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=Text=
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{{#Wiki_filter:lU. S. NUCLE AR HEGUL ATORY CO*.1 MISSION
{{#Wiki_filter:l
,~J RC FCRM 'u6 S:7 7D LICENSEE EVENT REPORT conTnOL stOcx: l lllll(PLE AS'i PRINT OR TYPE alt HEQUmED INF ORMATIONI l0 lH lD lB lS l1 @lh 0l 0
                                                                                                                                                                                                              ,
-] 0l 0l NJ Pl Fl -l 0] 3l@l4 l1 l1 l1 1l@lll@j h 26 LICENSE IN PE JO Si LAI $$lo 1 LICENSE NLWEH
U. S. NUCLE AR HEGUL ATORY CO*.1 MISSION
!8 9 LICENSEE CODE 14 7. "y l L l@l 0 l 5 l 0 l- [ 0 l 3 l 4 l 6 l@l 1 l 2 l 2 l 7 l 7 l 9 l@l 0 l 1 l 0 l 8 l 8 l 0 l@
  ~J RC FCRMS'u6
CON'T'4 75 htpOa1 D ATE 80:o i M 63 EVENT 0 ATE 0)61 COCK ET NU'.'UE R 8 EVENT DESCRIPTION A ND PROB ABLE CONSECUENCES h lOn December 21, 1979, it was discovered that there was insufficient clearance between j
:7 7D LICENSEE EVENT REPORT conTnOL stOcx: l                   l    l    l    l  l                        (PLE AS'i PRINT OR TYPE alt HEQUmED INF ORMATIONI o                                                                                -] 0lLICENSE 0l NJNLWEH Pl Fl -l 0] 3l@l4                         l1 l1IN PE1l@l l1LICENSE              JO l
:o 2[the Reactor Coolant System (RCS) hot leg and some of the shims of the pipe whip res-o 3 ltraints. On December 27, 1979, it was determined that this was in conflict with an j to-that there be no contact betweentheRCy lassumption of the RCS piping seismic analysis, io s This became immediately reportable under T.S. j 0 6 l hot leg piping and the whip restraints.
Si LAI $$
There was no danger o the health and safety of the public or station per-l l6.9.1.8.h.
l@                    j l
O 7;sonnel. These restraints do not affect normal operation.(NP-32-79-14) lro a CO*.'P.VALVE S Y S T Gt CAUSE CAUSE CCLE CODE SU8 CODE CO'*PONENT CODE SU't CO D E SUSCODE R l T l@ l X @ lZl@
1 8 9   l0 lHLICENSEE lD lBCODE      lS l1 14@lh 0l 0                                                              h      26
l C l B j@ l Bl@ l Al@ l S j U j P O o 9 7 8 9 10 11 12 IJ 14 19 N REVISION_OCCUH A E".CE REPORT SEOJENTI AL gp pg EVENTTEAR REPOR T N1 CODE TYPE P , O ,a(yeq 1719!l-1 1113101 1/l 10131 Ll I---I I 28:: 23 24 26 21 28 D 3u 31 32 B l1 l3 ld1 E AKE A Y CNPLA T*E T HOURS 22 SL3 IT F R*ti P LI E MA FA!F glMZl@]@l Zl@l0 l0 10 l l{@]g dg 33 n 30 3/40 41 42 43 44 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h They werellThe cause of the occurrence was an architectural design error by Bechtel.
                                                                                                                                                                                                                !
i o discovered by TECo personnel while performing RCS hot leg RTD modification work.
CON'T
Undet ,[ Facility Change Request 79-441, Supplement 1, pipe wr.ip restraints R1 and R4 were ljij7j R3 had the shim completely removed.
:o          i              7. "y l L l@l 0 l 5 l 0 l- [ 0 l 3 l M4 l 636 l@l                                         1 l 2 l 2 l 7 l 7 l 9htpOa1 EVENT 0 ATE            '4       75         l@l      0l1l0l8l8l0 D ATE           80 8                      0)             61             COCK ET NU'.'UE R EVENT DESCRIPTION A ND PROB ABLE CONSECUENCES h
jl modified by removing shin packs from the shins.
:o        2 lOn December 21, 1979, it was discovered that there was insufficient clearance between j o      3
, 3 29, 1979.ll The work was completed by 1600 hours on December 80 i 4 7 8 9 DISCOVERY DESCRIPTION
[the Reactor Coolant System (RCS) hot leg and some of the shims of the pipe whip res-j to          -
* POWER OTHER ST ATUS DISCO RlSTA Sl1 l5 l W@ l dl 0l 0lhl NA llBl@ldurinnFCRimplementation
ltraints. On December 27, 1979, it was determined that this was in conflict with an that there be no contact betweentheRCy io          s        lassumption of the RCS piping seismic analysis, This became immediately reportable under T.S. j 0       6 l hot leg piping and the whip restraints.
."'"" ACTIVITY
There was no danger o the health and safety of the public or station per-l O          7      l6.9.1.8.h.
'CO TENT LOCATION OF RELE ASE RELEASED OF RELE ASE A*.tOUNT OF ACTIVITY llzl @ lz l@ l NA ll NA i 6 80 44 45 7 8 9 10 11 PERSOV.EL FXPOSURES lli l 71 101 O UM>l Z l@ DESCRIPTION NU'.'a E R TYPE NA'" ''ES OESCm riON@
(NP-32-79-14)                                        l ro a ;sonnel. These restraints do not affect normal operation.
@ 0) I?U U h % ,lPERSO* NEL INJuF e suussa.li ia l 10 O l o l@l NA i 80 d.WGylnj 7 8 9 11 12 (lh b LOSS OF OH DA"%E TO FACILtTV lTYPE DE SC HIP TION
CO*.'P.         VALVE S Y S T Gt         CAUSE         CAUSE                                                   SU't CO D E      SUSCODE CCLE               CODE         SU8 CODE               CO'*PONENT CODE o        9                            l C l B j@ l Bl@ l Al@ l S j U j P                                       O     R l T l@ l X @ NlZl@
[Z_j@lNA 80 1 9 7 8 9' 10 NRC USE ONLY lllllll1llll%2 ocsCmPfiONO 80011 OlPU R L ICIT Y issVEo LN_jhl NA US 63 t10 L 2 o 743 k 7 8 9 fU-9-v w.TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFOR'4ATION FOR LER NP-32-79-14 DATE OF EVE:IT: December 27, 1979 FACILITY: Davis-Bcase Unit 1
14          19 10         11             12           IJ                                                                           REVISION 9
, IDENTIFICATION OF OCCURRENCE: A conflict between an assumption in the Reactor Coolant System (RCS) piping seismic analysis and some pipe whip restraints Conditions Prior to Occurrence: On December 21, 1979, while performing modifica-tion work on the RCS hotleg, it was discovered there was no clearcnce between the On December 27, 1979, hot leg and some of the shims of the pipe whip restraints.
_
it was determined that this was in conflict-with the RCS piping seismic analysis assumptions,that there would be no contact between the hot leg piping and the pipe whip restrainta during a seicnic event. This became tenediately reportable under Technical Specification 6.9.1.8.h as a condition which conflicts with an assump-tion of an accident analysis.
7                8                                                                                                      OCCUH A E".CE         REPORT SEOJENTI AL                                                 TYPE                            P ,
Being in cold shutdown (Mode 5), the unit remained down until corrections were made.
REPOR T N1                             CODE gp pg      EVENTTEAR 1113101               1/l             10131                     Ll         I---I           I O ,a(yeq              1719!                  l-1 23             24           26       21             28       D           3u             31             32 28          ::
F  R*                P LI E              MA      FA    E CNPLA T                                   HOURS 22           SL3 IT                     ti AKE      A Y                                    *E T l0 l0 10 l                 {@               ]g               dg                   B l1 l3 ld1
                          !F 33 glMZl@                      ]@
n l30Zl@          3/                   40 l
41               42               43                 44                 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h                                                                                                             They were              l i        o      lThe cause of the occurrence was an architectural design error by Bechtel.
Undet
                  ,
discovered by TECo personnel while performing RCS hot leg RTD modification work.
l jij7j              [ Facility Change Request 79-441, Supplement 1, pipe wr.ip restraints R1 and R4 were R3 had the shim completely removed.                                         j
          ,      3      l modified by removing shin packs from the shins.
29, 1979.                                                                 l i 4            l The work was completed by 1600 hours on December                                                                                                                         80 7             8 9 DISCO    R                              DISCOVERY DESCRIPTION
                                              *. POWER                       OTHER ST ATUS STA S                                                                                                                                                                          l l    lBl@ldurinnFCRimplementation l1 l5 l W@ l dl 0l 0lhl
      '
                                                              '
NA
                                                                    "                             "
                      " ACTIVITY       CO TENT                                                                                                 LOCATION OF RELE ASE RELEASED OF RELE ASE                         A*.tOUNT OF ACTIVITY                                                                                                                 l l         l NA 7
i 6 8   9 lzl @ lz l@ l NA10            11 44          45 80 PERSOV.EL FXPOSURES NU'.'a E R            TYPE                                                                                                                                                l li l 71               101 O UM>l Z l@NADESCRIPTION
      '               " '                                                                                                         '
PERSO* NEL INJuF ES suussa                OESCm     e riON@                                                                 @ 0) I?U U h % ,                                               l
.
li ia l 10 O l o l@l NA                                                                                                     d.WGy                      lnj b
i               80 7             8 9                 11       12                                                                                                     (lh LOSS OF OH DA"%E TO FACILtTV TYPE        DE SC HIP TION                                                                                                                                                     l 1 9            [Z_j@l            NA                                                                                                                                                        80 7             8 9         ' 10                                                                                                                                     NRC USE ONLY 2 o issVEo PU R L ICIT Y LN_jhl NA ocsCmPfiONO                                                                    80011 O                              l US 63 lllllll1llll%2                t10 L 7             8 9             fU-                                                                                                                           9   -                 v   743 k
 
