ML20154A832
| ML20154A832 | |
| Person / Time | |
|---|---|
| Issue date: | 09/28/1998 |
| From: | Birmingham J NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-693 NUDOCS 9810050019 | |
| Download: ML20154A832 (28) | |
Text
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i UNITED STATES g
j NUCLEAR REGULATORY COMMISSION
\\*****l2 WASHINGTON, D.C. 20656-4001 l
September 28, 1998 MEMORANDUM TO: Thomas Essig, Acting Chief Generic Issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation FROM:
Joseph L. Birmingham, Project Mana er Genetic issues and Environmental O
Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation x
SUBJECT:
SUMMARY
OF SEPTEMBER 22,1998, PUBLIC HEETING WITH THE B&W OWNERS GROUP EXECUTIVE COMMn i
On September 22,159, the Executive Committee of the Babcock and Wilcox Owners Group (B&WOG) met with U.S. Nuclear Regulatory Commission staff and management. B&WOG is made up of five utilities Duke Energy Corporation; Entergy Operations, Inc.; Florida Power Corporation; GPU Nuclear, Inc.; Toledo Edn on Company; and a vendor, Framatome Technologies, Inc. The Owners Group has seven active reactors at five sites.
After introducing the membership of the Owners Group, B&WOG described their r.ar ongoing activities which include a reactor pressure vessel integrity program, a once through steam generator life cycle management program, and a reactor coolant system materials program.
They also described recent pro-active initiatives such as the issue assessment plan developed in response to a control rod drive mechanism leak found at Prairie Island and development of risk-informed applications such as risk-informed inservice testing of air-operated valves. NRC management commented that it encouraged the development of risk-informed applications and I
that, in addition to risk, such applications should demonstrate consideration of existing regulatory requirements and philosophies such as defense-in-depth.
,/
The B&WOG described several projects to improve maintenance of steam generators and extend steam generator life. These projects include efforts to determine the probability of j
detection of defects, realistic determination of defect growth rates, and improved sizing of defects using eddy current testing. Other steam generator activities include re-roll of tubing in the upper and lower tube sheets, assessment of tube end cracking and cracks that occcur in the free span area. The Owners group discussed their support of the National Electric Institute's (NEI) steam generator program. NRC management commented it was hopeful that staff discussions with industry on the NEl steam generator program would lead to an acceptable proposal and negate the need to issue a generic communication for this area.
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9810050019 900928 PDR TOPRP EMVGENE 1,cQlby C
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T. Essig
-2 September 28, 1998 Other subjects discussed by the Owners Group were topical reports, license renewal initiatives, and boron dilution /recriticality issues. NRC commented that review of topical reports appeared to be on schedule and that license renewal initiatives were among the highest priority activities for NRC. Regarding the boron dilution /recriticality issue, the staff commented that it is reviewing the September 11,1998 submittal from B&WOG and would discuss the results of that review as soon as it was completed.
A list of those attending the meeting is provided as Attachment 1. The slides used by B&WOG during the meeting are provided in Attachment 2.
Project No. 693 cc w/atts: See next page Distribution:(w/atts 1&2)
E-Mail (w/att 1)
Central File S. Collins /F. Miraglia PUBLIC R. Zimmerman OGC B. Sheron ACRS
- 5. Gillespie G. Holahan B. Boger J. Roe D. Matthews T. Essig F. Akstulewicz J. Birmingham Document Name:g\\jlb\\baw-xmtg OFFICE PGEB:DRPMgf7 SC:PGEfQIlM R
NAME JBirminghamisw FAkhMD DATE 9/25/98 SM98 OFFICIAL OFFICE COPY L
n-h T. Essig September 28, 1998 Other subjects discussed by the Owners Group were topical reports, license renewal initiatives, and boron dilution /recriticality issues. NRC commented that review of topical reports appeared to be on schedule and that license renewal initiatives were among the highest priority activities for NRC. Regarding the boron dilution /recriticality issue, the staff commented that it is reviewing the September 11,1998 submittal from B&WOG and would discuss the results of that review as soon as it was completed.
A list of those attending the meeting is provided as Attachment 1. The slides used by B&WOG during the meeting are provided in Attachment 2.
Project No. 693 cc w/atts: See next page 1
i
_ - - - - - - - - ~
B&W OWNERS GROUP EXECUTIVE COMMITTEE MEETING ATTENDEES SEPTEMBER 22,1998 Name Randy Hutchinson Affiliation _
Bill McCollum Chairman, B&WOG Exec. Con - Entergy Operations Duke Energy Corp.
Bill Foster Dewey Rochester Duke Energy Corp.
Art Rone Duke Energy Corp.
