ML20072T008
| ML20072T008 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 03/28/1983 |
| From: | Van Braunt E, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, ANPP-23374-BSK, DER-82-42, NUDOCS 8304070410 | |
| Download: ML20072T008 (12) | |
Text
,
~'
Docket Nos. 50-528/529/530 Mk"gg) 50.55(e) Report 1
Y ' 3 " pl. G 9
Anz n Public Service Company Ro. BOX 21666
- PHOENIX, ARIZONA 85036 7,-f$ i O ~.
March 28, 1983 ANPP-23374-BSK/RQT U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chief Reactor Projects Branch 1
Subject:
Final Report - DER 82-42 A 50.55(e) Reportable Condition Relating to Unit 1 Reactor Coolant Pump Pressure Tap Nozzle Weld Leak Due To Overheating Stainless Alloy File: 83-019-026; D.4.33.2
Reference:
A) Telephone Conversation between J. Eckhardt and G. Duckworth on July 9, 1982 B) ANPP-21577 dated August 9, 1982 C) ANPP-22204 dated November 4, 1982 (Time Extension)
D) ANPP-22609 dated December 28, 1982 (Time Extensiva)
E) ANPP-23166 dated February 28, 1983 (Time Extension)
Dear Sir:
Attached is our final vtitten report of the Reportable Deficiency under 10CFR50.55(e), refererced above.
Very truly yours, b
/
'hp E. E. Van Brunt, Jr.
F APS Vice President, Nuclear Projects ANPP Project Director EEVB/RQT:wp Enclosure cc: See Attached Page Two 8304070410 830328 PDR ADOCK 05000528 Se~
PDR Y-e-
U. S. Nuclear Regulatory Comunission Page Two ANPP-23374-BSK/RQT j
cc: Richard DeYoung, Director
- Office' of Inspection and Enforcement U.-S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods,.Jr.
G. C. Andognini.
J.'A. Roedel D. B. Fasnacht i
A. C. Rogers 1
B. S. Kaplan-W. E. Ide J. Vorees.
l J. R. Bynum-D.'D. Green P.-P. Klute A. C. Gehr W.~J.-Stubblefield W. G. Bingham R. L. Patterson
- R.-W.; Welcher l
R.'N. Grant l-D. R. Hawkinson
.L._E. Vorderbrueggen G. A.~Fiorelli.
i I
e
- ]"
FINAk, REPORT-DER 82-42 H
DEFICIENCY EVALUATION 50.55(e)
'1 ARIZONA PUBLIC SERVICE' COMPANY (APS)
PVNGS' UNITS 1, 2 & 3 1
- i I. ' Description of Deficiency While filling the' reactor coolant system for initial hydrostatic tests
^
E
.(no fuel in reactor), a leak was detected from the discharge pressure-l ':
tap nozzle on Reactor Coolant Pump 25.
This nozzle consists of a nickel-chromium-iron piece which is welded (partial penetration) to the
' interior of the pump discharge nozzle and to a Type-316 stainless steel L
external piece. This external piece has a socket-weld end which receives l
[
connecting piping. The leak was through the wall of the stainless steel
'X portion of one pressure tap nozzle on Pump 2B only.
There are two such j
pres'sure nozsles.(suction and discharge) on each of four pumps, or eight i
per NSSS. Only one of eight leaked.
I
[
Investigations into the post weld he.e erwinent practices for the pump nozzle to main coolant' piping weld revealed that's three-hour soak at 1150*F caused the pressure tap nozzle to be exposed in the sensitizing range for that material. The upper or stainless steel portion of the
< pressure tap had been sensitized during.the field weld post weld heat
[
treatment in February, 1980, and then subjected to a corrosive environ-
. ment causing intergranular attack and leaking of the pressure boundary.
The corroding species could not be identified during subsequent metal-lurgical examination of the failed pressure tap, however, fluoride-
' -containing contaminants will cause intergranular attack. The other seven nozzles apparently had not been exposed to the corrosive environ-ment:since being exposed to post weld heat treatment,and successfully passed the hydrostatic tests.
~
There are flow restrictors.in the nickel-chromium-iron portion of these pressure tap nozzles. Failure of one nozzle or piping system outboard of these restrictors would allow orderly shutdown using normal makeup.
s
?However.since all the stainless steel nozzles have probably been 4
sensitized to some degree, there is-the potential of more than one failure occurring. Since core' load had not occurred, there are no-safety implications for this event. However, if this condition had gone
- N uncorrected, then simultaneous failure of two or more nozzles may have Q
.potentially created a small break LOCA. -This condition is therefore evaluated as reportable under the requirements of 10CFR50.55(e).
