L-83-582, 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

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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

>>'4 REGULATOR NFORMATION DISTRIBUTION "S EM (RIDS)

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8312190151 DOC ~ DATE! 83/12/10 NOTARIZED!

NO FACIL:;50 335 St>'Lucie'Planti Unit 1~ Florida Power 8 L'ight Co>

AUTH,NAME AUTHOR'FFILIATION HILLIAMSgJ ~ N ~

Fl or ida>> Power 8 Light Co,

'HECIP ~ NAMk RECIPIENT AFFILIATION MILLER'gJ ~ 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 8, findings date changes encl

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BOX 14000, JUNO BEACH, FL 33408

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FLORIDAPOWER & LIGHTCOMPANY 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 J WW/DAC/cab Enclosure ggig190151 831214 I

PDR ADOCK 05000335 P

PDR cc: Harold F. Reis, Esquire

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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 ID25 ISI OF REACTOR VESSEL 4-14 REMOVE CSB FROM VESSEL 5-24 THERMALSHIELD 4-4 PREP METHODS a MOBIUZE AT SITE REMOVE THERMAL SHIELD FROM CSS 5-12 7-25 CORE SUPPORT BARREL PREPARE REPAIR METHODS a MOBILIZEAT SITE REPAIR CSB: a SET N REAC'TOR VESSEL e-l 7 MEETING WITH NRC ON FAR.ORE MECHANISM ANALYSISRESULTS MEETNG WITH NRC ONPROPOSED FNAL REPORT CONTENT PLANT ON LNE FUEL

I8388JI 388 FUEL REMOVED FROM CONTAINMENT RELOAD FUEL PREP FOR STARTS FNAL EXXON RELOAD SUBMITTAL POSTWUG REMOVALFNAL NDE INSPECTION RESULTS

'-27 CONTNUOUS ASSESSMENT a I4IC REVIEW SAFETY ASSESSMENT 4 I 4-12 4-25 5-3 MEETING WITH NRC~

ON LPMS a EXCORE DETECTOR DATA REVIEW 5-23 5-15 Q-20 Q-22 1 1-10 WIC1I8 MEETNG WITH NAG~ SUBMITTALOF DRAFT FINALREPORT&

ON. THERMAL SHIELD NCLUDING INTEGRITYa STABILITYOF Ry NTERNALS AV NTERNALS, CONCLUSIONS a FINDINGS NSPECTION RESULTS.

REPAIR. AND ANALYSIS NRC MEETING-PRELIMNARYASSF SSMENT+

NRC MEETNG-RECOVERY PLAN/PTS CONSIDERATIONS PRESSURE/1EMPERATUAE OPERATNG CURVE ACCEPTABalTY REMEW TO NRC ExxoN RELDAD a GAMMAHEATNG SUBMITTALTO NAC CB

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