Locations Examined, No Additional Indications Detected n 1996: 2 Tubes with Axial Indications in Freespan Dents Located in Upper Bundle Detected with Bobbin, Confirmed with MRPC OD Initiated ,
In-situ Pressure Tested Largest Indications, Confirmed Thru-Wall Shown by Analysis to Satisfy Reg. Guide Burst / Leak l
Requirements
=o====samour B&WOG SG Committee / NRC Meeting, August 27,1997 Rockville, Md. W.F Mj 13
'II
DEGRADATION AT DENTS, CONT'D.
- Inspection History, Cont'd.
- oconee-1 1995: 1 Volumetric and 1 Circumferential Indication at 15th TSP Circumferential Indication Had Volumetric Characteristics .
Drilled Hole Locations
- CR-3 1996: Volumetric Indication in Freespan Dent above 13th TSP 1997: Two Volumetric and Four Circumferential Indications Volumetric Indications in Freespan Dents Circumferential Indications Near UTS Secondary Face Similar to ANO-1 Indications l
=
muuum ng.
t Augast 27,1997 Rockville, Md. ,- mFy dl 34
CURRE:NT IN'SPECTION PRACTICES FOR DE:STED LOCATIONS
- InitialInspection with Bobbin Coil
- All Plants Continue to Inspect a Sample of Dented Locations with Rotating Coil Techniques B&WOG SG Committee / NRC Meeting "
^"
- Rockville, Md. LT
TUBE-TO-TUBESHIGT ROLL TRANSITIONS
- Background
- Tube-to-Tubesheet Joint Formed by One-Inch Expansion Additional Seal Weld All Joints Stress Relieved During Full Bundle Stress Relief After Vessel Fabrication n Decreases Susceptibility to PWSCC at Roll Transitions
- Some Joints Re-rolled During Fabrication After Stress Relief Considered More Susceptible to PWSCC, Therefore Have Been Inspected as" Leading Indicators"
- Roll Transition is Contained Inside Tubesheet Tube Can Not Burst - Degradation is a Leakage Concern Only August 27,1997 "8'
g 16
e
! DEGRADATIOX IN TUBE-TS ROLL
)
REGIONS -
OUTAGE # TUBES WITH # TUBES WITH INSPECTION PLANT DATE VOL INDIC*S. AXIA L IN DIC'S, SCOPE COMMENTS I DB-1 3/96 0 1 A-SG 10% A-SG Tube Pulled, Concluded ,
3 */. B -S G to be Re-rolled C R-3 3/96 0 1 B-SG 4 A-SG Indication in Re-Rolled 55 B-SG Location l
6/97 46 A-SG 5 A-SG 100% A-SG l 8B-S G 45 B-SG (1 Circ) 100% B-SG 48 of 51 B-SG Axials in Previously Repaired
' Locations ;
AN O-1 9/96 3 A-SG 11 A-SG 21% A-SG 1 Tube Pulled.
- 1 B-SG 9 B-SG 21% B-SG I
ONS-3 10/96 1 A-SG 0 A-SG 2% A-SG 1 Tube Pulled.
l 10 B-SG 18 B-SG 100%B-SG ,
=ouessasamour B&WOG SG Committee / NRC Meeting, T
August 27,1997 Rockville, Md.
i- .
- . , - , -, , , -, . . , ,. . , , . . . , . ~ , , , .
J i
i TUBE PULL DATA FOR TLBESH KET ROLLS
- Davis Besse-1
'. - One Tube Pulled in 3/96
- - Lab Exam Confirmed PWSCC i
n 5 Axial Cracks in Roll Transition, Largest Was 0.092" long and 78%
- MnTW
- ANO-1 s
l - One Tube Pulled 9/96, Confirmed PWSCC ;
i - Largest Crack Was 0.082" Long,65% Max TW i - Oconee-3
- One Tube Pulled 10/96 (Lab Results Not Yet Available) l s
= ouesses amour B&WOG SG Committee / NRC Meeting, August 27,1997 '
Rockville, Md. .d.
