ML18139B213: Difference between revisions

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{{#Wiki_filter:NAC ~ORM 365 ' t;~n, . UPDATE REPORT
{{#Wiki_filter:NAC ~ORM 365 '
* U.S. NUCLEAR REGULATORY COMMISSION e LICENSEE EVENT REPORT PREVIceREPORT DATE 02-14-80 CONTROL BLOCK: I l Ii' (PL.EASE PRiNT OF! TYPE AL.L REOUIREO INFORMATION!
* U.S. NUCLEAR REGULATORY COMMISSION t;~n,        .        UPDATE REPORT e       LICENSEE EVENT REPORT PREVIceREPORT DATE 02-14-80 CONTROL BLOCK:             I
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                                                !o-1_ . . . _ _ . . _ . . _. . . . . .
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\.!./ [IE] I V l A I S I P I S I 1 IQ)l O I O l -I 7 S 9 ~ICENSES COOE 14 is 0 l 01 01 01 01 -I Ol O l(Dl 4 11 11 1111101 ' I© LICENSE NUMBER . 2S . 2S LICENSE TYPE JO 57 CAT 58 CON~ 1 o i 1 : ; 6
_..._-:.6 \.!./                   (PL.EASE PRiNT OF! TYPE AL.L REOUIREO INFORMATION!
!!!.J© I o I s l o I o I o I 21 s I o 101 o I 1 I 3 11 I s l o I© I O 13 1 2 l 7 J s f 1 I© 60 61 OOCKET NUMBER 66 69 EVENi OAT! .74 7S REPORT CA, E 80 EVENT OESCi:IIPTlON ANO PROBABLE CONSEQUENCES@
[IE] I V l A I S I P I S I 1 IQ)l                                       O   I Ol - I 0 l             01   01     01     01 -I Ol O l(Dl 4 11 11 1111101 ' I© 7        S    9        ~ICENSES COOE                14        is                              LICENSE NUMBER             .         2S . 2S       LICENSE TYPE       JO     57 CAT 58 CON~
l Pipe stress reanalysis on show cause liries outside cont*ainment has **t-eV'ealed an over-[[ID I stress on line 18"-CC-9-121, Unit No~ 2 supply to the "A" Residual Heat Removal .[[E) J Exchanger.
1o
This event is reportable in accordance with. the NRC-order lifting []J]J lsion of facility operation dated August 22,1979 and Technical Specification 6.6.2.a.9.J ]The health and safety of the public were not affected since the redundant train was .[]JI] ! operable and isolation capability of the affected line was available.
  ;
[ill] 7 8 9 r:rril 7 8 *SYSTEM cooE 1w IB I@ 9 10 CAUSE CAUSE COMP. CODE SUBCODE COMPONENT CCDE SU8COOE Ll.J@ L!..J@ , p , r , p , E , x , x ,e 1..~..1 11 12 1:J 18 19 SEQUENTIAL OCCURRENCE REPORT VAL.VE SUBCODE w@ 20 t:::... LERIRO LVENT YE.11,.R REPORT NO. CODE TYPE v.:.; Re"oRT I a I o I I I lo *1 1 I o I I /I I o I 1 I .LLJ 1-1 NUMBER 21 22 2:J 24 26 27 2S 29 :JO :n ACTION FUTURE EFF!:CT
i 1 6:           ~;~~~~    !!!.J© I o I s l o I o I oI 60              61                  OOCKET NUMBER 21 s I o 66 101 o I 1 I 3 69 11 EVENi OAT!
* SHUTDOWN ATTACHMENT NPFID-4 PRIME COMP. REVISION NO. w __ 3' COMPONENT MANUFACTURER I so 'TAKEN ACTION ON PLANT METHOO HOUR$ SUBMITTED . FORM tiUB. SUl"PUER LI@W@ W W !,o lo! *o Io I L.!J@). L!J* W@ :J:l :JS :J6 :17 40 41 42 '3 '-Jz I 2 I 2 I 2 I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 47 . . [II§] JStress calculations revealed that the installed supports would riot prevent an oyer-o::::o:::J 1stressed condition on the affected line during a Design Basis Earthguake.
I s l o.74I© I7SO 13 REPORT      12 l CA,7JE s   f1 80 I© EVENT OESCi:IIPTlON ANO PROBABLE CONSEQUENCES@
Modifics1,tjorl o:II] !was initiated in accordance with preliminary design drawings and completed priori~ to [il]J !the final stress calculation.
l Pipe       stress reanalysis on show cause liries outside cont*ainment                                                                         has **t-eV'ealed an over-
{IE] .-.L.....---------~--------------------------~ , a 9 *so FACIL.ITY . '3o' METHOD OF t,;:;\ STATUS . POWER . OTHER STATUS \:::;:/ DISCOVERY DISCOVERY DESCRIPTION tIELLl.J 11 I O I O '*' _ __;.;N~/ A;;,;,_ ___ *__. W@I Architect Engineer Analysis I : -a....,=~.:..:--:;.;....:;:.:;,:.c.i.;;=--:--:==.~=------8""'-0 8 9 10 12 13 44 45 '6 ACTIVITY CONTENT /.:'\ . . . . REL.EASED OF RELEASE AMOUNT OF ACTIVITY . . _I.DCA'!ION OF RELEASE _ITJI] UJ@ WI . . N/A I I N/A . , a e 10 11 " 7 80 PERSONNEL EXPOSURES IC\ NUMBER ~TYPE~ DESCRll'TION [TITI jO j O I O ,~Ll.J~l,,_..----.;;;.N:..:/
[[ID I stress                   on line 18"-CC-9-121, Unit No~ 2 supply to the "A" Residual Heat Removal
A,;,__ ___ ~--------------~ , a e 11 ,2 13
.[[E) J Exchanger.                             This event is reportable in accordance with. the NRC- order lifting susp~ri-
* so PERSONNEL INJURIES t::':'\ NUMBER OESCRll"TION\!,;., EE] Jo I o I o l@i...* ------~N1..:./A;!,.._
[]J]J           lsion of facility operation dated August 22,1979 and Technical Specification 6.6.2.a.9.J
____ ....;... ___________ 7 8 9 11 12 80 I.OSS OF OR OAMAGE TO FA(;II.ITY  
  ~ ]The health and safety of the public were not affected since the redundant train was
'43' TYPE DESCRIPTION [TJil -~{s)'---*-**--*------~N~/A~----------------------~
.[]JI] ! operable                     and isolation capability of the affected line was available.                                                                                                         I
7 a SI 10 80 PUBLICITY . NRC USE ONLY "' ISSUED~ OESCR.IPTION  
[ill]
\e!,I [fIT] l!Ll~-------------N_/
7         8   9                                                                                                                                                                                       so
A _____________ _ I I I 1 l I I I I l I I J_! 7 8 9 10 68 69 80 ;; l>Y0N::.....;;(_B0_4..;.)_*_35_7_-_3_l_B4__, __ _
                                        *SYSTEM                  CAUSE                  CAUSE                                                          COMP.            VAL.VE r:rril 7         8                         9 cooE 10 CODE 1w IB I@ Ll.J@ L!..J@ , p , r , p 11 SUBCODE 12                1:J COMPONENT CCDE
SURRY POWER DOCKET NO: REPORT NO: EVENT DATE: STATION, UNIT 1 50-280 80-010/0lX-l 01-31-80 e TITLE OF REPORT: EXCESSIVE STRESS ON PIPE 18"-CC-9-121
                                                                                                                              , E,   x, x 18
: 1. DESCRIPTION OF EVENT: During progress of the pipe stress reanalysis effort, it was determined that line 18"-CC-9-121 would have been overstressed (exceeding 50 percent ultimate capacity) in the event of a Design Basis Earthquake.
                                                                                                                                                ,e     SU8COOE 1..~..1 19 SUBCODE w@
