ML20002D282
| ML20002D282 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/15/1981 |
| From: | Delgeorge L COMMONWEALTH EDISON CO. |
| To: | Bournia A Office of Nuclear Reactor Regulation |
| References | |
| NEDO-24057A, NUDOCS 8101200245 | |
| Download: ML20002D282 (2) | |
Text
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'x Commonwealth Edison l
) One First National Plaza, Chicago, litinois i
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January 15, 1981 4
g Mr. A. Bournia Licensing Branch No.1 JAN 191981 = bf8
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Division of Licensing ca me,e U.S. Nuclear Regulatory Commission
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Washington, DC 20555 9
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Subj e ct :
LaSalle County Station Units 1 and 2
" Assessment of Reactor Internals Vibration in BWR/4 and BWR/5 Plants" Licensing Topical Report NEDO-24057A
Dear Mr. Bournia:
Enclosed are three (3) copies of the subject report dated De cembe r, 1980 for your information.
The NRC's evaluation of this document is included in the report in the form of a letter of acceptance from NRC's R. L. Teoesco to G. G. Sherwood..at.GE,, dated October 28, 1980.
This acceptance uses Reg. Guide 1.20 Criteria and acknowledges the dominance of vibration resonses during pre-operatior.1 tests over those existing during normal plant operating conditions.
It also acknowledges the acceptability of successful pre-operational tests and inspections at three prototype plants, including Tokai 2 wich is the LaSalle prototype BWR-5.
LaSalle test results for pre-operational test PT-PV-101 have been accepted by Commonwealth Edison and are a part of the permanent records at the station.
They may be audited by Region III or other NRC auditors during a site visit.
Confirmation of satisf actory performance of reactor internals including the modified feedwater spargers, thermal sleeves for ECCS nozzles, and the steam separators, is included in the Vibration Measurements of Start-up Test No. 34.
That test sequence includes three power-levels / core flow conditions to cover the operations regime of the reactor equipment.
Again, this confirmation test objective conforms to Reg. Guide 1.20 requirements.
The results of this start-up confirmatory test on LaSalle Reactor internal vibrations will also be a part of the permanent station records.
Audit of that record can be performed after November 1981.
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o Mr. A. Bournia January 15, 1981.
Page 2 Although no outstanding issue currently exists on this subj e ct, it was judged appropriate to transmit this report to your attention for-information.
In the event you have any questions, please direct them to this of fice.
Very.truly yours, J,-
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L. O. DelGeorge Nuclear Licensing Ad inistrator Atta chment cc:
NRC Resident Inspiector - LSCi (w/att.)
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UNITED STATES NUCLEAR REGULATORY COMMISSION
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Dr.. G. G. Sherwood, Manager L
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Dear Dr. Sherwood:
SUBJECT:
ACCEPTANCE FOR REFERENCING TOPICAL REPORT NEDE-24057 P ASSESSMENT OF REACTOR INTERNALS VIBRATION IN BWR/4 AND BWR/5 PLANTS The Nuclear Regulatory Commission has completed its review of the General Electric Company Licensing Topical Report NEDE-04057 " 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 sumary 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 acceptab.le; that for
. plants which are closely similar to the valid prototypes, confimatory 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 plant classifications and the specific limitations are as stipulated in the Regulatory Position section of the attached Topical Report Evaluation.
We find the topical repor'. NEDE-24057(P) (proprietary version) and NED0-2405/(NP) (non-proprietary version) and their two supplements -1 and -2, are acceptable for referencing in the operating license application of the BWR/4 and BWR/5 plants listed in table 1 to 5 of the f
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Dr. G. G. Sh:rwood
-2 OCT 2 81980 atte.hed Totical 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.
7 In accordance with established procedure, it is requested that General hfM Electric Company publish an approved version of these reports, proprietary 4b-i 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 report are invalidated, General Electric Company and/or the arplicants 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 repo'rt without revision of their respective documentation.
Sincerely, l
Robert L. Tedesco, Assistant Director for Licensing Division of Licensing i
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NEDO-24057A Class l December 1980 LICENSING TOPICAL REPORT ASSESSMENT OF REACTOR INTERNALS VIBRATION IN BWR/4 AND BWR/S PLANTS J. D. GM C. S. Duckwald D. G. Umble Approved:
"[tb /11 Approved:
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J. B. Carr, Manager J. Jacobson, Manager Reactor Servicing Reactor Design and Auxiliaries Design
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DUPLICATE DOCUMENT Entire document previously uENT. GENE R AL ELECTRIC COMPANY entered into system under:
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i DISCLAIMER OF RESPONS184WTY This document was prepared by or for the General E!3ctric Company. Neither the General Electric Company nor any of me contributors to this document:
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Makes any warranty or representatx1, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this docu-ment, or that the use of any information disclosed in this document may not infrutge privately owned rights; or B. Assumes any responsibility for liability or damage of any kind which may result from the use of anyinformation disclosedin this document.
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