ML18283B487

Abnormal Occurrence Report BFRO-50-296/761W Blade Guide Assembly Removed from Reactor as Part of Fuel-Loading Operations

ML18283B487
Person / Time
Site:	Browns Ferry
Issue date:	07/16/1976
From:	Fox H Tennessee Valley Authority
To:	Moseley N NRC/IE, NRC/RGN-II
References
BFRO-50-296/761W
Download: ML18283B487 (6)

Text

TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 July 16, 1976 Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and. Enforcement Region II 230 Peachtree Street, NW., 8th Floor Atlanta, Georgia 30303

Dear Mr. Moseley:

TENNESSEE VALLEY AUTHORITY - BROWNS FERRY NUCLEAR PIANT UNIT 3-DOCKET NO. 50-296 - FACILITY OPERATING LICENSE DPR-68 - REPORTABLE OCCURRIRICE REPORT BFRO-50-296/761W The enclosed report is to provide details concerning a blade guide assembly that was being removed from the reactor as part of fuel-loading operations and. is submitted in accordance with Appendix E to Regulatory Guide 1.16, Revision Il, August 1975. This event occurred on Browns Ferry Nuclear Plant unit 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY H. S. Fox Dixector of Power Production Enclosure (3)

CC (Enc1osure):

Director (3)

Office of Management Information and. Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (Il0)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer

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~ ICENSEE EVENT REPORT ~

CONTROL BLOCK: (PLEASE PRINT ALL REQUIRED INFORMATION) 1 LCENSEE LCENSE EVENT NAME LCENSE NUMBER TYPE TYPE Kg89 A L B R F 3 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~01 7 14 15 25 26 30 31 32 REPORT REPORT 7

[OD~] CON'7 8

~7 CATEGORY 57 58 TYPE 1

59 SOURCE 1

60 61 0 5 DOCKET NUMBER 0 0 2 9 6 68 69 0 7 EVENT DATE 0 4 7 6 74 0

75 7

REPORT DATE y 2 7 6 80 EVENT OESCRIPTION

[OD~] See attached sheet) 7 8 9 80 7 89 80

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7 8 9 80 7 8 9 80 Jag 7 8 9 80 SYSTEM CAUSE COMPONENT COBE CODE COMPONENT CODE MANUFACTLÃKA VCLATION 7

ICD7] ~PD 8 9 10

~E X:: X X X X ~N 5 3 9 2 11 12 17 43 44 47 48 CAUSE OESCRIPTION LOOM See attached sheet) 7 8 9 80

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7 89 80 QO]

7 89 80 FACIUTY METHOD OF STATUS POVVER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

@~g ~c ~oo o N/A B 7 8 9 10 12 13 44 45 46 80 FORM OF ACTIVITY COATENT 0 RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Hl 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~TO ~OO O Z N/A 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION ITT4I ~oo o N/A 7 89 11 12 80 OFFSITE CONSEQUENCES fiis] N/A 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE OESCRPTION D Blade unde handle sheared and sto ins bent 7 89 10 80 PUSLICITV

[<i~] N/A 7 89 80 AOOITIONAL FACTORS N/A 7 89 80 7 89 80 NAME: PHONE:

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Event Descri tion A blade guide assembly was being removed from the reactor as part of fuel-loading operations. When the bottom of the blade guide assembly was approximately three feet above the upper core plate, a section of the telescoping grapple boom slipped downwards When this section reached its normal extended position, it impulsed the lower sections which caused an abrupt force on the boom which broke the blade guide assembly handle. The blade guide assembly fell back into the incore position from which it was removed. (BFRO-50-296/761)

Interference between two adjacent sections of the boom as the grapple was being lifted caused one section to stop before it was fully extended, Then the section fell to its fully>>extended position.

Additional Factors All pieces of the boom and blade guide assembly were accounted for; the surrounding fuel assemblies, adjacent LPRM incore, and the fuel support piece inspected and no evidence of damage observed; and the boom was replaced with the unit 2 boom which had demonstrated reliability during fuel loading on 1

that unit,

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