The affected line feeds the Unit No.2 "A" RHR. Heat Exchanger.
20 SEQUENTIAL                            OCCURRENCE              REPORT                        REVISION t:::... LERIRO LVENT YE.11,.R v.:.; Re"oRT NUMBER I21 a I o22I                I2:J I REPORT NO.
This event is reportable in accordance:JWith the NRC order lifting suspension of unit operation dated August 22,1979 and Tech. Spec. 6.6.2.a.9.
lo *1 1 I o26I 24 I27/I CODE I2So I 1 29I TYPE
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: Since the redundant train was operable and isolation capability, for the affected line was available, the health and safety of the public were not affected.
                                                                                                                                                            .LLJ
: 3. CAUSE: The problem was disclosed when the architect engineer, who is conducting the pipe stress reanalysis required by the NRC Show Cause Order, discovered the overstress condition.
:JO 1-1
: 4. IMMEDIATE CORRECTIVE ACTION: The overstressed condition was relieved by installing a constraint in accordance with preliminary design drawings.
:n w __
: 5. SUBSEQUENT CORRECTIVE ACTION: No subsequent action is required since the overstressed
3' NO.
:condition has been rectified.
ACTION       FUTURE                 EFF!:CT
: 6. FUTURE CORRECTIVE ACTION: None required.
* SHUTDOWN                                     ~      ATTACHMENT         NPFID-4         PRIME COMP.               COMPONENT
                'TAKEN       ACTION             ON PLANT                 METHOO                           HOUR$     ~      SUBMITTED       . FORM tiUB.         SUl"PUER             MANUFACTURER LI@W@ :JSW
:J:l        ~
W
:J6
                                                                                                    !,o lo! *o Io40I 41L.!J@). L!J*
:17                                             42 W@ '-Jz I 2 I 2 I 2 I
                                                                                                                                                                        '3                              47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                           @             .                       .
[II§]         JStress calculations revealed that the installed supports would riot prevent                                                                                           an oyer-o::::o:::J   1stressed condition on the affected line during a Design Basis Earthguake.                                                                                               Modifics1,tjorl o:II] !was initiated in accordance with preliminary design drawings and completed priori~ to
[il]J         !the final stress calculation.
,{IE]     a  .-.L.....---------~--------------------------~
9                                                                                                                                                                                     *so FACIL.ITY
                                    ~ POWER
                                                                                        .           '3o'       METHOD OF DISCOVERY DESCRIPTION ~
t,;:;\
tIELLl.J 7        8 STATUS .
9 ACTIVITY 11 10 CONTENT IOIO          12
                                                        '*' _ -
13
                                                                          . OTHER STATUS \:::;:/
__;.;N~/A;;,;,__ _ _*__.
                                                                                                    /.:'\
44 DISCOVERY W@I'6 Architect 45 Engineer Analysis a....,=~.:..:--:;.;....:;:.:;,:.c.i.;;=--:--:==.~=------8""'-0
                                                                                                                                                        .             .     . .   ~
I:
REL.EASED OF RELEASE                             AMOUNT OF ACTIVITY                 ~          ..                                     _I.DCA'!ION OF RELEASE ~
_ITJI] UJ@ WI                                                   . . N/A                                     I             I       N/A
.,         a e                   10           11                                                         "               ~                                                                            80 PERSONNEL EXPOSURES                                           IC\
NUMBER       ~TYPE~ DESCRll'TION ~
[TITI
,        a e jO j OI O11,~Ll.J~l,,_..----.;;;.N:..:/
                                            ,2              13
* A,;,___ _ _~ - - - - - - - - - - - - - - ~                                                         so PERSONNEL INJURIES                       t::':'\
NUMBER               OESCRll"TION\!,;.,
EE] Jo I o I ol@i...*------~N1..:./A;!,..__ _ _ _....;..._ _ _ _ _ _ _ _ _ _ _~~
7        8    9                11        12                                                                                                                                                           80 I.OSS OF OR OAMAGE TO FA(;II.ITY TYPE        DESCRIPTION
                                                                  '43'
                                                                  ~
[TJil 7          a
                -~{s)'---*-**--*------~N~/A~----------------------~
SI           10                                                                                                                                                                         80 PUBLICITY             . ~                                                                                                                                  NRC   USE   ONLY ISSUED~ OESCR.IPTION             \e!,I                                                                                                                                                       "'
[fIT] l!Ll~-------------N_/A                                                                         _____________~ _I I I 1 l I I I I l I I J_!
7         8   9             10                                                                                                                                     68   69                           80 ;;
l>Y0N::.....;;(_B0_4..;.)_*_35_7_-_3_l_B4__,_ __ ~
 
