ML20248J524
| ML20248J524 | |
| Person / Time | |
|---|---|
| Issue date: | 06/04/1998 |
| From: | Combs F NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Jocelyn Craig NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| CON-FIN-W-6479, REF-GTECI-MI, REF-GTECI-SC, TASK-*****, TASK-OR IEB-97-002, IEB-97-2, IEIN-96-052, IEIN-96-52, IEIN-97-091, IEIN-97-91, TAC-L20319, TAC-L21140, NUDOCS 9806090180 | |
| Download: ML20248J524 (14) | |
Text
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. v June 4, 1998 l
MEMORANDUM TO: John W. Craig, Director Division of Regulatory Applications, RES i FROM: Frederick C. Combs, Acting Director (orig. signed by) l Division of industrial and ,
I Medical Nuclear Safety, NMSS l
l l
SUBJECT:
SUBMITTAL OF NEW GENERIC ISSUES FOR TRACKING IN THE {
l GENERIC ISSUES MANAGEMENT AND CONTROL SYSTEM (GIMCS)
Information on the following generic issues is attached for entry into GIMCS:
FC-1 ' Criticality Benchmarks >5% Enrichment )
IM-1 Yeaf 2000 Computer Problem - Nonreactor Licensees IM-2 Amersham Radiography Source Cable Failures IM-5 Troxler Gauge Source Rod Weld Failures SF-2 Spent Fuel Dry Cask Weld Cracks SF-3 Inadequate Transportation Packaging Puncture Tests The prioritization of these issues was reviewed at the NMSS Operational Events Briefing on May 11,1998.
Attachments: As stated cc: E. Ten Eyck C. Haughney CONTACT: Kevin M. Ramsey, NMSS/IMNS .
(301)415-7887 DISTRIBUTION: f NRC Central File - SParra SJLee REmrit IMNSi/f ~ ' CNilsen LCamper TOMartin /
NMSS r/f GPurdy TKobetz DTiktinsky PDR: YES _2L NO //[g.
DOCUMENT NAME: G:GIMCS.KMR To receive a copy of this document, indicate in the box:
"C"= Copy w/o att/ encl. "E" = Copy w/att/ encl. "N" = No copy * = See previous concurrence OFC OB* E OB* E M )
NAME KD y/ll SMoore [ mms '
DATE 5/21/98 5/27/98 6lk /98 OFFICIAL RECORD COPY IMNS/SEC C 6 C${11d
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. o MEMORANDUM TO: John W. Craig, Director p Division of Regulatory Applications, RES FROM: Donald A. Cool, Director Division of Industrial and Medical Nuclear Safety, NMSS
SUBJECT:
SUBMITTAL OF NEW GENERIC ISSUES FOR TRAC G IN THE GENERIC ISSUES MANAGEMENT AND CONTROL STEM (GIMCS)
Information on the following generic issues is attached for entry into MCS:
FC-1 Criticality Benchmarks >5% Enrichment IM-1 Year 2000 Computer Problem - Nonreactor Licensees IM-2 . Amersham Radiography Source Cable Failures IM 5 Troxler Gauge Source Rod Weld Failures SF-2 Spent Fuel Dry Cask Weld Cracks SF-3 Inadequate Transportation Packaging Punctu Tests The prioritization of these issues was reviewed a he NMSS Operational Events Briefing on May 11,1998.
Attachments: As stated cc: E. Ten Eyck C. Haughney CONTACT: Kevin M. Rams , NMSS/IMNS (301) 415-788 DISTRIBUTION:
NRC Central File SParra SJLee REmrit IMNS r/f CNilsen LCamper NMSS r/f GPurdy TKobetz PDR: YES X_ DTiktinsky TOMartin DOCUMENT AME: G:GIMCS.KMR To receive a py of this document, indicate in the box:
"C"= Copy o att/ enc!. "E" = Co )y w/attlenci "N" s No copy OF OB 69) IMNS kME KRam h bCombs DCool
[DATE' 5/c2/ /98 5/ /98 5/ /98
/ OFFICIAL RECORD. COPY IMNS/SEC
/ /96
4 0 GENERIC ISSUE MANAGEMENT AND CONTROL SYSTEM INFORMATION ltem Number FC-1 1 Title Criticality Benchmarks >5% Enrichment Prionty Low (reviewed at 5/11/98 Operational Events Briefing)
L Lead Office NMSS/FCSS Ciner Office RES/DRA Task Manaqar S. Parra, NMSS C. Nilsen, RES TAC Number -
l Work Authorization Contractor Account No. 41W6479W1 i Contract Title Development and Applicability of Criticality Safety Software for l Licensing Review Contractor / FIN No. ORNL, FIN W6479 Work Scooe The importance of software (metheds and data) in establishing the criticality safety of systems with fissile material is increasing as licensees work to optimize facilities and storage / transport packages at the same time that access to experimental data is decreasing. Available experimental data are insufficient to validate nuclear criticality safety evaluations for all required configurations at uranium-235 enrichments in the range of 5-20% The purpose of this project is to develop and confirm the adequacy of methods, analytical tools, and guidance for criticality safety software to be used in licensing nuclear facilities. The contractor will develop and test methods to estimate trends in calculational bias and uncertainty (thus extending the range of applicability) using sensitivity analysis techniques that relate the importance of the system parameters to the calculated neutron multiplication factor; provide. expert guidance on assessing the adequacy of the parameter phase space used in the validation process and the resulting bias and uncertainty; and illustrate use of the guidance by -
application to a regime of experimental phase space (such as 5-10%
U-235 and degree of moderation) that has limited measured data but extensive interest in terms of current and planned safety evaluations.
