ML22305A515

EN 56192 - Grand Gulf Nuclear Station Re Elevation Outer Containment Personnel Airlock Door Failed Its Technical Specification Leakage Test

ML22305A515
Person / Time
Site:	Grand Gulf
Issue date:	02/22/2022
From:	Hardy J Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
56192
Download: ML22305A515 (2)

Text

PAGE 1 OF 2 NRC FORM 361 U.S. U.S. NUCLEAR NUCLEAR REGULATORY REGULATORY COMMISSION COMMISSION APPROVED BY OMB: NO. 3150-0238 EXPIRES: 10/31/2022 (02-2020) OPERATIONS CENTER 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 REACTOR PLANT EVENT input to the public website. Send comments regarding burden estimate to the Information Services Branch (T-6 A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-NOTIFICATION WORKSHEET mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0238), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

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 #

Grand Gulf Nuclear 1 Jeff Hardy / Regulatory 1-601-437-2103 Station Assurance Mgr.

Event Time & Zone Event Date Power/Mode (At Time of Event) Power/Mode (At Time of Notification) 1826 CT February 22, 2021 100% / MODE 1 86% / MODE 1 EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe S/D Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SIT/AAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC 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 50.72 NON-EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss Comm/Asmt/Response ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Offsite Notification APRE 60-Day Optional 10 CFR 50.73(a)(1)

MATERIAL/EXPOSURE B???? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3) Invalid Specified System Actuation AINV FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identify)

OTHER UNSPECIFIED REQMT. (see last column) (ii)(B) Unanalyzed Condition AUNA 10 CFR Part 21 NONR INFORMATION ONLY NNF (iv)(A) Specified System Actuation AESF NONR DESCRIPTION Event Description (Include: Systems affected, actuations and their initiating signals, causes, effect of event on plant, actions taken or planned, etc.) (Continued on Page 2)

On February 22, 2021 while in Mode 1 and at 100% power, Grand Gulf Nuclear Station (GGNS) identified through surveillance testing that the 208' elevation outer containment personnel airlock door failed its Technical Specification leakage test. Analysis indicated that the airlock equalizing valves were leaking due to lack of lubrication during installation.

Subsequent analysis determined that the lubrication was to have been performed during a vendor's qualification /

dedication process. GGNS completed a Substantial Safety Hazard Evaluation and determined that the failure to lubricate the valve components constituted a substantial safety hazard.

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.

NOTIFICATIONS YES NO WILL BE Anything Unusual or not understood? Yes (Explain above) No NRC RESIDENT Did all systems function as Yes No (Explain above) required?

STATE(s) Mode of operations until corrected MODE 1 LOCAL (if applicable)

OTHER GOV AGENCIES Additional Information continued on next page? YES NO MEDIA/PRESS RELEASE NRC FORM 361 (12-2019) Continued on next page

ADDITIONAL INFORMATION PAGE 2 OF 2 NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION (02-2020) 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 *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 uCi/sec 0.01 Ci Particulate 1 uCi/sec 1 mCi Liquid (excluding tritium and 10 uCi/min 0.1 Ci dissolved noble gases)

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 Primary Secondary and Units:

List of Safety Related Equipment or 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)