L-83-509, Discusses Reactor Vessel Internals & Thermal Shield & Plant Recovery Program.Outline of Final Rept of Integrity & Stability of Internals W/O Thermal Shield,Presented at 830922 Meeting,Encl.Info Submittal Dates Listed
| ML17214A487 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 10/06/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| L-83-509, NUDOCS 8310130009 | |
| Download: ML17214A487 (20) | |
Text
REGULATORY FORMATION DISTRIBUTION S M 'RIDS)
ACCESSION NBR;8310130009 DOC,DATE: 83/10/06 NOTARIZED:
NO FACIL:50-335 St. Lucie Planti Uni;t 1< Florida Power 8 Light Co<
AUTH,NAME AUTHOR AFFILIATION UHRIGiR ~ ED Florida Power 8 Light Co, RECIP ~ NAME RECIPIENT AFFILIATION MILLER<J,R.
Operating Reactors Branch 3
SUBJECT:
Discusses reactor vessel internals 8 thermal shield L plant recovery program,Outline of final rept of integrity 8
stability of internals w/o thermal shieldipresented at 830922 meetingiencl, Info submittal dates
'listed, DISTRIBUTION CODE:
A001S COPIES RECEIVED:LTR g ENCL SIZE' TITLE:
OR Submittal:
General Distribution NOTES:
DOCKET 05000335 RECIPIENT ID CODE/NAME NRR ORB3 BC 01 COPIES LTTR ENCL 7
7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL INTERNAL: ELD/HDS2 NRR/DL D IR NRR/DS
/METB EXTERNAL: ACR/
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NRR/DE/MTEB NRR/DL/ORAB NRR/DS I/RAB RGN2 LPDR NSIC 03 05 1
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TOTAL NUMBER OF COPIES REQUIRED:
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. BOX 14000, JUNO BEACH, FL 33408 FLORIDAPOWER & LIGHTCOMPANY October 6, I 983 L-83-509 Office of Nuclear Reactor Regulation Attention:
Mr. James R. Miller, Chief Operating Reactors Branch /k3 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 - Recover Plan Revision In a meeting held on September 22, l983, Florida Power & Light Company (FPL) provided you with an outline of the final report on St..Lucie I Integrity and Stability of Internals Without Thermal Shield (Conclusions and Findings).
That outline presentation is included on an attachment to this letter.
A draft submittal schedule was discussed at that meeting, and with Mr. Don Sells of your office on September 26, l983, in order that a final FPL presentation could take place on October 20, l983.
Due to difficulties encountered in the Core Support Barrel repair machining process, and the factoring of additional support activities required to return St. Lucie I
to power, it has become necessary to revise the St. Lucie I Recovery Plan.
Revision 4 of that Recovery Plan is enclosed.
Contingencies affecting the date for return to power of St. Lucie I, are shown on the revised Recovery
- Plan, and are attributable to factors, the duration and/or occurrence of which are unknown at this time.
Remaining information submittal
- dates, updating our letter of August 22, l 983, (L-83-452) and the tentative dates of your letter of April 26, I 983, our as follows:
Items (Desi nation from our A ril l9 letter L-83-230)
Tentative Submittal B.
Thermal Shield Failure Analysis D(5)
Integrity and Stability of Internals D(6)
Conclusions and Findings October 17, I 983 December 15, I 983 December l5, l983 Completed items/tasks integral to the St. Lucie Unit I Plant Recovery Proaram, are as follows:
8310130009 83i006 PDR ',ADOCK., 05000335 P.i-" j,, "i'i] -.'-,P.DR)-~.~'l i
PEOPLE... SERVING PEOPLE
0
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Page 2 Office of Nuclear Reactor Regulation Mr. James R. Miller, Chief L-83-230 Action Items
~Sub'ect (NA)
INITIALASSESSMENT OF REACTOR VESSELL INTERNALS Letter L-83-230 Date 4/19/83 (4/l2/83 NRC Meeting)
(Dl)
REACTOR VESSEL INTERACTIONS (PTS)
L-83-263 4/27/83 (C)
RECOVERY PLAN L-83-264 4/27/83 (4/25/83 NRC Meeting)
(D2)
EFFECTS ON FUEL PERFORMANCE L-83-265 4/27/83 (NA)
TECHNICAL SPECIFICATION P/T LIMITS L-83-280 5/3/83 (D3&D4) LPMS AND EXCORE DETECTOR DATA REVIEW L-83-345 6/7/83 (6/3/83 NRC Meeting)
(NA)
RV GAMMAHEATING SUBMITTAL (NA)
EXXON RELOAD SUBMITTAL (NA)
FINAL EXXON RELOAD SUBMITTAL (A)
REACTOR VESSEL INTERNALS AND INSPECTION RESULTS (NA)
RECOVERY PLAN REVISION (NA)
POST-LUG REMOVALFINAL NDE INSPECTION RESULTS L-83-367 6/23/83 L-83-369 6/23/83 L-83-429 7/27/83 L-83-452 8/22/83 L-83-475 9/7/83 L-83-49I 9/20/83 Should any questions arise, please contact vs immediately.
