ML20203C917
| ML20203C917 | |
| Person / Time | |
|---|---|
| Issue date: | 02/18/1998 |
| From: | Joshua Wilson NRC (Affiliation Not Assigned) |
| To: | Essig T NRC (Affiliation Not Assigned) |
| References | |
| PROJECT-691 NUDOCS 9802250290 | |
| Download: ML20203C917 (76) | |
Text
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h UNITED STATES NUCLEAR REGULATORY COMMISSION i
e WASHiteSTON, D.C. Estet 4eM
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February 18. 1998 MEMORAN00M-TO:
Thomas H. Essig. Acting Chief-Generic Issyes and Environmental Projects Branch Division of Reactor Program Management. NRR l
i FROMf Janes H. Wilson Senior Project Manager Standardization Project Directorate l
Divisiots of Reactor Program Management isRR SUBJECTf
SUMMARY
OF MANAGEMENT MEETING HELD ON JANUARY 15. 1998 WITH THE BOILING WATER REACTOR OWNERS' GROUP 1
On January 15,1998, the staff held a public meeting at NRC headquarters in Rockville. Miryland with representatives of the Boi ing Water Reactor Deers'
-Group (BWR0h). The purpose of this meeting was to discuss the status of work
-in progrest and to discuss future activities. A list of attendees and their affilisi.ons is provided as Attachment 1.
i The agenda for this meeting is 1rovided as-Attachment 2.
The BWROG made a L
brief presentation on each of tw agenda items
- ussed it with the i
staff, as discussed below. The slides used by.
G in its presentations are provided as Attachment 3.
l ECCS Fuction Strainer Perfor,mgggg The staff and the BWROG discussed the status of issues related to Bulletin-96 03, which was issued on May 6, 1996.- The staff issued its draft SER on the i
BWROG's utility resolution guidance document on December 31. 1997, with a L-60 day comment period. The draft SER identified a number of-issues and the
' BWROG is. working to establish a prioritized list of impacts.
Individual L
utilities are reviewing the draft SER and the BWROG requested that the staff meet with the industry in early February to discuss this effort and proposes a March 2.- 1998. response date.- The BWROG wants the staff to address the issue of margin for each plant and expressed the concern that the staff's additive
),
l a>proach may be overly conservative. The staff has received submittals from tw Spring 1998 outage plants (Limerick Brunswick, and Duane Arnold) and J
these packages are now undergoing staff review.-
3
. Net Positive Suction Head (NPSH) *4 ggi Generic Letter 97-04 described the safety implications of the NPSH issue.
N' requesting that utilities respond within 90 days to der.cribe the impact on their facilities, but did not request t. final resolution. The BWROG is working to assist utilities to develop consistent r2sponses to the generic L
letter.
In a meeting with the NRC staff held on November 19, 1997.- the BWROG described its 90 day response template, which was issued to utilities on December 4.:1997. The B4ROG participated in the ACRS meeting in December that considered NPSH and containment overpressure issues. To date. the staff has
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2-received approximately 40 responses to the generic letter. The staff is reviewing the utility responses and will determine the next step after 1' has evaluated them.
Containment Coatinos
^
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The BWROG has been participating in EPRI's program to develop a containment coating utility resolution guidance (CCURG) document. The industry is conducting additional autoclave testing of coupons that are engineered to fail (because of i preparation. groper curin!) time. igroper thickness. improper substrateThis Sesting is designe etc.).
on the mechanism of failure of costings systems, which.-in turn, has an effect on transport and settling. The stait indicated that its generic letter on this issue will go to CRGR at the end of January and issuance is targeted for Spring 1998.
Annendix R Multiole Hot Shorts /Sourious Actuating As a result of an operational event at River Bend, a circuit analysis issue has arisen concerning the potential for multiple hot shorts. The staff is working on a generic letter to address interpretation of Appendix R requirements with a primary focus on circuit analyses. Because this issue involves the entire industry, the staff suggested that the BWROG's effort be expanded, perhaps under the imprimatur of NEl.
In response to a BWROG request to meet with the staff on this issue in January, the staff indicated it judged-
~that such a meeting was premature. A number of important interactions are scheduled to take place in the near future that may serve to focus efforts to resolve this issue. The staff plans to brief the NRR Executive Team near the end of January and a Comission meeting on this issue is scheduled for March.-
In addition. the staff indicated that its contractor. Sandia, was preparing a report on over 300 tests from around the world on cable, shorts, fires, etc.
Also, the BWROG stated that it was meeting with EPRI and SAIC in January-to discuss a vendor evaluation by product line. The staff stated that it might be better to wait until these activities had taken plbce before meeting with the industry to discuss this issue further.
