ML17213B360
| ML17213B360 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 05/03/1983 |
| From: | Sells D Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-49, REF-GTECI-RV, TASK-A-49, TASK-OR TAC-51343, NUDOCS 8305120520 | |
| Download: ML17213B360 (20) | |
Text
MAY 3
1983 gag PS-<<~
LICENSEE:
Florida Power and Light Company FACILITY: St. Lucie Plant, Unit No.
1
SUBJECT:
MEETING
SUMMARY
- THERMAL SHIELD ANALYSIS On April 25, 1983, a meeting was held in Bethesda, MD with Florida Power and Light Company (FP&L) to discuss FP&L's plans to address the questions of thermal shock to the reactor pressure vessel with the removall of the thermal shield from St. Lucie Plant, Unit No. l.
A list of attendees is attached.
Vugr aph slides used in the FP&L presentation are attached also.
FP&L sees no problem with regard to thermal shock or embrittlement resulting from the operation of St. Lucie 1 with the thermal shield removed.
In sup-port of this initial conclusion, FP&L will conduct an evaluation of one surveillance capsule, update its fluence calculations,.and conduct a 1005 beltline weld inservice inspection.
In addition, all vessel welds will be inspected.
The survei llance capsule was scheduled,'o be removed on Apri 1 25.
The staff pointed out that the use of one capsule only to establish a beoch-mark may not be valid.
The metal pieces that have been recovered from the core have been prepared for shipment toB'attelle Columbus for examination.
01 lplnal Signed 4 Attachments:
As stated cc:
See next page Donald E. Sells, Project Manager Operatipg Reactors Branch 83 Division of Licensing pSgp 83p5pg 83p5g
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/83 NRC FORM 318 (10-80) NRCM 0240 FFICIAL RECORD COPY US0 PO: 1981-33&960
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SUMMARY
DISTRIBUTION Licensee:
Florida Power
& Light Company
- Copies also sent to those people on service (cc) list for subject plant(s).
Docket File NRC PDR L PDR NSIC ORB83 Rdg ORB03 Summary File JHeltemes BGrimes RAClark Project Manager PMKreutzer OQ.D ELJordan
~
JMTaylor ACRS-10 NRC Participants 4
'4 4
4 4
Florida Power 8 Light Company
~ ~
cco Harold F. Reis, Esquire Lowenstein,
- Newman, Reis 5 Alexrad 1025 Connecticut Avenue, N.W.
Washington, D. C.
20036 Norman A. Coll, Esquire McCarthy, Steel, Hector 8 Davis 14th Floor, First Natipnal Bank Building Miami Florida 33131 Mr. Jack Schr eve Office of the Public Counsel Room 4, Holland Building Tallahassee, Florida 32304 Resident Inspector c/o U.S.N.R.C.
7900 S. AIA 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 Planning and Devel pment Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Builling Tallahassee, F1 ori da 32301
Attachment LIST OF ATTENDEES THERMAL SHIELD ANALYSIS MEETING APRIL 25, 1983 NRC R. Clark B. D. Liaw D. Sells R. Klecker P. Randall L; Lois F. Litton P.
Leech K. Heitner FPKL D. Chancy T. Diliard J.
Moaba CE T. Gates D. Peck S. Ritterbusch
ST, LUCIE j.
PTS NEETING AGENDA j,
REVIEW PRESENT PTS STATUS 2,
EFFECTS OF THERMAL SHIELD REMOVAL ON PTS ONGOING PTS EFFORT SCHEDULES
ST, LUCIE - 1 PRESENT PTS STATUS 1.
MELD C8ENISTRY 2,
FlUENCE CALCULATIONS RT-NDT PREDICTIONS
FIGURE F6-1 ST.
LUCIE NI REACTOR PRESSURE VESSEL HAP INITIALRTg)T IN 'F o
c CV 1
=e 1
e 20 Vl CtjX 60
~ I C ~ S ~3' 203HZ@
C 8 2 EZP.'
8 ILLS IOO C3
~ 3 C V-I QD 2 203EZi3 C-7 2QLl C
V 3E22 p
',tt,
- /
/t Ce
>>/
tw C
/- t 1
CI I 40 4J CK I
ISO a
220
~2 C ~ 813 CK3 3 203EZ8
+CORE C -8.IKh8 C ~ 8 ~
2'60
-0 ISO ggb 360 A2 I NUTAAL LOCAllUll,DEGREES
TABLE FG-1 ST.
