ML003709602
| ML003709602 | |
| Person / Time | |
|---|---|
| Site: | Boiling Water Reactor Owners Group |
| Issue date: | 05/01/2000 |
| From: | Pulsifer R NRC/NRR/DLPM |
| To: | Richards S NRC/NRR/DLPM |
| Pulsifer R M,NRR/DLPM, 415-3016 | |
| References | |
| Download: ML003709602 (76) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 1, 2000 MEMORANDUM TO: Stuart A. Richards, Director Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM:
Robert M. Pulsifer, Project Manager, Section 2 Project Directorate 1 Division of Licensing Project Management Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF MANAGEMENT MEETING WITH THE BOILING WATER REACTOR OWNERS GROUP (BWROG) AND THE BOILING WATER REACTOR VESSEL AND INTERNALS PROGRAM (BWRVIP)
On March 16, 2000, the staff met with members of the Boiling Water Reactor Owners Group (BWROG) and the Boiling Water Reactor Vessel and Internals Project (BWRVIP) to discuss various activities of both the BWROG and the BWRVIP. A list of attendees of the March 16, 2000, meeting and their affiliations is provided as Attachment 1. The meeting started with the BWROG activities then proceeded to the BWRVIP activities. A copy of the handouts provided by the staff, BWROG, and BWRVIP for their presentations is provided as indicated.
Members of the staff and the BWROG continued the meeting as summarized below:
Opening Remarks/Introductions The meeting began with the review of the action items from the previous BWROG meeting of December 8, 1999. It was decided that the action items would be discussed when the subject was addressed according to the agenda (Attachment 2). The action item that involved the activities of the integrated risk informed regulation (IRIR) committee of the BWROG regarding A.4 of the maintenance rule will be discussed at a future meeting.
BWR Operating Experience (Attachment 3)
The BWROG led a discussion on how the BWROG keeps its members informed of recent happenings. The BWROG stated that sharing experience and information is handled through several means including: (1) discussions during their quarterly General Meeting of the BWROG, (2) during specific BWROG committee meetings, (3) via fax or e-mail, and (4) disposed through the Potential Issue Review Team (PIRT). The PIRT is a team of individuals from the BWROG, General Electric (GE), and outside contractors to screen and disposition issues raised to the PIRT. The BWROG stated that "Voluntary Initiatives" are processed through the PIRT and the staff indicated that guidelines on "Voluntary Initiatives" to the industry and public which will include a definition of "Voluntary Initiatives" are being developed and should be issued for public comment following Commission approval.
S. A. Richards PASS, H2, Loose Parts Monitoring (Attachment 4)
The BWROG said that the objective is to relax regulatory requirements of the post accident sampling system (PASS), H2/0 2 monitors, H2 recombiner, and loose parts monitoring system (LPM). The BWROG is monitoring similar staff work with the pressurized water reactor owners and will submit requests for PASS and LPM relaxations this year. The staff indicated that its review did not identify any specific requirements for the LPM, or a clean dependence on the LPM for closure of specific issues.
DC Motor Methodology (Attachment 5)
The BWROG provided a short update on their work concerning direct current motors on motor operated valves. They stated that the final draft of their report is scheduled to be issued this month to their members and that Limitorque has been requested to review/endorse the work.
The BWROG said that they anticipate a meeting with the staff in the Fall of 2000 after the review by Limitorque; however, the staff recommended that the BWROG not wait for the Limitorque review before scheduling another meeting with the staff. The staff said that this work by the BWROG has been a good effort and that-there has been good communications between the BWROG and the staff.
Update on Containment Coatings Issue The staff provided a brief discussion regarding the NRC research effort on the generic containment coatings issue. A public meeting is tentatively set for May 2000 to discuss this effort. There has been delays with the testing due to the unavailability of materials used in older plant containment coatings. Testing is scheduled to be completed by the end of this year.
Status of SLMCPR TSTF The staff stated that it had rejected the safety limit minimum critical power ratio (SLMCPR) technical specification task force (TSTF) issue. The decision of the staff will be issued in writing soon. The BWROG said that they are now looking at alternatives.
Appendix R Document Status (Attachment 6)
The staff provided a presentation on its efforts to review the SRV/LPS (safety relief valve/low pressure systems) topical report and the submittals from the BWROG and Nuclear Energy Institute on fire-induced circuit failure methodology. The staff indicated that there are technical as well as legal issues that need to be addressed and that a meeting is being arranged for April 25, 2000 to discuss these issues. The BWROG has requested that NRC management meet with the BWROG after the technical meeting to discuss the legal issues.
Feedwater Nozzle Inspection Safety Evaluation (SE)
The staff stated that the feedwater nozzle inspection SE for its review of Topical Report GENE-523-A71-0594, Revision 1, "Alternate BWR Feedwater Nozzle Inspection Requirements" was issued on March 10, 2000. The BWROG indicated that licensees would save about
$279,000 each time they need to do this inspection. M~y 1, 2000
S. A. Richards Excess Flow Check Valve SE The staff stated that the excess flow check valve SE for its review of Topical Report B21-00658-01, "Excess Flow Check Valve Testing Relaxation," dated November 1998 was issued on March 14, 2000.
Global Nuclear Fuel (Attachment 7)
Mr. Klapproth from GE provided a brief overview of their new joint venture in the nuclear fuel business consolidating fuel activities in Wilmington, NC, Japan, and Europe under an organization called Global Nuclear Fuel reporting to GE Nuclear Energy in San Jose, California.
Open Discussion During the open discussion, the staff briefed the BWROG on the closure of Generic Safety Issue (GSI) B-55 (Attachment 8) on improved reliability of target rock safety relief valves (SRV).
The staff had determined that if actions need to be taken to improve the performance of the SRVs in the future, the existing quality assurance, maintenance rule, and codes and standards regulations provide regulatory mechanics for pursing additional improvements on a plant specific basis. The staff plans to issue a Regulatory Issue Summary to inform the industry of the closure of GSI B-55.
The staff asked the BWROG to comment on their recent meeting on a potential concern regarding local suppression pool temperature limits and ECCS strainer steam ingestion. The BWROG stated that the PIRT has addressed this concern and that they will provide a report to the BWROG. The staff asked whether GE Service Information Letter (SIL) 615 was considered during the PIRT review. Immediately following the meeting the BWROG informed the staff that it did not consider SIL-615 during their review because it had been dispositioned earlier.