Air Ooerated Velves (ADV) Joint Owners' Groun (J0G) Proaram Representatives from all four owners' groups are participating in the J0G program to address ADVs. A number of meetings are scheduled in early 1998 to discuss the issue and increased involvement !)etween the J0G and NEI is expected.- A number of industry interactions in late 1997 and early 1998 are expected to lead to the development of a comon and cost effective U.S.
nuclear-utility ADV program to enhance safe and reliable ADV performance and allow timely address of industry and r ulatory ADV issues. The staff
. indicated that the briefing presented b the BWROG on this issue was an effective approach to reso ution.
It i helpful to know what the industry is doing before the staff begins to formulate a plan of action.
3-Year 2000 1ssue The BWR03 sumarized its activities related to the Year 2000 issue. Owners are well aware of this issue, which affeets nuclear and other power plants, transmission and distribution systems, and computer systems and software.
NE!
Management Group. gh level prbgram through the Nuclear Utility Software has developed a hi EPRI has develo performing information collection, ped testing procedure guidance and is synthesis, and dissemination role for embedded systems. The issue is also being discussed in NEl/ Joint Owners' Groups meetings. The BWROG sumarized the challenge that resolving this issue involves: significant resources are required to address the issue: wide variation exists among installed potentially susceptible components / software at different plants; and the potential exists for substantial duplicative efforts. The initial BWROG meeting is scheduled in con quarterly workshop to determine a>propriate workscopes. junction with the EPRI The BWROG plans to continue close cooperation with E)RI and NEl. The staff cautioned the BWROG that if changes had to be made at a plant to address concerns associated with the Year 2000 issue, outage schedules should be carefully considered in order to eliminate unnecessary shutdowns.
Licensees should also identify what design changes can be made under 10 CFR 50.59 and those requiring license amen @ents should be submitted for staff review in a timely manner.
Emeroency Procedures In response to the staff's request for additional information, the BWROG has prepared Rev. I to its Emergency Procedure / Severe Accident Guideline and expects to transmit it to the staff before the end of February. This information is being submitted to the staff for information only. A BWR severe accident mitigation (SAM) demonstration at Duane Arnold is scheduled for February 1998 end is expected to provide increased understanding of the BWROG SAM product. All 21 utilities with BWRs are participating in this program.
Resoonse Time Testino On December 12,1997, the BWROG submitted the Supplement I to NED0-32291 A to the NRC. This supplement includes an appendix covering incremental similarity work completed following SER issuance and corrects minor errors in the original document. The supplement states that undetected response time degradation can be bounded and surveillance other than response time testing can detect increase in response times. The staff will develop a review schedule for NEDO 32291 A. Supplement 1.
Inteorated Risk-Based Reoulation The BWROG sumarized the activities of its Probabilistic Safety Assessment Certification Comittee, which is intended to provide peer certification of internal events PSAs to support use for specific applications.
In 1998, the committee intends to re review three pilot plants to benchmark the adequacy of the process. Six additional plants are also scheduled to be reviewed in 1998.
The committee also intends to issue a final report to the industry on the certification process and to participate in an NEI workshop.
4 MSIV Leakaae The staff has identified some problems with the BWROG's response to the staff's request for additional information concerning NEDC 31858P.
In particular, the staff is concerned with the adequacy of the seismic experience data. The BWROG anticipates transmitting information to address the staff's concerns in February 1998. After receipt of this information, the staff will develop a schedule for issuance of its SER.
JDtermediate Voltaae Breaker Maintenance The BWROG has implemented a program to evaluate lubricants in breakers and to develop maintenance guidelines for them. The BWROG plans to use information developed in NUPlc audits, to pool industry expertise capability, and to work closely with EPRI/NMAC in developing maintenance guidelines. The final product will result in GE recomendations relative to maintenance, testing, and overhaul frequencies. The BWR0G will then consider how to address other vendor breakers.
IErq3t Rock Safety Relief Valves (SRVs)
The Br;ROG described the status of its activities aimed at resolving Target Rock two6tage SRV setpoint drift issues. The owners' group is pursuing both advanced materials (ion beam implanted platinum alloy disc for a catalyst /
recombiner) and engineered (pressure switch) approaches to resolution. The owner's group will first meet to discuss this issue in April /May 1998, following the CP&L Spring outage and intends to share the results with the staff in May/ June.
[WNorrieinsoettion The BWROG stated that it is in the process of finalizing its response to the staff's RAI and expects to submit it to the staff by the end of January 1998.
The staff and the BWROG representatives agreed that meetings such as this one are a valuable means of comunication, providing an opportunity for feedback between the industry and the staff, and that another management meeting should be held in ipring 1998.
Project No. UJ s
Attachments: As stated cc w/ atts: See next page
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MSIV Leakaoe The staff has identified some problems with the BWROG's response to the staff's request for additional information concerning NEDC-31858P.
In particular, the staff is nerned with the adequacy of the seismic experience data.
The BWROG antici u transmitting information to address the staff's concerns in February 19.
After receipt of this informat on, the staff will develop a schedule for is, ince of its SER.
Jntermediate Voltaae Breaker Maintenance The BWROG has implemented a program to evaluate lubricants in breakers and to develop maintenance guidelines for them.