w
.
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFOR'4ATION FOR LER NP-32-79-14 DATE OF EVE:IT: December 27, 1979 FACILITY: Davis-Bcase Unit 1                                                         ,
IDENTIFICATION OF OCCURRENCE: A conflict between an assumption in the Reactor Coolant System (RCS) piping seismic analysis and some pipe whip restraints Conditions Prior to Occurrence: On December 21, 1979, while performing modifica-tion work on the RCS hotleg, it was discovered there was no clearcnce between the hot leg and some of the shims of the pipe whip restraints. On December 27, 1979, it was determined that this was in conflict-with the RCS piping seismic analysis assumptions,that there would be no contact between the hot leg piping and the pipe whip restrainta during a seicnic event. This became tenediately reportable under Technical Specification 6.9.1.8.h as a condition which conflicts with an assump-tion of an accident analysis. Being in cold shutdown (Mode 5), the unit remained down until corrections were made.
Designation of Apparent Cause of Occurrence: The cause of the occurrence was an architectural design error by Bachtel. These errors were discovered while perform-ing RCS hot leg resistance temperature detector (RT3) modification work. .These original design errors were random and not due to any general deficiency in the original design method.
Designation of Apparent Cause of Occurrence: The cause of the occurrence was an architectural design error by Bachtel. These errors were discovered while perform-ing RCS hot leg resistance temperature detector (RT3) modification work. .These original design errors were random and not due to any general deficiency in the original design method.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. These whip restraints are not required for normal system performance.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. These whip restraints are not required for normal system performance.
Corrective Action: Under Facility Change Request 79-441, Supplement 1, pipe whip R3 was restraints R1 and R4 were modified by removing shim packs from the shims.
Corrective Action: Under Facility Change Request 79-441, Supplement 1, pipe whip restraints R1 and R4 were modified by removing shim packs from the shims. R3 was modified by removing the shim completely. All affected whip restraint modifications were completed by 1600 hours on December 29, 1979, prior to returning the unit to operation.
modified by removing the shim completely. All affected whip restraint modifications were completed by 1600 hours on December 29, 1979, prior to returning the unit to operation.
Failure Data: There were no previously reported conflicts between the pipe whip restraints and the assumptions of the seismic analysis.
Failure Data: There were no previously reported conflicts between the pipe whip restraints and the assumptions of the seismic analysis.
LER #79-130 1738 027.}}
LER #79-130 1738 027
            .}}

