ML20202D841

Summary of 971120 Meeting W/Ceog in Rockville,Md to Discuss Topics of Mutual Interest.List of Attendees,Meeting Agenda & Copies of Slides Used by CEOG in Presentations During Meeting Encl

ML20202D841
Person / Time
Issue date:	11/24/1997
From:	Stewart Magruder NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
PROJECT-692 NUDOCS 9712050167
Download: ML20202D841 (40)

Text

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• 8g 8t UNITED STATES

.j NUCLEAR REGULATORY COMMISSION

• a WASHINGTON, D.C. 306 4 0001 o

November 24, 1997 y,

MEMORANDUM TO: Thomas H. Essig, Acting Chief Ger e ic issues and Environmental Projects Branch Divi ion of Reactor Program Management Office Of Nuclear Reactor Regulation FROM:

Stewart L. Magruder, Project Manager M1Lh A

Generic lasues and Environmental Projects Branch Divicion of P.eactor Program Management Office of Nuclear Reactor Regulation

SUMMARY

OF NOVEMBER 20,1997, MEETING WITH THE EXECUTIVE COMMITTE5 0." THE COMBUSTION ENGINEERING OWNERS GROUP (CEOG) t On November 20,1997, a public meeting was held at the U.S. Nuclear Regulatory Commission (NRC) offices in Rockville, Maryland, between representatives of the NRC and the Executive Committee of the CEOG. Attachment 1 provides a list of attendees.

The purpose of the meeting was to discurs topics of mutualinterest. Attachment 2 provides the meeting agenda and Attachment 3 provides copies of the slides used by the CEOG in their presentations during the meeting.

Sam Collins, Director, Office of Nuclear Reactor Regulation (NRR) opened the meeting by welcoming the executives. Mr. Collins stated that these meetings were important to help maintain a dialog with the industry. He also requested that some time be set aside on the agenda for the next meeting for an overview of current NRR activities. This was quickly agreed to by the group.

David Pilmer, CEOG Chairman, next presented a report on CEOG activities, including a list of the 1998 strategic issues. During this presentation, Mr. Collins noted that he would like a discussion of the status of CEOG plants converting to the improved standard technical specifications on the agenda for the next meeting. This was also quickly agreed to.

Kevin Sweeney, Chairman of the CEOG Steam Generator Task Force, next provided an update on the task forces activities. In response to a question from the staff, the group indicated that they preferred a Generic Letter over a ne~ rule on steam generator (SG) tube integrity issues.if7 8 7 '

The group also discussed CEOG and EPkl guidance on in situ testing of SG tubes.

Dp Mr. Sweeney noted that the CEOG took the lead on this issue and provided input to EPRI. In \\)

response to a question from the staff, the CEOG stated that they would consider sharing their

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guidance with the staffin the near future.

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Bob Hardies, Chairman of the CEOG Reactor Vessel Working Group, next provided an update i

on materials issues. He discussed reactor vessel head penetration issues, reactor vessel Intemals degradation, and reactor vessel integrity. He noted that a recent inspection of.nli reactor vessel head penetrations at Millstone 2 revealed only one penetration with a very minor indication.

Jack Strosnider, Acting Deputy Director, Division of Engineering, NRR, next led a discussion of the stafs assessment of the industry response to Generic Letter (GL) 92-01, Revision 1, Supplement 1, regarding reactor vessel structuralintegrity. He noted that a meeting on this subject was held with representatives of all the owners groups on November 12,1997. He also i

stated that the stafs goals are to ensure that licensees evaluate all the available weld data for i

their reactor vessel and that the reactor vessel integrity database contains accurate data.

Mr. Strosnider presented a schedule for closing out the review of the GL. This schedule is Included as Attachment 4. A brief discussion of some new techniques for predicting reactor vessel embrittlement and for direct measurement of fracture toughness followed.

