IR 05000416/2020004
ML21034A563 | |
Person / Time | |
---|---|
Site: | Grand Gulf ![]() |
Issue date: | 02/03/2021 |
From: | Jason Kozal Division of Reactor Safety IV |
To: | Franssen R Entergy Operations |
References | |
IR 2020004 | |
Download: ML21034A563 (29) | |
Text
February 3, 2021
SUBJECT:
GRAND GULF NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000416/2020004
Dear Mr. Franssen:
On December 31, 2020, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Grand Gulf Nuclear Station. On January 13, 2021, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
No NRC-identified or self-revealing findings were identified during this inspection.
A licensee-identified violation which was determined to be of very low safety significance is documented in this report. We are treating this violation as a non-cited violation (NCV)
consistent with Section 2.3.2 of the Enforcement Policy.
If you contest the violation or the significance of the violation documented in this inspection report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; the Director, Office of Enforcement; and the NRC Resident Inspector at Grand Gulf Nuclear Station. This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Jason W. Digitally signed by Jason W. Kozal Kozal Date: 2021.02.03 14:19:15 -06'00'
Jason W. Kozal, Chief Reactor Projects Branch C Division of Reactor Projects Docket No. 05000416 License No. NPF-29
Enclosure:
As stated
Inspection Report
Docket Number: 05000416 License Number: NPF-29 Report Number: 05000416/2020004 Enterprise Identifier: I-2020-004-0004 Licensee: Entergy Operations, Inc.
Facility: Grand Gulf Nuclear Station Location: Port Gibson, MS Inspection Dates: October 1, 2020, to December 31, 2020 Inspectors: D. Antonangeli, Health Physicist B. Baca, Health Physicist N. Greene, Senior Health Physicist M. Hayes, Operations Engineer S. Hedger, Emergency Preparedness Inspector J. O'Donnell, Senior Health Physicist E. Simpson, Health Physicist T. Steadham, Senior Resident Inspector M. Thomas, Senior Resident Inspector Approved By: Jason W. Kozal, Chief Reactor Projects Branch C Division of Reactor Projects Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Grand Gulf Nuclear Station, in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A licensee-identified, non-cited violation is documented in report Section 71124.0
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
None.
PLANT STATUS
Grand Gulf Nuclear Station, Unit 1, began this inspection period at 83 percent power. On November 6, 2020, a reactor scram occurred from 84 percent power following a sensed low primary water system coolant flow. This system provides cooling to components related to the main generator. Following modifications to the primary coolant flow instrument sensing lines and turbine control valve actuators, the unit was restarted on November 29, 2020. During startup, operators shutdown the plant from approximately 0 percent power on November 30, 2020, to conduct repairs on a condensate booster min flow valve, which had failed. Following repairs, the unit was restarted on December 2, 2020, and reached 98 percent power on December 6, 2020. On December 7, 2020, reactor power was reduced to 70 percent power for a rod pattern adjustment. On December 11, 2020, a reactor scram occurred following a low water level in the primary water system tank. The unit was restarted on December 12, 2020, following modifications to the primary water system. The unit was returned to 100 percent power on December 17, 2020, where it remained at or near for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
Starting on March 20, 2020, in response to the National Emergency declared by the President of the United States on the public health risks of the Coronavirus Disease 2019 (COVID-19),resident inspectors were directed to begin telework and to remotely access licensee information using available technology. During this time, the resident inspectors performed periodic site visits each week; conducted plant status activities as described in IMC 2515, Appendix D, Plant Status; observed risk-significant activities; and completed on-site portions of IPs. In addition, resident and regional baseline inspections were evaluated to determine if all or portions of the objectives and requirements stated in the IP could be performed remotely. If the inspections could be performed remotely, they were conducted per the applicable IP. In some cases, portions of an IP were completed remotely and on-site. The inspections documented below met the objectives and requirements for completion of the IP.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Division 2, 125 VDC lineup on October 19, 2020
- (2) Residual heat removal subsystem B during subsystem A testing on October 26, 2020
- (3) High pressure core spray partial alignment on November 9, 2020
- (4) Standby gas treatment system B alignment while the opposite train was undergoing maintenance on November 13, 2020
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a walkdown and performing a review to verify program compliance, equipment functionality, material condition, and operational readiness of the following fire areas:
- (1) Division 2 standby service water pump house on October 6, 2020
- (2) Outside control building, standby diesel generator building, fire pump house, and both standby service water pump houses, Fire Zone YARD, on October 6, 2020
- (3) Auxiliary building, Elevations 166 feet and 174 feet above main steam tunnel, Fire Zones 1A402 and 1A404, on December 10, 2020
71111.11A - Licensed Operator Requalification Program and Licensed Operator Performance
Requalification Examination Results (IP Section 03.03) (1 Sample)
- (1) The inspectors reviewed and evaluated the licensed operator examination failure rates for the requalification annual operating exam administered on November 9 through December 10, 2020.
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the following planned and emergent work activities to ensure configuration changes and appropriate work controls were addressed:
- (1) Condition Report CR-GGNS-2020-10382, equipment out of service model appears to be incorrect when removing standby service water inlet to residual heat removal heat exchanger valve from service on October 20, 2020
- (2) Maintenance risk assessment with moisture separator reheater drain tank level oscillations and primary water flow perturbations on December 11, 2020
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (4 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
- (1) Condition Report CR-GGNS-2020-10213, unexpected relay trip during Division 3 testing on October 5, 2020
- (2) Condition Report CR-GGNS-2020-12198, elevated drywell leakage and safety relief valve tailpipe weeping on December 29, 2020
- (3) Condition Report CR-GGNS-2020-12059, NRC-identified scaffolding within 2-inch rattle space of Division 2 emergency diesel generator on December 29, 2020
- (4) Condition Report CR-GGNS-2020-12062, overthrust condition with control room air conditioner service water return valve P41F189 on December 29, 2020
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Work Order 52894197, standby service water to residual heat removal heat exchanger A inlet valve test following maintenance on October 21, 2020
- (2) Work Order 543019, replace recirculation pump A suction temperature element on November 19, 2020
- (3) Work Order 553442, drywell cooler damper actuator rebuild on November 19, 2020
- (4) Work Order 549948, recirculation flow control valve A rotary variable differential transformer replacement on November 19, 2020
- (5) Work Order 550987, flush drywell cooler line on November 30, 2020
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (2 Samples)
- (1) The inspectors evaluated the licensee's response to Forced Outage 23-03 from November 6, 2020, to December 3, 2020.
- (2) The inspectors evaluated the licensee's response to Forced Outage 23-04 from December 11, 2020, to December 13, 2020.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Work Order 52905300-01, Procedure 06-IC-1E31-A-1004, Attachment I, reactor core isolation cooling room high temperature calibration on October 19, 2020
- (2) Increased drywell unidentified leakage monitoring on December 21, 2020
- (3) Work Order 52935765, perform Procedure 06-OP-1P41-Q-0006-01, high pressure core spray service water pump and valve operability test on December 31, 2020
71114.02 - Alert and Notification System Testing
Inspection Review (IP Section 02.01-02.04) (1 Sample)
- (1) The inspectors evaluated the maintenance and testing of the alert and notification system from November 3, 2018, to November 13, 2020.