Revision as of 13:03, 19 October 2019

LER 79-130/03L-0:on 791227,insufficient Clearance Discovered Between RCS Hot Leg & Pipe Whip Restraint Shims.Caused by Bechtel Design Error.Pipe Whip Restraints Modified
ML19211C728
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/08/1980
From:
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19211C727 List:
References
LER-79-130-03L, LER-79-130-3L, NUDOCS 8001140320
Download: ML19211C728 (2)


Text

l

,

U. S. NUCLE AR HEGUL ATORY CO*.1 MISSION

~J RC FCRMS'u6

7 7D LICENSEE EVENT REPORT conTnOL stOcx: l l l l l l (PLE AS'i PRINT OR TYPE alt HEQUmED INF ORMATIONI o -] 0lLICENSE 0l NJNLWEH Pl Fl -l 0] 3l@l4 l1 l1IN PE1l@l l1LICENSE JO l

Si LAI $$

l@ j l

1 8 9 l0 lHLICENSEE lD lBCODE lS l1 14@lh 0l 0 h 26

!

CON'T

o i 7. "y l L l@l 0 l 5 l 0 l- [ 0 l 3 l M4 l 636 l@l 1 l 2 l 2 l 7 l 7 l 9htpOa1 EVENT 0 ATE '4 75 l@l 0l1l0l8l8l0 D ATE 80 8 0) 61 COCK ET NU'.'UE R EVENT DESCRIPTION A ND PROB ABLE CONSECUENCES h
o 2 lOn December 21, 1979, it was discovered that there was insufficient clearance between j o 3

[the Reactor Coolant System (RCS) hot leg and some of the shims of the pipe whip res-j to -

ltraints. On December 27, 1979, it was determined that this was in conflict with an that there be no contact betweentheRCy io s lassumption of the RCS piping seismic analysis, This became immediately reportable under T.S. j 0 6 l hot leg piping and the whip restraints.