The BWROG plans to use information g
developed in NUPlc audits, to pool industry expertise capability. and to work closely with EPRl/NMAC in developing maintenance guidelines.
The final product will result in GE recommendations relative to maintenance, testing, and overhaul frequencies.
The BWROG will then consider how to address other vendor breakers.
Tarcet Rock Safety Relief Valves (SRV)s The BWROG described the status of its activities aimed at resolving Target Rock two-stage SRV setpoint drift issues. The owners' group is pursuing both advanced materials (ion-beam implanted platinum alloy disc for a catalyst /recombiner) and engineered (pressure switch) approaches to resolution. The owner's group will first meet to discuss inis issue in April /May 1990, following the CP&L Spring outaae and intends to share the results with the staff in May/ June.
FW Nozzle Inspection The BWROG stated that it is in the process of finalizing its response to the staff's RAI and expects to submit it to the staff by the end of January 1998.
The staff and the BWROG representatives agreed thtt meetings such as this one are a valuable means of communication, providing an opportunity for feedback between the industry and the staff, and that another management meeting should be held in Spring 1998.
Project No. 691 Attachments: As stated cc w/atts:
See next page DISTRIBUTION w/oattachments:
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4 PROPOSER '0EliDA Public Meeting B'.ers'en JRC Staff twe and BWR Ow,
'roup Janua'ry 15. 1998 9:30 a.m.
12:30 p.m.
Room 10 B 11 OWFN 9:30 Introduction TOPICS FOR DISCUSSION e
.ECCS Suction Straine-Performance e
NPSH Issues e
Containment Coatings Appendix R - Multiple Hot Shorts / Spurious Actuations e
i e
A0V Joint Deiers' Group Program STATUS ITEMS e
Emergency Procedures e
Response Time Testing e
Integrated Risk Based Regulation o
MSIV Leakage e
Intermediate Voltage Breaker Maintenance e
Target Rock SRVs OPEN DISCUSSION 12:30 Adjourn l
L.
i l
l
I t
LIST OF ATTENDEES AT MANAGEMENT HEETING WITH THE BWROG HELD IN ROCKVILLE MARYLAND ON SEPTEMBER 30. 1997 lieg
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AFFILIATION B. Sheron NRC S. Newberry NRC G. Lainas NRC R. Wessman NRC L. Marsh NRC D. Terao NRC J. Kudrick NRC R. Caruso NRC A. El Bassioni NRC K. Kavanagh NRC R. Elliott NRC R. Palla NRC S. West NRC G. Hamer NRC S. West NRC P. Gill NRC A. Pal NRC J. H. Wilson NRC M. Marshall NRC T. Rausch Comed /BWROG C. Terry NMPC/BWROG R. Sgarro PP&L/BWROG H. Williams TVA/BWROG G. Warren SNC/BWROG W. Russell Entergy/BWROG J. Cuirk GE D. Townsend GE D. Robare GE P. Naigus GE
NRC/BWR OWNERS' GROUP MAN AGEMENT *AEETING - J ANU ARY i S,1998 AGENDA 1
DISCUSSION ITEMS PRESENTER ECCS Suction Strainer Performance R. Sgarro, PP&L NPSH lasues H. L.. Williams, TVA Containment Coatings H. L. Williams, TVA Appendix R Multiple Hot Shorts / Spurious Actuations D. Robare, GE AOV Joint Owner's Group Program G. Warren, SNC STATUSIINFORMATION ITEMS Year 2000 Activities T. Rausch, Comed Emergency Procedures W. Russell, Entergy Response Time Testing T. Rausch, Comed PSA Certification D. Townsend, GE MSIV Leakage T. Rausch, Comed Intermediate Voltage Breaker Maintenance D. Townsend, GE Target Rock SRVs G. Warren, SNC Feedwater Nozzle inspection T. Rausch, Comed
ECCS SUCTION STRAINER COMMITTEE Presentation for NRC/BWROG Management Meeting January 15,1998 Washington, DC R. Sgarro Pennsylvania Power & Light TAG 97104 s.
