L-83-345, 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)
DOCKET 05000335 NQTES:
'AOCBSSION NBR:8306100087 DOO,DATE: 83/06/07 NOTARIZED; NO FACIL:50 335 "St. Lucie Planti Uni<<t'i Florida Power L Light Co ~
'AUTH~ NAME AUTHOR AFFILIATION UHRIGiR, 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:
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0 FLORIDAPOWER & LIGHTCOMPANY 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 office.
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 D(5) Integrity and Stability of Internals D(6) Conclusions and Findings 30087t "MO607 I-~-'DR'DQCK",05000335:
P"
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September I5, l983 August 24, I 983 August 25, l 983 gl PEOPLE... SERVING PEOPLE
Page 2 Office of Nuclear Reactor Regulation Mr. Robert A. Clark, Chief C ~API (PPC I
4-83-264 9 4 77 27, 1988 d
dl D(l) - Reactor Vessel Interactions (FPL letter L-83-263 of April 27, l983), 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)
FAILURE ANALYSIS REMOVE DEBRIS FAOM REACTOR VESSEL METALLURGICALANAL PAEPARE FAILURE ANALYSIS REPOA TO NR 9-15 ISI OF REACTOR VESSEL 4-14 REMOVE CSB FROM VESSEL 5-24 THERMAL SHIELD PREP METHODS d MOBILIZEAT SITE 4-4 6-19 REMOVE THERMALSHIELD FAOM CSB 5-12 CORE SUPPORT BARREL PREPARE REPAIR METHODS d, MOBILIZEAT SITE REPAIR CSB d SET IN REACTOR VESSEL 6-29 RELOAD FUEL FUEL FUEL REMOVED FROM CONTAINMENT PREP FOR START-UP
. 8-5 8-12 PLANT ON LIN SAFETY ASSESSMENT 4-1 PRESSURE/TEMPERATURE OPERATING CURVE ACCEPTABILITY'REVIEWTO NAC 5-3 MEETING WITfl NRC ON LPMS d EXCORE DETECTOA DATA REVIEW CONTINUOUS ASSESSMENT d NRC REVIEW 6-3 6-15 EXXON RELOAD SUBMITTALTO NAC 8-24 9-2 MEETING WITH NRC ON INTEGRITY d STABILITYOF RV INTE CQ SYS14MS MANAGEMENT
SUMMARY
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MEETING WITH NAC ON THERMAL SHIELD AND RV INTERNALS INSPECTION RESULTS, REPAIA, AND ANALYSIS G":
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