ML20246G115
| ML20246G115 | |
| Person / Time | |
|---|---|
| Issue date: | 03/01/1989 |
| From: | Advisory Committee on Reactor Safeguards |
| To: | Advisory Committee on Reactor Safeguards |
| References | |
| ACRS-2622, NUDOCS 8905150190 | |
| Download: ML20246G115 (48) | |
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SUMMARY
/ MINUTES OF THE ACRS SUBCOMMITTEE MEETING ON SAFETY RESEARCH PROGRAM FEBRUARY 8, 1989 BETHESDA, MARYLAND INTRODUCTION I
The ACRS Subcommittee on Safety Research Program held a meeting on Wednesday, February 8, 1989, at 7920 Norfolk Avenue, Bethesda, Maryland, to discuss the ongoing and proposed NRC Safety Research Program and budget and other related matters. The entire meeting was open to public attendance. Mr. Sam Duraiswamy was the cognizant ACRS Staff Engineer for this meeting. A list of documents submitted to the Subcommittee is l
included in Attachment A, and a copy of the presentation schedule for the meeting is included in Attachment B.
ATTENDEES ACRS:
C. P. Siess (Subcommittee Chairman), W. Kerr, C. Michelson, F. J. Remick, P. G. Shewmon, and C. J. Wylie.
Sam Duraiswamy (Cognizant ACRS Staff Engineer).
Principal NRC Speakers:
E. Beckjord, G. Arlotta, W. Houston, B. Sheron, and l
B. Morris.
EXECUTIVE SESSION Dr. Siess, the Subcommittee Chairman, convened the meeting at 8:30 a.m.
and stated that the purpose of the meeting was to hear presentations by l
and hold discussions with representatives of the Office of Nuclear Regulatory Research (RES) with respect to the following:
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' Organizational structure of the NRC Safety Research Program.
DESICHTED ORIGIRL l
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Safety Research Program Meeting Minutes February 8, 1969 I'
- Ongoing and proposed NRC Safety Research Program and budget.
- Impact of the budget reduction proposed by the Office of Management andBudget(0MB)onthecontinuingandproposedNRCSafetyResearch i
Program.
- Contributions of research in the past five years.
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- Interaction with the Nuclear Safety Research Review Committee.
Dr. Siess stated that the Subcommittee had received neither written comments nor requests for time to make oral statements from members of the public. He mentioned that this meeting was intended primarily to obtain an overview of the ongoing and proposed NRC Safety Research Program and budget. Any detailed discussions of a specific research program should be handled by appropriate Subcommittees at separate meetings.
ORGANIZATION OF RES - DR. E. BECKJORD Dr. Beckjord discussed briefly the current organization of RES (Attach-ment C, Page 1). He stated that the research office consists of two-Deputy Directors and four Divisions. These four Divisions fall into two major categories:
Divisions Responsible for Research
- Division of Engineering
- Division of Systems Research These Divisions will come under Dr. Ross, Deputy Director for Research.
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,f Divisions Responsible for Resolution of Issues and Development of L
Rules and Requirements l
' Division of Safety Issue Resolution
- Division of Regulatory Applications These Divisions will come under Dr. Speis, Deputy Director for Generic Issue Resolution.
ORGANIZATIONAL STRUCTURE OF THE SAFETY RESEARCH PROGRAM - DR. E.
BECKJORD Dr. Beckjord stated that the Safety Research Program is divided into five major program areas that consist of several research elements as.
shown below.
1.
Integrity of Reactor Components This program consists of the following four major research ele-ments:
- Reactor Vessel and Piping Integrity
' Aging of Reactor Components
- Reactor Equipment Qualification
- Seismic and Fire Protection Research 2.
Preventing Damage to Reactor Cores The major research elements included under this program are as follows:
- Plant Performance
- Reactor Applications
- Human Performance
- Reliability of Reactor Systems
- Accident Management
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n Safety Research Program Meeting Minutes February 8, 1989 3.
Reactor Containment Performance and Public Protection from Radi-ation This-program consists of six major research elements as noted below:
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- Core Melt and Reactor Coolant System Failure
- Reactor Containment Safety
- Reactor Containment Structural Integrity
- Reactor Accident Risk Analysis
- Severe Accident Policy
- Radiation Protection and Health Effects 4.
Confirming the Safety of Nuclear Waste Disposal This program consists of two major research elements:
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- Low-Level Waste
- High-Level Waste 5.
Resolving Safety Issues and Developing Regulations This program consists of four major research elements:
- Generic and Unresolved Safety Issues
- Standardized and Advanced Reactors
- Fuel Cycle, Materials, Transportation, and Safeguards
- Developing and Improving Regulations Research Program Budget Dr. Beckjord discussed briefly the funding for research programs, and non-DOE contract activities (Attachment C, Pages 2-6).
