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{{#Wiki_filter:r ;c F~'.1366 (i*77)' LICENSEE EVENT REPORT LI.NUCLEAR REGULATORY COMMISSION CO\'JTROL BLOCK: ._I_...____....
{{#Wiki_filter:r ;c F~'.1366                                                                                                                                     LI.NUCLEAR REGULATORY COMMISSION (i*77)'
_ _.___. _ _..____,!
LICENSEE EVENT REPORT CO\'JTROL BLOCK:             ._I_...____...._ _.___._ _..____,! G)                             (PLEASE PRINT OR TYPE t:LL REQUIRED INFORMATION) 1                                          6
G) 1 6 (PLEASE PRINT OR TYPE t:LL REQUIRED INFORMATION)
[IT] IV 7        a    9
[IT] IV ! A I s Ip . I s I 1 101 0 l O I "'." I O I O I O I O I O I 7 I O 10 101 4 l 1 ' 1 ' 11 1101 I l 0 7 a 9 LICENSEE CODE 14 1S LICENSE NUMBER
                            !A   I s Ip . I s I 1 LICENSEE CODE                14 101 0 1S l O I "'." I O I O I O I O I O I LICENSE NUMBER 7
* 25 26 LICENSe TYPE :JO S7 CAT ss  
I O 10 101 25      26 4 l 1 ' 1 ' 11 1101 LICENSe TYPE       :JO I
~©I 01 s I o I o I o I 2 I 8 I o GI o 12 I 2 I s I 8 I 1 101 o I 3 l 1 l 1 ! s l 1 l © 60 61 DOCKET NUMBER \(_._ 68 69 EVENT DATE . 74 7S REPORT DATE 80 E:VE'\IT DESCRIPTION AND PROBABLE CONSEQUENCES@ . . !With the unit defueled, RT examination of loops A, B, C, main steam piping.revealed C£::J]J !linear i~di~ations at the weld near the safety va~ve riser: RT examination was []JI] !being conducted as *follow-up to the finding reported in LER 80-067/0lT-Oo This event! C2:l}] jis reportable per T.S. 6~6.2.a.(9).
S7 CAT ss l0
The indications found represent surface pitting []]]] 1and were code allowable.
                            ;~~~~~    ~©I                 01   s I oDOCKETI o I o I 2 I 8 I o GI o 12 I 2 I s I 8 I 1 101 o I 3 l 1 l 1 ! s l 1 l © 60             61                           NUMBER \(_._             68     69           EVENT DATE       .     74     7S     REPORT DATE           80 E:VE'\IT DESCRIPTION AND PROBABLE CONSEQUENCES@                                                                       .                               .
Therefore, the health and safety of the public were not [IT:] !affected.
                    !With the unit defueled, RT examination of loops A, B, C, main steam piping.revealed C£::J]J !linear i~di~ations at the weld near the safety va~ve riser:                                                                                             RT examination was
[ill] 7 8 9 [III] 7 8 SYSTEM CODE 1 c 1 c I@ 9 10 (.".;'\ LEA/RO CVENT YEAR \::,I REPORT j 8 l 1 ! NUMBER 21 22 CAUSE CAUSE COMP. cooe SUBCOOE COMPONENT CODE SUBCOOE. ~@ ~@ I Pl 11 Pl El XI x1@ ~@) 11. 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT VALVE SUBCOOE ~@ 20 REPORT NO. CODE TYPE I I I O I 0 1 1 1 1.,.....1 I 01 11 lLl l=1 23
[]JI]         !being conducted as *follow-up to the finding reported in LER 80-067/0lT-Oo                                                                                           This event!
* 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUTDOWN t.::\ ATTACHMENT NPR04 PRIME COMP. REVISION NO. LQJ 32 COMPONEI\IT MANUFACT..JRER 80 TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM liUB. SUPPLIER W@W@ LU@ 1.U I 01 01 01 01 L!J@). LI W 33 34 35 36 37 . 40 41 42 43 I GI 21 s 1 7 !@) CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 44 47 tfhe cause ,appears to be a type of corrosion pitting usually associated with stagnant 0JJJ ,oxygenated water. -~he-subject_-areas w:t;n be r.epaired_pri)JtJ;o  
C2:l}] jis reportable per T.S. 6~6.2.a.(9).                                                           The indications found represent surface pitting
*startup Of the unit. OE 7 . 8 9 FACILITY * '3a' METHOD OF STATUS % POWER OTHER STATUS \;:::J DISCOVERY DISCOVERY DESCRIPTION Inservice Inspection so tITIJ l!J@ I O I O I O !@)jS/G:::Repla~ement::.
[)))) 1and were code allowable.                                             Therefore, the health and safety of the public were not
j-~I 7 8 9 10 12 1'3 44 45 ----------------"------180 ACTIVITY CONTENT t:;;;\ RELEASEO OF RELEASE AMO.UNT OF ACTIVITY [ill] uJ @) LJ@I.___N_A
[IT:] !affected.
_____ _. 7 a 9 10 11 NA _LOCATION OF RELEASE @ 44 45 80 ?ERSONNEL EXPOSURES r:;;:;., NUMBER TYPE DESCRIPTION  
[ill]
*., ETI] -Jo* jO jO !~@.__ __ N_A _____________________
7       8   9                                                                                                                                                                                     80 SYSTEM                 CAUSE               CAUSE                                                               COMP.         VALVE CODE                  cooe           SUBCOOE                       COMPONENT CODE                         SUBCOOE.       SUBCOOE
---1 7 a 9 11 12 13 ?ERSONNEL INJURIES (A'.;\ NUMBER DESCRIPTION~
[III]
60 NA I [QTI Io! ol oj@ 1 a 9
7        8 1c 1c I@ ~@ ~@ I Pl 9          10            11.                  12              13 11      Pl El XI x1@       18
* 11 ... 12~----------------------------------------1 8 0 !..OSS OF OR DAMAGE TC FACILITY '4JI TYPE DESCRIPTION [QI] lU@ a 9 1~0-------------------------------------------'
                                                                                                                                                            ~@) ~@
90 NA .1 ?UBL I CITY Q\ ISSUEOC,;\
19             20 SEQUENTIAL                               OCCURRENCE             REPORT                     REVISION
DESCRIPTION~
(.".;'\  LEA/RO CVENT YEAR                                              REPORT NO.                                     CODE               TYPE                         NO.
NRC USE ONL y "' IIITJ lN.J6 _______ ___.:;..aN=A