71114.03 - Emergency Response Organization Staffing and Augmentation System
Inspection Review (IP Section 02.01-02.02) (1 Sample)
- (1) The inspectors evaluated the readiness of the Emergency Preparedness Organization from November 3, 2018, to November 13, 2020. Inspectors also evaluated the licensee's ability to staff their emergency response facilities in accordance with emergency plan commitments.
71114.04 - Emergency Action Level and Emergency Plan Changes
Inspection Review (IP Section 02.01-02.03) (1 Sample)
- (1) The inspectors evaluated the following emergency plan and emergency action level revisions:
- Emergency Plan, Revision 79, submitted on October 29, 2019
- Emergency Plan, Revision 81, submitted on November 30, 2020
- Emergency Action Level bases document, submitted on November 30, 2020 In addition, the inspectors evaluated the 10 CFR 50.54(q) emergency plan change process and practices between November 3, 2018, and November 13, 2020. This involved review of licensee screening and evaluation documentation. The reviews of the emergency plan and emergency action level revisions, in addition to the change process documentation, do not constitute NRC approval.
71114.05 - Maintenance of Emergency Preparedness
Inspection Review (IP Section 02.01 - 02.11) (1 Sample)
- (1) The inspectors evaluated the maintenance of the emergency preparedness program between November 3, 2018, and November 13, 2020. The evaluation reviewed the conduct of drills and exercises, licensee audits and assessments, and the maintenance of equipment important to emergency preparedness.
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)
(1 Sample)
- (1) Yellow team drill on October 28,
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Walkdowns and Observations (IP Section 03.01) (10 Samples)
The inspectors evaluated the following radiation detection instrumentation during plant walkdowns:
- (1) Personnel contamination monitoring equipment at the plant 133 feet access control point: five Canberra ARGOS-5AB units
- (2) Personnel monitoring equipment at the plant 133 feet access control point: two Canberra GEM-5 units
- (3) Small article monitoring equipment at the plant 133 feet access control point: three Canberra Cronos-4 units
- (4) Plant area radiation monitor: auxiliary building sample station monitor 1D21K616
- (5) Plant area radiation monitor: hydrogen sample panel A, 1D21K618
- (6) Plant area process radiation monitor: fuel handling area 1D21K6124
- (7) Radiation monitoring equipment: CHP-CR-272, Ludlum Model 12 count-rate meter
- (8) Radiation monitoring equipment: CHP-DR-263, Ludlum Model 9-3 ion chamber
- (9) Radiation monitoring equipment: CHP-TEL-144, Mirion Telepole II
- (10) Radiation monitoring equipment: CHP-MF-136, Ludlum Model 12-4 (neutron) survey meter
Calibration and Testing Program (IP Section 03.02) (13 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Ludlum Model 9-3, RBS-EPI-007, 11/17/2020
- (2) Eberline AMS-4, CHP-AMS-D067, 11/17/2020
- (3) RADeCO H-810 air sampler, CHP-ASA-027, 11/07/2019
- (4) Canberra Argos, ARGOS-012, 08/13/2020
- (5) Canberra Cronos, CRONOS-001, 09/02/2020
- (6) Canberra Gem-5, GEM-002, 07/07/2020
- (7) Main Steam Line High Radiation Monitor, 1D17-K610B, 05/19/2020
- (8) Main Steam Line High Radiation Monitor, 1D17-K610C, 07/17/2019
- (9) Containment High Range Radiation Monitor, 1D21K648A, 10/22/2019
- (10) Containment High Range Radiation Monitor, 1D21K648D, 04/25/2019
- (11) Radwaste Instrument Rack Area Radiation Monitor, 1D21K642, 04/24/2019
- (12) Solid Radwaste Area Radiation Monitor, 1D21K647, 02/05/2020
- (13) Standby Gas Treatment System B Ventilation System Particulate Iodine Noble Gas (SPING) Monitor, 1D17P024 and 1D17P025, 10/02/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (2 Samples)
- (1) Work Order 52866647, Containment Building Vent Radiation Monitor, 1D17-K603, 02/06/2020
- (2) Work Order 52860275, Liquid Radwaste Effluent Radiation Monitor, SD17-K606, 01/16/2020
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (4 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
- (1) Unit 1 standby gas treatment system
- (2) Unit 1 off-gas and radwaste building ventilation system
- (3) Unit 1 turbine building ventilation system
- (4) Unit 1 liquid radwaste treatment system
Sampling and Analysis (IP Section 03.02) (3 Samples)
The inspectors evaluated effluent samples, sampling processes and compensatory samples, as available, for the following systems:
- (1) On November 17, 2020, the inspectors observed the weekly effluent sampling of particulate and iodine for the radwaste, turbine, and containment building ventilation systems using Procedure 06-CH-1D17-W-0017, "Gaseous Release Points, Iodine, Tritium, and Particulates."
- (2) On November 18, 2020, the inspectors observed the pre-release liquid effluent sampling of equipment drain sample tank A using Procedure 06-CH-SG17-P-0041, "Radwaste Pre-Release
Analysis.
"
- (3) On November 19, 2020, the inspectors observed the turbine building monthly isotopic gas sampling using Procedure 06-CH-1D17-M-0005, "Building Ventilation Exhaust Gaseous Isotopic," and the turbine building monthly tritium sampling using Procedure 06-CH-1D17-M-0003, "Building Ventilation Gaseous Tritiums."
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) Liquid Waste Batch Permits: 2018164, 2019040, 2019051, 2020001, 2020089,
===2020148, 2020149
- (2) Continuous Gaseous Waste Permits: Containment Building Ventilation (2019012, 2019019); Fuel Handling Area Ventilation (2019020); Radwaste Building Ventilation (2018157, 2019036); Turbine Building Ventilation (2019017, 2019067)
Abnormal Discharges (IP Section 03.04) ===
The inspectors evaluated the following abnormal discharges:
- (1) Turbine roof hatch release, December 5, 2019, through December 6, 2019; Condition Report CR-GGNS-2019-10085
71124.07 - Radiological Environmental Monitoring Program
Environmental Monitoring Equipment and Sampling (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated environmental monitoring equipment and observed collection of environmental samples.
Radiological Environmental Monitoring Program (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the implementation of the licensees radiological environmental monitoring program.
GPI Implementation (IP Section 03.03) (1 Sample)
- (1) The inspectors evaluated the licensees implementation of the Groundwater Protection Initiative program to identify incomplete or discontinued program elements.