'II.-.
Analysis of Safety Implications N
- The stainless steel portion of the 2B nozzle was returned to CE Windsor-Nuclear Laboratories for investigation., It received an ASTM A262 Practice'E test.
In addition, a similar but uninstalled complete p essure ta'p nozzle was also returned. This latter nozzle was put l
,J b
2-through a post-weld heat treatment cycle, and then the nickel-chromium-iron portion received a modified Huey test for sensitization. The base material was not sensitized, but the heat-affected zone was.
III.- Corrective-Action
- For Units 1 and 2, all of,the pumps' pressure tap nozzles will have the stainless portion of the nozzle removed and replaced by a double socket piece.ofLinconel (essentially a custom coupling for the discharge tap and custon' elbow for the suction tap). Replacement will occur prior to core loading. Corrective action wi.1 be completed as per CE letter V-CE-16870 dated August 12, 1982 and V-CE-17050 dated September 3, 1982.
For Unit 3, the corrective action plan is outlined as follows:
-1.. Post Weld Heat Treat (PWHT) the casing nozzle girth welds with the pressure taps nozzles in place. After PWHT, remove the stainless steel portion of the nozzles as was done on Unit #2.
- 2. - Install replacement couplings in the same manner as was done on Unit
~
CE is conducting a continuing investigation of the potential for i
corrosion of the nickel-chromium-iron material which receives post weld heat treatment. - It is anticipated that the results of this investigation
. will assist CE in-implementing a corrective action plan which will preclude recurrence of this condition in future projects.
Y B
l r
v Tr--
a r,y m
p yg-7 e
-e y
am+*w m--
me-
.q
-r.
--W--em
-u-m-
,.c.
c c
C E P:w:r Sy:t:ms Tel 203/6881911 Attachment to DER 82-42 Cornoustion Engineering. Inc.
Telex 99297 1000 Prospect Hill Road Wincsor. Connecticut 06095
(
/23w7 hS MS September 3, 1982 V-CE-17050 SEP 19'82 t,,
A ' -
p Mr. W. J. Stubblefield N*
Z Bechtel Power Corporation
-A-ZU,"
P.O. Box 49 e
{U Palo Verde, Arizona 85343
Subject:
Arizona Nuclear Power Project bi mi Reactor Coolant Pump Pressure 1,. ' "
Tap Replacement Unit 2 - Information us
__ C*
Required by Bechtel
_u e
Reference:
(A) CE letter V-CE-17031 dated 9/3/82 Gib Subject Unit 1 RCP Pressure Tap Replacement 7,,',"
Enclosures:
(1) C-E Manufacturing Order No. 9403834 E
(2) C-E Manufacturing Order No. 9230163
Dear Mr. Stubblefield:
(
In response to the request of the field for the subject pressure tap replacement work for Unit 2, Enclosure (1) invokes the revised pump specification which moves the boundary. The revised specification (in paragraphs 2.3.8 and 4.1.15) forwarded as Enclosure (1) to the referenced letter, moves the boundary uf the pressure tap from the former field stainless socket weld to the end of the inconel tube of the pump suction and discharge nozzles.
The replacement inconel nozzle coupling design has been approved by C-E Engineering and formal supporting documentation will be forwarded for the design.
CE-Avery Field Engineering Service has been authorized by the Enclosure (2) manufacturing order to replace the Unit 2 suction and discharge nozzle pressure taps under their Section III code authorization in the field as you have requested.
t The above responds to the field requested information by Bechtel to move the code boundary of responsibility on the RCP Nozzles for Unit 2.
Should you have questions, please advise.
ler *
- yours, zg
. Fer, s n Project Manager CF/VSK/mg i
Enclosure cc: Messrs:
E. E. Van Brunt, Jr.w/e J. W. Dilk W. L, MacDonald G. C. Andognini w/e G. A. Butterworth l
J. Vorees S. N. Mager w/e W. H. Wilson S. W. Shock w/e T
W, G. Binoham w/e D. B. Amerine w/e
4 O
O O
O
.O O
O
.O P
9o ( r]
p p
e c
c ~ ~
~
~
__(..; PO, WER
~~
c ususnON ENGINEERING,INC 2
1000 PROSPECT HILL ROAD gp E
CO/ JS d f rCNIERiNG INO TEL. 203 6881911/TWX 710-4471870/ TELEX 099 297 m
4.