ACTIONS TAKEN TO ADDRESS TUBE-TS ROLLS
- Inspection
- All Plants Sampling Hot Leg Transitions with MRPC
- Non-Stress Relieved Cold Leg Transitions Sampled with MRPC
- Appendix H Sizing Work in Progress
- Repair Options Considered
- Tube Re-roll (B&WOG has Prepared Qualification Report)
Similar to Process Applied in RSGs Topical Report to be Submitted This Year Some Plants May Require Tech Spec Change
- Shot Peening
- Alternate Repair Criteria (Being Considered by B&WOG)
B&WOG SG Committee / NRC Meeting, August 27,1997 Rockville, Md. i
- First Identified at ONS-1 in 1994 Via Tube Pull
- Since Identified at ONS-2, ONS-3, ANO-1, and CR-3
- Discussed with NRC on Several Occasions
- Believed to be Associated with Axial Grooves Believed to Resulting from Tube Insertion During Fabrication
- Inspection Results Indicate an Active Mechanism B&WOG SG Committee / NRC Meeting
- 20 M7 IM7 Rockville, Md. T
- . _ _ =
IGSCC IN FREESPANS -INSPECTION RESULTS OUTAGE # TUBES INSPECTION PLANT DATE AFFECTED SCOPE (Bobbin) COMMENTS ONS-1 5/94 7 61% A,64% B 7 Tubes Pulled 11/95 40 100S'.
ONS-2 10/94 9 61%A,64% B ,
4/96 173 100 % 4 Tubes Pulled ONS-3 6/95 22 100 %
10/96 67 100 % 4 Tubes Pulled,1 For FS Axial ANO-1 9/96 14 100 %
CR-3 6/97 I 100 %
TMI-l 9/95 0 23% A&B 100% Planned 9/97 DB-1 3/96 0 20% A&B Total = 333
= ownsas amour
' B&WOG SG Committee / NRC Meeting, I
A"#
- Rockville, Md. i
FREESPAX IGSCC ELEVATIONAL DISTRTRUTION 70 e TF 3 2+ 2 60 D' fj 'fi-gq s g3 M ;h s0 b
se N W t 3 e9-ne 6 :.,
e-ao :,
e _A_
s ..; q. ! e w et a
a w y-. ;3 8 '4-W fi .. -
dPe - f+d- %s a 2W-g 30
$[ $ $$ $8 sih l 20
@R p
rd e
p d
e; a
trK E O N h h5 IM-R is id _
r re es g ,
l
% 9 @! $ E
@j m
d in N_
d 0
03S- 045- 055 06S- 073- OSS- OSS. SOS- 115- 125- 13S- 143- 155-045 055 OSS 07S OSS 093 103 113 125 13S 143 15S UTS FREESPAN ELEVATRON
= owesens enour B&WOG SG Committee / NRC Meeting
- August 27,1997 .
Rockville, Md. ,-
T
- p. .
22
)
l i
)
! TL BE PELL RESE LTS - FREESPAN ,
! IGSCC
~
1
- - Data from Oconee-1,2, and 3 l - 12 Tubes Total
! - All Testing Indicates Margin Above Reg. Guide 1.121 4
Structural Limits i
- Leak Tests Indicate No Leakage
- In-Situ Testing at ANO-1 Supports Above Results
}
, =oussses enour B&WOG SG Committee / NRC Meeting, -
g August 27,1997 Rockville, Md. m
. . -- , , , , - , , - - - - --- , , ,- ,---,n ,- ,
IGSCC IN FREESPANS - CURRENT l ACTIONS
- Inspection / Disposition
- Inspect with Bobbin, Confirm with MRPC Lab Analysis of Tube Pull Results Confirm Adequate Bo'obin Patection
- Plug on RPC Confinnation Tube Integrity
~
- Burst Testing of Tube Pull Snmples (Oconee Plants) & In-Situ Pressure Testing (ANO-1) Indicates Adequate Structural Margin
- No Leaking Tubes l - Preliminary Probabilistic Analysis Demonstrates Current Planned Cycles Acceptable i
B&WOG S3 Committee / NRC Meeting, ,
Augu, ,7,1997 Rockville, Md. t d '
