ML17214A590

Forwards Final Rept for Plant Recovery Plan Re Reactor Vessel Internals & Thermal Shield Conclusions & Findings. Schedule Changes Reevaluation of D (5) Integrity & Stability of Internal & D (6) Conclusions & Findings Encl

ML17214A590
Person / Time
Site:	Saint Lucie
Issue date:	12/14/1983
From:	Williams J FLORIDA POWER & LIGHT CO.
To:	John Miller Office of Nuclear Reactor Regulation
References
L-83-582, NUDOCS 8312190151
Download: ML17214A590 (6)

Text

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ACCESSION 8312190151 DOC ~ DATE! 83/12/10 NOTARIZED! NO DOCKET' FACIL:;50 335 St>'Lucie'Planti Unit 1~ Florida Power 8 L'ight Co> 05000335 AUTH, NAME AUTHOR'FFILIATION HILLIAMSgJ ~ N ~ Fl or ida>> Power 8 Light Co,

'HECIP ~ NAMk RECIPIENT AFFILIATION MILLER'g J ~ R ~ Oper~ting, Reactors Branch 3 SUBJECT; Forwards final rept for plant r ecover y .plan r e reactor vessel internals 8, thermal shield conclusions 8 findings>

Schedule reevaluation re'D (5) integer ity 8 stability of internal 8 D (6) conclusions

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FLORIDA POWER & LIGHT COMPANY December l4, I 983 L-83-582 Office of Nuclear Reactor Regulation Attention: Mr. James R. Miller, Chief Operating Reactors Branch jI3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Miller:

Re: St. Lucie Unit I Docket No. 50-335 Reactor Vessel Internals and Thermal Shield; Plant Recovery Program - Final Report (Inte rit and Stabilit of Internals - Conclusions and Findin s Our letters of April l9, l983 (L-83-230) and October 25, l983 (L-83-53I), committed to provide "Integrity and Stability of Internals - Conclusions and Findings" pursuant to the St. Lucie Unit I Plant Recovery Program (Items D(5) and D(6). from our L-83-230),

tentatively by December I 5, I 983.

Schedule reevaluation in the recovery operation has suggested that the above referenced submittal date should be re-scheduled. As discussed with Mr. Don Sells of your office, these dates are:

Items (Desi nation from Our A ril l9 l 983 letter L-83-230 Tentative Submittal Date D(5) Integrity and Stability of Internals Week of January 9, I 984 (Presentation, if necessary, the week of Jan. 23, l984)

D(6) Conclusions and Findings Week of January 9, l984 (Presentation, if necessary, the week of Jan. 23, l984)

Should any questions arise, please contact us immediately.

Very truly yours, Q J. W. Williams, Jr.

Vice President Nuclear Energy ggig190151 831214 I J WW/DAC/cab PDR ADOCK 05000335 P PDR Enclosure cc: Harold F. Reis, Esquire 'I o PEOPLE... SERVING PEOPLE

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ST. LUCIE 1 PLANT RECOVERY PLAN (REVISIONS)

FAILURE ANALYSIS t REMOVE DEBRIS FROM REACTOR VESSEL METALLURGICALANAL. PREPARE FAILURE ANALYSIS REPORT TO NRC ID 25 ISI OF REACTOR VESSEL 4-14 5-24 REMOVE CSB FROM VESSEL PREP METHODS REMOVE THERMAL a MOBIUZE AT SITE SHIELD FROM CSS 7-25 THERMAL SHIELD 4-4 5-12 PREPARE REPAIR REPAIR CSB: a SET METHODS a MOBILIZE AT SITE N REAC'TOR VESSEL CORE SUPPORT BARREL e-l 7 MEETING WITH NRC ON FAR.ORE MECHANISM ANALYSIS RESULTS MEETNG WITH NRC FUEL FUEL REMOVED FROM CONTAINMENT PLANT ON LNE ONPROPOSED FNAL

I8388JI 388 REPORT CONTENT RELOAD FNAL EXXON RELOAD SUBMITTAL POSTWUG REMOVAL FNAL FUEL PREP FOR NDE INSPECTION RESULTS STARTS CONTNUOUS ASSESSMENT a I4IC REVIEW '-27

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SAFETY ASSESSMENT 4 I 4-12 4-25 5-3 5-23 5-15 Q-20 Q-22 1 1-10 WIC 1I8 4/54*

NRC MEETING-PRELIMNARYASSF SSMENT + MEETING WITH NRC ON LPMS a EXCORE MEETNG WITH NAG~NCLUDING SUBMITTAL OF DRAFT FINAL REPORT&

INTEGRITY a STABILITYOF

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ON. THERMAL SHIELD NRC MEETNG-RECOVERY PLAN/PTS CONSIDERATIONS AV NTERNALS, CONCLUSIONS a FINDINGS DETECTOR DATA REVIEW Ry NTERNALS NSPECTION RESULTS.

PRESSURE/1EMPERATUAE ExxoN RELDAD a REPAIR. AND ANALYSIS OwtA OPERATNG CURVE GAMMA HEATNG CB ~STSICI85 MANAGEMENT l

ACCEPTABalTY REMEW TO NRC SUBMITTAL TO NAC 0 ~ 8 8888 4 EARLIEST ESTILIATED 88 14 8888

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