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{{#Wiki_filter:-7,77,"'- Y #. ." t.lCENSEE EVENT REPORT CONTROL BLOCK: l llllll(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 GTl I Nl Cl P l El Pl 1[gl50 j 0 ] -l 0 l 0 ] 0 ] 0 l 0 l - l 0 l 0 lgl 4 l 1 l l j 1l l jgl llg 7 8 9 LICENSEE CODE 14 1 LICENSE NUMBER 25 26 LICENSE TYPE JO
{{#Wiki_filter:-
$7 CA T 58 CON'T E ERCE IL h l Ol 5l0l-l013l215 @l1lllllOl7l9l@l llllll@" 7 8 60 61 DOCK ET NUMBER 68 69 EVENT CATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 I lWhile work was progressing on the seal replacement of the"A" reactor recirculation l pump, a mechanic noted that a nonisolable weld on pump"A" suction line test con-lo a o 4 Inection was leaking. The 3/4-inch line is about 2-1/2 feet in length and contains a
                                                                                                                                            . .
, o s 90* elbow, two 3/4-inch valves, and a cap.
            "
The crack was associated with the pipe to l telbow weld away from the recirculation loop.
7,77,"'- Y #
I o e O 7 i Technical Specifications 6.9.1.8c lI o a i 80 7 8 9 DE CODE SLBC E COMPONENT CODE SU8 CODE S ElClBl@@ l C l@ lP lIl P l E l X l X l@ J@ l Zl @
t.lCENSEE EVENT REPORT CONTROL BLOCK: l                       l      l      l      l  l    l                    (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1                                       6 GTl 8I 9Nl ClLICENSEE      P l El           Pl       1[gl50           j 0   ] -l   0 l 0 ] 0     ] 0 l 0   l - l 0 l250 lgl l     lg 14                              LICENSE    NUMBER                              26 4 LICENSE l 1 l   l j TYPE1l JOl jgl$7 CA T 58 7                                        CODE                    1 CON'T E                           "
O 9 7 8 9 10 11 12 IJ 18 19 20 ,_SEOUENTIAL OCCURRENCE REPORT REVISION LE R/RO EVENT YE AR REPORT No.
ERCE IL h l Ol 5l0l-l013l215 @l1lllllOl7l9l@l                                                                                       75 l      l    l    l    l 80 l@
CODE TYPE N O.OO yUQEl7l9ll-l0l9l6ll/ll0l1ll Tll-ll0 lRE RT 21 22 23 24 26 27 N 3 30 31 32 T KN ACT ON ON PLANT TE hours S8 i O FOR 8.SUPPLIE MANUFACTURER lFl@lXl@Cl@LZ_j@l0l0l7l0ll Y l@lYl@lNl@lBl4l5l0l@
68    69        EVENT CATE                74                REPORT DATE 7         8                       60               61               DOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 I lWhile work was progressing on the seal replacement of the "A"                                                                               reactor recirculation o  a      l pump, a mechanic noted that a nonisolable weld on pump "A"                                                                     suction line test con-                           l o   4     Inection was leaking. The 3/4-inch line is about 2-1/2 feet in length and contains a
33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h lThe line*was cut upstream of the 90* elbow, plugged, and capped per an approved plant i olTTTl [ modification. A similar modification was performed on the"B" pump during this period.i g JThe Unit No. 2"B" pump was modified in 1977 and the Unit No. 2"A" pump will be modi-l g , l 31 lfied at the next scheduled cold shutdown (presently December 1979). Affected welds on[
        ,
L' L4J Iboth Unit No. 1 connections will be metallurgically evaluated to determine the cause
90* elbow, two 3/4-inch valves, and a cap.                                                       The crack was associated with the pipe to l o  s o e        telbow weld away from the recirculation loop.                                                                                                                                       I O   7     i Technical Specifications 6.9.1.8c                                                                                         l I
[80 7 8 9 STA S% POWER oTHER STA TUS is O RY DISCOVERY DESCRIPTION W l,_Gj @ l0l 0 l 0l h l N/A ll A l@l Mechanic Surveillance l0 ACTIVITY CO TENT'RETE ASEo CF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE
o a i                                                                                                                                                                                       80 7         8 9 DE                 CODE         SLBC E                   COMPONENT CODE                       SU8 CODE           S         E 7
{_gj @ W@l N/A l N/Ali c 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION lO!0l0l@lZl@lN/A l7 PensONNE t iN;u'siES
O  9 8
, h g 9" 3 ,1 g''#" 80'' 'lNOUtt E R DESCitiPT10N l0l0l0lhlN/A
lClBl@
(,Ei (b J-'#i 1 M 9 11 12 go LOSS OF On DAMAGE TO F ACILITY TYPE DE SCniP TION j hlZl@lN/Ali 9 F M'J 10 80 Pt stLL ICl l Y NRC USE ONLY
9            10            11
