ML20070L332
| ML20070L332 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/15/1982 |
| From: | Haggart K DRAGON VALVES, INC. |
| To: | Dodds B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-82 N30108A, NUDOCS 8301030093 | |
| Download: ML20070L332 (5) | |
Text
??f!Vro e
DRAGON VALVES, INC.
ms,aaasion oniva. nwn!CJnns ooeso CABLCADDRESS DnAGONVALVE lV I?gg,,q.
213.on.eaos December 15, 1982 2'3 m >883 N30108A United States Nuclear Regulatory Commission Office of Inspection and Enforcement, Region V 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596 Attention:
Mr. Bob Dodds
Reference:
Arizona Public Service Co.
Palo Verde Nuclear Generating Station Bechtel Power Corp. Deficiency Evaluation Report No. 82-48 Dragon Valves Excess Flow Check Valves Gentlemen:
We have recently received word from Bechtel Power Corp. that the above refer-enced Deficiency Evaluation Report has been filed with the NRC by Arizona Public Ser-vice Co. as a 10CFR50.55(e) reportable deficiency. As required by 10CRF21.21, and to supplement the above referenced Deficiency Evaluation Report, the following infor-mation is provided:
1.
The subject Excess Flow Check Valves are Dragon Valves' Model Number 14388. Dragon Drawing No. 14388, Revision A, which describes the valves as origi-nally shipped to the site, is enclosed. The subject valves are unique to Palo Verde Nuclear Plant.
2.
The failure of the ccmponent is that, when welding the inlet connection, the poppet sticks in the open position. The I.D. bore in the body is reduced in the weld area and this localized deformation contacts the rear porti(n of the poppet.
The deficiency was first identified on the -3 and -3A in January 1982 at the site by Bechtel site construction personnel. The -1,
-1A, -2 and -2A deficiency was identi-fled in June or July or 1982 hy Bechte] site construction personnel.
3.
The Dragon Model 14388 was designed to the unique requirements of the purchase specification for the Palo Verde project. The inlet design, the area where the deformation during welding occurs, is also unique to the Palo Verde Project.
This valve is designed at Bechtel's request to be inserted into a pipe socket and then fillet welded.
Other projects using Dragon Valves Excess Plow Check Valves use a socket bore (for welding to pipe / tube using a fillet weld) or pipe / tube ex-tensions welded to the valve bodies prior to hydrostatic and functional testing.
4A.
Corrective action on the -3 and -3A valves was accomplished by reworking the valve inlet to a butt weld configuration and supplying a welding adaptor, weld-ing the valve adaptor to the valve body with the poppet removed, boring out the valve 8301030093 821215 PDR ADOCK 05000528 S
pgg MANUFACTURERS OF VALVES FOR DNDUSTRY SINCE 1945
ce 1
, [
United States Nuclear Regulatory Commission December 15, 1982 Mr. Bob Dodds Page 2 1
1.D. and reinstalling the poppet into the body weldment. The dis-assembly and weld-ing was accomplished by Bechtel Power Corp. at the sitt.
All other rework was ac-complished by Dragon. The reworked valves were verified to function in accordance with the purchase specification requirements prior to returning them to the site.
i Bechtel has indicated that the reworked valves, once installed, have functioned satisfactory.
4B.
The corrective action on the -1, -1A, -2 and -2A valves was accomplished by designing a new poppet configuration which would accomodate the I.D. bore dimen-sion change withcut affecting the valve function.
Sample modified poppets were sent to the site for Bechtel evaluation. The modified poppets were found to function,after welding without further rework or modification. Modified poppets, enough for one power plant unit, were shipped to the site to be installed in valves for Unit 1.
Units 2 and 3 valves will be returned to Dragon for installation of modified poppets.
In both cases, a'"M" was added to the part number to identify the valves with the modified poppet (i.e. 14388-lM).
4C, Dragon Valves' Drawing No. 14388, Revision D, the current revision, in-corporating the modifications discussed above, is enclosed.
It is Dragon Valves' understanding that the rework / modification, as identified above, has proved effective in correcting the deficiency. Your office shall-be no-tified of any further developments.
Should further information be required, please contact the writer at (213) 773-3883.
1 Sincerely,.
DRAGON VAL S, I 'C.
s pf++r
+
Kim D. Haggar Q. A. Manager V
KDil:kk Encls.
cc:
H. C. Bond, Pres., DVI, w/o encls.
R. E. Bond, Vice-Pres., DVI, w/o encls.
l
'W. G. Bingham, Bechtel LAPD, w/o encls.
l
newsons 14308 6
.c-l SPECIFICATIONS A
E O. 0 8 0 4 #
G.#-5. s (% 4 I
ELECTRO eTCN 1.