Pat Walsh GPU Nuclear John Link GPU Nuclear John Paul Cowan GPU Nuclear John Wood Florida Power Corp.
John Bohart Toledo Edison Company Joe Kelly Framatome Technologies Rick Edwards Framatome Technologies Mike Schoppman Framatome Technologies Jack Bastin Framatome Technologies Sam Collins Westinghouse Brian Sheron NRR, Director Scott Newberry NRR\\ADT Jack Strosnider NRROSSA Tim Collins NRR\\DE Jerry Mauck NRR\\DSSA Glenn Kelly NRR\\DRCH Ted Sullivan NRR\\DSSA J. Birmingham NRROE NRR\\DRPM 3
ATTACHMENT 1
1 6
i B&W OWNERS GROUP EXECUTIVE COMMITTEE MEETING ATTENDEES SEPTEMBER 22,1998 Name Affiliation Randy Hutchinson Chairman, B&WOG Exec. Com. - Entergy Operations Bill McCollum Duke Energy Corp.
Bill Foster Duke Energy Corp.
Dewey Rochester Duke Energy Corp.
Art Rone GPU Nuclear Pat Walsh GPU Nuclear i
John Link GPU Nuclear
)
John Paul Cowan Florida Power Corp.
John Wood Toledo Edison Company John Bohart Framatome Technologies Joe Kelly Framatome Technologies Rick Edwards Framatome Technologies Mike Schoppman Framatome Technologies Jack Bastin Westinghouse Sam Collins NRR, Director Brian Sheron NRR\\ADT Scott Newberry NRR\\DSSA Jack Strosnider NRR\\DE Tim Collins NRR\\DSSA Jerry Mauck NRR\\DRCH Glenn Kelly NRR\\DSSA Ted Sullivan NRR\\DE J. Birmingham NRR\\DRPM i
ATTACHMENT 1
i i
l B&WOG Executive Committee /NRR Meeting l
l l
Rockville, MD l
l September 22,1998 F
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-l 6
B&WOG Executive Committoe/NRC Meeting 1:30 NRC Opening Remarks Sam Collins 1:45 B&WOG Opening Remarks Randy Hutchinson
- Membership 1:50 Major B&WOG Budget items
' Bill Foster 2:00 B&WOG Pro-Active initiatives Bill Foster Response to Prairie Island CRDM Leak Support of Industry Materials Forum Risk-Based Applications initiatives 2:15 Once Through Steam Generator (OTSG)
Dewey Rochester lasues
- Draft Generic Letters
- Discontinued ARC's
- Electrosleeving
-Inspection Requirements 2:35 B&WOG Topical Report Status Randy Hutchinson 2:40 License RenewalInitiatives Randy Hutchinson 2:45 Boron Dilution /Recriticality lasue John Link 3:00 Feedback From the NRC on B&WOG Sam Collins issues of Interest 3:15 NRC lasues of Interest Sam Collins 3:30 Adjourn 1
i i
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B&W Owners Group Membership 4
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Duke Energy Corporation Oconee Nuclear l
Station, Units 1,2 and 3 i
i Entergy Operations, Inc Arkansas Nuclear i
One, Unit 1 i
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Florida Power Corporation Crystal River
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l GPU Nuclear, Inc TMI-1
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Toledo Edison Company Davis-Besse 1 4
Framatome Technologies, Inc 1
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Major B&WOG Budget items l-e Reactor Pressure Vessel Integrity i'
RCS Materials i
OTSG Life Cycle Management i
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i Reactor Pressure Vessel Integrity i
j e Irradiation of Surveillance capsules 4
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e Materials testing i
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e Reactor vessel materials analysis in compliance with 10CFR 50
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Support of industry development of analysis and test
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1998 effort $1.4M l
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RSC Materials Activities l
- RV internals bolting i
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Other alloy 600 issues i
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l 1998 effort $1.5M 1
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OTSG Life Cycle Management l
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e Largest single issue being addressed by the B&WOG (over 40% of the entire budget)
I e Activities span several different groups.
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Analysis Committee l:
Chemistry Committee NDE Committee l
Steam Generator Committee l
e NRC interface activities will be discussed later in this meeting l
1998 effort ~$3.8M
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B&WOG Pro-Active Initiatives l
- Response to Prairie Island CRDM Leak l
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- Support of Industry materials Forum e Risk-informed Applications initiatives
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j Response to Prairie Island CRDM Leak i
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- Developed issue assessment plan i
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= Inspected 77 B&WOG plant motor tubes (three different types) i
- Researched construction / material histories i
l
- Completed preliminary safety assessment
. Topical Report BAW-2326, " Control Rod Drive Mechanism Motor i
Tube Integrity Evaluation," was submitted to the NRC on June 24, 1998 l
Support of Industry Materials Forum
. Represented on the MRP Executive Group e Participating on the following:
CRDM PWSCC/ Alloy 600 ITG RPV Internals ITG RPV Integrity ITG Issues Integration Group e
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Risk-informed Applications initiatives l
. PRA Certification Process
. PRA Comparison Project e Industry Standards & Strategic Efforts Application Specific Risk Informed Projects l
- Risk-Informed inservice Testing (AOVs) i i
- Risk-Informed Inservice inspection i
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l B&WOG Steam Generator issues l
j e NEl 97-06 SG Program
. LTS Re-roll j
e Multiple Re-Rolls (LTS & UTS)
Tube end cracking / anomalies Electrosleeving 5
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. Fourteen Currently in Operation Projects are to Maintain & Extend SG Life e Largest Cost Component to B&WOG l
Budget of ~ $3.8 Million in 1998 for SG Projects t
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. B&WOG Member Utilities Support initiative l
l Method of Clarifying requirements j
= Significant Utility Resources Needed to implement i
j e B&WOG Project To Support:
l EPRI Guidelines
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4 POD, Realistic Growth Rates & ECT Sizing for Each Mechanism i
Consistency Among B&WOG Plants
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Multiple Re-Rolls 1
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- Only one upper re-roll currently allowed at some plants Desire to have for both UTS and LTS I
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- B&WOG project to improve re-roll process l
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Determining maximum number of rolls Determining ways to minimize / reduce roll-induced loads in the tubes e All B&WOG members have an interest I
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- i Lower Tube Sheet Re-Roli
- Anticipate need for lower tubesheet re-roll i
l Objective is to keep tubes with structural / leakage integrity in service
- B&WOG project to address issue
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I Determine effect of sludge in LTS crevice
- All B&WOG members have an interest i
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Tube End Cracking / Anomalies i
l lssue identified in NRC Information Notice
- B&WOG Members Have Exchanged Information B&WOG Project to Address issue l
Possible Submittal of an ARC f*..*
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- Steam generators require significant utility resources.
Resources must be used wisely to maintain and i
improve both safety and performance.
- B&WOG members are committed to working with NRC personnel:
- To improve communication and interfaces
- To resolve technical issues promptly I
i l
B&WOG TOPICAL REPORT STATUS REPORT REPORT TITLE SUBMITTAL B&WOG LEAD Branch B&WOG REMARKS DATE PRIORITY BAW-2248 Demonstration of the Management of Aging 7/29/97 GLRP PDLR 1
Meetings 2/12/97, 8/28/97 Effects for the Reactor Vessel intemals NEXT ACTION: RAls - NRC (12/4/98)
BAW-2251 Demonstration of the Management of Aging 7/31/96 GLRP PDLR 1
initial meeting 2/6/96 Effects for the Reactor Vessel Meetings 8/28/96,2/12/97,6/4/97 RAls 8/28/96,12/19/96,4/2/97 RAI response 11/20/96,4/1/97 DSE issued 9/18/95 BAW-2275 Low Upper-Shelf Toughness Fracture 8/96 GLRP PDLR 1
Appendix B to BAW-2251 Mechanics Analysis of B&W Designed Reactor Vessels for 48 EFPY DSE issued 9/18/98 BAW-2274P Fracture Mecharucs Analysis of Postulated 1/24/97 GLRP PDLR 1
Appendix C to BAW-2251 Underciad Cracks in B&W Designed Reactor Vessels for the Period of Extended Ooeration DSE issued 9/18/98 BAW-2241P Fluence and Uncertainty Analysis 5/14/97 Materials Committee SRXB 1
RAls 1/30/98 & 4/8/98 RAI response 5/29/98 & 10/30/98 (projected)
Met with NRC on 8/5-6/98.
Supports BAW-2251.
BAW-10227P Evaluation of Advanced Cladding and 11/24/97 FCF SRXB 1
Review funded thru FY99. BNL to review.
Structural Material (MS)in PWR Reactor Fuel TE submitted License Amendment 9/8/98.
NRC says SE by 4/95 BAW-2297 Justification for Extension of Allowed Outage 9/30/98 RRWG 2
Supports tech spec changes for DB and Rev.1 Time for Low Pressure injection and Reactor DEC.
Building Spray Systems NEXT ACTION: Submrt report to NRC.
BAW-10226P Altemate Repair Criteria for Volumetnc Outer 8/13/97 Steam Generator SRXB 2
ANO-1 lead plant, application 12/12/97. Due Diameter Intergranular Attack in the Tubesheet Rev.1, Committee to NRC concems, work suspended.
of Once-Through Steam Generators 1/31/98 NEXT ACTION: ANO reevaluate 1" qtr. 99.
