05000334/LER-1980-017-01, /01T-0:on 800326,reanalysis of Seismic Pipe Stress of Main Steam Piping Inside Valve House for OBE long-term Criteria Showed,For Some Conditions,Allowable Stress Level May Be Exceeded in Headers for Main Steam Relief Valves

From kanterella
(Redirected from ML19305D794)
Jump to navigation Jump to search
/01T-0:on 800326,reanalysis of Seismic Pipe Stress of Main Steam Piping Inside Valve House for OBE long-term Criteria Showed,For Some Conditions,Allowable Stress Level May Be Exceeded in Headers for Main Steam Relief Valves
ML19305D794
Person / Time
Site: Beaver Valley
Issue date: 04/08/1980
From: Werling J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19305D782 List:
References
LER-80-017-01T, LER-80-17-1T, NUDOCS 8004150529
Download: ML19305D794 (2)


LER-1980-017, /01T-0:on 800326,reanalysis of Seismic Pipe Stress of Main Steam Piping Inside Valve House for OBE long-term Criteria Showed,For Some Conditions,Allowable Stress Level May Be Exceeded in Headers for Main Steam Relief Valves
Event date:
Report date:
3341980017R01 - NRC Website

text

__

nV U. S. NUCLEAR REGULATORY COMMISSloN NRC FCO.#. 366 (7 77) 1.tcENSEE EVENT REPORT CONTROL stocx: l l

l l

l l

l@

iPtEAsE PRINT OR TYPE ALL REQUIRED INFORMATION) lo j i j l P l A l 3 l V l S l 1 l@l 0 l0 l-l 0 l 0 l 0 l 0 l 0 l-l0 l 0 l@l4 l1 l1 l1 11 l@lsiwse@

l l

8 9 uCEssEE CooE i4

s uCE%st wveER

.s uCEssE rveE 20 cOwT l L ]@l 0 l 510 l 010 l 3 l 3 l 4 l@l 01312 l 6l 810l@l 0l 4l 01 81810 l@

10ISI s uRC I

8 60 el QOCK ET NwYSER 6d 63 EVENT Q ATE 14

's RE* ORT C Art do EVENT CESCRIPTION ANO PROB ABLE CONSEQUENCES h The reanalysis of the seismic pipe stress of the main steam piping inside the l

O I2l l valve house for the OBE long term criteria indicates that for certain load l

gl conditions the code allowable stress level may be exceeded in the headers that l

l o 14 l l 10 I s l I support the main steam safety relief valves. When the safety relief blowdown loads l f5Ts 1 l are combined with the OBE, pressure and dead load stresses, the computer code i

l o 171 l allowabic stress icvel of 1.25h is exceeded in the headers. The reanalysis of the I

!olal I remainder of the main steam piping inside the valve house (continued on attached) l 60 7

8 9 Sv5 TEM

CAUSE

CAUSE COMP.

VA LV E C00E CODE SUSCODE COMPONENT CO DE SUSCCOE SUSCCCE i

I zl zlO LB_]@ l Al@ l zi zi zi zl zl zl@ l zl@ l zi@

i o 9

?

8 9

10 18 52 13 18 19 20 SE QUENTI AL OCCURAENCE REPORT REVISloN I

LER RC EVENTYEAR REPORT NO.

COCE TYPE No.

l i8 l0 l l~1 l 0 l 1l 7l l/l l 0l 1l lTl i~i l0l h,REQE 7 21 22 23 24 26 27 28 23 30 31 32 K N AC C ONP NT VE HOUR $

$8 i POR t h 8.

5 P* LIE V ANUP ACTURER

.l F l@l F l@

W@

l Z l@

l 0 l 0 l 0 l 01 lYl@

lN l@

lZl@

lZl9l9l9[@

JJ Ja 35 36 31 40 46 42 43 44 4;

CAUSE CESCRIPTION AND CORRECTIVE ACTIONS @

lilo g ] The original calculations of record which qualified the headers were reviewed.and l

gl it was determined that the safety relief blowdown loads had -been considered in a l

l

,,2j l local stress calculation using the PITRUST omputer code but had not been

(

, 3 l considered in the Equation 9 analysis. The FSAR (Response to Question 3.23, I

i 4 l Amendment 1, 4/23/73) indicates that both the PITRUST and tcontinued on attached)

I

~

80 7

8 9

'sT N

  • . POWE R CTMER STATUS 35 0 RY DISCOVERv OESCRIPTION l Xl@ l 0 l 0 l 0 l@l N/A l

lDi@lNotificationfromA/E l

i s Co'0 TENT l

ACTiviTv AA10UNT OP ACTIVITY LOCATION CP RELEASE l

RELEASE @D OP mELEASE l N/A l

l N/A l

l2l 1 6 7

8 9 10 13 44 45 80 PERioNNEL EXPOSURES i

NUUSER

?vPE DESCRIPTICN t

I'iTTi l 01010 l@l z i@l N/A l

'd PEasoNNE L imau'dits otsCRiPTioNh NUveER I T 1 I o l o ! o !@l s/A l

go 7

8 9 18 12 LOSS OP CR OAVAGE TO P ACILtTY TvPE C E SC Rt* TION W @l N/A l

8 9 80 t

7 8 9 10 NRC USE ONLY asscEf@lDESCRsPTION lN N/A l

llllllllll l lq 2,

.0. ;

0
  • N*IliU" 412-643-1258 2

NAME OF PREPARER PHONE:

800.4150520

a Attachment To LER 80-17/01T Beaver Valley Power Station Duquesne Light Company Docket No. 50-334for the OBE case is still in progress. Since the plant is shutdown for refueling and maintenance, there is no potential safety hazard existing.

Cause Description And Corrective ActionsEquation 9 tests must be met, which was not done. The comparison equations are being completed at the present time.

i 4

e I

I