Mr. Klopproth from GE asked if the staff was shifting resources away from topical report reviews to licensing actions. The staff said that the present rate of expenditure of resources for topical report reviews would result in exceeding the budgeted resources for the year; therefore, resources are temporarily being diverted to the completion of licensing actions. The staff said that they will inform the BWROG if the review of a topical report is slipping because of budget concerns. Mr. Sheron did emphasize that it is important that licensees respond to the staff's request to identify potential licensing submittals that would need staff review so that proper resources can be budgeted.
Summary and Review Action Items (1)
The staff will set up the Appendix R (SRV/LPS) technical and management meetings.
This technical meeting has been set for April 25, 2000. The management meeting is still to be scheduled.
(2)
The BWROG will discuss at a future management meeting the activities of the IRIR committee regarding A.4 of the maintenance rule.
May I1, 2000 S. A. Richards (3)
The BWROG will inform the staff whether the PIRT considered SIL-615 in their recent ECCS suction strainer review. As stated above, the BWROG did inform the staff after the meeting.
Members of the staff and the BWRVIP continued the meeting as summarized below:
Opening Remarks/Introduction The staff met with the Executive Oversight Committee (EOC) of the BWR Vessel and Internals Project (BWRVIP) to discuss issues related to the status of technical reviews and future activities by the BWRVIP (Attachment 9).
Update of BWRVIP Key Accomplishments and Activities Mr. Terry, the Chairman of the BWRVIP EOC began the meeting with a brief update of the key accomplishments and activities of the BWRVIP since the last EOC meeting with senior NRR staff in March 1999. These activities include submittals for the Integrated Surveillance Program (ISP, BWRVIP-78), proposed revisions to NUREG-0313 inspection schedules (BWRVIP-75),
revisions to the vessel and core shroud inspection guidelines (BWRVIP-74 and -76, respectively), initiation of complementary research with the NRC's Office of Nuclear Regulatory Research on weldability of irradiated material, and vessel and internal inspection summaries for Fall 1998 outages. He then provided a short summary of key BWRVIP accomplishments since the March 1999 NRR/EOC meeting, and activities the BWRVIP will undertake in 2000.
Technical Committee Summaries The Technical Chairs for the Integration, Assessment, Inspection, Repair and Mitigation Committees then provided a synopsis of the key issues each committee is addressing in the coming year, and the proposed deliverables to the staff. These are summarized in the BWRVIP handout (Attachment 9).
Open Discussion In the open discussion portion of the meeting, the NRC Lead Project Manager (LPM) summarized the status of BWRVIP documents presently under review, including a proposed schedule for issuing SEs (Attachment 10). The review of the BWRVIP license renewal (LR) appendices was discussed, and the LPM stated that as of the present time, no obstacles are foreseen to prevent the LR SEs from being completed, or otherwise impacting the review of the Hatch Plant LR submittal. The BWRVIP has 12 Inspection and Flaw Evaluation (I&E)
Guidelines under staff review for the license renewal period, plus two additional reports that directly support LR. Of these, seven are complete or essentially complete (BWRVIP-18, -25,
-26,.-27, -47, -48, and -49), and five are expected to be completed in the next few months (BWRVIP-38, -41, -42, -75, and -76). The two remaining reports (BWRVIP-74 and -78) involve issues related to RPV shell welds, for which confirmatory research is underway, and the ISP.
The staff expects to complete the reviews of these two documents in early 2001, which will allow for completion of the Hatch Plant LR review on schedule. May 1I, 2000
S. A. Richards Also discussed was the staff's review of the BWRVIP's proposal for inspection relief based on hydrogen water chemistry (HWC). This proposal is under staff and contractor review. A draft technical evaluation report (TER) has been received from the contractor, and the staff is reviewing the draft TER.
Mr. Terry then discussed an approach the BWRVIP is evaluating for assessing how the member utilities are implementing BWRVIP products. The BWRVIP is considering having Institue of Nuclear Power Operation (INPO) involved in the pilot assessments of 2 to 3 utilities in 2000. This process will be evaluated and the future scope and schedule will be determined following the completion of the pilot assessments.
Finally, Mr. Terry discussed the closeout of the BWRVIP program and transitioning to a maintenance mode, which will continue interaction with the NRC, collecting and disseminating plant inspection data and experience, and responding to future issues in a timely and 15roactive way. Mr. Terry also re-stressed briefly license renewal issues, the ISP submittal, revised NUREG-0313 inspection schedules, and inspection relief for HWC.
Research Efforts Regarding Cascading Failures (Attachment 11)
Finally, a presentation was made by the staff on the results of NRC confirmatory research program performed by Idaho National Engineering and Enviromental Laboratory on "Risk Associated with IGSCC-Induced Failure of BWR Internals," which examined the potential risks associated with the synergistic failures of degraded BWR internals. It concluded that, with no inspection, monitoring or repair, degraded internal components could fail in either a common mode or in a cascading, synergistic manner, potentially leading to an inability to insert rods or cool the core in the event of a severe internal or external event. However, for licensees following the current BWRVIP program, as approved by the staff, there is a significant decrease (on the order of two-plus orders of magnitude) in core damage frequency (CDF) caused by failures of BWR internals, bringing the CDF to less than 5 x 106 events/yr.
The meeting ended with an agreement that future meetings with the BWRVIP will be arranged as needed and required.
Project No. 691 Attachments: 1. Attendance List
- 2. Draft Agenda
- 3. BWROG Operating Experience
- 4. Regulatory Relaxations
- 5. MOV/DC Motors
- 6. SRV/LPS Topical Report
- 7. Joint Venture Scope
- 8. Closeout of GSI B-55
- 9. BWRVIP Handout
- 10. Status of BWRVIP Submittals
- 11. Risk Associated with IGSCC-lnduced Failure of BWR Internals cc w/atts: See next page DISTRIBUTION: See attached list Accession No. ML0037
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DOCUMENT NAME: G:\\PDIV-2\\bwrog\\031600 Meeting Summary.wpd C.*
OFFICIAL RECORD COPY May 1, 2000
BWR Owners Group cc:
Mr. James M. Kenny BWR Owners' Group Vice Chairman PP&L, Inc.
Mail Code GENA6-1 Allentown, PA 18101-1179 Mr. Thomas J. Rausch RRG Chairman Commonwealth Edison Company Nuclear Fuel Services 1400 Opus Place, 4th Floor Downers Grove, IL 60515-5701 Mr. Drew B. Fetters PECO Energy Nuclear Group Headquarters MC 61A-3 965 Chesterbrook Blvd.
Wayne, PA 19087-5691 Mr. H. Lewis Sumner Southern Nuclear Company 40 Inverness Parkway PO Box 1295 Birmingham, GA 35201 Mr. Carl D. Terry Vice President, Nuclear Engineering Niagara Mohawk Power Corporation Nine Mile Point - Station OPS Bldg/2nd Floor PO Box 63 Lycoming, NY 13093 Mr. George T. Jones PP& L, Inc.
