05000334/LER-1978-053-01, /01T-1 on 781026:during Review of Steam Injection Piping Stress Calculations,Error in Original Piping Stress Analysis for One Steam Injection Was Discovered.Caused by Use of Unacceptable Computer Program.Mods to Be Installed: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
 
Line 1: Line 1:
{{Adams
#REDIRECT [[05000334/LER-1978-053-01, /01T-0:on 781026,error Noted in Original Piping Stress Analysis for on Steam Infection Line.Error Caused by Misapplication of Simplified Analysis Technique Employed During Original Design.Corrective Action Implemented]]
| number = ML19248D208
| issue date = 08/01/1979
| title = /01T-1 on 781026:during Review of Steam Injection Piping Stress Calculations,Error in Original Piping Stress Analysis for One Steam Injection Was Discovered.Caused by Use of Unacceptable Computer Program.Mods to Be Installed
| author name = Werling J
| author affiliation = DUQUESNE LIGHT CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
| docket = 05000334
| license number =
| contact person =
| document report number = LER-78-053-01T, LER-78-53-1T, NUDOCS 7908130424
| package number = ML19248D204
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 2
}}
{{LER
| Title = /01T-1 on 781026:during Review of Steam Injection Piping Stress Calculations,Error in Original Piping Stress Analysis for One Steam Injection Was Discovered.Caused by Use of Unacceptable Computer Program.Mods to Be Installed
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000334
| LER year = 1978
| LER number = 53
| LER revision = 1
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:'yjc om >G Update Report - Previous Report Date 12/6/78 U.S NUCLE AR HtGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: l l
l l
l l
l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6 6
lo l i l l P l A l 0 l V l S l 1 l@l 0 l 0 l-l 0 0 l0 l 0 l 0 l-l0 ! 0 l@l4 l1 l1 (1 l1 l@l l
l@
7 8 9 LICENSEE CODE 14 15 LICENSE NUMukH 25 2G LICENSE 1Yrt #J bl CA! 53 CON'T l L @ 0 l 5 l 0 l 0 l 0 l 3 l 3 l 4 l@l l l 0 l 2 l 6 l 7 l 8 l@l0 l 8 lo I 1l7 lo l@
o 0
1 3 n 7
8 60 G1 DOCKET NUvuER 03 09 EVENT DATE 14 7b RE POHT DATE EO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h
[ During a review of SI piping stress calculations an error in the original piping l
!o 2
g 3 l stress analysis for one SI line was discovered.
The line supports were modified.
In l o,, l March,1979, further investigation of the A-E piping stress computer program revealed l g,, ; the program provided pipe stress calculations unacceptable to the NRC for certain seismic events.
The station was shut down on March 9, 1979 for resolution of the g
o i r, o, l pipe stress reanalysis.
[
l O
H 7
8 9 N
SYSTEM CAUSC
 
==CAUSE==
C OY P.
VetLvr CODE CODE SUBCODE COMPONENT CODE SUhCODE SubCODF l S l F lh lB lh Alh l S lU l P l0 lR !T lh l D h Zlh o
9 7
8 9
10 11 12 IJ id 19 2U SE OUE N TI A L OCCUR R E NCE Hfrony R E VISIO N LER EVENT YE AR REPORT NO.
COOC TYPE N O.
@ agg/RC I 71 al I-l 101 s l 3 i I/l 10 l1 l lTI
:- l 111
_ 21 22 23 24 2G 27 2d 29 Ju 31 32 ACTION FtlTUnE EFFECT SHUTDOWN ATT ACHY E N T NPRO 4 PRIVECOMP COYPOP '.T 1AKEN ACliON ON PL ANT METHOD HOURS Suavi rT t o FOHMtUH SUPPLIEH MANUTAC1LAiq 4
lF l@l Zl@
lZ l@
lZ l@
l0l0l0l0 W@
lY l@
l A l@
l Xl 9 l 9 9l@
33 34 L
36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l The incident resulted from the use of an unacceptable computer procram for l
i o
i i
l calculation techniques of seismic loading.
All pipinn systems which unt be i
7 l seismically analyzed will be completed using an acceptable computer prouram.
Anv l
3 3
l modifications to supports which are determined necessary as a result of these j
l analyses will be installed during the fall refueling outace.
I i
4 7
8 9 83 SI 5
% POWE H oTHERSTATUS ISC vFY DISCOVERY DESCHiPTION lGlh l0l0l0l@l N/A l
l D lhl Architect-Engineer Review l
1 5
ACTIVITY CO TENT nEtE ASE D Or nE LE ASE AMOUNT OF ACTIVITY LOCATION OF RELE ASE l 2 l @ l Zl@l N/A l
l N/A l
1 6
7 6 9 10 t
44 45 80 PE RSONNEL EXPOSUMES NUMP.F R TYPE
 
