ML20037B070
| ML20037B070 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 05/20/1977 |
| From: | Desiree Davis Office of Nuclear Reactor Regulation |
| To: | Bolger R COMMONWEALTH EDISON CO. |
| References | |
| TASK-05-06, TASK-5-6, TASK-RR NUDOCS 8009030783 | |
| Download: ML20037B070 (4) | |
Text
- . ~ -
j
's 31STRIILUTION Qhtcket 15)
JRBuchanan HR DRs (5)
^ -
m.
...i
.::47/2 a ORB #2 Reading DkDavis e-S~; / ;M~
MAY 2 0 M-RMDiggs Cc mom.calth Ecisen Cc :pany RDSilver RBevan
' m.
?.. L. Sol;cr'r, esident
.lTT: :
is,i st:nt Vice P P0'Connor iost Office oox 767 4
GZwetzig Cuicaco, Illinois $690 0 ELD
,i 01&E (3)
DEisenhut i
Gentl enen:
TBAbernthy DE:
DRESDE!! ilVCLEA~< POUER STAT 10:1 Ui!IT NDS.1/2/3 OUAD CITIES i:UCLEAP, PC'JER STATIG'i U !IT l 05.1/2
'c revis o / c :.0 re_deivea frca reactcr vessel materiti 3"recillince
.nrcerc.m indicates tr.ht ti,c naterial, used in reactor vessel fabricction ray have a wider variation in sensitivity to radiation da" age than originally anticipated.
In addition, sone reactor vessels incorporate are than one heat of naterials, including weld netals in their beltline regions, out all of these heats nay not be included in the reactor vessel
.#.terial surveillance progran.
i,1taouch cer reviou of these data does not reveal a basis fer concern regarcing continued re.'ctor vessel integrity over the nat several y0ars, the information coes indicate the need f or e ~detailco review tac r.aterials enployed in reactor vessel ccnstructicn (in licht ntof tnis recent cata) and a review of ti.e specircns employed in the surveillance progran to cetemine if ti>e present specimens reasonably represent tile liniting naterials in the reactor vessel beltline region.
In order 'to perfora these reviews, we will need the intornation listed in the enclosurc relative to each of your recctor vessel (s) and associated surveillance specimens.
Accordingly, you are requested to sut, ply one signed original and 39 co sies of the inferr6tien listed in the enclosure siithin 00 dys of recaict of t';is letter.
nis rco: :st for ; meric infor,:ation s.e s 3pproved af U.N enc: r e
- 1,
< t clearence weer :.-190;:<5 (M72); this cl<:crence scircs f'
e lv.il, 197 7.
A 3
f
/
g9C Sincerely,
- 4
' DOR:0RB#{
0 Wal @ne by DOR:0RB #2 sa-W/)
J we i9 P0'Connor:ro RBevan
[ //7/}')
f//f/ h7
? "
- , I N ' 2 ti " 9 0I E/M 7 7 M R:0RB #
zi E3 sir, cf S.cIrati.E PeactorF i
.. D.d..G. R.m..#. 2
. D D A@,
~
RDSil-r
- - s*;,
.m a.n ? T.h.C.V& ' W n l
S. E /(?.).
Lem AECOt s (Rev. 9.H1 AICM 0240 TT u. s. cov e.~= r mt.as~ema o r rie rs s e n.s a s.ise Q
l s
MAY 2 01977 2-Commonweal th Edison Company I
cc w/ enclosure:
Mr. Charles Wnitmore Fresident and Chairman Iowa-Illinois Gas and Electric Company 206 East Second Avenue Davenport, Iowa 52801 Mr. John W. Rowe Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor Chicago, Illinois 60603 Anthony Z. Roisman, Esquire Roisman, Kessler and Cashdan l
102515th Street, N. W., 5th Floor Washington, D. C.
20005 Moline Public Library 504 - 17th Street Moline, Illinois 61265 4
Morris Public Library 604 Liberty Street l
Morris, Illinois 60451 s
e I
o e
t s
i i
I REQUEST FOR INFORMATION REACTOR VESSEL f1ATERIAL SURVEILLANCE PROGRAM i
l 1.
Provide the estimated maximum fluence (E>l ftev) at the inner i
surface of the reactor vessel wall as of March 31, 1977.
t 2.
Provide the effective full power years (EFPY) of operation accumulated as of March 31, 1977.
3.
Identify the firm or firms that fabricated your reactor vessel.
4.
h.
Provide a sketch of the reactor vessel showing all materials welds, in the beltline region
- and provide an identification number for each material.
b.
Provide the following inforniation for each of the weld's in the beltline. region:
(1) Shop control number or procedure qualification number; (2)
Filler metal and heat number; (3)
Type of flux and batch number; j
(4) Welding process'(sub arc, electroslag, manual metal arc, etc. )
1 (5)
Post-weld heat treatment; 1
(6)
Chemical composition (particularly Ce, P and S content);
i (7) Drop weight TriDT; (8) RT I
~
t1DT (9)
Charpy upper shelf energy (unirradiated);
li (10) Tensile properties (unirradiated);
(11)
Firm performing weld if more than one firm participated in welding; (12) The maximum end-of-life fluence at the vessel inner wall.
- As defined in 10 CFR 50, Appendix G, Section II.H.'
l
o w
i !
c.
Provide the following information for each of the plates or forgings in the beltline region:
1 (1) Plate or forging serisl number; (2) Plate or forging heat number; (3) Plate or forging material specification number; (4) Plate or forging supplier; (5) Plate or forging heat treatment;
^
(6) Chemical composition (particularly Cu, P and S content);
(7 ) Drop weight T I
(9) Charpy upper shelf energy (unirradiated);
(10) Tensile properties (unirradiated);
(11) The maximum end-of-life fluence at the vessel inner wall.
5.
a.
List the weld, plate and forging materials included in the vessel material surveillance program.
b.
For each weld listed in 5.a., provide the infomation requested in items (1) through (11) of question 4.b.
c.
For each plate or forging specimen listed in 5.a, provide the infomation listed in items (1) through (10) of question 4.c.
d.
Provide a copy of the report which describes the surveillance progran for your~ reactor vessel (s), if available.
1 m
_