ML26048A131
| ML26048A131 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/26/2023 |
| From: | Beverly Smith Entergy Operations |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 56641 | |
| Download: ML26048A131 (0) | |
Text
PAGE 1 OF 1 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB:
NO. 31 50-0238 EXPIRES:
07/31/2023 (07.01.2023)
OPERATIONS CENTER REACTOR PLANT EVENT Pg yCr.
725 r
g A
238 NOTIFICATION WORKSHEET q
d d
30 8
rb EN NRC OPERATIONS TELEPHONE NUMBERS: PRIMARY-301-816-5100 or 800-532-3469*, BACKUPS
- [1st] 301-951-0550 or 800-449-3694*,
[2nd] 301-415-0550 and [3rd] 301-415-0553. *Licensees who maintain their own ETS are provided these telephone numbers.
FAX
- 301-816-5151, EMAIL
- hoo.hoc@nrc.gov Notification Time Facility or Organization Unit Name of Caller/Title CALL BACK #
River Bend 1
- 7.,.,
(225) 381 -4524 r
/
C..)
Station
,,c.i.-..
/
1-Event Time & Zone Event Date Power/Mode (At Time of Event)
Power/Mode (At Time of Notification) 15:14 CDT 7/18/23 100%/Mode 1 100%/Mode 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1)
LI (v)(A)
Safe S,D Capability AINA LI GENERAL EMERGENCY GEN/AAEC LI T5 Deviation ADEV LI (v)(B)
RHR Capability AINB LI SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2)
LI (v((C)
Control of Rad Release AINC
[] ALERT ALE/AAEC LI (i)
TS Required S/D ASHU F]
(vl(D(
Accident Mitigation AIND LI UNUSUAL EVENT UNU/AAEC LI liv)(A)
ECCS Discharge to RCS ACCS LI (xv)
Of/site Medical AMED F] 50.72 NON-EMERGENCY (see next columns) 1J (iv)(B)
ARPS
[]
(xiii)
Loss Comm/AsmtlResponse ACOM F] PHYSICAL SECURITY (7371)
DDDD F]
(xi(
Of/site Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)
LI MATERIAL/EXPOSURE B????
8-Hr. Non-Emergency 10 CFR 50.72(b)(3)
LI Invalid Specified System Actuation AINV LI FITNESS FOR DUTY HFIT LI (ii)(A(
Degraded Condition ADEG OTHER UNSPECIFIED REQUIREMENTS (IDENTIFY)
OTHER UNSPECIFIED REQMT.
Isee lasI columnl LI (if/B)
Unanalyzed Condition AUNA 10 CFR 21.21 (d)(3)(i)
NONR LI INFORMATION ONLY NNF LI (iv((A)
Specified System Actuation AESF LI NONR Event Description (Include: Systems affected, actualions and their initiating signals. causes, effect of event on plant, actions taken or planned. etc.) (Continued on Page 2)
On July 18, 2023 while in Mode 1 and at 100% power, River Bend Station completed an internal Part 21 evaluation on a Motor Driven Relay (MDR) that tailed preinstallation testing. The evaluation concluded that a failure to comply that could create a substantial safety hazard existed.
MDR 66-4 serial number 29 supplied by Curtiss-Wright Nuclear under Purchase Order 10552971 failed preinstallation testing. A failure analysis was performed on the relay which determined that the failure was due to buildup of corrosion between the rotor and relay core.
The relay was planned for use in the Remote Shutdown System.
The NRC Resident has been notified.
This is a non-emergency notification required by 10 CFR 21.21 (d)(3)(i).
A written notification will be provided within 30 days.
WILL NOTIFICATIONS YES NO BE Anything Unusual or not understood?
El Yes (Explain above)
No NRC RESIDENT El El STATE(s)
El El Did all systems function as required?
Yes El No (Explain above)
LOCAL El El OTHER GOV AGENCIES El
[1 Mode of operations until corrected it apphcaixtel Mode 1 MEDIA/PRESS RELEASE El El Additional Information continued on next page?
El Yes No NRC FORM 361 (07-01-2023/