ML19345D389: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:al iautu 13 a mxi n FWU mfi it M!L L .l i - n@ m U +1
{{#Wiki_filter:al iautu 13 a mxi n FWU mfi it M!L L.l i - n@ m U +1
                                                                          %O Cacb
%O Cacb
  ~
~
PART 21 IDBEIFICATIOM NO. So- 320-oco               CTPANY (WEJe<*ri 4 Cws Opp DATE OF IIITER_     d26ltro       DIKET NO.       6-y 6             h                 j DATEDISTRIBlHED       idE to A m -     _ ORIGli!AL REPORT %     SUPPLF5NNTARV DISTRIBUTION:
PART 21 IDBEIFICATIOM NO.
s 2
So-320-oco CTPANY (WEJe<*ri 4 Cws Opp DATE OF IIITER_
ea
d26ltro DIKET NO.
                                                                                  .J f
6-y 6 h
REACTOR (R) a
j DATEDISTRIBlHED idE to A m -
                    %                FEL CYCLE &                   SAFEGUARDS,(S) 1
_ ORIGli!AL REPORT%
  * .      -, , m                   PATERIALS OD IE FILES EES                           IEFILES                       AD/SG AD/FFFEI                     AD/ROI EGIONS I,II,III,IV,V         REGIONSI,II,III,IV,V         REGIONSI,II,III,IV,V T
SUPPLF5NNTARV DISTRIBUTION:
VStOR   BR. R-IV             VEEOR BR. R-IV               VENDOR BR. R IV LEB / FPA FIG 5715           ffSS/FCES       SS-395       NPS/D3L AEOD         FIB 7602         LOEB/FPA       F135715       g,ES / SG SS-881 NRR/ DOE                     Ac0D           FIS 7602       LDEB/FPA     MG 5715 NRR/DSI                       ASLBP E M     450           AEOD         FIG 762 ta W T                   -
2
SAP /SP fi'B-7210A           ASLBP     E/W 450 NRR/ DOL           -
.J f
CSEPAL FILES       015     CBHPAL FILES     016 EN 450
s ea REACTOR (R)
                                                    ~
FEL CYCLE &
ASLBP CENiPAL FILES ( GRON)       CBUPAL FILES    (GR0io CBERAL FILES       016         PDR                         CENTPAL FILES   SS-395 CENTRAL FILES (GR0fD             LPDR                         PDR PDR                             TEPA                         LPDR LPDR                                                         TERA m[fsb                                                                     '
SAFEGUARDS,(S) 1
ACi!0[{:
-,, m PATERIALS OD a
IE FILES EES IEFILES AD/SG AD/FFFEI AD/ROI EGIONS I,II,III,IV,V REGIONSI,II,III,IV,V REGIONSI,II,III,IV,V VStOR BR. R-IV VEEOR BR. R-IV VENDOR BR. R IV T
LEB / FPA FIG 5715 ffSS/FCES SS-395 NPS/D3L AEOD FIB 7602 LOEB/FPA F135715 g,ES / SG SS-881 NRR/ DOE Ac0D FIS 7602 LDEB/FPA MG 5715 NRR/DSI ASLBP E M 450 AEOD FIG 762 ta W T SAP /SP fi'B-7210A ASLBP E/W 450 NRR/ DOL CSEPAL FILES 015 CBHPAL FILES 016 ASLBP EN 450
~
CBUPAL FILES (GR0io CENiPAL FILES ( GRON)
CBERAL FILES 016 PDR CENTPAL FILES SS-395 CENTRAL FILES (GR0fD LPDR PDR PDR TEPA LPDR LPDR TERA m[fsb ACi!0[{:
PRELIMINARY EVALUATION OF THE' ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOWUP AS SHOWN BELOW:
PRELIMINARY EVALUATION OF THE' ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOWUP AS SHOWN BELOW:
IE   K                           ,NRR2                         ffES [         OTHER     _
IE K
EES 8012750030                       s.                                        Pa'. 8/1/80 Mnhc id r.lto
,NRR2 ffES [
OTHER EES 8012750030 Pa'. 8/1/80 s.
Mnhc id r.lto


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    ==                                SOUTH CAROLINA ELECTRIC a gas COMPANY POST C F FsCC 90 764 CotunsiA. Souin CAnctiwA esais   ,
SOUTH CAROLINA ELECTRIC a gas COMPANY
T. C %cwots.JR.
 
