ML19290C402
| ML19290C402 | |
| Person / Time | |
|---|---|
| Issue date: | 03/29/1979 |
| From: | Angelo J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-17, REF-GTECI-SY, TASK-A-17, TASK-OR NUDOCS 8001110249 | |
| Download: ML19290C402 (5) | |
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9, y s ; a :979 Generic Task A-17 PROJECT:
Task A-17, Systems Interaction in Nuclear Power Plants
SUBJECT:
SUMMARY
OF MEETING WITH ATOMIC INDUSTRIAL FORUM, INC.
ON MARCH 14, 1979 Members of the NRC staff and its contractor, Sandia Laboratories, met with the comittee on systems interaction of the Atomic Industrial Forum, Inc. in Bethesda, Maryland on March 14, 1979 to present information on the status of the effort at Sandia Laboratories on systems interaction and to present the views of one NSSS vendor and one Architect-Engineering firm on the subject of systems interaction in nuclear power plants.
Persons who attended the meeting are listed in Enclosure 1 to this meeting summary.
Information on the work effort at Sandia Laboratories was presented by J. Hickman, W. Cramond, D. Carlson, D. Murphy, and S. Asselin, all of Sandia Laboratories.
An outline of their presentations is shown in.
J. Hickman summarized the objectives of the program and outlined the basic steps that are being taken to achieve the objectives.
W. Cramond presented information related to the development of plant and system fault trees for various plant operating modes and transient condi-tions. The initial effort has been concentrated in the development of fault trees for the hot shutdown mode of operation with a loss-of-offsite power transient as an initiating occurrence.
Fault trees for other condi-tions and transients are currently being developed.
D. Murphy presented information relating to the types of systems interac-tions that will be covered by the present study and the types of interac-tions that will not be covered by the study at this time. These characteris-tic kinds or types of interactions are listed in Enclosure 2.
Briefly,
the present study will include common energy or power source, common location, common flow paths, and comon support systems as interaction characteristics.
The study will not at this time include such common characteristics as common manufacturer, common installation, maintenance, calibration, test procedures, operator errors, or similiar component parts as the interactive characteristic.
As an aid to development of interaction potentials, Sandia Laboratories performed an analysis of Licensee Event Reports (LER's) that were included in the Zion Station Systems Interaction Study that was completed by Fluor Power Services, Inc. (formerly Fluor Pioneer, Inc.) and Commonwealth Edison Company.
The results of the analysis were presented by D. Murphy 1733 258 8 0 01110z4 7
. fM ' : 9 70 and are summarized in Enclosure 2.
The 67 LER's that were analyzed had been obtained by Comonwealth Edison Company from a population of 9000 LER's.
Briefly, about 26 of the 67 LER's represent events that would be covered by the scope of the task at the present time.
The methods of analyzing fault trees for potential interactions was presented by D. Carlson who also presented examples of qualitative criteria that could or may be used to evaluate the potential interac-tive sets of components. Basically, the fault trees will be evaluated by the SETS Code which will identify the unique combination of basic component faults that could result in the top event of a fault tree.
These combinations, (cut sets), will then be evaluated for interaction characteristics such as location, power source, lubrication, cooling, or other typical characteristics.
From this evaluation, a second cut set will be derived which contains the potentially interactive sets.
This second set will be further reduced by a more detailed investiga-tion of the interactive characteristics.
Finally, the third cut set will then be subjected to the qualitative criteria to obtain the final assessment.
These steps are shown in the summary sheets of Enclosure 2.
As preparation for the assessment of the Standard Review Plan (SRP) with regard to interactions, Sandia Laboratories conducted a preliminary ranking of sections of the review plan against NRR review organizational units with primary and secondary review responsibility. The information was presented by S. Asselin and is shown in Enclosure 2.
Sandia has identified 210 assignments of primary responsibility and 450 assignments of secondary responsibility.
These assignments are to 18 review branches.
S. Asselin also presented a matrix of safety systems, supportive systems, functional review areas, and the branches and sections of the SRP that discuss these interrelated subjects. This is shown on the last sheet of Enclosure 2.
Dr. Frank R. Hubbard of Combustion Engineering presented a NSSS vendor's view of systems interaction which is summarized in Enclosure 3.
