ML17214A649
| ML17214A649 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/05/1984 |
| From: | Sells D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8401130459 | |
| Download: ML17214A649 (61) | |
Text
Docket No. 50-335 JAIL 5 884 (y))P~lk LICENSEE:
Florida Power and Light Company FACILITY: St. Lucie Plant, Unit No.
1
SUBJECT:
MEETING
SUMMARY
- FAILURE MECHANISM ANALYSIS On November 10, 1983 the St. Lucie Plant, Unit No.
1 licensee (Florida Power and Light Company) and its subcontractor (Combustion Engineering) presented the results of the Failure Mechanism Analysis dealing with thermal shield support structure failure and resulting core barrel damage.
List of attendees at Attachment l.
The initial presentation consisted of a brief review of the identification of thermal shield damage and its subsequent removal and disposition.
This review was provided for the benefit of attendees who were not fully aware of the sequence of events from discovery of damage and the subsequent dis-posal of the thermal shield.
Following this brief review, a proprietary session was initiated to discuss the Failure Mechanism that will be a part of the final report, now expected to be submitted in early January 1984.
Copies of the non-proprietary slides that were used in this presentation are attached (Attachment 2).
In essence, the Failure Mechanism Analysis is based on a detailed review of design data, fabrication data, installation procedures, and looking at the precritical and post critical vibration monitoring programs and data.
The thermal shield dropped and tilted as a result of damage to the support struc-ture.
All wear and fractures are indicative of vertical loading.
Metal-lurigical examination was also conducted of broken pieces of the thermal shield and the support lugs.
The results of the evaluation of data is proprietary.
Attachments:
As stated Original signed bg Donald E
Sells proJect Manager Operating Reactors Branch ¹3 Division of Licensing cc:
See next page ORB+'DL 0
Pggr'eutzer D
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/84 1/ y/84
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'401130459 840i05 PDR ADGCK 05000335 P
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MEETING
SUMMARY
DISTRIBUTION Licensee:
Florida Power and Light Company
- Copies also sent to those people on service (cc) list for subject plant(s).
~acket File NRC PDR
,L PDR NSIC ORB83 Rdg ORB83 Summary File JHeltemes BGrimes JRMiller Project Manager PMKreutzer OELD ELJordan JMTaylor ACRS-10 NRC Participants
Florida Power 8 Light Company CC:
Harold F. Reis, Esquire Lowenstein,
- Newman, Reis 8 Alexrad 1025 Connecticut
- Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire McCarthy, Steel, Hector 8 Davis 14th Floor, First National Bank Building Miami Florida 33131 Mr. Jack Schreve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.N.R.C.
7900 S.
A1A Jensen Beach, Florida 33457 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Mr. Weldon B. Lewis County Administrator St. Lucie County 2300 Virginia Avenue, Room 104 Fort Pierce, Florida 33450 U.S. Environmental Protection Agency Region IV Office ATTN:
Regional Radiation Representative 345 Courtland Street,,
N.E.
Atlanta, Georgia 30308 Mr. Charles B. Brinkman Manager - Washington Nuclear Operations C-E Power Systems Combustion Engineering, Inc.
7910 Woodmont Avenue
- Bethesda, Maryland 20814 Regional Administrator Nuclear Regulatory Commission, Region II Office of Executive Director for Operations 101 Marietta Street; Suite 3100 Atlanta, Georgia 30303 State Pl arming and Devel pment Clearinghous Office of Planning and Budgeting Executive Office of the Governor The Capitol BuHding Tallahassee, Florida 32301
Attachment 1
Failure Mechanism Analysis
- Meeting, November 10, 1983 NRC G. Lainas W. Johnston F. Miraglia L. Rubenstein B.
D. Liaw J. Miller D. Sells C.
D. Sellers R. Klecker A. Wang C.
Hsu S Hou E.
Imbro E. Tourigny K. Heitner L. Lois FPE(L D. Chancy L. Slepow T.
Vogan D. James CE B. Selig R. Longo C. Molnar J. Crawford R. Mills J.
Kingseed C. Brinkman Others T. McIvor, OPPD K. Morris, OPPD M. Cass, NEU A. Cayia, MY J.
- Reynolds, FP&L Consult.
C. Adams, FP8L Consult.
R. Niederberger FPSL Consult.
C. Gilmore, West*
- non-proprietary only OPPD - Omaha Public Power District NEU
- Northeast Utilities, MY
- Maine Yankee
Attachment 2
CEN-258(F)-NP ST.
LUCIE UNIT 8 1
FAILURE MECHANISM ANALYSIS RESULTS
- November, 1983 Combustion Engineering, Inc.
Nuclear Power Systems Windsor, Connecticut
~
~
CP 1
LEGAL NOTICF THIS REPORT WAS PREPARED AS AN ACCOUNT OF WORK SPONSORED BY COMBUSTION ENGINEERING, INC.
NEITHER COMBUSTION ENGINEERING NOR ANYPERSON ACTING ON ITS BEHALF:
A.
MAKES ANY WARRANTY OR REPRESENTATION, EXPRESS OR IMPLIED INCLUDING THE WARRANTIES OF FITNESS FOR A PARTICULAR PURPOSE OR MERCHANTABILITY, WITH RESPECT TO THE
- ACCURACY, COMPLETENESS, OR USEFULNESS OF THE INFORMATIONCONTAINED IN THIS REPORT, OR THAT THE USE OF ANY INFORMATION, APPARATUS, METHOD, OR PROCESS DISCLOSED IN THIS REPORT MAY NOT INFRINGE PRIVATELY OWNED RIGHTS; OR B. ASSUMES ANY LIABILITIESWITH RESPECT TO THE USE OF, OR FOR DAMAGES RESULTING FROM THE USE OF, ANY INFORMATION,APPARATUS, METHOD OR PROCESS DISCLOSED IN THIS REPORT.
AGENDA FOR PROPRIETARY MEETING l<ITH NRC ST, LUCIE UNIT j.
FAILURE MECHANISM'NALYSIS'ROGRAM RESULTS I,
FAILURE MECHANISM ANALYSIS PROGRAM DESCRIPTION EVALUATIONS PERFORMED CONCLUSIONS CORE SUPPORT BARREL REPAIR SITE ACTIYITY OVERVIEW
0 PROJECT STATUS OVERVIEN - TASKS. COMPLETED INITIALASSESSMENT OF REACTOR VESSEL INTERNALS REACTOR VESSEL INTERACTIONS (PTS)
EFFECTS ON FUEL PERFORMANCE TECHNICAL SPECIFICATION P/T LIMITS LPMS AND EXCORE DETECTOR DATA REVIEW RV GAMMA HEATING SUBMITTAL EXXON RELOAD SUBMITTAL FINAL EXXON RELOAD SUBMITTAL REACTOR VESSEL INTERNALS AND INSPECTION RESULTS PLANT RECOVERY PLAN REVISION FINAL POST-LUG REMOVAL NDE RESULTS PLANT RECOVERY PLAN REVISION PLANT RECOVERY PLAN REVISION DRAFT FAILURE MECHANISM ANALYSIS L-83-263 L-83-265 L-83-280 L-83-345 L-83-367 L-83-369 L-83-429 L-83-452 L-83-475 L-83-491 L-83-509 L-83-521 L-83-531 4/12/83 4/27/83 4/27/83 5/3/8 6/7/83.
6/23/83 6/23/83 7/27/83 8/22/83 9/7/83 9/20/83 10/6/83 10/13/83 10/25/83
FAILURE NECHANIStt ANALYSIS PROGRAM"PRESENTATION o
FAILURE NECHANISf'1 ANALYSIS PROGRAN DESCRIPTION o
RESULTS OF INDIVIDUAL INVESTIGATIONS IN FAILURE NECHANISN ANALYSIS PROGRAN o
INTEGRATION OF RESULTS OF INVESTIGATIONS o
FAILURE NECHANISN PROGRESSION o
FAILURE NECHANISN INITIATION
VROGBAH PLAN TIIERHAL SIIIELD I-AILURE HECliANISH ANALYSIS IIYDRAULIC LOADS
- PERIODIC, RANDOH saner ~eg vsvoqsv suvvon WsNIP 5dnirions
- DESIGN, I-ABRICATION a
INSTALLATION DATA VYHV R DAtlAGE VISUAL INSPECTION DATA LVH a IVH DATA HETAI l URGICAL EXAH.