e SURRY POWER STATION, UNIT 1 DOCKET NO:      50-280 REPORT NO:      80-010/0lX-l EVENT DATE:    01-31-80 TITLE OF REPORT:   EXCESSIVE STRESS ON PIPE 18"-CC-9-121
: 1. DESCRIPTION OF EVENT:
During progress of the pipe stress reanalysis effort, it was determined that line 18"-CC-9-121 would have been overstressed (exceeding 50 percent ultimate capacity) in the event of a Design Basis Earthquake. The affected line feeds the Unit No.2 "A" RHR. Heat Exchanger. This event is reportable in accordance:JWith the NRC order lifting suspension of unit operation dated August 22,1979 and Tech. Spec. 6.6.2.a.9.
: 2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:
Since the redundant train was operable and isolation capability, for the affected line was available, the health and safety of the public were not affected.
: 3. CAUSE:
The problem was disclosed when the architect engineer, who is conducting the pipe stress reanalysis required by the NRC Show Cause Order, discovered the overstress condition.
: 4. IMMEDIATE CORRECTIVE ACTION:
The overstressed condition was relieved by installing a constraint in accordance with preliminary design drawings.
: 5. SUBSEQUENT CORRECTIVE ACTION:
No subsequent action is required since the overstressed :condition has been rectified.
: 6. FUTURE CORRECTIVE ACTION:
None required.
: 7. GENERIC IMPLICATIONS:
: 7. GENERIC IMPLICATIONS:
The reanalysis has been directed towards all Show Cause Lines. As overstressed conditions arise*, the appropriate corrective actions are implemented.}}
The reanalysis has been directed towards all Show Cause Lines. As overstressed conditions arise*, the appropriate corrective actions are implemented.}}

