ML20067C954
| ML20067C954 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 12/01/1982 |
| From: | Root L IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML19268D482 | List: |
| References | |
| REF-SSINS-6820 IEB-82-03, IEB-82-3, NG-82-2653, NUDOCS 8212100295 | |
| Download: ML20067C954 (14) | |
Text
-
4) t Iowa Electric Light and Pbwer Company December 1 1982 NG-82-2$53
.I r s" Mr. James G. Keppler Regional Administrator Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Duane Arnold Energy Center Docket No: 50-331 Op. License No: DPR-49 Response to IE Bulletin 82-03, IGSCC
Dear Mr. Keppler:
3 This letter and attachments are submitted in response to your IE Bulletin 82-03 Revision 1, issued October 28, 1982.
In accordance with your request,thisletterprovidesresponsetothoseitemsinyourBulletinforwhich 1982. Additional information will be you requested information by December 1 developed prior to and during the DAEC dycle 7 refueling outage which is currently scheduled to begin on February 11 1983. This additional information will be forwarded to you as it is developed,.
I responds on an item by item basis to IEB-82-03. For convenience we have also reproduced the questions and requests for information ofyourBulletin.
Four additional attachments are provided which contain i
i i
detailed information.
Preparation and submittal of this letter and information to the NRC is estimated to have required approximately three man weeks of engineering effort.
l Estimates of resources that will be devotco to preparing future submittals will l
be provided in subsequent correspondence.
In accordance with your request, this letter and attachments are submitted under oath and affirmation.
IOWA ELECTRIC LIGHT AND P0 ER COMPANY f
b AM2.
8212100295 821201 BY PDR ADOCK 05000331
[ Larry U. Koot G
PDR LDR/WJM/dmh*
Subscribed and sworn to Before Me on Attachments this
/ce day of /?m,,,/a,v 1982.
cc:
W. Miller D. Arnold Nl44 8 d4 hill F. Apicella Notary vuulic in ana tor tne state or towa NRC Resident Office g
Ref: Comnitment Control No. 82-0434
/I, '*-
many E. sEnnEto if<'d,Q I tammisstoN EXPla!NG Po 1882. A CENTURY OF SERVICE -
?
$1PTEMBER 30, 1983 1
General DjinY
- l'O. lien 331. rether it,up<h, gama 334pg. 3;g,39g,44,,
f f Il a
T NG-82-2653 D
December 1, 1982 a
(1).
ATTACHMENT 1 IEB 82-03 Item 1 Actions To Be Taken by Licensees of BWR Facilities Ident_ified in Table 1:
1.
Before resuming power operations following the current refueling or extended outage, the licensee is to demonstrate the effectiveness of the detection capability of the ultrasonic methodology used or planned to be used to examine welds in recirculation system piping. This demonstration shall be made on representative service-induced cracked pipe samples.
Arrangements should be made to allow NRC to witness this demonstration.
This demonstration shall employ those procedures and standards, the same type of equipment (same transducer size, _ frequencies and calibration-standards), and representative UT personnel from the inservice inspection (ISI) organization utilized or to be utilized in the examinations at the plant site.*
Response to Item 1 The Level III Inspector that DAEC will utilize for the Cycle 7 DAEC refueling outage inspections is Mr. Elwin L. Thomas of the firm of Lambert, Macgill and Thomas.
Mr. Thomas has previously demonstrated on behalf of Northeast Utilities the effectiveness of UT methodology that is functionally equivalent to that to be employed at DAEC. This demonstration was conducted at the Battelle Memorial Institute in Columbus, Ohio and included samples of the Nine Mile Point Unit 1 Plant.
It is our understanding that representatives of the NRC were present to witness this' demonstration.
It is our intent not to repeat the demonstration by Mr. Thomas.
In the event the NRC believes a repeat of this demonstration is necessary, we request prompt notification to allow scheduling of a demonstration that will avoid impacting the DAEC refueling schedule.
I IEB 82-03 Item 2 2.
Before resuming power operations following the current refueling or extended outage, the licensee is to provide a litting of results of recirculation system piping inspections.
Response to Item 2 The requested information will be provided prior to resuming power operations following DAEC Cycle 7 refueling outage.
i 1
- We understand that Electric Power Research Institute (EPRI) has arranged to have samples from the Nine Mile Point Unit 1 plant available for industry l
demonstrations of UT methodology. The samples have been taken to Battelle l
Memorial Institute in Columbus, Ohio for characterization and subsequent use, l
l l
t
NG-82-2653 o
0:cember 1, 1982 (2)
IEB 82-03, Item 3 3.
