ML20134E337
| ML20134E337 | |
| Person / Time | |
|---|---|
| Issue date: | 10/29/1996 |
| From: | Collins T NRC (Affiliation Not Assigned) |
| To: | Curet H SIEMENS POWER CORP. (FORMERLY SIEMENS NUCLEAR POWER |
| Shared Package | |
| ML20134E293 | List: |
| References | |
| TAC-M95745, NUDOCS 9611010126 | |
| Download: ML20134E337 (1) | |
Text
. _ _ _ . - , - . _ _ _ .
., e p tM4 9 g4 % UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001
% # October 29, 1996 Mr. H. D. Curet !
Manager. Product Licensing l Siemens Power Cor) oration 2101 Horn Rapids Road P.O. Box 130 '
Richland. Washington 99352--0130 I
Dear Mr. Curet:
SUBJECT:
ACCEPTANCE FOR REFERENCING OF TOPICAL REPORT EMF-96-029(P).
VOLS. 1 AND 2. " REACTOR ANALYSIS SYSTEM FOR PWR'S" (TAC NO. M95745)
We have reviewed the topical report submitted by Siemens Power Corporation (SPC) by letter dated May 8. 1996. We find the report to be acceptable for referencing in license applications to the extent specified and under the limitations stated in the enclosed safety evaluation. The evaluation defines the basis for accepting the report.
We will not repeat our review of the matters described in the report and found acceptable when the report appears as a reference in license applications. l except to ensure that the material presented applies to the specific plant i involved. Our acceptance applies only to the matters described in the report. i In accordance with procedures established in NUREG-0390. " Topical Report l
Review Status." the NRC requests that SPC publish an accepted version of the l report within three (3) months of receiving this letter. The accepted version l shall incorporate this letter and the enclosed evaluation between the title page and the abstract and include an "-A" (designating accepted) after the ;
report identification symbol.
If the NRC's criteria or regulations change such that its conclusions as to the acceptability of the report are invalidated. SPC and the applicants referencing the topical report should revise and resubmit their respective i documentation, or submit justification for the continued applicability of the ,
topical report without revising their respective documentation. 1 Sincerely.
Timothy E. Collins. Acting Chief '
Reactor Systems Branch Division of Systems Safety and Analysis
Enclosure:
EMF-96-029(P) Safety Evaluation '
9611010126 961029 i PDR TOPRP EMVEXXN /
C PDR j
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