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| issue date = 06/09/1978
| issue date = 06/09/1978
| title = LER 78-035/01T-0 for Dresden, Unit 2 Re During pre-installation Corrosion Inspection of Recently Purchased Spent Fuel Storage Racks, Cracks Through Weld Metal in Aluminum Channel to Base Plate Fillet Welds Were Found in 8 of 18 Racks
| title = LER 78-035/01T-0 for Dresden, Unit 2 Re During pre-installation Corrosion Inspection of Recently Purchased Spent Fuel Storage Racks, Cracks Through Weld Metal in Aluminum Channel to Base Plate Fillet Welds Were Found in 8 of 18 Racks
| author name = Stephenson B B
| author name = Stephenson B
| author affiliation = Commonwealth Edison Co
| author affiliation = Commonwealth Edison Co
| addressee name = Keppler J G
| addressee name = Keppler J
| addressee affiliation = NRC/RGN-III
| addressee affiliation = NRC/RGN-III
| docket = 05000237
| docket = 05000237
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:,-Commonw.h Edison e Dresden Nucle ower Station R.R. #1 Morris; Illinois 60450 Telephone 815/942-2920
{{#Wiki_filter:e Commonw.h Edison Dresden Nucle       ower Station R.R. #1
* REGUlf\TORY on&KU tUl con June 9 ' BBS Ltr. #932 James G. Keppler, Regional Director Directorate of Regulatory Operations
                                              *REGUlf\TORY on&KU tUl con Morris; Illinois 60450 Telephone 815/942-2920
-Region III U.S. Nuclear Regulatory Com_mission 799 Roosevelt Road Glen Ellyn, IL 60137 1978 . C) (t) *-I ;.-t.1 CT:* o;C: c::  
                                                                            . C)
>o_ x:z:-('")(/) :;o :i:: ,.,, (") ::0 < ("') f'T1 (I) -'* '&deg; :.:n -* co *r.; r;.. E u:.1**1 ,,1:c: z -<o O'I no rri-.. (/)(./) i: -; C::Q z--CO -iC: -f .f!>o. 0 z ...... Reportable Occurrence Report #78-035/0lT-O, Docket #050-237 is hereby submitted to your office in accordance with.Dresden Nuclear Power Station Technical Specification performance of structures,  
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: systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases: or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition, BBS/deb Enclosure cc: Director of Inspection  
                                                                                        '&deg; co
& Enforcement tep son Station Superintendent Dresden Nuclear Power Station Director of Management Information  
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& Program Control File/NRC 7 ..... 11*;0027 C.1 -i*
                                                                                                    *r.;
NRC FORM 366 17-77) U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT e CONTROL BLOCK: I I Ir,'\ .____,__........__.___.__...._-:!6\..'.)
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e * .. (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1 *r I LI DI RI s I 2101 0 I 0 I -I 0 I 0 I 0 I 0 I 0 I 0 I 0 IG)l 4 11 11 11 I 1 101 I 10 7 B 9 LICENSEE COD.E 14 15 LICENSE NUMBER 25 26 LICENSE TYPE :JO 57 CAT 5B CON'T {ili] .7 B L!JG) I o I .s I o I o I o I 2 I 3 I 1 101 o I s I 3 I o I 1 I s '(DI o ! 6 I o I 9 I 1 I s I G) 60 61 DOCKET NUMBER. 68 69 EVENT DATE i"-75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
                                                                              *-I
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BBS Ltr. #932                                                            f'T1                  0
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                                                                                      ......             i*
James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Com_mission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #78-035/0lT-O, Docket #050-237 is hereby submitted to your office in accordance with.Dresden Nuclear Power Station Technical Specification 6.6~B.l.(i), performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases: or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition, tep        son Station Superintendent Dresden Nuclear Power Station BBS/deb Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC
                                                            ..... 11*;0027 7 C.1 -
 