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Safety Research Program Meeting Minutes February 8, 1989 OVERALL-IMPACT OF THE BUDGET REDUCTION PROPOSED BY THE OMB ON THE FY 1990 NRC RESEARCH PROGRAM DR. E. BECKJORD Dr. Beckjord stated that the overall budget request submitted to the OMB during September 1988 included a total budget of $120.6 million for the FY 1990 NRC Safety Research Program which is about $25 million more than the FY-1989 budget.
In order to accommodate the reduction proposed by the OMB to the overall agency budget, the Safety Research Program support budget was reduced by $12.6 million, from $120.6 million to $108 million. The proposed allocation of this reduction to various research-programs is given below.
- Integrity of Reactor Components
- $ 3.6 M
- Preventing Damage to Reactor Cores
- $ 2.5 M
- Reactor Containment Performance and Protection from Radiation
- $ 4.3 M
- Nuclear Waste Disposal
- $ 0.9 M
- Resolving Safety Issues and Developing Regulations
- $ 1.3 M Total
- $12.6 M Dr. Beckjord discussed briefly the principal focus of the NRC research program during FYs 1990 and 1991, and key research efforts during FYs 1989 and 1990 (Attachment C, Pages 7 and B).
Stating that in its report on Revitalizing Nuclear Safety Research the National Research Council recommended that the NRC consider separating the functions of standards development and research, Dr. Siess asked why that recommendation was not adopted. Dr. Beckjord stated that if a separate office is established to develop standards, it would require additional people and resources.
Further, since results of the research
O Safety Research Program Meeting Minutes February 8, 1989 are used as a basis for developing certain standards, he believes that it is more appropriate to have both of these functicns in the same office.
He said that the Commission is in agreement with not separating the functions of standards development and research and it made the suggestion to add a statement pertaining to standards development to the research philosophy, i
Dr. Siess commented that including standards development as part of the research philosophy does not seem appropriate. Also, the people manag-ing research could be able to do a better job if they don't have to perform two functions.
Dr. Kerr asked how the information obtained from the Seismic Margins research program will be used in making regulatory decisions. Dr.
Beckjord stated that this information may be used in the Individual Plant Examination (IPE) program for evaluating the seismic capabilities of the operating plar.ts.
Mr. Michelson asked whether they plan to perform any fire protection research.
Dr. Beckjord stated that there is no fire protection research planned at this time. However, he believes that there will be some work in this area in FY 1990.
Dr. Siess asked whether Generic Issues are now resolved faster than they I
are being generated. Mr. Houston stated that basically Generic Issues are resolved faster than before.
In response to a question from Dr. S1ess regarding the funding for i
i research work perfonned by orgar.intions other than DOE Laboratories, Dr. Beckjcrd stated tht Nr. Todreas, Chairman of the Nuclear Safety Research Eeview Cemittu (hSRRC), has expressed ar. interest in reviewing the research work being performed or planned outside of the
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i Safety Research Program Meeting Minutes February 8, 1989 National Laboratories and the related expenditures. Accordingly, RES is in the process of developing necessary information on this matter.
Dr. Siess requested that a copy of the information on research performed outside of the National Laboratories and the associated expenditures be provided to the ACRS when available.
Dr. Beckjord stated that he would provide that information to the ACRS after completion of the review by the NSRRC.
Stating that sometimes the National Laboratories subcontract part of the research work to certain private contractors, Dr. Siess asked whether RES has any control over the selection of subcontractors by the National Laboratories. Dr. Beckjord stated that he has urged the Directors of the National Laboratories to subcontract the work to universities and private contractors who could produce high-quality work. However,' he never tells the National Laboratories which specific subcontractors they should choose. Dr. Sheron stated that every research contract issued from his Division states explicitly that before using a subcontractor the National Laboratories should submit a written request for using that subcontractor.
Dr. Kerr asked about the process that they use in deciding what research should be done. Dr. Beckjord stated that generally, a need for certain research is decided on the basis of the needs of the research user offices, such as the Office of Nuclear Reactor Regulation (NRR) and theOfficeofNuclearMaterialsSafetyandSafeguards(NMSS). Also, 1
research f s planned to develop information for use by the agency in making decisions on important regulatory issues.
Dr. Kerr asked how dc they decide when 6 specific research program is i
completed.
Dr. Deckjerd stated that they periodically evaluate the research programs to see whether they have fulfilled their intended needs.
If it was determined that they did, they will be considered finished.
Safety Research Program Meeting Minutes February 8, 1989 INTEGRITY OF REACTOR COMPONENTS - MR. G. ARLOTTO Mr. Arlotto stated that research in this area is directed primarily to look at problems at operating plants.
It is to ensure that reactor plant systems and related components perform as designed and that their functional integrity and operability can be maintained over the life of the plant.