                                                                            @ l C l@ lP 12            IJ lIl P l E l X l X l@ J@ l Zl @
18             19               20 SEOUENTIAL                          OCCURRENCE               REPORT                         REVISION
                                    ,_
EVENT YE AR                                   REPORT No.                             CODE                   TYPE                             N O.
LE R/RO OO     RE RT yUQE                l7l9l                    l-l                0l9l6l                  l/l          l0l1l                    l Tl            l-l          l0 l 21           22           23             24             26         27           N         3             30               31             32 T KN ACT ON                         ON PLANT               TE                     hours               S8 i     O       FOR         8. SUPPLIE                 MANUFACTURER lFl@lXl@
33          34                      35 Cl@               LZ_j@
36 l0l0l7l0l 37                      40 l41Y l@           lYl@ lNl@ lBl4l5l0l@
42                   43               44             47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i  o      lThe line*was cut upstream of the 90* elbow, plugged, and capped per an approved plant lTTTl [ modification. A similar modification was performed on the "B" pump during this period.i g JThe Unit No. 2                                   "B" pump was modified in 1977 and the Unit No. 2 "A" pump will be modi-l g , l 31 lfied at the next scheduled cold shutdown (presently December 1979). Affected welds on[
L' L4J Iboth Unit No. 1 connections will be metallurgically evaluated to determine the cause                                                                                                       [
7       8 9                                                                                                                                                                                   80 STA S                 % POWER                             oTHER STA TUS                 is O RY                                 DISCOVERY DESCRIPTION W l,_Gj @ l0l 0 l 0l h l N/A                                                                       l      l A l@l Mechanic Surveillance                                                           0 l
ACTIVITY       CO TENT
                                                                                                                                        '
RETE ASEo CF RELEASE                               AMOUNT OF ACTIVITY                                                             LOCATION OF RELEASE i  c      {_gj @ W@l N/A                                                                   44 l N/A 45                                                                              80 l
7       8 9                   10               11 PERSONNEL EXPOSURES NUMBER                   TYPE           DESCRIPTION
  '
7 lO!0l0l@lZl@lN/A                             "                                                                                                          "      ,1              80 l
          ' ' PensONNE''t iN;u'siES         #
                                                                                                                                  ,
g             9           l 3         g NOUtt E R               DESCitiPT10N                                                                           h                                                        #
(b l0l0l0lhlN/A                                                                                                               (,Ei                           J     -     '
i M 9                   11       12 go 1
LOSS OF On DAMAGE TO F ACILITY TYPE       DE SCniP TION                                                                                                                 j         h l
F i 9 M
lZl@lN/A
                'J           10                                                                                                                                                                   80 Pt stLL ICl l Y                                                                                                                                           NRC USE ONLY
[1Loj G8f"NE" '
[1Loj G8f"NE" '
79112603 9/3 iititiiiiiiiil) 68 69 80 5;#M U 10~NAME Of PREPAHEli PHONE:_  
  #        MU                10 79112603 9/3 iititiiiiiiiil)                   68 69                               80 5;
-..a..LER CONTINUATION--RO #1-79-96 FACILITY: BSEP Unit No. 1 EVENT DATE:
                                                                                                                                                                      ~
11-10-79 of failure.
NAME Of PREPAHEli                                                                                             PHONE:
!-1Toi 194.G e}}
_
 