ery vly
- ours,
'ert E. Uhrig Vice President Advanced Systems & Technology REU/DAC/cab Enc losure cc: Harold F. Reis, Esquire
t
ATTACHMENT 1 ST, LUCIE UNIT 1 EVALUATION OF OPERATION WITHOUT A THERMAL SHIELD SEPTEMBER 22, 1983
PROJECT STATUS OVERVIEW TASKS COMPLETED INITIALASSESSMENT OF REACTOR VESSEL INTERNALS REACTOR VESSEL INTERACTIONS (PTS)'FFECTS ON FUEL PERFORMANCE TECHNICAL SPECIFICATION P/T LIMITS LPMS AND EXCORE DETECTOR DATA REVIEW RV GAMMA HEATING SUBMITTAL EXXON RELOAD SUBMITTAL FINAL EXXON RELOAD SUBflITTAL REACTOR VESSEL INTERNALS AND INSPECTION RESULTS L-83-263 L-83-265 L-83-280 L-83-345 L-83-367 L-83-369 L-83-429 L-03-<l52 4/12/83 4/27/83 4/27/83 5/3/83 6/7/83 6/23/83 6/23/83 7/27/83 8/22/S3 PLANT RECOVERY PLAN REVISION FINAL POST-LUG RENOVAL NDE RESULTS L-83-t':75 L-83-l!9" 9/7/83 9/20/83
PURPOSE DISCUSS FINAL REPORT CONTENT
REPORT OVERVIEW CHAPTER 1
SUMMARY
AND CHRONOLOGY OF EVENTS CHAPTER 2 DESCRIPTION OF REACTOR INTERNALS AND REACTOR VESSEL INTERFACES CHAPTER 3 PRESSURIZED THERMAL SHOCK CHAPTER 4 NON-DESTRUCTIVE EXAMINATION (NDE) TECHNIQUES CHAPTER 5 NDE INSPECTION RESULTS CHAPTER 6 CORE SUPPORT BARREL REPAIR CHAPTER 7
FA I LURE, IECHANI SM ANALYSIS CHAPTER 8 CORE SUPPORT BARREL STRUCTURAL INTEGRITY CHAPTER 9 SAFETY ANALYSIS CHAPTER 10 MONITORING AND INSPECTION PROGRAMS
CHAPTER j.
SU$1ARY AND CHRONOLOGY OF EVENTS o
SVf1NARY (CONCLUSIONS AND FINDINGS) o CHRONOLOGY OF EVENTS CHAPTER 2 DESCRIPTION OF REACTOR INTERNALS AND REACTOR VESSEL INTERFACES o
DESCRIPTION OF REACTOR INTERNALS o
.DESCRIPTION OF REACTOR VESSEL INTERFACES
CHAPTER 3 PRESSURIZED THERMAL SHOCK o
INTRODUCTION END-OF-LIFE RTNDT o
REACTOR VESSEL GAMf'lA HEATING CHAPTER 4 NON-DESTRUCTIVE EXANINATION TECHNIQUES o
DESCRIPTION OF TECHNIQUES VISUAL EDDY 'CURRENT ULTRASON I C
~
o CRITERIA o
CALIBRATION o
SEQUENCE OF INSPECTION
RAPTER 5 NDE INSPECTION RESULTS o
REACTOR VESSEL INTERFACES AND INTERNALS INSPECTION RESULTS o
THERMAL SHIELD INSPECTION RESULTS o
CORE SUPPORT BARREL INSPECTION RESULTS o
FUEL iNSPECTION RESULTS CHAPTER 6
CORE SUPPORT BARREL REPAIR o
CSB REPAIR PROCESS REPAI'R MACHINING OBJECTIVES MACHINING DESCRIPTION o
CSB EXPANDABLE PLUG REPAIR DESIGN DESCRIPTION THERMAL HYDRAULIC CONSIDERATIONS STRUCTURAL CONS IDERAT IONS TESTING INSTALLATION CONCLUDE IONS P LUG INTEGRI TY
CHAPTER 7 FAILURE MECHANISM ANALYSIS 0
INTRODUCTION CHRONOLOGY AND HISTORY PROGRAM DESCRIPTION
SUMMARY
o BAS I C INFOPMATION HYDRAULIC LOADS STRUCTURAL RESPONSE
- DESIGN, FABRICATION AND INSTALLATION DATA PVMP AND VISUAL INSPECTION DATA LPM AND IVM DATA METALLURGICAL EXAMINATION o
FAILURE MECHANISM INITIATION PROGRESSION o
CONCLUSIONS
CHAPTER 8 CORE SUPPORT BARREL STRUCTURAL INTEGRITY o
