L-83-263, Summarizes 830425 Meeting W/Nrc Re Reactor Vessel Internals & Thermal Shield Plant Recovery Program Concerning Pressurized Thermal Shock.Plant May Safely Operate W/O Restriction from Pressurized Thermal Shock Considerations
| ML17213B314 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/27/1983 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR L-83-263, NUDOCS 8305020345 | |
| Download: ML17213B314 (23) | |
Text
REGULA~
Y INFORMATION DISTRIBUTIO YSTEM =('R IDS)
ACCESSION NBR:8305020345 DOC ~ DATE: 83/04/27 NOTARIZED; NO FACIL:50-335 St, Lucie Planti Unitt ii Florida Power 8, Light Co<
AUTH,NAME AUTHOR AFFILIATION i
UHRIG'RNE ~
Florida Power 8 Light Co ~
REC IP, NAME RECIPIENT AFFILIATION CLARKiR~
AD
'perating Reactors Branch 3
SUBJECT:
Summarizes 830425 meeting w/NRC re,reactor vessel internals 8 thermal shield plant recovery program concerning pressurized thermal shock.'Plant may safely operate,w/o
.restriction from pressurized thermal shock considerations.
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Thermal 'Shock to Reactor Yessel NOTES'OCKET 05000335 REC IP IENT ID CODE/NAME NRR ORB3 BC 01 INTERNAL: ELD/HDS2 12 NRR DIR NRR/DE/MTEB NRR/DL DIR NRR/DSI DIR N
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P. O. Box 14000, JUNO BEACH, FL 33408 FLORIDAPOWER & LIGHTCOMPANY April 27, I 983 L-83-263 Office of Nuclear Reactor Regulation Attention:
Mr. Robert A. Clark, Chief Operating Reactors Branch
$/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 Recover Pro ram In a meeting on April 25, 1983, Florida Power and Light Company provided you with information about the St. Lucie Unit I reactor vessel with respect to pressurized thermal shock (PTS).
This letter sum'marizes that meeting and satisfies item D(l) of our letter of April I 9, I 983 (L-83-230).
CEN-I89, Appendix F ("Evaluation of PTS Effects due to Small Break LOCA's with Loss of Feedwater for the St. Lucie I
8 2 Reactor Vessels"
- December, l98I),
provided an evaluation of the St. Lucie I reactor vessel for PTS effects of certain specific hypothetical plant transients (post TMI 2 Action). The governing axial weld is located in the lower shell course at an azimuthal location where the fluence profile is 47% of the peak fluence.
Using the material and fluence data developed in CEN-I89, Appendix F, the residual chemistry for this weld is 0.30 wt. % Cu and.64 wt. % Ni. The resultant end-of-life RTNDT for this weld is predicted to be 2I7OF using the shift prediction method of SECY-82-465 ("NRC Staff Evaluation of PTS",
November 23, I 982).
For the sake of comparison only, even if St. Lucie I operated from beginning-of-life to end-of-life without a thermal shield, the end-of-life RTNDT predicted by the method of SECY-82-465 would still only be 252OF.
Since St. Lucie I has operated until now with a thermal shield, the end-of-life RTNDT would be somewhat less than this upper bound value.
We understand the NRC staff and their consultants are developing a revision to the RTNDT shift prediction method of SECY-82-465 which would result in a lower EOL RTNDT prediction.
830502034~
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Office of Nuclear Reactor Regulation Mr. Robert A. Clark, Chief These evaluations will be updated as the results of the surveillance capsule program become available.
Also, the vessel beltline weld in-service inspections being completed this outage will provide additional confirmation of the soundness of the vessel material.
Based on these evaluations, St. Lucie I may safely operate without restriction from PTS considerations.
Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REUjDAC/cab cc: Harold F. Reis, Esquire Enclosure
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ST, LUCIE -'1 PTS MEETING AGENDA APRIL 25, 1983 1,.
REVIEW PRESENT PTS
.STATUS 2.
EFFECTS OF THERMAL SHIELD REMOVAL ON PTS 3,
ONGOING PTS EFFORT E4, SCHEDULES
ST, LUCIE j.
PRESENT PTS STATUS l..
MELD CHENI.STRY 2,
FLUENCE CALCULATIONS 3,
RT-NDT PREDICTIONS
FIGURE F6-1 ST.
LUCIE El REACTOR PRESSURE VESSEL HAP INITIAL RTNPT IN 'F 20 4J
~
X Z
eo
~ I C ~ 6
~ 3 E3D I 203@@
C. 6-2 Egg";.
C 6 II%03 UJ IOO C3 C ~ 7-I QD 2 2o3CZ5 C-V.2 Qfj C
V ~ 3C~~Q a
Iio 4J (Z
I 100 a
~ 2 C
8 3CEI 3 2o3E9 CORE C
8 ~ I C++3 C
~ 8-2~
220 eo..0 IeO Al I tlUTIIAL LOCA I I otl, OCGREE5
TABLE F6-1 ST.
