ML20199H078

Summary of 971113 Meeting W/Wog in Rockville,Md to Discuss Issues of Mutual Interest Including WOG Strategic Plan, Interactions W/W on Potential Issues,Fuel Rod Internal Pressure & Incomplete Rod Insertion.List of Attendees Encl

ML20199H078
Person / Time
Issue date:	11/18/1997
From:	Craig C NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
PROJECT-694 GL-92-01, GL-92-1, NUDOCS 9711260012
Download: ML20199H078 (36)

Text

-

O g.a..gk UNITED STATES j

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s NUCLEAR REQULATORY COMMISSION 1

WASHINGTON, D.C. 30eeH001 November 18, 1997 MEMORANDUM FOR: Thomas H. Essig, Acting Chief Generic lasues and Environmental Projects Branch Division of Reactor Program Management Office of Nucler Reactor Regulation FROM:

Claudia M.

sig, Senior Project Manage M(( w,

C Generir '

s and Environmental Projects Branch Divisior.

Reactor Program Management k

Office of A -Jear Reactor Regulation

SUMMARY

OF SEMI ANNUAL NRP/ WESTINGHOUSE OWNERS GROUP (WOG) SENIOR MANAGEMENT MEETING The subject meeting was held at the NRC offices in Rockville, Maryland on November 13,1997, between senior management of the WOG and NRR, The purpose of the meeting was to discuss issues of mutual interest including the WOG strategic plan, WOG interactions with Westinghouse on potential issues, fuel rod intemal pressure, incomplete rod insertion (IRI),

baffle barrel botting, risk informed /probabilistic risk assessment applications, life cycle management / license renewal program, Generic Letter (GL) g2-01, Supplement 1 closeout, utility 10 CFR Part 50, Appendix B quality assurance audits of vendors, and Year 2000 issues. is a list of participants. Attachment 2 is the WOG presentation material.

The WOG desciibed the orga9zation of the various WOG subcommittees. Over the past year, the WOG has developed a strategic plan to assess how the WOG can best serve its membership in the future. The effort resulted in identifying a number of proposed actions locluding creating an executive management group, improving NRC interface, evaluating how to deal with more programs than the budget allows, and identifying utility resource requirements.

The WOG also described how it interacts with Westinghouse regarding potential issues. The potential issues core team was formed to improve defining, communicating, and resolving potential issues with Westinghouse. The WOG and Westinghouse intend to continue the rrocess.

The WOG summarized a recent meeting concerning WOG activities with regard to the fuel rod intomat pressure issue. The staff requested that when the generic screening criteria are exceeded and a plant specific analysis is performed, the WOG provide to the NRC the conclusion of the plant sp,,ile analysis with regard to compliance with 10 CFR 50.46.

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November 18, 1997 The staff provided the WOG information regarding close-out of tlm IRl issue (Attachment 3).

The staff summarized the issue, recent developments, and the staff review conclusions. The staff provided its position that IRI is a degraded condition per 10 CFR Part 50 Appendix B, and thus, the staff will continue to monitor corrective actions through normalinspection and j

reporting actMties. A Federal Register notice will be published in the near future announcing that a supplement to Bulletin 96-01 will not be issued, i

i The WOG provided an overview of the program to systematically assess the condition of bolts in the befne barrel region. This is a broad, long term program that involves EPRI and l

intomational mJvisory committees. The WOG provided a summary of activities to date and described the activities that need to occur to meet the proposed inspection schedule. The WOG stated that inspections are being planned for the fall of 1998 and the submittels will need to be approved prior to the inspections.

The WOG discussed their life cycle management / license renewal program. To date, five generic topical reports (GTRs) have been submitted and need to be reviewed to support WOG member license renewalinitiatives. The staff informed the WOG that the review of the G I

a low pr:arity item and may be subject to budget cuts.

N WOG provided information on risk informed PRA applications and the WOG expectations

. the risk-informed applications need timely review and approval for fall 1998 outages.

