ML20149K898
| ML20149K898 | |
| Person / Time | |
|---|---|
| Issue date: | 07/25/1997 |
| From: | Birmingham J NRC (Affiliation Not Assigned) |
| To: | Matthews D NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-693 NUDOCS 9707300237 | |
| Download: ML20149K898 (26) | |
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t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20656-0001
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i MEMORANDUM TO: David B. Matthews, Chief 4
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()Env}ronmental I f
Projects Branch A / J p i-f 4'
DivisionofReactofProgramManaNnl j
Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF JULY 23, 1997, PUBLIC MEETING WITH THE B&W i
OWNERS GROUP EXECUTIVE COMMITTEE i
l On July 23, 1997, the B&W Owners Group (B&WOG) Executive Committee met with
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U.S. Nuclear Regulatory Commission staff and management.
The B&WOG Executive l
Committee presented the status of significant issues that occurred during the previous year and discussed activities planned for the coming year.
Past issues discussed included reactor control cluster assembly insertion concerns, high-pressure injection pipe crack at Oconee Unit-2, boron precipitation post small-break loss-of-coolant accident concerns, and reactor vessel head penetration inspections. Ongoing or planned issues discussed included steam generator tube alternate repair criteria, a review of the plant emergency operating procedures to achieve more consistent implementation, and generic license renewal program activities.
The NRC staff and management discussed the above issues and proposed projects with the Owners Group and commented on the status of NRC review. The NRC also commented on the availability of staff resources for review of submittals for the proposed projects.
The meeting attendees are listed in Attachment I and details of the issues and i
projects discussed are contained in Attachment 2 which is the slides presented j
during the meeting.
Project No'. 693 I
Attachments: As stated i
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See next page l
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The meeting attendees are listed in Attachment I and details of the issues and projects discussed are contained in Attachment 2 which is the slides presented during the meeting.
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Project No. 693 Attachments: As stated cc w/atts:
See next page l
i Summary:BWOG Executive Committee Mtg. July 23, 1997 Distribution:(w/atts 1&2)
Central File PUBLIC PEGB r/f i
OGC i-ACRS j
JBirmingham E-Mail (w/att 1)
S. Collins i
F. Miraglia R. Zimmerman T. Martin M. Slosson D. Matthews B. Sheron i
G. Holahan i
B. Boger J. Lyons R. Wessman J. Strosnider l
F. Akstulewicz DOCUMENT NAME:
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B&W OWNERS GROUP EXECUTIVE COMMITTEE MEETING ATTENDEES JULY 23, 1997 NAME ORGANIZATION R. W. KEATEN GPU NUCLEAR J. K. WOOD CENTERIOR\\ DAVIS-BESSE R. A. ANDERSON FLORIDA POWER CORPORATION B. JONES DUKE ENERGY D. WHITAKER DUKE ENERGY P. WALSH GPU NUCLEAR D. MIMS ENTERGY D. STELLFOX MCGRAW HILL T. COLEMAN FRAMATOME C0GEMA FUELS J. H. TAYLOR FRAMATOME TECHNOLOGIES R. GANTHNER FRAMATOME TECHNOLOGIES J. J. KELLY FRAMATOME TECHNOLOGIES J. BROWN FRAMATOME TECHNOLOGIES D. FIRTH FRAMATOME TECHNOLOGIES R. EDWARDS FRAMATOME TECHNOLOGIES T. MARTIN ADT:NRC\\NRR G. HOLAHAN NRR\\DSSA B. SHERON NRR\\DE L. SPESSARD NRR\\DRCH K. WICHMAN NRR\\EMCB P. KU0 NRR\\PDLR J. LYONS NRR\\DSSA\\SRXB M. CHATTERTON NRR\\DSSA\\SRXB d
J. BIRMINGHAM NRR\\DRPM\\PGEB 4
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ATTACHMENT 1 l
l
NRC/B&WOG Executive Committee Meeting Agenda l
July 23,1997 a
l 1.
Introduction i
1
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+ Meeting Purpose l
+ BWOG Mission, Organization and Operating l
Principles 11.
Specific Technical issues-NRC Actions Reauested i
l
+ RCCA/CRA Insertion issue
+ Fuel Rod Corrosion / Advanced Alloys 1
l
+ Boron Precipitation Following SBLOCA l
+ Steam Generators: Alternate Repair Criteria (ARC) l
+ Generic License Renewal Program (GLRP) 111.
