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REACTOR PLANT EVENT NOTIFICATION WORKSHEET
ICR 202607-3150-002 · OMB 3150-0238 · Object 171015700.
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Document Metadata
| File Type | application/pdf |
|---|---|
| File Title | REACTOR PLANT EVENT NOTIFICATION WORKSHEET |
| Last Modified By | Designer 6.5 |
| File Modified | 2026-06-23 |
| File Created | 2026-06-12 |
| Conversion State | complete |
Extracted Text
Page NRC FORM 361 (MM-DD-YYYY) U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER EXPIRES: (MM/DD/YYYY) APPROVED BY OMB: NO. 3150-0238 REACTOR PLANT EVENT NOTIFICATION WORKSHEET 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 [email protected], 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 800-532-3469ǂ, BACKUPS - [1st ] 301-951-0550 or 800-449-3694ǂ, [2nd] 301-415-0550 and [3rd] 301-415-0553. ǂLicensees who maintain their own ETS are provided these telephone numbers. FAX - 301-816-5151, EMAIL - [email protected] Notification Time Facility or Organization Unit Name of Caller/Title Event Time & Zone Event Date Power/Mode (At Time of Event) Call Back # Power/Mode (At Time of Notification) 1-HR. NON-EMERGENCY 10 CFR 50.72(b)(1) EVENT CLASSIFICATION GENERAL EMERGENCY Safe S/D Capability AINA (v)(B) RHR Capability AINB (v)(C) Control of Rad Release AINC GEN/AAEC TS Deviation SITE AREA EMERGENCY SIT/AAEC 4-HR. NON-EMERGENCY 10 CFR 50.72(b)(2) ALERT ALE/AAEC (i) TS Required S/D ASHU (v)(D) Accident Mitigation AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/Asmt/Response ACOM 50.72 NON-EMERGENCY (see next columns) 10 CFR 20 RAD MATERIAL/EXPOSURE 10 CFR 21 DEFECT/NONCOMPLIANCE (xi) HFIT 10 CFR 73 SECURITY EVENT INFORMATION ONLY NNF APRE 60-DAY OPTIONAL 10 CFR 50.73(a)(1) OTHER UNSPECIFIED REQUIREMENT (IDENTIFY) 8-HR. NON-EMERGENCY 10 CFR 50.72(b)(3) CCCC 10 CFR 26 FITNESS FOR DUTY Offsite Notification ADEV (v)(A) Invalid Specified System Actuation AINV (ii)(A) Degraded Condition ADEG (ii)(B) Unanalyzed Condition AUNA NONR (iv)(A) Specified System Actuation AESF 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) NOTIFICATIONS YES NRC RESIDENT STATE(s) LOCAL NO WILL BE Anything Unusual or not understood? Yes (Explain above) No Did all systems function as required? Yes No (Explain above) OTHER GOV AGENCIES Mode of operations until corrected (if applicable) MEDIA/PRESS RELEASE Additional Information continued on next page? NRC FORM 361 (MM-DD-YYYY) Yes No Page NRC FORM 361 (MM-DD-YYYY) of U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET (Continued) EN # RADIOLOGICAL RELEASES: CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in event description) 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 Release Rate (Ci/sec) % T.S. Limit HOO Guide *State release path in description Total Activity (Ci) % T.S. Limit HOO Guide Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10 μCi/sec 0.01 Ci Particulate 1 μCi/sec 1 mCi Liquid (excluding tritium and dissolved noble gas) 10 μCi/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 Leak Start Date Time T. S. Limits Coolant Activity and Units: Sudden or Long-Term Development Primary Secondary List of Safety Related Equipment not Operational 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) NRC FORM 361 (MM-DD-YYYY)