=
DATA INTEGRATE vvnvUvE SELECT CANDIDATE MILURE INITIATION PROGRESSION HECIIANISHS TEST HECliANISHS QUANTITATIVELY (PERFORH
RESPONSE
CALCULATIONS)
CIIECK COHVLIANCE HITII SUPPORTING DATA SELECT CREDIBLE HECllANISH PREPARE REPORT
~
I ~
Exponsion Coet pensct I ng I Vpper Guide Structure Support Plate Ahgnesesst Key 1
A Shroud Outlet Nozzle Core iiistrumentction Guide Tube Alignment Pins l
I I
Core Support 8arrel Fuel Alignment Plcte W
~
I'Wi Thermcl Shield Fuel Alignment Pins Core Support Plcte
~i)
Core Support Assembly Snubber FLOklDA POWER 8 UGHT CO.
St.
Lucie Plont Un' Reactor Internals Assembfy Roure
- 4. 2-7
Therm@i Shield Support Pin
>ertmai
'ieki Care.
Support Barre]
t THER%, SHAN SRm, Lt6 Therma) 5hieid Supxrt Shtm I'asiHanina Pin Thermal Sh.ield Conner:ion I tGUli 2.3'
"REST"'POS I' I'ON 'OF'HERNAL SH IEL'D 110~
(LUG 3) 2900 (LUGS 7,8)
HEHT UP Iil SLOT (Pll QLL CRACKS I!! ilEL)
SUPPORT P Ii'l PROTRUOES PASi THERNL SHIELD AREAS OF LUG !!EAR 2"
GAP
'i9, CC 0
VlQ C5 0 Vl Vl O>>
LOCK PAR HISSI!lG POSITIQNI!lG Pi!l llISSI!IG THERMAL SHIELO POSITiON 7/X (c70
)
CRACY
~ROY~? LOOSE, RUT Ill PLACE SUPPORT PI?l PROTRUOI!tG 1/2" I.'I (HIS AREA CRACY 1/2" GAP
~ LARGE CRACY
((E'ER?'AL SHI (3 SUPPORT LUG PROTRUOES i~ON 1" 0'l TOP 70 1/4" ON BO~(?t IA I
OLJ Qs rag 8/4 3//" GAP CI 4rt
'l0 VISIBLE iP'NGE THERt".AL SKI LD 'POSITION 1/R (SO
)
DESIGN DATA REYIEM DESIGN CALCULATIONS, STRESSES DUE TO DESIGN CONDITIONS BELOM ASME CODE ALLOMABLE VALUES, FABRICATION DATA REVIBI OF NTERIAL SPECIFICATION, ALL, NATERIALS ACCEPTABLE.
INSTALLATION PROCEDURE AVAILABLEDATA UNDER REVIEh
PVNP INSPECTION (POST HOT"FUNCTIONAL)
VISUAL INSPECTION OF THE INTERNALS, NO INDICATIONS OF UNUSUAL SIGNS OF WEAR OR CONTACT, INSERVICE RENOTE VISUAL INSPECTION OF AREAS OF THE LOWER HEAD, NO INDICATION OF.
LOOSE PARTS OR DAMAGE TO THE INTERNALS FOUND,
t"lETALLURGICAL EXAMINATIONS CONCLUSION BASIS FOR CONCLUSION SUPPORT PIN AND THERNAL SHIELD AND CORE SUPPORT BARREL CRACKINb CHARACTERISTICS OBSERVED OPTICAL NETALLOGRAPHY
SCANNING ELECTRON NICROSCOPY'F REPLICAS
LOCKING BAR MELDS AND L'UG j.
(T'OP')
MELD OPTICAL NETALLOGRAPHY
THERMAL SHIELD MECHANICAL PROPERTIES ELEVATED TEMPERATURE TENSILE TESTS SPECIMEN TENSILE STRENGTH YIELD STRENGTH TOTAL ELONGATION IN j."
UNIFORM ELONGATION REDUCTION OF AREA A
(LUG 9)
B (LUG 4)
C (LUG 4)
MONITORING OF INTERNALS THROUGH THE USE OFl
~
LPM - SIGNALS FROM ACCELEROMETERS PLACED ON THE REACTOR VESSEL
~
IVM - VARIATIONS IN EXCORE NEUTRON DETECTOR SIGNALS
IVM and LPM Data Tapes Reviewed for Post-Outage Analyses
- 1. Magnetic Tapes IVM Data LPM Data cycle Date cycle Date 1A 3
5 May 1977 March 1980 Sept.
1982 1A 3
5 March 1978 March 1980 Sept.
1982 2.