Specific Technical Issues - Information Only
+ High Pressure injection / Makeup Nozzle Leak Investigation Activities
+ Reactor Vessel Head Penetration inspections
+ Other issues IV.
Action item Summary V.
General Discussion July 23,1997
B&W Owners Group Membership l
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Duke Energy Corporation Oconee Nuclear l
Station I
Entergy Operations, Inc Arkansas Nuclear J
t l
One, Unit 1
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l Florida Power Corporation Crystal River Unit 3 4
l GPU Nuclear, Inc TMI-1 4
i Toledo Edison Company Davis-Besse 1 l
Framatome Technologies, Inc
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l July 23,1997 i
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B&W Owners Group l
l The B&WOG was formed to:
l
- Collectively address NRC, industry, and i
generic projects in a cost-effective manner i
- and, l
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- Improve communications among members.
1 i
l Our goals are to identify problems and i
solutions, improve safety, achieve high plant l
availability, and reduce costs.
h July 23,1997
i I
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B&W OWNERS GROUP ORGANIZATION t
i EXECUTIVE COMMITTEE 4
i STEERING COMMITTEE j
I l
RISK BASED APPLICATIONS WORKING GROUP REGULATORY REDUCTION WORKING GROUP I
I I
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ANALYSIS CHEMISTRY CORE PERFORMANCE GLRP l&C L
ICR W/G I
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MATERIALS NDE OPERATOR SUPPORT PLANT PERFORMANCE STEAM GENERATOR L RV W/G
- TRAINING T/F
- VALVE WORKING GROUP
- SAMG W/G
- OUTAGE MANAGEMENT W/G
- MAINTENANCE W!G
- DOSE REDUCTION T/F July 23,1997
i l
RCCA/CRA Insertion Issue i
l
= Objective: To demonstrate that the requirements l
of the proposed supplement to NRC Bulletin 96-i 01 do not apply to Framatome Cogema Fuel (FCF) fuel designs i
i
Background:
l l
- There have been cases of incomplete RCCA insertion l
at Wolf Creek, South Texas, Ringhals, and Doel i
FCF fuel has not experienced this problem when used e
l in either B&W or Westinghouse-designed reactors i
l Bases For Exclusion:
l
- Analytical Results i
Operational Data e
j Design Comparisons e
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Chronology of B&WOG/NRC Interactions i
e December 18,1996:
- FCF/B&WOG met with NRC l
{
January 31,1997:
j
- B&WOG submitted summary of Dec 18* meeting 3
i July 23,1997 l
l j'
i RCCA/CRA Insertion issue L
(con't?
May 20,1997:
- NRC issued proposed supplement tc,Bulletin 96-01 i
- June 18,1997:
j
- FCF/B&WOG submitted comments on proposed I,
bulletin supplement i
j
- July 18,1997:
- B&WOG submited information to supplement j
January 31" submittal l
l Requested NRC Actions:
l e Complete review on B&WOG submittal before issuing the bulletin supplement.
j e Concur that FCF fuel is not subject to
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RCCA/CRA insertion problems, i
l OR i
l Identify technical basis for not
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granting exclusion.
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July 23,1997 I
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CORROSION / ADVANCED ALLOYS l
Objectives:
. Obtain NRC acceptance of 125 micron corrosion limit for current fuel.
1 Facilitate licensing of advanced alloy (M5) for routine i
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batch use.
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Background:
l BAW-10186, Extended Burnup Topical, requested an l
increase in the burnup limits for FCF fuel.
j Burnup extension was granted, but the fuel rod j
corrosion limit was reduced from 125 to 100 microns.
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. The imposed 100 micron criterion restricts fuel cycle designs such that the allowable burnup is reduced.
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. BAW-10186 contained data on FCF fuel showing 125 l
microns of oxide was acceptable.
j Status / Schedule:
j
. FCF is preparing an advanced alloy (MS) topical for submittal in September 1997 4
i Requested NRC Actions:
l
. Revise the corrosion limit in BAW-10186 to 125 I
microns
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OR l
Identify the technical basis for not accepting it.
j
. Complete the advanced alloy topical report review by i
9/30/98.
3 i
July 23,1997
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i BORON PRECIPITATION i
l FOLLOWING SBLOCA i
Peoject Objective:
i l
Demonstrate the capability of each plant to adequately j
manage the control of boron in the reactor coolant system following a LOCA.