Mr. Collins next took some time to briefly discuss the myriad of issues that NRR is working on now. Some highlights of the discussion are listed below:

decommissioning issues some issues also apply to operating plants (e.g. disposal of

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radioactive waste r

advanced reactors the staff is actively involved in the Westinghouse AP 600 review i

license renewal no application yet - two lead plents

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architect engineer design inspections -looking at 16ssons lemmed evaluating whether e

to reduce number of large inspections and depend n ore on regional inspections -

l agreed to incorporated lessons learned from ongoing Millstone inspections 1

Generic Letter 91 18 - recently issued update to guidance regarding nonconforming or degraded conditions 10 CFR 50.59 developing rulemaking package l-final safety analysis reports developing positions / guidance on risk-informed updates and removal of information-l 10 CFR 50, Appendix R developing new nsk-informed rule L

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T. Ecsig 3-risk informed licensing submittals trying to be responsive to industry licensing issuc s Important that staff and licensees have clear understanding of scope of work and schedule control rod insertion - no more industry testing required Improved standard technical specifications staff resources lost to Millstone, therefore, some reviews have been pushed back - understand licensee's concem with schedules NRR organization many changes hope to stabilize early next year overall plant assessment process - one of EDO's top three issues - goal is to have new process defined by June 1998 next step is review of inspection process overall inspection hours have been dectuasing NRC Strategic Plan provides guidance for prioritizing staff activities - suggested everyone in industry read Direction Setting issue (DSI) 22 rulemaking function will move to NRR early next year DSI 13 - intent is to rely more on industry initiatives DSI 14 - staff in more sensitive to content and tone of public communications Following Mr. Collins, Brian Sheron, Acting Associate Director for Technical Review, NRR, added a brief discussion of dry cask issues. He also emphasized that, in accordance with DSI 13, the staff is being encouraged to endorse industry standards and guidelines rather than developing independent positions.

Nanette Gilles of the Technical Specifications Branch, NRR, next gave a short presentation on the status of the CEOG risk informed technical specification pilot program. Attachment 5 provides a copy of her handout. There was a short oiscussion of the requirement to develop a configuration risk management program. The CEOG stated that they are working on a program and that San Onofre would be the lead plant. The representative from Arkansas Nuclear One briefly discussed some plant specific issues. The staff agreed to pursue the issues further.

Tom Rodack, Director, Fuel Mechanical Design and Advanced Products, ABB-CE, next made a short presentation on ABB CE fuelissues. His presentation highlighted the fact that ABB-CE is aware of recent issues with other vendor's fuels and is proactively evaluating issues to avoid problems in ABB CE fueled cores.

Mr. Sheron next led a brief discussion on two issues that he believes deserve greater attention from the industry. These issues are: Year 2000 (Y2K) software problems, and licensee inspections of vendors. Regarding the Y2K issue, he noted that the Nuclear Energy institute

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440 f%.oped a guideline document but that the industry was not committed to following it. He noted that the staff planned to issue a draft generic letter on the subject soon and he encouraged the CEOG to comment on it. Regarding the vendor inspection issue, he noted that the staff has been performing inspections at vendors and discovering problems that licensees had not identified. He suggested that licensee audits should not be limited to paperwork reviews and that technical experts should be part of the audit teams.

After a brief review of action Nems, the group agreed to schedule another meeting in approximately six months.

Project No. 692 i

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' had developed a guideline document but that the industry was not committed to following it.' He noted that the staff planned to issue a draft generic letter on the subject soon and he

- encouraged the CEOG to comment on it. Regarding the vendor inspection issue, he noted that.

the staff has been performing inspections at vendors and discovering problems that licensees -

had not identified. He suggested that licensee audits should not be limited to paperwork.

reviews and that technical experts should be part of the audit teams.

- After a brief review of action items, the group agreed to schedule another meeting in approximately six months.-

Project No, Bg2 '

Attachments:. As stated cc w/atts: See next page

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CE' OWNERS GROUP Project No. 692 cc:

Mr. Gordon C. Bischoff CEOG Project Manager ABB Combustion Engineering M.S. 9615-1932 2000 Day Hill Road Windsor, CT 06095 Mr. David Pilmer, Chairman CE Owners Group San Onofre Nuclear Generating Station 14300 Mesa Road 1

- San Clemente, CA 92672 Mr. Charles B. Brinkman, Director Nuclear Systems Licensing ABB Combustion Engineering, Inc.

Post Office Box 500 2000 Day Hill Road Windsor, CT 06095 Mr. Charles B. Brinkman, Manager Washington Nuclear Operation's ABB Combustion Engineering, Inc.

12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852 e.