MC GENA6-1 Two North Ninth Street Allentown, PA 18101 Mr. John Kelly New York Power Authority 14th Floor Mail Stop 14K Centroplex Building 123 Main Street White Plains, NY 10601 Mr. Thomas G. Hurst GE Nuclear Energy M/C 182 175 Curtner Avenue San Jose, CA 95125 Mr. Thomas A. Green GE Nuclear Energy M/C 182 175 Curtner Avenue San Jose, CA 95125 Mr. W. Glenn Warren BWR Owners Group Chairman Southern Nuclear Company 42 Inverness Parkway P.O. Box 1295 Birmingham, AL 35201 Project No. 691
DISTRIBUTION FOR MARCH 16,2000, MEETING WITH THE BOILING WATER REACTOR OWNERS GROUP Dated:
May 1, p0nn PUBLIC PDIV-2 Reading File JZwolinski/SBlack (RidsNrrDIpm)
SRichards (RidsNrrDIpmLpdiv)
SDembek (RidsNrrDIpmLpdiv2)
EPeyton (RidsNrrLAEPeyton)
RPulsifer (RidsNrrPMRPulsifer)
BSheron (RidsNrrAdpt)
BBateman (RidsNrrPMBBateman)
EWeiss CECarpenter RAnand GHubbard WBeckner (RidsNrrDripRtsb)
TScarbrough RCaruso RHermann JStrosnider TCollins
Meetina With Boilina Water Owners GrouD Meeting Attendees To Discuss Reactor Vessel And Internal Program March 16, 2000 NAME Robert Pulsifer Stephen Dembek Bill Bateman Eric Weiss George Hubbard William Beckner Thomas Scarbrough Ralph Caruso C. E. Carpenter Robert Hermann Jack Strosnider Brian Sheron Tim Collins Raj Anand George Vandesheyden Richard E Ciemiewicz James W. Langenbach Bob Carter Tom Mulford Jack Dillich Raj Pathania Larry Steinert George Selby Christine Cave Nancy Chapman Carl Larsen Bruce McLeod Harry Salmon Vaughn Wagner John A. Wilson Paige Negres Jim Klapproth Tom Hurst Lewis Sumner Glen Warren Jim Kenny Carl Terry John Kelly Mike Neal AFFILIATION NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC NRC COMED/BWRVIP PECO Energy PECO Energy EPRI EPRI EPRI EPRI EPRI EPRI McGraw Hill SERCH/BECHTEL Vermont Yankee (BWRVIP)
SAIC/BWRVIP NYPA/BWRVIP/EOC CP&L/BWRVIP AmerGen/BWRVI P GE GE GE SNC SNC PPL Niagara Mohawk New York Power Authority NUSIS
NRC/BWRVIP/BWR OWNER'S GROUP MANAGEMENT MEETING March 16, 2000 - 9:00AM - 12:00PM Room T8A & F1 DRAFT AGENDA DISCUSSION TOPICS BWROG Agenda (9:00am) 10 min.
10 min.
10 min.
10 min.
5 min.
5 min.
5 min.
5 min.
5 min.
10 min.
10 min.
5 min.
Opening Remarksllntroductions BWROG BWROG is proactive in solving problems for the fleet, incorporating the efforts of our technical exchange committees. Opportunity to share efforts, schedules, and priorities with the staff members Update BWROG/NRC action items BWROG/NRC BWR Operating Experience BWROG Discuss BWROG methods to internally communicate Potential Issues that may affect owners.
PASS, H2, Loose Parts Monitor BWROG/NRC Following pressurized water reactor actions, the BWROG will discuss status of committee work and solicit NRC comments on these issues.
DC Motor Methodology The BWROG is developing a computer model to provide guidance for determining the performance of dc-powered motor-operated valves.
Status BWROG work in developing methodology.
Obtain NRC Feedback on potential Generic Communication in this area.
Update on Containment Coatings Issue NRC Latest results of NRC research on generic containment coatings concern.
Status of SLMCPR TSTF NRC Update on status of TSTF-357.
APPENDIX R document status NRC Follow-up of BWROG 11/15/99 submittal and discuss NRC direction and schedule.
Feedwater Nozzle Inspection SER NRC Status of topical report review "Alternate BWR Feedwater Nozzle Inspection Requirements" Excess Flow Check Valve SER NRC Status of topical report review "Excess Check Valve Testing Relaxation" Global Nuclear Fuel Jim Klapproth GE announces new fuel partners Open Discussion Summary and Review Action Items BWROG/NRC
BWRVIP Agenda (10:30am)
Opening Remarksllntroductions EOC/NRC A special industry review group, the Boiling Water Reactor Vessels and Internals Project (BWRVIP), was formed in 1994 by the member licensees of the BWROG to address issues related to reactor vessel, reactor coolant piping, and reactor internals degradation. The BWRVIP has been instrumental in developing and implementing proactive guidelines to address these issues.
Update of BWRVIP Key Accomplishments and Activities Technical Committee Summaries Integration Assessment Inspection Repair Mitigation Status of Key Technical Issues Integrated Surveillance Program License Renewal Appendices Revision to NUREG-0313 Open Discussion Status of NRC Review/Acceptance of BWRVIP Products Assessment of BWRVIP Implementation BWRVIP Direction in 2000 and Beyond Items from the Floor Research Efforts Regarding Cascading Failures NRC Present the results of RES Program on "Evaluation of Degradation of BWR Internals."
Summary and Review Action Items C. Terry H. Salmon G. Vanderheyden W. Eaton G. Jones L. Sumner C. Terry BWRVIP/NRC NRC C. Terry C. Terry BWRVIP/NRC 10 min.
45 min.
15 min.
15 min.
5 min.