- May demonstrate a solubility margin already OXISts.
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. Appropriate procedure and plant hardware i
changes will be made.
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Project Status:
1
= Material presented at July 1996 RRG meeting has been documented and sent to NRC.
i B&WOG currently supporting development of the e
FPC active dilution methodology (ie, hot leg j
injection).
l FPC submittal of hot leg injection method planned l
for late August /early September timeframe.
l l
Test plan for boron solubility testing has been approved by Analysis and Chemistry Committees.
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July 23,1997 i
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BORON PRECIPITATION FOLLOWING SBLOCA (Con't)
Project Schedule j
Solubility testing, if needed or desirable, to be e
completed in mid-1998.
i Requested NRC Actions:
NRC feedback on acceptability of submitted i
information.
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July 23,1997
E Steam Generator Alternate Repair Criteria (ARC) Project J
i OBJECTIVE i
. Obtain ARC for OTSG Tube " Patch" Intergranular j
Attack (ICA) in Tubesheet and Freespan Regions i
STATUS i
l
- ANO-1 Lead Plant.
Pulled Tube Database Assembled.
e IGA Samples Manufactured and Inspected.
j Probability of Detection / Growth Rate / Probe Wear e
Studies Completed.
l Stress Analysis Near Completion.
)
Leak / Burst Testing in Progress; NDE Correlations to e
Follow.
l l
Likely Result: Voltage for Detection, Rotating e
l Pancake Coil for Length / Width, with Max. Defect Sin l
Based on Stress Analysis and burst / leak correlations.
1 i
i Jul/ 23,1997
Steam Generator Alternate Repair Criteria 4
(ARC) Project (con't?
l SCHEDULE:
i l
- Staggered Submittals in 1997/1998
- Mechanism Morphology / Lab Samples 7/25/97
- Tube Loads / Analysis 8/7/97
- Correlations / Repair Limit (Tubesheet) 9/1/97 I
- Correlations / Repair Limit (Freespan) 1/31/98
- Usage Goals:
j
- Spring 1998 Use of Tubesheet ARC
- Spring 1999 Use of Freespan ARC Requested NRC Actions:
I
- Timely Reviews /RAls by Multiple Technical Branches to Support Usage Goals.
- Timely Resolution of Severe Accident Consideration.
July 23,1997
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Generic License Renewal Program l
l The objectives of this program are:
l
- Support the ability of at least one utility to make
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decision regarding submittal of a License Renewal l
Application (LRA) before mid-1998, and position the
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other B&W plant owners to submit an LRA either concurrent with the lead plant or shortly thereafter l
- Perform generic activities where possible l
- Maintain proactive program to support industry l
initiatives l
j Program Accomplishments:
l
- NEl 95-10 License Renewal Implementation Guide -
l Demo results showed that 10CFR54 has produced a stable and efficient process for renewal 4
- Received DSER on Pressurizer Report on Sept.17, 1996
- Leadership role in industry activities July 23,1997
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Generic License Renewal Program 1
(con't) i Current Status:
4 Pressurizer Report final SER expected by July 31,1997 i
e l
- RV Report draft SER expected by end of third quarter i
1997. Response to final set of RAls to be submitted l-on August 15
- RV Internals Report to be submitted by August 1, l
1997 l
- Emerging potential Aging Management issues will be presented to the NRC technical staff in August.
i Requested NRC Actions:
l l
Two B&WOG Topical Reports need NRC attention:
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- Reactor Vessel (6/96) - Thirteen months and no DSER l
yet i
Reactor Vessel Internals (8/97) - Draft feedback will be e
needed for Oconee LRA submittal in mid-1998.
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l July 23,1997 e
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'HIGH P'RESSURE INJECTION / MAKEUP NOZZLE LEAK INVESTIGATION ACTIVITIES i
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Plant Events:
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l in 1997 a Leak occurred.in Oconee Unit 2 HPl/MU o
i nozzle. Degradation was found in nozzle components.
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. Degradation was also found in Oconee Unit 3 HPl/MU j
nozzle components.
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l Degraded components were original equipment e
i installation.
j Affected components for both nozzles were replaced e
l with improved design.
Oconee Unit 1 HPl/MU nozzle components were found j
e to have no significant degradation.
July 23,1997
HIGH PRESSURE INJECTION / MAKEUP NOZZLE LEAK INVESTIGATION ACTIVITIES (con't)
Root cause investigation:
Degraded components were delivered to metallurgical laboratory for analysis.
e Duke Energy Corporation Failure Investigation Process l
(FIP) Team report was prepared evaluating possible causes of degradation and leak.
