05000346/LER-1979-133-03, /03L-0:on 791219,calculations by Itt Grinnell Revealed Seismic Support Design High Pressure Injection Line Exceeded Slenderness Design Ratio.Caused by Failure to Correctly Evaluate Slenderness Ratio.Mods Completed 791223

From kanterella
(Redirected from ML19257B989)
Jump to navigation Jump to search
/03L-0:on 791219,calculations by Itt Grinnell Revealed Seismic Support Design High Pressure Injection Line Exceeded Slenderness Design Ratio.Caused by Failure to Correctly Evaluate Slenderness Ratio.Mods Completed 791223
ML19257B989
Person / Time
Site: Davis Besse 
Issue date: 01/15/1980
From: Dietrich K
TOLEDO EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19257B983 List:
References
LER-79-133-03L, LER-79-133-3L, NUDOCS 8001220505
Download: ML19257B989 (2)


LER-1979-133, /03L-0:on 791219,calculations by Itt Grinnell Revealed Seismic Support Design High Pressure Injection Line Exceeded Slenderness Design Ratio.Caused by Failure to Correctly Evaluate Slenderness Ratio.Mods Completed 791223
Event date:
Report date:
3461979133R03 - NRC Website

text

U. S. NUCLE AR HLGUL ATORY COMt.11SSION Nf(C F ORM 3GG U7h LICENSEE EVENT HEPORT CONTROL HL OCK: l l

l l

l l

lQ (PLEASE PRINT On TYPE ALL REQUIRED IflFORMATION)

D j Bj_Sj 1 @L0]0 0

0 [N P lF 0 l3 @1b l 1 l 1 1j@l l

l@

lo l t l l 0 H

25

?t, L6CtNJL lire J0 SI L A1 '/

l C 9 LIC-M L t,04 14 15 L IC L * 'l NL."., t. H "C (Aj@l 015 l 0 l-l 0 l 3 l 4 l 6 l@l 1 l 2 l 1 l 9 l 7 l 9 l@l0 l1 l1 l5 l8 l0 l@

CON'r o

i M

td EVENT D All 74 iu HLPCt41 DAT E CJ t0 01 DOC K E T NU'.'3 L R 7

8 EVEfJT DESCRIPTION AND PROB ARLE CON'iFOUENCES h l ITT Grinnell personnel performing calculatioas for IE Bulletin 79-02 discovered that j o

2 1

the design of one seismic support on High Pressure Injection Line 1-1 exceeded the o

a l This deficiency is beim; re-1

[ slenderness design ratio of 200 used hv ITT Grinnell.

o a

operation]

ported under T.S. 6.9.1.8.1 as an item requiring remedial action to prevent o

s l o c l in a rianner less conservative than that assumed in the accident analysis. There was j

[ no danger to the health and safety of the public or station personnel. The support i

o 7

o a l Is not required for normal system operation.

(SP-33-79-154) l 60 7

6 4 C O'.' P.

VALVE SMTEM C AUSE CAU$E CODE COUL SUBCODE CO'/PONLNT CODE SUBCODE SUSCOOL

@ LO @

s ] F l@ LnJ@ Iz l@ l si ul e] O nl Tl8 B

o o

_/

8 9

10 11 12 TJ id 1) 20 HEVISION SEQUE N11 At OCCUR RE f.CE HEPORT trp on EVENT VE AR REPORT NO.

CODE TYPE fio.

O ggi I 71 91 1-1 11 31 31 L-J I DI 3I l'I l-J ol

_ 21 22 U

24

.6 21 2d 2J JJ 31 32 AT T ACH'.'E N T NPRD 4 "R I'/ E C.O*.'P.

CO*.'PON ! N T TAKEN AC TION ON PL ANT f.'l l H O D HOUR 3 SUU '.'i T T L D F Oll'.',UH.