v.co.u.u., .- s . tne ,=         November 25, 1980 u.ea.. cn..
==
POST C F FsCC 90 764 CotunsiA. Souin CAnctiwA esais T. C %cwots.JR.
v.co.u.u.,.- s. tne,=
November 25, 1980 u.ea.. cn..
Mr. James P. O'Reilly U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Mr. James P. O'Reilly U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 3100 Atlanta, GA 30303
Suite 3100 Atlanta, GA 30303


==Dear Mr. O'Reilly:==
==Dear Mr. O'Reilly:==
==Subject:==
==Subject:==
Virgil C. Summer Nuclear Station, Unit 1 Docket No. 50/399 Reportable Su ,bstantial Safety Hazard Westinghouse 3" Gate Valve Closure Failure On October 30, 1980, Mr. John Rausch of NRC Region II was informed by means of a telephone call of a potential significant deficiency.
Virgil C. Summer Nuclear Station, Unit 1 Docket No. 50/399 Reportable Su,bstantial Safety Hazard Westinghouse 3" Gate Valve Closure Failure On October 30, 1980, Mr. John Rausch of NRC Region II was informed by means of a telephone call of a potential significant deficiency.
During Hot Functional Testing, 10 Westinghouse 3" gate valves failed to completely close under test conditions which are less severe than the equipment specification design conditions.               The valves stroked to significantly restrict flow, but the full stroke was not accomplished to trip the " closed" positfen indicati:n contcets in the motor operator or to seat the valve disc within the valve body.
During Hot Functional Testing, 10 Westinghouse 3" gate valves failed to completely close under test conditions which are less severe than the equipment specification design conditions.
Failure of these valves to close completely could impair the ability of_the plant to operate or shutdown safely.               Under the South Carolina Electric and Gas Company program, we are reporting-this as a. substantial safety hazard as defined by 10CFR21.
The valves stroked to significantly restrict flow, but the full stroke was not accomplished to trip the " closed" positfen indicati:n contcets in the motor operator or to seat the valve disc within the valve body.
am Westinghouse and SCE&G are working concurrently at Summer Station on a solution which will be tested prior to issuance of a generic response by Westinghouse.     This is an interim report and a final report vill be sent when an adequate solution is achieved.
Failure of these valves to close completely could impair the ability of_the plant to operate or shutdown safely.
;                        If you have any questions, please contact us.
Under the South Carolina Electric and Gas Company program, we are reporting-this as a. substantial safety hazard as defined by 10CFR21.
am Westinghouse and SCE&G are working concurrently at Summer Station on a solution which will be tested prior to issuance of a generic response by Westinghouse.
This is an interim report and a final report vill be sent when an adequate solution is achieved.
If you have any questions, please contact us.
Very truly yours,
Very truly yours,
                                                                                                    /
/
r               ,
r T. C. Nichols, Jr.
T. C. Nichols, Jr.
NEC:rm e
NEC:rm e


e 1
e 1
i
i Mr. James P. O'Reilly j
  ;        Mr. James P. O'Reilly j         Page 2 4-4 4
Page 2 4
CC: Messrs.             V. C. Summer
4 4
{                                 G. H. Fischer E. H. Crews, Jr.
CC: Messrs.
D. A. Nauman
V. C. Summer
!                                  O. S. Bradham J                                   0. W. Dixon R. B. Clary W. A. Williams, Jr.
{
G. H. Fischer E. H. Crews, Jr.
D. A. Nauman O. S. Bradham J
: 0. W. Dixon R. B. Clary W. A. Williams, Jr.
J. B. Knotts, Jr.
J. B. Knotts, Jr.
J. Skolds B. Bursey NPCF/Whitaker File s
J. Skolds B. Bursey NPCF/Whitaker File U. S. Nuclear Regulatory Commission #
U. S. Nuclear Regulatory Commissions #
s s
Office of Inspection and Enforcement i               Washington, DC 20555 U. S. Nuclear Regulatory Commission
Office of Inspection and Enforcement i
,                Document Management Branch Washington, DC 20555                           .
Washington, DC 20555 U. S. Nuclear Regulatory Commission Document Management Branch Washington, DC 20555 i
i
1 5
!                                                                        1 5
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Latest revision as of 09:43, 24 December 2024

Part 21 Rept Re Westinghouse Gate Valve Failure to Close Under Test Conditions Less Severe than Design Specs, Initially Reported on 801030.Cause Is Unknown.Final Rept Will Be Submitted Upon Determination of Resolution
ML19345D389
Person / Time
Site: Summer 
Issue date: 11/24/1980
From: Nichols T
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
REF-PT21-80-320-000 NUDOCS 8012150035
Download: ML19345D389 (3)
v • d • e


Text

al iautu 13 a mxi n FWU mfi it M!L L.l i - n@ m U +1

%O Cacb

~

PART 21 IDBEIFICATIOM NO.