9 IGSCC IN FREESPANS - CURRENT ACTIONS, CONT'D.
- Investigating Causes and Mitigation Options
- Formed B&WOG Chemistry Committee
- Titanium Injection at Oconee and TMI-1
- B&WOG Tube Pull Program Lab Sample Analysis ,
Burst & Leak Testing NDE Correlation with Met Results
- Chemistry Analysis
- Additional Duke Power Efforts SIMS Analysis (Additional Causal Factors Data)
- Investigating Repair Options B&WOG SG Committee / NRC Meeting Augd 27, M7 Rockville, Md. : i
._.__._.____._____.______.mm__-_
INDICATIONS IN SLUDGE PILE REGION
-- Observed at ANO-19/96 Outage
- 9 Tubes With Axial Indications Localized Area
! Within 0.5 Inch of Top ofTubesheet l Some Indications Were Through-Wall Based on Observed Leakage
! Detected With Bobbin Coil, Confirmed with MRPC
! Located in 1" Deep Sludge Pile Not Associated With Dents
- Not Observed at Other OTSGs
- Affected Area Inspected During Normal Outage Inspections B&WOG SG Committee / NRC Meeting, 8"
- Rockville, Md. Mbi 6
TUBE PELL RESULTS: ANO-1 SLUDGE PILE REGION
- 2 Tubes Pulled for Lab Exam
- Confumed OD Initiated Attack
- Some Indications Confirmed to be Through-Wall
- Axial Cracks Originated at the Bottom of Shallow Areas of Wastage 1
i B&WOG SG Committee / NRC Meeting" 27
^"E
- Rockville, Md. :
d
- Background
- Sleeves First Installed at ANO-1 in 10/84
- Two Lengths 80" Sleeve Extends to Below 15th TSP 31" Sleeve Extends to Below UTS
- Reason forInstallation Preventive Measure to Mitigate High Cycle Fatigue Near Open Tube Lane All Plants Span Areas of Degradation
= owessas amour eedng, August 27,1997 gff 28 g ,
a-w
,,s,,,ggrrrrFHUE' ,
Y
'N I
2> %
i 52 EVE TUBE 5HEET ce= .
TUBE
- hh !
lb W $ $ '
)) i
\\
August 27,1997 B&WOG SG Committee / NRC Meet.mg, OWNERSGROUP Rockville, Md. w -
- Background, Cont'd.
- Two Materials Alloy 600 Sleeves Installed from 1984 to 1990 921 TotalInstalled ANO-1, ONS-1, ONS-3 Alloy 690 Sleeves Installed 1990 to 1995 2867 Total Installed All Plants Except ONS-1 B&WOG SG Committee / NRC Meeting' 0
^"E
- Rockville, Md. .
.i
DEGRADATION HISTORY OF SLEEVED TLBES PLUGGED DUE TO SLEEVE PLUGGED TOTAL TOTAL RELATED FOR OTHER REMAINING MATERIAL INSTALLED DEGRADATION REASONS IN SERVICE ALLOY 600 921 4 SERVICE 34 883 INDUCED ALLOY 690 2867 6 SERVICE 42 2819 INDUCED B&WOG SG Committee / NRC Meeting' '
August 27,1997 Rockville, Md. d
SERVICE INDUCED DEGRADATION OTSG ROLLED SLEEVES NO. TUBE /
PLANT DATE MAT:L. SLEEVES LOCATION SLEEVEM IND.
ONS-3 10/96 A-690 1 FS ROLL SLEEVE SCI ANO-1 9/96 A-600 4 3 - UTS ROLL TUBE SCI l - FS ROLL SLEEVE SCI A-690 5 4 - UTS ROLL TUBE MAI/ SCI l - FS ROLL TUBE SCI
- 1. Indicates Whether the Indication is in the Sleeve or the Parent Tube.