The FlP Team determined the root cause of the weld j
e j
failure to be:
Failure to implement an effective HPl nozzle j
inspection program and, i
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Failure to effectively evaluate known problems and l
implement appropriate corrective actions l
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i July 23,1997
l I-I l
HIGH PRESSURE INJECTION / MAKEUP NOZZLE l
LEAK INVESTIGATION ACTIVITIES l
(con't) i i
B&WOG Actions:
I.
1 l
- Interim B&WOG report was submitted to the NRC on j
6/5/97, documenting design and operational differences among the B&WOG plants. The report identified differences between Oconee 2 and 3 and the rest of the B&WOG plants.
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- Final report documenting the root cause analysis and j
future recommendations will follow in late 1997.
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. Recent examinations at other B&WOG plants have shown acceptable conditions for HPl/MU nozzle components.
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r July 23,1997
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REACTOR VESSEL HEAD PENETRATION INSPECTIONS The objectives of this program are:
. Ensure applicability of Safety Evaluation
- Evaluate susceptibility to cracking l
- Perform Vessel Head Penetration inspections, as 4
necessary to support B&WOG program i
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- Provide tools and information for effective utility management of economic risk I
Participate in industry efforts e
i l'
1 4
July 23,1997
REACTOR VESSEL HEAD PENETRATION INSPECTIONS (con't)
Program Accomplishments:
o Oconee 2 initial and followup inspections have been completed o CIRSE (crack susceptibility) model has been developed o Material data has been retrieved and evaluated o Relative susceptibility has been determined o Joint industry programs on crack initiation, crack growth, and mitigation initiated o inspection techniques and acceptance criteria developed for below RV head and top of RV head July 23,1997 u;
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4 REACTOR VESSEL HEAD PENETRATION INSPECTIONS l
(con't) l Current Program Status:
i B&WOG response to GL 97-01 is on schedule e
(120-day response)
Third inspection planned at Oconee 2 (1999)
=
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Inspection planned at Crystal River 3 (1999) i i
Water jet conditioning process development is on e
j schedule (repair and mitigation) i t
l Thermocouple nozzles (Oconee 1 and TMI-1) are l
being evaluated, inspections likely in about 2001 i
i
.i July 23,1997
4 OTHERISSUES l
i 1
. B&WOG EOP REVISION PROGRAM i
RV MATERIALS DATA BASE AUDIT a
i NRC QUESTION REGARDING POSSIBLE CR-3 GENERIC ISSUES I
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i July 23,1997
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NRC Requested Actions Summary 1.RCCA/CRA Insertion Actions:
l
. Complete review on B&WOG submittal before j
issuing the bulletin supplement.
i
. Confirm that FCF fuel is not subject to RCCA/CRA l
insertion problems.
i OR i
Identify technical basis for not granting exclusion.
- 2. Fuel Rod Corrosion / Advanced Al!oys Actions:
l
. Revise the corrosion limit in BAW-10186 to 125 l
microns.
l OR j
Identify technical basis for not accepting it.
j
. Complete the advanced alloy topical report review l
of 9/30/98.
. NRC feedback on acceptability of submitted j
information.
l
- 4. Steam Generator Alternate Repair Criteria (ARC) l Project actions:
. Timely Review /RAls by Multiple Technical l
Branches to Support Usage Goals.
. Timely resolution of Severe Accident considerations.
l
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July 23,1997
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- 5. Generic Licensing Renewal Program actions:
Two B&WOG Topical Report need NRC management attention to achieve the review cycle required to support program objectives:
)
. Reactor Vessel (6/96) - Thirteen months and no
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DSER yet.
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. Reactor Vessel Internals (8/97) - Draft feedback will be needed for Oconee LRA submittal in mid-1998.
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t July 23,1997
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cc:
B&W Owners Group Project No. 693 Mr. Robert W. Keaten, Chairman Mr. W. W. roster, Chairman B&WOG Executive Committee B&WOG Steering Committee Vice President & Director of Director of Safety Assurance Technical Functions Duke Power Company 1
GPU Nuclear Corporation 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 Mr. f. McPhatter, Manager i
Framatome Cogema Fuels 3315 Old Forest Road P.O. Box 10935 Lynchburg, VA 24506-0935 i
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