BAW-2181 CRAFT 2-RELAP-MOD 2 Companson for Small 2/19/93 Analysis Commrttee SRXB 3
Low prionty, not under actrve review.
Break LOCA Analysis BAW 2245 Inst:al RTeor of LINDE 80 Welds Based on Rev.1, 9/22/95 RVWG EMCB 3
RAls 3/14/96 Rev.1 Fracture Toughness in the Transition Range RAI response 5/24/96 Request to suspend review 7/24/96 NEXT ACTION: Wait for ASTM achon BAW-2301 B&WOG integrated Response to Generic 7/25/97 Materials Commrttee EMCB 3
Low NRC prionty due to resources. No Letter 97-01:" Degradation of Control Rod immediate safety concem.
Drive Mechanism Nozzle and Other Vessel NEXT ACTION: NRC RAls sent to Closure Head Penetrations:
Licensees. (DEC's dated 8/27/98.) NRC _
requested responses by 11/20/98.
BAW-2326 Control Rod Drive Mechanism Motor Tube 6/24/98 Matenals Committee SRXB 3
inrtiated following leak at PI-2. WOG wil!
Integnty Evaluation receive RAls. Not sure about B&WOG.
HiX:
License Renewal & Environmental Review Project Directorate High Prionty PDLR Pnonty #1
=
=
Priority #2 Normal Prionty SRXB =
Reactor Systems Branch
=
Materials & Chemical Er.gineering Branch Prionty #3 Low Priority EMCB =
=
Sept.15,1998
ANTICIPATED B&WOG REPORT SUBMITTAL REPORT REPORT TITLE SUBMITTAL B&WOG LEAD Branch B&WOG REMARKS DATE PRIORITY BAW-ARC for Tube-to-Tube Sheet Joint integrity 6/99 Steam Generator EMCB 1
Utilities submit report to NRC for tech. spec.
Issues Comm.
update.
BAW-2308 Selected Linde 80 Weids - USE Code Case 1" half of 99 RVWG EMCB 2
Method BAW-CRDM inspection and Repair Flaw Feb-Mar 99 Materials Committee SRXB 2
Submit in Feb - Mar 1999 timeframe.
Acceptability Criteria BAW-Resolution of PSC 1 Boron Dilution / Core 9/99 Analysis Committee SRXB 2
Anticipated submittal date of report Recriticality September 1999.
Air Operated Valve Program Document 1" qtr. of 99 Joint OG 2
Industry initiatrve by Joint Owners Groups.
Submit 1" qtr. of '99.
BAW-Linde 80 Welds 1" qtr of 99 RVWG EMCB 2
Submit report for materials with test data to NRC.
KEY:
License Renewal & Environmental Review Project Directorate High Prienty PDLR =
Priority #1
=
Normal Priority SRXB Reactor Systems Branch Priority #2
=
=
Materials & Chemical Engineering Branch Prionty #3 Low Priority EMCB =
=
Sept.15,1998 e
License Renewal Activities Generic Effort to Support Member Applications
- Oconee Application Submitted 7/7/98
- ANO-1 as early as 2000 B&WOG Reports Submitted to NRC
- RCS Piping (ApprovedD j
- Pressurizer (Approved) l
- RV (DSER) l RV Internals (Under Review)
B&WOG Reports Developed to Support Individual Utility License Renewal Application Once Through Steam Generators Reactor Coolant Pumps CRDM Motor Tube RV Supports t
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.i Boron Dilution /Recriticality i
l
. Introduction l
- Potential for Core Criticality Following SBLOCA i
l
. B&WOG Activities t
- Plant Guidance Issued and Implemented to Restrict RC Pump Bumps and Restart
- Interim Status Reports
. Evaluation Report Conclusions
- Low Safety Significance i
- Conservative Analysis l
- Low Energy Deposition
- Schedule for Further Work e Future Interactions I
I gg
.. cc:
Mr. Randy Hutchinson, Chairman Mr. John Link, Chairman B&WOG Executive Committee B&WOG Analysis Committee Entergy Operations Inc.
Framatome Technologies, Inc.
P.O. Box 1439 PO Box 10935 1448 S.R. 333 Lynchburg, VA 24506 Russellville, AK 72801-0967 Mr. W. W. Foster, Chairman Mr. J. J. Kelly, Mgr B&WOG Steering Committee B&WOG Licensing Operations Duke Power Company Framatome Technologies, Inc.
Oconee Nuclear Station P.O. Box 10935 PO Box 1439 Lynchburg, VA 24506-0935 Seneca, SC 29679 l-
.