CODCs AsME SECTION M, CLASS E SECNTEL M ARK N O.
IS77 ED., S'7 7 A DO.
/ TAG N O.
E.
PRESSURE CLASS: #ECO
' 5
'^~
l L_T u gg -
4.
service..
'I -E,- 3) WAT E R Of L / ST E A t%A j
f // / _f p
s I
~
y-
- f A, -t As *3 A) ADR l
~4
.ss DIA.
- 5. RESCTTING ORIFICE: TA BULATED
- f56 Ol/T LE T INLE T,
/
\\
14385-3A 1+40s f.S - 3.0 SCFM
.020 MA Y.
~
u bau.uws so. O
- ,",,,i i+38s-3 I4405"
. 5
.7 GPM
.040 MA X.
3%b__
Q 14 3 5 9 -E A 14404
- 8. 5 - 3 0 S C F M
.O E O MAX.
1.315 Di t 4
g
- }
gg g,7 14388-2 14403
.5
.7 GPM
.040
?1Ax.
' s y ;' #a '
^
e43as-IA I44of 15-3.o scr M
.O z o MA x.
-] { 8 3 DIA.
2.0 14386-8 f440s 5
.7 GPM
.040 MAX.
~ * '
8
'C
~
INLET OUT L ET PART NUMBER PAAT3 LIST SHUT OFF FLOW Of 1N b
{NPT.
FITS 1* PIPE
+.50 PER S OC N C T WE L D 14385-Z (LIQUID}
ANSI B E. 8 8 4 388 - E A ( A f R) 4 3
2 l
OUT LET
.15 6 z* PsPC SOCKET WELD 1.
A DENOTES PRESSURE R E TAININ G PARTS
- 3DIAv--
NOTES
//
G E
DRIVE SCREW STAINLESS STEEL 300 SERIES M
/
S 1
NAME PLATE STAINLCSS STEEL 300 S ERIES 4
I ACTAINER FIN STAIN L E S S STEEL 300 SERIES p
N 2.375 DtA.
_ s y v==xmy J Jg A
3 J
POP P E T STAIN L ES S STEEL ASME SA473 TV 316 DIA.
,, a w M I( F E
I SPRING STAINL ESS ' STE EL 300 SERIES r
rLow
/
A I
I 80DY STAINLES S STEE L AS M E Sale 1 GR PSIG
+
/
P gyy f
ASSh PART NAME M ATERIAL S PECIFIC ATIONS PARTS LIST
/
ARIZON A PUBLIC SCRVICE COM PANY INLET PALO VERDC NUCL EAR S ENERATING STATION FIT 3 E* PsPE G
S
.45-UN870 ** ' #
SOC M E T WEL D BECHTEL P. O. lO 407 - f 3-J M - 70 F
== :
u -
" m w a 4Ise==N 4wl8 EXCESS FLOW CHECK VALVE N >- d # 8 vammassa ams w AUTOM ATIC RESCT 1 A b.
t500 L B NUCLEAR o
@n cr-,
NON E TA..
ga g;.g,-
J on,rAeo,n vgres, me.
C 97399 14388 4
I--
N 3OIOS A Fe s
,F
-~-u----
meveone 1438"1 6
SPECIFICATIONS A
E.O. s e O + :
s.e-a s m::r ELECTRO ETCH
- 1..CDDEs ASME SECT 40W E, r r ass E -~ 8 Ea #8078
'Newa q C C.O.82006 2-443 hJ
&ECNTEL MARK NO.
-
- 1377 ED.~, 5 P T ADD.
/' TAG N O.
E.
PRESSURE CLASSs 1500
- D CA S2046 so-m M l_.
3 OPERATING PRESSURE / TEMP.e
(
.-e.-b 3600 PSIG AT IOO*P Dh
- I
{'s A SERVICE:.
. h-E.-M1CJWATER,01I./ STEAM.J
)l r /. / / ~/
-ta, -z Ap3AJ AIR u
F. TLESETTseG DRIPICEs TABULATED
- J3 OfA.
S. CLOSING PLOW s TABULATED 1
.f58 --
OllTLET NLET
.T. PART NUMSER s TADULATED Pars j,eer -
4.50 f NPT PER I 4 3 O O "IA4-(LIO UN ~ ?-
i SOCacET wE 4.D y4se6-rAu(Arm ANSI S E.1
__u Ax.
j E sassa-sC 3 +s e r..
3.s - +.o S P u
.04O l
~
3 14 388 -3A 14406 f.S - 3.0 SCPM
.020 MA X.