NRC FORM 366                                                                                                                                     U.S. NUCLEAR REGULATORY COMMISSION 17-77)
CONTROL BLOCK: .____,__........__.___.__...._-:!6\..'.)
eI I    LICENSEE EVENT REPORT Ir,'\                                                        e (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI
~            1*r I LI DI RI s I 2101                             0 I 0 I - I 0 I 0 I 0 I 0 I 0 I~ I 0 I 0 IG)l                                 4   11 11 11 I 1 101 I 10 7       B   9       LICENSEE COD.E                 14       15                           LICENSE NUMBER                             25     26       LICENSE TYPE       :JO   57 CAT 5B CON'T
{ili]               :c;~~~~- L!JG) I o I                     .s I o I o I o I 2 I 3 I 1 101 o I s I 3 I o I 1 I s '(DI o ! 6 I o I 9 I 1 I s IG)
.7        B                    60               61               DOCKET NUMBER.                         68     69         EVENT DATE           i"-       75       REPORT DATE           BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@
I . During pre-installation corrosion inspection of recently purchased spent fuel storage!
I . During pre-installation corrosion inspection of recently purchased spent fuel storage!
racks, cracks through weld metal in aluminum channel to base plate fillet welds were I [ill] [TI[] found in 8 of !B racks. Eight other racks from same shipment were previously installfad before last ILDRS-3 refueling outage. The *s installed racks were not specifically  
[ill]              racks, cracks through weld metal in aluminum channel to base plate fillet welds were I
. . inspected for cracks but did pass similar pre-instaliatiOn inspection that found thesr :[&#xa3;]2] I cracks. Minimal safety significance evident since fuel was not stored in any racks . I [Ill I known to have weld cracks. This event _is not repetitive.
-~                found in 8 of !B racks.                                   Eight other racks from same shipment were previously installfad
7 B 9 BO SYSTEM CAUSE* CAUSE COMP. .VALVE CODE COL>E.-.
[TI[]            before last ILDRS-3 refueling outage.                                                         The *s installed racks were not specifically
SUB CODE COMPONENT CODE [ill]
  ~                inspected for cracks but did pass similar pre-instaliatiOn inspection that found thesr
UJ@ L!@ Ix Ix Ix I xi xi xl8 SUBCODE . SUBCOOE UJ@) UJ@ 7 B 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE  
:[&#xa3;]2] I cracks.                     Minimal safety significance evident since fuel was not stored in any racks . I
@ LERiRO CVENT YEAR REPORT NO. CODE REPORT I 7 I 8 I l=:J Io I 3 Is I ,,.,.., I 01 11 NUMBER 21 22 23 24 26 27 28 29 REPORT TYPE L:!J JO l=1 31 REVISION NO. l.QJ 32 COMPONENT MANUFACTURER ACTION FUTURE EFFECT. SHUTDOWN  
[Ill I known to have weld cracks.                                                 This event _is not repetitive.
(.;::;\ ATTACHMENT NPR0-4 PRIME.COMP.
7       B 9                                                                                                                                                                                       BO SYSTEM                     CAUSE*         CAUSE                                                                   COMP.           .VALVE CODE                     COL>E.-.     SUB CODE                           COMPONENT CODE                     SUBCODE          . SUBCOOE
SUPPLIER I cl o Is lo I ACTION ON PLANT METHOD HOURS SUBMITTED FORM :::.UB. . LxJ@W@ W@ W I o I o I o I o I W@ IJLJ(&sect; 33 34 35 36 37 40 41 42 ll!J@ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 43 44 47 I Cause unknown.  
[ill]                           LE.L~@.                        UJ@ L!@ Ix Ix Ix I xi xi xl8 UJ@) UJ@
-all fuel removed from 8 installed racks in ILDRS-3.
7       B                       9             10             11             12                       13                               18           19               20 SEQUENTIAL                                       OCCURRENCE           REPORT                        REVISION
An investigation; is being conducted by G.E. to determine the cause of the weld cracks, formulate a IITIJ repair program for the welds and an inspection program for the 8 installed racks and .[JJJ] I remaining welds on the 18 racks not installed.  
              @     LERiRO CVENT YEAR REPORT NUMBER I7 I8 I                     l=:J REPORT NO.
-Results of this investigation.
Io I 3 Is I                         ,,.,..,           CODE I 01   11 TYPE L:!J           l=1 NO.
will I be submitted in a supplemental report upon receipt.
l.QJ 21              22          23              24                      26        27              28      29            JO              31            32 ACTION FUTURE                     EFFECT.           SHUTDOWN                                       (.;::;\   ATTACHMENT         NPR0-4         PRIME.COMP.               COMPONENT TAKEr~      ACTION               ON PLANT               METHOD                             HOURS ~              SUBMITTED       FORM :::.UB.       SUPPLIER              MANUFACTURER
7 B 9 FACILITY STATUS % POWER OTHER STATUS [QI] UJ@ I o I 9 I* 4 l@_I _N_A ___ B 9 10 12 n 44 ACTIVITY CONTENT . t::;\ RELEASED OF RELEASE . AMOUNT O.F LzJ@ W@ ..... I -=NA=----------
            . LxJ@W@
8 9 10 . 11 44 PERSONNEL EXPOSURES NUMBER OESCRl?T'ON 80 METHOD OF A DISCOVERY DISCOVERY DESCRIPTION LQJ@ ... I _N_o_t_1_*
33        34 W@
_E_. --------45 46 80 LOCATION OF RELEASE@
35 W
I NA 45 BO GI?] lo Io lo lLJ@ NA 8. 9 11 12 .
36 I o I o I o I o I W@ IJLJ(&sect; ll!J@ I cl o Is lo I 37                           40     41             42                 43              44            47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @
PERSONNEL INJURIES  
I Cause unknown. - all fuel removed from 8 installed racks in ILDRS-3. An investigation; is being conducted by G.E. to determine the cause of the weld cracks, formulate a repair program for the welds and an inspection program for the 8 installed racks and IITIJ
. Q NUMBER o I 0*1 ol@'.":--.  
.[JJJ] I remaining welds on the 18 racks not installed. - Results of this investigation. will
-,--*--'-.  
  ~            I be submitted in a supplemental report upon receipt.
-*--=-*IA.._*
7       B   9                                                                                                                                                                                     80 FACILITY                                                                                       METHOD OF                                                                A STATUS             % POWER                             OTHER STATUS                           DISCOVERY                              DISCOVERY DESCRIPTION ~
B 9 ' 11 12 . . . so LOSS OF OR DAMAGE TO FACILITY  
[QI] UJ@ I o I                       9     I* 4 l@_I_N_A_ _ _~                                                LQJ@I..._N_o_t_1_*f_i_c_a_t_i_o_n_f_r~o_m_G_._E_.- - - - - - - -
@3 . TYPE DESCRIPTION
B   9             10                   12         n                                         44     45            46                                                                    80 ACTIVITY       CONTENT                                     .                 t::;\
* * .[Q2J Li.J@ * . .
RELEASED OF RELEASE                             . AMOUNT O.F     ACTIVITY\~.V                                                          LOCATION OF RELEASE@
* NA a 9 10
~8 LzJ@       9 W@
* PL;BLICITY  
10 I.....-=NA=----------
. G\
                                        . 11                                                                           45 NA                                                                I 44                                                                                         BO PERSONNEL EXPOSURES                                     ~
* so NRC tJSF. ONLY "' ISSUE DC\ UESCRIPTION [ili]  
NUMBER       ~TYPE                  OESCRl?T'ON ~.
. 8 9 10 I I I I I I I I I I I I I! NAME OF PRE PARER ____ J_._B_r_u_n  
GI?]8. lo    9 Io lo 11lLJ@      12        .
.... n.;;..e'-r___,*  
NA 1-3---~~---------------------------------~80.
------------
PERSONNEL INJURIES                   .     Q NUMBER             OESCRIPTION~
68 69 so.-;;. o* a. . . o '. PHONE:_X_-_4_7_2
~        B    9 oI 0*1 ol@'.":--.-,--*--'-.-*--=-*IA.._*--~---------------~---~
________
                        '     11       12 . .             .                                                                                                                                         so LOSS OF OR DAMAGE TO FACILITY TYPE        DESCRIPTION                      *
                                                              @3 * .
-* ATTACHMENT TO LICENSEE EVENT REPORT 78-035/0lT-0 COMMONWEALTH EDISON COMPANY (CWE) DRESDEN UNIT-2 (ILDRS-2)
.[Q2J Li.J@ * .                                                 .
DOCKET 11050-237 During a G.E. pre-installation corrosion inspection of the spent fuel storage racks cracks, l" to long through the weld metal in the aluminum*
* NA                                                                                                                           -~
chan:iel to base plate fillet welds, were found in 8 out of 18 racks. During D-3 8 other racks have been installed that came from the same. shipment as the above 18*racks mentioned.
a   9           10
These 8 racks were not inspected by G.E. _specifically for cracks in welds but did *pass same type of inspection found cracks in 8 out of 18 pre-installed storage racks. The cracks found in the pre-installed racks pose no safety question at this time
* so PL;BLICITY           . G\
* since there has been no fuel placed in the racks. This is the first time -:.racks have been found in any of the welds and thus should not be a repetitive occurrence  
* NRC tJSF. ONLY ISSUE DC\ UESCRIPTION ~
. . Upon finding*that 8 out of 18 pre-installed spent fuel storage racks had cracks in the welds, all f,uel was removed from the 8 racks now installed in the D-'-3 spent fuel pool 'therefore eliminating any chance of an accident with spent An int.ensive study program is being performed by G.E. on the cause of the cracks, repair program for the welds, inspection required for 8 racks currently installed in D-3 spent fuel pool and inspection for remaining.welds on the 18 racks not installed.
[ili]         LN.J~                                        .                                                                                                                                          "'
A supplemental repo+t will be submitted detailing the results of the investigations by G.E.}}
I I I I I I I I I I I I I!
8    9          10                                                                                                                                      68    69                          so.-;;.
o*
NAME OF PRE PARER _ _ _ _                      J_._B_r_u_n....n.;;..e'-r___,*- - - - - - - - - - - -                 PHONE:_X_-_4_7_2_ _ _ _ _ _ _ __                        a. .
                                                                                                                                                                                                        .o '.
 