SUDPLitH V ant f r ACTUEF 84 ACTION ru1UnE ffitCT SHu T Lc...N JJ 11 JL J/

40 41 42 43 44 47 CAUSE DESCntP110N AND CORRECTIVE ACTIONS h l The error is not due to a general deficiency in the original design methods used by

[

i o

the slenderness ratio li 11 I l ITT Grinnell but was caused by a failure to correct 1v evaluate i

l,; ; j for the affected support.

Modifications to the seismic support were completed by 0304 li),] l hours on December 23, 1979 under Facility Change Request 79-445.

1 I

i 2

1 80 7

8 9 ME THOD cr ST ANS 2 PO?. E H OTHE R ST A TUS '

DISCovi nY DISCOVE RY DESCHiP TIO'J 3.

F ACillTY Cj@(DuringanalysisforIEBulletin79-02 j [IlT] W@ l 0l 0l 0l@l NA A 11Vl T Y CO 1 E '. T LOC ATION OF FIE t E AS E nr LE A'.t A*/OUNT Of ACTIVITY l

l1 l c l l Z l @O Or l' Elf C.Ey @ l NA l

NA 60 44 45 7

8 9 10 11 PE 5iSC'/.E L i UOwl'E %

l0[0 dj@l ZTY PF @lDF $ChlP flON.

l NU Vf:f a NA i

/

E3 ft E 5 otscn.Piinsh g fr,1 PE nse* ".E t INi h

g%%, @g r

l y %n lil ll010 Oj@l NA W u tl 3JW g Jg da i

eo i

a o n

e io.sor m o.vu-rTarAcioiv..

LLLd I z @ h 17M M9 1NfL

('t tetPli yj i

s 9 o

NRCUM WIY

... (( N H:c a r nh I

l l l l ll l l ll l I I:

I2lol D,if dl NA r.,,

.o w

293{

DVR 79-200 Ken Dietcrich 8 001 e e n 419-259-5000, Ext.

yo,

%.nOrr'm>w,o

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER SP-33-79-154 DATE OF EVENT: Dec ember 19, 1979 FACILITY: Davis-Besse Unit 1 1DENTIFICATION OF OCCURRENCE: Design of seismic support 33-CCB-2-H46 on High Pres-sure Injection (HPI) Line 1-1 did not meet the slenderness ratio that is required The unit was in Mode 5, with Power (MWT) = 0, and Conditions Prior t:o Occurrence:

Load (Gross MWE) = 0.

Description of Occurrence: Uhile performing calculations for IE Bulletin 79-02, ITT Grinnell personnel discovered the design of seismic support 33-CCB-2-H46 on HPI Line 1-1 exceeded the slenderness ratio design criteria of 200 used by ITT Grinnell. Tbc analysis was performed assuming the worst case design basis carth-quake loading, however, the analysis failed to correctly evaluate the slenderness ratio.

This design deficiency was discovered while the unit was in cold shutdown during a unit outage.

This incident is being reported in accordance with Technical Speci-fication 6.9.1.8.1.

Designation of Apnarent Cause of Occurrence: The cause of this occurrence was design errors by ITT Grinnell in the initial calculations of the stresses and deflections in this hanger. This design error was discovered while calculating base plate forces and moments for the analysis required by IE Bulletin 79-02.

The error is not due to a general deficiency in the original design methods used by ITT Grinnell but was caused by a failure to correctly evaluate the slerderness ratio for the af fected support.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. This support is not required for normal systen performance but is required only to protect the system f rom a worst case condition of maximum carthquake loading.

HPI String 1-2 was operable if an earthquake had occurred.

Corrective Action

The existing pieces of angle iron were replaced with 3 x 3 x 1/4" and 2 x 2 x 1/4" structural tubing. The affected hanger modifications were completed by 0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> on December 23, 1979, prior to the unit returning to operation. Work was performed under Facility Change Request 79-445.

Failure Data: There have been two previously reported similar occurrences, see Licensee Event Reports NP-32-79-08 and NP-32-79-13.

LER #79-133 1783 360