10.O
-.a
. i i
._ w s
[
M, -
E 14388-3 14405"
.7
.T
$6PM
.040 MA lt.
4
- - T)-b K 'O 143 S D -E A M I4404
- 1. F - 3.0 SC P M
.O E O MA X.
l.365 DfA.
,g7 g
{. ~
14SSS-2M 44403
.5
.T GPM
.04O M A Jr.
)
'/,/-
m, n
~
~~
.e..
- 4385 - I A M 1440E I.5-3.0 SCFM
.020 &4A E.
l
. 1.0
.8 3 DIA.
143SS-#M 14408
.5
.T GPM
.O40 M A X.
--"N M
I T
'-"*"88--
l' ' ~ '
DUTLET PWPTNUMDER mR73 LIST saevT OPP PLOW m
FITS 1 *. PI P E
_+.56 NPT. PER COCatET WELD
.14 388 -EM (LIQUID)..
ANSI & E.8 EDENOTES EXCESS PLOW CNCCM lesLVE REQUlEfMS WELD
"' E.
. ADAPTER. WELD ADAPTER TO E>E PLELD WELDED TO I
l
. yALyt. my Cv3TOuta. '..
.I l
. _. e +sse-zAM (Ano t. _.
c.
L A DENOTES PRCSSURD RETAINING PARTS.
{sp t
- - 4
.--4
-3
-1 1 ' OUTLET 7
- wayE3,
[
WEL D
^
L l
1-
.33 3 -
&.X._
! '.' WELD ADAPTER: STAINLESS. STEEL. ASMC SAist en gls 1
l y
~
~'
" ' ^ ' '
i s.
E DasvC SCnEw -
sTA'iNLEss STEEL sco sEsuCS t
13ee.. }f
'O j
9 a; ',
, i d
y
.I NAME PLATE STAINLESS STEEL 300 SERIES
..l
,.o.
i
+.o nETAINEn Pm ' STAINLESS STEEL 300 SEMES??2-L.
1' s.
4
.a
-a m s wen.
t
,q.g..*
APN%PJ q
J ] 6,,
e..
g S
I POPPET STAINLESS S'? EEL ASeat SA4TS TV Ste
"~
r
~ E.3rr otA."
Is -
.J.
g7 iI
~ k.
l l
%J;. '.3 l I 7""
.)
[. Q Dee. W C..
d.,*
.E.
3 SPRafe.
STAsNLESS STEEL 300 SERIES i
n i
'.ft.Ow
+
& ^1-I DODY STAINLESS STEEL AsME SAleE #R P Set, t 17De FARY NAME.
.. ? MATrasAL ' SPECIF8CATIONE...,
/
n ss.
Ismars uSr
/
.f 68 MAMr-ARIEDMA. PUS > lac SERVICE COMPANY 1
PALO VERDE $8MCLEAR'SESERATtNS STATION ~
INLET a
s -
S-
<.se-~-ns-P,rs e e,ee SOCMET WELD SECNTEL P.O. BO407-IS _JM-705
8"==8'
"CsusKat 444s '" N 4lgdg gg gggggg a
4.P5_
- E.0.
. m===e,=4==mg pty,m Al/TDMATIC RESET IAh 34338-3 (LfGUID)
WELD ADAPTER 3500 LB NUCLEAR e4 388-3 A $1R) au smu s==i. E4
""' esONE
" TA&. as
~"(("
'""T'**==
se name mesr.am mee um C~
I4388-3 C (LIQUID-HfGH FLOW) g asAeon essaus, sue.
C 97399 I4360 4
,/ ""lll"
===m"-
N3OIOS A Fl
,8 l{
i
6th$
V Arizona Public Service Company P o. Box 21666. PHOENIX. ARIZONA 85036 December 7, 1982 ANPP-22459-GHD/BSK U. S. Nuclear Pegulatory Commission Region V Creekside Oaks Office Park l
1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention:
Mr. D. M. Sternberg, Chief Reactor Projects Branch 1
~
Subject:
Final Report - DER 82-48 A 50.55(e) Reportable Condition Relating to Dragon Valve Company Instrument Line Check Valves Seized Open by Welding Heat File:
82-019-025 D.4.33.2
Reference:
(A) Telephcne Conversation between T. Young and G. Duckworth on September 1, 1982 (B) ANPP-21927, dated September 30, 1982 (Interim Report)
Dear Sir:
Attached, is our final written report of the reportable deficiency, under the requirements of 10CFR50.55(e).