                    \::,I REPORT NUMBER j8 l1        !          I23 I               I O I 0 1 1261              1.,.....1         I28 01   11           lLl           l=1           LQJ 21        22
______________
* 24                         27                           29         30             31           32 ACTION     FUTURE               EFFECT             SHUTDOWN                                   t.::\     ATTACHMENT             NPR04         PRIME COMP.             COMPONEI\IT TAKEN       ACTION             ON PLANT             METHOD                           HOURS   ~            SUBMITTED       FORM liUB.       SUPPLIER             MANUFACT..JRER W@W@
__, I I I l l I I l l I l l
33          34 LU@
* I ! 1 8 9 s 1 0 10 s 11 o s s s* 68 69 80 ; J. L. Wilson (804) 357-3184 NAME::)!=
35 1.U I 36                  37 01 01 01 01
OPEPARE=l-------~.:......--------
                                                                                                                        . 40 L!J@). LI 41               42 W
;,ucNE:-------------
43 I
0 *l, f ;-*~ATTACHMENT 1, PAGE 1 OF 2. SURRY POWER STATION, UNIT ! 1 e DOCKET NO: 50-280 .,. REPORT NO: 80-001/0lT-0 EVENT DATE: 02-25-81 ., / ,, . TITLE OF EVENT: MAIN STEAM PIPING DISCREPANCIES
44 GI   21 s 1 7 !@)
: 1. DESCRIPTION OF EVENT: With the unit defueled for steam generator replacement, RT examination of loop 'A' main steam piping revealed linear indications.
47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                     @
The indications are located in the vicinity of the welds that are adjacent to the safety valve riser stab-in. The safety valve riser is located outside the containment.
tfhe cause ,appears to be a type of corrosion pitting usually associated with stagnant 0JJJ         ,oxygenated water. - ~he- subject_-areas                                               w:t;n     be r.epaired_pri)JtJ;o *startup Of the unit.
The indications are in the lower third of the pipe's*circumference and at the transition of a counter bore. RT examination was being conducted as a follow-up to the findings reported on Unit No. 1 LER 80-067/0lT~
OE8 7 .           9                                                                                                                                                                                   so FACILITY STATUS
                                        % POWER                           OTHER STATUS
                                                                                                  '3a'
                                                                                                  \;:::J METHOD OF DISCOVERY                                   DISCOVERY DESCRIPTION tITIJ l!J@ I O I O I O !@)jS/G:::Repla~ement::. j- ~I 7       8   9               10               12       1'3                                     44     45 Inservice Inspection
                                                                                                                                ----------------"------180 ACTIVITY         CONTENT                                                       t:;;;\
RELEASEO OF RELEASE                             AMO.UNT OF ACTIVITY                                                                   _LOCATION OF RELEASE        @
[ill]         uJ @)           LJ@I.___N_A_ _ _ _ __.                                                                                   NA 7       a     9               10           11                                                     44           45                                                                               80
                        ?ERSONNEL EXPOSURES                                   r:;;:;.,
NUMBER         ~ TYPE               DESCRIPTION      
*., ETI]         -Jo* jO       jO   !~@.____N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                                                                                        ---1 7       a   9                 11       12           13                                                                                                                                         60
                        ?ERSONNEL INJURIES                     (A'.;\
NUMBER               DESCRIPTION~
[QTI 1        a 9
* Io! ol oj@       11        1 NA                                        I
                                              ... 2 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1                                                                   0 8
                  !..OSS OF OR DAMAGE TC FACILITY               '4JI TYPE         DESCRIPTION                     ~
[QI] lU@                                                             NA
    .1        a   9             1~0-------------------------------------------'
                          ?UBL I CITY               Q\
90 ISSUEOC,;\ DESCRIPTION~                                                                                                                                           NRC USE ONL y           "'
IIITJ lN.J6 __________.:;..aN=A_ _ _ _ _ _ _ _ _ _ _ _ _ ___, I I I l l I I                                                                                                               l l I l l* I!
1       8     9             10                                                                                                                                  68  69 s 1 0 s 11 os s s*                                 J. L. Wilson                                                                               (804) 357-3184 80 ;
0
                                                                                                                                                                                                              *l, NAME::)!= O P E P A R E = l - - - - - - - ~ . : . . . . . . - - - - - - - -                                         ;,ucNE:-------------
 
