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1 1.
1
Abnormal Occurrence Report No. 50-313/74-12 2.
: 1.     Abnormal Occurrence Report No. 50-313/74-12
Report Date:
: 3.    ' Occurrence Date:             11/9/74
11/18/74 3.
: 2.      Report Date:         11/18/74                 ,
' Occurrence Date:
                              ^
11/9/74
: 4.     Facility:         . Arkansas Nuclear One-Unit 1                                                   '
^
Rus_sellville, Arkansas                                                             ,
4.
PDT-1035, PDT-1037, and PT 1039
Facility:
: 5. Identification of Occurrence:
. Arkansas Nuclear One-Unit 1 Rus_sellville, Arkansas PDT-1035, PDT-1037, and PT 1039 Identification of Occurrence:
5.
Reactor Protection System (RPS) instrument line socket weld failure.
Reactor Protection System (RPS) instrument line socket weld failure.
                                                                                      ~
~
              -                      6. -Conditions Prior to Occurrence:
: 6. -Conditions Prior to Occurrence:
                                                                                                                                                        ~
~
Reactor Power                 0                 MWth i        Steady-State Power Net Output                    0              MWe Hot. Standby 0
Reactor Power 0
Cold Shutdown                     X                 Percent of Full Power                           %
MWth Steady-State Power i
4 Refueling Shutdown Routine Startup Operation Routine Shutdown                                     .
Hot. Standby Net Output 0
Operatio.n                                                   -  -
MWe Cold Shutdown X
Load Changes During Routine Power peration                             .
Percent of Full Power 0
Other (Specify)                                                                                               2 1'
4 Refueling Shutdown Routine Startup Operation Routine Shutdown Operatio.n Load Changes During Routine Power peration Other (Specify) 2 1'
:                  7. Description of Occurrence:                                                         .
7.
Description of Occurrence:
During a routine operator inspecfion at 1900 hours on 11/9/74, boric acid crystals were noticed near the three socket welds between isolation valves RC-1039B, RC-1035B and RC-1036B, and instruments PT-1039, PT-103.5 and PDT-1037 respectively. 'these are RPS instrumentation lines (3/8" 0.
During a routine operator inspecfion at 1900 hours on 11/9/74, boric acid crystals were noticed near the three socket welds between isolation valves RC-1039B, RC-1035B and RC-1036B, and instruments PT-1039, PT-103.5 and PDT-1037 respectively. 'these are RPS instrumentation lines (3/8" 0.
and 1/4" ID) on B RCS hot leg.
and 1/4" ID) on B RCS hot leg.
A 12S psig air test was conducted on the three socket weld couplings                                       '
A 12S psig air test was conducted on the three socket weld couplings following removal and only one was found to be leaking through a pin-Further examination will be conducted to determine hole in'the weld.
following removal and only one was found to be leaking through a pin-hole in'the weld. Further examination will be conducted to determine if all three welds were leaking or if boron crystals were deposited ort two welds from spray from the leaking weld.
if all three welds were leaking or if boron crystals were deposited ort two welds from spray from the leaking weld.
I-8 004170j3I NSP-10, Rev. 0                               - Page 1 of 3' July S, 1974
I-004170j3I 8
                                                                                                                      - , -        -,-r, - - -
July S, 1974 NSP-10, Rev. 0
                                                                          ,-a.n   -
- Page 1 of 3'
                                                                                            ..n.-     -m ,-
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    . b. /- .
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                                                                                                                                                                    ;
Sheet 2 l-50-313/74-12 Abnormal Occurrence Report No.
Sheet 2 l-           .
50-313/74-12 Abnormal Occurrence Report No.
: 8. - Designation of Apparent Cause of Occurrence _:
: 8. - Designation of Apparent Cause of Occurrence _:
Procedure                                           .
Procedure Design
Design
~
        ~
Unusual Service
Unusual Service
                                                  -Manufacture                                     Condition Including-Environmental
-Manufacture Condition Including-Environmental Installation /
                    ;
f Construction-Component Failure Opere. tor Other (Specify)
Installation /                 _
Not determined at this time.
f                                 Construction-                             Component Failure Opere. tor Other (Specify)   Not determined at this time.
i 9.
i
Analysis of Occurrence _:
: 9. Analysis of Occurrence _:
di- -
di- -
(                                                                                                                                       l h and At the'Ihere time  of no were    the safetyoccurrence implications the or hazard     reactor to thewas        hea tat co fication tion.
At the time of the occurrence the reactor was at co
safety of plant personnel or the public due to prompt identi and corrective action.
(
                                                                                                                              ~
l h and
'Ihere were no safety implications or hazard to the hea t fication safety of plant personnel or the public due to prompt identi tion.
and corrective action.
~
5:
5:
:6                                                                   ,
:6
: 10. Corrective Action:                                                                             i      ~;
: 10. Corrective Action:
A section of the tube 6" on either side of the socket weld c were removed and replaced with a new coupling.
~;
at 2285 psig did not reveal any defects.                                                                  .
i A section of the tube 6" on either side of the socket weld c were removed and replaced with a new coupling.
                \         's
at 2285 psig did not reveal any defects.
      ~)                                       .
\\
's
~)
Page 2 of.3l NSP-ID, Rev. O July 5, 1974
Page 2 of.3l NSP-ID, Rev. O July 5, 1974
                                                                                                            . , . . .,.        , .---.,.-,r--.,_r     --  , ...
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Abnormal Occurrence Report No.                                                     ' Sheet 3
I
                                                                              '50-313/74-12
' Sheet 3 Abnormal Occurrence Report No.
: 11. Failure Data:                                                                 i
'50-313/74-12 11.
                            ~
Failure Data:
i                          No prior failures of this type. Couplings are being given a metal -
i i
                                      'lurgical examination. These results will be submitted in a follow-up report.                            .
No prior failures of this type. Couplings are being given a metal -
s
~
: 12. Reviews and Approvals:
'lurgical examination. These results will be submitted in a follow-up report.
              ;
s 12.
Reviewed and Approved by: Plant Safety Committee                 Yes (x)       No ( )
Reviews and Approvals:
Plant Superintendent         Yes (X)       No ( )
Reviewed and Approved by: Plant Safety Committee Yes (x)
No ( )
Plant Superintendent Yes (X)
No ( )