Mr. Arlotto said that during 1988 they met with individual members of the ACRS and several ACRS Subcommittees such as Metal Compo'ients, Structural Engineering, and Reliability Assurance to discuss several research elements related to Embrittlement of Reactor Pressure Wssel Supports, Piping Integrity, Seismic, Nuclear Power Plant Aging, etc.
(Attachment C, Pages 9-11).
Mr. Arlotto stated that the Integrity of Reactor Components Program consists of four major research elements. He discussed the planned accomplishments for FY 1990 in these areas and the impact of budget reduction proposed by the OMB (Attachnient C, Pages 12-15).
Reactor Vessel and Piping Integrity The planned accomplishments in this research area include the following:
- Determine relative radiation embrittlement sensitivity of typical reactor vessel support steels.
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- Complete studies of the effect of environmental loading conditions
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and thermal aging on stress-corrosion cracking of reactor inter-j nals.
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- Complete studies and provice data for upgrading ASME Sections III l
and XI.
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- Complete data analysis of Shippingport shield tank material to provide data on embrittlement of reactor pressure vessel supports.
Dr. Shewmon asked who is going to do the work on irradiation assisted stress corrosion cracking. Mr. Arlotto stated that Argonne National Laboratory is going to do this work..
Aging of Reactor Components The planned accomplishments in this area for FY 1990 include the follow-ing:
- Complete evaluation of methods for detecting degradation in check valves, breakers and relays, snubbers, and diesels.
- Develop criteria for NRC inspection, testing, and maintenance.
- Complete aging assessment of several systems such as service water, component cooling water, auxiliary feedwater, residual heat re-moval, etc.
- Evaluate monitoring techniques for risk sensitive areas.
' Recommend maintenance practices.
Mr. Arlotto discussed briefly the activities of the industry related to aging (Attachment C, Pages 16-20).
Dr. Siess asked about the coordination between the NRC Staff and indus-try in research activities related to aging. Mr. Arlotto stated that the NRC Staff is interacting with the ir.dustry on this matter through l
Huclear Management and Resources Ccur.cil (NUMARC).
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Stating that at a recent ASME Code meeting, he heard that there are plans to make changes to certain sections of the ASME Code that deal with plant life extension, Dr. Shewman asked about the nature of the changes expected to be made. Mr. Vora stated that the ASME Code Com-mittee is expected to make changes to take care of the inconsistencies between Section III and Section XI. He does not have all the details as to how they plan to make these changes. The Staff plans to deveYop regulatory guidance based on the revised ASME Code.
Dr. Kerr asked whether the Staff has performance or reliability stan-dards for use by the NRC inspectors in determining whether a specific component is performing satisfactorily. Mr. Arlotto stated tnat he does not have any answer to this question at this time.
Dr. Siess suggested that the Cognizant ACRS Subcommittees explore the issue raised by Dr. Kerr during the discussion of the aging research.
Dr. Siess asked whether the Staff is familiar with the study on aging performed by Japan. Mr. Vora stated that they are aware of the Japanese study.
Dr. Shewmon asked whether they plan to look at the cast iron casks under the High-Level Waste (HLW) research program. Mr. Arlotto stated that they do not plan to look at such casks under the HLW program. However, NMSS is reviewing the cast iron casks proposed by Japan.
RES is provid-ing some assistance to NMSS in reviewing these casks. He said he would be happy to brief Dr. Shewmon on what is being done and what has been learned so far on this matter.
4 Seismic Research The planned accomplishments in this area included the following:
- Pursue basic geological and seismological investigations to define source zones and their active structures.
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Meeting Minutes February 8, 1989 j
- Complete seismic Category I structures program and issue final reports.
- Address limitations of the seismic design margins program.
- Complete data collection and analysis of seismic response of components and piping systems.
Mr. Arlotto stated that the seismic research program is expected to be closed out in the early part of 1990s.
PREVENTING DAMAGE TO REACTOR CORES - DR. B. SHERON Dr. Sheron stated that this program is to obtain information for use in improving the understanding of both human and plant systems behavior during accidents and transients. He discussed briefly the major re-search elements under this program, and their scopes and associated funding (Attachment C, Pages 21 and 22).
Dr. Sheron stated that the work related to the development of thermal-hydraulic codes such as TRAC and RE! AP-5 is winding down. They do not plan to spend major efforts in this area.
He rentioned that these codes are being used by several foreign countries.
If these countries want furt.her development of these codes beyond what the NRC has planned, they have to provide necessary funding to the NRC for such development. He stated that they plan to put more enphasis in the human factors area.
Dr. Sheren state.d that the expected accomplishments in FY 1990 in the area of Preventing Danage to neactor Cores include the following:
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- Conclude analysis and testing of primary depressurization to minimize Direct Containment Heating (DCH) during station blackout.
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Safety Research Program Meeting Minutes February 8, 1989
- Complete evaluation of major in-vessel and ex-vessel accident management strategies.