' A new statement of work may need to be developed for other contract work (e.g., applying the methods developed to determine margins of safety for actual scenarios, training NRC personnel on the contract methods, revising national standards, or performing benchmark experiments).
e ~
- Attachment
Affected Documents A new guidance document will be developed as part of the contract.
NMSS anticipates that the results of the contract will be incorporated into NRC guidance documents (e.g., NUREGs, Regulatory Guides, and Standard Review Plans). Information developed in this project should also be applied in licensing reviews for commercial fuel fabrication facilities and other licensing evaluations (e.g., AVLIS).
Milestones Milestones for Current Contract Original Date Current Date Actual Date Acquisition and Documentation of Russian 05/31/98 12/30/98 -
Data Development of Generalized Sensitivity 12/31/97 03/31/99 -
Methods Development of Guidance for Defining Ranges 07/01/98 07/01/98' --
of Applicability Application of Guidance to Extend Low- 09/30/98 09/30/986 -
Enrichment Range Technical Assistance and Project Planning 03/31/99 03/31/99 -
Other Milestones Original Date Current Date Actual Date Receive final ORNL contract report 03/31/99 03/31/99 -
Evaluate final ORNL contract report -- - -
Determine if user needs have been met by - - -
ORNL contract if user-needs were not met by ORNL contract:
Issue user-need request for study - - -
Issue request for bids - -
Receive bids - -
Award contract - -
- Current estimated dste for completion is 12/30/98; NMSS needs information by original j due date (7/01/98) for timely incorporation into licensing reviews.
- Current estimated date for completion is 3/30/99; NMSS needs information by original due date (9/30/98) for timely incorporation into licensing reviews.
[
Receive draft report -- -- --
Accept final report -- -
Implement necessary regulatory changes -- -
Close out activity - -
Etatus Research is ongoing. RES and NMSS meet periodically (e.g., every couple of months) with contractors for briefings on the status and developments of the project. Most recent briefing (2/98) indicated the possibility of using existing critical experiment data to extend range of analysis under certain conditions. RFPs for future possible contracts have not yet been developed.
Problem / Resolution Access to some of the critical experiment data, especially in the international arena, may be limited by country and company confidentiality and proprietary restrictions. In addition, the scientists who conducted much of the early critical experiments are approaching retirement or have already retired. Additional work is being planned to access experimental data at Los Alamos and other institutions prior to retirement of key scientists. In addition, government funding is being used to ensure the availability and accessibility of experimental data.
Company proprietary information submitted by licensees will be evaluated against publicly accessible information to confirm adequacy and availability of the information in support of licensing.
I
L, GENERIC ISSUE MANAGEMENT CONTROL INFORMATION ltem Number IM-1 Ijtig Year 2000 Computer Problem - Nonreactor Licensees Pnonty High (reviewed at 5/11/98 Operational Events Briefing)
Lead Office NMSS/IMNS Other Office --
Task Manager G. Purdy, NMSS/IMNS TAC Number L20319 Work Authonzation -
1 Contract Title -
Contractor / FIN No. -
Work Scone The Year 2000 computer problem has the potential to pose a threat to public m sith, site safety & safeguards, and worker safety. Many computer systems may potentially fail to recognize the change to a new century. These systems may misread the year 2000 and thus may cause the systems to fail or generate faulty data.
