ML19340B715
| ML19340B715 | |
| Person / Time | |
|---|---|
| Issue date: | 10/28/1980 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Sherwood G GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19340B716 | List: |
| References | |
| NUDOCS 8011110745 | |
| Download: ML19340B715 (2) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION y \\ ;e g
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OCT 2 81980
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General Electric Company ATTN: Dr. G. G. Sherwood, Manager Safety and Licensing 175 Curtner Avenue San Jose, California 95114
Dear Dr. Sherwood:
SUBJECT:
ACCEPTANCE FOR REFERENCING TOPICAL REPORT NEDE-24057 P ASSESSMENT OF REACTOR INTERNALS VIBRATION IN BWR/4 AND BWR/S PLANTS The Nuclear Regulatory Commission has completed its review of the General Electric Company Licensing Topical Report NEDE-24057 " Assessment of Reactor Internals Vibration in BWR/4 and BWR/5 Plants," including the Amendments Nos. I and 2.
The topical report provides an introduction as to the need for the test program; a summary of the report; a description of the reactor internals involved in the program; a description of the test including its scope, sensor types and locations, test conditions for preoperational, precritical, and startup tests as well as flow modes; inspection program; and data acquisition system; the results of the vibration measurements; the analysis and discussion of the tests; and the program conclusions. The summary of our evaluation is attached.
As a result of our review, we generally concluded: that the overall vibration assessment programs are adequate and the inspection results are satisfactory; that the inspection of internals immediately following the completion of preoperational tests is acceptable; that the steam dryer assemblies are adequate to sustain flow induced vibration expected in service; that the accessibility for inspection is acceptable; that for plants which are closely similar to the valid prototypes, confirmatory tests consisting only of non-instrumented preoperational testing and subsequent inspection of internals are acceptable; that the confirmatory test program using instrumented vibration monitoring during hot startup test without inspection in lieu of confirmatory preoperational flow test with inspection is acceptable. Specific conclusions as to prototype and non-prototype 1;lant classifications and the specific limitations are as stipulated in the Regulatory Position section of the attached Topical Report Evaluation.
We find the topical report NEDE-24057(P) (proprietary version) and NED0-24057(NP) (non-proprietary version) and their two supplements -1 and -2, are acceptable for referencing in the operating ifcense application of the BWR/4 and BWR/5 plants listed in table 1 to 5 of the 80212yo y C
Dr. G. G. Sherwood
-2 OCT 2 81980 attached Topical Report Evaluation, provided conditions established for the specific plant as delineated therein are met in its implementation of Regulatory Guide 1.20, " Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing."
In order to satisfy the conditions specified in the Topical Report Evaluation, additional plant specific information shall be submitted for NRC review on a case by case basis.
Pending the availability of test results, we are unable to conclude that the internals of the Chinshan 1 can be referenced as the valid prototype for licensing applications.
As for the internals in Bailly, a similarly constructed program as for Tokai 2 is acceptable only if the program and test results of the Chinshan internals, BWR/4-201 " size prototype becomes available and is accepted by NRC.
In lieu of this, additional measurements comparable to the BWR/4 prototype programs may be implemented for qualifying Bailly internals as the prototype of the BWR/4-201" size internals.
We do not intend to repeat the review of the safety features described in the topical report and found acceptable in the attachment. Our acceptance applies only to the features described in the topical report and under the conditions discussed in the attachment.
In accordance with established procedure, it is requested that General Electric Company publish an approved version of these reports, proprietary and non-proprietary, within three months of receipt of this letter. The revisions are to incorporate this letter and the attached topical report evaluation following the title page and thus just in front of the abstract.
The report identifications of the approved reports are to have a -A suffix.
Should Nuclear Regulatory Commission criteria or regulations change such that our conclusions as to the acceptability of the repnrt are invalidated, General Electric Company and/or the applicants referencing the topical report will be expected to revise and resubmit their respective documen-tation or submit justification for the continued effective applicability of the topical report without revision of their respective documentation.
Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing