ML20153F400

Summary of 980805 Meeting W/Util in Rockville,Md to Discuss Status of Current BWROG Activities & Future Initiatives

ML20153F400
Person / Time
Issue date:	08/31/1998
From:	Wilson H NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
PROJECT-691 NUDOCS 9809290112
Download: ML20153F400 (78)

Text

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Men g o& UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20066-4001

. \...../ August 31,1998 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management, NRR FROM: James H. Wilson, Senior Project Manager 1

Standardization Project Directorate r-Division of Reactor Program Management, NRR

SUMMARY

OF MANAGEMENT MEETING HELD ON AUGUST 5,1998, WITH THE BOILING WATER REACTOR OWNERS' GROUP i On August 5,1998, the staff held a public meeting with management of the Boiling Water Reactor Owners' Group (BWROG) at NRC headquarters in Rockville, Maryland. The purpose of this meeting was to discuss the status of current BWROG activities and future initiatives. A list of attendees and their affiliations is provided as Attachment 1.

The agenda used at the meeting is included at the beginning of the slide package used by the BWROG in its presentations which is provided as Attachment 2. The BWROG presented information on each of the agenda items as described below.

I ECCS Suction Strainer Performance As a result of concerns identified in Bulletin 96-03, BWR licensees have been installing .

replacement screens with filtering areas between 9 and 55 times larger than originally used.  !

Bulletin 96-03 requires confirmation of completion of required actions within 30 days of strainer ,

installation. The staff is finalizing its safety evaluation of the BWROG utility resolution guidance l

document and has left the issue of closure of Bulletin 96-03 as an open issue. One strategy '

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being considered is to close Bulletin 96-03 and conduct any remaining activities as follow-on items. The suction strainer issue is the subject of an ACRS meeting scheduled from 2:45 p.m. h until 4:15 p.m. on September 2,1998. y Containment Coatinas -

The industry is developing a utility resolution guidance (URG) document to address safety-related coatings. The Nuclear Energy Institute and the BWROG have scheduled a series of meetings during the months of August and September,1998, with the staff at NRC headquarters in ,

Rockville to discuss Generic Letter 98-04, the URG, and the results of the BWROG's coatings test program. Staff from the Office of Nuclear Reactor Research (RES) are taking the lead to set up a meeting in the September / October time frame to discuss the NRC's coatings research program and possible coordination of research by RES and the industry to support the containment coatings program.

Emeraency Procedures -

The BWROG has developed emergency procedures and severe accident guidelines (EP/ SAG) ,

as part of an industry initiative for accident management and mitigation; The staff reviewed the j NDa n,, qyqc(7 9809290112 980831 PDR TOPRP ENV9ENE h h*g [0k%,

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- BWROG's EP/ SAG document and transmitted a request for additional information (RAI) to the owners' group in April 1997. After reviewing the BWROG response to the RAI, the staff sent a letter to the owners' group dated July 20,1998, which stated that, although the industry should proceed with implementation of the EP/ SAG initiative, a meeting to discuss the program was desirable. The BWROG stated that once the industry has had a chance to consider the positions outlined in the staff's July 20,1998, letter, it will contact the staff to schedule a meeting on the issue.

Vendor Oversicht The BWROG discussed the activities of the Reload Analysis and Core Management Committee to team with NUPIC to address vendor oversight issues. The owners' group is working with NUPIC to develop guidelines as a means to enhance the quality and depth of oversight of vendor analytical activities. Audits of GE, Siemens, and ABB are planned. The NRC was receptive to the approach and encouraged the effort.

Channel Bowina The BWROG provided a summary of the industry efforts related to a the reported incidence of bowing in fuel channels with cold work at Limerick that were exposed to bumups beyond 40 GWD/MTU. The BWROG has been proactive on this issue, working with GE to determine which plants had susceptible fuel channels and when those plants' operating schedules were expected to reach burnup levels that could cause bowing. The staff stressed the importance of maintaining documentation for actions taken in industry initiatives such as this.

Appendix R issues The BWROG Appendix R program supplements the NEl's generic industry Appendix R program, including the NEl task force on circuits analysis. The BWROG expects to submit a draft pilot containing proprietary information for staff review. The BWROG was encouraged to coordinate its efforts with those of NEl to avoid unnecessary expenditure of staff resources.

Year 2000 Activities The BWROG reported the results of a study by GE that revealed that there are no safety-related components or systems in BWRs that u susceptible to the Year 2000 (Y2K) problem. BWRs licensees are working to be Y2K-ready (n, t -compliant), for safety-related and nonsafety-related systems needed for plant operability.

SRV Setpoint Drift Fix The BWROG is no longer directing utilities toward a platinum alloy material solution as a permanent fix for Target Rock 2-stage safety relief valves (SRVs). Instead, the BWROG is continuing to monitor platinum ion beam combarded disc performance, as well as developing an ASME code case seeking code credit for overpressure protection for BWRs. The NRC staff was requested to expedite approval and inclusion of the code case into Reg Guide 1.84 (ASME Section 111 - design and fabrication code case acceptability), after ASME issues the code case.