Before resuming power operations following the current refueling or extended outage, the licensee (if the inspections indicate the presence'of cracks) is to describe the corrective actions taken and report these in accordance with the appropriate regulations.
~
Response to Item 3:
The requested information will be provided prior to resuming power operations following DAEC Cycle 7 refueling outage.
IEB 82-03, Item 4a 4.
To assist NRC's further evaluation of this issue, the following shall be submitted by December 1, 1982:
a.
A description of the sampling plan used or to be used during this outage for UT examinations of recirculation system piping welds and the bases for the plan. The description should:
(1) Provide an isometric drawing of the recirculation system piping showing all the welds, and the number of welds and their locations that have been examined or.will be examined.
(2)
Identify criteria for weld sample selection (e.g., stress rule index, carbon content, high stress location, and their values for each weld examined).
(3) Describe piping material (s), including material type, diameter, and wall thickness.
(4) Estimate the occupational radiation exposure incurred or expected and briefly summarize measures taken to maintain individual and collective exposures as low as reasonably achievable.
Response to Item 4a:
(1) Attachment 2 contains isometric drawings of the DAEC recirculation system and a matrix of prior and scheduled weld inspections fcr the DAEC Cycle 7 refueling outage.
(2) Criteria for weld sample selection for all recirculation system welds that have been examined since the 1980 refueling outage and those welds to be examined during the 1983 outage have been based upon stress rule index and carbon content.
In addition to the above, all welds in these recirculation system bypass loops have been examined during each refueling outage since 1975. Also, all welds in the recirculation inlet risers will have been examined once and more than 1
L
NG-82-2653 o
Decemb r 1, 1982 (3) fifty percent of the riser welds will have been examined a second time with the 1983 outage examinations.
The isometric drawings and IGSCC Susceptibility Matrix (Attachment 2) identifies all welds and the year of the latest examination. Also, the Stress Corrosion Cracking Evaluation Program Report - Duane Arnold Energy Center; dated April 23,1980 (Attachment 3) identifies the carbon content of material and the stress rule index for each weld.
(3) Attachment 3 identifies each component in the recirculation system by size and material specification and type. The main loop piping is 22 inch 0.D. Schedule 80 pipe and fittings.
The ring headers are nominal 16" 0.D. with nominal thickness of 1 and 1/8".
The header cap is 16" 0.0. with a minimum wall thickness of 0.708".
The inlet risers are 10" schedule 80 nominal size pipe and the bypass loops are 4" Schedule 80 nominal pipe size.
(4) The estimated occupational exposure for personnel involved in preparing for scheduled recirculation system inspections (insulation removal for example), conducting inspections, and restoring the piping systems to pre-inspection status is 37 man rems.
This calculation does not include exposure that would be incurred in the event any repairs are warranted.
The primary means that will be utilized to limit occupational dose is:
(a) the installation of temporary shielding blankets and (b) limiting worker time in radiation fields. Based on past experience, installation of heavy shielding or internal systems decontamination are not judged to be cost effective or effective in dose reduction due to increased exposure to install heavy shielding or to decontaminate systems.
IEB 82-03, Item 4b b.
A summary description of the UT procedures and calibration standards used or to be employed in the examination at the licensee's plant site. This description should include the scanning sensitivity, the evaluation sensitivity and the recording criteria.
Response to Item 4b:
Iowa Electric plans to use Ultrasonic Procedure #UT-27 Revision 0 with field changes in our next refueling outage. This procedure has successfully detected cracks at Duane Arnold in 4" schedule 80 pipe which was verified by Dye Penetrant Test after pipe removal. A description of #UT-27 Revision 0 is l
as follows:
(1) The primary reflection is 5% notchs for Class 1 piping.
L
NG-82-2653 Decemb:r 1, 1982 (4)
(2) Evaluation sensitivity is established by setting the nearest notch echo to 80% of full calibrated scale.
(3) Scanning sensitivity shall be 6 db breater than the primary response.
(4) A calibration check is required before and after each examination.
(5) Examiners must be certified at a minimum as Level II in Ultrasonic Testing to evaluate results and subsequent review and evaluation by Level III, will be r-ovided.
(6) Evaluation is in accordance with IWA 3100 (b) of ASME Section XI (1974) with addenda through Summer, 1975.
Iowa Electric plans to continue its policy of recording any indication determined to be a crack regardless of amplitude or size.
(7) Strip chart recordings are planned for recording shear wave results.