BWROG Operating Experience Presentation for BWROG/NRC Management Meeting March 16, 2000 Washington, DC BWROG EOC Meeting March 16, 2000 I
Presentation Obj ective o Provide information on methods utilized by the BWROG to keep all members informed of recent happenings BWROG EOC Meeting 2
March 16, 2000
Sharing Experience and Information
- Potential Issue Review Team (PIRT)
- General Meeting Roundtable
- General Meeting Presentations
- Committee Presentations
Potential Issue Review Team
"* Established as part of BWROG Charter and Operating Priciples
"° Team makeup
- BWROG Chairman and Vice-Chairman
- RRG Chairman
- Advisory Committee (Prime Reps)
- Selected Committee Chairmen
-GE
- Outside Contractors March 16, 2000 BWROG EOC Meeting 4
Potential Issue Review Team
"* Dedicated staff member to manage
"* Data base maintained
- Issue Log
- Action Items
- Available on BWROG Web page
"* Anyone can submit issue for review
"* Determine if immediate need to address
- Chairman can authorize funds March 16,2000 BWROG EOC Meeting 5
Potential Issue Review Team
"* Scheduled discussion: every 6 - 8 weeks
- More often if needed
"* Screen issues for applicability to BWRs
- Determine appropriate disposition
- Assign to current committee
- Create new committee
- Authorize work to outside contractor
- Close without work BWROG EOC Meeting March 16, 2000 6
General Meeting Roundtable
- Quarterly with all utility Prime Reps
- Mostly Middle Management levels
- 2 day meeting
- 2 hrs dedicated to Operating Experience
- Each plant submits written and verbal
- Events, Experience, and lessons learned
- Operational and licensing BWROG EOC Meeting 7
March 16, 2000
General Meeting Presentations
"* Prime Reps can request agenda time
- Typical agenda slot for last minute addition
"* PIRT may ask for presentations
"* Any member of BWROG can request to present or have presentation made
"* NEI, EPRI, and INPO routinely present BWROG EOC Meeting March 16, 2000 8
Committee Presentations
"° Specific presentations are made at applicable committee meetings
"* Applicable committees present at General and Executive Meetings BWROG EOC Meeting March 16, 2000 9
Sprint Fax and E-mail
"* All committees are on Sprint Fax and E-mail distribution lists
"* Any member can share information with utility peers via Project Manager Distribution is then made to all applicable members BWROG EOC Meeting March 16, 2000 10
A'
'Itt C:4-3 XEE PASS, H2/0 2 Monitors, H2 Recombiner, 0
Loose Parts Monitoring System Regulatory Relaxations Presentation for NRC/BWROG Management Meeting March 16, 2000 Washington, DC PASS 3-16-00 1
PASS, H2/0 2 Monitors, H2 Recombiner, Loose Parts Monitoring System Regulatory Relaxations Committee Objective:
Eliminate unnecessary post-accident sampling and analysis requirements for BWRs
" Declassify H2/0 2 monitors to non-safety related
- Eliminate requirements for H2 recombiners and Containment Air Dilution (CAD) systems or relax to non-safety
- Justify elimination of Loose Parts Monitoring System Presentation Objective:
"* Update NRC Management Request NRC provide promised information regarding elimination of Loose Parts Monitor System PASS 3-16-00 2
PASS, H2/0 2 Monitors, H2 Recombiner, Loose Parts Monitoring System Regulatory Relaxations Current Status/Schedule:
- BWROG monitoring similar work performed by PWR Owners Awaiting issuance of Safety Evaluation Reports on PASS elimination
- Discussed issues with NRC Staff on October 7, 1999 NRC provided comments and suggestions regarding BWROG approach In December '99, NRC provided preliminary comments regarding elimination of Loose Parts Monitoring System and agreed to provide additional information later regarding their comments
- BWROG has been responsive to NRC requests which support risk informing 10CFR50.44 (combustible gas control)
Utility cost burden important PASS 3-16-00 3
PASS, H2/0 2 Monitors, H2 Recombiner, Loose Parts Monitoring System Regulatory Relaxations H2 Recombiner/CAD System Regulatory Relaxation Status:
Deterministic evaluation approach successful if core iodine release is small (a few % of core inventory)
Detonable gas mixture would not occur for design basis events
- Radiolytic decomposition of water increases significantly at higher iodine concentrations
- NUREG-1465 specifies gap and early release of 30% of core iodine inventory Increases radiolytic decomposition of water such that recombiners may be beneficial for design basis events PASS 3-16-00 4
PASS, H2/0 2 Monitors, H2 Recombiner, Loose Parts Monitoring System Regulatory Relaxations Loose Parts Monitor Elimination:
9 BWRs do not have requirements for this system
"* Currently collecting system operating experience from all other BWRs
"* Goal is show that the operating experience does not demonstrate that LPM Systems provide safeybenefits Compare RG1.1335'reuirements expectations to system operating history
" B WROG requests additional clarification from NRC regarding preliminary comments Use of LPM to resole VIP issues On-going ASME activities PASS 3-16-00 5
PASS, H2/0 2 Monitors, H2 Recombiner, Loose Parts Monitoring System Regulatory Relaxations Program Summary Subject PASS H2/02 Monitors H2 Recomb./CADs Loose Parts Monitor Approach Develop revised CDA prodedure Follow PWR successes Submittal to eliminate all requir.
Maintain parallel deterministic /
informed resolution options Schedule 2QOO 3QOO risked-T-Maintain parallel deterministic / risked informed resolution options Complete surveys and submit separate LTR
)
6 2QOO PASS 3-16-00 6
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BWROG-NRC Meeting 1
March 16,, 2000
BWROG MOV/DC MOTORS PURPOSE OF PRESENTATION zwProgram Update zSchedule Review BWROG-NRC Meeting 2
March 16) 2000
BWROG MOV/DC MOTORS PRIMER
Žlssue: Motor speed/output affected by stem load, supplied voltage and winding temperature.
zwPotential Impact:
"* Longer MOV stroke times
"* Lower motor output (torque), thus lower valve thrust BWROG-NRC Meeting 3
March 16,,2000
BWROG MOV/DC MOTORS NOTABLE EVENTS SINCE LAST BRIEF w Oct 99: Draft I of report issued to BWROG for initial review and comment. [Limitorque on distribution]
w Dec 99: VTRG Telecon with contractor (MPR Associates) to discuss utility comments; MPR addressed all utility comments.
w Feb 00: Draft 2 of report issued to BWROG for second review; additional comments addressed by VTRG and MPR. [Limitorque on distribution]
w Mar 00: Final BWROG issued to utilities; official Limitorque review/endorsement requested.
BWROG-NRC Meeting 4
March 16, 2000
BWROG MOV/DC MOTORS NRC INTERFACE w Have kept NRC briefed on program status:
- Apr 99 & Oct 99 JOG PV-NRC Status Meetings
- Aug 99 & Dec 99 EOC-NRC Management Meetings
- Planned Jul 00 NRC/ASME Pump & Valve Symposium w NRC has supported BWROG schedule & is interested in reviewing the final BWROG product.
