ML19296A840
| ML19296A840 | |
| Person / Time | |
|---|---|
| Site: | Sterling |
| Issue date: | 01/10/1980 |
| From: | Robert Carlson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Petrick N STANDARDIZED NUCLEAR UNIT POWER PLANT SYSTEM |
| References | |
| NUDOCS 8002190123 | |
| Download: ML19296A840 (1) | |
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Docket No. 50-485 Jia 1 C 27 SNUPPS ATTN: Nicholas A. Petrick 5 Choke Cherry Road Rockville, Maryland 20850 Gentlemen:
Subject:
Rod Drop Analysis (Your letter of December 14, 1979)
Thank you for your letter, referenced above, which forwarded an interim report pursuant to 10 CFR 50.55(e) regarding the subject matter.
Your report will be reviewed and evaluated, and should we require additional information concerning this matter prior to receipt of your final resolution, we will contact you.
Your cooperation with us is appreciated.
Sincerely, i
t. Carlson, Chief Reactor Construction and Engineering Support Branch cc:
K. V. Seyfrit, Director, RIV J. G. Keppler, Director, RIII 8002100
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Y SNUPPS Standardized Nuclear unit Power Pfant System 5 Choke Cherry Road Rockville, Maryland 20850 f 301) 8694010 December 14, 1979 SLNRC 79-22 File: 0491.10.2 SUBJ: Rod Droo Analysis Mr. Boyce Grier Director, Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Comission 631 Park Avenue King of Prussia, Pennsylvania 19406 Docket Nos:
STN 50-482, STN.50-483, STN 50-485, STN 50-486 Ref:
- 1. SNUPPS letter to NRC Region I, SLNRC 79-5, dated April 26, 1979, Rod Drop Safety Analysis
- 2. Westinghouse letter (T.M. Anderson), NS-TMA-2167, to USNRC (A.
Schwencer), dated November 15, 1979, same subject.
Dear Mr. Grier:
On November 16, 1979, SNUPPS informed the Nuclear Regulatory Commission, Region I Office of Inspection and Enforcement, of a potential deficiency involving the dropped rod safety analysis.
The information was communicated by telechone to Mr. Bateman of your staff pursuant to 10 CFR 50.55(e).
Reference I withdrew an initial notification of a reportable deficiency con-cerning the dropped rod analysis on the basis of Westinghouse studies for four loop plants.
Reference 1 also indicated that the matter would be further examined.
As a result of that ongoing review, Westinghouse determined that the original concern may, in fact, involve four loop plants such as SNUPPS.
Reference 2 described the specific concerns with the single and multiple rod drop analyses.
SNUPPS will continue to pursue the resolutien of this matter and will address it in a revision to the SNUPPS FSAR.
A permanent resolution of the concern is expected by mid - 1980.
However, should a permanent fix not be approved prior to start-up of the first SNUPPS plant, procedural changes can be adopted as an interim solution.
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SLNRC 79-22 File: 0491.10.2 Page 2 As further information is available on this matter, SNL, will inform s
the NRC.
Ver truly yours,
<w \\C Nicholas A. Petrick RLS/yt cc:
Mr. James G. Keppler, Director, Region III, USNRC Mr. Karl V. Seyfrit, Director, Region IV, USNRC Mr. Victor Stello, Jr., Director, Office of Inspection and Enforcement, USNRC, Washington, D.C.