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{{#Wiki_filter:0611612011 | {{#Wiki_filter:0611612011 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze I Power Reactor Event# | ||
Unit: 1 | 46964 Site: FITZPATRICK Notification Date / Time: 06/16/2011 12:14 (EDT) | ||
Reactor Type: | Unit: 1 Region: 1 State: NY EvenrtDate/Time: 06/15/2011 14:00 (EDT) | ||
21.21 | Reactor Type: [1] GE-4 Last Modification: 06/16/2011 Containment Type: MARK I NRC Notified by: EUGENE DORMAN Notifications: JUDY JOUSTRA 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 ROSEMOUNT MODEL 710 TRIP UNITS WOULD NOT TURN ON DURING TESTING "On June 15. 2011, the site vice president was notified that the 10 CFR 21 evaluation of.Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21 (d)(1) are met. | |||
"During pre-installation testing it was found that 3 of 4 Rosemount Model 710 Trip Units would not turn on. The units were returned to Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unit was failed. This prevented the trip unit from starting. Based on engineering analysis some of the applications for the trip unit require it to energize to perform the associated safety functions. Therefore, the identified failure mechanism could have represented a substantial safety hazard if the components had been installed, and the condition is reportable. | |||
"The condition had no actual safety consequences as the deficiency was identified during pre-installation testing and if installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount. This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i)." | |||
The licensee notified the NRC Resident Inspector. | The licensee notified the NRC Resident Inspector. | ||
@6/16/2011 | @6/16/2011 12:14 3153436480 JAF SITE VP PAGE 02/02 PAGE 1 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSiON (12-2000) | ||
NRC OPERATION TELEPHONE NUMBER: | REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN # | ||
NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-100 or 800-532-3469*, BACKUPS - (let] 301-951-0550 or B00-442-3e54", | |||
NOTIRCAllON TIME | .2ndi 301-415-0550 and [3rdl 301-415-0553 "Licensees who maintain their own ETS are provided these telephone numbers. | ||
NOTIRCAllON TIME FACIUITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK # | |||
EVENT CLASSIFICATIONS | ,ao*,I James A-Fitzpatrick NPP 1 | ||
MATERIALEXPOSURE | Eugene Dorman (315) 349-6810 rGNTTIME | ||
: 1. Zota ERWr UATE POUEhMIODE *:*RE POVWERMODE AFTER 1400 06/15/2011 Mode 1 /100% | |||
Mode 1 / 100% | |||
DESCRIPTION Include: Systems | EVENT CLASSIFICATIONS I-Hr. Non-Emergency 10 CFR 60.72(b1) | ||
.. (v)(A) | |||
Safe SIO Capability ANNk GENGRp.. EMERGENCY GEN(AAEC AT Devian Aj (0)3) | |||
RW-R COPONRY ANW ST 5IAREAEMERGENCY Wr/AAEC 4-Hr. Non-Ememency 10 CFR 60.72 b)(2) -- | |||
(v)(C) | |||
Controterf Rad Release AINC ALERT A-E/AAE | |||
: 0) | |||
TS Required SO A,.-U (v)(D) | |||
Ac6ident Mitigation AM LNUSUAL EVENT LNUIAAEC (iv)(,) | |||
ECCS Diftmme 10 RCS ACCS (d) | |||
Offalte MediCal AMED 50,72 NON-EBsERGENCy (see nan columns) | |||
(Iv)(B) | |||
RPS Actuation (scramn) | |||
PW'5 tat) | |||
Loss Conlm/AsmtiResp xw PHYSICAL SECURITY (73.71) tM (xi) | |||
O*,ste Notincalon AE 60-Day Optional 10 CFR 60.73(a)(1) | |||
MATERIALEXPOSURE 277? | |||
8-Hr. Non-Emerency 10 CFR 50.72(b)(3) | |||
Irivaflkspecf*fied st | |||
,n Actuation AMt RTNE55FoR Duty terr J (i(CO Dgraded Consoo AmEG Other Unspecified Requirement (identify) 0THLPISPEýCE REaDrEMT (sselastcolumn) | |||
Q (B) unanst-"dCondition AutA, v/' 10 (IF2,,,Jd)Lii)( | |||
£ roe INFORMATION ONLY | |||
-p 1(ivfA) | |||
Specifid Syater Actuation A | |||
DESCRIPTION Include: Systems effecWte, ectuations and their initiating signal., causes, effect of event on plant. actions taken or plasneo. etc. (Confltnue ornback) | |||