JOG AOV The BWROG summarized the status of the initiative by the Joint Owners' Group (JOG) conceming air-operated valves. The JOG is seeking to develop a common and cost-effective US nuclear utility AOV program to enhance safe and reliable AOV performance and allow timely

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, address ofindustry and regulatory AOV issues. The JOG is comprised of 42 utilitities with 69 plants and a total of 104 reactor units from all four NSSS vendors. The JOG is considering relevant ASME Code Cases and Maintenance Rule aspects; using risk-informed methodology for determining the level of AOV attention; using existing valid bases to justify current AOV design i basis assumptions and performance and conducting testing to validate where a lack of  ;

confidence exists; and applying GL 89-10 (MOV) lessons learned. The JOG considers that a key I element ofits program is NRC/ JOG agreement on the issues. The staff summarized recent I

activities by BRC to develop a better understanding of AOV issues and reaffirmed its intent to j interact closely with NEl, ASMI, and the JOG in this area. j i

Intermediate Voltaae Breaker Maintenance l l

The BWROG has formed a committee to take up the issue of intermediate voltage breaker maintenance. The associated committee activities are ongoing at this time.

1 PSA Certification i

The BWROG developed probability safety assessment (PSA) certification inethodology in July 1996, revising it in January 1998. To date,17 BWRs have been reviewed and 6 more are scheduled. At the April 1998 NEl PSA workshop, the industry recognized the value of a single approach. The WOG completed its first pilot in July 1998, while the B&WOG and the CEOG are planning pilot plant reviews in late 1998 or 1999. At the NRC's Risk Informed Workshop in July 1998, the industry indicated a desire to support discussions with the NRC staff on PSA methodology.

Response Time Testina The BWROG wishes to eliminate response time testing of intermediate response time loops by demonstrating that changes in respons, times beyond acceptable limits are detectable during other routine periodic testing. In December 1997, the BWROG submitted a supplement to the NRC-approved licensing topical report NEDO-32291, " System Requirements for the Elimination of Selected Response Time Testing Requirements", for staff review and approval. On May 21, 1998, the NRC staff issued an RAI on the supplement to NEDO-32291. The BWROG is working to resolve the issues identified in the staff's RAI and expects to submit supplementalinformation to the staff at the end of October 1998.

MSIV Leakaae BWR licensees at 8 plants have obtained technical specification (TS) changes to eliminate requirements for MSIV leakage control systems and to increase MSIV leakage rates based on methodology in NEDC-31858P. Three more BWRs are actively pursuing TS at this time. In January 1998, the staff issued a letter requesting that the BWROG evaluate the impact of revising the seismic experience data base by el:minating data from sites at too great a distance from reference seismic events. The BWROG's May 1998 reply is under review and the NRC staff is preparing a safety evaluation on the revised NEDC-31858P.

Improved Water Chemistry The BWROG is seeking clarification / relief from the NRC on 3 SER positions (on a 1991 BWROG topical report) to allow utilities to achieve HWC implementation credit in seeking recirculation piping inspection relief. In August 1998, Boston Edison Company submitted a lead plant submittal for its Pilgrim plant. The BWROG is seeking NRC review of the Pilgrim submittal and issuance of a safety evaluation in the fall of 1998 to support a Spring 1999 outage at Pilgrim.

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. Excess Flow Check Valves Because of the large number of excess flow check valves in most BWRs and the cost (both in time and occupational exposure) of operability testing of these valves, several BWR licensees are interested in amending their plant technical specifications to reduce the testing interval for these valves. A meeting between the NRC staff and the BWROG has been scheduled for August 6,1996, to discuss this issue further.

At the conclusion of the meeting Mr. Sheron, the NRR Associate Director for Technical Review, reminded the BWROG that the Commission briefing by all the owners' groups has been rescheduled for September 15,1998.

A workshop has been scheduled for September 1,1998, in Chicago on DSI-13 to address industry initiatives. Mr. Sheron stated that the staff was concerned about finding out when a licensee participating in a voluntary program to address some issue either changed a commitment or postponed it.

At the end of the meeting, there was a brief discussion of voluntary compliance with codes and standards. The NEl representative expressed concern that the update to 10 CFR 50.55a might be a backfit. There was some apprehension that the code process could wither and die.

The staff noted that that risk-informed submittals were usually relaxations that led to saving money and expressed the concern that licensees might be tempted to " cherry pick" changes based on risk-informed arguments.

The NRC staff observed that if one looks at design basis only, there may be an unconsidered risk component. In particular, the staff was concerned how severe accidents might be treated and cautioned that the industry needs to ensure that it integrates the risk side with the technical side. j Project No. 691 Attachments: As stated l l

cc w/atts: See next page l L. .

. Excess Flow Check Valves Because of the large number of excess flow check valves in most BWRs and the cost (both in time and occupational exposure) of operability testing of these valves, several BWR licensees are interested in amending their plant technical specifications to reduce the testing interval for these valves. A meeting between the NRC staff and the BWROG has been scheduled for August 6,1996, to discuss this issue further.

At the conclusion of the meeting Mr. Sheron, the NRR Associate Director for Technical Review, reminded the BWROG that the Commission briefing by all the owners' groups has been rescheduled for September 15,1998.