Revision as of 03:16, 21 October 2019

Updated LER 80-010/01X-1:on 800131,overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE
ML18139B213
Person / Time
Site: Surry Dominion icon.png
Issue date: 03/27/1981
From: Joshua Wilson
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B212 List:
References
LER-80-010-01X-01, LER-80-10-1X-1, NUDOCS 8104020621
Download: ML18139B213 (2)
v • d • e


Text

{{#Wiki_filter:NAC ~ORM 365 '

  • U.S. NUCLEAR REGULATORY COMMISSION t;~n, . UPDATE REPORT e LICENSEE EVENT REPORT PREVIceREPORT DATE 02-14-80 CONTROL BLOCK: I
                                               !o-1_ . . . _ _ . . _ . . _. . . . . .

l Ii' _..._-:.6 \.!./ (PL.EASE PRiNT OF! TYPE AL.L REOUIREO INFORMATION! [IE] I V l A I S I P I S I 1 IQ)l O I Ol - I 0 l 01 01 01 01 -I Ol O l(Dl 4 11 11 1111101 ' I© 7 S 9 ~ICENSES COOE 14 is LICENSE NUMBER . 2S . 2S LICENSE TYPE JO 57 CAT 58 CON~ 1o 

 ;

i 1 6: ~;~~~~  !!!.J© I o I s l o I o I oI 60 61 OOCKET NUMBER 21 s I o 66 101 o I 1 I 3 69 11 EVENi OAT! I s l o.74I© I7SO 13 REPORT 12 l CA,7JE s f1 80 I© EVENT OESCi:IIPTlON ANO PROBABLE CONSEQUENCES@ l Pipe stress reanalysis on show cause liries outside cont*ainment has **t-eV'ealed an over- [[ID I stress on line 18"-CC-9-121, Unit No~ 2 supply to the "A" Residual Heat Removal .[[E) J Exchanger. This event is reportable in accordance with. the NRC- order lifting susp~ri- []J]J lsion of facility operation dated August 22,1979 and Technical Specification 6.6.2.a.9.J 

 ~ ]The health and safety of the public were not affected since the redundant train was

.[]JI] ! operable and isolation capability of the affected line was available. I [ill] 7 8 9 so 

                                        *SYSTEM                   CAUSE                   CAUSE                                                           COMP.            VAL.VE r:rril 7         8                         9 cooE 10 CODE 1w IB I@ Ll.J@ L!..J@ , p , r , p 11 SUBCODE 12                1:J COMPONENT CCDE
                                                                                                                              , E,   x, x 18
                                                                                                                                               ,e      SU8COOE 1..~..1 19 SUBCODE w@

20 SEQUENTIAL OCCURRENCE REPORT REVISION t:::... LERIRO LVENT YE.11,.R v.:.; Re"oRT NUMBER I21 a I o22I I2:J I REPORT NO. lo *1 1 I o26I 24 I27/I CODE I2So I 1 29I TYPE 

                                                                                                                                                            .LLJ
JO 1-1
n w __

3' NO. ACTION FUTURE EFF!:CT

  • SHUTDOWN ~ ATTACHMENT NPFID-4 PRIME COMP. COMPONENT
               'TAKEN       ACTION              ON PLANT                  METHOO                            HOUR$      ~       SUBMITTED       . FORM tiUB.         SUl"PUER              MANUFACTURER LI@W@ :JSW
J:l ~

W

J6
                                                                                                    !,o lo! *o Io40I 41L.!J@). L!J*
17 42 W@ '-Jz I 2 I 2 I 2 I
                                                                                                                                                                       '3                               47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS                                            @              .                       .