BWROG-NRC Meeting 5
March 16, 2000
BWROG MOV/DC MOTORS SCHEDULE 2 Final BWROG Report issued: Week of March 6 w Anticipated Limitorque Review/Endorsement:
Summer 2000 w Anticipated NRC-BWROG meeting to discuss:
Fall 2000 BWROG-NRC Meeting 6
March 16,, 2000
SRV/LPS TOPICAL REPORT 0
September 1, 1999 BWROG submitted Topical Report "BWR Owner's Group Appendix R Fire Protection Committee Position on SRVs and Low Pressure Systems used as
'Redundant' Shutdown Systems Under Appendix R" 0
Enforcement in abeyance due to EGM (Systems selection is part of circuit analysis) 0 Staff is willing to accept proposals that reduce regulatory burden provided that they maintain safety (level of FP in existence) 0 Staff Review of Risk shows Removal of Fire Detection and Suppression Features associated with lll.G.3 could result in factor of 10 increase risk for some rooms at some plants (Plant Specific Analysis is Important) 0 March 1, 2000 call-BWROG position is that about 20 plants were licensed with SRV/LPS as a "Redundant" means (Two examples provided on March 2, 2000)
Evidence of "Redundant" means as a licensing basis not clear (Ill G.2 Redundant means was not required to be reviewed by the staff) 0 Staff acceptance of SRV/LPS as a "Redundant" would have legal and technical implications that are inter-related 0
More work needed to converge on an acceptable approach Candidate proposed resolution paths for accepting SRV/LPS o
Licensing Basis Documentation o
NFPA 805 analysis and rule change (March 2001 and March 2002) o Exemption Request o
License Condition o
Credit for Feedwater as redundant safe S/D 0
Schedule o
Technical meeting proposed for April o
May 2000 - RAI o
July 2000 - RAI response C-VAYFLES'W*Idilý~ [
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2000 M2000 (9
I
NEI RISK-INFORMED FIRE-INDUCED CIRCUIT FAILURE METHODOLOGY 0
On April 13, 2000 the staff will meet with NEI for a presentation of a partial, initial draft of the NEI risk-informed, fire-induced circuit failure methodology.
0 The staff will review the April 13, 2000 NEI document in parallel with ongoing NEI and EPRI confirmatory fire tests and pilot applications, and provide a draft RAI to NEI by May 15, 2000. The confirmatory fire test and pilot application schedules will be available by April 15, 2000.
The staff will meet with NEI and possibly EPRI during June, 2000 to revise the RAI based on NEI/EPRI clarifications. A final RAt will be issued shortly after this meeting.
It is planned that by August 15, 2000, NEI will respond to the final RAI, contingent upon completion of confirmatory fire testing. At that time SPLB, SPSB and EEIB, and possibly SNL, will conduct reviews of the RAI response from NEI.
0 The time frame for issuance of an SER on the NEI risk-informed fire-induced circuit failure methodology is, of course, dependent on the technical complexity and adequacy of the NEI RAI response. The staff expectation is that an SER can be issued during fall, 2000.
0
[It should be noted that a planned NRC/industry expert elicitation panel supporting NEI's effort now will likely not have NRC participation for Federal Advisory Committee Act (FACA) and NRC cost reasons. It is possible that this expert panel will complete its review of fire test data and provide important input into NEI's August 15, 2000 RAI response. It is also possible that the RAI response will be delayed pending expert panel input, scheduled to be defined.]
BWROG DETERMINISTIC FIRE-INDUCED CIRCUIT FAILURE METHODOLOGY 0
EEIB/NRR and SPSB/NRR are to have provided their comments on the BWROG methodology by March 20, 2000, and SNL will also have provided the staff with their review results by March 20, 2000.
By March 31, 2000, SPLB plans to issue a draft RAI to BWROG.
0 The staff will meet with the BWROG during April, 2000 to revise the RAI based on BWROG clarifications. A final RAI will be issued shortly after this meeting.
It is planned that by June 15, 2000 the BWROG will respond to the final RAI. At that time SPLB, SPSB and EEIB, and possibly SNL, will conduct reviews of the RAt response from BWROG.
0 The time frame for issuance of an SER on the BWROG deterministic fire-induced circuit failure methodology is, of course, dependent on the technical complexity and adequacy of the BWROG RAI response. The staff expectation is that an SER can be issued during summer, 2000.
C lR t
" W V W M.Wd
- JV Activities
- Design
° Licensing
° Engineering e Manufacturing
"* Fabrication
"* Marketing
"* Distributing
@ Selling
- JV Products & Services
"* Fuel Bundles
"* Components
"* Engineering Services
° Core Monitoring Services
- Fuel Inspection Services
- R&D Jv Scope Covers All Fuel Related Activities I (ft-l'-1k 4 JV Scope.
Nuclear'Fuel Joint Venture E
"The Scope of the Joint Venture Shall be the Nuclear Fuel Business"
- JV Structure
._Nuclear Fuel. Joint Venture SGENEi IFuel
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Wilmington (USA)
ENUSA (Europe)
JNF (Japan)
Fuel JV Part of GE Nuclear JV Control will Reside with GE
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'~Ky Nuclear Fuel Joint Venture Go To Market.
Region Specific I
CLOSEOUT OF GENERIC SAFETY ISSUE B-55, IMPROVED RELIABILITY OF TARGET ROCK SAFETY RELIEF VALVES
"* GSI B-55 created in early 1980's as a result of problems with spurious opening and blowing down of Target Rock 3-stage SRVs and upward setpoint-drift of 2-stage SRVs.
"* As a result of actions which have been taken by the BWROG and individual licensees to improve the performance of Target Rock SRVs, the staff decided to close GSI B-55 based on:
"* The spurious lifting and blowing down of Target Rock three-stage SRVs has been significantly improved by improved maintenance, increased simmer margins, and reduced numbers of challenges.
"* For the two-stage SRVs, licensees implemented one of three modifications which have significantly improved the upward setpoint drift problem:
Ion-beam implanted platinum pilot disks 0
Stellite 21 pilot disks 0
Additional pressure actuation switches
The staff also found that the BWROG and individual licensees were continuing to evaluate and improve the performance of the valves, as necessary, with sufficient resources.
The staff determined that if actions need to be taken to improve the performance of the SRVs in the future, the existing Quality Assurance, Maintenance Rule, and Codes and Standards regulations provide regulatory mechanisms for pursuing additional improvements on a plant specific basis.
"* The ACRS reviewed the resolution of GSI B-55 on October 1, 1999, and the staff closed out the issue in a letter to the EDO dated December 17, 1999.
"* As a followup activity, the staff plans to issue a Regulatory Issue Summary to inform the industry of the closure of GSI B-55.
2
BWRVIP/NRC Management Meeting March 16, 2000 NRC Offices Rockville, MD BWRVIP EOC/N RC-3/16/2000
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BWRVIP/NRC Management Meeting "t
AAgenda 10:30 a.m.
10:40 a.m.
11:25 a.m.
