ML20004F655
| ML20004F655 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 04/21/1981 |
| From: | Madsen G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| NUDOCS 8106190336 | |
| Download: ML20004F655 (1) | |
Text
_ _. _
-p'3:;g'A 05# "'C '4 UNITED STATES 4
V D
NUCLEAR REGULATORY COMMISSION REGION IV g
,h '
,s /ghg IS81r
-8 k A*,Y8 611 RYAN PLAZA DRIVE. SUITE 1000 b,
,8 ARLINGTON, TEXAS 76011 p
7 z & '* h
\\
\\_
April'21, 1981 MEMORANDUM FOR: 'Those Listed Below FROM:
G. L. Madsen, Chief, Reactor Projects Branch, IE:RIV
SUBJECT:
IE BULLETIN NO. 81-02 Subject IE Bulletin has been sent to the following listed licensees. A copy of the IE Bulletin is attached for your information.
Arkansas Power & Light Company Gulf States Utilities ANO-1 & 2 (50-313; 50-368)
River Bend (50-458; 50-459)
Nebraska Public Power District Houston Lighting & Power Company Cooper Nuclear Station (50-298)
South Texas (50-498; 50-499)
Omaha Public Power Distric't Kansas Gas & Electric Company FortCalhoun(50-285)
Wolf Creek (STN 50-482)
Public Service Company of Colorado Louisiana Power & Light Company Fort St. Vrain (50-267)
Waterford-3(50-382)
Texas Utilities Generating Company Comanche Peak (50-445; 50-446) sW" G. L. Madsen, Chief Reactor Projects Branch ATTACHMENT:
As stated DISTRIBUTION:
IE/DMS MPA/L0EB IE/RPRIB IE/ REB IE/SRSI IE/EP ADM/DMB 8106190
7 SSIN No. 6820 Accession No.:
8011040283 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 81-02 April 9, 1981 Page 1 of 5 FAILURE OF GATE VALVES TO CLOSE 1
AGAINST DIFFERENTIAL PRESSURE Description of Circumstances:
As a part of its pressuri:ted water reactor (PWR) Safety and Relief Valve Testing Program, the Electric Power Research Institute (EPRI) conducted limited testing of a number of valves used on PWRs as power-operated relief valve (PORV) isolation or block valves.
These tests indicate a number of cases in which certain of these valves failed to fully close undar conditions that approximated those of their intended service (i.e., saturated steam at approximately 2,400 psij.
The valves that failed to fully close are gate type motor-ooerated valves that may be used in various safety-related applications in addition to PORV block valves.
Background on EPRI Testing:
The proposed full-scale qualification testing of PORV block valves, tith a completion date of July 1,1982, was first provided to the utilities in a September 5, 1980, draft of NUREG-0737.
The item was formally issued, with Commission approval, in NUREG-0737 on October 31, 1980.
The block valve qualification testing was proposed in NUREG-0737 primarily as an additional means of reducing the number of challenges to the emergency core cooling system and the safety valves during plant operation.
In anticipating a request for PWR block valve testing, EPRI decided to make provisions for the installation of block valves between the test steam source and the test PORV in July 1980 at the Marshall test facility.
The Marshall i
test facility is a full-flow steam test facility owned by Duke Power Company.
l
)
Test PORVs had been carefully selected, with close coordination between EPRI, its consultants and PWR utilities, to assure that PORVs representative of those in service or intended for service would be tested.
However, for the block followed because an NRC D+'
y npyMur4Mf g qqtMn-% ya*5y3 t
valves that have been teQ @ M if; h Or/r:a W W % R t c 9
- p@
c Therefore, seven readilyU RI primarily to obtain some DUPLICATE DOCUMENT
@sur,e l
gJ i
capability.
)t Entire document previously
/
Fortheblockvalvesthag entered into system under:
tjt at the Ostruction,/
time of testing, the popa
%lI0t/0 3 3 A
ANo f
No. of pages:
[
,'j y '
% m a mme._ g
. 4;
.;v April 9,1981 IEB 81-02 TABLE 1.
. IDENTIFICATION OF.W-EMD MANUFACTURED VALVES ANO
. DIFFERENTIAL PRESSURE'LIRITS FOR VALVE OPERATION Nominal W-EMD 1
Valve Model
" VALVE W***
SizeL(in.)