NMSS has taken a number of actions to ensure that the Year 2000 computer problem will be either eliminated or minimized for its materials licensees. These actions include issuing information notices on the Year 2000 issue, coordinating with FDA regarding medical devices, establishing a Year 2000 team to address Year 2000 impacts on materials and fuel cycle licensees, conducting interviews with the management of materials and fuel cycle licensees to identify Year 2000 issues, pub!ishing articles in industry publications, and following up on all ,
activities through personal contact by materials and fuel cycle inspectors.
NMSS will issue a Generic Letter to fuel cycle licensees addressing the Year 2000 problem. NMSS will continue to produce Newsletter articles or Information Notices to emphasize the Year 2000 problem.
Affected Documents inspection Procedures Milestones Oriainal Date Current Date Actual Date
- Information Notice 96-70 12/96 12/96 12/96 Information Notice'97-61 7/97 7/97 7/97 NMSS Newsletter Article 9/97 9/97 9/97
' Establish Y2K Team ' 9/97 9/97 9/97 Memo to inspectors (ask Y2K questions) ~ 11/97 11/97- 11/97 Complete Site Visits ,
12/97 12/97 12/97
l Milestones Oriainal Date Current Date Actual Date HPS Article 1/98 1/98 1/98 Revise inspection Procedures 5/98 6/98 issue Generic Letter Requesting Responso From Fuel Cycle Licensees 5/98 6/98 issue Another information Notice to Other NMSS Licensees 6/98 6/98 Status Generic Letter to fuel cycle licensees and certificate holders in concurrence.
Problem /ResolutiQD None
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GENERIC ISSUE MANAGEMENT AND CONTROL SYSTEM INFORMATION Item Numi.tr IM-2 Iilla Amersham Radiography Source Cable Failures Prionty High (reviewed at 5/11/98 Operational Events Briefing)
Lead Office NMSS/IMNS Other Offices -
l- Task Manaaet Larry Camper, IMNS TAC Number -
Work Authorization -
Contract Title -
Contractor / FIN No. -
Work Scooe During November and December 1997, NRC received 3 reports of radiography source disconnects involving drive cable breaks (see EN 33351, PN-1-97-75, and PN-3-97-93). Each of these incidents involved Amersham equipment. Information Notice 97-91 was issued on 12/31/97 to alert all radiography licensees to the problem. Amersham is analyzing the cable functions.
Between December 1997 and March 1998, special team inspections were conducted at Amersham facilities in Massachusetts and Louisiana.
. Additional followup actions will be considered after the investigation report is issued.
Affected Documents -
Milestones Oriainal Date Current Date Actual Date Complete SpecialInspections 3/98 3/98 3/98 Issue inspection Report 4/98 6/98 Task Additional Followup Actions 5/98 6/98 Complete Additional Followup Actions - -
Closeout Activity - -
Status inspections and draft report completed. Preparing final report.
PIQblem/ Resolution None
r 1
1 GENERIC ISSUE MANAGEMENT AND CONTROL SYSTEM INFORMATION I
Item Numtter IM-5 Ijile Troxler Gauge Source Rod Weld Failures Erjonty Medium (reviewed at 5/11/98 Operational Events Briefing)
Lead Offjgg NMSS/MSB Other Office OSP Task Manaaer Seung Lee, MSB TAC Number --
l Work Authorization -
I Contract Title -
Contractor / FIN No. --
I Work Scoom On 6/25/97, the source from a Troxler moisture density gauge broke off l '
the source rod and was left at a temporary job site (see PN-1-97-42). On 7/17/97, NMSS and North Carolina staff met with Troxler (a State licensee) to discuss the ongoing problem with cracked and broken source rods. Information Notice 96-52 previously recommended that users inspect source rods for cracks. There have been 6 known disconnects and 57 additional devices with cracked welds since 1996.
Between 7/97 and 4/98, the staff worked with the State of North Carolina on a Consent Order to Troxler. The order requires Troxler to ISSUE a customer bulletin, conduct accelerated device inspections, revise procedures, and perform additional tests. The customer bulletin will address the problem and request customers to have their gauges inspected. The bulletin will also provide information on how to identify and respond to source disconnects.
The staff will continue to work with North Carolina to ensure no cracked rods remain in service (repaired or replaced by authorized licensees),
and ensure the manufacturing process is reviewed / modified to reduce the potential for recurrence.
Affected Documents -
Milestones Oriainal Date Current Date Actual D. alt North Carolina Order Issued 4/98 4/98 4/98 Troxler issues Customer Bulletin 7/98 7/98 Troxler Provides Response Status 10/98 10/98 NRC determine need to issue order or bulletin to licensees that have not responded 11/98 11/98 Troxter Completes Metallurgical Testing TBD Troxler Provides Testing Results TBD + 90 days Troxler Revises Operating Manual TBD Closecut Activity TBD Status The Consent Order was issued to Troxler 4/98.