f       ;-*~ATTACHMENT 1, PAGE 1 OF SURRY POWER STATION, UNIT DOCKET NO:         50-280
: 2. ! 1
                                                                              /
e REPORT NO:       80-001/0lT-0 EVENT DATE: 02-25-81 TITLE OF EVENT:       MAIN STEAM PIPING DISCREPANCIES
: 1.     DESCRIPTION OF EVENT:
With the unit defueled for steam generator replacement, RT examination of loop
                            'A' main steam piping revealed linear indications. The indications are located in the vicinity of the welds that are adjacent to the safety valve riser stab-in.
The safety valve riser is located outside the containment. The indications are in the lower third of the pipe's*circumference and at the transition of a counter bore. RT examination was being conducted as a follow-up to the findings reported on Unit No. 1 LER 80-067/0lT~
Subsequent.RT examination of loops 'B' and 'C' main steam piping revealed similar indications at corresponding locations.
Subsequent.RT examination of loops 'B' and 'C' main steam piping revealed similar indications at corresponding locations.
This event is being*reported pursuant.
This event is being*reported pursuant. to Technical Specification 6.6.2.a.(9).
to Technical Specification 6.6.2.a.(9).
: 2.     PROBABLE CONSEQUENCES The indications found were allowable per ASME Section XI. In addition, the indi-cations were substantially less than the critical flaw size as referenced in the FSAR, Appendix D. Therefore, the health and safety of the public were not affected.
: 2. PROBABLE CONSEQUENCES The indications found were allowable per ASME Section XI. In addition, the cations were substantially less than the critical flaw size as referenced in the FSAR, Appendix D. Therefore, the health and safety of the public were not affected.
: 3.     CAUSE:
: 3. CAUSE: 4. The cause appears to be a type of corrosion pitting usually associated with stagnant oxygenated water. The "boat samples" were removed from A & C Main Steam piping and subjected to X-ray, macroscopic, and microscopic examination, revealing only corrosion pits and no cralking. . *
The cause appears to be a type of corrosion pitting usually associated with stagnant oxygenated water. The "boat samples" were removed from A & C Main Steam piping and subjected to X-ray, macroscopic, and microscopic examination, revealing only corrosion pits and no cralking. .                 **
* IMMEDIATE CORRECTIVE ACTION: The indications were verified by liquid penetrant examination.
: 4.      IMMEDIATE CORRECTIVE ACTION:                                                       .
: 5. SUBSEQUENT CORRECTIVE ACTION: The subject areas will be repaired prior to startup of the unit. Also, the shape of the counter-bore will be changed to reduce the stress in this area. ,,. <:_:*,.:;-~so-'6*.  
The indications were verified by liquid penetrant examination.
*-ACTIONS TAKEN TO PREVENT RECURRENCE:
: 5.     SUBSEQUENT CORRECTIVE ACTION:
As noted above, the indications were within code allowable tolerances.
The subject areas will be repaired prior to startup of the unit. Also, the shape of the counter-bore will be changed to reduce the stress in this area.
Routine surveillance as required by*T.S. 4.15" is considered adequate to detect problems in the future. (/ . 
,,. <:_:*,.:;-~so-'6*. *- ACTIONS TAKEN TO PREVENT RECURRENCE:
-..... :ATTACHNENT 1, PAGE 2 OF 2-SURRY POWER STATION, UNIT NOo 1 DOCKET NO: 50-280 REPORT NO: 80-001/0lT-0  
As noted above, the indications were within code allowable tolerances. Routine surveillance as required by*T.S. 4.15" is considered adequate to detect problems in the future.
&#xa3;VENT DATE 02-25-81 TITLE OF EVENT: MAIN STEAM PIPING DISCREPANCIES
(/
 