- Develop and test a protocol for investigating root causes of human errors.
- Develop preliminary guidelines for training on the management of severe accidents.
Dr. Shewmon asked when the first IPE submittal is expected to be received by the NRC Staff from the utilities. Mr. Houston stated that they expect to receive the first submittal by the end of 1989.
Dr. Remick stated that recently he read an article about a test con-ducted by the Idaho National Engineering Laboratory (INEL) in which they linked up a computer with a simulator and ran RELAP and SCDAP codes on real time to demonstrate that the simulator capability can be extended to look at some of the accident management questions. He asked whether the Staff has additional information on this matter. Dr. Sheron responded that he was not aware of any such test conducted by INEL. The l
Staff has been looking into the feasibility of running codes such as RELAP and SCDAP by liking them to the plant analyzer but not to a simulator.
He said that he would try to find out the details of the demonstration test conducted by INEL.
Stating that some of the low-probability accidents are not identified by the PRAs as significant contributors to risk, Mr. Michelson asked whether such accidents are being considered under tne accident manage-ment program. Dr. SFeron stated that owing to budget ccr.straints low probability accidenis that are not ideratified by the PRAs as major contributors to risk are not cons 1dered.
1 Safety Research Program Meeting Minutes February 8, 1989 REACTOR CONTAINMENT PERFORMANCE AND PUBLIC PROTECTION FROM RADIATION-DR. B. SHERON Dr. Sheron stated that this program is intended to provide necessary information for use in:
- Improving the understanding of the severe reactor accident pheno-menolocy.
- Confirming the adequacy of safety margins in the current regulatory requirements.
- Identifying cost-effective options for safety improvements.
He stated that this I rogram includes six major research elements. He discussed the proposed funding levels for, and the scopes of, these research elements (Attachment C, Pages 22-24).
Dr. Sheron stated that significant accomplishments expected of this program in FY 1990 include the following:
- Complete the PRA for the LaSalle plant.
- Complete external events analysis for Sequoyah, Grand Gulf, and Zion for inclusion in NUREG-1150, " Severe Accident Risk: An Assessment for Five U.S. Nuclear Power Plants."
- Complete a comparison of the capabilities of the MELCOR severe accident source term analysis code against the capabilities of the earlier source term code package.
- Initiate experiments to investigate the behavior of hydrogen-air-steam mixtures at elevated ter.paratures.
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1 Safety Research Program Meeting Minutes February 8, 1989
- Determine why natural circulation was not observed in the TMI-2 accident.
'l Dr. Siess commented that they could spend an awful lot of money for research to get definitive answers to some of the questions. At some
'l point in time, the Staff has to decide how much of the information that i
they.really need to meet the safety goals and to protect the public
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Dr. Sheron stated that at present they do not have explicit criteria to determine how much information is good enough to predict the behavior of the plants under certain situations. Trying to come up with some sort of criteria for use in determining how accurately that they need to have answers to certain questions is one of the high priority items in his list.
.Dr. Siess asked how many of the questions that the Staff tries to get answers from research do not have an answer. Dr. Sheron stated that even though they have answers to certain questions, they do not know how accurate those answers are. Some of the research are to confirm the adequacy of these answers and their understanding of several issues.
In response to a question from Dr. Kerr relating to DCH issue, Dr.
Sheron stated that he believes that DCH is still an important issue and they plan to perform significant research to understand it b)tter.
Dr. Siess asked how would they know that they have understood the DCH issue clearly. Dr. Sheron stated that after the planned research on this matter is completed, they would evaluate the results and decide whether they are adequate.
If found inadequate and/or if the Commission wants more definitive information for use in making a decision on this issue, the Staff would plan additional research.
i Safety Research Program Meeting Minutes February 8, 1989 i
Stating that the core-concrete interaction test that was performed recently did not provide the correct information on certain important issues, Dr. Siess asked whether it was because of bad research or inadequate research. Dr. Sheron stated that it was not because of bad research; it was because of the deficiency in the computer code. The chemical reaction resulting from the interaction of Zirconium with molten core was not included in the code.
Dr. Siess commented that it would have been better to plan the research program at some sequences rather than to start everything at once. To plan a research with the intention of learning everything about everything is not a good philosophy. Dr. Sheron stated that a new research plan is being put together which he believes would take care of the concern' expressed by Dr. Siess.
Mr. Michelson stated that at present the Staff does not have a computer code to model the migration of heat and smoke; if they cannot model the migration of heat and smoke, he does not believe they can model the inadvertent actuation of fire protection systems inside a building. He asked whether the Staff plans to develop any tools to deal with the migration of heat and smoke issue. Mr. Murphy stated that PRAs could be modelled to provide a bounding estimate on this issue of propagation of heat and smoke. LaSalle PRA is modelled to provide such information.