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. NRC/CEOG EXECUTIVE COMMITTEE MEETING ATTENDEES November 20,1997 NAME ORGANIZATION Gary Gates Omaha Public Power District Charlie Cruse Baltimore Gas & Electric Marty Bowling Northeast Utilities Richard Bemier Arizona Public Service David Pilmer Southem Califomia Edison Steven Wawro Consumers Power Co.

Early Ewing Entergy-Waterford Dwight Mims Entergy ANO Dwight Nunn Southern Califomia Edison Bob Hardies Baltimore Gas & Electric Kevin Sweeney Arizona Public Service Gordon Bischoff ABB Combustion Engineering (ABB CE)

Mike Bamoski ABB-CE Tom Rodack*

ABB-CE Ron Fitzgerald ABB-CE Phil Richardson ABB-CE Charlie Brinkman ABB-CE Leslie Collins ABB-CE Sam Collins NRC Brian Sheron NRC Gus Lalnes NRC Jerry Wermlel NRC Frank Grubelich NRC Stu Magruder NRC Tony Ulses*

NRC Ted Sullivan*

NRC Keith Wickman*

NRC Nan Gilles*

NRC Frank Orr*

NRC Scott Newberry*

NRC Millard Wohl*

NRC Shih Liang Wu*

NRC Om Chopra*

NRC Greg Cwilina*

NRC

• Attended portions of the meeting

e NRC/CEOG EXECUTIVE MEETING AGENDA NOVEMBER 20,1997 8:00 am introductions (Gary Gates, OPPD) 8:15 am Opening Remarks (Sam Collins, NRC) 8:45 am C-E Owners Group Report (Dave Pilmer, SCE) 9:00 am Steam Generator issues (Kevin Sweeney, APS) 9:45 am CEOG Activities to Address Materials issues (Bob Hardles, BGE)

- CEDM Penetration PWSCC

- Reactor VesselInternals 10:00 am Discussion of GL 92 01 Industry Responses (Brian Sheron, NRC) 10:15 am Risk informed Technical Specifications issues (Gary Holahan, NRC) 10:30 am Discussion of FuelIssuec (Tom Rodack, ABB) 10:45 am Year 2000 issue (Jerry Wermlel, NRC) 11:00 am Licensee inspection of Vendors (Brian Sheron, NRC) 11:15 am Meeting Wrap-up and Review of Action items 11:30 am Adjourn

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NRC/CEOG Executive Committee Meeting November 20,1997 Canaveton Enemeenne Deers Group NRC/CEOG Exec Committee Meeting Thursday, November 20,1997 8.00 em intrododions (Gary Gates, OPPD) 8:15 am Opening Romerks (Sam Collins, NRC) 9 00 am C E Owners Group Report (Deve Pilmer, SCE) 9.15 mm Steam Generator issues (Kevin fweeney, APS) 10.00 am CEOG Activities to Address Materials issues (Bob Hard es. APS)

. CEDM Penetration PWSCC

. Reactor Vesselintemels 10:15 am Discussion of GL 92-01 Industry Responses (8 tion Sheron, NRC) 10:30 am Discussion of Fuelissues (Tom Rodeck, A88) 11:00 am Year 2000 lasue (Brian Sheron, NRC) 11:15 am Licensee Inspections of Vendors (Brian Sheron, NRC) 11:30mm MeetingWrap-upandReviewofAdionhems 11:40 am Adpum coaston Em Owners GeoLe

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CEOG Chairman's Report Dave Pilmer (SCE)

November 20,1997 ce=s,,,o Topics e Overview e Mission e Organization e Strategicissues I

Cornbusbon Ervroeg Owrers Group

Membership (1998) e 8 Domestic Utilities (14 units)

- Artrone Public Service (Palo Verde 1,243)

- Baltirnore Gas and Electric (CCNPP 1&2)

- Consumers Energy (Palisades)

- Entergy(WSES and ANO2)

- Florida Power and Ught (St. Lucie 1&2)

- Northeast Utilities (Millstone 2)

- Omaha Public Power District (Ft. Calhoun)

- Southem Califomia Edison (SONGS 2&3) e 1 International Member (3 units)

- KEPCO,(Yongwang 344; Ulchin 3) e ABB(non-voting) co e,,n e o, CEOG MISSION

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e Address safety and regulatory issues o Provide a mechanism for establishing unified positions with the NRC e Undertake efforts which will reduce O&M and capital costs and reduce outage time e Provide a mechanism to share costs i

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Combu. ion Engin.enne 0 n. Identified most common SSCs involved in forced shutdowns

= identified largest contributors to unreliability and failures a Long term program will focus upon

- unplanned capability loss factor

- reduction of LERs Combuse Engmeenne Own.f8 G'oup

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Equipment Obsolescence y...