Reference IDENT."*
" VALVE I.D."**
(psid) 3-3GM88 03000GM88 3GM58 or 3GM78 or 3GM88 1500 3GM88 03002GM88 3GM58 or 3GM78 or 3GM88 1500 3GM99 03001GM99 3GM58 or 3GM78 or 3GM88 750 4
4GM88 04000GM88 4GM78 or 4GM88 750 4GM88 04002GM88 4GM78 or 4GM88 750 4
4GM87 04000GM87 4GM77 750 4GM87 04002GM87 4GM77 750 This number is found on the yoke-mounted nameplate and occupies the first nine positions of a 24 position number.
It is used in evaluating the functional WP requirements.
This number is found on the yoke-mounted nameplate and occupies the first three positions of a six position number.
Valves sold as spares or replacements may not contain this number.
D essure below which valve will close (as shipped).
Notes:
A " position" may contain more than one character.
The three position
" VALVE I.D." number consists of five digits in the three positions; for example, 3 GM 78.
All nameplates have " VALVE IDENT." numbers, but those sold as spares or replacements may not have " VALVE I.D." numbers.
The " VALVE IDENT."
number includes the manufacturer's model reference, and the " VALVE I.D." number is a reference to the valve system application.
The
" VALVE I.D." nuaber also appears on Westinghouse valve indexes and system flow diagrams.
There is no reference to the " VALVE IDENT."
number on these indexes or flow diagrams.
t I
i I
i
April 9, 1981 IEB 81-02 TABLE 2.
PARTI /1L LIST OF PLANTS WITH AFFECTED VALVES MANUFACTURED BY W-EMD
" VALVE IDENT." Number 04000GM88 l
04002GM88 03000GM88 04000GM87 03002GM88 03001GM99 04002GM87 plant Operating plants (supplied as spares or replacements except as noted):
Beaver Valley 1 X
Connecticut Yankee X
Farley 1,'
2 X*
Indian Point 2
! X Kewaunee X
North Anna 1, 2 X
Oconee 1, 2, 3 X
X San Onofre 1 X
Surry 1, 2 X
X X
Zion 1, 2 X
l i
Nonoperating plants (supolied as original scope of supply except as noted):
Beaver Valley 2 X
X Braidwood 1, ?.
X X
Byron 1, 2~
X X
Callaway 1, 2 lX X
Comanche Peak 1, 2 X
X Harris 1, 2, 3, 4 X
X Jamesport 1, 2 X
X Marble Hill 1, 2 X
X San Onofre 2, 3 X**
Seabrook 1, 2 X
X South Texas 1, 2 X
Summer X
X Vogtle 1, 2 X
X Watts Bar 1, 2 X
X Wolf Creek X
X
- Transferred from inventory at another plant.
- Spares or replacements.
l
2 April 9, 1981 IEB 81-02 TABLE 3.
PARTIAL LIST OF PLANTS WITH AFFECTED VALVES MANUFACTURED BY BW-NVD Pl a.r.t NVD-P/N
. Arkansas Nuclear One, Unit 2 75460 Bellefonte 79190 Palo Verde 77910 l
l l
l I:
d *. =
IE Bulletin No. 81-02, April 9,1981 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To
.No.
80-22 Automation Industries, 9/11/80 All radiography licensees Model 200-520-008 Sealed-Source Connectors 80-23 Failures of Solenoid 11/14/80 All power reactor facilities Valves Manufactured by with Operating License (0L)
Valcor Engineering or Construction Permit (CP)
Corporation 80-24 Prevention of Damage 11/21/80 All power reactor facilities Oue to Water Leakage with Operating License (OL)
Inside Containment or Construction Permit (CP)
(October 17, 1980 Indian Point 2 Event)
Sup. 4 Failure of Control Rods 12/18/80 To specified BWRs with Bulletin to Insert During A Scram an Operating License (OL) 80-17 at a BWR and All BWRs with a Construction Permit (CP) 80-25 Operating Problems with 12/19/80 All BWR facilities with Target Rock Safety-Relief Operating License (OL)
Valves at BWRs and specified near term Operating License (OL)
BWR facilities and all BWRs with a Construction Permit (CP) 81-01 Surveillance of 1/27/81 All power reactor Mechanical Snubbers facilities with an Operating License (0L) and to specified facilities with Construction Permit (CP) 80-17, Failure to Control Rods 2/13/81 All BWR facilities Sup. 5 to Insert During a Scram with Operating License (0L) or Construction Permit (CP) 81-01 Surveillance of Mechanical 3/4/81 All power reactor facilities Rev. 1 Snubbers with an Operating License (0L) and specified facilities with a Construction Permit (CP)
Enclosure
_