-..... :ATTACHNENT 1, PAGE 2 OF 2 -
SURRY POWER STATION, UNIT NOo 1 e
DOCKET NO:     50-280 REPORT NO:   80-001/0lT-0
      &#xa3;VENT DATE   02-25-81 TITLE OF EVENT:     MAIN STEAM PIPING DISCREPANCIES
: 7. GENERIC IMPLICATIONS:
: 7. GENERIC IMPLICATIONS:
e A special UT examination was conducted of the corresponding areas of main steam piping on Unit 2, while the unit was at power. -The examination found no evidence of cracking or other significant indications that could be attributed to internal flaws. I {,;}}
A special UT examination was conducted of the corresponding areas of main steam piping on Unit 2, while the unit was at power. -The examination found no evidence of cracking or other significant indications that could be attributed to internal flaws.
I
{,;}}

Latest revision as of 12:38, 17 March 2020

LER 81-001/01T-0:on 810225,w/unit Defueled for Steam Generator Replacement,Routine Testing Exam of Loop a Main Steam Piping Revealed Linear Indications.Caused by Corrosion Pitting.Subj Areas Will Be Repaired
ML18139B171
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/11/1981
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B170 List:
References
LER-81-001-01T, LER-81-1-1T, NUDOCS 8103170585
Download: ML18139B171 (3)
v • d • e


Text

r ;c F~'.1366 LI.NUCLEAR REGULATORY COMMISSION (i*77)'

LICENSEE EVENT REPORT CO\'JTROL BLOCK: ._I_...____...._ _.___._ _..____,! G) (PLEASE PRINT OR TYPE t:LL REQUIRED INFORMATION) 1 6