A workshop has been scheduled for September 1,1998, in Chicago on DSI-13 to address industry initiatives. Mr. Sheron stated that the staff was concerned about finding out when a licensee participating in a voluntary program to address some issue either changed a commitment or postponed it.

At the end of the meeting, there was a brief discussion of voluntary compliance with codes and standards. The NEl representative expressed concern that the update to 10 CFR 50.55a might be a backfit. There was some apprehension that the code process could wither and die.

The staff noted that that risk-informed submittals were usually relaxations that led to saving money and expressed the concern that licensees might be tempted to " cherry pick" changes based on risk-informed arguments.

The NRC staff observed that if one looks at design basis only, there may be an unconsidered risk component. In particular, the staff was concerned how severe accidents might be treated and cautioned that the industry needs to ensure that it integrates the risk side with the technical side.

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LIST OF ATTENDEES AT MEETING WITH THE BWROG HELD IN ROCKVILLE, MARYLAND ON AUGUST 5,1998 NAME AFFILIATION B. Sheron NRC S. Newberry NRC R. Wessman NRC J. Wermiel NRC R. Barrett NRC R. Caruso NRC K. West NRC M. Rubin NRC M. Chatterton NRC G. Hammer NRC R. Elliott NRC i M. Drouin NRC D. Skeen NRC K. Naidu NRC M. Cheok NRC J. Davis NRC J. Colaccino NRC R. Palla NTC G. Thomas NRC J.H. Wilson - NRC G. Jones BWROG - CPP&L W. Warren BWROG-SNC D. Fetters BWROG - PECO Energy

-T. Rausch BWROG - Com Ed S. Haller BWROG - IES Utilities W. Berg BWROG - PSE&G G. Kreuger BWROG - PECO Energy J. Ondish BWROG - PSE&G R. Sgarro BWROG - PP&L M. Coleman BWROG - PSE&G J. Kelly BWROG - NYPA C. Terry BWROG - Niagra Mohawk D.Townsend GE F. Emerson NEl Attachment 1

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l ECCS SUCTION STRAINER COMMITTEE i

Presentation for NRC/BWROG Management Meeting i

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August 5,1998 j Washington, DC I

i Rocky Sgarro PP&L, Inc.

TAG 98-15 revision 2 -

Attachment 2

NRC/BWR OWNERS' GROUP MANAGEMENT MEETING - AUGUST 5,1998 DISCUSSION ITEMS PRESENTER ECCS Suction Strainer Performance R. Sgarro, PP&L Containment Coatings R. Sgarro, PP&L Emergency Procedures B. Berg, PSE&G Vendor Oversight T. Rausch, Comed Channel Bowing T. Rausch, Comed Appendix R issues T. Rausch, Comed Year 2000 Activities S. Haller, IES SRV Setpoint Drift Fix J. Ondish, PSE&G JOG AOV M. Coleman, PSE&G STATUSIINFORMATION ITEMS Intermediate Voltage Breaker Maintenance G. Warren, SNC PSA Certification G. Warren, SNC ,

Response Time Testing G. Warren, SNC MSIV Leakage G. Warren, SNC Improved Water Chemistry G. Warren, SNC Excess Flow Check Valves G. Warren, SNC I

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- ECCS SUCTION STRAINER i

j i Committee Objectives: l I

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. Resolve the ECCS Suction Strainer issue for l

BWRs 1

. Ensure interim safe operation

. Ensure final resolution meets regulatory requirements

. Assist utilities in resolving Generic Licensing issues Presentation Objective:

. Discuss program status with NRC management i

TAG 98-15 revision 2

ECCS SUCTION STRAINER ..

1 US NRC Reaulatory Status:

. Bulletin 96-03 published on May 6,1996

-+ Associateu stegulatory Guide 1.82 Revision 2 issued May 10,1996

. URG submitted in November 1996

. NRC issued draft SER on URG for comments on December 31,1997

-+ Key issues discussed with NRC on 2-6-98

. BWROG transmitted comments on draft SER on March 13,1998 TAG 98-15 revision 2

. ECCS SUCTION STRAINER i

i US NRC Regulatory Status: (Continued)

Summary ofBWROG Comments on Draft SER:

. Bulletin 96-03 Final Closure 1 ,

• Requires confirmation of completion of j required actions within 30 days of strainer

! installation l

• Final compliance remains dependent on several i regulatory uncertainties (e.g., GL 98-04)

• Followup generic communication to clarify

Bulletin 96-03 closure plan appears to be

! appropriate.

. Compounded Conservatism 4

-+ NRC draft SER acknowledged existence of l conservatism in several areas, but applied ,

most conservative NRC recommendations to l each portion of the URG l

-+ BWROG communicated potential impacts, evidence of conservatism, and recommendations that would retain flexibility

. Technical issues TAG 98-15 revision 2

i l ECCS SUCTION STRAINER .

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- Provided recommendations regarding draft l SER statements of concern to BWROG i

l US NRC Regulatory Status: (Continued)

! . Based on discussions with the staff regarding our j comments, we believe that our concerns have l been satisfactorily resolved pending review of the

! final URG SER.

