L-83-265, Forwards Reactor Vessel Internals & Thermal Shield Plant Recovery Program Per 830419 Commitment to Provide Safety Assessment of Possible Effects on Fuel Performance Due to Loose Parts.No Fuel Problems Indicated at Facility
| ML17213B318 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/27/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| L-83-265, NUDOCS 8305020519 | |
| Download: ML17213B318 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION 'SYSTEM
('RIDS)
,AOCES.SION NBR; 83050205 DOC, DATE ~ 83/00/27 NO i R IZED:
NO FACIL:50"335 'St, Lucie Plant<
Uni~t 1~ Florida Power L Light Co+
AUTH,NAME AUTHOR AFFILIATION UHRIGg R,E.
Florida Power L Light Co,
>RE~C IP ~ NAME RECIPIENT AFFILIATION CLARKgR ~ A, Operating Reactors Branch 3
SUBJECT:
Forwards reactor vessel inter nals 8 thermal >shield plant recovery program per 830419 commi,tment 'to provide ~safety assessment of possible effects on fuel performance due to loose par,ts,No fuel problems indicated at facility>
DISTRIBUTION CODE A049S
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OR Submittal:
Thermal 'Shock to Reactor Vesse*l NOTES:
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FLORIDA POWER 8 LIGHT COMPANY April 27, I 983
'L-83-265 Office of Nuclear Reactor Regulation Attention:
Mr. Robert A. Clark, Chief Operating Reactors Branch PP3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Clark:
Re:
St. Lucie Unit I
Docket No. 50-335 Reactor Vessel Internals and Thermal Shield; Plant Recover Pro ram In our letter of April l9, l983 (L-83-230), Florida Power & Light committed to provide a Safety Assessment, to include the subject of "possible effects on fuel performance due to loose parts" (item D(2)).
As an enclosure to this letter, please find such assessment.
No objective evidence
,.to date is indicative of anomalous fuel failure or fuel problems since the first cycle of St. Lucie operation.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REU/DAC/cab cc: Harold F. Reis, Esquire Enclosure 8305020519 830427 PDR ADOCK 05000335
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PDR PEOPLE... SERVING PEOPLE
ST. LUCIE 't PLANT RECOVERY PLAN (4>>2JS>>
FAILURE ANALYSIS REMOVE DEBAIS FROM REACTOR VESSEL METALLURGICALANAL PREPARE FAILURE AJJALYSIS 0-15 ISI OF REACTOR VESSEL 4-14 5-12 THERMALSHIELD PREP METHODS 6 MOBILIZEAT SITE REMOVE CSB FROM VESSEL REMOVE THERMAL SHIELD FROM CSB 5-13 CORE SUPPORT BARREL PREPARE RFPAIR METHODS 6 IAOBILtZEAT SITE REPAIR CSB 5 SFT IN REACTOR VESSEL 5-15 RELOAD FUEL FUEL FUEL REMOVED FROL'I CONTAINMEIJT PREP FOR START-UP PLANT ON LINE 6 12 6-19 CONTINUOUS ASSESSMEtJT I, t5IC REVIE1V SAFETY ASSESSMENT 4
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