[II§] JStress calculations revealed that the installed supports would riot prevent an oyer-o::::o:::J 1stressed condition on the affected line during a Design Basis Earthguake. Modifics1,tjorl o:II] !was initiated in accordance with preliminary design drawings and completed priori~ to [il]J !the final stress calculation. 

,{IE]     a   .-.L.....---------~--------------------------~

9 *so FACIL.ITY 

                                    ~ POWER
                                                                                        .            '3o'        METHOD OF DISCOVERY DESCRIPTION ~

t,;:;\ tIELLl.J 7 8 STATUS . 9 ACTIVITY 11 10 CONTENT IOIO 12 

                                                       '*' _ -

13 

                                                                          . OTHER STATUS \:::;:/

__;.;N~/A;;,;,__ _ _*__. 

                                                                                                   /.:'\

44 DISCOVERY W@I'6 Architect 45 Engineer Analysis a....,=~.:..:--:;.;....:;:.:;,:.c.i.;;=--:--:==.~=------8""'-0 

                                                                                                                                                       .             .      . .    ~

I: REL.EASED OF RELEASE AMOUNT OF ACTIVITY ~ .. _I.DCA'!ION OF RELEASE ~ _ITJI] UJ@ WI . . N/A I I N/A ., a e 10 11 " ~ 80 PERSONNEL EXPOSURES IC\ NUMBER ~TYPE~ DESCRll'TION ~ [TITI 

,         a e jO j OI O11,~Ll.J~l,,_..----.;;;.N:..:/
                                           ,2              13
  • A,;,___ _ _~ - - - - - - - - - - - - - - ~ so PERSONNEL INJURIES t::':'\

NUMBER OESCRll"TION\!,;., EE] Jo I o I ol@i...*------~N1..:./A;!,..__ _ _ _....;..._ _ _ _ _ _ _ _ _ _ _~~ 7 8 9 11 12 80 I.OSS OF OR OAMAGE TO FA(;II.ITY TYPE DESCRIPTION 

                                                                 '43'
                                                                 ~

[TJil 7 a 

               -~{s)'---*-**--*------~N~/A~----------------------~

SI 10 80 PUBLICITY . ~ NRC USE ONLY ISSUED~ OESCR.IPTION \e!,I "' [fIT] l!Ll~-------------N_/A _____________~ _I I I 1 l I I I I l I I J_! 7 8 9 10 68 69 80 ;; l>Y0N::.....;;(_B0_4..;.)_*_35_7_-_3_l_B4__,_ __ ~

e SURRY POWER STATION, UNIT 1 DOCKET NO: 50-280 REPORT NO: 80-010/0lX-l EVENT DATE: 01-31-80 TITLE OF REPORT: EXCESSIVE STRESS ON PIPE 18"-CC-9-121

1. DESCRIPTION OF EVENT:

During progress of the pipe stress reanalysis effort, it was determined that line 18"-CC-9-121 would have been overstressed (exceeding 50 percent ultimate capacity) in the event of a Design Basis Earthquake. The affected line feeds the Unit No.2 "A" RHR. Heat Exchanger. This event is reportable in accordance:JWith the NRC order lifting suspension of unit operation dated August 22,1979 and Tech. Spec. 6.6.2.a.9.

2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS:

Since the redundant train was operable and isolation capability, for the affected line was available, the health and safety of the public were not affected.

3. CAUSE:

The problem was disclosed when the architect engineer, who is conducting the pipe stress reanalysis required by the NRC Show Cause Order, discovered the overstress condition.

4. IMMEDIATE CORRECTIVE ACTION:

The overstressed condition was relieved by installing a constraint in accordance with preliminary design drawings.

5. SUBSEQUENT CORRECTIVE ACTION:

No subsequent action is required since the overstressed :condition has been rectified.

6. FUTURE CORRECTIVE ACTION:

None required.

7. GENERIC IMPLICATIONS:

The reanalysis has been directed towards all Show Cause Lines. As overstressed conditions arise*, the appropriate corrective actions are implemented.}}

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