7

';ne NRC staff suggested discussion of three additional topics. First, the staff provided an update of the activities on the closeout of GL g2-01. The staff recently met with NEl and the vessel owners group and discussed the staffs plans to write letters to licensees identifying the closeout requirements for each plant. The staff summarized the meeting and staff plans.

Second, the staff expressed concem over licensees' 10 CFR Part 50 Appendix B quality assurance audits. Recent NRC inspections at fuel vendors identified significant de6ciencies and programmatic weaknesses that raise the issue of thoroughness of customer audits. Third, the staff requested information on WOG participation in the Year 2000 issue. The staff questioned the level of industry support for the NEl document, ' Nuclear Utility Year 2000 Readiness,* NEl/NUSMG g7-07, since it was not considered a formal NEl initiative. The staff discussed possible future actions.

The WOG and staN agreed that emerging issues should be added to future NRR/WOG senior management meeting agendas. Two such emerging issues were discussed at this meeting:

sump issues and fire protection. With respect to the sump issue, the WOG questioned what credit would be given for plants with leak before break as far as eliminating loads used to evaluate the sump issue. The staff requested the WOG submit their proposal as part of the i

comments on the draft GL and Regulatory Guide.

Project No. 694 Attachments: As stated cc w/stts; See next page s

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November 18, 1997 The staff provided the WOG information regarding close-out of the IRI issue (Attachment 3).

The staff summarized the issue, recent developments, and the staff review conclusions. The staff provided its position that IRI is a degraded condition per 10 CFR Part 50 Appendix B, and thus, the staff will continue to monitor corrective actions through normal inspection and reporting activities. A Federal Register notice will be published in the near future announcing that a supplement to Bulletin 96-01 will not be issued.

The WOG provided an overview of the program to systematically assess the condition of bolts in the baffle barrel region. This is a broad, long term program that involves EPRI and intemational advisory committees. The WOG provided a summary of activities to date and described the activities that need to occur to meet the proposed inspection schedule. The WOG stated that inspections are being planned for the fall of 1998 and the submittals will need to be approved prior to the inspections.

The WOG discussed their life cycle management / license renewal program. To date, five generic topical reports (GTRs) have been submitted and need to be reviewed to support WOG member license renewal initiatives. The staff Informed the WOG that the review of the GTRs is a low priority item and may be subject to budget cuts.

The WOG provided information on risk informed PRA applications and the WOG expectations that risk informed applications need timely review and approval for fall 1998 outages.

The NRC staff suggested discussion of three additional topics. First, the staff provided ari update of the activities on tSe closeout of GL 97.-01. The staff recently met with NEl and the vessel owners group and discussed the staff's plans to write letters to licensees identifying the closeout requirements for each plant. The staff summarized the meeting and staff plans.

Second, the staff expressed concern over licensees' 10 CFR Part 50 Appendix B quality assurance audits. Recent NRC inspections at fuel vendors identified significant deficiencies and programmatic weaknesses that raise the issue of thoroughness of customer audits. Third, the staff requested information on WOG participation in the Year 2000 issue. The staff questioned the level of industry support for the NEl document, ' Nuclear Utility Year 2000 Readiness," NEl/NUSMG 97 07, since it was not considered a formal NEl initiative. The staff discussed possible future actions.

The WOG and staff agreed that emerging issues should be added to future NRR/WOG senior management meeting agendas. Two such emerging issues were discussed at this meeting:

sump issues and fire protection. With respect to the sump issue, the WOG questioned what credit would be given for plants with leak before break as far as eliminating loads used to evaluate the sump issue. The staff requested the WOG submit their proposal as part of the comments on the draft GL and Regulatory Guide.

Project No. 694 Attachments: As stated cc w/atts: See next page DOCUMENT NAME: 11_13_97. MIN DISTRIBUTION: See next page OFFICE PGEB y,.

