ML20038A844: Difference between revisions

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=Text=
=Text=
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Docket Nos. 50-361/362 Bulletin No. 81-02 Southern California Edison Company                               g5 P O. BOX 800 2 2 44 W ALN UT GRCVE AVENU E ROSEME AD. CALIFORNI A 91770 K. P. B AS KIN                                                                               TELEPHONE M AN AGE R OF NUCLE A R ENG tNEE RING.                                                                   (213)572 1401
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m Docket Nos. 50-361/362 Bulletin No. 81-02 Southern California Edison Company g5 P
O. BOX 800 2 2 44 W ALN UT GRCVE AVENU E ROSEME AD. CALIFORNI A 91770 K. P. B AS KIN TELEPHONE M AN AGE R OF NUCLE A R ENG tNEE RING.
(213)572 1401 Nove.nber 13, 1981
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U.S. Nuclear Regulatory Commission                       l' fl0
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Suite 202, Walnut Creek Plaza                                 ""'ig!Lp 8 l                     1990 N. California Blvd.                                   d                                   -
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l Walnut Creek, California                                         3                 1 Attention: R. H. Engelken, Director
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==Subject:==
==Subject:==
IE Bulletin 81-02, Supplement No.1                                   f55 Docket Nos. 50-361 and 50-362                                         "
IE Bulletin 81-02, Supplement No.1 f55 Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 i
San Onofre Nuclear Generating Station Units 2 and 3 i                    


==Reference:==
==Reference:==
Letter, SCE to NRC dated July 7,1981:
Letter, SCE to NRC dated July 7,1981:
;                                          subject; IE Bulletin 81-02 IE Bulletin 81-02 requested that construction permit holders review their facilities design and ascertain whether any of the valves specifically _
subject; IE Bulletin 81-02 IE Bulletin 81-02 requested that construction permit holders review their facilities design and ascertain whether any of the valves specifically _
identified within the bulletin (all 3 or 4 inches in size) were used in safety related systems or as PORV block valves. The referenced letter provided the
identified within the bulletin (all 3 or 4 inches in size) were used in safety
{
{
;                      SCE response, indicated that two of the subject valves were utilized at San Onofre Units 2 'and 3, ~and stated that the recommended _ corrective action had been completed.
related systems or as PORV block valves. The referenced letter provided the SCE response, indicated that two of the subject valves were utilized at San Onofre Units 2 'and 3, ~and stated that the recommended _ corrective action had been completed.
Subsequently, the NRC issued the subject- supplement to Bulletin 81-02 which expanded the scope of suspect Westinghouse EMD gate valves to include valves 6 to 18 inches in size, and requested CP holders to determine the extent of use of these valves in safety related systems. Upon investigation, SCE has determined that none of the subject valves have been installed in safety related systems. However, three of the subject valves are maintained as spares and could ultimately be installed in a safety related capacity.         Therefore, SCE has instructed the S023 A/E to have the valve vendor provide for the necessary actuator modifications so the valves will meet the
Subsequently, the NRC issued the subject-supplement to Bulletin 81-02 which expanded the scope of suspect Westinghouse EMD gate valves to include valves 6 to 18 inches in size, and requested CP holders to determine the extent of use of these valves in safety related systems. Upon investigation, SCE has determined that none of the subject valves have been installed in safety related systems. However, three of the subject valves are maintained as spares and could ultimately be installed in a safety related capacity.
                                        ~
Therefore, SCE has instructed the S023 A/E to have the valve vendor provide for the necessary actuator modifications so the valves will meet the
                    '8111240204 8111'13 PDR ADOCK 05000361                                                                                  l%s\
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P.DR St[O-6/-I97