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, and
Transportation
Radioactive Material Storage (IP Section 03.01)
- (1) The inspectors evaluated the licensees performance in controlling, labelling, and securing radioactive materials.
- (2) The inspectors evaluated the following sealed sources:
- 92-495, Ra-226
- 92-581, Am-241/Be
- 92-582, Am-241/Be
- 92-583, Cs-137
- 92-587, Cs-137
- 92-588, Cs-137
- 93-087, Cs-137
- 93-088, Cs-137
- (3) The inspectors evaluated the following radioactive material storage areas:
- Radwaste Building
- Southeast Yard
- Radwaste Pad
- Northwest Laydown Area
Radioactive Waste System Walkdown (IP Section 03.02 (2 Samples)
- (1) The inspectors walked down accessible portions of the solid radioactive waste systems and evaluated system configuration and functionality.
- (2) The inspectors also walked down the radwaste control room to assess the operability of radwaste system equipment.
Waste Characterization and Classification (IP Section 03.03) (2 Samples)
- (1) The inspectors evaluated the licensees characterization and classification of radioactive waste.
- (2) The inspectors evaluated waste characterizations for the following types of packages:
- Dry active waste
- Mechanical filters
- Spent resin
- Irradiated hardware
Shipment Preparation (IP Section 03.04) (1 Sample)
- (1) The inspectors observed a shipment containing radioactive material to determine if it was prepared according to the requirements contained in GGN-2020-1110; UN2912, Radioactive Material, LSA-I, 7; dated November 19, 2020.
Shipping Records (IP Section 03.05) (5 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
- (1) GGN-2018-1201; UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, RQ; Irradiated hardware; 12/11/2018
- (2) GGN-2019-0101; UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, RQ; Irradiated hardware; 01/09/2019
- (3) GGN-2019-0202; UN3321, Radioactive Material, LSA-II, 7; Dewatered resin; 02/07/2019
- (4) GGN-2019-0313; UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, RQ; TriNuke Filters; 04/03/2019
- (5) GGN-2020-0518; UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, RQ; Dewatered resin; 06/04/2020
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
EP01: Drill/Exercise Performance (IP Section 02.12) ===
- (1) January 1, 2019, through September 30, 2020
EP02: ERO Drill Participation (IP Section 02.13) (1 Sample)
- (1) January 1, 2019, through September 30, 2020
EP03: Alert & Notification System Reliability (IP Section 02.14) (1 Sample)
- (1) January 1, 2019, through September 30, 2020
MS09: Residual Heat Removal Systems (IP Section 02.08) (1 Sample)
- (1) October 1, 2019, through September 30, 2020
MS10: Cooling Water Support Systems (IP Section 02.09) (1 Sample)
- (1) October 1, 2019, through September 30, 2020
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program for potential adverse trends in troubleshooting practices that might be indicative of a more significant safety issue.
Annual Follow-up of Selected Issues (IP Section 02.03) (1 Sample)
The inspectors reviewed the licensees implementation of its corrective action program related to the following issues:
- (1) Condition Report CR-GGNS-2020-00915 on November 30, 2020
71153 - Followup of Events and Notices of Enforcement Discretion Personnel Performance (IP Section 03.03)
- (1) On December 1, 2020, the inspectors evaluated personnel performance related to the following plant scrams: May 25, August 8, August 24, and November 6, 2020.
- (2) On December 1, 2020, the inspectors evaluated personnel performance related to the June 16, 2020, unplanned down power due to reactor feed pump B high vibrations.
- (3) On December 1, 2020, the inspectors evaluated personnel performance during the July 18, 2020, unplanned down power due to the high-pressure turbine control valve A electrohydraulic control leak.
- (4) On December 1, 2020, the inspectors evaluated personnel performance during the August 8, 2020, reactor water Level 3 scram following manual scram recovery.
- (5) The inspectors evaluated personnel performance during the April 16, 2020, inadvertent low-pressure coolant injection.
- (6) On December 14, 2020, the inspectors evaluated personnel performance during the December 11, 2020, unplanned reactor scram.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71124.08 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Technical Specification 5.4.1(a) requires, in part, that written procedures shall be implemented covering applicable procedures recommended in Regulatory Guide 1.33, "Quality Assurance Program Requirements (Operation)," Revision 2, Appendix A, February 1978. Section 7(e) of Regulatory Guide 1.33 covers Radiation Protection Procedures.
Contrary to the above, on April 24, 2020, the licensee failed to implement written procedures for radiation protection when they free released a temporary chiller with detectable radioactivity from the protected area, and subsequently shipped it offsite to a vendor without proper radiological controls. Specifically, the licensee failed to implement requirements in licensee Procedure EN-RP-121, "Radioactive Material Control," Revision 16.
On April 24, 2020, two temporary chillers that were used during the licensee's refueling outage activities were shipped offsite without proper surveys conducted by radiation protection (RP) staff. One of those temporary chillers, the larger one, contained detectable levels of radioactivity. The temporary chiller was previously identified as having detectable radioactivity via chemistry samples performed on April 8, 2020. These water samples were verified on April 17, 2020, and again, determined there were detectable amounts of radioactivity. At that time, RP staff instructed that labeling be placed on the system plant chillers and supportive equipment, but staff failed to complete these requirements.
Consequently, the equipment was not labeled as, "Potentially contaminated - Contact RP prior to breaching the system," before being stored away for any further use and to establish appropriate radiological controls. When the temporary plant chillers were shipped offsite, RP staff were not contacted and did not survey and frisk the temporary chillers prior to leaving the site. This resulted in free release of radioactive material from the licensee's protected area into the public domain.
Five days later, on April 29, 2020, RP staff discovered that the temporary chillers used to supplement the plant chill water system during the outage were no longer at the licensee's site when they questioned their location. RP staff understood that chemistry samples and surveys previously taken on these chillers identified low trace amounts (but detectable) of radioactivity, with contact dose rates of 0.1 millirem per hour; therefore, they immediately became concerned that the temporary chillers were not controlled as radioactive material.
They soon confirmed these two chillers were shipped offsite without appropriate radiological controls, as required.
Procedure EN-RP-121, "Radioactive Material Control," Revision 16, states, in part, the following:
- Section 5.2.1.1 - Items indicating the presence of radioactive material, other than naturally occurring, MUST be labeled in accordance with this procedure.
- Section 5.6.1 - For "Control and Release of Material," items may be considered for free release as long as ALL of the following criteria are met:
No detectable fixed activity above background, other than naturally occurring isotopes No detectable loose surface contamination No detectable/suspected internal contamination No detectable alpha contamination No radioactive labels or markings
- Section 5.9.1 - All materials leaving the protected area through the sally port may be evaluated prior to being removed from the protected area by completion of
12.
12 to Procedure EN-RP-121 essentially requires the licensee to evaluate/survey radioactive material prior to release, as authorized by RP staff.