RESOLVING SAFETY ISSUES AND DEVELOPING REGULATIONS - MR. W. HOUSTON Mr. Houston stated that this program is directed toward the development of the technical basis and related regulatory requirements needed to protect the health and safety of the public form the risk resulting from the generation of electricity and the manufacture, use, transport, and storage of nuclear fuel and other radioactive materials. This program l-also supports efforts to ensure that proposed Commission's regulations are adequate and that they are developed with an efficient and timely
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4 S.afety Research Program Meeting Minutes February 8, 1989 Mr. Houston stated that this program does not involve actual research.
He mentioned that there are four major elements included under this program.
Some of the anticipated accomplishments are as follows:
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- Prioritize about 24 new Generic Issues per year.
- Resolve about 12 Generic Issues in FY 1990 and resolve all Generic f
Issues already prioritized by the end of FY 1991.
- Complete reviews of about 10 early IPE submittals by joint RES, NRR teams with contractor assistance.
- In early FY 1990, complete a plan for implementing IPEs for ex-cernal events and issue Generic Letter and guidance to licensees.
- During FY 1989-1990, implement a plan to identify generic contain-ment vulnerabilities and potential improvements to correct these vulnerabilities.
- In 1990, complete the resolution of remaining control room habit-ability issues.
Dr. Siess stated that Revision 1 to RES Office Letter No. 3 Procedure and Guidance 'for the Resolution of Generic Issues, states that if there are no new requirements or guidance resulting from the resolution of a specific Generic Issue, the resolution package of that Generic Issue will be sent to the EDO for approval without an ACRS review of the adequacy of the resolution. He said that this procedure is not con-
- sistentwiththeprovisionsoftheMemorandumofUnderstanding(MCU) between the ACRS and the EDO.
In accordance with the MOU, the Staff should provide an opportunity to the ACRS for review of the proposed resolutions of Generic Issues irrespective of the nature of the re-l
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Safety Research Program Meeting Minutes February 8, 1989 1
solution. He mentioned that this matter was discussed previously with Dr. Speis and Mr. Minners and they agreed to provide proposed resolution packages for all Generic Issues so as to give an opportunity for the ACRS for review if it so desires.
When the list of Generic Issues l
identified by the ACRS was combined with that of NRC Staff, he was under the impression that the Staff will provide an opportunity to the ACRS to review the adequacy of the proposed resolutions. He suggested that the l
Staff provide the ACRS with copies of the proposed resolution packages l
for all Generic Issues irrespective of the Staff's decision whether to j
propose new requirements or not. After receiving such packages, 1
cognizant ACRS Subcommittees and/or the ACRS will decide which issues that they want to review in detail and the Staff will be notified of that decision. He suggested also that the Staff revise the RES Office Letter No. 3 to make it consistent with the MOU. Dr. Beckjord and Mr.
I Houston stated that they would look into this issue.
In response to a question from Dr. Beckjord, Dr. Siess stated that after receiving the resolution package for a specific Generic Issue, it would take about a month fc4 the ACRS Subcommittees and/or the ACRS to decide and notify the Staff whether they want to review that specific issue.
STANDARD 1ZATION AND ADVANCED REACTORS - MR. B. MORRIS Mr. Morris stated that there is no research involved in this area. The anticipated accomplishments in this area in FY 1990 include the follow-ing:
- Issue rules and reguhtory guides related to severe accident applications for new plants, f
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- Implement the Comission's Policy on Advanced Reactors.
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FUEL CYCLE, MATERIALS, TRANSPORTATION, AND SAFEGUARDS - MR. B. MORRIS Mr. Morris stated that there is no research involved in this area also.
Some of the expected accomplishments in this area are:
- Issue policy statements and/or rules for decommissioning of facil-ities and decontamination of lands, equipment, and materials
- Issue final policy statement on "Below Regulatory Concern"
- Issue final policy statement on Access Authorization at Nuclear Power Plants.
RADIATIONPROTECTIONANDHEALTHEFFECTS-MR.B.MORRg Mr. Morris stated that anticipated accomplishments in this area include the following:
- Identify and reduce uncertainties in radiation risk coefficients used for health effects estimates in PRAs and regulatory decisions.
- Identify areas where radiation protection standards need to be revised based on scientific information.
- Mcdify radiation protection regulations and guidance to be consis-tent with the Presidential Guidance on radiation protection re-quirements.
In response to a question from Dr. $1ess, Mr. Morris stated that they have been interacting with the Advisory Comittee on Nuclear Waste to get advice on several issues related to radiation protection and health L
effects, decommissioning, below regulatory concern, etc.
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SUBCOMMITTEE ACTION / FUTURE MEETING This meeting was intended to obtain an overview of the continuing and 1
proposed NRC Safety Research Program and Budget. The Subcommittee Chairman decided to provide a brief Subcommittee report to the full p
Committee on this matter during the February 1989 ACRS meeting. No further meeting of the Safety Research Program Subcommittee is scheduled at this time.