ECCS SUCTION STRAINER Committee Oblective:
Resolve the ECCS Suction Strainer issue for BWRs Ensure interim safe operation Ensure final resolution meets regulatory requirements Assist utilities in resolving Generic Licensing issues e
Assist in resolution of related containment coating issue Presentation Objective:
Dit. cuss program status and schedule for NRC issuance of final SER f
i 1AGt7108
ECCS SUCTION STRAINER Reaulatorv Status (Continued):
NRC review of B ROG Utility Resolution Guidance BWROG formally answered initial NRC questions on January 30,1997 BWROG completed survey for NRC in January '97 which showed how URG is being conservatively applied One (1) additional NRC comment regarding combined RMI plus fibrous debris head loss received on August 19,1997
+
BWROG provided formal response on September 19,1997 that justifies URG methodology
'I NRC issued draft SER on URG for comment on December 31,1997
+
60 day comment period 4
TAGtM04
r ECCS SUCTION STRAINER Reaulatorv Status:
Bulletin 96-03 published on May 6,1996
~
Proposed resolution options acknowledged BWROG work Associated Regulatory Guide 1.82 Revision 2 issued May 10,1996
+
Provides limited NRC position on acceptable resolution methodology
(
a TAG 97108
ECCS SUCTION STRAINER Bulletin 96-03 Imolementation:
t Alternate passive strainers is preferred resolution option for all U.S. BWRs 12 US BWRs installed new strainers in 1997:
Quad Cities 2 Dresden 3 Pilgrim Cooper Monticello Hope Creek (partial installation)
River Bend Hatch 1 Browns Ferry 2 Brunswick 2 Peach Bottom 3
)
Perry TAG 97106
ECCS SUCTlON STRAINER Current Issues / Actions:
BWROG review and response to draft SER on URG Key SER issues identified:
Transport percentage for large debris below the lowest grating Transport factors for Mark ll containments Non-qualified coatings MEB 3-1 unacceptable for selecting pipe break location (may not maximize debris generation)
Demonctration that~ thin bed effects do not exist for new ECCS strainers Use of jet centerline pressure versus area averaged pressure to evaluate insulation destruction Combined fibrous plus RMI debris head loss Credit for containment overpressure in NPSH calculations Revised hydrodynamic load calculations /need for testing Establie prioritized list of plant impacts Early F coruary meeting with NRC March 2,1998 submittal target TAG 97100
ECCS SUCTION STRAINER Current issues / Actions. (continuedh T
NRC issuance of generic SER a
TAG 97.\\06
NET POSITIVE SUCTION HEAD (iGL 97-04)
Update Presentation for NRC/BWROG Management Meeting January 15,1998 Rockville, MD Lee Williams TVA
l Net Positive Suction Head Committee Objectives:
Develop BWROG template for utility GL 97-04 90-day response Support NRC in addressing ACRS overpressure issues Share costs in responding to industry NPSH issues Presentation Objective:
Update NRC on recent NPSH Committee activities Membershin:
Generic
~ ~
Net Positive Suction Head RecentActivities:
Developed drafd 90-day response template Met with NRC Nov 19 to establish dialog and e
discuss BWROG NPSHICOP issues Reviewed draft 90-day response template Staff provided favorable feedback (11/20 meeting minutes) issued BWROG 90-day response template to e
utilities on Dec 4 Participated in NEl GL 97-04 Workshop on Dec 2 Supported NRC Staff at Dec 2 3 ACRS meeting regarding NPSH and containment overpressure issues.
Net Positive Suction Head Follow-vo:
BWROG will continue dialog with NRC to address any issues resulting from Staff review of utility 90-day responses Summary:
Use of BWROG key in developing consistent e
utility response to GL 97-04 Close dialog between BWROG & NRC key to developing utility response model acceptable to NRC
i CONTAINMENT COATINGS COMMITTEE Presentation for NRC/BWROG Management Meeting January 15,1998 Washington, DC Lee Williams TVA TAG 97107
CONTAINMENT COATINGS Committee Obiective:
Lead the US nublear industry in resolution of the containment coating issue Impacts ECCS pump suction strainer performance and final resolution of the suction strainer plugging issue Presentation Obiective:
Update NRC Management Backaround:
NRC has expressed concern regarding performance of non-qualified and indeterminate containment coatings with respect to ECCS suction strainer plugging Draft Generic Letter (TAC No. M97146) issued on May 13,1997 6
TAG 97107
~
CONTAINMENT COATIN'GS Backaround (Continued)
BWROG authorized Containment Coating Committee in October 1997:
Ensure consistent industry response to Generic Letter Integrate BWRIPWRIEPRI efforts into unified approach under SWROG leadership Evaluate effect of containment coating debris on ECCS suction strainers TAG 97107
CONTAINMENT COATIN'GS hisue Resolution Strateav:
Review available test data to develop defendable containment coating source terms Supplement with autoclave testing Use tr nsport, set *Iing, and strainer head loss methooology deve.oped by ECCS Suction Strainer Committee Supplement test data where required Determine timing for coating debris release from substrate Delayed release facilitates increased settling in suppression pool Develop Containment Coating Utility Resolution e
Guidance (CCURG) similar to what was developed by ECCS Suction Strainer Committee (URG)
TAG 97107
CONTAINMENT COATINGS Work Scope:
\\
Program Overview e
Interim safety assessment (if required)
Interim guidance Information meetings with NRC Industry /EPRIIPWR interface Response shell for GL Data compilation Source Term andDebris Characterization e
Data acquisition and analysis (particle size at failure, timing of release from substrate, quantity released)
Autoclave testing of coupons engineered to fall under LOCA conditions Key inputfor other committee tasks Transport Guideline Review, modify, validate transport sett!ing methodology for Mark I,11, til (DBA, IBA)
Particle characteristics sensitivity Timing sensitivity HeadLoss Guidelines e
Function of paint, fiber and sludge characteristics and quantities Effect of temperature TAGt7107 l
l
CONTAINMENT COATINGS 1
Recent/ Current Acti'ons:
Decemb7r 2,1997 committee /NRC meeting Positive feedback on BWROG programs Containment Coating survey completed e
Working Group developed plan for autoclave tests in support of source term and debris characterization Incorporates survey informeCen 6 coatings systems engineered to fall Issued purchase order to Carboline for test coupon preparation and autoclave testing; and to University of Massachusetts for radiation aging of test coupons Initial autoclave test data to be available in March e
1998 issuance of NRC Generic Letter e
TAG 97107
APPENDIX R (FIRE PROTECTION)
Presentation for NRC/BWROG Management Meeting January 15,1998 Rockville, MD Dave Robare GE/BWROG APPRNRC
Appendix R (Fire Protection)
Presentation Obigctiv_gs
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Summarize the planned BWROG efforts to address' Appendix R issues Backaround:
BWROG committeeformed e
Workplan underway to address interpretation of Appendix R requirements, with a primary focus on circuit analysis issues; Standardization of definitions Regulatory requirements assessment Applicable industry research BWROG Positions PSAISafety significance, e.g.