I Y
B&WOG SG Committee / NRC Meeting' 32
^"E
- Rockville, Md. i
UTILITY ACTIO.NS - SLEEVE DEGRADATION
- Inspection
- Inspect Sample of Sleeve Joints (A-600 & A-690) With Plus Point Each Outage
- Disposition
- Plug Indications of Pressure Boundary Degradation on Detection
- Future Plans l
- B&WOG Investigating NDE Sizing Capabilities for Sleeve Rolls
- Develop Method to Remove Sleeve for Laboratory Analysis Difficult Due to Freespan Expansions
- Continue to Monitor Installed Sleeves
- Sleeving Still Considered Future Repair Option B&WOG SG Committee / NRC Meeting, Augus 27, M7 Rockville, Md. g 33
DEGRADATION MECHANISMS
SUMMARY
OF AFFECTED PLANTS PRI SEC ROLL OD SLUDGE SIDE SIDE TRANS EROSION- FRET / GROOVE PILE PLANT EFPY IGA IGA PWSCC CORR WEAR IGA / SCC AXIALS ONS-1 17.5 X X X X ONS-2 17.1 X X X X ONS-3 16.6 X X X X X ANO-1 15.5 X X X X X TMI-l 13.5 X X X CR-3 12.2 X X X X DB-1 11.7 X X X B&WOG SG Committee / NRC Meeting'
^"E# *I Rockville, Md. i
B&WOG STEAM GENERATOR RELATED PROJECTS
- Tube Pull .
- Objectives Correlate Lab Results with Field NDE n Determine Degradation Mechanisms n Evaluate Structural / Leakage Integrity
- All Tube Pulls Jointly Funded Since 1994 Ensures Participation in Planning and Communication of Results by All Utilities .
- 88 Total Tubes Pulled to Date 4 l
B&WOG SG Committee / NRC Meeting' 35 August 27,1997 Rockville, Md. ,
TUBE PULL HISTORY AT B&WOG PLANTS PLANT YEARS DAMAGE MECHANISMS FOUND ONS-1 77,78,81,94 HCF, IMPINGE, IGA PIT, F REESPAN IGSCC, WEAR ONS-2 76,88,96 EROS-CORR, HCF, WEAR, FREESPAN IGSCC ONS-3 81,82,96 IMPINGE, WEAR, HCF, FREESPAN IGSCC, OD IGA,
, ROLL TRANSITION PWSCC ANO-1 78,82,84,96 OD IGA (UTSF), ROLL TRANSITION PWSCC, LTS SLUDGE PILE CR-3 92,94 OD IGA PIT, WEAR TMI-l 82,86 ID IGSAC, OD IGA j
97 (PLANNED)
DB-1 96 ROLL TRANSITION PWSCC 98 (PROPOSED)
= ownsas amour B&WOG SG Committee / NRC Meeting' g 7 3997 36 Rockville, Md. m
e B&WOG PROJECTS, CONT'D.
- Alternate Repair Criteria for OD IGA l
- Started Fall 1996
- First Submittal Expected 9/97 (Tubesheet Only)
- Final Submittal Expected January 1998
- Tube Integrity
- Objective: Determine Degradation-Specific Effect on Tube ,
Structural Integrity
- Burst Testing of Simulated Flaws (Completed)
- Cycle Length Analysis for AxialIGSCC (In Progress)
- Hideout / Return Studies (Completed)
B&WOG SG Committee / NRC Meeting'
^"8
- Rockville, Md. ; .I
e B&WOG PROJECTS,: CONT'D.
- Tube Integrity, Cont'd.
