ML19323H711

Revised LER 80-002/03L-1:on 800116,during Fuel Bundle Clip Insp Prior to Fuel Sipping, Fuel Bundle UD3-023 Was Misoriented & Not Properly Seated in Core Cell.Caused by Personnel Error & Inadequate Procedures.Procedures Revised

ML19323H711
Person / Time
Site:	Oyster Creek
Issue date:	06/05/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19323H705	List: ML19323H704 ML19323H711
References
LER-80-002-03L, LER-80-2-3L, NUDOCS 8006160086
Download: ML19323H711 (4)

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74 75 AEPORT QATE 83 6G 61 OCCKET ALMBER EVEN f OESCAlPTION AND PRC0ASLE OoNsECuENCES h On Januarv 16. 1980, during a fuel bundle clio insoection ocior to fue; I ie i:J l Joi2; } " sipping"; it was discovered that fuel bundle UD3-023 was mi mriented I loi4; i 180* and was not properly seated in core cell location 05-74. This ,j

, i3; ; event is considered to be reportable in accordance to T.S.6.9.2.b.3 l

,e.,! I Fuel bundle UD3-023 aas insoected for fuel rod clad failure by the fuel  ;

};;7, ; vacuum sipping method. The inspection results indicated that no clad l

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3 ,aji The cause of this event is attributed to cersonnel error and to inad- 1 ii ,i ; ; e

;uate crocedural control s. Procedure 205 " Reactor Refueling" has been l revised to include the use of a " Fuel Sundle Orientation" map to be ut-  ;

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NAME OF 8cE8ARER Conald A. Ross PHCNE: bEC-E N

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Jersey Central Power & Light Company

- ff (' Madison Avenue at Punen Scwi Rcao Mcmstown. New Jersey 07983 (201)455-8200 OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reoortable Occurrence No. 50-219/80-2/3L-1 Reoort Date Update Report: June 5, 1980 Previous Report Date: February 15, 1980 Date of Occurrence January 16, 1980 Identification of Occurrence Operaticn with a misorientated fuel assembly during cycle Vill.

This event is considered to be a reportable occurrence as defined in the Techni-cal Specification:. .=ragraph 6.9.2.b.(3).

Conditions Prior to Occurrence The plant was shutdown for refueling and maintenance.

Description of Occurrence On January 16, 1980, at approximately 6:00 AM, during a fuel bundle clip inspec-tion prior to fuel " sipping", it was discovered that fuel bundle 03-023 was misorientated 180* and was not properly seated in its core cell location 05-14.

Accarent Cause of Occurrence Operator error, procedural controls and error on the cart of other persennel involved in the refueling activity, contributed to the cause of this event.

Analvsis of Occurrence A review of cycle 8 power distributions indicate a maximum cycle bundle radial power of 0.63 Utilizing " worst case" peaking factors (1.57 axial and 1.277 local) would result in a bundle CPR of 2.54 if UO3-023 was correctly orientated.

An analysis discussed in Facility Change Request #4,Section V. A.2, January 18, ,

1973, determined that a 7 x 7, type !!!F fuel bundle miserientated 180* would resuTt in a 21% increase to the bundle local peaking. This increase indicates that the minimum CPR of bundled 003-923 in its misorientated position was 2.23 -

which is considerably above the Technical Specification operating limit of 1.64.

Jersey Central P0wer & Ugst Comcary is a Memcer Of :.*e Genera: PubdtWhes Systern

Reportable Occurrence No. 50-219/80-2/3L-1 Page 2 June 5, 1980 Previous Report Date: February 15, 1980 An analysis was also performed by the fuel vendor. The analysis considered both the effects of the change in local power due to the misorientated bundle, and the reduction in assembly flow rate due to the hangup of the fuel channel clip. 1 The analysis concluded that the minimum ' thermal margin was well above the criti-cai power ratio operating limit of 1.64.

In addition, fuel bundle U03-023 was inspected for fuel rod clad failure by the fuel vacuum sipping method. The inspection concluded that no clad failure had occurred. Fuel Assembly UD3-023 was discharged from the core as scheduled.

Further, core cell 05-14 is located at a low flux peripheral core area. A letter from R. E. Engel (General Electric) to D. G. Eisenhut (NRC), " Fuel Assemoly Loading Error," dated November 30, 1977, states that a fuel loading error in a low flux peripheral core location is not significant.

Therefore, since analysis concludes the CPR of the misorientated fuel bundle is considerably above the technical specification operating limit CPR, an inspection of the fuel bundle determined no fuel clad failure, and the determination that a misorientated fuel bundle in a low flux core peripheral location is insignifi-cant, the safety significance of the occurrence is considered minimal.

A critical review of operator methods and procedural controls utilized during final fuel loading and bundle orientation verification was conducted. The review indicated that operator metheds of determining bundle orientation is inadequate in that no procedural guidance or core map displaying the proper orientation of each bundle is utilized.

Although the proper orientation of non peripheral bundles is easily determined by the repeatable pattern of control cell markings, peripheral bundles are located at the edge of the marking pattern and some bundles are not included in any control cell. This discontinuous area of orientation marking pattern increases the margin for fuel bundle orientation error.

The review also indicates that the operator methods and procedural control of core verification could be improved. Fuel bundle orientation verification is conducted, (as required by procedure,) utilizing a video monitoring system. The camera asso-ciated wl:F the monitor system is not stabilized during bundle orientation veri-fication and its " free 3 winging" ability produces shadows and other distortions to the TV moni tor. These distorted visual effects decrease the ability to per-form a proper bundle orientation verification and increases the probability of a bundle orientation verification error. Although video monitoring conditions are not totally conducive to bundle orientation verification, procedure 1001.24,

" Core Verification", required only one verification of proper bundle orientation.

Corrective Action The following procedural controls will ce implemented to insure the occurrence will not be repeated:

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l Reportable Cccurrence No. 50-219/80-2/3L-1 Page 3 June 5, 1989 Previous Report Dated: February 15, 1980 (1) Procedure 205, " Reactor Refueling" has been revised to include the use of a " Fuel Sundle Orientation" map to be utilized during fuel loading.

(2) Procedure 1001.24, " Core Verification" will be revised to include: (a) ,

documentation of bundle orientation during verification of fuel bundle identification numbers. (b) if possible fuel bundle orientation verifica-tion will be video taped, and (c) quality Assurance personnel will perform an independent orientation verification in addition to the verification (s) required above. Additionally, there will be a requirement that the Video l Monitoring System be modified such that a " stabilized" video display will be produced during bundle orientation verification.

1 Failure Data Not applicable j

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