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! . Our understanding is that the SER is currently j projected to be issued the week of August 17, i 1998.

TAG 9815 revision 2

. ECCS SUCTION STRAINER i

i US NRC Bulletin 96-03 Implementation:

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i l . Alternate passive strainers is preferred resolution

option for all U.S. BWRs i

• Replacement strainer filtering area per BWR

plant ranges from approximately 1200 to 5400 square feet

! - Results in increased strainer area by factor of 9 to S5 l ,

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• For most BWRs the increase in strainer area ranges from 25 to 40 times that of the original design

. BWRs which have installed or will install new strainers in 1997/98 are addressing a wide range of design requirements:

TAG 98-15 revision 2

ECCS SUCTION STRAINER ..

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US NRC Bulletin 96-03 Implementation: (Continued)

! 1997M998 BWR Strainer Installations i

1997 Spring 1998 Fall 1998 l Browns Ferry 2 Brunswick 1 Browns Ferry 3

! Brunswick 2 Dresden 2 Fitzpatrick Cooper Duane Arnold Fermi 2

! Dresden 3 Grand Gulf Hatch t i

Hatch 1 LaSalle 2 LaSalle 1 Hope Creek Limerick 1 Oyster Creek (partial) NMP-2 Peach Bottom 2 LaSalle 1 Susquehanna 1 Quad Cities 1 Monticello Vermont Yankee Peach Bottom WNP-2 Perry Pilgrim Quad Cities 2 Riverbend i

i Lessons learned based on installations are communicated to all BWROG Members.

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TAG 98-15 revision 2

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. ECCS SUCTION STRAINER CurrentIssues/ Actions:

. Meet with NRC Staff to discuss final Bulletin 96-03 i closure plans

-+ Targeting mid-September if SER is issued prior to August 24th e Continue to provide member support until Bulletin 96-03 is closed l

TAG 98-15 revision 2

l CONTAINMENT COATINGS COMMITTEE Presentation for NRC/BWROG Management Meeting August 5,1998 Washington, DC Rocky Sgarro PP&L, Inc.

for Jeff Branum, SNC TAG 98-16 revision 2

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Containment Coatings Committee Objectives:

f i e Resolve the containment coatings issues

described in GL 98-04 in support of final

! resolution of the suction strainer plugging issue 1

. Provide input to NEl in support of resolution of ,

these issues for other U.S. nuclear plants  ;

\ Presentation Objective:

. Update NRC Management

Background:

. NRC has expressed concern regarding performance of non-qualified and indeterminate containment coatings with respect to ECCS suction strainer plugging

. Generic Letter 98-04 issued on July 14,1998 TAG 98-16 revison 2

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Containment Coatmgs 1 j

! Issue Resolution Stratenv:

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. Review available test data to develop defendable l

containment coating source terms Supplement with LOCA testing 1

( i j . Use transport methodology and results l developed by NRC and documented in l NUREG/CR-6369

! . Determine timing for coating debris release from

! substrate Delayed release facilitates increased settling l in suppression pool Use settling and strainer head loss methodology developed by ECCS Suction Strainer Committee

. Develop Containment Coatings Utility Resolution Guidance (CCURG) similar to what was developed by ECCS Suction Strainer Committee (URG) l

Containment Coatings l

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l Testina Results:

e Completed autoclave testing per ASTM DS911 i (ANSI N101.2) of 6 " engineered to fail" coatings i systems to determine

Time of failure Debris characteristics

. Five of the six coatings systems tested performed well for 30 minute LOCA

. Three of the coatings systems survived the 6-hour LOCA test intact

. These results indicate:

No immediate safety concern exists Most coating systems in use, when supplemented with periodic inspection and assessment in accordance with EPRI guidance, will not provide significant contributions to the potential for ECCS strainer head loss

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Containment Coatings Actions:

. Continue to support NEl Task Force

. Meet with NRC (include NEI):  ;

l Discuss BWROG approach to GL 98-04 closure Review BWROG LOCA test results Discuss NRC Containment Coatings test program objectives Evaluate. benefits beyond BWROG work versus impact on closure of Bulletin 96-03 issues

. Prepare template for BWR GL 98-04 response

. Draft BWR Containment Coatings Resolution Guidance TAG 98-16 revision 2

l EMERGENCY PROCEDURES COMMITTEE Presentation for BWR Owners' Group NRC Management Meeting August 5,1998 Rockville, MD Bill Berg PSE&G

! EMERGENCY PROCEDURES COMMITTEE j

i Committee Objective: l 4

! . Implementation of the Severe Accident Management program As outlined in NEl 91-04 Using the BWROG EPG/ SAG products Presentation Objective:

. Acknowledge receipt of NRC staff questions on EPG/ SAG, Rev.1

. Discuss the.BWROG position for discussion of the questions

EMERGENCY PROCEDURES COMMITTEE

Background:

The BWROG submitted EPG/ SAG Rev. O to the NRC for information in August 1996

. The NRC issued a RAlin April 1997 The BWROG responded to the RAl in January 1998 Further RAls were not expected The BWROG submitted EPG/ SAG Rev.1 to the NRC staff for information in January 1998

. NRC staff letter received in July 1998

l EMERGENCY PROCEDURES COMMITTEE Issues: l

- The NRC staff letter requests dialogue with the BWROG on specific questions

- BWR licensees are heavily involved in EPG/ SAG implementation to meet commitments and any redirection of resources to discuss or address the questions will delay EPG/ SAG implementation l

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1 EMERGENCY PROCEDURES COMMITTEE

! Actions:

l BWRs co'mplete EPG/ SAG implementation on i scheduie i

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In 1999, the Emergency Procedures Committee officers will arrange for a meeting to clarify the l NRC staff questions.

