ML051390239

Part 21 Report 41702 Re Flex-Wedge Disc Fabricated by Crane- Aloyco

ML051390239
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/17/2005
From:	Scheide R Entergy Operations
To:	Office of Nuclear Reactor Regulation
References
41702
Download: ML051390239 (2)

Text

0511712005 U.S. Nuclear Regulatory Commission OperationsCenter Event Report Pace I Power Reactor Event# 41702 Site: ARKANSAS NUCLEAR Notification Date/ Time: 05/17/2005 11:24 (EDT)

Unit: 2 Region: 4 State: AR Event Date I Time: 03/19/2005 (CDT)

Reactor Type: [1] B&W-L-LP,[2] CE Last Modification: 05/17/2005 Containment Type: DRY AMB DRY AMB NRC Notified by: RICHARD SCHEIDE Notifications: REBECCA NEASE R4 HQ Ops Officer: CHAUNCEY GOULD OMID TABATABAI NRR Emergency Class: NON EMERGENCY 10 CFR Section:

21.21 - UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit Init Power Initial RX Mode ICurr Power ICurrent RX Mode 2 N No 0 Refueling Jo Refueling PART 21 FOR A FLEX - WEDGE DISC FABRICATED BY CRANE - ALOYCO "On March 19, 2005, during refueling Outage 2R17, it was identified that a Flex-wedge disc intended for installation in a Containment Sump isolation valve, did not have a machined slot around the disc edge, as required by the purchase specifications. A feature of the flex-wedge design is to allow the disc faces to flex, thereby reducing the potential for thermal binding. The discrepancy was identified during pre-installation inspection; therefore, the disc was not installed in the plant. Considering that extensive machining and handling of the disc is necessary during installation, it is extremely unlikely that the discrepancy could have gone undetected. The outboard containment sump isolation valve is normally closed and receives a Recirculation Actuation Signal (RAS) to open when the Refueling Water Tank volume is depleted (post-LOCA) in order to shift the Emergency Core Cooling System (ECCS) suction to the sump. Had the subject disc been installed in this valve, the discrepancy could have resulted in thermal binding of the disc, thereby rendering a complete train of ECCS inoperable upon initiation of a RAS. The subject disc was manufactured by Crane - Aloyco, and was delivered to Arkansas Nuclear One in 1991."

"This condition was determined to be reportable pursuant to 10CFR21 on 5/17/2005."

MAY-i7-2005 09:45 FROM: 479-858-4985 TO: 913018165151 P: 1'1.

A/h1-7 02-ARKANSAS NUCLEAR ONE PAGE: 2 E-DOC TITLE: E-DOC NO. CHANGE NO.

GUIDELINES FOR EMERGENCY NOTIFICATIONS 1015.047-ATT-A 000-00-0 Form Uged by the NRC for ETS Calls (Pogo 1 of 2)

NRC FORM 361 REACTOR PLANT U.S.NUCLEAR REGULATORY COMMISSION (120 ) EVENT NOTIFICATION WORKSHEET E OPERAINSCENTER NRCOPERATION TELEPHONE NUMBER: PRIMARY-301-816-5100', BACKUPS-(1st) 301-951-0550',

(2nd) 301-415-0550 and (3rd) 301-415-0553 'Llcensees who maintain their own ETS are provided these telephone numbers.

NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT CALLER'S NAME CALLBACK#

Arkansas Nuclear One 2 j R.H. Schelde 479-8SB-4618 EVENT TIME & ZONE EVENT DATE POWER / MODE BEFORE POWER I MODE AFTER N/ANA N/A N/A EVENT CLASSIFICATIONS 8-Hr Non-Emergency IOCFR 50.72(b)(3) 0 GENERAL EMERGENCY GENIAAECO (ii)(A) Degraded Condition ADEG Cl SITE AREA EMERGENCY SIT/AAEC ° (ii)(B) Unanalyzed Condition AUNA El ALERT ALE/AAEC 0 (Iv)(A) Specified System Actuation AESF 9 UNUSUAL EVENT UNUI/AAEC (v)(A) Safe SID Capability AINA O 50.72 NON-EMERGENCY (below &noxt column) Q (v)(B) RHR Capability AINI O PHYSICAL SECURITY (73.71) DDDD 0 (v)(C) Control of Rod Release AINC l MATERIAL EXPOSURE B??? [l (v)(D) Accident Mitigation AIND El FITNESS FOR DUTY HFIT 0 (xii) Offsito Medical AMED OTHER UNSPECIFIED REOMT. (next collnn) (x) Loss CommlAsmnt/Resp ACOM E INFORMATION ONLY NNF 60-DAY OPTIONAL IOCFR _.73(a)(1) 1-Hr Non-Emorgoncy ioCFR 50.72(b)(1) OEl Invalid Specified System Actuation AINV El TS Deviation ADEV Other Unspecified Roquirement (Identify) 4-Hr Non-Emergency OCFR 50.72(b)(2)R

_(i) TS RequiredSID ASHU NONR O (lv)(A) ECCS Discharge to RCS ACCS . * - .  ;'.

a (iv)() RPS Actuation (scram) ARPS , .  : '-., '

El (x)(B) Offsite Notification APRE _,., '!;y-..

DESCRIPTION Include: Systems affected, actuations & their initiating signals, causes, effect of event on plant, actions taken or planned, etc.

On March 19, 2005, during refueling Outage 2R17, It was identified that a Flex-wedge disc intended for Installation in a Containment Sump Isolation valve, did not have a machined slot around the disc edge, as required by the purchase specifications. A feature of the flex-wedge design Is to allow the disc faces to flex, thereby reducing the potential for thermal binding. The discrepancy was IdentIfied during pre-installation Inspection; therefore, the disc was not installed In the plant. Considering that extensive machining and handling of the disc Is necessary during Installation, It Is extremely unlikely that the discrepancy could have gone undetected. The outboard containment sump isolation valve Is normally closed and receives a Recirculation Actuation Signal (RAS) to open when the Refueling Water Tank volume Is depleted (post-LOCA) in order to shIft the Emergency Care Cooling System (ECCS) suction to the sump.

Had the subject disc been Installed In this valve, the discrepancy could have resulted In thermal binding of the disc, thereby rendering a complete train of ECCS Inoperable upon Initiation of a RAS, The subject disc was manufactured by Crane-Aloyco, and was delivered to Arkansas Nuclear One In 1991.

This condition was determined to be reportable pursuant to 1OCR21 on 5/17/2005.

- Y, -,

NOTIFICATIONS I -YES I NO WILL BE Anything unusual NRC RESIDENT ID I or not understood?

STATE(s) Li

- -- +

Li iii-Did all systems function LOCAL El El as required?

OTHER GOV AGENCIES _ El _ _

10 .- El

_ Mode of operation MEDIAJPRESS RELEASE El a until corrected: NIA I

05/17/2005 TUE 11:31 [TX/RX NO 5262] IaO1