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Mr. R. H. Engeken, Director                                 specified service requirements. It is expected that those modifications will be completed prior to commercial operation. However, the suspect valves are being controlled in accordance with established SCE Non-Conformance Control Procedures to ensure they are not utilized until those modifications have bee'n effected.
Mr. R. H. Engeken, Director '
specified service requirements.
It is expected that those modifications will be completed prior to commercial operation. However, the suspect valves are being controlled in accordance with established SCE Non-Conformance Control Procedures to ensure they are not utilized until those modifications have bee'n effected.
Should you have any questions or require additional clarification, please contact me.
Should you have any questions or require additional clarification, please contact me.
Very truly yours, k$h'f)     r     -
Very truly yours, k$h'f) r 3
3
/
                                                                          /
cc: Director, Office of Inspection and Enforcement, NRC Washington, D.C.
cc: Director, Office of Inspection and Enforcement, NRC Washington, D.C. 20555 A. Chaffee, USNRC Site Inspector, S023 i
20555 A. Chaffee, USNRC Site Inspector, S023 i
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Latest revision as of 01:35, 20 December 2024

Responds to IE Bulletin 81-02,Suppl 1, Failure to Gate Type Valves to Close Against Differential Pressure. No Westinghouse Electro-Mechanical Div Gate Valves Installed in safety-related Sys
ML20038A844
Person / Time
Site: San Onofre  
Issue date: 11/13/1981
From: Baskin K
SOUTHERN CALIFORNIA EDISON CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
REF-SSINS-6820 IEB-81-02, IEB-81-2, NUDOCS 8111240204
Download: ML20038A844 (2)
v • d • e


Text

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m_

m Docket Nos. 50-361/362 Bulletin No. 81-02 Southern California Edison Company g5 P

O. BOX 800 2 2 44 W ALN UT GRCVE AVENU E ROSEME AD. CALIFORNI A 91770 K. P. B AS KIN TELEPHONE M AN AGE R OF NUCLE A R ENG tNEE RING.

(213)572 1401 Nove.nber 13, 1981

, A,r

v. ANO L.c E N

.N 1

S q\\

Y 9~ 1, s

N 4

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[

j U.S. Nuclear Regulatory Commission l'

fl0 31985 '2 E

l~

Region V g-l Suite 202, Walnut Creek Plaza

""'ig!Lp 8 l

1990 N. California Blvd.

d 1

l Walnut Creek, California 3

Attention: R. H. Engelken, Director i

Gentlenen:

O.

5 o<

f..

g i

ra

Subject:

IE Bulletin 81-02, Supplement No.1 f55 Docket Nos. 50-361 and 50-362 San Onofre Nuclear Generating Station Units 2 and 3 i

Reference:

Letter, SCE to NRC dated July 7,1981:

subject; IE Bulletin 81-02 IE Bulletin 81-02 requested that construction permit holders review their facilities design and ascertain whether any of the valves specifically _

identified within the bulletin (all 3 or 4 inches in size) were used in safety

{

related systems or as PORV block valves. The referenced letter provided the SCE response, indicated that two of the subject valves were utilized at San Onofre Units 2 'and 3, ~and stated that the recommended _ corrective action had been completed.

Subsequently, the NRC issued the subject-supplement to Bulletin 81-02 which expanded the scope of suspect Westinghouse EMD gate valves to include valves 6 to 18 inches in size, and requested CP holders to determine the extent of use of these valves in safety related systems. Upon investigation, SCE has determined that none of the subject valves have been installed in safety related systems. However, three of the subject valves are maintained as spares and could ultimately be installed in a safety related capacity.

Therefore, SCE has instructed the S023 A/E to have the valve vendor provide for the necessary actuator modifications so the valves will meet the

'8111240204 8111'13

~

l%s\\

PDR ADOCK 05000361 G

P.DR St[O-6/-I97

r-r ey*.

Mr. R. H. Engeken, Director '

specified service requirements.

It is expected that those modifications will be completed prior to commercial operation. However, the suspect valves are being controlled in accordance with established SCE Non-Conformance Control Procedures to ensure they are not utilized until those modifications have bee'n effected.

Should you have any questions or require additional clarification, please contact me.

Very truly yours, k$h'f) r 3

/

cc: Director, Office of Inspection and Enforcement, NRC Washington, D.C.

20555 A. Chaffee, USNRC Site Inspector, S023 i

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