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RELOAD ANALYSIS & CORE MANAGEMENT COMMITTEE VENDOR OVERSIGHT P

Presentation For NRC/BWROG Management Meeting 1

! August 5,1998 Tom Rausch Comed for l

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Clifford Bonneau l

l NSP

I RACMC Vendor Oversight 1 1

Committee Objectives: i l l i e Information Sharing Among Members t

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• Advisory Group To Industry 3

i e Facilitate issue Resolution e Vendor Oversight i-1 i Presentation Objective:

i e Inform the NRC of planned vendor oversight !

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RACMC Vendor Oversight 3

Background:

. RACMC one year old Addressing a variety of technical issues Providing best practices and technical guidance

. July 1997 NRC Letter to Siemens Power Corp.

(SPC) licensees on LOCA methodology

- Deficiencies in documentation of analysis codes and models and V&V of approved codes aRer changes Licensees responsible for analyses and to conduct meaningful audits of contractors

. BWROG teaming with NUPIC to address issue

l' RACMC Vendor Oversight i Vendor Oversicht Plans 3

i e 1998 i

! - Develop program

- Audit GE- LOCA 4

e 1999 -If program viewed positively, propose to:

L j - Audit SPC & ABB-LOCA l

- Consider other technical areas l

. In-depth technical audit

! - Approximately 2 weeks in length

! - Team approach

- NUPlC lead auditor l

- LOCA consultant

6 utility members 1

l l . Use NUPIC process for resolving findings e ,

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RACMC Vondor Ovorsight Vendor OversichtPlans. Continued

. Areas Covered By Audit

- Computer Codes

. Change Processes

.V&V

. Versions Used

. Compliance with SERs

- Analysis inputs

. Design control

. Interface with utility

. Applicability of generic inputs

. Compliance with SERs

- Models used (Heat Transfer, Quenching, Spray efficiency, test data)

. Applicability

. Conservatism

. Technical bases

. Compliance with SERs

- Records I

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RACMC Vendor Oversight

Conclusions / Discussion

! e Team approach enhances the quality and technical depth of oversight 4

Addresses issues raised by NRC Reduces need for NRC review l e BWROG interested in NRC feedback i

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! CHANNEL BOW ISSUES COMMITTEE 4

i Presentation for NRC/BWROG Management Meeting August 5,1998 i

Tom Rausch '

Comed

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l Committee Objeclives:

. Develop BWROG Channel Bow Monitoring Plan (Complete)

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. Independently review the results of the GE Part 21 i Evaluations and monitor follow-on activities 4

. Continue dialog with the NRC l

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\ Presentation Objectives: l l

! . Review issue background and summarize current l committee activities i

. Overview BWROG independent review effort -

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\ Backaround:

4 l 6 Initial indication of channel bow occurred at j Limerick Unit 1 - noticeably slower scram time

! response but still within Tech Specs l . Preliminary root cause information and summary of l impacted plants provided to NRC by GE (May 11, l 1998 letter)

L l . Reactivity Controls Review Committee developed a high exposure Channel Bow Monitoring Plan

- Draft prepared in 2 weeks, finalized less than -

one month from initial NRC contact

- Formally approved by BWROG Primary Representatives shortly thereafter

- Transmitted to BWROG Executives as an Operating Recommendation for impacted plants

- Transmitted to the NRC for information

. NRC/GE/ Utility conference calls have been conducted periodically l

l CurrentActivities

. BWROG Primary Representatives approved funding for cafeteria Channel Bow issues Committee i

e First Committee Meeting (assessment) held July 29-30,1998 in Wilmington

. Reviewed entire GE PRC Assessment

- Root cause and materials / process issues

- Safety issues

. Channel / control blade interi~crence

. Increased local power peaking

. Critical power performance

. Thermal / mechanical performance

. Loss of coolant accident

. Control rod drop accident

. Core monitoring

. Conclusions of Assessment

- Agree with GE that earlier fabrication processes likely created the condition

- No safety impact, therefore no additional operating recommendations are required

- Confirmatory channel measurements planned

Conclusions

. Safety issues have been addressed

. NRC/BWROG open communications have been positive and have contributed to issue closure

. Resolution ofissues in this manner can reduce impacts on both NRC and licensees l

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APPENDIX R (FIRE PROTECTION) l l GENERIC COMMITTEE i

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l Presentation for j BWR Owners' Group /NRC

[ Management Meeting l

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Rockville, MD i l 3

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Tom Rausch I Comed d

l Greg Krueger

! PECo Energy i

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APPENDlX R (FIRE PROTECTION) ,.