Thus, the licensee failed to follow multiple procedural requirements when they did not label the radioactive temporary chiller, control it as radioactive material, failed to contact RP staff to evaluate/survey the temporary chiller prior to leaving the site, and free released it from the protected area. Upon discovery, the licensee conducted radiological surveys of the plant chiller system equipment and appropriately implemented radiological controls. The licensee identified 500 corrected counts per minute of fixed internal contamination on the larger temporary chiller that was free released offsite to a vendor.
As immediate corrective actions, the licensee contacted the vendor to which the uncontrolled material was delivered and sent a licensee representative to retrieve the items, conducted surveys of the plant chiller system, and reviewed and updated their procedures to enhance the requirements.
Using NRC Inspection Manual Chapter 0612, Appendix E, "Examples of Minor Issues," the inspectors determined that the performance deficiency was more than minor because it was similar to Example 6.a, in which the licensee failed to survey the radioactive material, as required, resulting in a failure to adequately control the release of radioactive material from the site.
Significance/Severity: Green. The inspectors determined that the finding was of very low safety significance (Green) because although it involved a failure in radioactive materials control and was transported from the site, surface contamination levels were less than 5 times any limits and there was no radiation exposure above 1 percent of any occupational or public dose limit (less than
.005 rem).
Corrective Action References: Condition Report CR-GGNS-2020-05694 Observation: Semiannual Trend Review 71152 Through a review of recent issues documented in the licensees corrective action program, the inspectors noted a potential trend related to less than thorough troubleshooting practices at the site. The inspectors noted that these practices unnecessarily challenged plant staff in responding to multiple equipment issues. The following examples demonstrate this potential trend:
1. In the summer of 2020, the licensee wrote multiple condition reports detailing failures of
the control room air conditioner compressor B (Condition Reports CR-GGNS-2020-08197 and CR-GGNS-2020-08349), for which the NRC issued a Green, non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, in Integrated Inspection Report 05000416/2020003 (ADAMS Accession No. ML20302A448). The inspectors found, in this instance, that a failure to adequately troubleshoot the direct cause of the compressor trip such that there was high confidence that the direct cause of the trip was identified and corrected prior to returning it to service, led to the licensee declaring the component operable when it, in fact, would not have met safety function requirements as evidenced by its subsequent failure a day later.
2. As documented in Integrated Inspection Report 05000416/2019004 (ADAMS Accession
No. ML20044F733), the inspectors identified a non-cited violation of 10 CFR Part 50, Appendix B, Criterion XVI, when the licensee failed to correct a condition adverse to quality related to the 208-foot elevation containment airlock door. Specifically, the inspectors identified that Condition Reports CR-GGNS-2016-03721, CR-GGNS-2018-02927, CR-GGNS-2018-03251, CR-GGNS-2018-03261, CR-GGNS-2018-07849, CR-GGNS-2018-08613, and CR-GGNS-2019-03109 were all closed with less than thorough troubleshooting. This lack of effective troubleshooting allowed the underlying condition to go undiagnosed and unresolved as described in the violation.
3. In 2020, the inspectors identified eight condition reports (Condition Reports
CR-GGNS-2020-00872, CR-GGNS-2020-04116, CR-GGNS-2020-05780, CR-GGNS-2020-05784, CR-GGNS-2020-06048, CR-GGNS-2020-07317, CR-GGNS-2020-08156, CR-GGNS-2020-08734) detailing failures/issues of security Door OC708. In most of these condition reports, an issue was identified with the door handle sticking or otherwise not working properly causing the door to not secure properly. In Condition Report CR-GGNS-2020-08754, the inspectors identified potential issues with long-standing degradation of this security door. As evidenced by the repetitive failures of this door, it appears that less than thorough troubleshooting practices for correcting the cause has led to continual challenges.
4. Condition Reports CR-GGNS-2020-09739, CR-GGNS-2020-09756, and CR-GGNS-2020-09797 document an issue with reactor recirculation flow control valve A unexpectedly changing position. The licensees initial troubleshooting led them to believe there was an issue with the position indicator on the valve itself. Upon replacement of the position indicator, the licensee continued to observe issues with the flow controller. The licensee replaced another component within the control system, which appeared to have corrected the subsequent issue; however, while monitoring system response, the licensee observed continued issues with the controller necessitating additional troubleshooting and corrective maintenance.
5. Condition Reports CR-GGNS-2020-05268, CR-GGNS-2020-05270, CR-GGNS-2020-05404, CR-GGNS-2020-05405, and CR-GGNS-2020-05427 document an issue with the standby gas treatment system drawdown surveillance not meeting acceptance criteria. While the licensees initial troubleshooting did identify leaking door seals and drains between rooms that could have contributed to the failed drawdown test, it did not identify the direct cause of the failure, which was containment configuration during this surveillance test.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On November 19, 2020, the inspectors presented the emergency preparedness program inspection technical debrief inspection results to Mr. M. Lewis, Manager, Emergency Preparedness, and other members of the licensee staff.
- On November 19, 2020, the inspectors presented the public radiation safety inspection results to Mr. R. Franssen, Site Vice President, and other members of the licensee staff.
- On December 16, 2020, the inspectors presented the emergency preparedness program inspection telephonic exit inspection results to Mr. B. Wertz, General Manager of Plant Operations and other members of the licensee staff.
- On January 13, 2021, the inspectors presented the integrated inspection results to Mr. R. Franssen, Site Vice President, and other members of the licensee staff.
THIRD PARTY REVIEWS The inspectors reviewed the most recently issued Institute of Nuclear Power Operations report during the inspection period.
DOCUMENTS REVIEWED
Inspection Type Designation Description or Title Revision or
Procedure Date
71111.04 Corrective Action CR-GGNS- 2020-11173, 2020-11193, 2020-11312
Documents
71111.04 Drawings E0121-09 Summary of Relay Setting 480V Load Center Engineered 6
Safety Feature 16BB4, 16BB5, & 16BB6
71111.04 Drawings E1020 One Line Meter and Relay Diagram 480V bus 15BA6 and 11
16BB6
71111.04 Drawings E1023 One Line Meter and Relay Diagram 125V DC bus 11DA, 38
11DB, and 11DC
71111.04 Drawings E1026 One Line Meter and Relay Diagram 120V Engineered Safety 14
Feature Uninterruptible Power Supply
71111.04 Drawings M-1086 P & I Diagram High Pressure Core Spray System 35
71111.04 Drawings M-1102A P & I Diagram Standby Gas Treatment 24
71111.04 Drawings M-1102B P & I Diagram Standby Gas Treatment 6
71111.04 Drawings M-1469 HV & AC Auxiliary Building Elevation 208'-110" Area 9 25
71111.04 Procedures 04-1-01-E22-1 High Pressure Core Spray System 130
71111.04 Procedures 04-1-01-L11-1 Plant DC Systems 131
71111.04 Procedures 04-1-01-L62-1 Static Inverters Systems 54
71111.04 Procedures 04-1-01-T48-1 Standby Gas Treatment 39
71111.04 Procedures DCP 82-4110 Addition of Opposed Blade Volume Dampers to the Standby 0
Gas Treatment System
71111.04 Work Orders WO 52849113
71111.13 Corrective Action CR-GGNS- 2020-10382
Documents
71111.13 Miscellaneous MCR-GG-6796
71111.13 Miscellaneous MCR-GG-6797
71111.13 Procedures EN-DC-151 PRA Maintenance and Update 8
71111.15 Corrective Action CR-GGNS- 2020-10213, 2020-10258, 2020-12059, 2020-12062, 2020-
Documents 12198
71111.19 Procedures 06-OP-1P41-Q- Standby Service Water Loop A Valve and Pump Operability 130
0004 Test
71111.19 Work Orders WO 543019, 549948, 550987, 553442, 52894197
71111.22 Corrective Action CR-GGNS- 2020-11531
Inspection Type Designation Description or Title Revision or
Procedure Date
Documents
71111.22 Procedures 06-IC-1E31-A- RCIC Equipment Room High Temperature Calibration 106
1004, Channel A
I
71111.22 Work Orders WO 52905300, 52935765
71114.02 Miscellaneous GIN No. 2017- Grand Gulf FEMA REP 10 Report 03/06/2017
00031
71114.02 Procedures 01-S-10-3 Emergency Planning Department Responsibilities 24
71114.03 Miscellaneous File No. GIN2018- Quarterly Off-Hours Unannounced Everbridge Test 01/08/2019
226
71114.03 Miscellaneous File No. GIN2019- Quarterly Off-Hours Unannounced Everbridge Test, 03/25/2019
00056 Notification ID: 315839010242543
71114.03 Miscellaneous File No. GIN2019- Quarterly Off-Hours Unannounced Everbridge Test - 2nd 06/14/2019
00100 Quarter 2019
71114.03 Miscellaneous File No. GIN2019- Quarterly Off-Hours Unannounced Everbridge Test - 3rd 08/15/2019
00145 Quarter 2019
71114.03 Miscellaneous File No. GIN2019- Quarterly Off-Hours Unannounced Everbridge Test - 4th 12/18/2019
268 Quarter 2019
71114.03 Miscellaneous File No. GIN2020- Quarterly Off-Hours Unannounced Everbridge Test - 1st 03/30/2020
00078 Quarter 2020
File No. GIN2020- Quarterly Off-Hours Unannounced Everbridge Test - 2nd 06/20/2020
00108 Quarter 2020
71114.03 Miscellaneous File No. GIN2020- Quarterly Off-Hours Unannounced Everbridge Test - 3rd 08/28/2020
00152 Quarter 2020
71114.03 Procedures 10-S-01-6 Notification of Offsite Agencies and Plant On-Call Emergency 58
Personnel
71114.03 Procedures EN-EP-310 Emergency Response Organization Notification System 9
71114.04 Miscellaneous Attachment 1, Procedure/Document Number: 10-S-02-1, Revision: 21, 02/20/2020
10CFR50.54(q)(2) Facility: GGNS
Review
71114.04 Miscellaneous Attachment 1, Procedure/Document Number: EN-EP-308; Revision: 6; 02/04/2020
10CFR50.54(q)(2) Facility: GGNS
Review
71114.04 Miscellaneous Attachment 1, Facility: GGNS, Title: Closure of Grand Gulf Road 03/17/2020
Inspection Type Designation Description or Title Revision or
Procedure Date
Review
71114.04 Miscellaneous Attachment 9.1, Procedure/Document Number: 10-S-01-38, Revision: 6, 06/03/2019
10CFR50.54(q)(2) Facility: Grand Gulf Nuclear Station
Review
71114.04 Miscellaneous Attachment 9.2, Procedure/Document Number: EN-EP-801, Revision: 17, 01/25/2019
10CFR50.54(q)(3) Facility: GGNS, Title: Emergency Response Organization
Screening
71114.04 Miscellaneous Attachment 9.2, Revision: Version 3.4.1.0; Equipment/Facility/Other: URI 12/10/2018
10CFR50.54(q)(3) Version 3.4.1.0/GGNS; Title: Replace Dose Calc with URI
Screening Version 3.4.1.0 as the Primary Dose Assessment Software
71114.04 Miscellaneous Attachment 9.2, Procedure/Document Number: Emergency Plan, Revision: 79 09/18/2019
Screening
71114.04 Miscellaneous Attachment 9.3, Revision: Version 3.4.1.0; Equipment/Facility/Other: URI 12/10/2018
10CFR50.54(q)(3) Version 3.4.1.0/GGNS; Title: Replace Dose Calc with URI
Evaluation Version 3.4.1.0 as the Primary Dose Assessment Software
71114.04 Miscellaneous Attachment 9.3, Procedure/Document Number: EN-EP-801, Revision: 17, 01/25/2019
10CFR50.54(q)(3) Facility: GGNS, Title: Emergency Response Organization
Evaluation
71114.04 Miscellaneous Attachment 9.3, Procedure/Document Number: Emergency Plan, Revision: 79; 09/18/2019
10CFR50.54(q)(3) Facility: Grand Gulf
Evaluation
71114.04 Miscellaneous GIN No. 2020- Emergency Plan Revision 81 10/30/2020
00176
71114.04 Miscellaneous GNRO- Emergency Plan, Revision 79; Grand Gulf Nuclear Station, 10/29/2019