SC:PGEB, CCraighk. MCasef NAME DATE f,/ k /97 H / / /97

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/97 OFFICIAL RECORD COPY

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WOGlNRR SENIOR MANAGEMENT MEETING NOVEMBER 13,1997 MEETING PARTICIPANTS Name Organization Michele D:Wtt Westinghouse /NSD j

Hank Sepp Westinghouse T. Satyan Sharma AEPMOG C. l. Grimes NRC/NRR/PDLR G. C. Laines NRC/NRR/DE Brian Sheron NRC/NRR/ADT Sam Collins NRC/NRR Tom Greene Southern NuclearMOG Jack A Bailey TVA/WOG EAC Vice Chairmen Lou Liberatori Consolidated Edison /WOG Andy Drake Westinghouse /WOG Project Office Sam Binger Westinghouse /WOG Project Office Adel El Bassioni NRC/NRR/SPSB Greg Cwalina NRC/NRR/HQMB Muffet Chatterton NRC/NRR/SRXB Bob Borsum B&W Owners Group i

Vance VanderBurg AEP/WOG Jack Stringfellow SNC/WOG Claudia Craig NRC/NRR/PGEB Scott Newberry NRC/NRR/DSSA Larry Phillips NRC/NRR/SRXB Jack Strosnider NRC/NRR/DE Lee Spessard NRC/NRR/DRCH Ted Marsh NRC/NRR/SPLB Steve West NRC/NRRISPLB Dick Wessman NRC/NRR/EMEB ATTACHMENT 1 w

C DISTRIBtJ"lON: w/ attar:hments: Summary of November 13,1997, meeting with WOG dated November

'8, 1997 Hard Copy Central Files PUBUC Project File PGEB R/F i

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SCollins/FMiraglia RZimmerman BSheron JRoe/DMatthews GHolahan/SNewberry Glainas/JGtrosnider CGrimes AEBassioni GCwalina MChatterton LPhillips LSpessard TMarsh S W est RWessman o

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WESTINGHOUSE OWNERS GROUP WOG/NRC MANAGEMENT MEETING November 13,19971:30 PM - 3:30 PM Two White Flint Building - 8' Floor Room A1/F1 Agenda 1:30 PM INTRODUCTION Jack Bailey, WOO EAC Vice Chairman Tennessee Valley Authoriry Meet ng Purpose e

Agen a Review Tom Greene, WOG Chairmaa e

1991 WOG Steering Committee Southern Nuclear e

1:45 PM IL WOG PRESENTATIONS Tom Greene Review of WOG Strategic Plan e

PotentialIssues Communications e

Fuel Rod Internal Pressure Issue e

Incomplete Rod Insertion e

Baffle Barrel Bolting Program e

Life Cycle Management / License Renewal Program Risk Informed / PRA Applications 2:45 PM IIL REVIEW WOG NRC SUBMTITALS lou Liberatori,WOG Vice Chairman Consolidated FAmn Priority of WOO Submittals Future Planned WCAP Submittals 3:00 PM IV. NRC NRC Comments / Suggestion

• GL 92-01 Supplement 1

+ Utility Appendix B Audits of Vendors

+ Year 2000 Actionitem Review e

3:30 PM V. CLOSING COMMENTS Tom Greene EmergingIssues e

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'1 WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 i

I. INTRODUCTION Meeting Purpose

- WOG/NRC Information Meetings Implemented in 1992

- Conducted on a Bian.lual Basis Last Meeting April 16,1997

- Interface Meetings Provide Maintain & enhance communication channels Candid discussion of open issues / concerns Major program activity update ReviewNRC status of WOG submittals 1

NRC input to WOG program planning & prioritization process Agenda Review l

1997 WOG Steering Committee

- OrganizationalChart i1/13/97 97NRC2. PPT 2

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Review of WOG Strategic Plan Defined process to assess how the WOG can best serve its membership over the next 3-5 years Process elements included: era analysis, business environment assessment, key strategic issues, self assessment, vision / aspiration, value proposition, assessment of performance and process issues, process changes, specific strategies, and implementation plan Why WOG undertook strategic review Enhance ability to obtain and retain utility participation on Steering Committee and Subcommittees Reverse decreasing trend in utility involvement in program guidance and review of deliverables Address issues identified from 1996 Subcommittee self assessment