Multiple hot shorts Multiple spuricus actuations APPRNRC
Appendix R (Fire Protection)
BWROG is working with NEl and supports their efforts and positions to c.larify these requirements BWROG is willing to work with NRC on draft GL and rulemaking activities issues:
Consistent, appropriate interpretation of Appendix R requirements NRC plan for rulemaking and potential impact on industry Actibns:
BWROGINRC (Fire Protection Branch) meeting tentatively planned for last week in January BWROG to monitor ACRd Sub-Committee
=
(Late January) and Commissioners meeting (February) on Fire Protection issues APPRNRC
JOINT OWNERS' GROUP AIR-OPERATED VALVE PROGRAM
' update s
Presentation for NRC/BWROG Management Meeting January 15,1998 Rockvill, MD Glenn Warren Southern Company v
Joint Owners' Group Air-Operated Valve Program 1
R Committee Objecti es:
Joint Owners Group (JOG) program to I
e E
address AOVs.
Presentation Objective:
O BWROG/ JOG AOV activities update Membership:
Generic P
.ii,-
Joint Owners' Group Air-Operated Valve Program Recent BWROG/ JOG AOVActMtles BWROG approved participation in JOG-AOV effort First JOG-AOV meeting (Ad Hoc) held Nov 5-6 to investigate JOG interest 19 attendees (17 utilities)
{ attendance limited to "AOV Core Groups"from each OG")
All 4 OGs represented C
All 4 OGs agreed to recommend participation in a JOG AOV effort to their respective OGs J
6
Joint Owners' Group Air-Operated Valve Program Recent BWROG/JbG AOVActMiles (Continued)
All 4 OGs making final decisions on JOG-AOV participation / funding during Jan-Feb 98 OG General Meetings Industry announced plans to pursue JOG-AOV effort at Joint MUGIAUG December meeting in Clearwater High utility interest NRC (Scarbrough) offered encouragement to pursue Second JOG Core Group meeting being held this week (Jan 13-16) in Monroeville Interviewing potential contractors Discussing scopelschedule for JOG effort Reviewing on-going industry AOV efforts
e Joint Owners' Group Air Operated Valve F rogram 3
JOG-AOV VISION Develop a common and cost effective US nuclear utility Air-Operated Valve (AOV) program to enhance safe and reliable AOV performance and allow timely address of industry and regulatory AOV issues.
Expect high utility participation JOG-MOV can be model for JOG-AOV SINGLE program description document Utility /NRC communication via JOGlNRC interface Increased involvemant between JOG and NEl e
Frequent communication between JOG, NRC e
and AUG m
3 YEAR 2000 lSSUE Presentation for NRC/BWROG Management Meeting January 15,1998 Rockville, MD S
Tom Rausch Comed i
Year 2000 issue Presentation Oblective:
Summarize BWkOG Y2K activities Backaround Owners are well aware of issue; it affects:
Nuclear and other power plants Transmission and distribution systems Computer systems / software NEl has high level program through NUSMG (Nuclear Utility Software Management Group)
NEl/NUSMG 97-07 recently issued as
" program development resource" Y2K coordinator workshop held Nov.14 Facilitating information exchange / coordination Developing Internet newsgroup EPRI has developed testing procedure guidance and is performing information collection, synthesis, and dissemination role for embedded systems Covering entire electricalindustry Facilitate sharing details of reviews, results, solutions, etc.
y2kntc01. doc
Year 2000 issue Backaround. Continued Issue is being discussed in NEl/ Joint Owners' Group meetings Examples of BWR digital applications:
Instrumentation and recorders Integrated instrumentation (e.g. NUMAC)
GE FANUC, Bailey or other controllers DG, FW control, RW process control)
Programable Logic Controllers: e.g.
