L-83-475, Forwards Rev 3 to Plant Recovery Plan for Reactor Vessel Internals & Thermal Shield to Refine NDE Data & pre- & post-core Support Barrel Lug Removal
| ML17214A421 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 09/07/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| L-83-475, NUDOCS 8309120345 | |
| Download: ML17214A421 (5) | |
Text
REGULATORY FORMATION DISTRIBUTION SYLM (RIBS)
ACCESSION NBR 83091203 f5 DOC ~ DATE 83/09/07 NOTARIZED~
NO FACIL:50-335 St. Lucie Pl anti Uni t 1r Florida Power 8 Light Co.
AUTH-NAt<E AUTHOR AFFILIATION UHRIGPR E ~
Flor ida Power 8 Light Co ~
REC IP ~ NAME RECIPIENT AFFILIATION KILLERSJ R
Operating Reactors Branch 3
SUBJECT:
Forwards Rev 3 to plant recovery plan for reactor vessel internals 8 thermal shield to refine NDE data 8 pre 8
post-core support barrel lug removals DISTRIBUTION CODE:
ABOIS COPIES RECEIVED:LTR ENCL SIZE:
Z I
~
TITLE:
OR Submittal:
General Distribution NOTES:
DOCKET 05000335 RECIPIENT ID CODE/NAME NRR ORB3 BC 01 INTERNALS ELD/HDS2 NRR/DL D IR N
I TB EXTERNAL ACRS 09 NRC PDR 02 NTIS COPIES LTTR ENCL 7
7 1
0 1
1 1
'1 1
1 6
6 1
1 1
RECIPIENT ID CODE/NAME NRR/DE/HTEB NRR/DL/ORAB NRR/DS I/RAB RGN2 LPDR NSIC 03 05 COPIES LTTR ENCL 1
1 1
0 1
1 1
1 1
~
1 1
1 jY U
TOTAL NUYiBER OF COPIES REQUIRED: 'TTR 25 ENCL 23
ill
~
~
'Ir 1I I,
Box 14000, JUNO BEACH, FL 33408 yQIicz FLORIDA POWER & LIGHT COMPANY September 7, 1983 L-83-475 Office of Nuclear Reactor Regulation Attention:
Mr. James R. Miller,Chief Operating Reactors Branch P/3 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 Recover Pro ram On 'August I 6, 1983, Florida Power and Light Company provided you with a presentation on St. Lucie Unit I Core Support Barrel Inspection,
- Repair, and Analysis, and Thermal Shield Removal.
In addition, a revised St. Lucie Unit No.
I Recovery Plan (Revision 2) status was discussed during the August l6th meeting and a copy forwarded in our letter of August 22, l983 (L-83-452).
In order that our presentation of Non-Destructive Examination (NDE) data be refined and consolidated into pre and post Core Support Barrel (CSB) Lug removal states, the St. Lucie Unit No.
I Recovery Plan (Revision 3) has been revised and is herein forwarded.
This subject has been discussed with Mr. Don Sells of your office on September 6,
I 983.
Should any questions arise, please contact us immediately.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REU/DAC/cab Enclosure cc:
Harold F. Reis, Esquire 0gl l
r "8309i20345 830907
.-",)PDR ADOCK 05000335 P, "~'i'g,
"-,g'PDR. "j,, '4.
PEOPLE... SERVING PEOPLE
q f)
ST. LUCIE 1 PLANT RECOVERY PLAN (REVISIONS)
FAILURE ANALYSIS REMOVE DEBRIS FROM REACTOR VESSEL METALI.URGICALANAL PRFPARE FAILURE ANALYSIS REPORT TO NRC 10-15 ISI OF REACTOR VESSFI.
4-14 REMOVE CSB FROM VESSEL 5-24 THER/1AL SHiELD PREP METHODS 3!'lOBIUZE *T SITE 4 4 REMOVE THERMALSHIELD FROM CSB 7-25 CORE SUPPORT BARREL PREPARE REPAIR METHODS 5 MOBILIZEAT SITE REPAIR CSB 4 SET IN REACTOR VESSEL 8-17 RELOAD FUEL PREP FOR START-UP FUEL FUEL REMOVED FROM CONTAINMENT FINALEXXON RELOAD SUBMITTAL POSTWUQ REMOVALFINAL NDE INSPECTION RESULTS 10-9 10-16 PLANT ON SAFETY ASSESSibiENT COtlTINUOUS ASSESSMENT 5 t31C REVIEW 7-27 4-25 5-3 PRESSURE/TEMPERATURE OPERATING CURVE ACCEPTABIUTYREVIEW TO NRC 4-1 4
12 NRC MEETVIG-PRELIMINARYASSESSMENT+
NRC MEETING-RECOVERY PLAN/PTS CONSIDERATIONS 8-3 MEETDIQ WITH NRC~
ONLPMS 5 EXCORE DETECTOR DATA REVIEW EXXON RELOAD 5 GAMMAHEATDIQ SUBMll'TALTO NRC 6-23 8-18 MEETBIQ WITH NRC~
ON THERMALSHIELD AND RV INTERNAI.S INSPECTION RESULTS.
REPAIR. AND ANALYSIS 9-28 10-20 I'I 14 MEETING WITH NRC OM INTEGRITY~
5 STABIUTYOF RV INTERNALS; POST-MACHININQ FINAL NDE BISPECTION RESUI.TS POw4il
~iy ti 4I gg AM 4ii3 MANAGEMENTSUMAARY
~ I
~iiI4 0
~ IS II4 II 44 IIV I4I44III44W4 ~ 44 4
~ I4IIII