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Address comments from Executive Advisory Committee members j

and Primary Representatives 11/1367 97NRC2. PPT 4

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Review of WOG Strategic Plan

- Process required five meetings over several months (April to October)

- WOG executive input obtained

- Conclusions Strengths - Confederacy (bottoms up); Utility involvement; l

Management structure; Broad focus Weaknesses - Executive involvement; Prioritization (ideas > budget);

Strategic process; NRC interaction

- Actionsidentified Improve executive involvement

- Proposal to create Executive Management Group

- Actionsidentified Improve NRC interface Program selection (base versus supplemental funding)

Utility resource requirements 11/13/97 97NRC2. PPT 5

WESTINGHOUSE OWNERS GROUPS l

WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS PotentialIssues Communications

- PI Core Team formed in 1992 to improve communication process on l

emerging issues

- The PI Core Team's function is to participate with Westinghouse in an interactive communications process that will enhance the definition, communication, and resolution of potential issues by drawing on collective knowledge of both WOG utility members and Westinghouse.

- WOG/W process to share preliminary potential issue information WOG participants include 8 to 11 members

- WOG has briefed NRC on the WOG PI Core Team process several times since 1992

- WOG intends to continue to use this process 11/13/97 97NRC2. PPT 6

1 WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting Novemher 13,1997 II. WOG PRESENTATIONS Fuel Rod Internal Pressure Issue

- WOG/W/NRC Meeting November 6,1997 Issue defined Screening criteria presented i

Plants currently in compliance i

Commitment to provide list of plants that will exceed screening criteria and when, and additional information

- Plants list will be provided shortly i

- WOG continues to participate in issue resolution Analysis Subcommittee will follow issue Generic guidance to be provided to membership on contents of licensee event reports Issue resolution plan details for both short term and long term to be developed 11/13/97 97NRC2. PPT 7

s WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Incomplete Rod Insertion

- WOG/NRC Meeting on October 3,1997 Present a response to the draft supplement Outlined a plan ofresolution Provided a follow-up response incorporating comments from the October 3rd meeting WOG waiting to hear from NRC 11/13h7 97NRC2. PPT 8

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Incomplete Rod Insertion

- WOG Proposed Process for Resolving Incomplete Rod Insertion Utilizes a burnup threshold limit, similar to the WOG's June 18th l

response to the proposed Supplement to Bulletin 96-01 The Westinghouse GROWBOW mechanical model is used to determine those fuel assembles susceptible IRI.

A plant specific safety evaluation can be performed to demonstrate adequate shutdown margin exist if the GROWBOW susceptibility criteria is exceeded.

Puts in place a mechanism that will demonstrate control rod insertability and provide for long term resolution of the IRI issue.

Use of the GROWBOW as a means of demonstrating control rod performance does not result in an unreviewed safety question.

11/13/97 97NRC2. PPT 9

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Incomplete Rod Insertion

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WOG Proposed Burnup Limits (MWD /MTU)

Assembly WOG Experience WOG Proposed -

Design Burnup Limits Burnup Limits 14x14 54,900 52,500 15715 52,500 52,500 17x17 IFM 58,000 5?,500 17x17 non-IFM 43,300 43,300 Higher burnup limits provides incentive for the utilities to collect higher burnup data.

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Baffle Barrel Bolting (BBB) Program l~

- 5 year program initiated by WOG in June 1997 to systematically assess the condition of bolts in the baffle barrel region:

barrel to former bolts baffle to former bolts edge bolts (baffle to baffle)

- Program objective is to maintain safety of plants by proactively managing aging effects on the bolts

- WOG program includes cooperation with:

JoBB (OGs, EPRI, vendors)

EdF - study of behavior of presently used reactor internals materials International / Japanese - develop alternate bolt materials for future use 11/13/97 97NRC2. PPT II

a WESTINGHOUSE OWNERS GROUPS-WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Baffle Barrel Bolting Program i

- WOG program management includes:

Executive Oversight Group Program Review Team Working group and task teams

- Update meetings with the NRC conducted on:

8/20/97 - program management review 9/25/97 - technical review 1

11/25/97 - technical review l

Intend to continue periodic meetings throughout program duration j

i 11/13/97 97NRC2. PPT 12

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Baffle Barrel Bolting Program

- Proposed NRC review schedule to support bolt inspection and replacement activities during plant outages:

topical report forjustification ofincreased break opening times -

submitted January 1997

- NRC approval March 1998 submittal of bolt analysis methodology and Multiflex 3.0 topical reports - January 1998

- NRC approval September 1998 submittal oflead plant group (2 loop) application of bolt analysis results - March 1998

- NRC approval September 1998

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting Novemhar 13,1997-l II. WOG PRESENTATIONS

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Baffle Barrel Bolting Program Primary Tasks for Lead Plant Inspection bid specs for on-site bolt inspection / removal / replacement risk-informed assessment licensing of enhanced analytical methods acceptable bolt distribution analysis on-site bolt inspection and destructive testing l

11/13/97 97NRC2. PPT 14

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Life Cycle Management / License Renewal Program

- 5 Year Effort (1993 - 1997) Objectives Generally Accomplished

- Major Deliverables are (4) Life Cycle Management Guides and (15)

License Renewal Generic Technical Reports (GTR)

- 5 GTRs Have Been Submitted to NRC NRC Approval of GTRs is Necessary to Support WOG Member License Renewal Evaluations / Initiatives 1

11/13/97 97NRC2. PPT 15

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 II. WOG PRESENTATIONS Risk-Informed PRA Applications

- Current programs include NRC endorsement of risk-informed IST application to pumps and check valves and risk-informed ISI application to piping.

WOG and WOG lead plants have worked closely with the NRC on linalizing the risk-informed SRPs and Reg Guides to achieve mutual benefits.

Issues need to be resolved to the satisfaction of the NRC and industry

- WOG Expectations ofRisk-Informed Applications WOG expects timely review and approval by NRC WOG expects that implementation of risk-informed regulation should not lead to another level of regulatory requirements.

11/13/97 97NRC2. PPT 16

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 III. REVIEW WOG NRC SUBMITTALS l

Priority of WOG Submittals Future Planned WCAP Submittals t

11/13/97 97NRC2. PPT 17 v

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Table 1: WOG WCAPs Submitted to NRC l

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Priority SER Date l

14748/14749 Justification for increasing Postulated Break OG-97-006 Genenc 9/98 Reviewinprogress. Included Opening Times in Westinghouse T a

January 31,1997 as a taskunder BBB program.

Water Reactors Risk Ranking Approach for Motor-Operated OG-97456 June 2, I Generic 2/98 Rev 1 to be udnessted to V-EC-1658-Rev 9 Valve in Response to GL 96-05 1997 h resolution of NRC RAls.

14333-P 1

Probabilistic Risk Analysis of the RPS and OG-95-51 Ginna end of Tecluscalreviewcompleted 14334-NP ESFAS Test Times and C@iaa Times June 20,1995 1997 by end of 9/97 14483 2

Genenc Me'hadatagy for Expan&d Core OG-95-093 Point Beach TBD Review =chahdal for 1/98 Operating Lintits Report December 1,1995 14696 3

Core Damage Assessment Guidance OG-96-098 Byron (tentatne)

TBD Review started but need lead l

1A,.m L-22,1996 plant subnuttal 14358 and 4

WOG Application of Risk-Based Methods to OG-96-078 Vogtle On Hold NRCissued draR 6/97 14358 Check Valve IST-Class 3 non-prop.

S-_ ;^- -- "-x 5,1996 ge' des /SRPs winch are tied to Sopit a,.a."