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...e e Reactor Protection System and Plant Protection System Long Term Maintenance Program n Ta sk objective is to de.velop cost eMeetive means to maintain RPS/PPS for the life of the plant

> Addreens en important obsolescence issue a EPRICollaboration c==a%% % %

Materialissues e improved Characterization of RVWeld Chemistry (Best estimato Cu and Ni values) m Completed, database issued to NRC e Development of Direct Measurement of Fracture Toughness e Generic CEOG Response to GL g7 01 on CEDM Penetration Cracking e RV Baffle Bolt evaluation e Psvised Plant Chemistry Manual cem t%=nne w om maw

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MATERIALSISSUES UPDATE BOB HARDIES (BGE)

CHAIRMAN, REACTOR VESSEL WORKING GROUP also presenting for Mike Melton (APS) Chairman, Materials Working Group CoutV5 TION ENGINEERING OMER8 GROUP l

MATERIALSISSUES UPDATE l

o CEDM Penetration Cracking a Generic Letter 97-01 Response a Millstone 2 Inspection a New Timing Model

> Proposed Direction l

e RVInternals Degradation

> Baffle Former Bolts a Otherintemals issues e RVIntegrity n GL 92-01 Response COMBUSTION ENGINEERING OWNERS GROUP

CEDM PENETRATION CRACKING e CEOG Response to GL 97-01 was issued to the Staff on July 25

> Believed to be responsive to GL

> Provided CEOG inspection plan

-Millstone in August 1997

-SONGS 3 in Early 1999

> Demonstrated that the issue was being appropriately managed by CEOG e Staff feedback?

CoutUST80N ENOWEERWG OWNERS OROUP CEDM PENETRATION CRACKING MILLSTONE 2 INSPECTION RESULTS e ABB inspected all 69 CEDM and 8 ICI penetrations using eddy current

> A cluster of axialindications discovered on CEDM penetration #15

-On the uphill side, below the partial penetration weld elevation

-indications lengths ranged from 0.16" to 0.44" e Depth sized by UT <0.022'

-Penetration #15 is located in an upper-middle row e Medium si *ceptibility within MP2 head COMBUSTION ENGINEERNO OWNERS GROUP nn.

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CEDM PENEiKATION CRACKING MILLSTONE 2 INSPECTION RESULTS

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-.e o Entireinspection performed:

n With one probe

> In 51/2 shifts (66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br />) n W1th total dose of 765mr o Indications were removed by grinding a Maximum depth of material removal was.032" o CEOG co-funded this inspection e Co-funding also available for next plant COM8USTION ENGINEERING OWNERS GROUP i

NEW TIMING MODEL l

e CEOG participating with EPRIin developing a new module for i

Checworks

> CEDM timing model developed by DEI l

> Currently used by BWOG and some WOG l

member plants n Updates current CEOG model

> This will provide input to overall industry inspection plan CouBUST10N ENGINEERING OWNERS GROUP

d REACTOR VESSELINTERNALS BAFFLE BOLTS e BAFFLE FORMER BOLT CRACKING

> EdF has experienced cracking of cold worked 316SS baffle to former bolts

- Most likely rnochanism is irradiation Assisted Stress Corrosion Cracking (lAsCC)

• W plants have configurations and materials similar to EdF units

- Concerned about potential occurrence in US e WOG and BWOG established JoBB (Joint Baffle Bolt Task Team)

= Work being managed by EPRI and funded via Owners Groups COW 808T10N ENGINEERING omdERS GROUP REACTOR VESSELINTERNALS BAFFLE BOLTS e Pallsr. des and Ft. Calhoun are the only CEGG plants whose core shrouds (baffles) are bolted to the former plates