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Committee Objectives:

. Develop consistent, reasonable, generic BWROG positions & guidance for Appendix R circuit analysis in a Guidance Document LTR e Provide common forum to resolve inconsistencies and interpretation differences for Appendix R circuit analysis issues

. Coordinate BWR owner response to pending l

Appendix R Generic Letter

. Develop generic resolution for ADS /LPCI (LPCS) functional redundancy issue Presentation Objective:

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. Provide program Status

. Present IRBR observations concerning fire IPEEEs Membershin: Generic Committee l

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! ., APPENDIX R (FIRE PROTECTION)

Recent Committee Actions:

. Completed comprehensive review of

!. Regulations, guidance and plant design &

) icensing bases l

l . Drafted sections of Guidance Document on j circuit analyses (Began October 1997) i

.- Held initial meeting with NRC Fire Protection l Section (April 13,1998)

. . Initiated communication plan and link to other 1 i Owners' Groups, maintaining NEl participation  ;

j (May 1998)

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! . Discussed Committee plans orid target schedule with NRC staff & management June 30,1998

- Reviewed portions of the draft documents

- Set stage for future interactions

. Reviewed BWROG IRBR Committee conclusions about application of fire IPEEE numerical results (July 16, '98)

i APPENDIX R (FIRE PROTECTION) ,.

) IRBR Committee Observations Re: Fire IPEEEs 4

i . Review of BWR fleet IPEEEs initiated to gain i overall insight l

l . IPEEE goal was to search for vulnerabilities l i

I o Methodologies designed to identify potential risk contributors in spatia! dependencies using gross and conservative screening

! methods i

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o Screening methods used assumptions which

. vary between plants

! o Assumptions are plant-specific, unit-specific, l (e.g., plant geometry, fire initiating frequencies, propagation) -

. Generic application of risk contributors should be done with caution

j ., APPENDIX R (FIRE PROTECTION)

IRBR Committee Observations. Continued i

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. Fire IPEEE results should not be used for p comparative evaluations / conclusions among

plants l . BWROG supports application of risk information i to Fire Protection and is working with other ,

l industry groups to develop the appropriate bases l

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APPENDIX R (FIRE PROTECTION) ,.

Anoendix R CurrentIssues/ Actions: l

. Prepare letter to NRC with 1) Committee plans, &

2) basis for proprietary claim

. Pilot the preparation, review & approval of  !

" draft" positions for discussion with NRC staff

. Meet with NRC staff to discuss pilot " draft" positions - mid September

. Establish schedule for reviewing with NRC staff the remaining " draft" positions and methodology

- target completion - end 1** Q '99 ,

. Continue communications with NEl and other Owners Groups

. Establish schedule for guidance document completion - target LTR submittal to NRC - end of 2"d Q '99 l

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f YEAR 2000 COMMITTEE '

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, Presentation for

' BWR Owner's Group / NRC Management Meeting August 5,1998 Steve Haller i IES Utilities

Year 2000 Committee ,.

Y2K Committee Objectives:

. Facilitation of best practices and information sharing among the member utilities

. Coordination of interfaces to other industry groups such as EPRI, NEl, INPO, NUSMG, USA and the NRC

. Perform initial assessment of GE-NE supplied (BWR specific) equipment Presentation Objective:

. Communicate BWROG Y2K project status

. Identify areas of future focus

. Obtain feedback on committee plan 2

i j ., ,

Year 2000 Committee 4

4 Status: ,

4 InitialAssessment: j

. GE-NE reviewing 105 systems for susceptible

components relative to the Y2K issue j - Work to date has not uncovered any Y2K l issues in any safety-related systems or components

. Information sharing when components are

! identified as potentially susceptible

. Examples of BWR digital applications:

O GE FANUC, Bailey or other controllers 0 3D Monicore and plant monitoring system software 1

3

Year 2000 Committee ..

i .

\ BWROG - Y2K Committee Benefits:

. Coordination of effort will provide consistency

in level of detail and eliminate interpretation l

questions

. A single program allows maximum cost j

leverage and on-going forums to share best i practices across the industry and communicate i findings l

l Areas ofFuture Focus: \

l l . BWROG sponsored peer assessments l

)

l J

. Coordination of detailed assessments and

! potential remediation

. Plan continued close cooperation with EPRI l and NEl, and other industry groups l . Continue participation in NEl Contingency Planning effort l

1 l

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1 _.

i SRV SETPOINT DRIFT FIX i DEVELOPMENT COMMITTEE l

l l Presentation for j BWR Owners' Group /NRC 1 Management Meeting i

i i

j. August 5,1998 ,

l Rockville, MD.

i 1

Joe Ondish Public Service Gas & Electric Co.

BWROG SRV Committee Chairman

?