LUCIE UNIT Nl REACTOR VESSL'L HATERIALS Product Form Viater ia 1 Identi fication Orop Weight
~NDTT
'F Initial RTND~T'F Nic el Phos horus ChemicaI Content~i)
Plate Plate Plate Plate Plate Plate Plate Plate Plate Wel d Wel d Wel d r
Meldf C6-1 C6-2 C6-3 C7-1 C7-2 C7-3 CS-1 CS-2 CB-3 1-203 A,B,8C 3-~03 A,B,tlC 9-203 10
-30
-10 0
-30
-30
. -10 0
0 N/A N/A N/A N/A N/A 10
-30
-10 Oa 0 a 10 20 0 a
'c
-50
-50
'-50
-60
-60
.53
.53
.53
.64
.64
.58
.56
.57
.SSd
.11 b
.14b
.14b
.14
,11
.11
.11
.15
.15
.12
~ 22
~l
.21
.23
'.012
. 011
.011
.004
.004
.004
.006
.006
.004
.015
.018
.013
.016
.013 N/A a
b c
d e
Not Available Oetermined using Branch Technical Position HTEB 5-2 E'stimated based on average of similar plates Estimated
{see Table F6-2)
Estimated Ni content {high nickel type wire)
Estimated Ni content low nickel type wire)
a
ST.
LUCIE 1 CURRENT FLUENCE CALCULATIONS (REF, CEN-j.89)
NS-2
. R5 DOT PROFILE CNS-2 POMER DIST.)
~
VIS-2 CAPSULE BENCHNARK SL-1 POINT KERNEL PEAK (SL-j. POWER DIST.)
I.b HORIIAL)ZED FAST FLUX ST.
LUCIEI AZIMUTHALFLUENCE VARIATION AI VESK Ojio INTSFAK b.7 8.6, b.k Jh 15
%TA IKNEES FIGURE F5-3
FIGURE F6-2 ST.
LUCIE fl REACTOR PRESSURE VESSEL NP ADJUSTEO RTNDT IN 'F (12/31/81) 3.55 Effect)ve Ful 1 Power Years 0.33 x 1019n/cm2 Peak Surface Fluence 20 th
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WX Z
60 4P uj IOO C)K C3 Iio 4
~ I I.203-2 203-C ~ 6
~ 3 i C ~ 7 ~ I I 203-2 203-C.6.2 C-7 ~ 2 C ~ 6.I
.T C
~ 7 ~ 3 4J(3 CZ I
tQ Cl I 80
~ 2 3 203>
C ~ 8,3 C~W 3203' C
B.I C ~ 8 ~ 2 220 260-ISO 360 Rl I tIUIIIRL LOCAI 10:7, OEGREES
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ST, LUCIE - 1 CURRENT STATUS I
EOL PEAK FLUENCE = 2..83 x 10 x/cz 'Ol NEv)
EOL HELD FLUENCE = A7..5X x PEAK 1,,305 x j019 v/c~2 EOL HELD RTNDT
=
2 17,.7 F
k
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ST, LUCIE j.
EFFECTS OF THERMAL 'SHIELD REMOVAL ON PTS 1).
EOL FI UENCE 2)
EOL RT-NDT
ST.
LUCIE 1
"(32.EFPY M/0 T,S.)
THERMAL SHIELD WORTH~1.75 x FLUENCE EQL PEAK FLUENCE =.+ Q,95 x 10 N/CN EOL WELD FLUENCE
+ 2.35 x 10 w/cm I
(CONSERVATIVE UPPER BOUND)
ST, LUCIE - 1 ONSOINj PTS EFFORT l)
SURVEILLENCE CAPSULE EVALUATION 2)
UPDATED FLUENCE CALCULATIONS 5) 1OOX BELTLINE HELD ISI
gg0 II 180 I~OUHet Nozzle
///
I I
Core Shroud
Core Suppor't Barrel lf
.F..
t Reactor Vessel I f Thermal Shield
~ inlet iNozzle
263 Core.
tNidpfane Vs'essel Capsule Ass embl) g 4
Thermal Shield Reactor Vessel Core Support Barrel p~,d nlan Vit FIGURE F5-4 Elevation View
ST, LUCIE 1 UPDATED FLUENCE CALCULATIONS SL-1 9'DOT (SL-1 POWER DIST, CY 1-5)
SL-1 Hk DOT (SL-1 CY6 POWER DIST.)
SL-1 SURVEILLENCE CAPSULE BENCH1ARK
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