ML20212A928
| ML20212A928 | |
| Person / Time | |
|---|---|
| Issue date: | 08/30/1999 |
| From: | Collins S NRC (Affiliation Not Assigned) |
| To: | Thadani A NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) |
| References | |
| NUDOCS 9909170197 | |
| Download: ML20212A928 (5) | |
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MEMORANDUM TO: Ashok Thadani, Director ffice of Nuclear Regulatory Research V
FROM:
amuel J. Collins, Director Office of Nuclear Reactor Regulation
SUBJECT:
NRR USER NEED REQUEST FOR SUPPORT OF RESOLVING MATERIAL ISSUES RELATED TO AGE RELATED DEGRADATION OF REACTOR VESSEL INTERNAL COMPONENTS By memoranda dated December 2,1994, and October 31,1996, the Office of Nuclear Reactor Regulation (NRR) requested that the Office of Nuclear Regulatory Research (RES) develop additional information to assist in NRR's assessment of industry's actions to solve the problem of the cracking of both boiling water reactor (BWR) and pressurized water reactor (PWR) internal components; assess the potential consequences and risks of the failure of BWI internals components caused by intergranular stress corrosion cracking, and provide verification and validation of low-alloy steel (LAS) crack growth models, weldability at s aus fluence levels, and underwater welding technology.
Since the December 2,1994, and October 31,1996, memoranda, the BWR Vessel and Internals Project (BWRVIP) has developed and submitted for staff review approximately 55 generic reports on inspection, assessment, mitigation and repair of BWR internal components and systems. These reports address aging management of reactor pressure vessel and internals, and the application of the various BWRVIP guidelines to the extended license renevyal period.
In light of issues raised through the review of operating experience and anticipated license renewalissues, NRR requests that RES expand the scope of confirmatory research to include the following:
a.
the effects of high fluence (in excess of 5 x 10 n/cm ) on crack growth rate 2
2 (CGR), with particular emphasis on components that have been partially sensitized by welding, including developing data to confirm estimates of CGR for highly irradiated austenitic stainless steel (SS) and nickel alloy weldments; b.
the causes and mechanisms for irradiation assisted stress corrosion cracking (IASCC) in reactor materials, especially in welded austenitic SS components, including:
b-n j)\\-(I CONTACTS: Robert A. Hermann, NRR 415-2768 C. E. Carpenter, NRR 415-21269 9909170197 990830 h 9_ h-/-
PDR ORG NRRA
Ashok Thadani determine how radiation and thermal sensitization of SS materials interact synergistically to contribute to IASCC and intergranular stress corrosion cracking (IGSCC) effects; review modeling efforts for predicting IGSCC and IASCC effects; c.
assess the effectiveness of the various mitigative water chemistry measures; d.
continued support to NRR as needed for review and evaluation input for allegations,10 CFR 2.206 petitions, and other reviews, including staff support for participation in public meetings; and, e.
support for reviews with regard to extended licensing period applications for IGSCC, lASCC, mitigation measures, and any other technical support needed by NRR to address environmentally assisted cracking.
The results of this work should be transmitted to NRR in the form of monthly progress reports, periodic NUREG reports, revisions to Regulatory Guides, and other appropriate documentation.
We have discussed this request with RES and understand that, as a result of budget limitations and other priorities in funding, some of the above work might not be initiated immediately. In order to assure that the results of the RES efforts in the above areas can be effectively utilized by NRR in a timely manner, the specific details regarding scope and schedule of the tasks involved should be developed through close interoffice coordination between NRR and RES.
We suggest that a detailed program plan be completed in early FY-2000.
The NRR contacts for this User Need Request are Robert A. Hermann and C. E. (Gene)
Carpenter, Jr.,in the Division of Engineering. Please keep the NRR staff informed of your progress.
Your continued support in this area is appreciated.
DISTRIBUTION:
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Your continued support in this area is appreciated.
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determine how radiation and thermal sensitization of SS materials interact synergistically to contribute to IASCC and intergranular stress corrosion cracking (IGSCC) effects; d.
review modeling efforts for predicting IGSCC and IASCC effects, including impurity effects in grain boundaries; e.
assess the effectiveness of the various mitigative water chemistry measures; f.
continued support to NRR as needed for review and evaluation input for allegations,10 CFR 2.206 petitions, and other reviews, including staff support for participation in public meetings; and, j
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support for reviews with regard to extended licensing period applications for l
IGSCC, lASCC, mitigation measures, and any other technical support needed by NRR to address environmentally assisted cracking.
We have discussed this request with RES and understand that, as a result of budget limitations and other priorities in funding, some of the above work might not be initiated immediately. In order to assure that the results of the RES efforts in the above areas can be effectively utilized by NRR in a timely manner, the specific details regarding scope and schedule of the tasks involved should be developed through close interoffice coordination between NRR and RES.
We suggest that a detailed program plan be completed in early FY-2000.
The NRR contacts for this User Need Request are Robert A. Hermann and C. E. (Gene)
Carpenter, Jr., in the Division of Engineering. Please keep the NRR staff informed of your progress.
Your continued support in this area is appreciated.
DISTRIBUTION:
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Ashok Thadani 2-determine how radiation and thermal sensitization of SS materials interact synergistically to contribute to IASCC and intergranular stress corrosion cracking (IGSCC) effects; review modeling efforts for predicting IGSCC and lASCC effects; c.
assess the effectiveness of the various mitigative water chemistry measures; d.
continued support to NRR as needed for review and evaluation input for allegations,10 CFR 2.206 petitions, and other reviews, including staff support for participation in public meetings; and, e.
support for reviews with regard to extended licensing period applications for IGSCC, IASCC, mitigation measures, and any other technical support needed by NRR to address environmentally assisted cracking.
The results of this work should be transmitted to NRR in the form of monthly progress reports, periodic NUREG reports, revisions to Regulatory Guides, and other appropriate documentation.
We have discussed this request with RES and understand that, as a result of budget limitations and other priorities in funding, some of the above work might not be initiated immediately. In
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order to assure that the results of the RES efforts in the above areas can be effectively utilized by NRR in a timely manner, the specific details regarding scope and schedule of the tasks involved should be developed through close interoffice coordination between NRR and RES.
We suggest that a detailed program plan be completed in early FY-2000.
The NRR contacts for this User Need Request are Robert A. Hermann and C. E. (Gene)
Carpenter, Jr.,in the Division of Engineering. Please keep the NRR staff informed of your progress.
Your continued support in this area is appreciated.
1