=>
Hydrogen addition control
=>
Circ water chemical blocide injection Typical Y2K owner actions:
Determine components potentially susceptible (does it have a microprocessor?)
Retrieve and review design documentation Develop test plans Perform bench and/or in-situ tests Document results If required: Develop fixes and documentation 32Lntc01. doc l
Year 2000 issue Backaround: Recent BWROG Actions issue discussed under BWROG Emerging issue e
Program and with Executive Oversight Committee Potential for substantial work sharing / cost reduction Can focus on implementation and cost sharing without overlapping EPRI or NEl activities Conference call held January 8,1998 to gauge
=
interest in a BWROG program Heavily attended call included EPRI and NEl Substantialinterest in addressing embedded systems Significant interest in core monitoring and other software systems issues Significant resources required to address e
issue Wide variation of installed potentially susceptible components / software among plants Potential for substantial duplicative efforts 32kntc01. doc
Year 2000 issue BWROGActions Initial BWROG nieeting scheduled January 28-e 29 In conjunction with EPRI quarterly workshop
. Objective: determine appropriate workscopes BWROG is well suited to coordinate a complex e
" cafeteria" program likely to arise Plan continued close cooperation with EPRI e
and NEl NRC Plans / Feedback Generic Letter BWROG plans e
32kntc01. doc
EMERGENCY PROCEDURES COMMITTEE Presentation for NRC/BWROG Management Meeting 4
January 15,1998 Rockville, MD Wayne Russell Entergy
Emergency Procedures Committee s
Committee Oblective:
To assist utilitie's as the'y implement their plant specific programs through information exchange To address and resolve EPG/ SAG implementation issues To support the NRC review of the EPG/ SAG, Rev. O Presentation Objective:
Discuss the status of BWROG response NRC RAI e
for EPGISAG, Rev. O Discuss SAM Demonstration at Duane Arnold e
Emergency Procedures Committee Backaround; i
BWROG provided NRC with accident e
management guideline implementation plan in 1994.
NRC responded to BWROG in 1995 with agreement on the plan; the guidelines would be reviewed, but not for approval BWROG issued EPG/ SAG, Rev. O to utilities and e
provided copy to NRC for review in 1996 NRC requested additional information needed to e
complete their review of EPGISAG, Rev. O in 1997 BWROG issued EPGISAG, Rev.1 to utilities in 1997 P
e 4
0
Emergency Procedures Committee issues and Actions.\\
BWROG Response to RAI on EPG/ SAG, Rev. 0 EPC has finished response and waiting for BWROG approval to submitto NRC Approval of transmittalis expected this month EPG/ SAG, Rev.1 to be included with response for information only as p eviously agreed BWROG is not anticipating further requests for information on the EPG/ SAG A BWR SAM demonstration at Duane Arnold is e
scheduled for February 1998 Demonstration is expected to provide increased understanding of the BWROG SAM product All21 utilitiesparticipating
RESPONSE TIME TESTING i
Presentation for NRC/BWROG Management Meeting 3
January 15,1998 Washington, DC Tom Rausch Commonwealth Edison
- m..
RESPONSE TIME TESTING Committeo Objective:
Simplify additiohal Res'ponse Time Testing (RTT) as defined in Tech Specs by demonstrating that changes in response times beyond acceptable limits are detectable during other routine periodic +.asting Presentation Objective:
Provide status Discuss NRC review schedule e
Backaround:
in December 1994, NRC approved Licensing e
Topical Report which;ustified eliminating selected RTT Supplemental program provides technical basis e
for simplification of selected RTTs not covered in NRC approved Licensing Topical Report 1AGt7100
RESPONSE TIME TEST;i4G Current Work Scope:
\\
includes intermediate response time loops e
RPS and IAS (MSIV) 330 ms to 1050 ms. esponse requirements Does not include fast response time loops e
(100 ms or less) e.g., APRM high, Turbine Stop Valve closure i
TAG 97100
RESPONSE TIME TESTING
)
Current Work Scope (Continued):
Component FMEA and experience review Establish " bounding response times" (BRT) e Sum BRT for loop (less sensor)
Add BRT for sensor Compare total to loop requirement Confirm " defense in depth" TAG 97100
l RESPONSE TIME TESTING Current Work Scope
Conclusions:
i Undetected response time degradation can be e
bounded Surveillance other than RTT can detect e
significant increase in response times Y
E
^'
TAGl?.100
e.