ACTIONS, ASSIGNMENTS, AGREEMENTS, COMMITMENTS, REQUESTS, ETC.
- There are no actions resulting from this meeting.
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- Dr. Siess requested that the RES Staff provide the ACRS with a copy of the report related to research work performed outside of the National Laboratories and the associated expenditures that is being prepared for use by the Nuclear Safety Research Review Committee (NSRRC). Dr. Beckjord agreed to provide that report after con-sideration by the NSRRC.
- Dr. Siess suggested that cognizant Subcommittees (Reliability Assurance, Materials and Metallurgy, and Mechanical Components),
when reviewing the Nuclear Plant Aging Research Program, explore the issue raised by Dr. Kerr as to whether the NRC Staff has performance or reliability standards for use by the NRC inspectors to detennine whether a specific component is performing satisfac-torily.
- Dr. Remick requested additional information from the RES Staff on a recent test conducted by INEL in which they linked up a computer with a simulator end ran RELAP and SCDAP codes on real time to demonstrate that the simulator capability can be extented to look at se:pe of the accident management questions. Dr. Sheron agreed to look into tiiis matter.
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I Safety Research Program Meeting Minutes February 8, 1989
- Dr. Siess stated that the procedures outlined in the RES Office Letter No. 3. Revision 1, regarding the resolution of Generic Issues are not consistent with the MOU between the ACRS and the l
EDO. He suggested that the NRC Staff provide the ACRS with copies of the proposed resolution packages for all Generic Issues L
irrespective of the Staff's decision whether to propose new l
requirements or not. After receiving the package, cognizant Subcommittees and/or the ACRS will decide whether to review it or not and notify.the Staff. Dr. Beckjord and Mr. Houston agreed to look into this matter.
- Mr. Arlotto committed to brief Dr. Shewmon or his Subcommittee on Materials and Metallurgy regarding what is being done on the cast-iron casks proposed by capan for transporting radioactive materials.
Dr. Siess thanked all participants and adjourned the meeting at 1:15 p.m.
NOTE:
Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 2120 L Street, N.W., Washington, D.C. 20006,(202)634-3273, or can be purchased from Heritage Reporting Corporation, 1220 L Street, N.W., Suite 600, Washington, D.C. 20005,(202) 628-4888.
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' LIST OF DOCUMENTS SUBMITTED T0.THE SAFETY RESEARCH PROGRAM SUBCOMMI11tE i
FEBRUARY 8, 1989 p
1.
Presentation Schedule.
2.
Portion of the " Green Book" dealing with the budget request-l (submitted to the Congress) for'FYs 1990-1991 NRC Safety Research Program.
3.
Portion of the Draft Copy of the NRC Five Year Plan document
-j dealing with the NRC Safety Research Program.
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Memorandum from V. Stello to Chaiman Zech regarding Revised FY.
1990 Budget Estimates (provides information on the impact of the OMB budget reduction) dated December 8, 1988.
5.
FIN-Level Budget Information, dated January 4, 1989.
6.
Revision 1 to RES Office Letter No. 3, Procedures and Guidance for I
the Resolution of-Generic Issues, dated December 21, 1988.
7.
Letter from E. Beckjord to N. Todreas, member of the National Safety Research Review Committee, dated December 20, 1988.
8.
Presentation Materials provided to the Subcommittee during the maeting.
ATTACHMENT A m.
E' REVISED.
2/1/89 PRESENTATION SCHEDULE ACRS SUBCOMMITTEE MEETING ON THE THE SAFETY RESEARCH PROGRAM
~7 FEBRUARY 8, 1989 ROOM P-114, 7920 NORFOLK AVENUE BETHESDA, MARYLAND ACRS CONTACT:
Sam Duraiswamy 301-492-9522 NOTE:
- Presentation Time should not exceed 50% of the Total Time allocated for a specific item. The remaining 50% of the time is reserved for the Subcommittee questions and answers by the Staff or its consultants / contractors.
- Number of copies of the presentation materials to be submitted to the Subcommittee:
25 copies.
TOTAL PRESENTATION ITEM PRESENTER TIME ACTUAL TIME 1.
EXECUTIVE SESSION 15 min 8:30 - 8:45 am 2.
RES PRESENTATION a.
Organization of the Eric Beckjord 10 min 8:45 - 8:55 am NRC Research Program b.
Overview of the RES 30 min 8:55 - 9:25 am Funding for FY 1987-FY 1990
' Research Program Support
- Technical Assistance Program Suppport Activities
- University Grants /
Contracts
- Personnel Salaries
- Other Expenses i
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- s Safety Research Program Meeting Presentation Schedule February 8,1989 C'
TOTAL PRESENTATION ITEM PRESENTER TIME ACTUAL TIME t
c.
