ML17214A160

Discusses Updated Submittal Dates for Reactor Vessel Internals & Thermal Shield Recovery Programs as Followup to Safety Assessment Provided at 830603 Meeting

ML17214A160
Person / Time
Site:	Saint Lucie
Issue date:	06/07/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Clark R Office of Nuclear Reactor Regulation
References
L-83-345, NUDOCS 8306100087
Download: ML17214A160 (6)

Text

REGULA'la<<Y 'INFORMATION OISTRIBUTIOlYSTEM (RIBS)

'AOCBSSION NBR:8306100087 DOO,DATE: 83/06/07 NOTARIZED; NO DOCKET FACIL:50 335 "St. Lucie Planti Uni<<t'i Florida Power L Light Co ~ 05000335

'AUTH ~ NAME AUTHOR AFFILIATION UHRIGi R, E ~ 'F 1 orida '.Power L Light Co ~

'RECIP NAME RECIPIENT AFFILIATION

<<CLARKE'RE AD Operating Reactors Branch 3

SUBJECT:

'Submits updated Isubmittal dates for .reactor vessel internals L thermal Ishield recovery programs--=as followup to lsafety assessment provided at 830603 meetings DISTR'IBUTION CODE: A001S <<COPIES <<RECEIVED:LTR:ENCL, SIZE!,

.TITLE: OR Submittal". General Distribution NQTES:

-RECIPIENT <<COPIES RECIPIENT <<COPIES ID 'CODE/NAME LTTR ENCL ID CODE/NAME- LT'TR ENCL NRR ORB3 BC 01 7 7 INTERNAL! ELD/HDS2 1 0 NRR/DE/MTEB 1 1 NRR/DL DIR 1 1 NRR/DL/ORAB 1 0 1ETB 1 1 NRR/DS I/RAB 1 1

'ffEG F I LE 00 1 1 RGN2 1 1 EXTERNALG ACRS 09 i6 LPDR 03 1 1 NRC PDR -02 1- 1 NSIC 05 1 1 NT I' 1 1

<<<<TOTAL NUMBER OF COPIES REQUIRED: L'TTR 25 ENCL 23

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0 FLORIDA POWER & LIGHT COMPANY June 7, l983 L-83-345 Office of Nuclear Reactor Regulation Attention: Mr. Robert A. Clark, Chief Operating Reactors Branch 7/3 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 Recovery Program - Loose Parts Monitor and Excore Detector Meetin (June 3 l 983)

In a meeting held on June 3, l983, Florida Power and Light Company provided you with a Safety Assessment which included:

"D(3) Loose Parts Monitor history and associated evaluations conducted."

"D(4 ) Review of noise history of excore detector."

Our letters of April I 9, l 983 (L-83-230) and May l9, l 983 (L-83-309), committed to provide the above information tentatively by'une 3, l983. The conduct of our meeting with you on that date, satisfied items D(3) and D(4) of our April l9th letter.

Portions of the June 3rd meeting contained proprietary information, and were presented accordingly. Three (3) proprietary (CEN-250(F)-P, dated May 3l, l983) and three (3) non-proprietary versions of the June 3rd presentation, accompanied by Combustion Engineering affidavit of June 2, l 983, were given, at the meeting, to Mr. Don Sells of your of fice.

In addition to the above, the revised St. Lucie Unit No. I Recovery Plan status was discussed during the June 3rd meeting (copy enclosed). Remaining information submittal dates, updating our letter of May l9, l983 (L-83-309) and the tentative dates of your letter of April 26, l983, are as follows:

Items (Desi nation from our A ril l9 letter L-83-230) Tentative Submittal Date

'A. Reactor Vessel Internals and Inspection Results July I 4, I 983 B. Thermal Shield Failure Analysis September I5, l983 D(5) Integrity and Stability of Internals August 24, I 983 D(6) Conclusions and Findings August 25, l 983 gl 30087t "MO607 I-~-'DR'DQCK",05000335:

"""i '

P" '. PDR~ <~ ' PEOPLE... SERVING PEOPLE

Page 2 Office of Nuclear Reactor Regulation Mr. Robert A. Clark, Chief C ~APIInteractions D(l) - Reactor Vessel (PPC I 4-83-264 9 4 77 27, 1988 (FPL letter L-83-263 of April 27, d

l983),

dl and D (2)

- Effects on uel Performance PL letter L-83-265 of April 27, l983) have been earlier satisfied.

Should any questions arise, please contact us immediately.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/DAC/cab Enclosure cc: Harold F. Reis, Esquire

ST. LUCIE I PLANT RECOVERY PLAN (REVISION I)

REPOA REMOVE DEBRIS FAOM REACTOR VESSEL TO NR METALLURGICALANAL PAEPARE FAILURE ANALYSIS FAILURE ANALYSIS 9-15 ISI OF REACTOR VESSEL 4-14 5-24 REMOVE CSB FROM VESSEL PREP METHODS 6-19 d MOBILIZE AT SITE REMOVE THERMAL SHIELD FAOM CSB THERMAL SHIELD 4-4 5-12 PREPARE REPAIR METHODS d, MOBILIZE AT SITE REPAIR CSB d SET IN REACTOR VESSEL CORE SUPPORT BARREL 6-29 RELOAD FUEL PREP FOR START-UP PLANT ON LIN FUEL FUEL REMOVED FROM CONTAINMENT

. 8-5 8-12 CONTINUOUS ASSESSMENT d NRC REVIEW SAFETY ASSESSMENT 4-1 5-3 6-3 6-15 ~ 7-14 8-24 9-2 PRESSURE/TEMPERATURE 1 OPERATING CURVE MEETING WITH NAC ON THERMAL MEETING WITH ACCEPTABILITY'REVIEWTO NAC EXXON RELOAD SHIELD AND RV INTERNALS NRC ON INTEGRITY d SUBMITTAL TO NAC INSPECTION RESULTS, STABILITY OF RV INTE REPAIA, AND ANALYSIS MEETING WITfl NRC ON LPMS d MANAGEMENT

SUMMARY

EXCORE DETECTOA DATA REVIEW CQ SYS14MS raOLLO ~ LaVLLLLCa ILLS G":

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