BSEP-80-1844, RO 80-83:on 801017,during Routine Insp,Craked Weld Found on HPCI Discharge Line Piping Support.Caused by Lack of Fusion at Weld Point.Support Repaired & Reinforced.Facsimile LER Encl

From kanterella
(Redirected from BSEP-80-1844)
Jump to navigation Jump to search
RO 80-83:on 801017,during Routine Insp,Craked Weld Found on HPCI Discharge Line Piping Support.Caused by Lack of Fusion at Weld Point.Support Repaired & Reinforced.Facsimile LER Encl
ML19339C600
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/11/1980
From: Tollison A
CAROLINA POWER & LIGHT CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEB-80-1844, BSEP-80-1844, RO-80-83, NUDOCS 8011180661
Download: ML19339C600 (3)


Text

.

Tcice:picd 11-11-80 Carolina Power & Light Company cn a ---_

m Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 November 11, 1980 s

FILE: B09-13516 SERIAL: BSEP/80-1844 Mr. James P. O'Reilly, Director U. S. Nuclear Ecgulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS.1 & 2 LICENSE NO. DPR-71 and DPR-62 DOCKET No. 50-325 and 50-324 Confir ation Facsimile for an Im=ediatelv Resortable Event (2-80-83)

Dear Mr. O'Reilly:

This facsimile confirms the conversation between Mr. E. A. Bishop, Project Engineer, and Mr. Austin Hardin of your office at 1600 on November 10, 1980.

During a normal routine inspection on October 17, 1980, a piping support on the Unit No. 2 HPCI discharge line outside the drywell was found to have a cracked weld. This support was evaluated by Plant Engineering on October 17 as not affecting the operability of the system due to the small loading in-volved. United Engineers and Constructors (UE&C) were instructed to perform an analysis of this support failure to verify system operability.

On November 10, 1980, UE&C reported that the failed support would, in fact, make the HPCI System inoperable due to revised loading calculations during a design basis seismic event.

Initial evaluations of the failed support indicates that the failure was a result of a lack of fusion at the weld point. The support was repaired and strengthened on October 17, 1980.

The same support on Unit No. I was inspected and found to be satisfactory.

Very truly yours, A. C. Tolliso, Jr., General Manager Brunswick Steam Electric Plant rf RMP/mcg 9

g cc:

Mr. R. A. Hartfield Mr. V. Stello, Jr.

80111goGG(

,.s-

NRCf ORM 346 U.S. NUCLEAR RE!ULATORY COMMISSION 17 77)

LICENSEE EVENT REPORT e@

CONTROL sLOCx: 1 I

I I

I I

l

,PLEAsE PRINT OR TYPE ALL REQUIRED INFORMATION) i io@l i

I I

I I

I I

I I

I l@l i

I I

I I@l l

I@

fo T 1 I I

I I

I I

l iS LICENSE NUMBER 25 26 LICENSE TYPE JQ 57 CAT 58 7

d 3 LICENSEE COGE CON'T IoIil A',"CI I

@l Olf 10101013 ISII@l flol i 1011 17@l81 Of II Ill I \\ l@

I 8

60 61 DOCKET P.VV8E R 66 6'4 EVENT DATE 74 75 RE' ORT CATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lo 121 l l

lo lal i N (Y l

101411 I

lo isi i l

10161I l

10171 I i

10181I l

7 4 3 80 C CE CCCE SLBC E COM80NENT CODE

$L8 COQ'E S

CE 10191 I

I lO L_J@ L_l@ l I

I I

I I

l@ l l@ U @

f 3

1) 11 12

??

18 13

.O SEQUENTI AL OCCURRENCE REPORT REV tS:ON tga og EVENTVEAR REP TNO CCCE TYPE NO.

@ sy. car li l Cl I-l 10$O l31 1/l i

I I

l l

l-l l

l a

g 22 23 24 46 27 28 29 30 01 32

,,,, 2 8 T K N A ON PLANT ET MOURS S8 IT FOR US.