There was no danger o the health and safety of the public or station per-l O 7 l6.9.1.8.h.

(NP-32-79-14) l ro a ;sonnel. These restraints do not affect normal operation.

CO*.'P. VALVE S Y S T Gt CAUSE CAUSE SU't CO D E SUSCODE CCLE CODE SU8 CODE CO'*PONENT CODE o 9 l C l B j@ l Bl@ l Al@ l S j U j P O R l T l@ l X @ NlZl@

14 19 10 11 12 IJ REVISION 9

_

7 8 OCCUH A E".CE REPORT SEOJENTI AL TYPE P ,

REPOR T N1 CODE gp pg EVENTTEAR 1113101 1/l 10131 Ll I---I I O ,a(yeq 1719! l-1 23 24 26 21 28 D 3u 31 32 28  ::

F R* P LI E MA FA E CNPLA T HOURS 22 SL3 IT ti AKE A Y *E T l0 l0 10 l {@ ]g dg B l1 l3 ld1

!F 33 glMZl@ ]@

n l30Zl@ 3/ 40 l

41 42 43 44 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h They were l i o lThe cause of the occurrence was an architectural design error by Bechtel.

Undet

,

discovered by TECo personnel while performing RCS hot leg RTD modification work.

l jij7j [ Facility Change Request 79-441, Supplement 1, pipe wr.ip restraints R1 and R4 were R3 had the shim completely removed. j

, 3 l modified by removing shin packs from the shins.

29, 1979. l i 4 l The work was completed by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on December 80 7 8 9 DISCO R DISCOVERY DESCRIPTION

  • . POWER OTHER ST ATUS STA S l l lBl@ldurinnFCRimplementation l1 l5 l W@ l dl 0l 0lhl

'

'

NA

" "

" ACTIVITY CO TENT LOCATION OF RELE ASE RELEASED OF RELE ASE A*.tOUNT OF ACTIVITY l l l NA 7

i 6 8 9 lzl @ lz l@ l NA10 11 44 45 80 PERSOV.EL FXPOSURES NU'.'a E R TYPE l li l 71 101 O UM>l Z l@NADESCRIPTION

' " ' '

PERSO* NEL INJuF ES suussa OESCm e riON@ @ 0) I?U U h % , l

.

li ia l 10 O l o l@l NA d.WGy lnj b

i 80 7 8 9 11 12 (lh LOSS OF OH DA"%E TO FACILtTV TYPE DE SC HIP TION l 1 9 [Z_j@l NA 80 7 8 9 ' 10 NRC USE ONLY 2 o issVEo PU R L ICIT Y LN_jhl NA ocsCmPfiONO 80011 O l US 63 lllllll1llll%2 t10 L 7 8 9 fU- 9 - v 743 k

w

.

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFOR'4ATION FOR LER NP-32-79-14 DATE OF EVE:IT: December 27, 1979 FACILITY: Davis-Bcase Unit 1 ,

IDENTIFICATION OF OCCURRENCE: A conflict between an assumption in the Reactor Coolant System (RCS) piping seismic analysis and some pipe whip restraints Conditions Prior to Occurrence: On December 21, 1979, while performing modifica-tion work on the RCS hotleg, it was discovered there was no clearcnce between the hot leg and some of the shims of the pipe whip restraints. On December 27, 1979, it was determined that this was in conflict-with the RCS piping seismic analysis assumptions,that there would be no contact between the hot leg piping and the pipe whip restrainta during a seicnic event. This became tenediately reportable under Technical Specification 6.9.1.8.h as a condition which conflicts with an assump-tion of an accident analysis. Being in cold shutdown (Mode 5), the unit remained down until corrections were made.

Designation of Apparent Cause of Occurrence: The cause of the occurrence was an architectural design error by Bachtel. These errors were discovered while perform-ing RCS hot leg resistance temperature detector (RT3) modification work. .These original design errors were random and not due to any general deficiency in the original design method.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. These whip restraints are not required for normal system performance.

Corrective Action: Under Facility Change Request 79-441, Supplement 1, pipe whip restraints R1 and R4 were modified by removing shim packs from the shims. R3 was modified by removing the shim completely. All affected whip restraint modifications were completed by 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on December 29, 1979, prior to returning the unit to operation.

Failure Data: There were no previously reported conflicts between the pipe whip restraints and the assumptions of the seismic analysis.

LER #79-130 1738 027

.