05000395/LER-1986-001, :on 860214,substantial Safety Hazard Evaluation Determined That Potential Failure Existed for Seven Valves in Emergency Feedwater Sys.Caused by Mfg Failure to Apply Capture Tack Welds to Internal Components
| ML20153F255 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/19/1986 |
| From: | Nauman D, Paglia A SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| References | |
| LER-86-001, LER-86-1, P-21-86-001, P-21-86-1, NUDOCS 8602250385 | |
| Download: ML20153F255 (5) | |
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. ACiun NA.E m Virgil C. Summer Nuclear Station 0 [ 5 l 0 l 0 l 013 l 915 1 lOFl 014 TITLE see Significant Safety Hazard Attributable to Anchor Darling Check Valves l'!ENT DAf t tSi LER NuesSER 864 REPORT Daf t (79 OTHER F ACILITitS INv0LvtD 488 UONia cAv vsAm vsAm seg
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AS$7 ACT rame re P400 moscos e e acerosev ** sea e,ve easte FF##WMFfDa4 88# 5101 On Feb ru a r y 14, 1986, the Licensee completed a Subs tan tial Sa fety Hazard Eva lua t ion (10CFR21) of the as found condition and des ign basis fu nc t ion for fifty-one Anchor Darling Check Va lv e s installed in various s ys te ms at the Virgil C.
S umme r Nuclear Station.
The eva lua t ion determined that a potential failure existed for s even va lv es in the E me r g e n c y Feedwater System.
This potential failure c ou ld represent a Substantial Sa fe ty Ha zard because o f the pos s ib ilit y o f a loss of Emergency Feedwater Flow and is reportable in accordance with 10CFR21.
The pot ential dis ab ling of the valves is a t t r ib u t ed to the manufacturer's failure to apply required capture t ac k-we ld s to certain internal components during the manufacturing process.
The mis s ing t ack-we ld s c ou ld allow hinge pins and disc nut thru pins to back out and d i s ab l e the va lv es.
The Licensee opened and inspected s ixt y-t hre e of the sixty-four Anchor Darling Check Va lve s installed in the plant.
Fifty-one velves had one or more of the t ac k-we ld s missing and were repaired during the inspection process.
No va lve s were found to be inoperable.
The remaining valve (XVC-1900 MU), a 3 inch valve in the return line to the Reactor Makeup Water Storage Tank, was not inspected because of its ina c ce s s ib ili t y.
Th is va lv e is not required for Safe S h u t d o wn of the plant.
8602250385 860219
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, =nc r mar mn On February 14, 1986, the Licensee determined that a potential substantial safety hazard (10CFR21) existed because of the po ten t ia l failure o f seven Anchor Darling check va lv es.
The seven va lv e s were missing required internal t ac k-we ld s used as a locking mechanism for the disc nut thru pin.
During the second re fu e lin g outage, the Licensee commenced an "open cnd inspect" program on installed Anchor Darling check va lve s based on technical correspondence from Anchor Darling dated August 16 and 19, 1985.
This correspondence id en t i f ied concerns with missing internal capture tack-welds.
The Licensee is aware that Palo-Verde Nuclear Generating Etation previously reported similar p r ob le ms to the NRC in December 1984.
Sixty-three o f s ixt y-f ou r installed Anchor Darling check valves were l
inspected.
Fifty-one va lve s e xh ib i t e d one or more of the mis s ing tack-l welds on the h in ge pin and/or the disc nut t hru p in.
In addition, missing l
t ac k-we ld s were noted on the hinge assembly and hinge as se mbly cap s c re ws l
which were not id en t i f ied in the Anchor Darling technical correspondence or the Palo-Verde report.
The remaining va lv e (XVC-1900-MU) is a 3 inch va lv e, in the return line to the Reactor Makeu p Wa te r Storage Tank.
The va lv e was not inspected at this time because of its inac c e s s ib ilit y.
An engineering evaluation determined that this valve is not required for safe s hu t d o wn.
Pages 364 of this report contain a list of va lv e s inspected.
Each l
valve was repaired prior to closure.
The Licensee performed an engineering l
eva lua t ion of as-found conditions and des ign func t ion for each of the fifty-one sus pec t va lv e s.
This evaluation determined tha* a potential failure existed in seven Emergency Feedwater Va lve s.
The potential f ailt re of these valves c o in c id e n t with an additional s ingle f ailure of the t u r b ii.e d r ive n Emergency Fe e d wa t e r Pump c ou ld cause a loss o f Emergenc y Fe e d wa t e r.
The following list id en t i f ie s the seven Emergency Fe ed wa t e r Va lv e s and their func t ion.
1)
XVC-1015 B-E F-E me r ge nc y Feedwater Pump "B" Discharge Chec k Va lv e.
2)
XVC-10 2 2 B -E F-S e r v ic e Water "B"
Makeup Check Va lv e to the Tu rb in e Driven Emergency Fe e d wa t e r Pump.
3)
XVC-10 3 4B-E F-Se r v ic e Water Makeup Supply Check Va lve to "B"
Emergency Feedwater Pump.
4)
XV C-10 2 2 A-E F-S e rv i c e Water "A" Supply Check Va lve for the Turbine Dr ive n Emergency Feedwater Pump.
5)
XVC-1015 A-E F " A"-Eme r genc y Fe ed wa t e r Pump Discharge Ch e c k Va lv e.
6)
XVC-1013A-EF-Condensate Storage Tank Supply Makeup to "A" Emergency Feedwater Pump Check Va lve.
7)
XVC-103 4A-E F-Se rv ic e Water "A"
Makeup to "A" Emergency Fe e dwa te r Pump Check Valve.
