IR 05000416/2023003
| ML23310A282 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 11/08/2023 |
| From: | William Schaup NRC/RGN-IV/DORS/PBC |
| To: | Kapellas B Entergy Operations |
| Schaup W | |
| References | |
| IR 2023003 | |
| Download: ML23310A282 (21) | |
Text
November 08, 2023
SUBJECT:
GRAND GULF NUCLEAR STATION - INTEGRATED INSPECTION REPORT 05000416/2023003
Dear Brad Kapellas:
On September 30, 2023, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Grand Gulf Nuclear Station. On October 4, 2023, 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.
One finding of very low safety significance (Green) is documented in this report. This finding involved a violation of NRC requirements. 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, William T. Schaup, Jr., Acting Branch Chief Reactor Projects Branch C Division of Operating Reactor Safety Docket No. 05000416 License No. NPF-29
Enclosure:
As stated
Inspection Report
Docket No.
05000416 License No.
NPF-29 Report No.
05000416/2023003 Enterprise Identifier:
I-2023-003-0011 Licensee:
Entergy Operations, Inc.
Facility:
Grand Gulf Nuclear Station Location:
Port Gibson, MS Inspection Dates:
July 1, 2023, to September 30, 2023 Inspectors:
B. Baca, Health Physicist N. Greene, Senior Health Physicist S. Hedger, Senior Emergency Preparedness Inspector N. Hernandez, Operations Engineer S. Lichvar, Acting Senior Resident Inspector K. Murphy, Operations Engineer W. Schaup, Acting Branch Chief A. Smallwood, Acting Senior Resident Inspector R. Williams, Operations Engineer Approved By:
William T. Schaup, Jr., Acting Branch Chief Reactor Projects Branch C Division of Operating Reactor Safety
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.
List of Findings and Violations
Inadequate Maintenance Procedures for Division 2 Drywell Purge Compressor Isolation Valve Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000416/2023003-01 Open/Closed None 71153 The inspectors are documenting a self-revealed, Green finding and associated non-cited violation of Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the failure to provide information appropriate to the circumstances in station procedures. Specifically, work order 00487808 did not contain instructions or drawings to describe or illustrate the proper installation of the motor-operated actuator in relation to the disc and stem for valve E61F003B, drywell purge isolation valve, resulting in the valve having to be declared inoperable. Additionally, the work order did not have an adequate post maintenance test, in that, the post maintenance test performed did not detect that the valve was incorrectly assembled.
Additional Tracking Items
Type Issue Number Title Report Section Status LER 05000416/2023-001-00 Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification 71153 Closed
PLANT STATUS
Grand Gulf Nuclear Station, Unit 1, began the inspection period at 98 percent rated thermal power (RTP). RTP returned to 100 percent on July 17, 2023. On July 22, 2023, RTP was reduced to 98 percent due to a main turbine generator stator bar cooling issue. On July 23, 2023, station power was increased to 99 percent. The station returned to 100 percent RTP on August 2, 2023. On September 30, 2023, power was decreased to 71 percent for a control rod pattern adjustment and was subsequently returned to 100 percent RTP that afternoon where power 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 performed activities described in IMC 2515, Appendix D, Plant Status, observed risk significant activities, and completed on-site portions of IPs. 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.
REACTOR SAFETY
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (2 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
(1)engineered safety feature electric bus 16AB on August 29, 2023 (2)division 1 and 2 standby service water pump house ventilation system on September 13, 2023
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)auxiliary building 119-foot elevation, fire zones 1A201 and 1A211, on July 25, 2023 (2)division 3 switchgear room, control building, 111-foot elevation, on July 26, 2023 (3)lower cable spreading room, control building 148-foot elevation, on September 12, 2023
Fire Brigade Drill Performance Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated the onsite fire brigade training and performance during an announced fire drill response to the 148-foot elevation lower cable spreading room on July 28, 2023.
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 from July 24, 2023, to August 30, 2023.
71111.11B - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Requalification Program (IP Section 03.04) (1 Sample)
- (1) Biennial Requalification Written Examinations The inspectors evaluated the quality of the licensed operator biennial requalification written examination administered on August 31, 2023.
Annual Requalification Operating Tests The inspectors evaluated the adequacy of the licensees annual requalification operating test.
Administration of an Annual Requalification Operating Test The inspectors evaluated the effectiveness of the licensee in administering requalification operating tests required by 10 CFR 55.59(a)(2) and that the licensee is effectively evaluating their licensed operators for mastery of training objectives.
Requalification Examination Security The inspectors evaluated the ability of the licensee to safeguard examination material, such that the examination is not compromised.