~
RESPONSE TIME TESTING Current issues:
BWROG completed supplement to NEDO-32291 A o
Includes appendix covering incremental similarity work completed following SER issuance, and also minor errors in original document Transmitted to NRC on December 12,1997 N
TAG 9M00
RESPONSE TIME TESTING Actions:
(
NRC review of NEDO-32291 A Supplement 1 TAGIM00
1 l
PSA CERTIFICATION COMMITTEE
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Presentation for l
l NRC/BWROG l
Management Meeting l
January 15,1998 Rockville, MD i
Dennis Townsend GENE
-,.-,-----,a
PSA CERTIFICATION COMMITTEE Committee Oblective:
PSA Certificatibn Committee Provide peer certification ofinternal events PSAs to support use for specific applications Presentation Objective:
Update the NRC
\\
l PSA Certification activities and schedule l
l 1
PSA CERTIFICATION COMMITTEE Backaround:
f PSA Certificatio'n
=
l Pilot plants completed in fall of 1996 l
f Report to industry issued in December 1996 11 plants reviewed in 1997 l
Review participants outside of the BWROG l
l included:
I INPO WOG B&WOG CEOG TVO NRC observed one review i
G
PSA CERTIFICATION COMMITTEE 5
Issues andActions:
PSA work scheduled for 1998 include:
Re-review of three pilot plants
=>
To benchmark adequacy of the process Review 6 plants Issue a final report to industry on the process Participate in a NEl Workshop on the process i
I
i MSIV LEAKAGE CLOSURE l
Presentation for NRC/BWROG Management Meeting l
r January 15,1998 Washington, DC J
Tom Rausch Commonwealth Edison i
uan.no
l '.'
MSIV LEAKAGE CLOSURE Committee Oblective:
Obtain technical specification relaxation to e
significantly increase allowable MSIV leakage rates and to eliminate requirements for MSIV Leakage control systems Support plant specific license change requests with e
respect to radiological dose calcylations Presentation Objective:
Provide status and discuss schedule TAQt?.110
MSIV LEAKAGE CLOSURs
~
Backaround:
Altemate treatmept equipment (main steam piping 3
and condenser) for MSIV leakage demonstrated to be highly reliable Lead BWROG License Change Requests have been approved Hatch 2 March '94 Limerick 1,2 February '95 Duane Amoid February '95 Susquehanna 1,2 August '95 LaSalle 1,2 April '96 Several plants have completed seismic verifications:
Hope Creek Perry Hatch 1 Nine Mile Point 2 Oyster Creek Peach Bottom 2,3 WNP-2 Brunswick 1 TAG 97110
MSIV LEAKAGE CLOSURE l
Backaround (Continued):
Generic approval of NEDC-31858P Revision 2 e
(submitted by BM(ROG in September 1993) pal issued March 29,1995 BWROG response transmitted February 19,1996 Conference call held on May 9,1996 to discuss l
BWROG response along with new NRC questions l
+
Reliability of the alternate pathway, include boundary valves in plant ISI program [new]
+
Seismic adequacy of condenser structural l
members in addition to anchorage [new)
+
For seismic database, clarify method used to estimate distance between the facility and the fault rupture (RAI #11)
BWROG revised RAI response to respond to remaining NRC questions on January 9,1997 l
i TAG 97110
1 i
MSIV LEAKAGE CLOSURE l
Background (Continued):
l
\\
NRC raised concerns regarding BWROG l
response to RAI #11
+
EQE International supplemented information l
on referenced seismic events Transmitted to the NRC on 9-24-97 Additional seismic spectrums where l
available Distances from seismic instrumentation and plant site to fault line (versus distance to epicenter) i Eliminate from data base where distance from site to seismic instrumentation is too large TAG 97110
MSIV LEAKAGE CLOSURE Issues / Actions:
i
's NRC has informally asked EQE Intemational to clarify e
l some of this information BWROG transmittal anticipated in early February l
NRC schedule for issuance of generic SER r
2
]
l 4
1 TAGl7110
BREAKER MAINTENANCE COMMITTEE s
Presentation for NRC/BWROG Management Meeting January 15,1998 Rockville, MD Dennis Townsend GE Nuclear Energy
Breaker Maintenance Committee Committee Oblective:
- Provide a basis fo\\r extending existing OEM requirements for inspections and overhauls by using Reliability centered maintenance techniques Supported by testing.
Presentation Oblective:
Discuss the issues motivating this project e
Explain the program technical content a
Present the committee schedule Obtain NRC feedback l
-r-.-
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e
.r m-e
Breaker Maintenance Committee 4
Backaround:
Problem techni al description Medium voltage (4kV to 16 kV) breakers play an important role in station electrical distribution systems Breakers have failed that could have been prevented by maintenance programs l
Maintenance Rule inspections are looking for l
comprehensive breaker maintenance plans I
- INPO SER 7-97 of 27 March 1997 states that all l
utilities to verify that their breaker maintenance programs and practices include appropriate guidance and activities to l
preclude identified problems
- Issues being considered by the committee are:
=>lnadequate maintenance may be creating l
failures
=>Are plants following inanufacturers' requirements
- oDo sealed breakers need maintenance /
lubrication v-._
--y
-. ~.
j i
l Breaker Maintenance Committee i
Backaround(Continuedh l
Committee resp'onse
- Initially it was believed that testing lubricant life was an adequate solution i
i
- The question of"what is the next component to fall" was raised
- A program of testfor lubricantlife and RCM i
analysis for all components was developed
- Phase 1 (develop the test plan and the RCM matrix) was funded and is now complete
- This program addresses breaker cycle and l
inspection frequencies as well as inspection content
- The product will provide ability to place breakers on a full or partial condition l
monitoring basir i
- The product will be for GE breakers only 4
6 i
Breaker Maintenance Committee Issues:
Need to define a program to address other vendor's breakers following Phase 11
Breaker Maintenance Committee Act!Pm:
A 1.