So-320-oco CTPANY (WEJe<*ri 4 Cws Opp DATE OF IIITER_

d26ltro DIKET NO.

6-y 6 h

j DATEDISTRIBlHED idE to A m -

_ ORIGli!AL REPORT%

SUPPLF5NNTARV DISTRIBUTION:

2

.J f

s ea REACTOR (R)

FEL CYCLE &

SAFEGUARDS,(S) 1

-,, m PATERIALS OD a

IE FILES EES IEFILES AD/SG AD/FFFEI AD/ROI EGIONS I,II,III,IV,V REGIONSI,II,III,IV,V REGIONSI,II,III,IV,V VStOR BR. R-IV VEEOR BR. R-IV VENDOR BR. R IV T

LEB / FPA FIG 5715 ffSS/FCES SS-395 NPS/D3L AEOD FIB 7602 LOEB/FPA F135715 g,ES / SG SS-881 NRR/ DOE Ac0D FIS 7602 LDEB/FPA MG 5715 NRR/DSI ASLBP E M 450 AEOD FIG 762 ta W T SAP /SP fi'B-7210A ASLBP E/W 450 NRR/ DOL CSEPAL FILES 015 CBHPAL FILES 016 ASLBP EN 450

~

CBUPAL FILES (GR0io CENiPAL FILES ( GRON)

CBERAL FILES 016 PDR CENTPAL FILES SS-395 CENTRAL FILES (GR0fD LPDR PDR PDR TEPA LPDR LPDR TERA m[fsb ACi!0[{:

PRELIMINARY EVALUATION OF THE' ATTACHED REPORT INDICATES LEAD RESPONSIBILITY FOR FOLLOWUP AS SHOWN BELOW:

IE K

,NRR2 ffES [

OTHER EES 8012750030 Pa'. 8/1/80 s.

Mnhc id r.lto

TW.c. \\b4 Ta -[.b b b -Mo - eso c

SOUTH CAROLINA ELECTRIC a gas COMPANY

==

POST C F FsCC 90 764 CotunsiA. Souin CAnctiwA esais T. C %cwots.JR.

v.co.u.u.,.- s. tne,=

November 25, 1980 u.ea.. cn..

Mr. James P. O'Reilly U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 3100 Atlanta, GA 30303

Dear Mr. O'Reilly:

Subject:

Virgil C. Summer Nuclear Station, Unit 1 Docket No. 50/399 Reportable Su,bstantial Safety Hazard Westinghouse 3" Gate Valve Closure Failure On October 30, 1980, Mr. John Rausch of NRC Region II was informed by means of a telephone call of a potential significant deficiency.

During Hot Functional Testing, 10 Westinghouse 3" gate valves failed to completely close under test conditions which are less severe than the equipment specification design conditions.

The valves stroked to significantly restrict flow, but the full stroke was not accomplished to trip the " closed" positfen indicati:n contcets in the motor operator or to seat the valve disc within the valve body.

Failure of these valves to close completely could impair the ability of_the plant to operate or shutdown safely.

Under the South Carolina Electric and Gas Company program, we are reporting-this as a. substantial safety hazard as defined by 10CFR21.

am Westinghouse and SCE&G are working concurrently at Summer Station on a solution which will be tested prior to issuance of a generic response by Westinghouse.

This is an interim report and a final report vill be sent when an adequate solution is achieved.

If you have any questions, please contact us.

Very truly yours,

/

r T. C. Nichols, Jr.

NEC:rm e

e 1

i Mr. James P. O'Reilly j

Page 2 4

4 4

CC: Messrs.

V. C. Summer

{

G. H. Fischer E. H. Crews, Jr.

D. A. Nauman O. S. Bradham J

0. W. Dixon R. B. Clary W. A. Williams, Jr.

J. B. Knotts, Jr.

J. Skolds B. Bursey NPCF/Whitaker File U. S. Nuclear Regulatory Commission #

s s

Office of Inspection and Enforcement i

Washington, DC 20555 U. S. Nuclear Regulatory Commission Document Management Branch Washington, DC 20555 i

1 5

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i 1

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