L-83-452, Summarizes 830816 Meeting W/Nrc to Discuss Reactor Vessel Internals & Thermal Shield & Plant Recovery Program - Reactor Vessel Internals & Insp Results.Remaining Info Submittal Dates Listed
| ML17214A410 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/22/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| L-83-452, NUDOCS 8308300360 | |
| Download: ML17214A410 (5) | |
Text
REGULATORY FORMATION DI'STRIBUTION 'S M (RIDS)
AOCESSION NBR:8308300360 DOC,DATE: 83/08/22 NOTARIZED:
NO FACIL:50~335 'St. Lucf e Planti UniIt 1i Flor ida Power 8 Light Co, AUTH,'NAME AUTHOR AFFILIATION UHRIGiR,E, Flor ida 'Power 8 'Light Co, REC IP ~ NAME RECIPIENT A'FFILIATION CLARKiR ~ AD Operating Reactons Branch <<3 SUBJECT; "Summarizes 830816 meetirig w/NRC to discuss neactor~-vessel internals 8 ~ther'mal shield L plant recovery piogr am r.eactor vessel interna'ls 8 insp results;Remaining "info submit:ttal dates listed>
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BOX 14000, JUNO BEACH, F L 33408 yyilg
/Ih FLORIDAPOWER 5 LIGHT COMPANY August 22, l983 L-83-452 Office of Nuclear Peactor Regulation Attention: Mr. Robert A. Clark, Chief Operating Reactors Branch f/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 - Reactor Vessel Internals and lns ection Results In a meeting held on August l6, l983, 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.
Our letters of April I 9, l983 (L-83-230) and July 27, l983 (L-83-430), committed to provide "Reactor Vessel Internals and Inspection Results" pursuant to the St.
'Lucie Unit I Plant Recovery Program (Item A from our L-83-230), during the week of August l5, l983.
Followup documentation of the presentation of this information was to be forwarded to your office by August 26, l983.
The conduct of our meeting with you on August l6, l983, together with follow up documentation herein contained, satisfies item A. of our L-83-230.
Portions of the August l6th meeting contained proprietary information, and were presented accordingly.
Three (3) proprietary (CEN-253(F)-P, dated August I 6, l983, and three(3) non-proprietary versions of the August l 6th presentation, accompanIed by Combustion Fngineering affidavit of August l5, l983, were given at tne meeting, to Mr. Don Sells of your office.
In addition to the above, the revised St. Lucie Unit No.l Recovery Plan status was discussed during the August 16th meeting (copy enclosed).
Remaining information submittal dates, updating our letter of June 7, l983 (L-83-345) and the tentative dates of your letter of April 26, l 983, are as follows:
83083003b0 830822 I
PDR ADOCK 05000335 P
PDR gob 1
t PEOPLE... SERVING PEOPLE
Items (Desi nation from our A ril l9 letter L-83-230) Tentative Submittal Date B.
Thermal Shield Failure Analysis D(5) Integrity and Stability of Internals D(6) Conclusions and Findings Completed items/tasks integral to the St. Lucie Unit I
follows:
October l5, l983 October 20, l983 October 20, l983 Plant Recovery Program, are as L-83-230 Action items
~Sub'ect (NA)
INITIALASSESSMENT OF REACTOR VESSEL INTERNALS Letter L-83-230 Date 4/ I 9/83 (4/I 2/83 NRC Meeting)
(Dl)
REACTOR VESSEL INTERACTIONS (PTS)
L-83-263 (C)
RECOVER Y PLAN L-83-264 (D2)
EFFECTS ON FUEL PERFORMANCE L-83-265 (NA)
TECHNICALSPECIFICATION P/T LIMITS L-83-280 (D3&D4)LPMS AND EXCORE DETECTOR DATA'-83-345 REVIEW (NA)
RV GAMMAHEATING SUBMITTAL L-83-367 (NA)
EXXON RELOAD SUBMITTAL L-83-369 (NA)
FINAL EXXON RELOAD SUBMITTAL L-83-429
. Should any. questions arise,'lease contact us immediately.
'Very truly yours, 4/27/83 4/27/83 (4/25/83 NRC Meeting)'/27/83 5/3/83 6/7/83 (6/3/83 NRC Meeting) 6/23/83 6/23/83 7/27/83 Robert E. Uhrig Vice President Advanced Systems 8 Technology REU/DAC/Img Enclosure cc: Harold F. Reis, Esquire
ST. LUClE 1 PLANT RECOVERY PLAN I nEVISION21 AEMOVE DEGAIS FAOM REACTOR VESSEL REPOAT TO NAC FAILURE ANALYSIS METALLUAOICALANAL PREPARE FAILURE ANALYSIS 10 III ISI OF REACTOR VESSEL 14 REMOVE CSG FAOM VESSEL 5-24 THERMALSHIELD PAEP METHODS 4 MOGILIZEAT SITE REMOVE TIIEAMALSiuELO FAOM CSG S
12 T-2tt COAE SUPPOAT BARREL PREPARE REPAIR LIETIIOOS 4 MOGILIZE AT SITE REPAIR CSG
- 4. SET IN REACTOR VESSEL 6-1T RELOAD EUEU PAEP fOll START UP PLANT ON LlttE FUEL AEMOVED FAOM CONTAINMENT FIIIALEXXOtl RELOAD SUGMITTAL PRE-MACIutGIIO Fttt4L NDE tNSPECTION AESULTS 10-9 10 SAFETY ASSESSMENT COIITIIIUOUS ASSESSMEHT 4 MIC REVIEW PRESSURE/TEMPERATURE OPEAAAIIOCUAVE ACCEPTAGLITYAEVIEW TO ITIC 6-3 6-3 MEETItIO WilliNAC ON LPMS 4 EXCOAE DETECTOR o4Ta REVIEW EXXON RELOAD 4 GAMMAIIEATlltQ SUGMITTAL TO IIAC 4
12 4 26 I
NAC MEETIIIO-PRELIMINARYASSESSMEIIT+
NAC MEETINO-AECOVEAYPLAIIIPTS COIISIOEAATIONS 1-21 6-23 6-10 MEETGIQ WITtl NAC~
ON TNEAMALSIIIELD htto AV ItITEANALS INSPECTION AESULTS.
AEGIR. hND AIIALYSIS 9-9 10 20 11 10 2
MEETVIO WITII NAC Ott INTEGAITY 4 STAGILITYOF AV INTERNALS; POST MACIIVIINQFINAL NOE INSPECAON AESULTS H)wtN 5151tlat O
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