l Very truly yours,
\\
E\\i% nd b E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects Management I
ANPP Project Director l
i EEVBJr/GHD:db Enclosure "N M4C333 cc: See Attached Page 2 j
sc:),13 8133050 GDi 03A002U burc of i
L:::;Y t ' im 1
(,
l',
a j-U. S. Nuclear Regulatory Commission December 7, 1932 l
Attention:
Mr. D. H.~Sternberg, Chief ANPP-22459-GHD/BSK Page 2 b
cc: Richard DeYoung, Director
]
Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission j
-Washington, D. C. 20555 4
T. G. Woods, Jr.
J. A. Roedel D. B. Fasnacht G. C. Andognini J.-R. Bynum A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. A. Brand A. C. Gehr W. J. Stubblefield l
U. G. Bingham R. L. Patterson R. U. Welcher R. !!. Grant D. R. Ilawkinson L. E. Vorderbrueggen G. A. Fiore111 P. P. Klute Lynne Bernabei, Esq.
flarmon & Weiss 1725 "I"
Street, Ini Washington, D. C. 20006 l
R. L. Greenfield Assistant Attorney General Dataan Memorial Building Santa Fe, New Mexico 87503 l
I l
f l
I i
__.. _. ~, _, _.
ge a
r FINAL REPORT - DER 82-48 DEFICIENCY EVALUATION 50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNIT 1 1.
DESCRIPTION OF DEFICIENCY An installation problem has been encountered with the Excess Flow Check Valves supplied by Dragon Valve Company (PVNGS specification 13-JM-705). Thermal expansion and distortion of the valve body in the heat affected zone during welding assembly with the piping systems causes the poppet to seize in the open position.
II.
ANALYSIS OF SAFETY IMPLICATION This condition is evaluated as Reportable. The condition precludes the device'from performing its intended function of preventing loss of fluid in the event of instrument tubing rupture or loss of pressure down stream of the check valve. Should the condition remain uncorrected, and in the event of a tubing rupture, the defect would result in release of radioactive fluids which could present a substantial safety hazard.
III. CORRECTIVE ACTION The movable internal poppet for the excess flow check valve has been redesigned by the vendor to preclude binding as a result of welding the valve in place.
Nonconformance Report PX-4379 will be dispositioned to test and/or rework all the subject flow check valves. delivered to the jobsite.
Valves failing an operationa,1 test, or not tested, will be reworked by installing the redesigned poppet. The' vendor will provide corrected valves for Units 2 and 3 to preclude recurrence of this problem at PVNGS.
In addition to reportability under 10CFR50.55(e), PVNGS Project considers the deficiency to be Reportable under the requirements of 10CFR Part 21 by the supplier. This Deficiency Evaluation Report l
(82-43) addresses the reporting requirements specified under 10CFR 21.21.(b) (3) with the exception of sub part (vi) which requires the number and location (customers and/or facilities) of other possibly defective equipment. A copy of this report has been sent to Dragon Valve Company requesting their review for reporting under 10CFR Part 21, including number and location of all components supplied.
k.
-. =
Lug sn!et no.
O f)
PART 21 REPORT 1.0G SHEET V ctles b<tkc V eNkVe ODTEks Subject of Report.- b rc 1.
ces ric 2.
Date Verbal Notification Received -
Received By -
+
3.
Date Infonnation Placed 'in Daily Repo~rt -
4.
Name and Address of Person Providing Verbal Notification a) Name -
G. DuckworI-b) Company and Address -
k r~i7.on d3bc QU tc.c a c._.
O b U Io b (,
ULEW h rit.
O503b c) Telephone ~No. -
(C,cM
)43 -7200
(^ 6020) 5.
Description of' Problem -
\\9e k cI n.
\\}cdsles do W him dM vLe bNdW C n a s e. 5 ' Donne VcdVe Io se 7 r cscio n Nedve' bob
/Ybbb O,
6.
Nuclear Facilities Affected -
cdb C>rcfe> d'n l 2,3 onl.,.
5
\\J
- 7. 'Date 5-day Written Report Due -
A Date -Received.- c (2 /l5/82.
8.
Mail Written' Report to HQ's and Other Affected Regions a) Date Mailed to HQ's' (Bill Mills) -
b)' ' Date ' Mailed' to Other Regions -
Regions Mailed To - b(m.
9.
Give Written Report to Each Region V Affected Principal Inspector a) :Date Given to Principal Inspector (s) -
I2/l5/8 Z cwbte b)
Name(s) of Inspectors Given To -
10.
Additional Comments -
Drcg% Nebe d(
cI ch
~PV t0 t-5 50 55U
~
scue suhd dichecl liom vid\\
l:e cc<crie d 60$SceT. b?stec,Jon
(
c<s Y
ik lact Z\\
is to,,s Aect eload
..