Paper Tapes (IYM system) cycle date BOC June, 1978 EOC March, 1979 BOC June, 1979 EOC Feb.,
1981 BOC Dec.,
1981 April, 1982 Sept.,
1982
LOCATIONS OF LPN TRANSDUCERS 0 STEAM GENERATOR A NORTH Qx TRANSOUCER LOCATIONS Qs RCP A-1 Q2 REACTOR VESSEL RCP 8-2 RCF B-1 STEA" GENERA
AMPLITUDE PROBABILITY DISTRIBUTION TIME BACKGROUND IMPULSES PROBABILITY AMPLITUDE AMPLITUDE
POST-OUTAGE ANALYSIS
SUMMARY
OF MODIFIED APD's
POST OUTAGE ANALYSIS LPN PEAK "6" VALUES
" CHANNEL 1978 1980 1981
ST.
LUCIE 1 EXCORE DETECTOR LOCATION AND IVM SYSTEM DETECTOR LOCATIONS A
SARW (345 )
RQQOR O
ME" CO@~PORC CONTROL 1 (220) o B SAFETY
~.
i 0 (75 )
n SAFETY (255 )
o:.
o CONTROt Z
+
C.
SAFETY (2~0)
(16'~)
ISO'XCORE SIGNALS tYM SYSTEM PSD,'s, CROSS
- PSDs, APDS COHEREHCE, PILOSE (Z-ZO HElTZI
REPRESENTATIYE SPECTRA PX2/HZ)
CPSD
,80 COHERENCE 00 PHASE 180 0
3 6
9 12 15 18 21 23 25 FREQUENCY (HZ)
PHASE'EPARATION 180 "OUT-OF-PHASE" NOTION
(-)
0 "IN-PHASE" NOTION
(+)
IlAtlD OUT-OF-PHASE ANALYSIS COHERENCE:
NEASURE TO DETERNINE IF A SIGNAL RESULTS FRON A "COmN SOURCE LQM COHERENCE:
o DIFFERENT SOURCES o
IN-AND OUT-OF-PHASE CANCELLATION PHASE SEPARATION TECHNIQUE o
PHASE EITHER 0 OR 180 o
ALCCRITHN BASED ON SIGN OF CPSD AND ABOVE ASSUMPTION EMPLE Oh PHASE SEPARATION
COMPARISON OF IVM OATA 1977 to 1982 CH 2/CH 1
1977/1982
COMPARISON OF IVM DATA 1980 to 1982 CH 2/CH 1
1980/1982
OBSERVATIONS -
CORE BARREL
CqCL~ ~
p~S02 BOC qg78 LSD~
pOC
~ q979
IVM DATA - CYCLE 3 PSD2 BOC 6-1979 PSD2 EOC 2-1980 COHERENCE 1 x,2
IVN DATA - CYCLE 4 PSD2 BOC 5-1980 PSD2 EOC 9-1981 COHERENCE 1 x 2
IVM DATA - CYCLE 5 PSD2 BOC 12-1981 PSD2 9-1982 COHERENCE 1 x 2
IVH DATA - CYCLE 5 PSD2 BOC 12-1981 (2-25 HERTZ)
PSD2 4-1982 (2-25 HERTZ)
PSD2 9-1982 (2-25 HERTZ)
t t
STRUCTURAL RESPONSE
~
FINITE ELEMENT MODELS TO COMPUTE VARIATION OF SYSTEM (COUPLED CORE SUPPORT BARREL AND THERMAL SHIELD)
FREQUENCY WITH DEGRADED SUPPORT CONDITIONS.