(8) All recorded chart signals shall be identified.
(9) Calibration blocks shall be of the same nominal size, thickness, material, and surface finish as the pipe to be examined in the 1983 outage.
IEB 82-03, Item 4c A summary of the results of any previous inspection of the c.
recirculation system piping welds which used the validated examinatio'n methodology as discussed in Action Item 1 above.
Response to Item 4c:
i sunnarizes the results of 1981 and 1982 recirculation system inspections. These inspections were conducted with functionally equivalent UT examination techniques as is discussed in the response to items 1 and 4b, above.
I l
IEB 82-03, Item 4d d.
An evaluation of the crack-detection capability of ultrasonic methodology used or planned to be used to examine recirculation system piping welds. This evaluation should result from conducting the demonstration required in Action Item 1 above, and should include a comparison of the service-induced pipe crack sample to those welds actually examined in the licensee's plant in terms of pipe wall thickness and diameter, weld geometry, and materials.
5 NG-82-2653 December 1, 1982 (5)
~ '
i
/
Response to Item 4d:
The requested information will be provided in a future submittal prior to DAEC resuming power operations following Cycle 7 refueling outage.
4 J
t
.. i O
a I
i l
i
(
i ye -
w-y e
my, w w pa---e-y----,v,,-,-o--
+
,-w9+
-4+,,.--
m y7-, e y 9
, - --~
r
,O - 1.20 1.21 - 1.50 STRESS RULE INDEX 1.51 - 2.00 2.01 +
RRA-J7 (5,7)
RCA-J 18 ( h RMA-J4 (5)
RMA-J8 (5) f RRD-J7'(5)
RMA-J10 (5)
RMA-J2 (5)
RMB-J5 (5)
+
fac -J'! (3)
RRG-J7 (5)
/
i, RMB-J 11 (5)
RMB-J9 (5) 2 RRF-J7 (5)
RCB-J21 (5)
RMB-J2 (5)
RRH-J7 (5)
RRB-J7 (5)
I '
RRC-J7 (5) l
(
S RCA J27 (5)
RCA-J34 (5)
RBB-J 1 * (5)
RRA/H-J5 (8 WELDS)(5) g o,
RBA-J7* (5)
RBA-JI' (5,7)
RBB-J7*
(5)
RBA-J6* (5,7)
RC8-J30 (5)
RRE-J4 (6)
RBB-J12' (5,7)
RBA-J8' (5,7)
RBB-J 68 (5,7) o RHC-F 2 (7)
RRF-J4 (6)
RHC-J1 (7)
RRG-J4 (5.7)
RB8-J8' (5,7)
RHD-F2 (2)
RRC-J4 (6,7)<
RHD-J 1 (2)
RRH-J4 (5,7)
RRD-J4 (5,7)
RRA-J4 (6)
REGlON Ill RCB-J3 (5)
RRB-J4 (6)
(HIGH SUSCFPTIBILITY)
RCA-J7 (7) RC8-J27 (4)
RCA-J:2 (1)
RMA-J5 (7)
RCB-
.7)
RBA-J9* (5)
RCA-JIS RCB-J31 (3 )
RCA-J13 (1)
RP%-J 7 (7)
')
RB8-J9* (5)
RCA-J24 (4) RCB-J41 RCA-J21 (4 )
RBA-J2 (5)
RM9-1)
RCA-J28 (3) RMB-J1 RCA-330 (7)
RBA-J3 (5)
RMB.
7)
RCA-J38 RP0-J12 (3)
RCA-J32 (7)
RCB-J6 (7)
RB8-J.
.5)
RMA-J1 RHB-J 1 (1 )
RCA-J41 (7)
RC8-J 7 (7)
RB8-J3* (5)
[
RMA-Jll (3)
RCA-J43 (7)
RCB-J33 (7) 5 g
RRA/H-J4A (8 WELDS)
RMA-J6 (7)
RCB-J35 (3,7)
-A, B, E, F (6)
RRA/H-J3 (8 WELDS)
N g
-C,D,G,H (5,7)
-A,B,E,F (6)
-C,D,G,H (5,7) g-RCA-J3 (1)
RCA-J4 (1) RC8-J24 (7)
RCA-J22 (4)
RCA-J6 (1 )
RCA-J5 (1) RCB-J46 (2 )
RBA-J10' (5)
RCB-J3 (1)
RBA-J12' (5,7)
RCB-J 25 (7)
RCB-J9 (1 )
RCS-J4 (1)
RBB-J10' (5) p RCB-J18 RC8-J 5 (1)
O.
