05000280/LER-1980-067-01, /01T-0:on 801028,indications Found on All Three Steam Generators.Caused by Original Const.Weld Areas Will Be Completely Machined Out & Replaced

/01T-0:on 801028,indications Found on All Three Steam Generators.Caused by Original Const.Weld Areas Will Be Completely Machined Out & Replaced

ML18139A816
Person / Time
Site:	Surry
Issue date:	11/10/1980
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A815	List: 05000280/LER-1980-067, Forwards LER 80-067/01T-0 05000280/LER-1980-067-01, /01T-0:on 801028,indications Found on All Three Steam Generators.Caused by Original Const.Weld Areas Will Be Completely Machined Out & Replaced
References
LER-80-067-01T, LER-80-67-1T, NUDOCS 8011140009
Download: ML18139A816 (2)

LER-1980-067, /01T-0:on 801028,indications Found on All Three Steam Generators.Caused by Original Const.Weld Areas Will Be Completely Machined Out & Replaced

Event date:
Report date:
2801980067R01 - NRC Website

text

...

NRC,FORM 366 (7-77)., __..

e e U.S. NUCLEAR REGUI..ATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:... I _..___.i..;.! _I.___.__..___..! G) 1 6

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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Iv IA Is Ip Is 11 101a 7

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LICENSEE CODE 14 15 I a I - 1 a I a I a I a I a 1-I a I o 101 4 I 1 I 1 I 1 I 1 101

• I 10 LICENSE NljMBER 25 26 LICENSE TYPE 30 57 CAT 58

. CON'T

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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75

• EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

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REPORT DATE 80 I Diri ng R. T. examination of Mam Steam ell::ow :weld to Steam Generator nozzle as

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Generators.

Since the Unit is.m a defueleti condition, the health and safety of the public was not affected.

This event is rep::,rtable r:er T. S. 6.6.2.a. (9).

7 8

9 80

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. 8 SYSTEM CODE IC IC I@

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LER/RO LVENTYEAR

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REPORT I 8 I O I NUMBER 21 22 ACTION f'IJTURE TAKEN ACTION EFFECT ON PLANT

CAUSE

CAUSE COMP.

CODE SUBCODE COMPONENT CODE SUBCODE

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11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REPORT NO.

CODE TYPE VALVE SUBCODE

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Io 11 I l!.J i.::=J 23 24 26 27 28 29 30 31 SHUTDOWN Q

ATTACHMENT NPRC:-4 PRiME COMP.

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. SUPPLIER

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REVISION NO.

t.QJ 32 COMPONENT M_ANUFACTURER I G!* 2 I 5 17 IC§:

44 47 I The in:iications were the result of original construction.

The subject weld areas will !

• ITIIJ i be completely machined out and replaced dur.mg the Stearn Generator Replacement.

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9 FACILITY

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STATUS

% POWER OTHER STATUS ~

[2J}] LLJ@ IO IO IO !@I S/G Replace:nent I 8

9 10 12 11 44 ACTIVITY CONTENT Q,.

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~

[2E uJ @) l2..l@._I _N--'-/_A _____

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.9 10 11 44 PERSONNEL EXPOSURES C\\

N/A 80 METHOD OF A

DISCOVERY DISCOVERY DESCRIPTION '23; L£J@.... l _sr:ec_*_i_al_Exarnina

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45 46 80 N/A.*

LOCATION OF RELEASE@.

45 80 NUMBER

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NUMBER DESCRIPTION~

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TYPE

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-~ _O 11 ]J:1~ gFQiPARER J. L. Wilson PHONE*

(80'1) 357-318'1 80 0 0

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e ATTACHMENT 1

- suRRY POWER STATION, UNIT 1 DOCKET NO:

50-280 REPORT NO:

80-067/0lT-0 EVENT DATE:

10-28-80 MAIN STEAi~ PIPING WELD DESCREPANCIES

1.

DESCRIPTION OF EVENT

With the Unit defueled, Radiography examination of the Main. Steam elbow at the Steam Generator outlet nozzle revealed indications in the weld area.

The indications were found on all three Steam Generators.

This examination was being preformed as required by ETA 30006 in preparation for Steam Generator replacement.

The indications are judged to be artifacts of the welding process and not service induced.

This event is reportable per Technical Specification 6.6.2.a. (9).

2.

PROBABLE CONSEQUENCES The integrity of the Main Steam Piping may have been degraded.

Since the Unit is in a defueled condition, the health and safety of the public was not affected.

3.

CAUSE

T'ne indications were the results of original.construction of the.main steam sys,tem.

4.

IMMEDIATE CORRECTIVE ACTIONS

A review of the original construction records was initiated to determine the origin of these indications.

The results of the review revealed that these indications did exist, and were. originally judged to be acceptable.

5.

SUBSEQUENT CORRECTIVE ACTIONS The subject weld areas will be completely machined out and replaced during the Steam Generator Replacement.

6.. ACTION TAKEN TO PREVENT RECURRENCE None

7.

GENERIC IMPLICATIONS An evaluation of the original radiographs of the main steam piping inside the containment is in progress.

Approximately 40% of the original radiographs have been evaluated and no rejectable indications have been identified.

In addition, RT examination of some of the welds will be conducted to confirm the results of the above evaluation.

The evaluation and RT examination will be com-pleted prior to hydrostatic testing of the Steam Generators.

A similar review of original construction radiographs for Unit No. 2 is in progress.

It should be noted that the nozzle to elbow welds for unit No. 2 were replaced during the Steam Generator Outage.