ML19339C600

From kanterella
Revision as of 11:05, 31 January 2020 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
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 CONTROL sLOCx: 1 I I I I I l ,PLEAsE PRINT OR TYPE ALL REQUIRED INFORMATION) i e@

fo T 1 I I I I I I l i I I I I I I I I I l@l26 i I I I I@l57 CAT l I@

7 d 3 LICENSEE COGE io@liS LICENSE NUMBER 25 LICENSE TYPE JQ 58 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 f

I 3

I 1) lO L_J@ L_l@ l 11 12  ??

I I I I I l@ l l@ U @

18 13 .O

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

a

@ sy. car g li l Cl

,,,, 2 8 22 I-l 23 10$O l31 24 46 1/l 27 i

28 I

29 I l 30 l l-l l l 01 32 T K N A ON PLANT ET MOURS S8 IT FOR US. SUPPLIE MANLFACTURER

~l JJ l@lJ4 l@ l 35 l@ l 36 l@ I 3 '.

I I I I 40 I

41 l@ l 42 l@ l 4J l@ l 44 l l l 47 l@

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 REtEASEo OFRELEASE LOCATION OF RELEASE @

AuOuNTOr ACTivery l@ l lilel' U

' ' @ U ' @l " '

l PERSONNEL ExPOSuAES Nuv8ER ceSCRiPriON @

ITTTll I I l@lTYPE l @l PERSO,uELiN;u%eS NUMBER DESCRIPTION 1

i a 8 9 l I l ii l@l 12 80 l

LOSS OF OR OAMAGE TO FACILITY TYPE DESCRIPTION LLLJ8 9l l@l10 I 7 80 F

2 o 8 9 U 10 @DE CRIPTION ISSUE l l 68 69 llll8ll1lllIl{

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 i

l l l l l e

lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

ITI l8 l9 I I I I I l@l15 14 i I I I I I LICENSE NVY8ER I I I I 25 l@l26 iI I LICENSE TYPE J0 I l@l$ 7 G iA T 56I@

7 LICENSEE CODE CON'T 101ii "= ltw Gl oiII oi oici3p 14 l@i gioi ? lo i i 17@ifio il it i t i 11@

od 63 EVENT DATE 14 75 REPORT CATE 33 i d 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10 121 l i 10131 1 $86 LM i I

10141 l lo isi l i 10161 l l 101711 1 l

10141l do 7 8 9 C DE CODE SL8C E COMPCNENT CCCE SLBC O'E St E 10i91 y i I

9 I

10 l@ LJ@ l l@ l ft 12 '2 I I i i i l@ l l@ U@

+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 29 l l l-l l l

_d 22 23 24 46 27 28 JO 31 .1 J T4 EN A TC O P ANT VE HOURS SB IT FOR S SUPPLI VANUFACTLRER I

JJ l@L_J@ a4 l_J@

35 l

36 l@ ,

1

  • /

I I I 40 I

L_J@

41 l

42 l@ l 43 l@ l 44 i I !J@

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

$A 5  % POWER OTHER STATVS Ots O RY DISCOVERY DESCRIPTION h 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 NUV8ER TYPE l1 l7ll l l l l lhl DESCRIPTION l 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 F $ 9 LJ@l TO 80 I

DESCRIPTION

  • ISSUE 12 l a l L_f@l I llllll111111l} l 7 8 3 10 68 69 80 %

NAME OF PRf DARER PHONE: I