ML11306A194
| ML11306A194 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/01/2011 |
| From: | O'Keefe M General Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 47395 | |
| Download: ML11306A194 (2) | |
Text
1110112011 U.S. NuclearRegulatory Commission OperationsCenter Event Report Page I Power Reactor Event# 47395 Site: SEABROOK Notification Date I Time: 11/01/2011 09:38 (EDT)
Unit: 1 Region: 1 State: NH Event Date / Time: 10/31/2011 18:00 (EDT)
Reactor Type: [1] W-4-LP Last Modification: 11/01/2011 Containment Type: DRY AMB NRC Notified by: MICHAEL O'KEEFE Notifications: NEIL PERRY R1DO HQ Ops Officer: PETE SNYDER Emergency Class: NON EMERGENCY 10 CFR Section:
21.21 UNSPECIFIED PARAGRAPH Unit Scram Code RX Crit lnit Power Initial RX Mode Curr Power Current RX Mode 1 N Yes 100 Power Operation :100 Power Operation GENERAL ELECTRIC CR-120B RELAYS SUPPLIED BY NATIONAL TECHNICAL SYSTEMS FAIL BENCH TEST "On October 31, 2011, NextEra Energy Seabrook, LLC completed a 10 CFR 21 evaluation of a condition associated with General Electric (GE)-CR-120B relays supplied by National Technical Systems, Inc. and intended for use at Seabrook. Six (6) Quality Level 1 GE-CR-120B relays failed bench testing. During bench testing, the subject relays failed to reset when de-energized. An evaluation was performed to determine the applications where these relays could have been and were installed and to determine if the failure of the subject relays could result in a Substantial Safety Hazard as defined in 10 CFR 21.3. The evaluation concluded that there is one safety significant application relative to the failure of the GE-CR-120B relays to reset in the Seabrook Diesel Air Handling System (DAH).
"Each DAH system train (includes one supply fan and one exhaust fan per train) has one relay that provides a start permissive for the ventilation fans. An analysis of the failure of a GE-CR-120B relay in the DAH system determined that, if the relays were installed, the condition could create a substantial safety hazard due to a subsequent loss of the emergency power function. Therefore, this report is being submitted pursuant to the requirements of 10 CFR 21.21(d)(3)(i). A written notification will be made to the NRC within 30 days pursuant to 10 CFR 21.21(d)(3)(ii).
"No actual safety consequences resulted from this condition because the GE-CR-120B relays were not installed in the plant in this safety significant application."
The licensee notified the NRC Resident Inspector.
7-
JAN-02-1996 23:07 P. 01/01 PAGE I OF 2 NRC FORM 361 N~c FOM U.S. NUCLEAR REGULATORY COMMISSION 361OPERATIONS CENTER (12-2000) REACTOR PLANT EN #
EVENT NOTIFICATION WORKSHEET NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-815-5100 or 80O-$32-3469. ,. BACKUPS
....... -[let) a01-51-0550 or B0O-449-S89d,
,ow. n E are rnwvidd thlse teleohone numbers.
- hir
. i r2nm 301-415-0550 and '3rdg301-415-0553 6=119138b w,13....... . -- - -- BACK.
NCTIRCATION TIME FACILITY OR ORGANIZATION UI.T NAME DRCALLER I A -I 7 -
Seabrook Station 1 Michael O'Keefe EVENT TME & ZONE EVENTCATE POIASVJOLC BEORE POWERMODEAIFTER 1-900/ 101312011 100%/I1 100%A/1 Ia-aI I II III EVENT CLASSIFICATIONS 1-Hr. NonEmemrency 10 CFR60,7.(b)() (v)(A) sale2sbo Cfpl GB2NE*tA EMREC - B i* .. . , AM G..Y. TDSviato AS - iv)-(B) MR (t)(5) C Ctlily STM AREAEMER-GECY S ',--EC 4-Hr. Non-Emeraencv 10 C PFR 60.7T 1b M2) - 1V)(Q) C onif Red Relesae AnERT ALEAAEC (.3 TS Reqluid WIP ASHU ,(v)(D) Accident Mi;igtise AMND uNUSUAL EVENT UNLIMAEC .(Iv(A) COCSDiasdise to RCS AOCS (161 OAStes Mo. AED 50.72 NON-EMERG,.ENCY (see noed colurnis) _(I1y)(8) RPS Actuation (scUm) 0d,) Lass, as&"Comnivfsp
.CM PH-fYSICAL SECURITY (271) D () olsite Noti*scao APpi 80-Day Optional 10 CFR 50.73(a)( 1 MATERL.*_XWOSURE e1 B-Hr. NonlEmeMency 10 CFR 60.721b4)3 T Invalid Spu..fi*d Sym Atllon PAW FrINESS FOR rY Hrr I(11,(A) D*od Cordi, A=C- Other Unspecified Requirement (Identify) 071-CRuN*SPECIFlED IMEO (see lest cclurnr) V() Unsmieyzed Condition AmA 1/ lg ez 2 i-o--.i. - OLm EFORMATION ONLY NIN (IX)(A) Spedlied System AdEuedon
-.. DESCRIPTION Ihdude: Systems affected, a.fjlions and m Initiating signals, caust es. ed of event on plant, adis takhn or planned. etc. (Con*En,' 6A bee¢)
On October 31, 2011, NextEra Energy Seabrook, LLC completed a 10 CFR 21 evaluation of a condition associated with General Electric (GE) CR-1 200 relays supplied by National Technical Systems, Inc. and intended for use at Seabrook. Six (6) Quality Level 1 GE CR-1208 relays failed bench testing. During bench testing, the subject relays failed to reset when de-energized. An evaluation was performed to determine the applications where these relays could have been and were installed and to determine if the failure of the subject relays could result in a Substantial Safety Hazard as defined in 10 CFR 21.3. The evaluation concluded that there is one safety significant application relative to the failure of the GE-CR 120B relays to reset inthe Seabrook Diesel Air Handling System (DAH).
Each DAH system train (includes one supply fan and one exhaust fan per train) has one relay that provides a start permissive for the ventilation fans. An analysis of the failure of a GE-CR 120B relay In the DAH system determined that, if the relays were installed, the condition could create a substantial safety hazard due to a subsequent loss of the emergency power function. Therefore, this report is being submitted pursuant to the requirements of 10 CFR 2121 (d)(3)(i). A written notification will be made to the NRC within 30-days pursuant to 10 CFR 21.21(d)(3)(i).
No actual safety consequences resulted from this condition because the GE-CR 120B relays were not installed in the plant in this safety significant application.
The Senior Resident Inspector was notified.
NOTIFICATIONS YES NO WIlL SE ANYTHING UNUSUAL OR Y--n NRC RESIDENT I N/ UNDERSTOOD?
IOT av __
ST ATE(s) I1 0 ALESY LL S YSSTE TME MSYEIDNAL Y abov LOCAL / FUNCTION AS REQUIRED? NO'-o OTHER GOV AGENCIES -. _ MODE OF OPERATION ESTIMATED ADmONALINFO ON BACK MEDIA/PRESS RELEASE CORRECTE.
.UNTIL N/A RESTART DATE:N/A [E YES ] NO NRC FORM 361 (12-2000)
TOTAL P.01