Opening Remarks/Introductions Update of BWRVIP Key Accomplishments and Activities Technical Committee Summaries Integration Assessment Inspection Repair Mitigation Open Discussion Status of NRC Review/Acceptance of BWRVIP Products Assessment of BWRVIP Implementation BWRVIP Direction in 2000 and Beyond BWRVIP Summary Items from the Floor Research Efforts Regarding Cascading Failures Summary and Review Action Items BWRVIP EOC/N RC-3/16/2000 K
EOC/NRC C. Terry V. Wagoner R. Carter C. Larsen B. McLeod J. Wilson BWRVIP/NRC NRC C. Terry C. Terry C. Terry NRC 11:55 12:
a.m.
noon
- 00 2
I
Asses GeogE ComE Execu Rich (
PECO Tech (
Bob C EPRI Task h K
BWRVIP Organization Carl Terry NMPC Chairman Joe Hagan PECO Energy Vice Chairman
- sment Inspection Mitigation Repair e Vanderheyden Bill Eaton Lewis Sumner George Jo d
Entergy SNC PPL itive Chair Executive Chair Executive Chair Executive 3iemiewicz Carl Larsen John Wilson Bruce McL Energy VT Yankee Amergen SNC
- hair Tech Chair Tech Chair Tech Chair arter Greg Selby Raj Pathania Ken Wolfe EPRI EPRI EPRI flgr Task Mgr Task Mgr Task Mgr Jack Dillich NPPD BWRVIP Liaison to EPRI Nuclear Power Council Bold indicates change since March 1999 meeting 41.
EOC/NRC-3/16/2000 nes Chair eod 3WRVIP J
3 E
Integration Harry Salmon NYPA Executive Chair Vaughn Wagoner CP&L Tech Chair Tom Mulford EPRI Task Mgr
BWRVIP Key Accomplishments Since March 1999 Submitted BWR Integrated Surveillance Program Plan
° Submitted technical basis for revisions to Generic Letter 88-01 inspection schedules
° Completed RPV and updated core shroud I&E guidelines
° Completed two updates to internals examination guidelines
° Initiated complementary BWRVIP and NRC RES project on weldability of irradiated material Transmitted to NRC Vessel and Internals Inspection Summaries for Fall 1998 outages and inspection plans for 1999 and 2000 EOC/N RC-3/1 6/2000 4
BWR I.
BWRVIP Key 2000 Activities Support NRC review and closure on all BWRVIP guidelines Support NRC review of M&E guidelines license renewal appendices Support NRC review of BWR Integrated Surveillance Program Plan and produce implementation plan
° Submit fracture toughness and crack growth evaluations of irradiated stainless steel Coordinate assessment of BWRVIP implementation similar to steam generator assessments Continue complementary BWRVIP and NRC RES work on weldability of irradiated material Continue transition to a maintenance mode SCNC
/BwRViP 5
I=
Integration Committee 2000 Deliverables
"* Vessel Internals Inspection Summaries for 1999 and 2000 outages Coordinate assessment of BWRVIP implementation
"* BWRVIP training modules Kev issues Continue technical dialog to achieve closure on all BWRVIP guidelines Coordinate BWRVIP transition to a maintenance mode EOC/NRC-3/1 6/2000-7B R I
Assessment Committee 1999 Deliverables "Evaluation of Stress Corrosion Crack Growth in Low Alloy Steel Vessel Materials in the BWR Environment (BWRVIP-60)," March 1999.
"Induction Heating Stress Improvement Effectiveness on Crack Growth in Operating Plants (BWRVIP-61)," January 1999.
° "Shroud Vertical Weld Inspection and Evaluation Guidelines (BWRVIP-63)," June 1999.
"Review of Test Data for Irradiated Stainless Steel Components (BWRVIP-66)," March 1999.
"BWR Reactor Pressure Vessel Inspection and Flaw Evaluation Guidelines (BWRVIP-74)," September 1999.
"Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (BWRVIP-75)," October 1999.
"BWR Core Shroud Inspection and Flaw Evaluation Guidelines (BWRVIP-76)," November 1999.
December 1999.
EOC/NRC-3/1 6/2000 9
I
/1"0-BWR-VIP EOC/N RC-3/16/2000 Assessment Committee 1999 Deliverables (continued)
"* Responses to NRC RAIs BWRVIP-05, 38, 41
"* Responses to NRC SEs on:
BWRVIP-18, 25, 26, 42, 47, 48 10
r EOC/NRC-3/16/2000 11 1.BWRIVIP Assessment Committee 2000 Deliverables BWR Integrated Surveillance Program (ISP)
Revised ISP test plan Implementation plan for ISP Conduct surveillance capsule testing in accordance with ISP
- Fracture Toughness of Irradiated SS Issue report on effects of radiation on fracture toughness of SS Evaluation of Crack Growth in irradiated stainless steel I&E Guideline Revisions Vibration Monitoring of Jet Pumps Issue report on feasibility I
N f
Assessment Committee Key Issues
- Support timely NRC review of remaining M&E guidelines
- Complete NRC review of:
License renewal appendices of M&E guidelines BWRVIP-75, revision to GL88-01 piping inspections BWRVIP-78, ISP EOC/N RC-3/16/2000 12 BWRVIP K
License Renewal Appendices License renewal appendices for RPV and all safety-related internals have been submitted to NRC
- These submittals support initial BWR license renewal application NRC has approved two license renewal appendices for referencing in license renewal applications -- need prompt NRC approval of remaining appendices BWRVIP 1%3
Revision to GL 88-01 Inspection Schedules BWRVIP revised GL 88-01 inspection schedules benefit both industry and NRC Important that NRC review be completed promptly Significant burden reduction via reduced piping inspection and person-REM exposure BWRVIP/
EOC/N RC-3/1 6/2000 1A I
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BWR Integrated Surveillance Prorgram Submitted BWR Integrated Surveillance Program (ISP) Plan in December 1999 Reviewed ISP Plan with NRC staff on March 14, 2000 BWRVIP goal is to obtain NRC approval by end of 2000 need prompt identification and resolution of issues need to maintain positive ISP cost-benefit for the BWR fleet BWRVlP EOC/NRC-3/16/2000 15
Inspection Committee Summary Carl Larsen Technical Chairman Vermont Yankee EOC/N RC-3/16/2000 16 BWRVIP r
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Inspection Committee 1999 Deliverables Revisions to examination guidelines BWRVIP-03
- Revision 1 submitted together with response to Revision 0 SER 3/99 NRC accepted both with no issues Revision 2 submitted (for information) 12/99 Advanced UT and ET methods for internals (core spray P9, core plate bolts from shroud OD, shroud H1 rapid exam)
Conducted three (3) IVVI Training sessions EOC/NRC-3/16/2000 17 JBWRVI-P K
f
K Inspection Committee 2000 Deliverables Update to internals examination guidelines (BWRVIP-03, Revision 3)
NDE methods for internal attachment welds Conduct one (1) IVVI Training session
- EOC/NRC-3/16/2000 18 BWRVIP
K EOC/NRC-3/16/2000 19 Inspection Committee Key Issues
- Stay ahead of internals inspection needs
- Internal attachment weld NDE program
- Other items as necessary
{BWRVIP
Repair Committee Summary Bruce McLeod Technical Chairman Southern Nuclear BWRVIP EOC/NRC-3/16/2000 20
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EOC/NRC-3/16/2000 21 BWR VIP!!!!!!I Repair Committee 1999 Deliverables Core Shroud Repair Design Criteria (Rev.2)