==Reference:==
==Reference:==
JWA-667       Date: 11/18/74 Reviewed by:          &-              ,                  Date: #       77[
JWA-667 Date: 11/18/74 Date: #
            ~l                                         ',          Licensing Supervisor                             i
77[
Reviewed by:
~l i
Licensing Supervisor
(
(
Approved by: I , / //A                 pw., ,/             Date: // Y 6' M
I, / //A pw.,,/
                                                                                                          '                ~
Date: // Y 6' M Approved by:
1
~
                    '                                  /          afet R'eview mmi ee Approved by: A [           , e s d i m M ;-'-             Date: h              7
/
                                                                                                                      /
afet R'eview mmi ee 1
                                                        ' 'unager of ucearServic[
Date: h 7
                                                                                /
Approved by: A [
                                                                                                              /     -
, e s d i m M ;-'-
n Approved byr             ;//* / & ~j t' p ['
' 'unager of ucearServic[
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Approved byr
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Date: /[- / '' / '/
Date: /[- / '' / '/
                                                    .[         Director of Power P oduction Approved by:        / .    /   !          /o             Date:   /' /f' Senior'Vice President                                       ~
.[
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Director of Power P oduction
l
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  'd l                                                                                                                               ..
/o Date:
NSP-10, Rev. O                       Page 3 of 3 July 5, 1974}}
Approved by:
/.
/
Senior'Vice President
~
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l July 5, 1974 NSP-10, Rev. O Page 3 of 3}}

Latest revision as of 08:52, 31 December 2024

AO 50-313/74-12:on 741109,PDT-1035,PDT-1037 & PDT-1039 Reactor Protection Sys Instrument Line Socket Welds Failed. Cause Unknown.Tube on Each Side of Socket Weld Coupling Replaced W/New Coupling.Metallurgical Test in Progress
ML19326B699
Person / Time
Site: Arkansas Nuclear 
Issue date: 07/05/1974
From: Cavanaugh W, Phillips J, Reuter D
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19326B689 List:
References
NUDOCS 8004170538
Download: ML19326B699 (3)
v • d • e


Text

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1 1.