- Develop Database to Allow Condition Monitoring and Operational Assessment
- OTSG Re-roll Procedure
- Qualification Report Complete l - Topical Report To Be Completed in 1997
- Increased Tube Plugging Limit
- Objective: Increase Tube Plugging Limit to 20% for All Plants
- Current Limits Vary Plant to Plant B&WOG SG Committee / NRC Meeting' .
^"E"# 'I - Rockville, Md. d
s B&WOG PROJECTS, CONT'D.
- OTSG Trending-Report
- Yearly Compilation ofInspection Results for All OTSGs
- Used to Identify Emerging Trends, Focus Resources on Most Important Issues
- SG Internals
- Following NEI Program i
i
- Repair Process for AxialIGSCC
- Planned for 1998 ,
- Being Considered for 1998
- ARC for Roll Transition PWSCC
- Feasibility Study for OTSG Sleeve ARC B&WOG SG Committee / NRC Meetine August 27,1997 Rockville, Md.
1 B&WOG PROJECTS, CO3T'D.
- Appendix H Qualification Projects
- Improve Detection and Sizing Techniques Sleeve Roll Joints n Tubesheet Roll Transitions Tubesheet Crevice (Complete for Detection)
- Probe Wear
- Quantify Bobbin Probe Wear in OTSGs
- Characterization ofIGA
- Optimize ECT Techniques for Detection and Sizing ofIGA in OTSGs B&WOG SG Committee / NRC Meeting' Augum 27,1997 Rockville, Md. d
- "~
B&WOG PROJECTS, CONT'D. !
- Probability of Detection / Human Factors
- Quantify Bobbin POD for Most Prevalent OTSG Damage Mechanisms
- Supports IGA ARC Project
- In Final Reporting Stage
- Analysis Guidelines Update
- Objective is to Develop Generic NDE Guidelines for OTSG Inspections
- OTSG Site Specific Testing i
- Develop ECT Database of OTSG Tube Indications to be Used in Site Training for Analysts B&WOG sG Committee / NRC Meeting' August 27,1997 Rockville, Md. hi
~-
SUMMARY
- Several New Areas of Degradation Observed in Last 3 Years at B&W Plants
- Tube Condition Continues to Satisfy Reg. Guide 1.121 Requirements
- B&W Utilities Continue to Communicate and Share Information on Steam Generator Issues
- B&WOG Actively Involved in Managing SG Degradation
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B&WOG SG Committee / NRC Meeting, g August 27,1997 Rockville, Md. g d
I B&W OWNERS GROUP MEETING ATTENDEES o AUGUST 27, 1997 NAME ORGANIZATION DEWEY ROCHESTER DUKE POWER RICHARD FREEMAN GPU NUCLEAR JOHN HATHCOTE ENTERGY/AND RICH ACKERMAN TOLEDO EDISON JOHN MAYAR FLORIDA POWER JEFF BROWN FRAMA10ME GLENN MCINTYRE TOLEDO EDISON JOE BIRMINGHAM NRC\NRR\PGEB PHit RUSH NRC\NRR\EMCB TED SULLIVAN NRC\NRR\EMCB JOHN TSAO NRC\NRR\ENCB STEPHANIE C0FFIN NRC\NRR\EMCB CHERYL BEARDSLEE NRC\NRR\EMCB JENNY WEll MCGRAW HILL Attachment 2
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B&W Omers Group Project No. 693 Mr. Robert W. Keaten, Chairman Mr. W. W. Foster, Chairman B&WOG Executive Committee B&WOG Steering Committee Vice President & Director of Director of Safety Assurance Technical Functions Duke Power Company GPU Nuclear Cor) oration Oconee Nuclear Station One Upper Pond Road PO Box 1439 Parsippany, NJ 07054 Seneca, SC 29679 Mr. R. B. Borsum, Manager Mr. J. H. Taylor. Manager Rockville Licensing Operations Licensing Services Framatome Technologies, Inc. Framatome Technologies, Inc.
1700 Rockville Pike, Suite 525 P.O. Box 10935 Rockville MD 20852-1631 Lynchburg. VA 24506-0935 l
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