ML17340B143

Part 21 Rept Re Review of All Deficiency Repts Submitted to NRC for 770810-800731.Forwards LERs Determined Reportable Under 10CFR21

ML17340B143
Person / Time
Site:	Turkey Point
Issue date:	03/31/1981
From:	Schmidt A FLORIDA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17340B144	List: ML17340B143 ML17340B145 ML17340B146 ML17340B147 ML17340B148 ML17340B149
References
REF-PT21-81-411-000 PT21-81-411, PT21-81-411-000, NUDOCS 8105050037
Download: ML17340B143 (4)

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FLORIOA POWER 4 LIGHT COMPANY March 31, 1981 PRN- L I-81-156 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Re: RI:VLB 50-250/50-251 Ref: L-80-135, May 1, 1980 Florida Power 5 Light Company committed to perform a review of all reports submitte'd to the NRC pursuant to 10CFR50.55(e) and Facility .Technical Specifications (LER's) for the period between August 10, 1977 and July 31 1980 in the referenced correspondence. This letter presents the results of that review. For each LER determined to be reportable under the requirements of 10CFR21, we have attached a copy of the original LER or RO and summarized the results of our evaluation.

The following LER's have been determined to be reportable under 10CFR21:

(1) LER 250-78-20 (5/26/79), Diesel Generators The design error which resulted in overheating and subsequent-failure in the exiter power transformer was a departure from the technical requirements and could have caused the failure of a safety-related component to perform its safety function.

(2) (a) LER 251-79-03 (3/24/78), Appendix K, ECCS Evaluation Model (b) LER 250-78-02 (3/24/78),- Appendix K, ECCS Evaluation Model (c) LER 250-79-33 (11/1/79), LOCA Analysis (d) LER 250-79-35 (11/9/79), ECCS Analyses - Potential Nonconservatism (e) LER 250-80-11 (5/25/80), ECCS Analysis These events were similar in that they all entailed an analytical error which could have contributed to exceeding a safety limit (peak PEOPLE... SERVING PEOPLE

clad temperatures), and represented a noncompliance with Title 10 Code of Federal Regulations relating to substantial safety hazards. This deficiency in safety related analyses resulted in a major deficiency. in design criteria and required substantial evaluation to meet the criteria and bases stated in the SAR.

(3) LER 251-78-09 (8/31/78), Hydraulic Snubbers The failure of the hydraulic snubbers to pass the testing requirements was a departure from the technical requirements that were essential to prevent a pipe rupture in the Hain Steam line from affecting the AFll system. This could have resulted in a major deficiency in the design criteria and caused a safety related component to fail to perform its safety function.

These events have been reviewed for generic applicability, and have-been found to be unique events to the nuclear plants within the FPL system.

Very truly yours, A . Schn >dt Vice President Power Resources JEth/mbd Attachments cc: Hr. H.F. Reis, Esquire