2019/00045 Unit 1; NRC Docket No. 50-416; Renewed Facility Operating
License No. NPF-29
71114.04 Miscellaneous GNRO- Emergency Plan, Revision 81 and Revision 0 of the EAL 11/27/2020
20/00040 Technical Bases Document; Grand Gulf Nuclear Station,
Unit 1; NRC Docket No. 50-416; Renewed Operating License
No. NPF-29
71114.04 Procedures EN-EP-305 Emergency Planning 10CFR50.54(q) Review Program 7, 8
71114.04 Procedures EN-EP-801 Emergency Response Organization 17
Inspection Type Designation Description or Title Revision or
Procedure Date
71114.05 Corrective Action CR-GGNS- 2017-07550, 2018-11473, 2018-12041, 2018-12281, 2019-
Documents 00174, 2019-00240, 2019-00468, 2019-00956, 2019-01439,
2019-04003, 2019-07102, 2019-08247, 2019-10145, 2020-
04869, 2020-05947, 2020-06708, 2020-06914, 2020-07514,
20-08304, 2020-08442, 2020-08624, 2020-08963, 2020-
09863, 2020-09904, 2020-10044, 2020-10087, 2020-10587
71114.05 Corrective Action Corporate 2017-00610
Documents Condition Reports
(CR-HQN-)
71114.05 Corrective Action CR-GGNS- 2020-11398, 2020-11474, 2020-11477, 2020-11539, 2020-
Documents 11542, 2020-11564, 2020-11586, 2020-11869
Resulting from
Inspection
71114.05 Miscellaneous Fire Drill Report, Date: 6/28/19, Time: 14:00; Shift/Team: C 06/28/2019
71114.05 Miscellaneous Fire Drill Report, Date: 10/16/20, Shift/Team: A 10/19/2020
71114.05 Miscellaneous Grand Gulf Nuclear Station After Action Report/Improvement 11/06/2018
Plan, Exercise Date - September 18-19, 2018, Radiological
Emergency Preparedness (REP) Program
71114.05 Miscellaneous Nuclear Independent Oversight Functional Area Performance 03/18/2020
Report, Site: Grand Gulf NS, Report Period: October 2019-
January 2020
71114.05 Miscellaneous Nuclear Independent Oversight Functional Area Performance 06/08/2020
Report, Site: Grand Gulf NS, Report Period: February 1, 2020
- May 31, 2020
71114.05 Miscellaneous Nuclear Independent Oversight Functional Area Performance 10/11/2019
Report, Site: Grand Gulf NS, Report Period: June 2019-
September 2019
71114.05 Miscellaneous After Action Report, Grand Gulf Nuclear Station, Radiological 06/04/2019
Emergency Preparedness Exercise, Exercise Date: March 13,
2019
71114.05 Miscellaneous EN-TQ-125, Fire Drill Scenario, Date: 12/3/18, Time: 12:30, Shift/Team: B 12/03/2018
GIN No. 2018- State and Local Annual Review of GGNS Emergency Action 08/20/2018
00146 Levels - 2018
Inspection Type Designation Description or Title Revision or
Procedure Date
71114.05 Miscellaneous GIN No. 2018- GGN 2018 October 3 Red Team Wertz ERO Training Drill 11/05/2018
210 Report
71114.05 Miscellaneous GIN No. 2018- GGN 2018 Site Medical Drill Report 12/13/2018
234
GIN No. 2018- Emergency Preparedness Letter of Agreement (LOA) Annual 12/17/2018
241 Review - 2018
GIN No. 2018- 2018 Annual Media Training 12/18/2018
248
GIN No. 2019- State and Local Annual Review of GGNS Emergency Action 01/08/2020
00007 Levels - 2019
71114.05 Miscellaneous GIN No. 2019- GGN 2018 November 14 Blue Team Wertz ERO Training Drill 12/12/2018
00062 Report
GIN No. 2019- GGNS March 13, 2019 Blue Team Wertz NRC Evaluated 06/13/2019
00091 Exercise Report
GIN No. 2019- GGNS May 9, 2019 Repair Team NRC Evaluated Exercise 06/13/2019
00092 Report
GIN No. 2019- GGNS March 13, 2019 First Half Semi-Annual Health Physics 06/13/2019
00095 Drill Report
GIN No. 2019- GGNS March 13, 2019 Radiological Monitoring Drill 06/13/2019
00096
GIN No. 2019- Quarterly Emergency Response Facilities Inventory Report - 07/08/2019
00118 2nd Quarter 2019
GIN No. 2019- Review of Census Growth Rates and Methodology for GGNS 09/11/2019
00181 2019 Annual ETE Update
GIN No. 2019- GGNS August 28, 2019 Yellow Team 3rd Quarter Drill Report 10/10/2019
00192
71114.05 Miscellaneous GIN No. 2019- GGNS 2019-01 EOF Mini Drill Report 10/14/2019
00193
71114.05 Miscellaneous GIN No. 2019- GGNS 2019-02 EOF Mini Drill Report 10/14/2019
00194
71114.05 Miscellaneous GIN No. 2019- GGNS October 23, 2019 Green Team 4th Quarter Drill Report 11/19/2019
224
71114.05 Miscellaneous GIN No. 2019- GGNS 2019-03 EOF Mini Drill Report 11/19/2019
227
Inspection Type Designation Description or Title Revision or
Procedure Date
71114.05 Miscellaneous GIN No. 2019- GGNS Medical Drill and Second Half Semi-Annual Health 12/12/2019
265 Physics Drill Report
GIN No. 2019- 2019 Annual Media Training 12/31/2019
275
GIN No. 2020- Emergency Preparedness Letter of Agreement (LOA) Annual 04/06/2020
00008 Review - 2019
71114.05 Miscellaneous GIN No. 2020- GGNS 2019-05 EOF Mini Drill Report 02/21/2020
00051
71114.05 Miscellaneous GIN No. 2020- GGNS First Half Semi-Annual Health Physics Drill Report 07/14/2020
00121
71114.05 Miscellaneous GIN No. 2020- GGNS 2020-02 EOF Mini Drill Report 08/20/2020
00142
71114.05 Miscellaneous GIN No. 2020- EAL Technical Bases Document Revision 0 10/30/2020
00179
71114.05 Miscellaneous GIN No. 2020- Quarterly Emergency Response Facilities Inventory Report - 07/30/2020
00123 2nd Quarter 2020
71114.05 Miscellaneous GIN No. 2020- Review of Census Growth Rates and Methodology for Grand 09/16/2020
00158 Gulf Nuclear Station 2020 Annual ETE Update
71114.05 Miscellaneous GNRO- Changes to Emergency Plan Implementing Procedures, Grand 09/14/2020
20/00026 Gulf Nuclear Station, Unit 1; Docket No. 50-416; License No.
