ML17252B506

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LER 77-049/01T-0 for Dresden, Unit 2 Re Discovery During Plant Life of Conditions Not Specifically Considered in the Safety Analysis Report or Technical Specifications That Require Corrective Measures to Prevent the Existence of Unsafe Cond
ML17252B506
Person / Time
Site: Dresden Constellation icon.png
Issue date: 10/31/1977
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR 1020-77 LER 77-049/01T-0
Download: ML17252B506 (5)


Text

Commonweal9:dison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 October 31, 1977 BBS LTR #1020-77 James G. Keppler, Regional Director

_Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL* *60137 Reportable Occurrence Report No. 77-049/0lT-O, Doaket No. 050~0237 is hereby submitted to your off ice in accordance with Dresden Nuclear Power Station Technical Specification 6.6.B.l.i., discovery during plant life of conditions not specifically considered in the safety analysis report or technical specifications 'that require corrective measures to prevent the existance or development of an unsafe condition ..

Dresden Power BBS:dlz Enclosure cc: Director of Inspection & Enforcement Director of Management Info_rmation:.!.& Program Control File/NRC

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Nov 3 .1977'*

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-LICENSEE EVENT REPORT e CONTROL BLOCK:

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[iliJ 7 B 9 I I I.LI DI RI s I 2 101 0 LICENSEE CODE 14 15 I 01 ~1 01 01 01 01 0 I -.

LICENSE NUMBER I 0 I 0101 4

. 25. 26 I1 I 1 I I 1

LICENSE TYPE 30 1 101 I 57 CAT 58 10 CON'T . . *~

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7 B 60 61 DOCKET NUMBER 68 69 EVENT DATt 74 75 REPORT DATE BO EVENT DESCRIPTiON AND PROBABLE CONSEQUENCES @ . .

[II.II I During refuel outage while performing inspec~:. ,"_--.of Mark 1 containment internal compo-nents, 14 weld 1ocati~ii~;* at vent header support colµmn to clevis were suspected to havel insufficient weld surface area per Mark 1 short term criteria. After acceptance cri-teria of 5/16" weld over 28" was determined i t was later found that only 7*of 14 met criteria. Safety implications minima+/- because i f a transient or accident occurred dur-1

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7 B 9 BO SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE . suBcobE COMPONENT CODE SUB CODE SUBCODE Is IAI@ L2J@ ~@ I xI XI XJ Xj xi x1@ l2J L3.J@

9 10 11 12 13 1B 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

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\;_,!,) REPORT NUMBER I 7I 71 I I I o I 41 91 I /I Io I l I LU 1=J LQJ 21 22 23 24 26 27 2B 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM !>UB. *SUPPLIER MANUFACTURER

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33 34 35 36 37 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

D:I:2J I Cause due to improper weld installation in its initial application. Weld areas re-paired per WR 119062 satisfied short term program structural criteria thereby satisfying!

long term corrective action.

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7 B 9 BO FACILITY STATUS  % POWER OTHER STATUS METHOD OF DISCOVERY DISCOVERY DESCRIPTION GTIJ L2ij@ I 01 01 01@1_ _ _ _N_A_ __ W@I Observer InsEection 7 B 9 10 12 1'3 44 45 46 BO AC.TIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY ~ LOCATION OF RELEASE @

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BO PERSONNEL EXPOSURES Q NUMBER TYPE DESCRIPTION (;}

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NUMBER DESCRIPTION~

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TYPE . DESCRIPTION v:::J G2J W@ . NA 7 B 9 10 BO PUBLICITY (';';'\ NRC SE ON y ISSUEOQ DESCRIPTION~ ' U L "'

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0 NAME OF.PRERARER-----S_t_e.;,_v_e_n_w......,_H_a....:J;....::i;....:i_s._ . ----- PHONE:----...;.._....::.2,,.6"5_ _ _ __ a.

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ATTACHMENT TO LICENSEE EVENT REPORT 77-049/0lT-0 COMMONWEALTH EDISON COMPANY (CWE)

DRESDEN UNIT 2 (ILDRS-(2)

DOCKET II 050-0237 . .

  • During th.e Unit 2 refueling outage of September, 1977 an inspection was niade of Mark I containment internal components in the Unit 2 totus. The inspe~tion included visual examinati.on .ot: tbe seam .weld for the vent header support column to cl~vis:conhection. Jhe short term program struc-tural acceptance criteria (MKl-02-:-012, Rev. 2. DTD June; 1976) at each of the 32 locations requires that the weld are~be ap~rdximately 7 square inches to maintain a factor of 2.0. to the ultimat:e strength of :the column .

Close examinatic;m reveah~d that 7 of these. column - clevis connections were discrepant and shoul* WH~5:

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To Call:

GE 858-2660x16

~ .: B. B. Stephenson, Superintendent Dresden Nuclear Power Statiori DC 1-301-492-7617 {auto) ** Commonwealth Edison Company i--'

N wri - '8~.5-942-4449/ 4321 .

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V1 Morris, IL

  • 60450 Station Dist:. Originator (copy)  :

Incident File (copy) ; Telephone: 815-94.2-2920/ 292l:x212 *,

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. I RECf::IVEO DOCUMENT F'i;OC[SS!HG UlllT 197 I NOV I I PM I 57

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