> There are several significant differences between these CEOG shrouds and others that make Ft. Calhoun and Palisades bolts less susceptible to IASCC COMSUSTION ENGINEERING OWNERS OROUP

PALISADES PANEL & FORMER PLATE CONFIGURATION N[%

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COMSUsTION ENGINEERING OWNERS 0400P REACTOR VESSELINTERNALS BAFFLE BOLTS e CE used annealed 316SS bolts, not cold worked a Less susceptible to SCC e Preload on bolts, as percent of YS, is rnuch less e Differentialpressure across core shroud panels (baffle plates) in CEOG plants does not put tensile load on bolts during normal operation e CE design allows flexure of former plates relative to support barrel a Wdesign is rigidly bolted leading to greater stresses unde:

differential thermal expansion a CE design leads to less stress and less susceptibility to (ASCC COMBUSTON ENGINEERING OWNEAs GROUP

REACTOR VESSELINTEGRITY GL 92-01 ISSUES e NRC met with NEl and representatives of the Owners Groups last week

> NRC Feedback COMBUSTION ENGWEERWO OWNERS OROUP

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Chairman cot 8eusfoes (NG8NtiRee0 OmstRS OROUP STEAM GENERATOR ISSUES e SG Regulatory issues Perspective a Staff Feedback Requested e CEOG Activities e TubeIntegrityissues a intemals Degradation a Technical meetings with NRC Staff CohaeustcN tNGm:ttRING OWNER 8 Omoup 3

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REGULATORY ISSUES -TUBE INTEGRITY o TubeIntegrity-CEOG understanding e Current Status NRC willnotissue a rule a Stan rnoving to Genenc Letter approach

- Sample ' compliance

• Tech Specs

- Detailed Regulatory Guide (DG 1074) on Steam Generator TubeIntegrity a Stan plans to issue GL for comment by 12/97 with 90 day comment period a industry enorts -NEl/EPRl/CEOG e Staff feedback?

COMSWETON ENG#dtf R980 oWWERs OROUP CEOG ACTIVITIES - TUBE INTEGRITY

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e involvement in Regulatory Process a NEl Task Force and Working Group participation e Conducted Technical Workshop - July 1997 m includad sessions on

- Regulatory Guide

• Requirements *

- Run-time anaYses Monte Carlo Analysis Approach

- Case Studies of Condition MonitoringCperational Assessment

- Use of Pulled Tubes and in Situ Tes'.s

- Status of Regulatory Process presented by NEl e Alternate Repair Criteria development CoutusT10N ENGINE (R##G OWNER $ GROUP 1

ALTERNATE REPAIR CRITERIA e AxialCracking a Long axial cracking (> 3/4 inch) is the most significant issue at CE plants

- includes eggerate, freest;m and sludge pile regions

- Repair options limited

- Attemate repair criteria (ARC) not currently avaltable e CEOG undertook a program to:

n Develop axial crack evaluation methodology in three stages

1. Justify full cycle operation with

• plug on detection *

2. Plug-on-sizing ARC based on results of two EC coils having different sensitivities 3.True plug-on-sizing ARC CoueUSTioN ENCWEERNO ovetERS oRouP v

PROGRAM MILESTONES e Laboratory test summary report January 1998 a NDE, burst and leakage e Plug-on-detection model a Single cycle code Complete a Mult;ple ycle code January 1998 e Pu!Ied tube database s Demonstration version Complete w Finalversion December 1997 e Intermediate 'two coil

• ARC methods Jusy1998 e Multi cycle plug-on-sizing methods December 1998 cowovsnoa twomeERac ovmRs chouP

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TUBE INTEGRITY ACTIVITIES o CEOG SGTF tube integrity program includes tasks complementary to ARC activities:

s Neurr.I Network

- Uses artificialintelligence (neural network techniques) to correlate modeling to deposits and defects locations

- Expected to help members define when and where to inspect a Dose Assessment e Develop metrix of cases using the standard review plan, flex, and best estwnste anahses a in Situ Pressure Test Guiderlines

- Candidate selection criteria and leakage assessment CousVSTs0N tNGsNEIRmG OmstRs OROUP REGULATORY ISSUES - SG INTERNALS e SG Internals-CEOG understanding n information Notice 96-09 & Supplernent 1

- SG intemals degradation identrfied at EdF plants

- Affected EdF SGs are similar in design tow Model 51

. Significantly different from CE SGs in design and rnanufacturs a NRC published proposed Generic t.etter-December 1996 m NEl Task Force formed

- ABB CE and CEOG utilities represented

- Plan presented to NRC on May 1,1997 e Stafffeedback?