Revision to address vertical weld repair 0 Respond to RAIs and SEs Repair Design Criteria CRD Weld Repair
° Repair Material Guideline 0 Continue BWRVIP work on weldability of, irradiated material Sampling tool development and qualification Sampling analysis plan and contract Plant and sample location selection Sample process development, crew training, mobilization k
Repair Committee 2000 Deliverables Material Guideline for use with BWRVIP Repair Design Criteria
"° Weldability of Irradiated Material Project Interim guidance for weld repair Interim report on jet pump riser brace sampling program RAI/SE Responses BWRV IP EOC/N RC-3/1 6/2000 22i.-
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Repair Committee Key Issues Optimize results from joint BWRVIP/NRC project on weldability of irradiated materials RC-3/16/2000
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Mitigation Committee Summary John Wilson Technical Chairman AmerGen BWRVIP EOC/N RC-3/16/2000 24
Mitigation Committee 1999 Deliverables Published reports on Duane Arnold NMCA durability and fuel surveillance after one cycle and completed data collection on NMCA durability and fuel after two cycles (BWRVIP-67, -68,-69)
NMCA done at 8 plants including reapplication at Duane Arnold Delivered BWRVIA Radiolysis and ECP Model and conducted two training workshops for utility staff Published BWR Water Chemistry Guidelines (BWRVIP-79)
Published reports on flow effects on ECP and IGSCC and in-core crack growth tests (BWRVIP-64, -73, -77)
BWRVEI.P EOC/N RC-3/1 6/2000 E,,,=
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Mitigation Committee 2000 Deliverables 0 Publish reports on Duane Arnold NMCA durability and fuel surveillance after two cycles
° Publish report on NMCA experience at other plants Conduct one cycle fuel surveillance at Peach Bottom 2 to evaluate the effect of higher fuel duty and noble metal loadings on fuel performance Respond to NRC RAIs on "Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection (BWRVIP-62)"
BWRP V P EO /NR -3/16/2000
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Open Discussion Status of NRC Review of BWRVIP Products
- Assessment of BWRVIP Implementation BWRVIP Direction in 2000 and Beyond BWRVIP Summary Items from the Floor EOC/NRC-3/16/2000 27
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Assessment of BWRVIP Implementation BWRVIP evaluating an approach for assessment of utility implementation of BWRVIP products Considering INPO involvement Develop and conduct 2-3 pilot assessments in 2000 Evaluate process and results after pilot assessments and determine subsequent scope and schedule K ~
3/2onnBWRVI P
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BWRVIP Direction in 2000 Expect closure with NRC on BWRVIP base program guidelines in 2000 BWRVIP transition to a maintenance mode Executive oversight and timely response to industry issues will be maintained continue NRC interaction collection and dissemination of plant inspection data and experience utility implementation assessments implementation, training and assistance program maintenance based on industry experience BWRVIP EOC/N RC-3/1 6/2000 29
BWRVIP Summary BWRVIP base program guidelines have been submitted to NRC Expect closure with NRC on BWRVIP base program guidelines in 2000
"* Need to continue close coordination between BWRVIP and NRC activities to ensure timely approval and implementation of products that will result in maintaining safety, reducing burdens and increasing effectiveness and efficiency for:
License renewal appendices
-ISP Revised GL 88-01 inspection schedules Inspection relief for HWC BWRVIP
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BWRVIP SUBMITTALS Title Submitted Status I & E REPORTS WITH. LR APPENDICES BWRVIP-18, Core Spray Intde als Inspection and Flaw' Evaluation Guidelines 07/26h996 12/0 199*9 CF Appendix C - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 12/20/1996 02/21/2000 CF BWRVIP-25,t Core Plate Inspection and Flaw Evaluation Guideline i12/297/1996 12/12/,19999 CF Appendix B - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54)'
07/17/1997 03/31/20001TB BWRVIP-26, B'Top umpide Inspectionaand Flaw Evaluation Guideline' 121/7/1996 09/29/1099 CF Appendix C - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 07/17/1997 03/09/2000CF BWRVIP-27, Standby Liquid Control System I Core Plate AP Inspection and, Flaw Evaluation Guidelines,,
04/2-9/1997 04/2711999 CF Appendix B.- Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 05/15/1998 12/:011999 CF BWRVIP-38, Shroud Support Inspection and Flaw Evaluation Guidelines 09/15/1997 09/1-6/19992Cl Appendix B - Demonstration of Compliance With the Licence Renewal Rule (10 CFR Part 54) 09/15/1997
/TBD0 BWRVIP-41, BWR Jet Pump Assembly Inspection and Flaw Evaluation Guidelines i10/15/1997 03/28/2000 T Appendix A - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 10/15/1997 TBD BWRVIP-42, BWR LPCI Coupling Inspection and Flaw Evaluation Guidelines 12/11/1 997 06/14/1 999 Cl*
Appendix A-Demonstration. of Compliance with the Licence.Renewal Rule (10 CFR Part 54) 12/11/1997 TBD BWRVIPA47,,
BWR Lower Plenum Inspection a'n'd Flaw, Evaluation' Guidelines 13019710/1 3/1999 CF,
.Appendix A - Demonstration of Compliance with the. Licence Renewal Rule (10 CFR Part.54) 12/30/19'97. 03/06/2000 CF BWRVIP-48, Vessel ID Attachment Weld Inspection and Flaw Evaluation Guidelines 03/06/1998 09/29/1999,[CF
<Appendix A -Demonstration of Compliance with the Licence, Renewal Rule (10 CFR Part 54) 03/06/1998 11/1.9/1999 CF BWRVIP-49, Instrument Penetration Inspection and Raw Evaluation Guidelines 03/13/1998 08/04/1998 CF, Appendix A - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 03/13/1998. 07/15/1999 CF BWRVIP-74, BWR Reactor Pressure Vessel Inspection and Raw Evaluation Guidelines 09/21/1999 TBD (subsumes BWRVIP-05, BWR RPV Shell Weld Inspection Recommendations)
Appendix A - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 09/21/1999 TBD BWRVIP-76, BWR Core Shroud Inspection & Flaw Evaluation Guidelines 12109/1999 04/30/2000 T (subsumes BWRVIP-07, Guidelines for Reinspection of BWR Core Shrouds, and BWRVIP-63, Shroud Vertical Weld Inspection and Evaluation Guidelines)
Appendix K - Demonstration of Compliance with the Licence Renewal Rule (10 CFR Part 54) 12109/1999 06/30/2000 T 0
E U-:
BWRVIP SUBMITTALS Title Submitted Status BWRVIP REPORTS THAT SUPPORT LR BWRVIP-75, Technical Basis for Revisions to Generic Letter 88-01 Inspection Schedules (NUREG-0313) 10/27/1999 04/30/2000 T BWRVIP-78, BWR Integiated Surveillance Program - Unirradiated Charpy Reference Curves for Surveillance 12/01/1999 12/3112000 T Material j
REPAIR REPORTS - NOT DIRECTLY APPLICABLE TO LR BWRVIP-16, Internal Core Spray Piping and Sparger Replacement Design Criteria 03/18/1997.