SUPPLIE MANLFACTURER

~l l@l l@

l l@

l l@

I I

I I

I I

l@

l l@

l l@

l l

l l

l@

JJ J4 35 36 3 '.

40 41 42 4J 44 47 CALSE DESCRIPTION AND CORRECTIVE ACTIONS l i 101 l 1

LLLLII I

li121 I I

U_L,J l I

it iAi I l

7 8 9 80 ST S

% POWER OTHER STATUS DISCO RY DISCOVERY 0ESCRIPTION li Ie l I l@ l I

I l@l l

I l@l i

ACTIVITY CO TENT AuOuNTOr ACTivery @ l LOCATION OF RELEASE @

REtEASEo OFRELEASE lilel U @ U @l l

l PERSONNEL ExPOSuAES ceSCRiPriON @

TYPE @l Nuv8ER ITTTll I

I l@l l

PERSO,uELiN;u%eS NUMBER DESCRIPTION l

I l

l@l 1

8 9 ii 12 l

i a 80 LOSS OF OR OAMAGE TO FACILITY TYPE DESCRIPTION LLLJ l l@l I

7 8 9 10 80 ISSUE @DE CRIPTION U

l l

llll8ll1lllIl{

2 o F

8 9 10 68 69 80 3 NAME OF PREPARER PHONE:

NRC gORM 366 U. S. NL,CLEA'l REEULAT!C.Y COMMtSSION (7 77)

LICENSEE EVENT REPORT CONTROL BLOCK: l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) i e

ITI l l I

I I

I I

l@l i

I I

I I

I I

I I

I l@l iI I

I l@l i

I@

7 8 9 LICENSEE CODE 14 15 LICENSE NVY8ER 25 26 LICENSE TYPE J0

$ 7 G A T 56 CON'T 101ii

"= l Gl oiII oi oici3p 14 l@i gioi ? lo i i 17@ifio il it i t i 11@

i d

tw 61 DOCKET NUMBER od 63 EVENT DATE 14 75 REPORT CATE 33 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10 121 l i

10131 1

$86 LM i

10141 l I

lo isi l i

10161 l l

101711 1

10141l l

do 7

8 9 C DE CODE SL8C E COMPCNENT CCCE SLBC O'E St E

10i91 I

I l@ LJ@ l l@ l I

I i

i i

l@ l l@ U@

y i

9 10 ft 12

'2

+4 13 2u SfQUENTIAL OLCLHRENCE REPORT 4EDSiCN uga nO EVENTy aR mE80RT NO COCr TYPE N O.

@ fjlS;ar I 5(I l-l i Ollfl El I/I I

I I

l l

l-l l

l

_d 22 23 24 46 27 28 29 JO 31

.1 J T4 EN A TC O P ANT VE HOURS SB IT FOR S

SUPPLI VANUFACTLRER I

l@L_J@

l_J@

l l@

1 I

I I

I L_J@

l l@

l l@

l i

I

!J@

JJ a4 35 36

  • /

40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l1 l0li l

12 li I i i

Ii I 'l i l

i 131 I l

i i i4i i I

7 8 9 80 DISCOVERY DESCRIPTION h

$A 5

% POWER OTHER STATVS Ots O RY ulu LJ@ l I

I l@l I

I l@l I

ACTivlTY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l1l6l l

l l

l 7

d 9 10 11 44 45 80 PERSONNEL EXPOSURES l1 l7ll l

l l

l lhl DESCRIPTION l

NUV8ER TYPE PERSONNELINJU IES NUM8ER DESCRIPTION ii viI i

i i@i i

F d 9 11

>2 80 LOSS 05 OR DAMACE TO FAClllTY h TYPE DESCRIPTION v

Li_LJ LJ@l I

F

$ 9 TO 80 ISSUE DESCRIPTION 12 l a l L_f@l I

llllll111111l}

7 8 3 10 68 69 80 %

NAME OF PRf DARER PHONE: