ML20046A469

LER 93-016-00:on 930619,Phase A,Auxiliary Bldg & Containment Isolations Manually Initiated as Result of Fuel Assembly Failing to Remain in Upright Position After Being Released. All Fuel Movement stopped.W/930719 Ltr

ML20046A469
Person / Time
Site:	Sequoyah
Issue date:	07/19/1993
From:	Fenech R, Proffitt J TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-016, LER-93-16, NUDOCS 9307280153
Download: ML20046A469 (6)

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nn 1 Tennessee Vaney Auttwnty, Post Office Box 2000. Soddy-Daisy. Tennessee 37379 2000 I

Robert A. Fenech Vice President, Sequoyah Naciear Plant i

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July 19, 1993  !

l U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

TENNESSEE VALLEY AUTHORITY - SEQUOYAH NUCLEAR PLANT UNIT 2 - DOCKET NO. 50-327 - FACILITY OPERATING LICENSE DPR LICENSEE EVENT REPORT (LER) 50-327/93016 The enclosed LER provides details concerning a manual Phase A isolation, an auxiliary building isolation, and containment ventilation isolation in accordance with plant procedures as a result of a fuel assembly not remaining upright after being released into position. This event is being reported in accordance with 10 CFR 50.73(a')(2)(iv) as an event that resulted in the manual actuation of an engineered safety feature.

Sincerely,

) $. .L P,bert A. Fenech Enclosure cc: See page 2 270050 1

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U.S. Nuclear Regulatory Commission

-Page 2 July 19, 1993 cc'(Enclosure):

INPO. Records' Center.

Institute of Nuclear' Power Operations 700 Calleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland. 20852-2739 NRC Resident. Inspector Sequoyah Nuclear Plant 2600 Igou' Ferry l Road Soddy-Daisys Tennessee 37379-3624 Regional Administrator U.S. Nucicar P,egulatory Commission Region II 101 Marietta Street, hW, Suite 2900 Atlanta, Georgia 30323-2711

NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6n9)

Expires 4/30/92 LICENSEE EVENT REPORT (LER)

FAC1t'b[tlAME(1) lDOCKETNUMBER(2) lPAGE(3)

SeftwyidtNyq1 ear Plant. Unit 1 101510]Sjk13jZ_l]_jllpf]014 I!Til (4) A Phase A Isolation, Auxiliary Building Isolation, and Containment Ventilation Isolation Were

_Mvu>allL10itjAted as a Resuli_g_f Fuel A11embly f ailingdale_ main in SLup.tigh_Lfolj tion Af ter BeingjehasesL._

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ADSTRAC1 (timit to 1400 spaces, i .e., approximately fif teen single-space typewritten lines) (16) on .inne 19, 1993, at 1054 Eastern daylight time (EDT), during fuel loading activities, a fuel assembly immediately tilted over after being released into position. The fuel assembly came to rest against the south core baffle plate leaning at an angle I approximately 18 degrees from vertical. At 1154 EDT, a Phase A isolation, auxiliary  !

building isolation, and containment ventilation isolation were manually initiated in accordance with abnormal operating procedures in response to the fuel-handling event.

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NRC iorm 366(6-89)

, e NRC f orm 366A U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 (6-09)

Expires 4/30/92 LICENSEE EVENT REPORT (LER)

• TEXT CONTINUATION FACILITY NAME (1) lDOCKETNUMBER(2) l LER NytiBfR (6) l I PAGE._(3L_.

l l l lSEQUENTIALj. l REVISION l l l l l Sequoyah Nuclear Plant, Unit 1 l lYEAR l I NUMJER I I NUMBER l l l l l i

. . _ . . _ _ 10151010[Q13 l2 17 19 13 1-1 0 l 1 1 6 l--I O_[ 0l012l0FlOL.4 ,

IEXI (if more space is required, use additional NRC form 366A's) (17) '

1. PLANT CONDITIONS Unit I was in Mode 6 in a refueling outage with core-loading activities in progress with 43 fuel assemblies in the core.

IJ. DESCRIPTION OF EVENT A. Eve.at On June 19, 1993, at 1054 Eastern daylight time (EDT), a fuel assembly immediately tilted over after being released into position. The fuel assembly came to rest against the south-core baffle plate leaning at an angle' approximately 18 degrees from vertical. At 1154 EDT, a Phase A isolation,- I auxiliary building isolation (ABI), and a containment ventilation isolation (CVI) were manually initiated in accordance with abnormal operating procedures l in response to the fuel-handling event.

B- Inoperable _StInntsteru_Componenth or Systema _lbat._ Contributed to thelvent

.I None.

l C. Datea_.anLApproxiInate Timea_nf_ Major Onnuttennes  !

June 19, 1993 Core-loading activities were in progress with 43 fuel assemblies in the core. i June 19, 1993 The next fuel assembly loaded immediately tilted over I at 1054 EDT after being released into position.

)

June 19, 1993 All fuel movement was stopped, the manipulator crane was at 1055 EDT positioned over the internals set-down area, and power was secured.

I June 19, 1993 A Phase A isolation, ABI, and CVI were manually )

at 1154 EDT initiated in accordance with abnormal operating l procedures. I 1

D. O the t_Syrd ema_u r_Se.c ond ary_Eun c.tiona_Affectrd i

None.  ;

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E. Methotof_Diacovery  ;

1 The fuel assembly was observed by Operations personnel during performance of 'l core-loading activities. l NRC Form 366(6-89)

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NRC form 366A. U.S. NUCLEAR REGULATORY COMMISSION Approved OMB No. 3150-0104 i

( f>-89 )

Expires 4/30/92 LICEM3EE EVENT REPORT (LER)

• TEXT CONTINUATION l ACIL11Y tlAttE (1) l DOCKET NUMBER (2) l LER NUMBER (6) } l fAGE (3)

.Sequoyah tioclear Plant Unit 1 l l l l SEQUENTIAL l l REVISION l l l.l l' l } KAR I l NUMBER I l NUMBElL} l l l l 1015]HlD1013 12 17 19 .13_l-l 0 1 1 l Jul-1 0 1 0_J_Rl _3]QIJ_D}_4 TEXT (II' more space is required, use additional NRC form 366A's) (17)

F. DPer h Attion Upon discovery of the leaning fuel assembly, Operations personnel stopped all fuel movement, the manipulator crane was positioned over the internals set-down area, and power was secured. A notice of unusual event was declared and the a Phase A isolation, ABI, and CVI were manually initiated.

G. Satety_SystenLResponse The equipment required to operate after the manual Phase A isolation, ABI, and the CVI performed as expected.

TI1. CAUSE OF EVENT Cauve The Phase A isolation, ABI and CVI were manually initiated in accordance with abnormal operating procedures following discovery of the leaning fuel assembly.

IV. ANALYSIS OF EVENT

) Plant equipment required to operate af ter the manual Phase A isolation, ABI, and the CVI performed as expected. There was no radiological release as a result of the event and the event is bounded by the Final Safety Analysis Report. Therefore, it can be concluded that there were no adverse consequences to the plant personnel or to the public as a result of this event.

V. CORRECTIVE ACTION A. InmindiatLCarrec_tlic_Attlon Upon discovery of the leaning fuel assembly, Operations personnel stopped all fuel movement, the manipulator crane was positioned over the internals set-down area, and power was secured. A Phase A isolation, ABI, and CVI were manually initiated.

B. Action _to_PretenLRecurrence None

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NRC form 366A .U.S. NUCLEAR REGULATORY COMMISSION Approvsd OMB No. 3150-0104 i (6-89)

• Expires 4/30/92 LICENSEE EVENT REPORT (LER)-

• TEXT CONTINUATION l CILITY NAME (1) lDOCKETNUMBER(2) l LER nut 91R (6) 'l l PAGE (3) l l .] l SEQUENTIAL l l REVISION l l l l l Sequoyah Nuclear Plant, Unit 1 l lYfARI l NUMBIE l__}_N_yMJfL1 l l l l

. _ _ . . . _ _ 10jhlp.1010.13_12_j]_{9_13_j-l 0 l 1 1 6 l-l 0 1 - Q._1_QJJQEl 01 4 IEXT (If more space is required, use additional NRC form 366A's) (17)

VI. ADDITIONAL INFORMATION A. failed._C.QmEQnents None.

B. PJteviQua_S.imilar_Even1E Although there have been previous engineered safety feature actuations (ESF).

there were no previous similar reportable events associated with a fuel-handling event resulting in an ESF.

C. Other The cause of the fuel-handling event was that the fuel-handling instruction was-not completely followed when the fuel assembly was inappropriately unlatched from the manipulator crane. The refueling senior reactor operator relied on visual inspections and other indications rather than the required indication.

A contributing cause to this event was that the fuel-handling instruction did not contain sufficient criteria for determining when the fuel assembly could be unlatched.

The appropriate fuel-handling instruction has been revised to include appropriate criteria for unlatching of a fuel assembly.

V!1. COMMIMENT None.

NRC form 366(6-89)