The Licensee recommends that other utilities using Anchor Darling Check Va lve s open and inspect these va lve s at the earliest oppor tunit y.
It is a ls o recommended that the NRC cons id er issuing an I&E Notice on this subject.
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SERIAL NUMBER XVC00971A-DG 3.000 E-6188 XVC009 71B-DG 3.000 E-6188 XVC00971C-DG 3.000 E-6188 XVC00971D-DG 3.000 E-6188 XVC01013A-EF 6.000 E -6188-7 2-1 XVC01013B-EF 6.000 E-6188-72-2 XVC01014-EF 8.000 E-6188-74-1 XVC01015A-EF 4.000 E-6188-8 2-1 XVC01015B-EF 4.000 E-6188-8 2-2 XVC01016-EF 4.000 E-6188-8 2-3 XVC01022A-EF 8.000 E-618 8-74-2 XVC01022B-EF 8.000 E-6188-74-3 XVC01024-E F 3.000 E-618 8-81-1 XVC01034A-E F 6.000 E-6188-72-3 XVC01034B-E F 6.000 E-618 8-7 2-4 XVC01038A-EF 4.000 E-6188-96-1 XVC01038B-E F 4.000 E-618 8-9 6-2 XVC01038C-E F 4.000 E-6188-9 6-3 XVC01039A-E F 4.000 E-618 8-9 6-4 XVC01039B-EF 4.000 E-6188-9 6-5 XVC01039C-E F 4.000 E -6188-9 6-6 XVC01680A-FW 3.000 E-6188-94-1 XVC01680B-FW 3.000 E-6188-9 4-2 XVC01680C-FW 3.000 E-6188-9 4-3 XVC01901A-MU 4.000 E-618 8-69-1 XVC01901B-MU 4.000 E-6188-69-2 XVC01902-MU 4.000 E-6188-69-3 XVC019 30-MU 3.000 E-6188-6 7-2 XVC02876A-MS 4.000 E-618 8-80-4 1
XVC02876B-MS 4.000 E-6188-80-2 XVC03006A-SP 12.000 E-6188-7 7-1 XVC03006B-SP 12.000 E-6188-7 7-2 j
XVC03009A-SP 10.000 E-618 8-79-1 i
XVC03009B-SP 10.000 E-6188-79-2 XVC03013A-S P 3.000 E-618 8-6 6-1 XVC03013B-SP 3.000 E-6188-66-2 XVC03120A-SW 4.000 E-618 8-68-1 XVC03120B-SW 4.000 E-6188-68-2 XVC03136A-SW 12.000 N/A XVC03136B-SW 12.000 E-6188-76-2 XVC03137A-SW 16.000 E-618 8-78-1 XVC03137B-SW 16.000 E-6188-78-2 XVC06410A-VU 3.000 E-618 8-6 2-2 XVC06410B-VU 3.000 E-6188-62-2 XVC06461A-VU 6.000 E-618 8-7 0-1 XVC06461B-VU 6.000 E-6188-7 0-2 l
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"*a 0 l4 0 l0 0 l4 or Virgil C. Summer Nuclear Station 0 l5 l 0 l 0 l 0 l 3 l9 l 5 8 l6 0 l 0l 1 rixt in-e ac w aBw.mn VALVE NUMBER SIZE (Inch)
SERIAL NUMBER XVC06461C-VU 6.000 E-6188-70-3 XVC06489A-VU 3.000 E-6188-6 2-3 XVC06489B-VU 3.000 E-6188-6 2-4 XVC06652-SF 10.000 E-6188-75-1 XVC06653-SF 10.000 E-618 8-7 5-2 XVC06799-FS 4.000 E-6188-8 6-1 XVC09570-CC 8.000 E-6188-73-1 XVC09573-CC 6.000 E-6188-71-1 XVC09579-CC 6.000 E-618 8-71-2 XVC09596A-CC 3.000 E-6188-64-1 XVC09596B-CC 3.000 E-6188-64-2 XVC09596C-CC 3.000 E-6188-64-3 XVC09602-CC 3.000 E-618 8-61-1 XVC09632-CC 8.000 -
E-6188-74-4 XVC09633-CC 8.000 E-618 8-74-5 XVC09680A-CC 4.000 N/A XVC09680B-CC 4.000 N/A i
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f South CaroNna Electric & Gas Company Den A. Neuman P.O. Box 764 Vc) President Columbia. SC 29210 Nuclear Operations I
(803) 748-3513 t)
SCE&G
. e s.,.,
a February 19, 1986 U.
S.
Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Virgil C.
Summer Nuclear Station Docket No. 50/395 Operating License No. NPF-12 LER 86-001 P-21-86-001
Dear Sir:
Attached is Licensee Event Report #86-001 for the Virgil C.
Summer Nuclear Station.
The report is submitted in accordance with 10CFR21, because of p rob le ms noted with Anchor Darling Check Valves.
S h ou ld there be any questions, please call us at your convenience.
Very trul
- ours, s/ w
'D-A.
hauman PDL: DAN:tdh Attachment c:
V.
C.
Su mme r K.
E.
Nodland O.
W.
Dixon, Jr./T.
C.
Nichols, Jr.
R. A.
Stough E.
H. Crews C.
O.
Pe r c iv a l E.
C.
Roberts R.
L.
Prevatte W.
A.
Williams, Jr.
J.
B.
Knotts, Jr.
J.
Nelson Crace INPO Records Center D.
R.
Moore ANI Lib r a r y Group Managers S.
b.
Hogge O.
S.
B r ad h am NPCF C.
A.
Price File R.
M.
Campbell W.
T.
Frady J.
F. Heilman C.
L.
Ligon (NSRC) i l