ML18283B035

LER 1976-010-00 for Browns Ferry Unit 2, Error by Licensed Operator in Pulling out-of-sequence Control Rod During Scram Time Testing

ML18283B035
Person / Time
Site:	Browns Ferry
Issue date:	09/17/1976
From:	Fox H Tennessee Valley Authority
To:	Moseley N NRC/RGN-II
References
LER 1976-010-00
Download: ML18283B035 (8)

Text

NRC FORM 195 U.S. NUCLEAR REGULATORY CO~SION DOCKET NUMBER I2.74) 50>>260 FILE NUMBER NRC DISTRIBUTION FoR PART GO,DOCKET MATERIAL VK INCIDENT REPORT To: Mr. Norman C, Mosley FROM: TVA DATE OF OOCUMLNT Chattanooga, Tenn. 37401 9-17-76 H,ST Fox DATE RECEIVED 9-20-76

%LETTER 0 NOTOR IZE D PROP INPUT FORM NUMBER OF COPIES RECEIVED

%ORIG INAI GIUNC LASS IF IE D 0 COPY 1 CC Ltr trans the following:

DEscRIPTIDN

'n 9-6-76Licensee ENcLosURE Event Report (RO"50-260/76-10 re operator error of out of aecuque c control .rod during'scram time testing,.;.,

(40 cye encl cec'd) ggo)'j~l I II~JIB bo Browns Ferry Unit 2 Plant ~ NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J .COLLINS FOR ACTION/INFORMATION DPA>TCU'lQTViiVe ence ~ ee veee ~ ~

Yl CYS FOR ACTION LIC.. ASST.:

W S ACRS S INTERNAL D IST R I BUTION NRC PDR I Ij'dE 2 MIPC SCHROEDER IPPOLITO HOUSTON NOVAK CHECK GRIMES CASE HITLER ISNAUER TEDESCO MACCARY EISENHUT HAER SHAO c VOLLEYER PUNCIr KREGEH J. COLLINS EXTERNAL DISTRIBUTION CON L NUMBER LPDR:

TIC:

9510 NIIC FORM 104 (2 74I

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TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 IPgnrrl~4~ . n s C4 ny Seyteaber 17~ 1976

~gggtA Mr I(oman C. Moscley, Director ~Q $ 0~~7 U.i, zaa.mr'aegaaso4 ~aston:.(i @",,,ay r jp gfPp Office of Xnayeebion and Enforcement, +~~ "c~~ O Region XX q~

230 Peach4ree Street, W., 8th FLoor Jgp AGlan5xp Qcor@a 30303 C

Dear Mr. Moaelqy; TEtQESSEE VAIZHKAHZOBXZf 3REDS PERE KJCXZAR PLAIT UKET 2-DOCKET MOo 50 260 PACXLITt O~QIZG LICENSE DPR 52 REPORTARK OCCUR&>CE EPOS EE>RO 50 260/76lO The oncloscd report ia to provido de~a concerning an error by a licensed. operator in pulling an out-of-sequence contro1 xod during scam 4'esting. This report ia au)md.tted in accordance

~d,th Srcens Perry Technical. Specifications Section 6. Thd.a event occurred on Brogans Parry Nuclear Plant unit t~ yours~

2'ery TEEKSSEE VAXZZiYAVKORXTX H. S. Pox Director of Po~~er Production Enclosure (3).

CC (Enclosure) i Director (3}

Office of Mmagmant Xnfomation and Program Control U.S. Muclear Re tory Could.ssion LfashinEton~ D. . 20555 OM.ce of Xnspeebion and, Znforcanent U.S. Bcc1ear Re~tory Commission Vaahimgton, D.C. 20555

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7 89 14 15 25 26 30 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE

[COijooN'T E L 0 0 0 2 6 0' 9 0 6 76, 7 0 57 58 59 60 68 69 74 75 ao I

EVENT DESCRIPTION toOI See Attachment (BFRO>>QO-260/7610) t 7 8 9 60 1

7 Os 80 7 8 9 eo IOOI 7 8 9

~08 7 8 9 PRfUIE 80 SYSTEM CAUSE COMPONENT COMPONENT 7

~or ~RB 8 9 10 CDOE CODE A

11 IC R 12 iCOMPONENT CODE D R V E 1.7 SUPPUER 44 6080 MANUFACTURER 47 48 CAUSE OESCRIPi:DN Q~~j See Attachment 89

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7 89 80 Qo I 7 89 FACILITY METHOD OF STATUS>> IL POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

~a ~O.O 1 RA 7 8 9 10 12 13 ,44 45. 80 FORM OF ACTIVITY CO'ITENT RELEASEO OF RELEASC ~

AMOUNT OF ACTIVITY I.OCARON OF RELEASE

~12 X R N A NA 7 8 9 10 11 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Qsj ~oo C,~E NA 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~)4 ~00 0 N A 7 89 11 12 60 OFFSITE CONSEQUENCES

~15 N A 7 8 9 80 LOSS GR DAMAGE .0 FACILITY

>YPE CESCR;PTION

~IS. 5 N A 7'89 10 80 PU8LICIT Y Q~J7 N A AO'.)ITIOIYAL FACTOPS DIqjo ~See Attachment 7 09 6'J 7 OO 63 NAME PHONE 0PO BE I d FR N

r Attachment Event Descri tion During the performance of scram times Surveillance instruction 4.3.C, with all "A" sequence rods in position 48, and two groups of "B" rods in gxoup notch control withdrawn to maintain rates pressure, the operator at the scram test panel placed a scram signal on an out-of-sequence, fully inserted rod (02-27) in error. The control room operator failed. to correctly identify this rod as an out-of-sequence rod. and pxoceeded to withdraw it to position 48 assuming that position was required by the rod program. The RHM was inoperable at this time,and a second licensed operator was being used to verify control rod program. (BFRO-50-260/7610)

Cause Descri tion Personnel erxor. Both licensed operators failed to verify the correct rod position by the rod program.

Additional Factors Corrective Action Special txaining will be held so that each licensed operator is again instructed to actually verify correct rod position by referring to the rod pxogram. This training shall emphasize the necessity for the second operator to check the rod. program and, verify that the console operator has the correct xod. selected and is going to withdraw or insert rod to specified notch.