Abnormal Occurrence Report No. 50-313/74-12 2.

Report Date:

11/18/74 3.

' Occurrence Date:

11/9/74

^

4.

Facility:

. Arkansas Nuclear One-Unit 1 Rus_sellville, Arkansas PDT-1035, PDT-1037, and PT 1039 Identification of Occurrence:

5.

Reactor Protection System (RPS) instrument line socket weld failure.

~

6. -Conditions Prior to Occurrence:

~

Reactor Power 0

MWth Steady-State Power i

Hot. Standby Net Output 0

MWe Cold Shutdown X

Percent of Full Power 0

4 Refueling Shutdown Routine Startup Operation Routine Shutdown Operatio.n Load Changes During Routine Power peration Other (Specify) 2 1'

7.

Description of Occurrence:

During a routine operator inspecfion at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on 11/9/74, boric acid crystals were noticed near the three socket welds between isolation valves RC-1039B, RC-1035B and RC-1036B, and instruments PT-1039, PT-103.5 and PDT-1037 respectively. 'these are RPS instrumentation lines (3/8" 0.

and 1/4" ID) on B RCS hot leg.

A 12S psig air test was conducted on the three socket weld couplings following removal and only one was found to be leaking through a pin-Further examination will be conducted to determine hole in'the weld.

if all three welds were leaking or if boron crystals were deposited ort two welds from spray from the leaking weld.

I-004170j3I 8

July S, 1974 NSP-10, Rev. 0

- Page 1 of 3'

,-a.n

..n.-

-m

-,-r, - - -

e a

~

3

?.

I 1

. b. /-

Sheet 2 l-50-313/74-12 Abnormal Occurrence Report No.

8. - Designation of Apparent Cause of Occurrence _:

Procedure Design

~

Unusual Service

-Manufacture Condition Including-Environmental Installation /

f Construction-Component Failure Opere. tor Other (Specify)

Not determined at this time.

i 9.

Analysis of Occurrence _:

di- -

At the time of the occurrence the reactor was at co

(

l h and

'Ihere were no safety implications or hazard to the hea t fication safety of plant personnel or the public due to prompt identi tion.

and corrective action.

~

5:

6
10. Corrective Action:

~;

i A section of the tube 6" on either side of the socket weld c were removed and replaced with a new coupling.

at 2285 psig did not reveal any defects.

\\

's

~)

Page 2 of.3l NSP-ID, Rev. O July 5, 1974

.---.,.-,r--.,_r

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I

' Sheet 3 Abnormal Occurrence Report No.

'50-313/74-12 11.

Failure Data:

i i

No prior failures of this type. Couplings are being given a metal -

~

'lurgical examination. These results will be submitted in a follow-up report.

s 12.

Reviews and Approvals:

Reviewed and Approved by: Plant Safety Committee Yes (x)

No ( )

Plant Superintendent Yes (X)

No ( )

Reference:

JWA-667 Date: 11/18/74 Date: #

77[

Reviewed by:

~l i

Licensing Supervisor

(

I, / //A pw.,,/

Date: // Y 6' M Approved by:

~

/

afet R'eview mmi ee 1

Date: h 7

Approved by: A [

, e s d i m M ;-'-

' 'unager of ucearServic[

/

/

n

/

Approved byr

//* / & ~j t' p [

Date: /[- / / '/

.[

Director of Power P oduction

/' /f'

/o Date:

Approved by:

/.

/

Senior'Vice President

~

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l July 5, 1974 NSP-10, Rev. O Page 3 of 3

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