RCB-J15 (1 )
RCB-J16 (1)
REGION lli (MODERATE SUSCEPTIBILITY)
RHB-F 3 (1 )
RCA-F2 (1) n 8
RC3-F2 (1 )
v RRA/H-F2A (8 WELDS)
-A,B,E,F (6)
REG ON I
-C,0,G,H (5,7)
(LCW SUSCyPTIBILITY)
NOTES In Service Sensitive Lines (4) Last examination in 1980 xxx Shop Water Sprayed Cooled (5) Last examination in 1981-(1) Last examination in 1976 (6) Last examination in 1982 (2) Last examination In 1977 (7) Scheduled for 1983 Ref uel Outage (3) Last examination in 1978
5 Y
l es 1
w
[
O s
si g
\\'
u j
wa Q
g a ' d $=
"o us j
e lP g
vr In r~-
.n9 a
"I T
f I
- 9. <CTA=
n, &~
N u
-v I
2 Q
$:C aY.
O!
=a f.
sm g
a c
d (A I
Wh.hga oN 15 ed
- 2 Gl w
vi et-(2 g
M ft L:
N k
l
~-
n h
Q
$ Ebb j
( h UJ E
'~QQ e c g =e ci <
g v
,T b
4
A 6
=p
)-
1 1
0 1
2 w
'g 3
9 y
'g U
p-
,*o.,
Uf L
u9 d
4@ 0 l
a
'[
wN N
m7 4
5
$N
<f 9 % af u q
$r Msqu M Ng GG6
,( [" 2
,3 e
m Uj.W m
y sy!
gz i
_.o A
~
5' g g-Q "k
c0
~
n.Jn
/
n zc a s
An n
N
$3 "
4 "9
k - :0 4
-6 u2 am
=
M.x g,g a
i WW Id n
M 4
R l
$k l
m I
s
e bE' g
k j$
E"$
i f
b f.$ %5i 'ff, Oh n e,
io o
L' g
@ if; b,1
~
o ro
~
3 1
i kkd 3
gt,
7k
' ;g
,o a
r 5
i A
t r2 g
t~
01
?
k Y
~
}
G 'W 33
,r V*a w
<g
'{
Nd g
3 g4 4
Ae
+g
,o
- z O
a
\\-
4 "d
.d en n
- d.Q*-
k',
Q N
J An g
N y
- j e
z w b
n. ggd*..,
b 0 gh
-r b
'A h
s h
17 p.
\\
a jW a
na n
~
l q u u ;L "1
US e d
,f,.
~9 & Mta'_,h-6
l.
J 8
m,
e d
o;8 9 s
l kn
'kE bh yg ru n
^
gg
%a
=
08 5
2 i
N 3 $d i
o4
/
6 2
.m t,
si,
n g
k a
e a
g n
b'8 4 R
g
$ " 50 p
4
,.-)
9
- j 4
0 a
.es q
8'R
,8 g
1 g
g g
u e
e, p-1
~
~
sM
$9 Dj'-
M i
s n.
-e II
'f n
N v$e-. sn e
.c; o -= ct an =;
. f/.
4 q
id i s'd T4 6 S W$ <,
l>
Bjici
,o i
8 c
u 9
'6
.>.)
m -s p
Bs N
'n b S b n ~ -h
7[
~
It, nzo c
2 3t.s q il g,
1 p % R S mr 9,"*
b as
.}u.
- b. beat. Neter I)elwAL-1BS r
L Rlib-
%CS, \\s" Iso.40. \\ t la N
}'N6 at4 N g.i t y as N
P9 KZl i-3b s jiq
.j J10
,xe m
'J l
'J
t' R!
4 E
4 I
.9 0
9 k
5 E- $
q
\\ 's e
.4 n\\
O o
k 7
c' s
- ~-
g e
%r, o
E 2n s
n' i
r 3
g g w-d' r$
- l
'g LA e
d 6
g "s z g,0x Sh 4
5Q-$
E' (4
di ai 63 H z n U
I a
,t s
li g
[f 44 I
('
0
'T n
is a
o h
N 1
- m 0F' W
"***0%
H m --
n'aumn f
r
~
M,Q' A + - +4 9
.O M 6
l h
il n
- e S
a 1
s e
4 1
cg 1
o 8
s sq 9
g
,s o
a d,
1 u
.o M
H3
'o "9 E
_.r_
eJ g
.o 0b.9 E
xP H
3 gJ.
I O
"M y
r e,
a n
i G
.n x
l - - --