The purpose of the presentation was to convince the NRC staff that potential systems interactions are presently being dealt with properly and to provide the NRC staff with information that is needed to convince the ACRS that this is so.
No specific details were presented on how the decision process is conducted that leads to a "yes" or "no" decision regarding systems interactions.
Dr. Hubbard stated that this is a rather lengthy and detailed process that could not be readily explained 1733 259
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. MAR 2 91W9 at such a brief infomation meeting.
Dr. Hubbard concluded that there was no demonstrated need for the industry or the NRC to expand the effort in the area of systems interaction.
T. Roell of Fluor Power Services, Inc. presented infomation on systems interaction from the viewpoint of his organization as an Architect-Engineer.
This information is sumarized in Enclosure 4.
Some of this material had been previously presented to the ACRS in the matter of its review of the BOPSSA?. standard B0P application.
- f. Roell described the process of design reviews for systems interac-tion that proceeds from systems listr, system definition and descrip-tion through logic diagrams to schematics, and identified where in this process the various technical groups provide input to the review process.
T. Roell also explained the reviewer checklist of items that are of significance to interaction potentials. He explained that his company makes use of such engineering aids as three-dimensional representations of the plant to verify location of equipment and uses operating information feedback and preoperational and startup testing, for example.
In concluding remarks by K. S. Canady, he stated that the objectives and scope of the NRC staff's efforts with regard to systems interac-tion was understood to be a task to confirm adequacy of our present review procedures as stated in the public forum by members of the NRC staff.
We do not at this time find any reason to disagree that design procedures and review procedures are acceptable.
We restated that our purpose in conducting this task was in response to the concerns of the ACRS, and that we fully intend to conduct this task in a disciplined manner using the methods described by Sandia Laboratories.
Recent developments with regard to the task were explained.
These developments included the action D) the Commissioners to include this task with 21 other gercric issue tasks that were reported to the Congress as " Unresolved Safety h:.>es," the action by us to extend the completion of Phase I of this isk to September 1979 instead of the orignial date of May 1979, and t w actior, to further restrict the task to PWR's and not carry BWR's a; 'Je preseat time.
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John Angelo, Task Manager Generic Task No. A-17 Division of Project Management
Enclosures:
As Stated cc:
See next page 1733 260 D**D
'3\\[g' ShM ow a
MAR 9 079 cc:
Mr. K. S. Canady Duke Power Company P. O. Box 33189 422 South Church Street Charlotte, North Carolina 28242 Mr. F. Stetson Atomic Industrial Forum 7101 Wisconsin Avenue Washington, D. C.
20014 Mr. Jack Hickman Sandia Laboratories Division 4412 P. O. Box 5800 Albuquerque, New Mexico 87185 Mr. Mark Wisenberg Tennessee Valley Authority 303 Power Building Chattanooga, Tennessee 37401 1733 261
ENCLOSURE 1 GENERIC TASK A-17_
ATTENDANCE LIST MEETING WITH THE ATOMIC INDUSTRIAL FORUM, INC.
ON MARCH 14, 1979 ORGANIZATION NAME Duke Power Company K. S. Canady Fluor Pov:er Services, Inc.
T. L. Roell Combustion Engineering H. Corcora.
Combustion Engineering F. Hubbard Commonwealth Edison Company T. Tramm Houston Lighting & Power Company R. Russell Babcock & Wilcox Company G. Brazill Westinghouse Electric Corporation F. Gigliotti General Electric Company N. Shirley Bechtel Power C. Judd H. Filacehionis Bechtel Power W. H. House, 11 Bechtel Power Battelle Northwest Lab Y. H. Sun Sandia Laboratories J. Hickman Sandia Laboratories W. Cramond Sandia Laborabories D. Carlson Sandia Labora 'ies D. J. Murphy Sandia Laboratories S. Asselin NRC J. Angelo
'G C A. Oxfurth NRC L. Lois f.RC C. Liang NDC H. Li NRC G. Bennett tiPC A. Buhl NRC H. Schierling NRC V. Benaroya NRC
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- 0. P. Chopra NRC W. A. Paulson NRC P. R. Matthews NRC J. Zwolinski NRC
.E. C. Marinos NRC .J. A. Norberg NRC R. Major NRC R. L. Wright NRC T. Scarbrougt NRC D. F. Ross NRC F. Rosa}}