Proposed FY 1990 research"and funding, impact of budgt!
reduction, and major contributions of research (past 5 years) in the following Areas:
- Integrity of Reactor Guy Arlotto 40 min 9:25 - 10:05 am Components, includ-ing Waste Management
- Preventing Damage to Brian Sheron 40 min 10:05 - 10:45 am Reactor Core
- BREAK ***
10 min 10:45 - 10:55 am
- Reactor Containment Brian Sheron 40 min 10:55 - 11:35 am Performance and Public Protection from Radiation
- Resolving Safety.
50 min 11:35 - 12:25 pm Issues and Develop-ing Regulations
- Developing Regu-Bill Morris lations, Advanced Reactors, etc.
- Radiation Protec-Bill Morris tion and Health Effects e.
Interaction with the Eric Beckjord, 20 min 12:25 - 12:45 pm Nuclear Safety Re-search Review Commit-tee; changes (if any) made in the direction and scope of the re-searchprogram(s)as a result of the recom-mendations of this Comnittee 3.
SUBCOMMI1 TEE REMARKS 15 min 12:45 - 1:00 pm
- ADJOURN ***
1:00"pm B-2
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INDUSTRY ROLE IN ENGINEERING RESEARCH AGING o.
NUMARC-NUPLEX ARE DEVELOPING A PROGRAM TO PROMOTE STABLE, TIMELY LICENSE RENEWAL PROCESS, AND COORDINATE UTILITY PLANT LIFE EXTENSION EFFORTS.
THE. PLANNED PROGRAM ELEMENTS INVOLVE:
COORDINATION TECHNICAL ISSUES LICENSING ISSUES CODES AND STANDARDS EACH PROGRAM ELEMENT HAS AN AGENDA 0F SUBELEMENTS AND TASKS THAT IMPLE-MENT THE NUPLEX PROGRAM OBJECTIVES.
- FY 89 COSTS -- UNKNOWN, BUT BELIEVED TO BE SIGNIFICANT
'o EPRI HAS A PROGRAM WHICH HAS THE OBJECTIVES OF ESTABLISHING AND MAINTAIN-ING AN OPTION FOR PLANT LICENSE RENEWAL, PROVIDING THE TECHNICAL BASES OF OPERATION BEYOND THE CURRENT LICENSE PERIOD, AND SUPPORTING THE SUBMIS-SION OF " LEAD PLANT" LICENSE APPLICATIONS TO THE NRC.
PROGRAM ELEMENTS INVOLVE:
(WITHDOE)COOPERATIVEPILOTPLANTSTUDIES-(W/PWR),ANDMONTICELLO (GE/BWR),OCONEE-(B&W/PWR),ANDCALVERTCLIFFS-(CE/PWR).
LWR COMPONENTS LIFE ESTIMATING METHODS.
PLEX SOURCE INFORMATION AND GUIDELINES.
i NATURAL VS ARTIFICIAL AGING OF COMPONENTS.
- FY 89 ESTIMATED COSTS -- $1.2 MILLION C-Ib
.~
o U.S. DEPARTMENT OF ENERGY HAS A PROGRAM WHOSE OBJECTIVES ARE TO DEVELOP THE TECHNOLOGY NEEDED TO ESTABLISH AND VERIFY LIFE EXTENSION AND LICENSE RENEWAL. _
PROGRAM ELEMENTS INVOLVE:
PHASE 1 (WITH EPRI): FEASIBILITYSTUDY(1985-1987); INCLUDES PILOT PLANT STUDIES
-0 PHASE 2 (WITH EPRI): DEVELOPMENT (1987-1991) INVOLVES TECHNICAL AND PROCEDURAL PROCESSES FOR REPLACEMENT, REFURBISHMENT, AND ENHANCE MONITORING IN THE SPECIFIC AREAS OF:
- PRV TECHNICAL EVALUATION
- SCREENING METHODOLOGY
- CABLE AGING
- PREDICTIVE PERFORMANCE PROGRAM' PHASE 3: VALIDATION (1991-1995); WILL INV'0LVE VERIFICATION OF THE LICENSE RENEWAL PROCESS.
- FY 89 ESTIMATED COSTS -- $5.0 MILLION o
NPP OWNERS GROUP PROGRAMS (IN CONJUNCTION WITH NSSS VENDORS AND ARCHITECT ENGINEERS) INCLUDES:
COMBUSTIONENGINEERINGANDCEREACTOROWNERSGROUP(CEOG)WITHA PROGRAM WHOSE OBJECTIVES ARE TO DETERMINE THE APPLICABILITY OF THE l
'SURRY 1 PLEX STUDY TO CE NUCLEAR STEAM SUPPLY SYSTEMS.
