05000250/LER-1980-025-01, /01T-0:on 801203,AE Advised That Insp Per IE Bulletin 79-14 Revealed Potential Deficiency in Support of Accumulator Nozzles 3A & 3B During Seismic Event.Caused by Max Stress Exceeding Acceptance Criteria

/01T-0:on 801203,AE Advised That Insp Per IE Bulletin 79-14 Revealed Potential Deficiency in Support of Accumulator Nozzles 3A & 3B During Seismic Event.Caused by Max Stress Exceeding Acceptance Criteria

ML17340A591
Person / Time
Site:	Turkey Point
Issue date:	12/15/1980
From:	Pace P FLORIDA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML17340A590	List: 05000250/LER-1980-025, Forwards LER 80-025/01T-0 05000250/LER-1980-025-01, /01T-0:on 801203,AE Advised That Insp Per IE Bulletin 79-14 Revealed Potential Deficiency in Support of Accumulator Nozzles 3A & 3B During Seismic Event.Caused by Max Stress Exceeding Acceptance Criteria
References
IEB-79-14, LER-80-025-01T-01, LER-80-25-1T-1, NUDOCS 8101130334
Download: ML17340A591 (4)

LER-1980-025, /01T-0:on 801203,AE Advised That Insp Per IE Bulletin 79-14 Revealed Potential Deficiency in Support of Accumulator Nozzles 3A & 3B During Seismic Event.Caused by Max Stress Exceeding Acceptance Criteria

Event date:
Report date:
2501980025R01 - NRC Website

text

NRC POR4VI 388 (7-771 LlCENSEE EVENT REPORT U. S. iNUCLEAR REGULATORY COMMISSION 1

I 1

I Qi 4

tPLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

[oar)

I I

I 31 CAT 33 Q

EVENT OATS

~Q I

I I-Ql Q~Q 3

9 UCENSEE COOE UCSiNSE IIVMSEA ZS 9

LiCSNSS TYPE 30 CCN'T 0

I soUAcs IX JQE 0 5 0

0 0

o Q a

do dl OQCXSTNUMSEA da ca 14 1$

ANPQAT OATS 30 EVENT DESCRIPTION AND PRO8AELE CONSEQUENCES QIO

~o 2

Notification was received that the ins ection evaluation in ro ress in

~o 3

accordance with USNRC Z&E Bulletin had revealed a deficienc involvin

~o

~

su rt. of the 3A and 3B accumulator nozzles.

This condition would

~o 9

tentially exist when safe shutdown earthquake loads are superimposed on other design basis loads.

~ ~Oa 7

S 9

~09

,a SYSTEM

CAUSE

CAUSE COMP.

VALVE COOS CQOE SVSCCOE COMPONENT COOS svacooa svacQcE 0'JQ NQo~Q rcc crc 9

!0 I I l2 IZ

~

la 19

~

20 SEQUENTIAL QCCVAFci'4CE ASPQAT AcVISIQN LNAIAO EVENT YEAR REPORT NO, COOS TYPE AIO.

.Q RVEM~SAA Lg l~ ~ ~~~, ~m

. Q}J~

~T

~

~0

'2 I ZZ '2 24 ZS 21 23 29 0

Zl 22 ACTION FVTUAE EFFEC.

SHUTCOWN Al,ACHMENT NPAOA PRVSN COMP CQVPQNcNT TAXEN ACTION QN I'LANT METHCO HQVAS Q22 SUSMITTEO FQRAI>US.

SVPPUEA MANUFACTURER rNQLJQ roo 04Q ~

crQ crQ uc ~(

ZS Zd 37 4l 42 44 47 CAUSc DESCRIPTION ANO CORRECTIVE ACTIONS Q27 o

Evaluation revealed that the calculated maximum stress exceeded the acce tance criteria (established for this review) on the above i in 7

A plant change/modification was implemented'o support the piping before the unit was returned to service followin an unrelated maintenance outa e.

4 1

3 9

PACILITY STATUS 9 POWER OTHER STATVS QSO 9

28 01.0 0,

29 NA PQ LJQ~Q~

ACTIVITY CONTENT RELPEASEO QF RELEASE AMOUNTOFACTIVITYQZS 8

~Z Q22

~ZQ2.

NA 1

I0'l 44 PERSONNEL EXPOSURES AIUMSEP.

TYPE O'ESCAIPTIQN Q29 [iir]~00 0 re> ~ZQs NA 1

3 I I IZ PERSONNEL liVZIONES NVA<SEA QESCAIPTICNQ4I [ii~] ~00 O

Q44r NA METHOO CF QISCOVEAY

- QS

~C QSI X&E Bulletin 79-14 Znspect2.on 45 LOCATIONQF RELEASE Q NA 4

SO 30 30 1

3 NAME OF PREPARER P.L.

Pace II 12 LOSS QF QA QAMAQc TQ FACILITYQ43 TYPE OESCAIPTICN

~Q42 7

I0 PVSLICI.Y lSSVEC 5ESCAIPT,'QN ~49

~IQ44 IO 3J NRC USc ONLY da 30 PHCNEI 30~

552 380 1 87 0 1 13 06Erg

c~

REPORTABLE OCCURRENCE 250-8 5

LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion and Probable Conse ences:

On Wednesday, December 3, 1980, notification was received from our Architect-Engineer that inspections and reanalyses in progress in accordance with USNRC IGE Bulletin 79-14 had revealed a potential problem involving inadequate support of the 3A and 3B accumulator nozzles.

This analysis was performed on an expedited basis as a

consequence of discovering a similar deficiency associated'ith the equivalent piping supports on Unit No. 4.

(Reference LER 251-80-14.)

Specifically, the results

'ndicated that 'the ca3,culated

'maximum stress associated'i;th the piping exceeded the acceptance criteria established for this review.

USNRC IaE Region II was notified of the above information both verbally and by facsimil'e transmission.

Similar occurrences (relating to the inspections pursuant to USNRC IGE Bulletin 79-14) were reported as LER 250-79-26, LER 250-79-40, LER 250-80-08,'ER 250-80-14, and LER 251-80-14.

'Additi'onal Cause Descri tion and Corrective Actions:

The evaluation, confirmed that an overstress condition could potentially exist.

Based on these results, a plant change/modification was expeditiously designed and installed to correct the deficiency. prior to heatup from an unrelated outage.

A full accounting of inspection results and reparis will be made in response to USNRC ISE Bulletin 79-14.

0 J