On June 15, 2011, the site Vice President was notified that the 10 CFR 21 evlauation of Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21(d)(1) are met,. | On June 15, 2011, the site Vice President was notified that the 10 CFR 21 evlauation of Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21(d)(1) are met,. | ||
During pre-installation testing ftwas found that 3 of 4 Rosemount Model 710 Trip units would not turn on:- The units were returned t | During pre-installation testing ftwas found that 3 of 4 Rosemount Model 710 Trip units would not turn on:- The units were returned t Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unitwas failed. This prevented t0 the u p Lin k I i i~ SLEI ung.., | ||
aedb onq enginee rirng analysissom olw 11*.10 alpplicatilons forthe tri p unlit require t to energize to perform the associated safety functions. Therefore, the identified failure mechanism could have represented a substantial safety hazard IF the components had been installed, and the condition is reportable. | |||
The condition had no actual safety consequences as the deficiency was identified during pria-installation testing and if Installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount. | The condition had no actual safety consequences as the deficiency was identified during pria-installation testing and if Installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount. | ||
This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i). | This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i). | ||
NOTIFICATIONS | NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR 0 YES (ExpJain above NO NRC RESIDENT | ||
STATE(S) | / | ||
NOT UNDERSTOOD? | |||
DID ALL SYSTEMS Vo | STATE(S) i DID ALL SYSTEMS LOCAL Vo FUNCTION AS REQUIRED? | ||
OTHER GOV AGENCIES | [ | ||
MEDIA/PRESS RELEASE | YES NO (Explain above) | ||
OTHER GOV AGENCIES V | |||
MODE OF OPERATION ESTIMATED ADlmoNAI INFO ON BPO( | |||
MEDIA/PRESS RELEASE | |||
/ | |||
UNTIL CORRECTED RESTART DATE: | |||
D E $ | |||
NO NRC FORM 381 (12-2000)}} | |||
Latest revision as of 05:46, 13 January 2025
| ML11171A066 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 06/16/2011 |
| From: | Eugene Dorman Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 46964 | |
| Download: ML11171A066 (2) | |
Text
0611612011 U.S. Nuclear Regulatory Commission Operations Center Event Report Paze I Power Reactor Event#
46964 Site: FITZPATRICK Notification Date / Time: 06/16/2011 12:14 (EDT)
Unit: 1 Region: 1 State: NY EvenrtDate/Time: 06/15/2011 14:00 (EDT)
Reactor Type: [1] GE-4 Last Modification: 06/16/2011 Containment Type: MARK I NRC Notified by: EUGENE DORMAN Notifications: JUDY JOUSTRA 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 ROSEMOUNT MODEL 710 TRIP UNITS WOULD NOT TURN ON DURING TESTING "On June 15. 2011, the site vice president was notified that the 10 CFR 21 evaluation of.Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21 (d)(1) are met.
"During pre-installation testing it was found that 3 of 4 Rosemount Model 710 Trip Units would not turn on. The units were returned to Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unit was failed. This prevented the trip unit from starting. Based on engineering analysis some of the applications for the trip unit require it to energize to perform the associated safety functions. Therefore, the identified failure mechanism could have represented a substantial safety hazard if the components had been installed, and the condition is reportable.
"The condition had no actual safety consequences as the deficiency was identified during pre-installation testing and if installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount. This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i)."
The licensee notified the NRC Resident Inspector.
@6/16/2011 12:14 3153436480 JAF SITE VP PAGE 02/02 PAGE 1 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSiON (12-2000)
REACTOR PLANT OPERATIONS CENTER EVENT NOTIFICATION WORKSHEET EN #
NRC OPERATION TELEPHONE NUMBER: PRIMARY - 301-816-100 or 800-532-3469*, BACKUPS - (let] 301-951-0550 or B00-442-3e54",
.2ndi 301-415-0550 and [3rdl 301-415-0553 "Licensees who maintain their own ETS are provided these telephone numbers.
NOTIRCAllON TIME FACIUITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK #
,ao*,I James A-Fitzpatrick NPP 1
Eugene Dorman (315) 349-6810 rGNTTIME
- 1. Zota ERWr UATE POUEhMIODE *:*RE POVWERMODE AFTER 1400 06/15/2011 Mode 1 /100%
Mode 1 / 100%
EVENT CLASSIFICATIONS I-Hr. Non-Emergency 10 CFR 60.72(b1)
.. (v)(A)
Safe SIO Capability ANNk GENGRp.. EMERGENCY GEN(AAEC AT Devian Aj (0)3)
RW-R COPONRY ANW ST 5IAREAEMERGENCY Wr/AAEC 4-Hr. Non-Ememency 10 CFR 60.72 b)(2) --
(v)(C)
Controterf Rad Release AINC ALERT A-E/AAE
- 0)
TS Required SO A,.-U (v)(D)
Ac6ident Mitigation AM LNUSUAL EVENT LNUIAAEC (iv)(,)
Offalte MediCal AMED 50,72 NON-EBsERGENCy (see nan columns)
(Iv)(B)
RPS Actuation (scramn)
PW'5 tat)
Loss Conlm/AsmtiResp xw PHYSICAL SECURITY (73.71) tM (xi)
O*,ste Notincalon AE 60-Day Optional 10 CFR 60.73(a)(1)
MATERIALEXPOSURE 277?
8-Hr. Non-Emerency 10 CFR 50.72(b)(3)
Irivaflkspecf*fied st
,n Actuation AMt RTNE55FoR Duty terr J (i(CO Dgraded Consoo AmEG Other Unspecified Requirement (identify) 0THLPISPEýCE REaDrEMT (sselastcolumn)
Q (B) unanst-"dCondition AutA, v/' 10 (IF2,,,Jd)Lii)(
£ roe INFORMATION ONLY
-p 1(ivfA)
Specifid Syater Actuation A
DESCRIPTION Include: Systems effecWte, ectuations and their initiating signal., causes, effect of event on plant. actions taken or plasneo. etc. (Confltnue ornback)
On June 15, 2011, the site Vice President was notified that the 10 CFR 21 evlauation of Rosemount Model 710 Trip Units supplied under purchase order 10174727 determined that the reporting criteria of 10 CFR 21.21(d)(1) are met,.
During pre-installation testing ftwas found that 3 of 4 Rosemount Model 710 Trip units would not turn on:- The units were returned t Rosemount for failure analysis and it was determined that a resistor in the start-up circuit for the trip unitwas failed. This prevented t0 the u p Lin k I i i~ SLEI ung..,
aedb onq enginee rirng analysissom olw 11*.10 alpplicatilons forthe tri p unlit require t to energize to perform the associated safety functions. Therefore, the identified failure mechanism could have represented a substantial safety hazard IF the components had been installed, and the condition is reportable.
The condition had no actual safety consequences as the deficiency was identified during pria-installation testing and if Installed without pre-installation testing the system could not have passed post maintenance testing. The three failed units were returned to Rosemount.
This notification is made pursuant to 10 CFR 21(d)(ii)(3)(i).
NOTIFICATIONS YES NO WILL BE ANYTHING UNUSUAL OR 0 YES (ExpJain above NO NRC RESIDENT
/
NOT UNDERSTOOD?
STATE(S) i DID ALL SYSTEMS LOCAL Vo FUNCTION AS REQUIRED?
[
YES NO (Explain above)
OTHER GOV AGENCIES V
MODE OF OPERATION ESTIMATED ADlmoNAI INFO ON BPO(
MEDIA/PRESS RELEASE
/
UNTIL CORRECTED RESTART DATE:
D E $
NO NRC FORM 381 (12-2000)