JHIPPING TACS, P A CICING LISTS g AN3 SH.PPING PAPER $ MUST INCLUDE O
f( NM1 ~d@
g THE APPLIC A B LE C-E CONTRACT NO
[ CCMPONENT CODE NO.. AND ORDER NO.
.~
"N
'ND vtNOO3 CODE l
L u h u e L b ) r a '..
TO:
Y-C 4 - G O 5 0 ko96a% ~
t f.EFER COMMUNICATIONS TO
- NR N /
s a T c.e4 M 20th of FOLLOWING MONTH suvan acct.no.
CO NT R ACT NO. & Sa cT.
EMOP JO B PeO.
.14373
~
,m.v.
.. T c-.....
,,,, g,,
(TEM QUANTITY COMPONENT CODE DESC RIPTION EVENT PRICE 31-14-54-0200 REACTOR COOLANT PUMPS The following specification revision is invoked on this order.
t This revision supersedes all previous revisions:
CE Project Specification for Reactor Coolant Pumps for Arizona Nuclear Power Project No.14273-PE-480, Rev. 03.
Five (5) copies of the above specification are enclosed.
i INVOICE 00 NOT f
4 TAX INvolCE REGISTRATION NO.
1 TAX
/
.DDaisONAL INFORM ATION
/
raan. acLeast out Vendor: CE Avery OTHen Au Mo T fa e
N.A.
A
/a O te T R A C T hAME RE u ss(T s ow w n,T E OT HER AUT MO R4T Y (St A*sPP - Unit #2
/'
. au*c Tor c7 n.
oTMca auTMonsTv tes 14373 ^ um (, gagg o4 g
ocef wacT t st aM AT E vaLug as or cowT. ADM**e.
neo o. sMarree.G oATE
' A./ **
ER.
GUA 7T T A5bW R A NGL Y
MA kD.
i
O C.
()
6t Co IJ t
s' v
O{O
+
J O
O O
~ ~ ' ' ' COf.tBUsTION ENGINEERING, INC.
- ~ ~ ~ '
,g_ POWER
,000,,o3,,c; mot no,o
..=L. ; SYSTEMS
..gg;-
,,so30,, coyy, o,og, 7 ;p m gC.yp
$*b t _
tp T L_
COf/BustiotJ Etd3'4EERaN3 INO TEL.703 GSB.1911mvX 710 4471870/ TELEX 099 297 l
lNew Order
=-
W-
-".a sdy M" d d!) D D. E3 AL.
SHIPPING TACS PACKING LISTE AN) SHIPPING PAPER'S uust INCLUDE 1
THE APPLIC A BL 1 C-C CONTRACT N O.,
g C*MPINENT C001 NO AND ORDER NO.
,,gg o,
' I ^
^
VEN'OR CODE
% (-t.es.ue+.CF)
To T0:
bC6.1~703O i
N.O. 923 o i f,.3 L
S T
4E 8 E2 COMMUNICATIONS 10.
4 suTEn Acct.No.
cont R Act no. a sect.
swop eos no.
y~ u s8 70th of FoLLOWING MONTH 14373 SMer oM P,a.s. Po t M T sMsPP8NG CM ARGES EMSP V8 A ITEM LUANT4TY COMPONENT CODE D ESC RIPT80N EVENT PRICE 31-14-54-0200 REACTOR COOLANT PUMPS 1
Install inconel couplings on suction and discharge nozzle pressure taps in accordance with:
CE Specification for Standard Plant for Reactor Coolant a..
r Pumps No. SYS80-PE-480, ~ Rev. 02.
b.
CE Project Specification for Reaptor Coolant Pumps No.
14273-PE-480, P.ev. 03.
ASME B&PV Code,Section III, Subsection NB, 1974 Edition.
c.
d.
CE-KSB Instruction Manual No. 8109-101-500, Rev. O.
CE Avery Quality Assurance Field Manual.
e.
f.
CE-KSB drawing C-8000-101-2017, Rev. 01, Wall Static Pressure Nozzle - Suction Safe End.
CE-KSB drawing C-8000-101-2018, Rev. 01, Wall Static g.
Pressure Nozzle - Discharge Safe End.
comuoosTv cooE 1NVOICE
- 00 NOT I%
'lNVOICE REGISTRATION No.
TAX TAX F A BR. MELE ASE OWE ADDulON AL sNF DAM ATiON.
V mdor:
CE-Avery oTHER T
j 8/4l e Vn:. '
- W 5269o4 R AT ER QT ML A Au 61 %
i e r.