[IT] IV 7 a 9

!A I s Ip . I s I 1 LICENSEE CODE 14 101 0 1S l O I "'." I O I O I O I O I O I LICENSE NUMBER 7

I O 10 101 25 26 4 l 1 ' 1 ' 11 1101 LICENSe TYPE :JO I

S7 CAT ss l0

~~~~~ ~©I 01 s I oDOCKETI o I o I 2 I 8 I o GI o 12 I 2 I s I 8 I 1 101 o I 3 l 1 l 1 ! s l 1 l © 60 61 NUMBER \(_._ 68 69 EVENT DATE . 74 7S REPORT DATE 80 E
VE'\IT DESCRIPTION AND PROBABLE CONSEQUENCES@ . .

!With the unit defueled, RT examination of loops A, B, C, main steam piping.revealed C£::J]J !linear i~di~ations at the weld near the safety va~ve riser: RT examination was

[]JI] !being conducted as *follow-up to the finding reported in LER 80-067/0lT-Oo This event!

C2:l}] jis reportable per T.S. 6~6.2.a.(9). The indications found represent surface pitting

[)))) 1and were code allowable. Therefore, the health and safety of the public were not

[IT:] !affected.

[ill]

7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE cooe SUBCOOE COMPONENT CODE SUBCOOE. SUBCOOE

[III]

7 8 1c 1c I@ ~@ ~@ I Pl 9 10 11. 12 13 11 Pl El XI x1@ 18

~@) ~@

19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

(.".;'\ LEA/RO CVENT YEAR REPORT NO. CODE TYPE NO.

\::,I REPORT NUMBER j8 l1  ! I23 I I O I 0 1 1261 1.,.....1 I28 01 11 lLl l=1 LQJ 21 22

  • 24 27 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN t.::\ ATTACHMENT NPR04 PRIME COMP. COMPONEI\IT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM liUB. SUPPLIER MANUFACT..JRER W@W@

33 34 LU@

35 1.U I 36 37 01 01 01 01

. 40 L!J@). LI 41 42 W

43 I

44 GI 21 s 1 7 !@)

47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

tfhe cause ,appears to be a type of corrosion pitting usually associated with stagnant 0JJJ ,oxygenated water. - ~he- subject_-areas w:t;n be r.epaired_pri)JtJ;o *startup Of the unit.

OE8 7 . 9 so FACILITY STATUS

% POWER OTHER STATUS

'3a'

\;:::J METHOD OF DISCOVERY DISCOVERY DESCRIPTION tITIJ l!J@ I O I O I O !@)jS/G:::Repla~ement::. j- ~I 7 8 9 10 12 1'3 44 45 Inservice Inspection

"------180 ACTIVITY CONTENT t:;;;\

RELEASEO OF RELEASE AMO.UNT OF ACTIVITY _LOCATION OF RELEASE @

[ill] uJ @) LJ@I.___N_A_ _ _ _ __. NA 7 a 9 10 11 44 45 80

?ERSONNEL EXPOSURES r:;;:;.,

NUMBER ~ TYPE DESCRIPTION

  • ., ETI] -Jo* jO jO  !~@.____N_A_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ---1 7 a 9 11 12 13 60

?ERSONNEL INJURIES (A'.;\

NUMBER DESCRIPTION~

[QTI 1 a 9

  • Io! ol oj@ 11 1 NA I

... 2 ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1 0 8

!..OSS OF OR DAMAGE TC FACILITY '4JI TYPE DESCRIPTION ~

[QI] lU@ NA

.1 a 9 1~0-------------------------------------------'

?UBL I CITY Q\

90 ISSUEOC,;\ DESCRIPTION~ NRC USE ONL y "'

IIITJ lN.J6 __________.:;..aN=A_ _ _ _ _ _ _ _ _ _ _ _ _ ___, I I I l l I I l l I l l* I!

1 8 9 10 68 69 s 1 0 s 11 os s s* J. L. Wilson (804) 357-3184 80 ;

0

  • l, NAME::)!= O P E P A R E = l - - - - - - - ~ . : . . . . . . - - - - - - - -  ;,ucNE:-------------

f  ;-*~ATTACHMENT 1, PAGE 1 OF SURRY POWER STATION, UNIT DOCKET NO: 50-280

2.  ! 1

/

e REPORT NO: 80-001/0lT-0 EVENT DATE: 02-25-81 TITLE OF EVENT: MAIN STEAM PIPING DISCREPANCIES

1. DESCRIPTION OF EVENT:

With the unit defueled for steam generator replacement, RT examination of loop

'A' main steam piping revealed linear indications. The indications are located in the vicinity of the welds that are adjacent to the safety valve riser stab-in.

The safety valve riser is located outside the containment. The indications are in the lower third of the pipe's*circumference and at the transition of a counter bore. RT examination was being conducted as a follow-up to the findings reported on Unit No. 1 LER 80-067/0lT~

Subsequent.RT examination of loops 'B' and 'C' main steam piping revealed similar indications at corresponding locations.

This event is being*reported pursuant. to Technical Specification 6.6.2.a.(9).

2. PROBABLE CONSEQUENCES The indications found were allowable per ASME Section XI. In addition, the indi-cations were substantially less than the critical flaw size as referenced in the FSAR, Appendix D. Therefore, the health and safety of the public were not affected.
3. CAUSE:

The cause appears to be a type of corrosion pitting usually associated with stagnant oxygenated water. The "boat samples" were removed from A & C Main Steam piping and subjected to X-ray, macroscopic, and microscopic examination, revealing only corrosion pits and no cralking. . **

4. IMMEDIATE CORRECTIVE ACTION: .

The indications were verified by liquid penetrant examination.

5. SUBSEQUENT CORRECTIVE ACTION:

The subject areas will be repaired prior to startup of the unit. Also, the shape of the counter-bore will be changed to reduce the stress in this area.

,,. <:_:*,.:;-~so-'6*. *- ACTIONS TAKEN TO PREVENT RECURRENCE:

As noted above, the indications were within code allowable tolerances. Routine surveillance as required by*T.S. 4.15" is considered adequate to detect problems in the future.

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-..... :ATTACHNENT 1, PAGE 2 OF 2 -

SURRY POWER STATION, UNIT NOo 1 e

DOCKET NO: 50-280 REPORT NO: 80-001/0lT-0

£VENT DATE 02-25-81 TITLE OF EVENT: MAIN STEAM PIPING DISCREPANCIES

7. GENERIC IMPLICATIONS:

A special UT examination was conducted of the corresponding areas of main steam piping on Unit 2, while the unit was at power. -The examination found no evidence of cracking or other significant indications that could be attributed to internal flaws.

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