- PROGRAM ELEMENTS INCLUDE:
- REACTOR VESSEL AND VESSEL INTERNAL EVALUATION
- DESIGN AND APPLICABILITY COMPARISONS
- REACTOR COOLANT SYSTEM COMPONENTS
- ENVIRONMENTAL ISSUES.
C-17 - _ _ _ _ _ _ _ _ _ _ - _ _ - _
1 v-h.
I BOILING WATER REACTOR OWNERS GROUP (BWROG) HAS A PROGRAM WHOSE OBJECTIVES ARE TO ECONOMICALLY PROVIDE THE TOOLS THAT PARTICIPATING
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UTILITY MEMBERS WILL REQUIRE TO PRESERVE THE LIFE EXTENSION OPTION dTTHEIRNPPS.
- PROGRAM ELEMENTS INCLUDE:
- DESIGN BASIS DOCUMENTATION
- VARIANCE STUDY
- RECORDING TRANSIENT CYCLES
- COMPONENT EVALUATION METHODOLOGY WESTINGHOUSEANDWESTINGHOUSEOWNER'SGROUP(WOG)PLEXACTIVITYHAS AS OBJECTIVES THE ADDRESSING OF TECHNICAL ISSUES RELATED TO MATERIALS AND COMPONENTS IN CONSIDERATION FOR PLANT LIFE EXTENSION, THE TO PROVIDE TOOLS THri PARTICIPATING UTILITY MEMBERS WILL REQUIRE TO PRESERVE THE LIFE EXTENSION OPTION AT THIS NPPS.
- PROGRAM ELEMENTS INCLUDE:
- MONITORING OF SECONDARY SIDE STEAM GENERATOR BLOWDOWN CHEMIS-TRY j
- MONITORING OF MICR0 PROCESSOR ROD POSITION INDICATION SYSTEM
- MONITORING OF REACTCR PRESSURE VESSEL AND RPV INTERNALS
- MONITORING MAJOR PUMPS AND YALVES
- MONITORING PIPING
- MONITORING RPV SUPPORTS
- MONITORING MATERIALS
- MONITORING CABLES, ETC.
l IN RELATED PROGRAM, BALTIMORE GAS AND ELECTRIC COMPANY HAS i
COMPLETED A SERVICE LIFE EVALUATION OF THE CALVERT CLIFFS UNITS 1 AND 2 RPVS; PUBLIC SERVICE ELECTRIC AND GAS C-18 L
p COMPANY HAS INITIATED PLANNING FOR NUCLEAR PLANT EXTENSION OF ITS HOPE CREEK AND SALEM UNITS; AND ALSO PROCEEDING US THE NORTHERN STATES POWER LIFE EXTENSION PROGRAM FOR THE-TWO UNIT PRAIRIE ISL'AND NUCLEAR GENERATING STATION.
- FY 89 ESTIMATED COST -- $2.5 MILLION o
PROFESSIONAL CODES AND STANDARDS GROUPS THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) HAS A PROGRAM WHOSE OBJECTIVES ARE TO RECOMMEND OR DRAFT RULES AND REQUIREMENTS FOR MODIFYING SECTION XI TO ACCOMMODATE NUCLEAR PLANT LIFE EXTENSION m
AND TO COORDINATE RELATED ACTIVITIES OF OTHER CODES AND STANDARDS GROUPS:
- PROGRAM ELEMENTS INCLUDE ALL ASPECTS OF PLEX AS THEY RELITE TO ASME SECTION XI RULES FOR NPPS NND INVOLVE REVIEWS OF:
NUCLEAR UTILITIES NEEDS, INDUSTRY PHILOSOPHY AND PLANS PLEX PROGRAMS UNDERWAY RELATED R & D PROGRAMS NRC'S REGULATORY PHILOSOPHY.
INSTITUTEOFELECTRICALANDELECTRONICENGINEERS(IEEE)HASA PROGRAM WHOSE OBJECTIVES ARE TO INVESTIGATE THE CODES AND STANDARDS ASPECTS OF PLANT LIFE EXTENSION AS THEY PERTAIN TO ELECTRICAL EQUIPMENT.
- PROGRAM ELEMENTS INCLUDE:
IDENTIFICATION AND CATEGORIZATION OF TECHNICAL ISSUES EVALUATION OF AGE RELATED DEGRADATION ASSESSMENT OF THE ADEQUACY OF IEEE NUCLEAR STANDARDS IDENTIFICATION OF NEEDED R & D EFFORTS C-19 i l
~__ _ _ _ - _ - - - -
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DOCUMENTATION AND RECOMMENDATIONS THERE ARE ALSO PLEX ACTIVITIES BEING CARRIED OUT BY THE BNCS STEER-2
'ING COMMITTEE, THE ACI AND THE ANSI BUT TO A LESSER DEGREE.
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- FY B9 ESTIMATED COSTS -- UNDEFINED.
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