ML20028E289

Updated LER 82-030/01T-1:on 821214,while Performing B once- Through Steam Generator Tubing Surveillance During Refueling Outage,Eddy Current Testing Revealed 5 Tubes W/Greater than or Equal to 40% through-wall Indications.Cause Undetermined

ML20028E289
Person / Time
Site:	Arkansas Nuclear
Issue date:	01/11/1983
From:	Rogers P ARKANSAS POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20028E287	List: ML20028E286 ML20028E289
References
LER-82-030-01T, LER-82-30-1T, NUDOCS 8301210182
Download: ML20028E289 (2)

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. U.S. NUCLEAR REGULATORY COMMISSION NRC FORM 366-(7-77) EXHIBIT A LICENSEE EVENT REPORT CONTROL BLOCK:

l_l_l_i_l_i_6l1l010101010 1

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[ 4 l 1 l 1 1 1 l 1 14 l l 15 IT l NIO I 12 10 0l 7-~ill8 R l A l FCODE~l15-l- I4 ,, _ ETCERIE IEMBEli 1 - ! O I~O 25 13 25 ETCENSE THE"JO

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9_A_lETCER5E 10 f,.I 8I REPORT l L 16 l0 l 1 l 2 1 1 1 4 l_8,,,) 2 18 10 1111118 7 SOURCE 65 - 61 -l_5_l~0 1 NLMBEli~

DUCEET 0 1 0 l 3 1 58 ~1 1-3 17 6F TvENT UXTE 74 75-l7EFdllT DATE 70 I 319 EVENT DESCRIPTION AND PROBABLY CONSEQUENCES 10 l1l11 10n 12/14/82, while performing the 'B' once through steam generator (OTSG) tubing surveillance during the l lTlIl l refueling outage, eddy current testing revealed 5 tubes with greater than or equal to 40% through wall indi- l

' l cations. These results caused entry into the C-3 Category as defined by T.S. 4.18 since greater than 1% of I 1111l

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l1l11 lthe tubes in the random sample were defective. The tubes are located in an expanded lane region adjacent to lbut not in the Group A-1 (lane region) defined by T.S. 4.18.3:a.3.(1) and outside the Group A-2 defined by l lllTI _

Other occurrences l111l lT.S. 4.18.3.a.3.(2). This occurrence is reportable per T.S. 4.18 and T.S. 6.12.3.1.(c). i 7

11l1l8 9 Iregarding steam generator tube problems were re5orted on LER's82-012, 8U-034,80-026 and 78-005. (cont'd) 80 1

CAUSE CAUSE COMP VAL)E SYSTEM CODE CODE SUBCODE COMP 0blNT CODE SUBCODE SUBCODE 1,C_I C 111 1 E l12 lX iHIT l F 115 l Z 116 ITITl 12 113 T ~~l11XlClHIM I8 1F 25 -

7 ~~8 9 70 IT-REPORT REVISION SEQUENTIAL OCCURRENCE REPORT NO. CODE TYPE NO LER/R0 l' EVENT YEAR 17 REPORT 8l2I l---l l0 l/ t011l lTl l--- 1.1 i NUMBER ll_2[I- ~ 22 2F 24 -l_3_] u !~ 26 27-l 2F ~29 35 - 31-l 2 ATTACHMENT NPRD-4 PRIME COMP. COMPONENT ACTION FUTURE EFFECT SHUTDOWN HOURS SUBMITTED FORM SUB 20PPLIER MANUFACTURER J TAKEN ACTION ON PLANT METHOD lN iN I8i0 1 1 5 i26 i X 118 I Z 119 I Z 120 IZ [0 1 0 l,0_l 0 122 lY l

3T- 3F 35 - 3 F l21 37 40 4I-~l23 42 - [24 4T-(25 4F-l 77 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 l111l lThe mechanism which caused the tube defects has not been determined at the time of this report. Per the l l1l1l l requirements of T.S. 4.18, the scope of the inspection was expanded to determine the boundary of the defects. l l1111 linspections have continued on 'A' OTSG. As of 1/05/83, 40 defective tubes in ' A' OTSG and 21 defective tubes int lllT,_,l l'B' OTSG have been found outside the A-1 Region (lane) and A-2 Region (periphery). As required by T.S. 4.18.6, I I

illTl la report containing more detailed information will be submithd within 45 days of inspection completion.

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80 l 7 8 9 FACILITY METHOD OF

% POWFR OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION STATUS r

lT i NA 130 iB Routine Surveillance 132 11128 l0 45-l31 46 l 80 7~~I T8I 9 15 1 0 l~01212913 44 ACTIVITY CONTENT AMOUNT OF ACTIVITY LOCATION OF RELEASE RELEASED OF RELEASE 135 i NA 136

, 7 111118 l 9_Z,,,133 l Z l34 l 16 - 11 NA 44 45 80 PERSONNEL EXPOSURES l DESCRIPTION NUMBER TYPE 139 I T__l T l i_0,_l 0_I O 137 l Z l38 l NA 80 7 8 9 Il 12 - 13 PFRSONNEL INJURIES NUMBER DESCRIPTION 141 ITITI l 0 1 0 1 0 140 l NA 60 7~ ~~8 9'~~ ~ 11 I~a I LOSS OF OR DAMAGL TO FACILITY TYPE DESCRIPTION I43 11111 !J,,.142l NA PUBLICITY NRC USE ONLY ISSUED DESCRITTION t 111118 l NA 145 l_i_l_i_i_l_l_i_i_l_l_l 50 1 68 69 l 7 9_N_l44 10 l NAML OF PREPARER Pa' rick Rocers PHONE: (501) 964-3100 l

8301210182 830111 PDR ADOCK 05000313 S . - .-_

PDR . - .

• l NRC FORM 366 . U.S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT EXHIBIT A LER No. 50-313/82-030/01T-3 Occurrence Date: 12/14/82 Evsnt Description and Probable Consequences (continued)

On 12/29/82, upon discovery of C-3 category in ' A' OTSG, a prompt notification was made. The facsimile stated that follow up information would be contained fr. LER-82-032. Since the 'A' OTSG findings are likely related to 'B' OTSG, the information is contained in this update versus a new LER.

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