COMeOSTION EdG*EERNG OWNERS GROUP

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CEOG ACTIVITIES - SG INTERNALS e CEOG response to IN 96-09, including Supplement 1 - April 1997 m Report documented design differences between subject EdF units and CEOG plants

- Demonstrated that degradation due to the same causal factors was unlikely for CE plants

- Noted that pre-1997 inspections had not identified intomals degradation coususnow ewometmwG omens omoup CEOG ACTIVITIES - SG INTERNALS e Response to proposed Generic Letter a NElIndustry Task Force formed

- CEOG and ABB represented e Industry developed an Action Plan to include:

• Root cause evaluation of EdF lasues (by EPRI)

• Susceptibility evaluations and ranking (by Owners Group) e inspectionrecommendations(OG) s Bounding analyses and supporting safety evaluations (OG)

= Need and Schedule for lead plant inspections (OG)

CouedanoN EseomtemmG owwems Gmove i

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CEOG ACTIVITIES - SG INTERNALS e CEOG Response to SONGS Intemals Degradation a May 1997, SCE observed eggerate degradation in SONGS 3

- Root cause assessed to be flow assisted corrosion (FAC)

June 1997 Task authorized for a detailed ' Evaluation of Degraded SG Secondary Intemals Operability Assessment" s Task Elements

- Operability Assessment

- Susceptibility Assessment e Exponence Summary e SusceptMityAnaysis e Boundmg Anaysis

- Recommended Actions COMouSTION ENOWitRWG oWNEMi GROUP REGULATORY ISSUES - NRC MEETINGS

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...s e CEOG met with the NRC Staff on July 31,1997 NRC issues / concems for CEOG:

- Use of ATHOS models forinspection planning

- Operability of CEOG SGs re:Intemals Degradation

- Update on SGTF activities a CEOG presentations

- Demonstrated that CEOG was already engaged in activities that paralleled NRC concems

- ARC presentation initialdiscussion

- Initiated dialog on severe accident issues a Future meetings on ARC technicalissues COMsUSTloN ENGWEERWO OWNERS GROUP

SUMMARY

e CEOG Poshion a Group (SGTF) dedicated to addressing SG issues a SG issues identined as top strategic issue for CEOG e CEOG SGTF mission a Effective fomm for discussion and resolution of SG issues a Making progress in addressing issues involving safety and reliability of steam generators a Active CEOG participation on regulatory / industry issues a Communicate CEOG interests / activities to NRC and other industry organizations comustoneso ten oomtasonour 9

e Fuel Performance issues Implications for ABB CE PWR Fuel presented to NRC and CEOG Executive Committee November 20,1997 by Tom Rodack Director, Fuel Mechac.ical Design &

Advanced Products B989 Outline CEOG requested to comment on recent industry fuelIssues and implications for ABB CE PWR fuel A!!!!

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h Recent Industry Fuelissues

• Control Rod insertion Problems

• Integral Fuel Burnable Absorber (IFBA) failures

• Axlal Offset Anomaly Debris Failures Bottom Grid.to-Rod Fretting a

Zircaloy Grid to Rod Fretting IFBA Rod Internal Pressure ABil Control Rod insertion Problems Fuelissue distortion of thimble tubes in small thimble tube fuel results in interference with control rod insertion ABB CE implications a no problem for ABB CE fuel as reported in CE-NPSD-1049-P under auspices of CEOG ABB CE fuel's large diameter, heavy wall guide tubes are much more resistant to distortion critical buckling load approx 30x higher A!!!!