11/16/1998 CI BWRVIP-1 9, Internal Core Spray Piping and Sparger Repair Design Criteria.
09/17/1996 11/16/1998 Cl BWRVIP-34, Technical. Basis for Part Circumferential WeldOverlay Repair of Vessel Internal Core Spray 05/22/1997 DEFERRED Piping BWRVIP4n4, UdeaterWeld Repair, of NickelAlIoy Reactor Vessel IntemnIls 10/211/1997, 06/09/1999 CF BWRVIP-45, Weldability of Irradiated LWR Structural Components 10/27/1997 REVIEWING BWRVIP-50, Top Guide / Core Plate Repair Design Criteria 05/14/1998 04/28/2000 T BWRVIP-51, Jet Pump Repair Design Criteria 05/14/1998 04/28/2000 T BWRVIP-52, Shroud Support and Vessel Bracket Repair Design Criteria 06/26t1998 04/28/2000 T BWRVIP-53, Standby Liquid Control Line Repair Design Criteria 07/02/1998 04/28/2000 T BWRVIP-55, Lower Plenum Repair Design Criteria 09/22/1998 04/28/2000 T BWRVIP-56, LPCI Coupling Repair Design Criteria 11/16/1998 04/28/2000 T BWRVIP-57, Instrument Penetrations Repair Design Criteria 12/16/1998 04/28/2000 T BWRVIP-58, CRD Internal Access Weld Repair 12/22/1998 04/28/2000 T MITIGATION REPORTS - NOT DIRECTLY APPLICABLE TO LR BWRV.P... iEvaluation of Crack'Growth in BWR Stainless Stee! RPV. Internals 03/18/19968 1203/1999 CF BWRVIP-59, Evaluation of Crack Growth in BWR Nickel-Base Austenitic Alloys in RPV Internals 12/23/1998 04/28/2000 T BWRVIP-60, *'kEvaluation of CrackGrowth In BWR Low Alloy Steel RPV Internals 03/30/1999 07/08/1 999 CF BWRVIP-62, Technical Basis for Inspection Relief for BWR Internal Components with Hydrogen Injection 12/31/1998 04/28/2000 T OTHER SUPPORTING BWRVIP REPORTS - NOT DIRECTLY APPLICABLE TO LR BWRVIP-03, ARPVIntemrals Examinaton Guidelines 1 1 072/...C BWRVIP-06, Safety Assessment of BWR Reactor Intemrals 10/05/1995 09/15/1998 CFP BWRVIP-61, BWR Vessel and Internals Induction Heating Stress Improvement Effectiveness on Crack 01/29/1999 04/28/2000 T Growth in Operating Plants
RISK ASSOCIATED WITH IGSCC-INDUCED FAILURE OF BWR INTERNALS NRC Program Manager: T.Y. Chang United States Nuclear Regulatory Commission Rockville, MD Principal Investigator: A.G. Ware Idaho National Engineering & Environmental Laboratory Idaho Falls, ID Presented to NRC Staff Rockville, MD March 2000
BACKGROUND
"* Program objective is to assess the potential risk associated with the failure of Intergranular Stress Corrosion Cracking (IGSCC)-susceptible Boiling Water Reactor (BWR) vessel internals components, both singly and in combination with the failures of others
"* Focus is on mechanical design, failure locations, consequences, potential accident scenarios, and characterization of risk
"* Only degradation mechanism considered is IGSCC, including contributing SCC mechanisms such as irradiation-assisted SCC (IASCC) other degradation mechanisms such as fatigue can act synergistically with IGSCC in that a crack which is initiated by IGSCC can propagate to failure from fatigue
BACKGROUND (Continued)
"* NRC investigating causes and contributing aspects of the IGSCC problem in separate programs
"* Industry groups are investigating inspection, mitigation, repair, and replacement, as well as the causes and contributing aspects of IGSCC
"* First phase of program gathered background information identified potential accident sequences
"* Second phase of program initially, jet pump failures studied to develop methodology potential accident sequences that could develop from failures of remaining reactor vessel internals investigated to assess risk
CONCLUSIONS
"* IGSCC has been detected at many locations in BWR reactor internals.
"* IGSCC cracking is expected to continue as the plants age.
"* Consequently, the probability of developing IGSCC cracks in reactor internals is assumed to be 1 (conservative).
"* With no inspection, monitoring, or repair, there are a number of internals, if severely degraded by IGSCC, that could fail either in a common mode or cascading manner, leading to an inability to insert rods or cool the core in the event of a severe internal or external event.
"* With no credit for inspection, monitoring, and repair, and a probability of significant cracks developing of 1, coupled with the initiating event frequencies and system failure frequencies in the PRA studied, an undesirable increase (> 5 x 10"6 events/yr) in the plant CDF is predicted.
CONCLUSIONS (CONTINUED)
- The BWRVIP submittals have been reviewed, independent confirmatory assessments and analyses have been performed, and probability estimates have been made for cascading events. The calculations and estimates in the documents submitted by the BWRVIP appear reasonable.
- With the current BWRVIP inspection, monitoring, and repair proposals, there is expected to be no significant increase in CDF (< 5 x 10-6 events/yr) caused by failures of BWR internals. That is, IGSCC problems can be identified and evaluated or corrected, to preclude a significant increase in the CDF.