ATTACHMENT TO LICENSEE EVENT REPORT 78-035/0lT-0 COMMONWEALTH EDISON COMPANY (CWE)
DRESDEN UNIT-2 (ILDRS-2)
DOCKET 11050-237 During a G.E. pre-installation corrosion inspection of the spent fuel storage racks cracks, l" to l~" long through the weld metal in the aluminum*
chan:iel to base plate fillet welds, were found in 8 out of 18 racks. During D-3 outage~ 8 other racks have been installed that came from the same.
shipment as the above 18*racks mentioned. These 8 racks were not inspected by G.E. _specifically for cracks in welds but did *pass same type of inspection tha~ found cracks in 8 out of 18 pre-installed storage racks. The cracks found in the pre-installed racks pose no safety question at this time
* since there has been no fuel placed in the racks. This is the first time -:.racks have been found in any of the welds and thus should not be a repetitive occurrence .
  . Upon finding*that 8 out of 18 pre-installed spent fuel storage racks had cracks in the welds, all f,uel was removed from the 8 racks now installed in the D-'-3 spent fuel pool 'therefore eliminating any chance of an accident with spent ~uel. An int.ensive study program is being performed by G.E.
on the cause of the cracks, repair program for the welds, inspection required for 8 racks currently installed in D-3 spent fuel pool and inspection for remaining.welds on the 18 racks not installed. A supplemental repo+t will be submitted detailing the results of the investigations by G.E.}}