SRV Satpoint Drift Fix Development ,.

i

Committee Objectives: -

l e Resolve Target Rock Two-Stage SRV Setpoint Drift issues i

i

- Pursue platinum ion-beam material i solution l

- Pursue, in parallel, the Pressure l Switch engineered solution.

l l Presentation Objectives: 1

. Program status Membership: (7)

DECO, NYPA, NUSCo, PECO, PSE&G, SNC,TVA J\SRVDF\NRC0898. doc 2 12/18/97

., SRV Satpoint Drift Fix Development  :

Status: ,

. Proposed platinum-alloy material solution deemed not to be a permanentfix to the SRV  !

setpoint drift problem; no longer being recommended to be actively pursued by BWROG utilities.

. BWROG is not directing utilities toward one specific solution.

. Continuing to monitor platinum ion beam bombarded (implanted) disc performance

- Reviewed fall 1997 results

- Reviewed spring 1998 results

. SRVDF Committee is developing an ASME Code Case seeking Code creditfor overpressure protection on early BWRs.

. Committee Chairman has recently discussed these issues with NRC (G. Hammer)

. Utilities are actively pursuing platinum ion beam (implanted) discs.

J\SRVDF\NRC0898. doc 3 l 12/18/97 l

SRV Sotpoint Drift Fix Dovalopment e

Committee Actions:

l l . Continue to monitor ion beam disc '

i performance

! . Develop ASME Code Case seeking relief i for overpressure protection credit on early i

BWRs.

l . Work with NRC to expedite approval &

inclusion of Code Case into Reg Guide 1.84 (design & fabrication code case acceptability ASME Section lli

.nSRVDFWRC0898. doc 4 12/18/97

JOINT OWNERS' GROUP AIR-OPERATED VALVE PROGRAM Update Presentation for BWROG/NRC Management Meeting August 5,1998 NRC White Flint Offices Mark Coleman Public Service Gas & Electric Company BWROG AOV Committee Chairman

e Joint Ownsrs' Group Air-Operated Valve Program Committee Objectives:

. Support Joint Owners Group (JOG) program to proactively address AOVs.

Presentation Objective:

. BWROG/ JOG AOV activities update l

l i

l SVIOVWRC0898. doc 2 08/04/98 l

l l

l

1

' l 1

!. Joint Owners' Group Air-Operated Valve Program 4

JOG-AOV VISION I

I l Develop a common and cost effective US nuclear l

utility Air-Operated Valve (AOV) program to enhance I

! safe and reliable AOV performance and allow timely

address ofindustry and regulatory AOV issues.

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S\AOV\NRC0898. doc 3 08/04/98 I

Y

Joint Owners' Group Air-Operated Valve Program .-

JOG AOV PROGRAM i

. JOG is made up of utilities in B&WOG, BWROG, WOG, and CEOG l

- 42 utilities

- 69 plants j

- 104 reactor units l

. Duke Engineering & Services is the primary subcontractor for JOG technical support.  ;

. JOG has been interfacing with NRC, EPRI, NEl,

!NPO, AOV Users' Group (AUG), USA & ASME ,

. JOG /DE&S have met with valve vendors to discuss JOG effort, AOV issues and vendor role in JOG assistance i

. JOG AOV program intended to be compatible with )

EPRI products and ASME position on testing l SL40V\NRC0898. doc 4 08/04/98 i

Joint Owners' Group Air-Operated Valve Program JOG AOV PROGRAM ELEMENTS Relevant ASME Cases (OM-3 and OM-19) and 4

Maintenance Rule aspects are being considered

. Risk-informed methodology to be used for determining level of AOV attention

. Existing valid bases to be used to justify current AOV design basis assumptions & performance; testing to validate where lack of confidence exists

• GL 89-10 (MOV) lessons learned to be applied 1

. The key element of this program is NRC/ JOG agreement of the issues 1

S\AOV\NRC0898. doc 5 08/04/98 i

l

4 4

> Joint Owners' Group Air-Opsrated Valve Program e i BU-1 Program Considerations

]

SCOPE All AOVs are being

! considered.

! CATEGORIZATION Categories based on safety significance and valve f

function

DESIGN BASIS To validate AOV function and i REVIEWS capability; extent and degree i based on category

.e BASELINE TESTING To verify DBRs where insufficient confidence exists in parameters &

assumptions.

PERIODIC TESTING To validate long-term AOV capability; frequency utility-dependent based on available margin and capability to perform through next scheduled test i

S\AOVWRC0898. doc 6 08/94/98

1. 1 1 1 i

i 4

i STATUS ITEMS i

Presentation for BWR Owners' Group /NRC j Management Meeting i

August 5,1998 Rockville, MD.

Glenn Warren SNC

t Intermediate Voltage Breaker Maintenance l

I l

, PSA Certification status:

. BWROG developed PSA Certification Methodology in July 1996 1

. Methodology revised in January 1998 e 17 BWRs reviewed to date with 6 more plants to review (including re-review of the three pilots)

. NEl PSA Certification industry Workshop held on April 7-8,1998 Industry recognizes value of a single approach

. WOG completed their first pilot in July 1998 while B&W and CEOG are planning pilot plant reviews in late 1998 or early 1999

. At the NRC Risk Informed workshop in July 1998 industry indicated a desire to support discussions with the NRC staff on PSA methodology Action:

. NRC and industry need to initiate dialogue for use of PSA Certification

Response Time Testing .