Problem / Resolution The Consent Order was delayed by extensive review and comment by the State and Troxler legal staff, and the resolution of Troxler concerns.
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I GENERIC ISSUE MANAGEMENT AND CONTROL SYSTEM !NFORMATION ltem Number SF-2 Iiiin Spent Fuel Dry Cask Weld Cracks Pnonty Medium (reviewed at 5/11/98 Operauonal Events Briefing)
Lead Office NMSS/SFPO Other Office NRR/DE/EMCB
! RES/DET/EMMEB Task Manager Timothy J. Kobetz, SFPO ,
TAC Number L21140, Welding Review Team Work A: theorization -
Contract Title -
Contractor / FIN No. -
Work Scooe in early 1997, NRC became aware that, on four separate occasions, utilities using the VSC-24 spent fuel dry cask storage system had experienced cracking while making the cask closure welds. In May 1997, NRC issued CALs to SNC and three utilities to document their commitments not to load additional VSC-24s until the root cause of the cracking was identified and corrective actions were implemented to prevent recurrence. SNC and the utilities formed an Owners Group to resolve the walding problems.
Research will assist NMSS/SFPO in the assessment of whether corrective actions implemented by the VSC-24 Cask Owners Group adequately resolve welding problems encountered by utilities. In addition, RES will review root cause of the welding problems for generic applicability to other cask designs currently in use.
ANacted Documents To be determined Milestones Original Date Current Date Actual Date Assess short term corrective actions 6/98 6/98 associated with the VSC-24 cask Assess long term corrective actions TBD associated with generic implications of casks designs currently in use
__-_________-______-___--_-_-_-_--_-__a
F g .
l 2 MS Performing inspection of prcposed corrective actions.
Problem / Resolution No problems identified.
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GENERIC ISSUE MANAGEMENT AND CONTROL SY3 TEM INFORMATION I
Item Number SF-3 f
Iille inadequate Transportation Packaging Puncture Testing Pnonty Medium (reviewed at 5/11/98 Operational Events Briefing) l Lead Office NMSS/SFPO Other Office -
Task Manaaer David Tiktinsky, SFPO TAC Number -
Work Authorization -
Contract Title -
Contractor /JCN -
Work Scooe The NRC became aware that two holders of NRC Certificates of Compliance for packages under Part 71 had performed the puncture test using a bar that was not properly mounted as specified in 10 CFR 71.73(c)(3). Based on these findings,Bulletin 97-02.vas issued on 9/23/97 to notify holders of Certificates of Compliance about issues related to the performance of the puncture test as specified in 10 CFR 71.73(c)(3) and request that all actions in the bulletin be implemented.
All holders of NRC Certificates of Compliance for packages were requested to review their puncture test assessment for each of their certified package designs. For package designs whose puncture test assessment was based on physical tests, the certificate holder was requested to determine whether the puncture test had been performed in accordance with 10 CFR 71.73(c)(3).
The responses to the bulletin identified packages that had not been puncture tested in full accordance with the regulations, in addition, there were some packages for which the Certificate holder was unable to determine whether the test was performed correctly. The certificate holders also submitted justifications for continued use of these packages.
The generic issue regarding puncture testing will be resolved through (1) developing guidance for applications for certification of new package designs, and (2) developing guidance for licensing actions for existing Certificates of Compliance for affected packages. Licensing actions include amendment and renewal of Certificates of Compliance for
- _ _________.__m
j 2-existing designs. The need for package retesting will be assessed for existing package designs. One factor will be the fabrication of additional packages of affected designs. After April 1,1999, the fabrication of new packages is only authorized for packages designated as "-85," as required in 10 CFR 71.13(b)(1). NRC will not designate a package as
" 85" unless the applicant can demonstrate that the puncture test was performed in full compliance with 10 CFR 71.73(c)(3).
Affected Documents -
Milestones Oriainal Date Current Date Actual Date Develop guidance for performance of 11/97 11/97 11/97 puncture testing for new package designs. See NUREG-1609, Standard Review Plan for Transportation Packages for Radioactive Material.
Develop guidance for processing 10/98 10/98 -
licensing applications for amendment and renewal of existing Certificates of Compliance. Amendments include designation of package design as "-85."
Communicate guidance to holders 11/98 11/98 -
of existing Certificates of Compliance.
Status Developing guidance for existing package designs internally.
Problem Resolution No problems identified.
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