LUCIE UNIT k'1 REACTOR VESSEL HATERIALS Product Form I'iateria1 Drop Height Identification NDTT
'F Initial RTND~T'F Nickel
~PI>os horus-Co~per Ciiomicdl Content~i)
Plate Plate Plate Plate Plate Plate Pl ate Plate Plate Held Held Held Held Held C6-1 C6-2 C6-3 C7-1 C7-2 C7-3 C8-1 CB-2 CB-3 1-203 A,B,&C 2-203 A,B,&C 3-203 A,B,&C 8-203 9-203 10
-30
-10 0
-30
-30
-10 0
0 N/A N/A N/A N/A N/A 10
-30
-10 0
'a Oa 10 20 0 a Oa
-50
-50
-50
-60
-60
.53
.53
.53
.64
.64
.58
.56
.57
.SSd
.99
.20
.64
.71
.11 b
.14b 14b
.11
.11
..11
.15
~.15
.12
.22
.12
.30
.21
.23
.012
. 011
.Oll
.004
.004
.004
.006
.006
.004
.015
.018
.013
.016
.013 N/A b
c d
Not Available Determined using Branch Technical Position NTEB 5-2 Estimated 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)
ST, LUCIE 1 CURRENT FLUENCE CALCULATIONS (REF.,
CEN-189)
NS-2 'O DOT PROFILE (NS-2 POMER DIST,)
(IS-2 CAPSULE BENCHNARK SL-1 POINT KERNEL PEAK (SL-1 POMER DIST,)
I.b HORNAL11EO FA5l FUIX ST.
LUCIEI AZIMUTHAL FLUENCE VARIATION hl PE5K OjLII IHISFhK b.5 b.i Jb l5 lIElh DEKE FIGURE F5-3
FIGURE F6-2 ST.
LUCIE JI REACTOR PRESSURE VESSEL HAP ADJUSTED RTNPT IN F (12/31/81) 3.55 Effective Full Power Years 0.33 x 1019n/cm2 Peak Surface Fluence 20 Ih
~
Wx eo 4J uj Loo tva
~ /
l 203-2-203-C ~ 6
~ 3
+
C ~ 7 ~ >
~
1203" 2~203-C.6.2
~23 C.I 2 C ~ 6 ~ I'3 C
~ 7 ~ 3 14o ORE cJ a:
ieo a
~2 3 203'
~ 8i3 pi+
3203'
~ B~l C ~ 8 ~ 2 220 ceo -0 F80
'60 A2 I NUTIIAL LOCAI I0!I, DEGREES
ST, LUCIE - 1 CURRENT STATUS EOL PEAK FLUENCE =.2.85 x 10 v/cz (Ol N~v)
EOL HELD FLUENCE = 47.5% x PEAK 1,545 x 10 N/CN EOL MELD RTNDT
=
2 17,7 F
ST, LUCIE - 1 EFFECTS OF THERMAL SHIELD REMOVAL ON PTS l)
EOL FLUENCE 2)
EOL RT-NDT
ST.
LUCIE 1
"(32 EFPY W/0 T,S,)
THERMAL SHIELD WORTH~1,75 x FLUENCE EOL PEAK FLUENCE O 0,95 x 10 w/cN EOL WELD FLUENCE) 2,55 x 10 x/cm EOL'ELD RTNDT
'252 7
F (CONSERVATIVE UPPER BOUND)
ST, LUCIE 1 ONGOING PTS EFFORT 1)
SURVEI,'LLENCE CAPSULE EVALUATION 2)
UPDATED FLUENCE CALCULATIONS 5) 100% BELTLINE HELD ISI
180 I~Oullel Nozzle
///I I
I I
Core Shroud
Core Support Barrel Jg
(~0~
I."
Reactor Vessel r
- inlet inozzle C
263 Core.
Midplane Vessel Capsule Ass embl~
r I
SJ Thermal Shield
\\
7 Thermal Shield Reactor Vessel Core Support Barrel enlarge' "lean>>'e-FIGURE F5-4 I
elevation Vievi
ST, LUCIE - 1 UPDATED FLUENCE CALCULATIONS SL-1 RO DOT (SL-1 POWER DIST, CY 1-5)
SL-1 RO DOT (SL-1 CY6 POMER DIST,)
SL-1 SURVEILLENCE CAPSULE BENCHNARK
T