Latest revision as of 07:32, 24 February 2020

LER 78-035/01T-0 for Dresden, Unit 2 Re During pre-installation Corrosion Inspection of Recently Purchased Spent Fuel Storage Racks, Cracks Through Weld Metal in Aluminum Channel to Base Plate Fillet Welds Were Found in 8 of 18 Racks
ML17252B515
Person / Time
Site: Dresden Constellation icon.png
Issue date: 06/09/1978
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR 932 LER 78-035/01T-0
Download: ML17252B515 (3)


Text

e Commonw.h Edison Dresden Nucle ower Station R.R. #1

  • REGUlf\TORY on&KU tUl con Morris; Illinois 60450 Telephone 815/942-2920

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BBS Ltr. #932 f'T1 0

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James G. Keppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Com_mission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #78-035/0lT-O, Docket #050-237 is hereby submitted to your office in accordance with.Dresden Nuclear Power Station Technical Specification 6.6~B.l.(i), performance of structures, systems, or components that requires remedial action or corrective measures to prevent operation in a manner less conservative than assumed in the accident analyses in the safety analysis report or technical specifications bases: or discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications that require remedial action or corrective measures to prevent the existence or development of an unsafe condition, tep son Station Superintendent Dresden Nuclear Power Station BBS/deb Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

..... 11*;0027 7 C.1 -

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION 17-77)

CONTROL BLOCK: .____,__........__.___.__...._-:!6\..'.)

eI I LICENSEE EVENT REPORT Ir,'\ e (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI

~ 1*r I LI DI RI s I 2101 0 I 0 I - I 0 I 0 I 0 I 0 I 0 I~ I 0 I 0 IG)l 4 11 11 11 I 1 101 I 10 7 B 9 LICENSEE COD.E 14 15 LICENSE NUMBER 25 26 LICENSE TYPE :JO 57 CAT 5B CON'T

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.7 B 60 61 DOCKET NUMBER. 68 69 EVENT DATE i"- 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

I . During pre-installation corrosion inspection of recently purchased spent fuel storage!

