ML19211C728: Difference between revisions
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{{#Wiki_filter:l | {{#Wiki_filter:l U. S. NUCLE AR HEGUL ATORY CO*.1 MISSION | ||
U. S. NUCLE AR HEGUL ATORY CO*.1 MISSION | |||
~J RC FCRMS'u6 | ~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 | :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 $$ | Si LAI $$ | ||
l@ j l | l@ j l | ||
1 8 9 l0 lHLICENSEE lD lBCODE lS l1 14@lh 0l 0 h 26 | 1 8 9 l0 lHLICENSEE lD lBCODE lS l1 14@lh 0l 0 h 26 CON'T | ||
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 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 | :o 2 lOn December 21, 1979, it was discovered that there was insufficient clearance between j o 3 | ||
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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@ | 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 | 14 19 10 11 12 IJ REVISION 9 | ||
7 8 OCCUH A E".CE REPORT SEOJENTI AL TYPE P , | 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 :: | 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 :: | ||
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n l30Zl@ 3/ 40 l | 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. | 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 | Undet discovered by TECo personnel while performing RCS hot leg RTD modification work. | ||
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 | 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. | , 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 | 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 | *. POWER OTHER ST ATUS STA S l l lBl@ldurinnFCRimplementation l1 l5 l W@ l dl 0l 0lhl NA | ||
NA | |||
" ACTIVITY CO TENT LOCATION OF RELE ASE RELEASED OF RELE ASE A*.tOUNT OF ACTIVITY l l l NA 7 | " 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 | 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 | ||
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 | 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 | 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 , | ||
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. | 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. |
Latest revision as of 04:47, 2 February 2020
ML19211C728 | |
Person / Time | |
---|---|
Site: | Davis Besse ![]() |
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
" 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
.