Committee will work closely with EPRl/NMAC which is developing maintenance guides.
2.
The final product will be resultin GE recommendations relative to maintenance, testing and overhaul frequencies.
3.
The committee will consider how to address other vendor breakers by the end of Phase ll.
Contact has already been made with ABB.
Participants:
l l
Comed, DECO, GPU-N, NMPC, NPPD, NSP, PECO Energy, Supply System I
+
e
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er
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SRV SETPOINT DRIFT FIX DEVELOPMENT COMMITTEE 1
l i
Presentation for NRC/BWROG Management Meeting I
l l
l January 15,1998 Rockville, MD.
l l
l Glenn Warren Southern Company B
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SRV Setpoint Drift Fix Development 1
Committee Oblectives:
Resolve Targqt Rock Two-Stage SRV Setpoint Drift ssues Pursue both advanced materials and a
engineered approach to resolution.
Presentation Oblectives:
. Program status e
SRV Setpoint Drift Fix Development Status:
Previous plati$um-alloy material solution deemed not to be a permanentfix.
BWROG is providing industry with real time datalresults as they become available
.i
SRV Setpoint Drift Fix Development Status!Continuedh Continuing to knonitor platinum ion beam bombarded (implanted) disc perform %
Committee plans to meet in May to e
discuss continued courses of action Plan to communicate with !%C e,
(teleconference) after May meeting to relay Committee recommendations i
b h
A
SRV Setpoint Drift Fix Development Particloatina Utilities:
(7)
DECO, NYPA, NUSCc, PECO, PSE&G, SC, TVA
- l FEEDWATER NOZZLE INSPECTION i
.\\
(
Presentation for NRC/BWROG Management Meeting January 15,1998 Washington, DC Tom Rausch Comed
^
Feedwater Nozzle Inspection Committee Oblective:
Obtain NRC approval of BWROG recommendations for feedwater nozzle inspections intended as an alternative to NUREG-0619 Presentation Objective:
Provide status of BWROG response to NRC RAls M
e h
Feedwater Nozzle inspection 3$
Backarouad;
\\
NUREG-0619 issued in 1980 as a result of feedwater nozzle cracking Due to lack of confidence in UT at the time, periodic liquid ps. strant testing and frequent UT exams required s
Improvements in UT and installation of new e
nozzle designs allow changes to inspection type and frequency 9
4 4 Feedwater Nozzle inspection Backaround:
s Generic BWROG Report (alternative inspection requirements) submittod for NRC review October 1995 Would eliminate PT exams and increase period between UT exams NRC issued letter (5/28/98): review of BWROG e
submittal will be complete before Fall 1996 outages In the interim, NRC approved deferral of PT exam for one operating cycle on a plant-specific basis NRC issued a RAI in December 1996 Meeting to discuss RAls (NRC, BWROG, EPRI) was held 4/22/97 The presentations and demonstration provided a general understanding of the issues in the staff's 12/96 RAI
.Feedwater Nozzle Inspection j
Actions:
BWROG responses to NRC RAls are in final draft e
for m and will be formally submitted in the near future Participatiaa Utilities:
SNC DECO NYPA PP&L CP&L Entergy NMPC PSE&G Centerior GPUN Supply System TVA Comed IES Utilities PECO Energy NSP 4
Project No. 691 Boiling Water Reactor Owners Group cc: Thomas J. Rausch, Chairman Warr:n W. Glenn Boiling Water Reactor Owners' Group Southern Nuclear / Georgia Power Comonwealth Edison Company E.I. H6tch Nuclear Plant Nuclear Fuel Services PO Box 1295 M/C B052 s
1400 Opus Place 4th FlooY ETWIII Birmingham, AL 35201 Downers Grove IL 60515 Carl D. Terry Dennis B. T u send 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 f
Nuclear Group Headquatters Mail Code 182 MC 62C-3 175 Curtner Avenue 965 Chesterbrook Blvd.
San Jcse. CA 95125 Wayne, PA 19087 John Hosner 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. I. Hatch Nuclear Power Plant U.S. Route 1 North Box 439 Baxley, GA 31513 L. A. En land Entergy erations Inc.
PO Box 3 95 Jackson, MS 39286 K. K. Sedney GE Nuclear Energy 175 Curtner Ave. M/C 182 S: ; Jose. CA 95125