~
REPRESENTATIVE SUPPORT CONDITIONS:
~
~
DETAIL% FINITE ELEMENT MODEL OF SOORT Lll6
~
~
I QJ
~ ~
~ ~ QJ UJ R I CYw cC
STRUCTURAL RESPONSE -
SECOND NODE I
SUPPORT CONOITIONS:
fRE(UENCY(HERTZ)
AIR:
WATER:
STRUCTURAL RESPONSE - THIRD t10DE I
SUPPORT CONDITIONS:
FRE(UENCY(HERTZ)
AIR:
WATER:
I
STRUCTURAL RESPONSE -
FOURTH llODE SUPPORT CONDITIONS:
FRE(UENCY(HERTZ)
AIR:
WATER:
L
I SUPPORT CONDITIONS:
STRUCTURAL RESPONSE - THERMAL SHIELD CANTILYER NODE FRE(UENCY(HERTZ)
AIR:
WATER:
L
FREQUENCIES OF COUPLED NODES, IN WATER; AS A FUNCTION OF THERNAL SHELD SUPPORT" CONDITIONS IN WATER FREQUENCY (HERTZ)
SUPPORT CONDITION
'I
SELF-EXCITED RESPONSE QUASI-STATIC DYNAMIC
~
UJI UJ I
U UJ
'I
~
tS
~
w C7
THERNAL SHIELD"STABILITY"NAP
P RELOAD CONSIDERATIONS POSITIONING PIN CSB NECHAN ICAL PRELOAD POSITIONING PIN CSB THERNAL LOAD TS CSB PRESSURE EFFECT TS
REPRESENTAT'IVE'XI'AL"'TENPERATURE "DI'STRIBUT'ION TOP 90 CORE BARREL 70 60 THERHAL SHIELD 50 8
40 30 20 10 BOTTOH 550 560 570 580 TEHPERATURE ( F )
590 600 610
ST.
LUCIE 1 CSB CYCLES 1 5
AZINUTHALTENPERATURE VARIATION FACTOR
UNFOLDED ELEVATION VIEW SHOWING RADIAL PRESSURE DIFFERENTIALS ACROSS THE CORE SUPPORT BARREL hP=2L.t's',
007LET WOn.LC hP=2L.bp gP=40.5 ps'NLET It/OZZ.LES b P= 2(,Lpsi hP=>4.4 ps',P
= 24.4 pt-OUTLE7 N027.LE dP=24.4 p.
/IVLE'7 NO2ZLES AV=2(.b qadi bP=2t.lp psi h p = 40.5psc op= 24.6 psi OurLer N'OZZLE 2I.9 l'l.l I9.I bP=ZI 8 p*'l.
V I'./
/g.l l9.!
I V.I l9.I Zl.'t V2/CCQAI SHIIT< b
/9.7 Jt.3 IR.3 IP.3
/S.g g.3
/9.V IS.3 I%3
/&.3 I8.3 lg.g IQ.Q dP= 20.8 pic.
SN 055E<
AF = /9.z. ps'
ESTIMATED'OPERATING T'INE"AT'HOT STANDBY (ZERO
- POWER, 4
PUMP OPERATION)
CYCLE DATE TINE/CYCLE (HRS)
CUNULATIVE TINE (HRS)
PRECRITICAL
- SEPT, 1975 APRIL 1976 JULY 1976
- DEC, 1976
- MARCH 1978 NAY 1978
- APRIL 1979 JUNE 1979 MARCH 1980 NAY 1980 SEPT, 1981 NOV, 1981 NARCH 1983 1824 936 576 432 216 240 1824 2280 3216 3792 4224 4440 4680
RELATIVE DEFLECTIONS HILS)
FOR FACTORS THAT INCREASE AND REDUCE POSITIONING PIN PRELOAD
CIIRONOLOGICAL COMPARISON - POST OUTAGE ANALYSIS EVENT POSTULATED LPM BASELINE ALARM EXCEEDED GRADUAL INCREASE IN ALARM LEVEL ALARM EXCEEDED)
AL)IO LEVELS EXCEEDED)Q RU FUR7UER INCREASES IH ALARM LEVEL IVM IHSPECTIOH COMPLETE VISUAL INSPECTION)
HO SIGNS OF CONTACT OR HEAR LIMITED, REMOTE VISUAL INSPECTION)
HO DAMAGE OR LOOSE PARTS LIMITED, REMOTE VISUAL INSPECTION)
'NO DAMAGE OR LOOSE PARTS TIME I97(
1976 19 7 1978 19 9 1980 CYCI.E I N57IF I
/- 7-I I 7R I
I' I l I I 1981 1982 "II
'0 1
E