71114.05 Miscellaneous QA-7-2019- Quality Assurance Audit Report, Audited Area Title: 05/20/2019
GGNS-1 Emergency Preparedness
71114.05 Miscellaneous QA-7-2020- Quality Assurance Audit Report, Audited Area Title: 05/11/2020
GGNS-1 Emergency Preparedness
71114.05 Procedures 01-S-10-5 Control of Emergency Response Equipment and Facilities 17
71114.05 Procedures 01-S-10-7 Emergency Operations Facility Management Program 4
71114.05 Procedures 04-1-01-D21-1 Area Radiation Monitoring System 19
71114.05 Procedures 10-S-01-34 Joint Information Center (JIC) Operations 23
71114.05 Procedures 10-S-01-39 Grand Gulf Equipment Important to Emergency Response 6
71114.05 Procedures 10-S-02-1 ERF Inspections, Inventories, Operability Checks and 21
Maintenance
71114.05 Procedures EN-EP-306 Drills and Exercises 10
71114.05 Procedures EN-LI-102 Corrective Action Program 42
Inspection Type Designation Description or Title Revision or
Procedure Date
71114.05 Work Orders WO 488789, 513199, 536655, 545092, 548558, 548559, 548560
71124.05 Calibration Calibration of the Canberra/Nuclear Data People Mover WBC 08/17/2017
Records System at the Entergy Grand Gulf Nuclear Station
71124.05 Calibration 2019-B2.28- Laboratory Standard Calibration/Verification Data 06/12/2019
Records LABSTN-00001
71124.05 Calibration 2019-B2.28- Source Verification 04/24/2019
Records SRCVER-0003
71124.05 Calibration 2019-B2.28- Source Verification 10/22/2019
Records SRCVER-0009
71124.05 Calibration 2019-B2.28- Source Verification 12/17/2019
Records SRCVER-0010
71124.05 Calibration 2020-B2.28- Portable Instrumentation Calibration Data Sheet 2020
Records CALDAT-01712
71124.05 Calibration WO 52761386-01 Standby Gas Treatment System B Normal/High Range 03/12/2019
Records Radiation Monitor System Calibration (P024)
71124.05 Calibration WO 52814444-01 Containment Building Ventilation Gaseous Monitor Calibration 02/11/2019
Records (D17-A-0025-03)
71124.05 Calibration WO 52860275 Liquid Radwaste Effulents Radiation Monitor Calibration (D17- 01/21/2020
Records A-1024)
71124.05 Calibration WO 52860275 Liquid Radwaste Effulents Radiation Monitor Calibration (D17- 01/21/2020
Records Supplemental A-1024) Supplemental
71124.05 Calibration WO 52866647-01 Containment Building Ventilation Gaseous Monitor Calibration 02/17/2020
Records (D17-A-0025-03)
71124.05 Calibration WO 52871185-01 Standby Gas Treatment System B Normal/High Range 10/07/2020
Records Radiation Monitor System Calibration (P024)
71124.05 Corrective Action CR-GGNS- 2018-11323, 2018-12961, 2019-00574, 2019-00801, 2019-
Documents 02988, 2019-03264, 2019-03557, 2019-04061, 2019-05863,
2019-05986, 2019-08140, 2019-08468, 2019-08564, 2019-
08910, 2019-08912, 2020-00209, 2020-04720, 2020-04747,
20-07329, 2020-07669, 2020-08393, 2020-08442, 2020-
08679, 2020-08990, 2020-09707
71124.05 Miscellaneous Grand Gulf Nuclear Station Offsite Dose Calculation Manual 42
71124.05 Procedures Entergy Quality Assurance Program Manual 39
71124.05 Procedures 10-S-01-1 Grand Gulf Nuclear Station Emergency Plan Procedure 132
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.05 Procedures EN-RP-303 Source Checking of Radiation Protection Instrumentation 4
71124.05 Self-Assessments LO-GLO-2019- Self-Assessment for Pre-NRC Inspection: Radiation Monitoring 07/30/2020
171 Instrumentation Assessment (IP 71124.05)
71124.05 Self-Assessments QA-14-15-2019- Combined Radiation Protection and Radwaste 10/21/2019
GGNS-1
71124.06 Calculations GIN 2020-00037 Calculation for Unmonitored Radioactive Effluent Release from 01/31/2020
Turbine Building Roof Hatch (CR-GGNS-2019-10085)
71124.06 Calculations GIN 2020-00047 Calculation for Unmonitored Radioactive Effluent Release from 02/12/2020
Turbine Building Roof Hatch (CR-GGNS-2020-0013)
71124.06 Corrective Action CR-GGNS- 2019-00099, 2019-00652, 2019-00934, 2019-01419, 2019-
Documents 02059, 2019-06409, 2019-07662, 2019-07766, 2019-07909,
2019-08776, 2019-10085, 2020-00013, 2020-00597, 2020-
05002, 2020-06046, 2020-08990, 2020-09540, 2020-10264,
20-10303, 2020-10577, 2020-10779
71124.06 Miscellaneous 2018 Grand Gulf Nuclear Station Annual Radioactive Effluent 04/30/2019
Release Report
71124.06 Miscellaneous 2019 Grand Gulf Nuclear Station Annual Radioactive Effluent 04/30/2020
Release Report
71124.06 Miscellaneous Spent Fuel Storage Radioactive Effluent Release Report for 02/20/2020
2019
71124.06 Miscellaneous Spent Fuel Storage Radioactive Effluent Release Report for 02/21/2019
2018
71124.06 Miscellaneous Grand Gulf Nuclear Station Offsite Dose Calculation Manual 42
71124.06 Miscellaneous EN002- Teledyne Brown Engineering Inc. Report of Sample 09/04/2020
3P50GRAND-14 Analysis/Certificate of Conformance
(L88546)
71124.06 Procedures 06-CH-1000-M- Effluent Dose Calculations 105
0049
71124.06 Procedures 06-CH-1D17-M- Building Ventilation Gaseous Tritium 110
0003
71124.06 Procedures 06-CH-1D17-M- Building Ventilation Exhaust Gaseous Isotopic 113
0005
71124.06 Procedures 06-CH-1D17-W- Gaseous Release Points Iodine, Tritium, and Particulates 108
0017
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.06 Procedures 06-CH-1T48-M- Standby Gas Treatment Exhaust Gaseous Isotopic 111
0037
71124.06 Procedures 06-CH-SG17-P- Radwaste Release Pre-Release Analysis 110
0041
71124.06 Procedures 08-S-04-218 Radiological Effluent Tracking and Dose Assessment Users 10
Guide
71124.06 Procedures EN-CY-102-01 Quality Control for Analytical Laboratory Interlab and Intralab 1
Cross-Check Programs
71124.06 Radiation Surveys 2020083 Unit 1 Turbine Building Ventilation Gas Isotopic Sample 11/19/2020
Analysis (Isotopic)
71124.06 Radiation Surveys 2020162 Equipment Drain Sample Tank Liquid Pre-Release Sample 11/17/2020
71124.06 Radiation Surveys 2020163 Equipment Drain Sample Tank A Pre-Release Liquid Sample 11/18/2020
Analysis
71124.06 Self-Assessments 1000-1-19-002 Grand Gulf Nuclear Station 2019 Radiometric INTERLAB and 10/17/2019
INTRALAB Cross-Check Results
71124.06 Self-Assessments LO-GLO-2019- Pre-NRC 71124.06 Inspection - Radioactive Gaseous and 08/14/2020
0173 Liquid Effluent Treatment
71124.06 Self-Assessments QA-2-6-2019- Combined Chemistry, Effluent and Environmental Monitoring 2019