==DESCRIPTION==
Lu2Jlol0101@lZl@l N/A I
7 a 9 11 12 13 SO PCMnNNF t 1NjumES NUYl)[n DESCRIP TION l 0 l 0 l 0 l@l N/A l
1 x
7 8 9 11 12 9
(
SO f
LCSS OF on DAMAGE TO FACILITY TYPE DE SC RIP TION V V 1 L5' 43 1'-
l1 9
N/A l
7 8 9 to 50 esut o@lmCnrfiON O,p, PUBLICITY 7oos1ao 8'Q7(-
pacgg[gyty y
N/A l L{ l l Illlll ltj:;
2 n
7 8 9 10 68 69 30 %
^*
l UE NAME OF PDEPARER PHONE
 
Attachment to LER 78-53/01T-1 Beaver Valley Power Stations Duquesne Light Company Docket No. 50-334 During a review of SI piping stress calculations an error in the original piping stress analysis for one SI line was discovered. One support on the SI line was modified and one snubber was added.
The Duquesne Light Engineering Department continued a review of the architect-engineer findings.
In Fbrch 1979, this continued review of the A-E pipe stress computer program revealed that the program provided pipe stress calculations unacceptable to the NRC for certain seismic ever.ts.
The station was shut down on March 9 for resolution of the pipe stress reanalysis.
All piping systems, which the present regulation require to be seismically analyzed, will be reanalyzed using Nu Pipe-SSI calculational techniques as described in Section 7 of the June 15, 1979 Report.
These NU Pipe-SSI computer analysis will than become the calculations of record for all piping systems which require computer analysis.
All supports for the computer analyzed problems will be evaluated or analyzed to 1'nclude the requirements of IE Eulletin 79-02 relating to baseplate flexibility and factors of safety for the concrete anchors.
Any modifications to the supports which are determined to be necessary as a result of these evaluations and analysis will be installed during the fall refueling outage.
Any modifications determined to be necessary to limit equipment nozzle and containment penetration loads to within Code allowable values will be installed during this same fall refueling shutdown.
All hydraulic snubbers for which the seismic loading exceeds the allowable load but is included within the one event capability of the snubber will be identified.
These snubbers will either be replaced or included in the appropriate technical specification as snubbers which must be tested for operability, subsequent to a seismic event of a magnitude which results in forces greater than the allowable snubber load prior to continuing operation or returning the unit to operation.
All of the above mentioned activities will be completed prior to returning the unit to service after the fall refueling outage.
F/1
'l Jvi
}}
 
{{LER-Nav}}

Latest revision as of 12:44, 26 May 2025

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=05000334/LER-1978-053-01,_/01T-1_on_781026:during_Review_of_Steam_Injection_Piping_Stress_Calculations,Error_in_Original_Piping_Stress_Analysis_for_One_Steam_Injection_Was_Discovered.Caused_by_Use_of_Unacceptable_Computer_Program.Mods_to_Be_Installed&oldid=5508121"