  ..a.
      -
                                                                    .
LER CONTINUATION--RO #1-79-96 FACILITY: BSEP Unit No. 1                           EVENT DATE: 11-10-79 of failure.
!                                                                                 -
1Toi     194
              .
G e}}

Revision as of 12:36, 19 October 2019

LER 79-096/01T-0:on 791110,nonisolable Weld on Pump a Suction Line Test Connection Discovered Leaking.Cause Unknown.Line Cut,Plugged & Capped.Affected Weld Connections Will Be Metallurgically Evaluated
ML19210D352
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 11/21/1979
From:
CAROLINA POWER & LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19210D351 List:
References
LER-79-096-01T, LER-79-96-1T, NUDOCS 7911260338
Download: ML19210D352 (1)


Text

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. .

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7,77,"'- Y #

t.lCENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 GTl 8I 9Nl ClLICENSEE P l El Pl 1[gl50 j 0 ] -l 0 l 0 ] 0 ] 0 l 0 l - l 0 l250 lgl l lg 14 LICENSE NUMBER 26 4 LICENSE l 1 l l j TYPE1l JOl jgl$7 CA T 58 7 CODE 1 CON'T E "

ERCE IL h l Ol 5l0l-l013l215 @l1lllllOl7l9l@l 75 l l l l l 80 l@

68 69 EVENT CATE 74 REPORT DATE 7 8 60 61 DOCK ET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o l 2 I lWhile work was progressing on the seal replacement of the "A" reactor recirculation o a l pump, a mechanic noted that a nonisolable weld on pump "A" suction line test con- l o 4 Inection was leaking. The 3/4-inch line is about 2-1/2 feet in length and contains a

,

90* elbow, two 3/4-inch valves, and a cap. The crack was associated with the pipe to l o s o e telbow weld away from the recirculation loop. I O 7 i Technical Specifications 6.9.1.8c l I

o a i 80 7 8 9 DE CODE SLBC E COMPONENT CODE SU8 CODE S E 7

O 9 8

lClBl@

9 10 11

@ l C l@ lP 12 IJ lIl P l E l X l X l@ J@ l Zl @

18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION

,_

EVENT YE AR REPORT No. CODE TYPE N O.

LE R/RO OO RE RT yUQE l7l9l l-l 0l9l6l l/l l0l1l l Tl l-l l0 l 21 22 23 24 26 27 N 3 30 31 32 T KN ACT ON ON PLANT TE hours S8 i O FOR 8. SUPPLIE MANUFACTURER lFl@lXl@

33 34 35 Cl@ LZ_j@

36 l0l0l7l0l 37 40 l41Y l@ lYl@ lNl@ lBl4l5l0l@

42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o lThe line*was cut upstream of the 90* elbow, plugged, and capped per an approved plant lTTTl [ modification. A similar modification was performed on the "B" pump during this period.i g JThe Unit No. 2 "B" pump was modified in 1977 and the Unit No. 2 "A" pump will be modi-l g , l 31 lfied at the next scheduled cold shutdown (presently December 1979). Affected welds on[

L' L4J Iboth Unit No. 1 connections will be metallurgically evaluated to determine the cause [

7 8 9 80 STA S  % POWER oTHER STA TUS is O RY DISCOVERY DESCRIPTION W l,_Gj @ l0l 0 l 0l h l N/A l l A l@l Mechanic Surveillance 0 l

ACTIVITY CO TENT

'

RETE ASEo CF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE i c {_gj @ W@l N/A 44 l N/A 45 80 l

7 8 9 10 11 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

'

7 lO!0l0l@lZl@lN/A " " ,1 80 l

' ' PensONNEt iN;u'siES #

,

g 9 l 3 g NOUtt E R DESCitiPT10N h #

(b l0l0l0lhlN/A (,Ei J - '

i M 9 11 12 go 1

LOSS OF On DAMAGE TO F ACILITY TYPE DE SCniP TION j h l

F i 9 M

lZl@lN/A

'J 10 80 Pt stLL ICl l Y NRC USE ONLY

[1Loj G8f"NE" '

  1. MU 10 79112603 9/3 iititiiiiiiiil) 68 69 80 5;

~

NAME Of PREPAHEli PHONE:

_

..a.

-

.

LER CONTINUATION--RO #1-79-96 FACILITY: BSEP Unit No. 1 EVENT DATE: 11-10-79 of failure.

! -

1Toi 194

.

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