GGNS-01 Audit Notification/Audit Plan Memorandum
71124.07 Calibration 2020-B2.28- Environment Air Sampler 06/03/2020
Records CALDAT-03905
71124.07 Calibration 2020-B2.28- Environment Air Sampler 06/03/2020
Records CALDAT-03906
71124.07 Calibration 2020-B2.28- Environment Aire Sampler 06/03/2020
Records CALDAT-03907
71124.07 Calibration 2020-B2.28- Environment Air Sampler 06/03/2020
Records CALDAT-03908
71124.07 Corrective Action CR-GGNS- 2018-13098, 2019-00771, 2019-07646, 2019-10479, 2020-
Documents 01555, 2020-05098, 2020-06817, 2020-07780, 2020-10134,
20-10189
71124.07 Corrective Action CR-GGNS- 2020-11520, 2020-11583
Documents
Resulting from
Inspection
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.07 Miscellaneous Annual Radiological Environmental Operating Report 04/30/2019
(AREOR) - 2018
71124.07 Miscellaneous Annual Radiological Environmental Operating Report 04/17/2020
(AREOR) - 2019
71124.07 Miscellaneous Groundwater Monitoring Plan for Grand Gulf Nuclear Station 6
71124.07 Miscellaneous 2019 Grand Gulf Meteorological Data Review 03/31/2020
71124.07 Miscellaneous 2020 MET Tower Meteorological Data Review from March through October of 2020
Data Monthly 2020
Review
71124.07 Procedures 06-IC-SC84-SA- Primary Tower Wind Speed/Direction, Air Temperature (T/dT) 109
1003 and Relative Humidity
71124.07 Procedures 08-S-04-964 MET Data Processing 3
71124.07 Procedures EN-CY-127 Land Use Census 1
71124.07 Procedures EN-CY-130-02 Radiological Environment Monitoring Program (REMP) - 1
Grand Gulf Nuclear Station
71124.07 Procedures EN-RP-113 Response to Contaminated Spills/Leaks 9
71124.07 Self-Assessments Pre-NRC Self-Assessment: Radioactive Environmental 07/23/2020
Monitoring Program - IP 71124.07
71124.07 Self-Assessments NUPIC Number 2019 Radioanalytical Laboratory Audit Report: Teledyne 04/19/2019
24791 Brown Engineering- Environmental Services (TBE-ES)
71124.07 Work Orders WO-GGN- 2018 Biannual Land Use Census 11/20/2018
2739965
71124.07 Work Orders WO-GGN- Primary Tower Wind Speed/Direction, Air Temperature (T/dT) 11/07/2019
2876579 and Relative Humidity
71124.07 Work Orders WO-GGN- Primary Tower Wind Speed/Direction, Air Temperature (T/dT) 06/02/2020
2905611 and Relative Humidity
71124.08 Corrective Action CR-GGNS- 2019-07812, 2019-08048, 2019-08334, 2019-08335, 2019-
Documents 08336, 2019-08347, 2020-01408, 2020-05694, 2020-
06915,2020-07906,2020-08235,2020-08951,2020-
09791,2020-10704
71124.08 Corrective Action CR-GGNS- 2020-011573
Documents
Resulting from
Inspection
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.08 Miscellaneous Grand Gulf Nuclear Generating Station Updated Final Safety 4
Analysis Report (UFSAR), Chapter 11.4 - Solid Radwaste
System
71124.08 Miscellaneous GIN-2019-00179 2018-2019 10CFR61 Waste Stream Analysis for BR-D-NA- 09/10/2019
SRT Bead Resin
71124.08 Procedures 02-S-01-11 Rad Waste Operations 23
71124.08 Procedures EN-RP-121 Radioactive Material Control 7
71124.08 Procedures EN-RW-101 Radioactive Waste Management 3
71124.08 Procedures EN-RW-102 Radioactive Shipping Procedure 19
71124.08 Procedures EN-RW-102 Radioactive Shipping Procedure 19
71124.08 Procedures EN-RW-105 Process Control Program 5
71124.08 Procedures EN-RW-106 Integrated Transportation Security Plan 6
71124.08 Radiation Surveys GG-1205-0988 Mausoleum 05/16/2012
71124.08 Radiation Surveys GGN-2001-00273 Northwest Laydown Area 01/23/2020
71124.08 Radiation Surveys GGN-2010-00170 118' Radwaste Entire Elevation 10/19/2020
71124.08 Radiation Surveys GGN-2011-00188 136' Radwaste Truck Bay 11/12/2020
71124.08 Radiation Surveys GGN-2011-00278 Radwaste Southeast Yard 11/14/2020
71124.08 Radiation Surveys GGN-2011-00279 Radwaste Pad Monthly 11/14/2020
71124.08 Radiation Surveys GGN-2011-00318 Yard - Other 11/16/2020
71124.08 Self-Assessments LO-GLO-2019- Pre-NRC Inspection Module 71124-08 07/27/2020
00172-CA-1
71124.08 Self-Assessments QA-14-15-2019- Combined Radiation Protection and Radwaste Audit 10/21/2019
GGNS-1
71124.08 Self-Assessments WT-GGN-2019- Radwaste Training 10/17/2019
00071 CA-30
71124.08 Shipping Records GGN-2018-1201 UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, 12/11/2018
RQ; Irradiated hardware
71124.08 Shipping Records GGN-2019-0101 UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, 01/09/2019
RQ; Irradiated hardware
71124.08 Shipping Records GGN-2019-0202 UN3321, Radioactive Material, LSA-II, 7; Dewatered Resin 02/07/2019
71124.08 Shipping Records GGN-2019-0313 UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, 04/03/2019
RQ; TriNuke Filters
Inspection Type Designation Description or Title Revision or
Procedure Date
71124.08 Shipping Records GGN-2019-1208 UN2912, Radioactive Material, LSA-I, 7; Dry Active Waste 12/17/2019
71124.08 Shipping Records GGN-2020-0518 UN2916, Radioactive Material, Type B(U), 7, Fissile-Excepted, 06/04/2020
RQ; Dewatered resin
71124.08 Work Orders WO-52881814 Leak Test of Sealed Sources 11/14/2019
71124.08 Work Orders WO-52908073 Leak Test of Sealed Sources 05/13/2020
71151 Corrective Action CR-GGNS- 2019-02168, 2020-07481
Documents
71151 Corrective Action CR-GGNS- 2020-11575, 2020-11578
Documents
71151 Miscellaneous MSPI Datasheets
71151 Miscellaneous GIN No. 2019- Alert Notification System Test 06/17/2019
00099
71151 Miscellaneous GIN No. 2019- Alert Notification System Test 09/05/2019
00177
71151 Miscellaneous GIN No. 2020- Alert Notification System Test - FEB20 02/27/2020
00061
71151 Miscellaneous GIN No. 2020- Alert Notification System Test - July 2020 07/30/2020
00128
71151 Miscellaneous GIN No. 2020- Alert Notification System Test - August 2020 08/05/2020
00138
71151 Procedures GGNS-SA-06- GGNS MSPI Basis Document and Supporting Information 6
00002
71152 Corrective Action CR-GGNS- 2020-00872, 2020-00915, 2020-04116, 2020-05268, 2020-
Documents 05270, 2020-05404, 2020-05405, 2020-05427, 2020-05780,
20-05784, 2020-06048, 2020-07317, 2020-08156, 2020-
08197, 2020-08349, 2020-08734, 2020-08754, 2020-09739,
20-09756, 2020-09797, 2020-10231, 2020-10279
71152 Work Orders WO 478532, 497673, 508458, 538756, 538759, 538760, 538761,
538762, 538763, 538764, 52831300
26