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Fuelissue 5 Zirlo< tad rods failed as a result of combined effects of core power history, operational strategy, axial offset anomaly, and core design ABB CE impilcations '

+ accelerated corrosion associated with crud deposition has not been observed in ABB CE fuel EPRI Water Chemistry Guidelines recommended for CE plants Allll

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Axial Offset Anomaly Fuelissue boron in crud deposits in upper regions of core where subcooled boiiing occurs, and causes power to shift to bottom of core subcooled boiling linked to aggressive fuel management ABB CE Implications no problems observed in modern ABB CE cores a very isolated historical occurrences of similar phenomenon at CE plants (1979 Calvert Cliffs 1)

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h Debris Failures Fuellssue some debris-resistant fuel has reduced, but not eliminated, debris failures ABB CE impilcations no debris failures have been observed in any ABB CE fuel equipped with the GUARDIAN debris-resistant spacer grid Ann i

Bottom Grid-to-Rod Fretting Fuellssue failures occurred at Wolf Creek due to inlet flow anomaly and/or mismatch in hydraulic conditions between standard & debris-resistant designs ABB CE 1mplications

• ABB CE's GUARDIAN design features solid end cap adjacent to grid support features - fretting cannot cause failure skirt between bottom grid and lower end fitting in all ABB CE fuel blocks crossflow at the bottom of the core Ann

gi Zircaloy Grid-to-Rod Fretting

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Fuel lasue grid-to-rod fretting failures in W reactors, TMI LFAs, and in non-CE fuel supplied to Fort Calhoun and Maine Yankee ABB CE implications co-resident ABB CE fuelin Fort Calhoun and Maine Yankee showed no failures or significant wear a laser-welded orids in current fuel, and advanced grid designs in development will eliminate isolated instances of fretting failures in ABB CE fuel A!!!!

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Rod Internal Pressure Fuelissue 100% helium release from zirconium diboride coating on surface of non-CE fuel pellets results in high rod internal pressure ABB CE Implications ABB CE uses erbia and gadolinia, dilute integral burnable absorbers solid fission products remain in the fuel pellet gas release not increased for integral absorber rods A!!!!

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hi Conclusions ABB CE continues to monitor industry developments identify issues elsewhere before they become a problem for ABB CE proactively address issues to avoid problems in ABB CE fueled cores None of the industry issues discussed today a

have implications for current ABB CE. fueled cores 8 1999 9\\\\E80

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. 4 4

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r SCHEDULE I

12/31/97: STAFF ISSUE RAls TO CEOG AND B&WOG LICENSEES 02/15/98: STAFF lSSUE RAls TO BWROG LICENSEES 03/31/98: LICENSEES RESPOND TO RAls 06/30/98:

STAFFISSUE FINAL CLOSEOUT LETTER TO j

LICENSEES 1

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12/31/98:

STAFF ISSUE REVISED NUREG 1511 AND RVID i

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l l

i

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'S STATUS OF THE RISK-INFORMED TECHNICAL SPECIFICATION PILOT PROGPAM SECY-97-095, April 1997, forwarded draft safety evaluation for RI-TS pilot to the Commission & identified open issue of commitment to a configuration risk management program (CRMP)

Commission approved issuance of RI-TS pilot plant amendments e

in May 1997 based on incorporation of CRMP commitment into the license Recently, lead pilot plant changed from ANO-2 to SONGS o

SONGS submittal to incorporate CRMP into TS Administrative Controls expected by early December Staff expects to issue SONGS amendments for LPSI & SIT allowed outage time extensions shortly after receiving December submittal Amendments for LPSI & SIT TS changes for remaining CE pilot e

plants will be issued as submittals to incorporate CRMP into TS are received Review of proposed changes for EDG TS will be corr.pleted early e

next year Attachraent 5

r.

~

b o.

i T., Essig -

4 had developed a guidelirw document but that the industry was not committed to following it. He noted that the staff planned to issue a draft generic letter on the subject soon and he encouraged the CEOG to comment on it. Regarding the vendor Irispection issue, he noted that the staff has been performing inspections at vendors and discovering problems that licensees had not identified. He suggested that licensea audits should not be limited to paperwork reviews and that technical experts should be part of the audit teams.

After a brief review of action items, the group agreed to schedule another meeting in approximately six months.

Project No. 692 Attachments: As stated cc w/atts: See next page DISTRIBUTION: See attach page l

OFFICE PM:PGEB:DRPM SC:PGhikRPM NAME SMagruder:sw 5M FAl sE[loNcz N

DATE 11/M/97 11 9 /97

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