RE visa oh CoteT H Aci h AME 7
o-
~
ANPP Unit #2
. su EcT.w-ovnER Auf moRave ecs t
- IYgW76 J f5 cnAwaETo He p.
'. d
. G V A LITY A 5 5W M A NIE csN T Act EST8M ATE V ALUE Ab oF CONT. AD*d4M.
MEQ o.SH6PP4N(e oATL
. bJ PV./ WC6. P 4Sk..
y
C E Power Systems
(
(
Tet 203/6881911
,'
- C moustion EngineennG In:.
Teux 99297 1000 Prosoe:t Hill Arc Wincsor. Ccnne::icut o6095 Attachment to DER 82-42 R"A POWER
/ w 9,;2o
(
umsSYSTEMS
- o. -
na N. 6.0 2-
.r.
6 $
^
M 16'E R
A I
y... -, --
Mr. G. C. Andognini T
.'l.50T Arizona Public Service Company ea=
P. O. Box 21666 - Sta. 4015 Phoenix, Arizona 85036 g^gy n
Subject:
Arizona Nuclear Power Project 4
Units 1 and 2 Reactor Coolant n i a Pump Pressure Nozzle Sensitization 0"
~
CC, CWilms
Reference:
(A) C-E Letter V-CE-16760 dated July 19, 1982 1:t 0 72
~
Subject - Unit 1 Reactor Coolant Pump 2B wa Pressure Nozzle Leak 10CFR50.55(e) Reportability 1 ElUf' aw Oc
Enclosures:
(1) C-E-KSB Sketch SC-8000-0098 Rev. 00, Alteration ec_
of Discharge Nozzle Pressure Tap t5 C
(2) C-E-KSB Sketch SC-8000-0099 Rev. 00, Alteration $$
of Suction Nozzle Pressure Tap
{
Dear Mr. Andognini:
Enclosure (1) to Reference (A) described in general tenns the corrective action necessary to remove the sensitized 316 stainless steel RCP pressure taps and to address the sensitization of the inconel Heat Affected Zone (HAZ). The purpose of this letter is to delineate this action in detail.
PVNGS #1 A.
Discharge Pressure Tao 2B 1.
Perform thorough visual examination of pressure. tap from inside the primary pipe prior to fuei load and report results.
2.
Perfonn dye penetrant examination of J-weld inside primary pipe to include the Heat Affected Zone (HAZ) at the same time.
B.
Discharge Pressure Taos IA, IB and 2A 1.
Remove the 316 stainless steel portion of the nozzle, the weld and as much as 1/4" of the inconel portion as possible. Return the removed portion to C-E since it is intended that the HAZ of the inconel be inspected at C-E Windsor. However, there is concern that access to the replacement fillet weld shown on Enclosure (1) might be overly restrictive. An optimum cutting elevation should be selected and its affect on the overall length of the replacement nozzle evaluated versus the field connected pressure pioing.
For Unit 1, replacement pressure nozzles have been fabricated to the Enclosure (1) dimensions.
T
c Mr. G. C. Andognini
(
August 12, 1982 Page 2 V-CE-16870 2.
Conduct a hydro on the completed field welds.
C.
All Suctton Taos 1.
Enclosure (2) depicts the removal of the stainless steel portion at about i
the centerline of the weld. This location of cut was assumed to be optimum for two reasons:
.1 a.
There would be sufficient access to make the fillet weld.
~
1.000'010 socket w uld I
b.
Dressing the stub OD so that it fit into the be a reasonable task.
If dressing the OD of the shop stainless steel-inconel weld is easier than anticipated, the location of cut could be raised slightly. For Unit 1, there replacement suction pressure nozzles have been fabricated to the Enclosure (2) dimensions.
2.
Hy'dro test the ' completed field welds.
PVNGS 82 A.
All Discharoe Pressure Taps
(
1.
Same steps as B above including returning the cut-off nozzles to C-E Windsor.
B.
All Suction Pressure Taos 1.
Same steps as C above.
