ML19260C928
| ML19260C928 | |
| Person / Time | |
|---|---|
| Issue date: | 01/14/1980 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | Gridley R GENERAL ELECTRIC CO. |
| Shared Package | |
| ML19260C929 | List: |
| References | |
| REF-GTECI-A-10, REF-GTECI-RV, TASK-A-10, TASK-OR NEDE-21821-02, NEDE-21821-2, NUDOCS 8002070141 | |
| Download: ML19260C928 (2) | |
Text
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UNITED STATE s q/ i NUCLEAR REGULATORY COMMISSION g q;l J
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January 14, 1980 Generic Task A-10 Mr. Richard Gridley, Manager Fuel & Services Licensing General Electric Company 175 Curtner Avenue San Jose, California 95215
Dear Mr. Gridley:
The NRC staff has completed its review of the General Electric Company proprie-tary topical report NEDE-21821-02 (BWR Feedwater Nozzle /Sparger Final Report, Supplement 2, August 1979). The report incorporates in full and replaces tne earlier documents NEDE-21821 (March 1978) and NEDE-218281-01 (January 1979) and includes changes to those documents fomarded by your letters dated March 1,1979 and March 20, 1979. You also incorporated into NEDE-21821-02 those changes in response to our recent comments regarding portions of NEDE-21 821 -01.
The staff's evaluation of these reports is enclosed.
The evaluation also implicitly includes the review of related non-proprietary documents NEDE-21821, NED0- 21821 -01, and NED0-21821-02A. NED0-21821-02A, which is the non-proprie-tary version of NEDE-21821-02, is to be issued after receipt of this letter and must incorporate this letter and the enclosed Safety Evaluation Report.
In the enclosed evaluation, any reference to an NEDE-document will apply to the corresponding non-proprietary NED0- document carrying the same number.
The earlier version of the sparger and nozzle report, NEDE-21840 (BWR Feed-water /Sparger Interim Report, February 1977) with supplements, is considered to have Deen superseded by the final report. Thus it will receive no formal evaluation and documentation.
As a result of our review, we have determined that the NEDE-21821-02 report, with the exception of Chapters 6 and 7 as discussed in the enclosed Safety Evaluation Report (SER), is acceptable for referencing in connection with licensing actions involving the removal of cladding and the installation of the General Electric final design sparger and thermal sleeve.
Inservice inspection and other additional plant-specific information noted in our SER should be addressed in applicant / licensee submittals.
The staff does not intend to repeat its review of the document when it appears as a reference in a particular licensing action.
Should regulatory criteria, regulations, codes or standards change such that any of our conclusions concerning NEDE-21821-02 are invalidatea, you will De notified and given the opportunity to revise ad resubmit the report (or suomit supplements or addenda) for review e.hould you desire.
1936 327 l '4 /
8002070 4
Mr. Richard Gridley January 14, 1980 In accoraance with established procedure, General Electric is requested to issue a revised version of NEDE-21821-02 to include the NRC acceptance letter together with SER. Both the proprietary and non-proprietary versions of this cocument must be referenced in future licensing actions.
If you have any questions concerning our evaluation of NEDE-21621-02, please contact this office.
Sincerely,
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-/'Darrell G. Eisenhut, A' ting Director c
Division of 0perating Reactors Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation Report 1936 328