05000272/LER-1982-090, Supplemental LER 82-090/01X-1:on 821121,video Insp of Removed Fuel Assemblies Revealed Cladding Ruptures on Element 13 in Fuel Assembly D-20.Caused by Isolated Instance of Secondary Hydriding

Supplemental LER 82-090/01X-1:on 821121,video Insp of Removed Fuel Assemblies Revealed Cladding Ruptures on Element 13 in Fuel Assembly D-20.Caused by Isolated Instance of Secondary Hydriding

ML20077G185
Person / Time
Site:	Salem
Issue date:	06/29/1983
From:	Frahm R, Zupko J Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
LER-82-090-01X, LER-82-90-1X, NUDOCS 8308030404
Download: ML20077G185 (4)

LER-2082-090, Supplemental LER 82-090/01X-1:on 821121,video Insp of Removed Fuel Assemblies Revealed Cladding Ruptures on Element 13 in Fuel Assembly D-20.Caused by Isolated Instance of Secondary Hydriding

Event date:
Report date:
2722082090R00 - NRC Website

text

NRC FC~ M 366 U.S. NUCLEAR REGUL ATORY t;OMMISSION 1

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LICENSEE EVENT REPORT f4 . CONTAOL 6LOCX: {l i

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61 ClO [0] 2l il 682 @]l l1 l2 l1 l0 l2 @l0l6 l2 6'J E 4 63=T DATE 74 75 REPORl9f DATE l8 l3_l(9) 60 7 DC~KET NUVSER EVENT DESCRIPTION AND PRGB ABLE CONSEQUENCES [0) 10 l 2 l jOn November 21, 1982, during routine refueling operations, video inspection of removed ;

[ O 131 lfitel assemblies revealed clRdding ruptures on Element 13 in Fuel Assembly D-20. Follow-(

lo l4i ling completion of inspection of the assembly, it was placed in the Sptnt Fuel Pit. l l o i s I trhe integrity of redundant fi::sion product barriers was maintainep The event consti- l l 0 l6 } ltuted possible abnormal de. gradation of the cladding in accordance with Technical Speci- l _

Lo_lij jfication 6.9.1.8c. I I

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41 tv J@ lNi@ lwl1]2l01 44 J3 34 JS 3/ 40 42 43 47' CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l1 I O l l Investigation revealed that the failure apparently was due to an isolated instance of l

[ilill secondary hydriding. The module was replaced with a substitute assembly, with the l IiI?Il appropriate changes made to refueling procedures. The failed module will not be used l W_3_j l in future fuel cycles. The present fuel examination program will continue to surveilld I1 14l l for any abnormalities during refueling. ]

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PUBLICITY Q 8308030404 830713 N R C USE ON L V a% SUED DESCRIPTION U PDR ADOCK 05000272 2 o [N_jhl s PDR l lllllllllllll 80 7 8 9 10 68 69 R. Frahm (609) 339-4309 NAME OF PREPARER PHONE:

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Public Servk.e Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Gencrating Sta. ion July 13, 1983 4.

Dr. Thomas C. Murley Regional Administrator USNRC Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

LICENSE NO. DPR-70 DOCKET NO. 50-272 REPORTABLE OCCURRENCE 82-090/01X-1 SUPPLEMENTAL REPORT Pursuant to the requirements of Salem Generating Station Unit No. 1 Technical Specifications, Section 6 9.1.8c, we are submitting supplemental Licensee Event Report for Reportable Occurrence 82-090/01X-1.

Sincerely yours, b 2. 2,2 y- c

, J. M. Zupko, Jr.

General Manager -

Salem Operations RF:kls CC: Distribution Y

d< g'A The Energy People /l E 2189120M) 1181

Report Number: 82-0 90/ 01X-1 Report Date: 06-29-83 Occurrence Date: 11-21-82 Facility: Salem Generating Station Unit 1 Public Service Electric & Gas Company Hancock's Bridge, New Jersey 08038 IDENTIFICATION OF OCCURRENCE:

Fuel Cladding Rupture - Assembly D-20.

This report was initiated by Incident Report 82-427 CONDITIONS PRIOR TO OCCURRENCE:

Mode 6 - Rx Power 0 % - Unit Load 0 MWe.

DESCRIPTION OF OCCURRENCE:

On November 21, 1982, during routine refueling operations, video inspection of removed fuel assemblies revealed cladding ruptures on Element 13 in Fuel Assembly D-20. The assembly had been in the core for three fuel cycles; it was in Core Location L-3 during the most recent cycle. Following completion of inspection of the assembly, it was placed in Spent Fuel Pit Location E-4. The integrity of the Reactor >

Coolant and Containment Systems was maintained throughout the occurrence.

APPARENT CAUSE OF OCCURRENCE:

A review of the tracecbility data did not indicated any trend related to manufacturing that would indicate a tendancy toward failure. Rod 13 appears to have failed due to secondary hydriding, without any apparent implications or correlations with respect to other fuel in the reactor or in the same batch. The failure was therefore assumed to be of an isolated nature.

ANALYSIS OF OCCURRENCE:

l

! The fuel cladding is a design feature which insures that radioactive l

fission products are contained in the fuel elements and not released to the primary coolant or containment atmosphere during normal operation and accidents of moderate or low frequency. The cladding is one of multiple fission product barriers which insure radiation dose l to the_public in the event of an accident is maintained within the limits of 10CFR100.

Although infrequent and limited failures of the cladding are consistent with fuel design criteria, any rupture possibly constitutes abnormal degradation and is reportable in accordance with Technical

, Specification 6.9.1.8c. As noted, the integrity of the redundant l fission product barriers was maintained. The occurrence therefore did not involve any undue risk to the health or safety of the public.

LER 8,2-090/01X-1 CORRECTIVE ACTION:

As noted, the assembly involved was transferred to the Spent Fuel Pit.

The module will not be utilized in future fuel cycles; appropriate procedural changes were implemented and a suitable replacement module was installed in its place. The present fuel examination program will continue to surveille for any abnormalities during refueling outages.

In view of tha nature of the failure, no further action was deemed necessary at this time.

FAILURE DATA:

Westinghouse Electric Corp.

Fuel Assembly A previous cladding failure was discovered in January of 1982 and is documented in LER 82-05/01X-1; the failure was attributed to excessive rod growth due to fuel lockup.

Prepared By R. Frahm V General nanager -

.SORC Meeting No.83-086 t

. . _ .