Objective:

j . Eliminate Response Time Testing (RTT) of intermediate response time loops (RPS and IAS l

with 300 ms to 1050 ms response requirements) l by demonstrating that changes in response times l

beyond acceptable limits are detectable during

! other routine periodic testing Status:

l . December 12,1997 - Supplement to NRC l

! Approved LTR NEDO-32291-A (" System l l Requirements for the Elimination of Selected l

Response Time Testing Requirements", October i

1995) transmitted to NRC e May 21,1998 - NRC issued RAI Actions:

. BWROG working with NRC (Jerry Wermiel) to resolve discrepancies between RAi and LTR Difficult for NRC to verify accuracy of loop component failure modes and effect analyses (FMEAs) and bounding response time calculations BWROG evaluating need for LTR supplement to strengthen " defense in depth" position BWROG targeting end of October for supplemental submittal to NRC TAG 98-14 revision 1

), MSIV Leakage i

1 Objective:

l . Obtain technical specification change to eliminate j requirements for MSlV Leakage Control Systems l and to increase allowable MSIV leakage rates i Status:

I . Lead BWROG License Change Requests have l been approved for 8 BWRs

) . Three (3) additional BWRs actively pursuing Tech i Spec changes i

j . September 1993 - BWROG Submitted i

NEDC-31858P Revision 2 to the NRC l l j . March 1995 - NRC issued RAI to BWROG l

Several questions involved seismic database j i . February 1996 - BWROG responded to RAI l l

. January 1997 - BWROG revised RAI response i

! . September 1997 - BWROG provided supplemental l information on referenced seismic events and l eliminated events where distance from site to l seismic instrumentation is too large i

I 1 TAG 98-13 revision 1 i

MSIV Leakage ,.

Status:(Continued)

. January 1998 - NRC issued letter asking BWROG to evaluate impact of revised number of database sites on seismic experience database May 1998 - BWROG responded to January 1998 letter Actions:

. NRC issuance of generic SER on NEDC-31858P Revision 2 (Schedule ?)

TAG 98-13 revision i

improved Water Chemistry l.

i Committee Objectives:

! I l . Seek clarification / relief from the NRC on 3 SER l

! positions to allow utilities to achieve HWC l implementation credit in seeking Recirc Piping

inspection relief.

i 1 1 1 l Status:

l i l

e April 1991- Original BWROG Topical (GE l NEDO) submitted l . January 1995 - NRC SER issued

. April 1998 - BWROG Supplement to Topical

{ submitted l . May 1998 - NRC (R. Hermann) recommended l

" lead plant" be identified; BECO (Pilgrim) l identified by BWROG

. BWROG/NRC dialog has been excellent Actions:

. August 1998 - BECO " lead plant" submittal to NRC

. BWROG seeking NRC review (SER) of Pilgrim

. submittal by fall '98 due to spring '99 Pilgrim outage S\1WCWRC10898. doc 08/0H98

g i

L Excess Flow Check Valve Committee L

Committee Objective:

)

i e To reduce or eliminate Excess Flow Check Valve l

(EFCV) testing requirements l

\ Backaround: \

L

= Most plants have ~90-100 EFCVs in instrument I

lines l

! . Two types of valve designs are used by vendors 1

• Plantimpact of testmg l l

70-350 man-hours

- Added radiation Exposure

- Often a Critical Path activity l Actions:

i

. BWROG requesting removal of testing from technical specifications

. Details will be discussed in the meeting on August 6,1998  !

Offsite Consequence l Reliability and Risk '

Operational Impact Technical Specification basis ,

. Obtain NRC managementfeedback

n '

A' Project No. 691

• Boiling Witir Ructor Owners Group cc: Thomas J. Rausch, Chairman W. Glenn Warrer.

Boiling Water Reactor Owners' Group Southern Nuclear / Georgia Power 1 Commonwealth Edison Company E.I. Hatch Nuclear Plant Nuclear Fuel Services PO Box 1295 M/C B052 1400 Opus Place,4th Floor ETWill Birmingham, AL 35201 Downers Grove, IL 60515 Carl D. Terry Dennis B. Townsend Vice President, Nuclear Engineering GE Nuclear Energy

- Niagara Mohawk Power Corporation M/C 182 Nine Mile Point-2 175 Curtner Avenue PO Box 63 San Jose, CA 95125 Lycoming, NY 13093 Drew B. Fetters Thomas A. Green PECO Energy GE Nuclear Energy Nuclear Group Headquarters Mail Code 182 '

MC 62C-3 175 Curtner Avenue 965 Chesterbrook Blvd. San Jose, CA 95125 Wayne, PA 19087 John Hosmer Commonwealth Edison Executive Towers,4th Floor 1400 Opus Place Downers Grove, IL' 60515 George T. Jones Pennsylvania Power & Light

. MC A6-1 Two North Ninth Street-Allentown,' PA 18101 Lewis H.' Sumner Southern Nuclear / Georgia Power E. l. Hatch Nuclear Power Plant -

40 inverness Parkway PO Box 1295 Birmingham, GA 35201 John Kelly New York Power Authority 14th Floor Mail Stop 14K Centroplex Building 123 Main Street White Plains, NY 10601 :

,