WCAP review

.WOG Application of Risk Based Methods to Subnutted by NEI Millstone 3 Sorry On Hold NRC iemmi draR 6/97 14572 5

Piping inservice l===~'ian April 4,1996 2

RPr winch are tied to review l

4 14486 6

ECCS Hot Leg Recirculation Elimination for OG-96-054 Comanche Peak TBD Review to start 6/98 Westinghouse 3 and 4 Loop Design NSSS July 18,1996 14571 7

WOG Application of Risk-Based Methods to OG-96-077 ShearonHams On Hold NRC iesmal draR 6/97 Pump IST-Class 3 iamuy.

S w. M 5,1996 gus' des /SRPs wluch are tied to

'6 WCAP review 13877 8

Reliability Asw +--- =: of Westinghouse Type TVA LAR Watts Bar TBD Review tobe completed by AR Relays Used as SSPS Slave Relays February 28,1996 12/97 14750 9

RCS Flow Verification Using Elbow Taps at Submitted by Farley "IBD Review to start i1/97 '

l Westinghouse 3-Imop PWRs Southern Company N,,... R 26.1996.

10541,Rev.2 10 Reactor Coolant Pump Seal Pesformance OG-84-122 Genenc On Hold WCAP not actively being l

Followingless of All AC Power 3,1984 reviewed because final i

206 (Rer. 2) resolution ofissue is' December 10.1986

'ag evaluated j

11992 11 Joint Westinghouse /WOG Program-ATWS OG-95-41 Byron On Hold NRCissued letter 7/1/97 Rule Administration Process May 2,1995 documenting their positions expressed in 12/96 nitg.

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Table 1: WOG WCAPs Submitted to NRC WCAP #

Titic OG Letter lead Plant Actions /Ceansments WOG Estimated Priority SER Date 12476 12 Evaluation ofIDCA During Mode 3 an.1 Mode OG-91-61 Generic on He*i No review currently ongoing, 4 Operation for Westinghouse NSSS November 27,1991 issue will eventually be resolved through the shutdown rulemaking.

License Renewal Submittals WCAP #

Title OG Letter Lead Plant ACII'" SIC'"""'"I8 WOG Estimated Priority SER Date 14422,Rev.2 1

License Renewal Evaluatiort Aging OG-97-024 Genenc 4/98 WOG has._,-:=" " to several Management for Reactor Coolant Supports March 4,1997 sets of RAls 14575 2

License Renewal Evaluadort Aging OG-96-071 Genenc 3/99 WOG has.+,-:- ' " to RA's Management for Class 1 Piping August 28,1996 6/13/97 14574 3

License Renewal Evaluation Aging OG-96-052 Generic 3/99 WOG has mpandret to RAIs Management for Pressurizer July 3,1996 14756 4

License RenewalEvaluation : Aging OC-96-103 Generic 2/99 Management for Pressurized Water Reactor December 11,1996 Containment Structure 14577 5

License Renewal Evaluation Aging OG-97-088 Generic 5/99 Management for Reactor Vessel Internals

%f 2-:12,1997 4

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Table 2: Anticipated WOG WCAP Submittals to NRC C'*"""

Title Estimated WCAP W.

WCG Submittal Date Priority Relaxation of PASS Requirements (NUREG-0737) 4 quaner,1997 Byronkad plant XXXXX (tentative) j.

Elimination of Periarlie Protection Channel Response Time Tests 4* quaner,1997 VogtleIxad Plant 14036 d

RT & ESF I.ogic and RxTrip AOTand STI 2 Quarter,1998 XXXXX d

Accumulator ACT 2 quaner,1998 XXXXX AppHeation Specific Integrated Circuits (ASICs) Program Consments Title g g;,,, g WCAP #

gg Subseittal Date Priority vanous Being submitteriin ASICS Development Program XXXXX sectioas. Firstsection submitted SouthTexas

, Izad Plant m

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 IV. _NRC -

4 Comments / Suggestions

- GL 92-01 Supplement 1

- Utility Appendix B Audits ofVendors

- Year 2000 i

Action Item Review l

V. CLOSING COMMENTS l

Emerging Issues -

Illl3M 97NRC1 PPT IR

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting I

November 13,1997 l

l Fuel Design Inspections Siemens inspection by NRC 2/97 thru 4/97 Findings: Significant deficiencies and programmatic weaknesses Specifics include:

1. Fuel bundle design may not meet GDC of 10CFR50 Appendix A

2. Data sets for some power profiles insufficient to justify uncertainty values

3. Computer code never brought under QA prograni

4. SPC documentation on T-H codes was inadequate

5. Insufficient guidance in computer code control procedure to ensure adequate V&V Overall, NRC confidence in SPC engineering is degraded

, Strengths include effective self-assessment, proactive management and SPC Action Plans Ref. NRC Meeting summary of May 13,1997; Siemens Inspection Exit 19 9mc2. PPT 11'8 3 Meeting dated May 'O,1997

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WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 FuelDesign Inspections Westinghouse inspection by NRC 2/5/95 thru 3/24/95; re: Performance-based Audit Findings: No violations or nonconformances were cited specifics include:

1. Westinghouse QA Plan implemented in an excellent manner for areas evaluated

2. Reload core design activities being adequately performed

3. Four volume MET COM document comprehensive and rich in analytical and procedural detail

4. W CNFD has a formalized, comprehensive training program

5. Strong quality culture exits

6. Performance of WCNFD staff, processes and products was adequate to excellent Weakness in procedural conformance of certain activities were identified (did not require specific action or written r sponse)

Ref: NRC Inspection Ry ort No. 99900005/95/01,7/25/95 11113/97 97NRC2. PPT 20

WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 l

Fuel Design Inspections Westinghouse Inspections Inspection-D No. 99901307/96-01,12/31/96 also resulted in no violations or nonconformances. Only minor weaknesses and minor inconsistencies in i

Westinghouse procedures were noted.

4 Customer audits of CNFD have also been favorable over the last three-year span including NUPIC k

t I1/13/97 97NRCdPT 21

l WESTINGHOUSE OWNERS GROUPS WOG/NRC Information Meeting November 13,1997 Year 2000 NEI issue " Nuclear Utility Year 2000 Readiness" document (NEI/NUSMG 97-07)

- Program development resource

- Compiled from best programs NEI working with the Nuclear Utility Sofhvare Management Group (NUSMG)

NEI has private electronic year 2000 news room available for utilities to share information between facility Y2K coordinators NUSMG will hold Y2K coordinator workshop on November 14 WOG will provide support to NEI as requested 11/13/97 97NRC2. PPT 22

CONTROL ROD INSERTION PROBLEMS CLOSE-OUT

O ISSUE e Incomplete Insertion of Control Rods e Events at South Texas and Wolf Creek S.TAFF ACTIONS eBulletin 96-01 eRequired Testing During 1996 eResults not conclusive eProposed Bulletin Supplement (For Comment) eRestrictive Burnup Limits eMid-Cycle Testing mm

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RECENT DEVELOPMENTS

• Industry Provided More Data & Analysis e Industry initiatives are expected to fully resolve issue e Staff Review

Conclusions:

e Current Regulation Met (TS,GDC)

• Defense in Depth Not Impacted (CR +

Boration available) e Low Safety significance

-Rods sticking high in core very unlikely

-Adequate safety margins even with some rods sticking in dashpot i

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STAFF POSITION

• IRI Is a " Degraded Condition" per Appendix B e Staff Will Monitor Corrective Actions Through NormalInspection and Reporting Activities e Supplement to Bulletin 96-01 Will Not Be Issued 1

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Westinghouse Owners Group cc:

Mr. Nicholas Liparulo Westinghouse Electric Corporation Mail Stop ECE 415 P.O. Bcx 355 P ttsbsrgh, Pennsylvania 15320-0355 1

Mr. Hank Sepp Westinghouse Electric Corporation Mail Stop ECE 4 07A P.O. Box 355 Pmsburgh, Pennsylvania 15320-0355 Mr. Andrew Drake Westinghouse Owners Group Westinghouse Electric Corporation Mail Stop ECE 516 P.O. Box 355 Pittsburgh, Pennspvania 15320-0355 W

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