REACTOR INTERNALS STRESS ANALYSIS RESULTS o
CSB STRESS ANALYSIS RESULTS INTRODUCTION CRITERIA CSB YIATERIAL EXAf"lINATION RESULTS STRESS ANALYSIS RESULTS
CHAPTER 9 SAFETY ANALYSIS 0
I NTRODUCT ION 0
EFFECT OF THERMAL SHIELD REMOVAL PRIMARY SYSTEM FLOW RATE CORE FLOW DISTRIBUTION 0
EFFECT OF CSB REPA IRK BYPASS LEAKAGE RATES ASSESSMENT OF PLUG FAILURE Ojl TRANSIE.'3T~ AND ACCIDENTS 0
CYCLE R LICE".!SING ANALYSIS APPLICARILITY
CHAPTER'10 MONITORING AND INSPECTION PROGRAMS o
INTRODUCTION o
MONITORING OBJECTIVES o
EXCORE MONITORING SYSTEM DESCRIPTION DATA ACQUISITION SCHEDULE DIAGNOSTICS ALERT AND ALARM LEVELS o
LOOSE PARTS MONITORING SYSTEM DESCRIPTION DATA ACQUISITION SCHED(JLE DIAGNOSTICS ALERT AND ALARM LEVELS o
INSPECTION OBJECTIVES SHORT TERM INSPECTION LONG TERM. INSPECT ION o
SUMMARY
ATTACHMENT 2 NRC MEETING 22 September
'83 (FPL - PSL-I THERMAL SHIELD RECOVERY)
NAME D. Sells B.
D. Liaw S.
Hou W. S. Hazelton J.
R. Miller Daniel Fieno Alan Wang Paul Leech Richard J. Kiessel Lambros Lois J.
C. Chandler T. A. Dillard D.
C.
Chancy C.
D. Sellers C.
M. Molnar J.
F. Mullooly Y. Hsii AFFILIATION NRC Project Manager NRC/MTEB NRC/MEB NRC/MTEB NRC/ORB3 Chief NRC/CPB ACRS NRC/ORB-3 NRC/IE/EGCB NRC/DST/CPB Exxon Nuclear FPL FPL NRC/l1TE8 C-E C-E NRC/CPB
~
~
H ST. LUClE 1 PLANT RECOVERY PLAN I REvlsloN 4)
FAILURE ANALYSIS REMOVE DEBRIS FROM REACTOR VESSEL METALLURGICALANAL.
PREPARE FAILURE. ANALYSIS REPORT TO NRC 10-17 ISI OF REACTOR VESSEL 4-14 REMOVE CSB FROM VESSEl.
8-24 THERMALSHIELD 4-4 PREP METHODS a MOBILIZEAT SITE
.. hEMOVE THERMAL SHIELD FROI4 CSB 8-12 7-28 CSB MACHVIING.REPAIII a Sur PORT ACTIVITIES CONIltlGFNCY PERIOD
.CORE SUPPORT BARREL FUEL PREPARE REPAIR METIIODS d MOBILIZEAT SITE FUEL REMOVED FROM CONTAINMENT REPAIR CSB a
SET TN REACTOR VESSEL MEETING WllH NRC ON FAILIIIIEMECHANISM ANALYSISRESULTS MEETING WITH NRC ONPROPOSED FVIAL REPORT CONIEMT
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PLANT ON LINE SAFETY ASSESSMENT CONTINUOUS ASSESSMENT d tFIC REVIFW FINAl. EXXON RELOAD SUBMITTAL POST-LUG REMOVALFVIAL NDE 9ISPECTIOM RESULTS T-2T RELOAD FUEL PREP FOR START-UP 4-1 4
12 4-2$
8 3 PRESSUREITEMPERATURE OPERATING CURVE ACCEPTABILITYRFVIEW TO NRC NRC MEETING-PRELIMINARYASSESSMENT+
NRC MEETING RECOVERY PLANIPTS CONSIDERATIONS 8-3 MEETING Wlltl NRC~
OM LPMS d EXCORE DETECTOR DATA REVIFW EXXON RELOAD 8 GAMMAIIEATIMO SUBMITTALTO NRC 8-23 8-18 MEETING WITH NRC~
ON 'llIERMAL SHIELD AtlD RV IttlERNALS tNSf'ECTIOM RESULTS, REPAIR. AND ANALYSIS 9 20 10 28 12 15 MEETItlO WITH NRC ON INTEGRITY d STABILITYOl RV Itl'fERNALS:
POST-MACHININO TRIAL NDE INSPECTION RESULT S t;gSeSI(MS 2-1 MANAGEMENTSUMI.IARY Ke
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