The replacement pressure nozzles have not been fabricated for Unit 2.
l There ~are four-(4) similiarly constructed pressure nozzles in each of the hot legs near the steam generators. They are approximately 44 inches from the centerline of the steam generator to hot leg field welds. We feel it is prudent for you to i
perform a re-review of the post weld. heat treat procedure for these welds on Units 1 and 2, to detemine if these~ pressure nozzles have been subjected to j
sensitization temperatures during post weld heat treatment. Please infom C-E l
of the results of this review.
l C-E has been proceeding in the interest of maintaining safety and schedule to provide a resolution to this problem. We must, at this time, request that a Field Material Requisition be issued to cover our expenditure of man-hours and material costs. Your attention to this matter is requested.
i V
1
- ours, C. Ferg Proje 6 % nager CF/ DEW /VSK/eh T
. ' Mr'. G. C. Andognini
- ~
Page 3 August 12, 1982 V-CE-16870
(
cc: Messrs:
E.E.VgnBrunt,Jr.-w/e J. Vorees - w/e W. H. Wilson W. G. Bingham - w/e R. H. Holm J. W. Dilk G. A. Butterworth S. N. Mager D. B. Amerine - w/e W. L. MacDonald J. M. Allen - w/e n
.o.
>m mm.
m k
4 I
e e
/
e i
J
s.
'~'
4 m
Ms t8 2/ '.y//,; / / / / / m x-x N
H
.Y/////r/, Q NC h u % (I.)
"T-o
~
m N.-CE w s7o
\\,
yy
\\
N--rzca N\\N N
acce Ux t...s. ~
~
oa i
GlW#M B/SO/4ME AU22"tE
\\\\\\
' \\ \\ \\ s\\ \\ \\ \\\\M
(.
Paswse rap
\\\\\\ \\
s tw r.ct:t:r-a
. v'd an A
o y
~~-
pfA I
sk i
.us.r.cvs- :
- o t *'s.r. cur reasedne n Lemn* Reavoreo m usee.on-heenHY4P4 fHTERK406 OR* ret.D /*/l'/Mts.
- t. w c~aons-d xxcHriVGD C.0 PKR M
COUPL/Nnr.. sea wre r Na-13S' f.a1,,05 TNGM 92 o f PV
! [0;..
n,,< rt. : so rsg
'.
- M I M '
M APw'M
.f
,1-ls d u u 'J X W N N N K W 7-""-"I
~
l{g f' "'"'RNWWNNN.g i
1
.l i.
.o
~
f fN3YAUATDv ep Cbupum PRELIMINARY 70 worzcc werg r/w. ear-tor.ma p{
FOR INFORMATION ONLY t
f i
ec.svu.cv as T,**'[----- Td8A-j Q
CE-MS PUMP CO. INC I
N 7-n e $
htwissatore. 8tM. t?89 a
e 3
em
."..7..t.7.%.'
s
=2 m.s.
s/ e f er no. eu.a aw a -~ ~ ~ ~r== c-1 cc-x.se nw ::ggr;?;[a, i
W E /0/
PEE.$$UM _7MP
- I
= s I
I Sc-eae- 009dlc_
o r
I I
g l
. m:r.
-,....,.,..,. _ _s; i
i 1
.. ~,... -........,,,
.-..-.g.,,...............
m g.
i, soea nea P.
- -t u r a re s 7/
N C Loa.ues (.2) g Y-c G. _ )(og f o x \\M \\ INTI. / /
b
\\\\
/
g \\; N q
I
- ANN \\
N is N1b /_ / /
,' -/
(
MnEL8' ItGC4 l
'i Cur 0F'f cdR.5fCT/0N N02'Zl.E B[9f,
~
l pressuge nap.
ffffffb,)/
yh'* &
]
1 s
,,o
- AV-o y
O
)
)F
, y J A4$'fA5
/
k
,, e /.
i D/4
.sf[*E J
pagg."o
,39e'*##E
$ter betsssnet rop pn teos vs.neauonen to
. ? 6t& * **VS tteNewmets oor m row.
m gg' * **~~1 4
i a e.n ceom orsauwco ao. rm i
l
." ic,
xa.z w rn oc:iwe m t n ne cvot oe >+ carrow, Mo enpEwo4.
. - - ~ -- e cognux; :,ae aer,,
s
" ^ " * ' "
. SC-8mO-M99 L
m M W//////
~
l H-sj
~.
' u x x x x af f f f f) s i
s s
\\/////
/
R
(/
PREllMINARY A
FOR INFORMATION ONLY nsraurion or mus.a TD MTZXt.E NECK P/M 8 0 0 0 2 / 4_. 0 8 P.
"C-p, %c4cjP'$t,fl
~r~
s-g,z.t.ra pgp co. C.
eew=,= %... _
. w=u EniE:..=E== =
= "
. _,., ~.
CGKSB PUMP
^LTEAA' M" '"
E TYPE BCP seicrioM No.ra presnuxe
~:~ **::
pc-stvo-covo 100 a=.-.......
n...
.