[ill] racks, cracks through weld metal in aluminum channel to base plate fillet welds were I

-~ found in 8 of !B racks. Eight other racks from same shipment were previously installfad

[TI[] before last ILDRS-3 refueling outage. The *s installed racks were not specifically

~ inspected for cracks but did pass similar pre-instaliatiOn inspection that found thesr

[£]2] I cracks. Minimal safety significance evident since fuel was not stored in any racks . I

[Ill I known to have weld cracks. This event _is not repetitive.

7 B 9 BO SYSTEM CAUSE* CAUSE COMP. .VALVE CODE COL>E.-. SUB CODE COMPONENT CODE SUBCODE . SUBCOOE

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7 B 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

@ LERiRO CVENT YEAR REPORT NUMBER I7 I8 I l=:J REPORT NO.

Io I 3 Is I ,,.,.., CODE I 01 11 TYPE L:!J l=1 NO.

l.QJ 21 22 23 24 26 27 28 29 JO 31 32 ACTION FUTURE EFFECT. SHUTDOWN (.;::;\ ATTACHMENT NPR0-4 PRIME.COMP. COMPONENT TAKEr~ ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM :::.UB. SUPPLIER MANUFACTURER

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36 I o I o I o I o I W@ IJLJ(§ ll!J@ I cl o Is lo I 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

I Cause unknown. - all fuel removed from 8 installed racks in ILDRS-3. An investigation; is being conducted by G.E. to determine the cause of the weld cracks, formulate a repair program for the welds and an inspection program for the 8 installed racks and IITIJ

.[JJJ] I remaining welds on the 18 racks not installed. - Results of this investigation. will

~ I be submitted in a supplemental report upon receipt.

7 B 9 80 FACILITY METHOD OF A STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION ~

[QI] UJ@ I o I 9 I* 4 l@_I_N_A_ _ _~ LQJ@I..._N_o_t_1_*f_i_c_a_t_i_o_n_f_r~o_m_G_._E_.- - - - - - - -

B 9 10 12 n 44 45 46 80 ACTIVITY CONTENT . t::;\

RELEASED OF RELEASE . AMOUNT O.F ACTIVITY\~.V LOCATION OF RELEASE@

~8 LzJ@ 9 W@

10 I.....-=NA=----------

. 11 45 NA I 44 BO PERSONNEL EXPOSURES ~

NUMBER ~TYPE OESCRl?T'ON ~.

GI?]8. lo 9 Io lo 11lLJ@ 12 .

NA 1-3---~~---------------------------------~80.

PERSONNEL INJURIES . Q NUMBER OESCRIPTION~

~ B 9 oI 0*1 ol@'.":--.-,--*--'-.-*--=-*IA.._*--~---------------~---~

' 11 12 . . . so LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION *

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a 9 10

  • so PL;BLICITY . G\
  • NRC tJSF. ONLY ISSUE DC\ UESCRIPTION ~

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I I I I I I I I I I I I I!

8 9 10 68 69 so.-;;.

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NAME OF PRE PARER _ _ _ _ J_._B_r_u_n....n.;;..e'-r___,*- - - - - - - - - - - - PHONE:_X_-_4_7_2_ _ _ _ _ _ _ __ a. .

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ATTACHMENT TO LICENSEE EVENT REPORT 78-035/0lT-0 COMMONWEALTH EDISON COMPANY (CWE)

DRESDEN UNIT-2 (ILDRS-2)

DOCKET 11050-237 During a G.E. pre-installation corrosion inspection of the spent fuel storage racks cracks, l" to l~" long through the weld metal in the aluminum*

chan:iel to base plate fillet welds, were found in 8 out of 18 racks. During D-3 outage~ 8 other racks have been installed that came from the same.

shipment as the above 18*racks mentioned. These 8 racks were not inspected by G.E. _specifically for cracks in welds but did *pass same type of inspection tha~ found cracks in 8 out of 18 pre-installed storage racks. The cracks found in the pre-installed racks pose no safety question at this time

  • since there has been no fuel placed in the racks. This is the first time -:.racks have been found in any of the welds and thus should not be a repetitive occurrence .

. Upon finding*that 8 out of 18 pre-installed spent fuel storage racks had cracks in the welds, all f,uel was removed from the 8 racks now installed in the D-'-3 spent fuel pool 'therefore eliminating any chance of an accident with spent ~uel. An int.ensive study program is being performed by G.E.

on the cause of the cracks, repair program for the welds, inspection required for 8 racks currently installed in D-3 spent fuel pool and inspection for remaining.welds on the 18 racks not installed. A supplemental repo+t will be submitted detailing the results of the investigations by G.E.