ML24320A089
| ML24320A089 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 11/14/2024 |
| From: | Matthews S NextEra Energy Seabrook |
| To: | Hoc H, Nytko B Office of Nuclear Reactor Regulation |
| References | |
| Download: ML24320A089 (1) | |
Text
From:
Matthews, Shaun To:
Hoc, HOO X
Subject:
[External_Sender] Attn: Bill Nytko EN FORM 361 Seabrook GE Hitachi Relay.pdf Date:
Thursday, November 14, 2024 11:14:27 AM Attachments:
EN FORM 361 Seabrook GE Hitachi Relay.pdf Attn: Bill Nytko
PART 21 - CONTROL RELAY DEFECT NextEra Energy Seabrook LLC. makes the following notification under 10 CFR 21.21(d)(3)(i) of a defect found in a GE - Hitachi Relay, CR120B (Model #DD945E118P0060) during pre-installation bench testing. During bench testing, the relay failed to energize and transfer all associated contacts. The relay was purchased from GE - Hitachi (GEH) as QL-1, safety-related, GE CR-120B relays. All GE CR-120B relays that were purchased in the same batch as the failed relay were located and quarantined in order to be returned to GEH for forensic testing. NextEra Energy Seabrook, LLC has concluded that this defect constitutes a Substantial Safety Hazard (SSH). An SSH exists because the nature of the defect was such that, if installed in certain safety-related applications and failed, it would have prevented the fulfillment of a safety function. On November 12, 2024, the Seabrook site Vice President was notified of the requirement to report this event under 10 CFR 21.21. This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i), a written notification will be provided in accordance with 10 CFR 21.21(d)(3)(ii).
Because the defect was discovered prior to installation, there was no impact to safety-related equipment.
The NRC SRI has been informed.
NRC FORM 361 (08-15-2024)
U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER EXPIRES: 07/31/2026 APPROVED BY OMB: NO. 3150-0238 REACTOR PLANT EVENT NOTIFICATION WORKSHEET NRC FORM 361 (08-15-2024)
Page of Estimated burden per response to comply with this voluntary collection request: 30 minutes. The information provided will be used for evaluation of licensee event description, facility status and for input to the public website. Send comments regarding burden estimate to the FOIA, Library, and Information Collections Branch (T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by email to Infocollects.Resource@nrc.gov, and and the OMB reviewer at: OMB Office of Information and Regulatory Affairs, (3150-0238), Attn:
Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503. The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.
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 Name of Caller/Title Unit Facility or Organization Call Back #
Event Date Event Time & Zone Power/Mode (At Time of Event)
Power/Mode (At Time of Notification)
EVENT CLASSIFICATION 1-HR. NON-EMERGENCY 10 CFR 50.72(b)(1)
GENERAL EMERGENCY SITE AREA EMERGENCY ALERT UNUSUAL EVENT 50.72 NON-EMERGENCY 10 CFR 73 MATERIAL/EXPOSURE FITNESS FOR DUTY GEN/AAEC SIT/AAEC ALE/AAEC UNU/AAEC (see next columns)
D???
B???
HFIT TS Deviation (i) TS Required S/D (iv)(A) ECCS Discharge to RCS (iv)(B) RPS Actuation (scram)
(xi) Offsite Notification (ii)(A) Degraded Condition (ii)(B) Unanalyzed Condition (iv)(A) Specified System Actuation (v)(A) Safe S/D Capability (v)(B) RHR Capability (v)(C) Control of Rad Release (v)(D) Accident Mitigation (xii) Offsite Medical (xiii) Loss Comm/Asmt/Response Invalid Specified System Actuation ADEV 4-HR. NON-EMERGENCY 10 CFR 50.72(b)(2)
ASHU ACCS ARPS APRE 8-HR. NON-EMERGENCY 10 CFR 50.72(b)(3)
ADEG AUNA AESF AINA AINB AINC AIND AMED ACOM AINV 60-DAY OPTIONAL 10 CFR 50.73(a)(1)
OTHER UNSPECIFIED REQUIREMENT (IDENTIFY)
NONR NONR Event Description (Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.) (Continue on Page 2)
OTHER UNSPECIFIED REQMT.
(see last column)
INFORMATION ONLY NNF NOTIFICATIONS NRC RESIDENT YES NO WILL BE STATE(s)
LOCAL OTHER GOV AGENCIES MEDIA/PRESS RELEASE Anything Unusual or not understood?
Did all systems function as required?
Mode of operations until corrected (if applicable)
Yes (Explain above)
No Yes No (Explain above)
Additional Information continued on next page?
Yes No 57424 1
1 1058 EST Shaun Matthews/Engineering Analyst 1
NEXTERA ENERGY SEABROOK, LLC 305-394-7454 10/01/2024 0738 EDT 99/1 100/1 10 CFR 21.21(d)(3)(i)
PART 21 - CONTROL RELAY DEFECT NextEra Energy Seabrook LLC. makes the following notification under 10 CFR 21.21(d)(3)(i) of a defect found in a GE - Hitachi Relay, CR120B (Model
- DD945E118P0060) during pre-installation bench testing. During bench testing, the relay failed to energize and transfer all associated contacts. The relay was purchased from GE - Hitachi (GEH) as QL-1, safety-related, GE CR-120B relays. All GE CR-120B relays that were purchased in the same batch as the failed relay were located and quarantined in order to be returned to GEH for forensic testing. NextEra Energy Seabrook, LLC has concluded that this defect constitutes a Substantial Safety Hazard (SSH). An SSH exists because the nature of the defect was such that, if installed in certain safety-related applications and failed, it would have prevented the fulfillment of a safety function. On November 12, 2024, the Seabrook site Vice President was notified of the requirement to report this event under 10 CFR 21.21. This is a non-emergency notification required by 10 CFR 21.21(d)(3)(i), a written notification will be provided in accordance with 10 CFR 21.21(d)(3)(ii).
Because the defect was discovered prior to installation, there was no impact to safety-related equipment.
The NRC SRI has been informed.
1
NRC FORM 361 (08-15-2024)
U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Continued)
NRC FORM 361 (08-15-2024)
Page of EN #
Liquid Release Gaseous Release Unplanned Release Planned Release Ongoing Terminated Monitored Unmonitored Offsite Release T.S. Exceeded RM Alarms Areas Evacuated Personnel Exposed or Contaminated Offsite Protection Actions Recommended
- State release path in description Release Rate (Ci/sec)
% T.S. Limit HOO Guide Total Activity (Ci)
% T.S. Limit HOO Guide Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 Ci/sec 0.01 Ci Particulate 1 Ci/sec 1 mCi Liquid (excluding tritium and dissolved noble gas) 10 Ci/min 0.1 Ci Liquid (tritium) 0.2 Ci/min 5 Ci TOTAL Plant Stack Condenser/Air Ejector Main Steam Line SG Blowdown Other RAD Monitor Readings Alarm Setpoints
% T.S. Limit (If applicable)
RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered in event description)
Location of the Leak (e.g., SG #, valve, pipe, etc.)
Leak Rate Units: gpm/gpd T. S. Limits Sudden or Long-Term Development Leak Start Date Time Coolant Activity and Units:
Primary Secondary List of Safety Related Equipment not Operational RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in event description)
Event Description (Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.) (Continued from Page 1) 57424