Remedial Training and Re-examinations The inspectors evaluated the effectiveness of remedial training conducted by the licensee, and reviewed the adequacy of re-examinations for licensed operators who did not pass a required requalification examination.
Operator License Conditions The inspectors evaluated the licensees program for ensuring that licensed operators meet the conditions of their licenses.
Control Room Simulator The inspectors evaluated the adequacy of the licensees control room simulator in modeling the actual plant, and for meeting the requirements contained in 10 CFR 55.46.
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (2 Samples)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during surveillances and power adjustments for primary water temperature adjustments on August 5, 2023.
- (2) The inspectors observed and evaluated licensed operator performance in the control room during down power for rod pattern adjustments and high-pressure turbine control valve testing on September 30, 2023.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator training scenario in the simulator on August 23, 2023.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following structures, systems, and components (SSCs) remain capable of performing their intended function:
(1)work order 52997899, division 3 emergency diesel generator motor-operated potentiometer cleaning and inspection on August 14, 2023 (2)work order 54047692, automatic depressurization system boost compressor check valve leak repair on September 25, 2023
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (3 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)protected system lineup during division 3 maintenance outage on July 19, 2023 (2)adjustments to primary water cooling to main turbine generator during excessive heat watch on August 1, 2023
- (3) Yellow risk due to surveillance procedure 06-IC-B21-Q-1009-02, reactor vessel water level, level 3 for automatic depressurization system, and reactor core isolation cooling level 8, functional test channel B on September 15, 2023
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the following operability determinations and functionality assessments:
(1)condition report CR-GGN-2023-13908, reactor core isolation cooling high vibrations during surveillance on July 18, 2023 (2)condition report CR-GGN-2023-13437, division 3 emergency diesel generator jacket water cooler degraded flow on August 7, 2023 (3)condition report CR-GGN-2023-14471, engineered safety feature transformer 11 high-temperature alarm on August 14, 2023 (4)condition report CR-GGN-2023-14716, emergency core cooling system jockey pumps for high-pressure core spray, low pressure core spray, and residual heat removal divisions 1, 2 and 3 trico oiler seismic evaluations on August 15, 2023 (5)condition report CR-GGN-2023-13838, E61F003B drywell purge compressor isolation butterfly valve actuator misalignment on September 24, 2023
71111.24 - Testing and Maintenance of Equipment Important to Risk
The inspectors evaluated the following testing and maintenance activities to verify system operability and/or functionality:
Post-Maintenance Testing (PMT) (IP Section 03.01) (8 Samples)
(1)work order 54006669, drywell purge supply isolation valve 1E61F003B on July 18, 2023 (2)work order 567598, replace valve SP64F020 per engineering change EC93721 on August 15, 2023 (3)work order 542229, replace valve SP64015 to correct leakage past check valve on August 22, 2023 (4)work order 586008, Flex emergency diesel generator fuel leak on August 24, 2023 (5)work order 587309, post maintenance test on auxiliary building secondary containment floor plugs on September 11, 2023 (6)work order 575709, operations post maintenance test diesel drive fire pump A on September 20, 2023 (7)work order 54053720, SP41F064A division 1 standby service water to control room air conditioning valve retest on September 27, 2023 (8)work order 587424, division 1 standby service water cooling tower fan B vibration testing on September 29, 2023
Surveillance Testing (IP Section 03.01) (2 Samples)
(1)work order 54018564, reactor core isolation cooling division 2 steam supply low pressure on August 11, 2023 (2)division 2 emergency diesel generator monthly surveillance run on September 14, 2023
71114.06 - Drill Evaluation
Drill/Training Evolution Observation (IP Section 03.02) (2 Samples)
The inspectors evaluated:
- (1) Blue team emergency preparedness drill on July 26, 2023
- (2) Red team emergency preparedness drill on September 13,
RADIATION SAFETY
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Walkdowns and Observations (IP Section 03.01) (5 Samples)
The inspectors evaluated the following radioactive effluent systems during walkdowns:
(1)auxiliary building ventilation A and B and the containment building ventilation systems (2)fuel handling building ventilation system (3)liquid radwaste discharge (4)radwaste building ventilation system (5)turbine building ventilation system
Sampling and Analysis (IP Section 03.02) (4 Samples)
Inspectors evaluated the following effluent samples, sampling processes and compensatory samples:
(1)gaseous release point iodines and particulates activity collection and analysis for containment, fuel building, radwaste, and turbine building: work order 53033395-01, dated August 8, 2023 (2)gaseous release point particulate alpha activity analysis for the auxiliary, containment, fuel building, radwaste, and turbine building: work order 54015776-01, dated August 10, 2023 (3)gaseous and tritium activity collection and analysis for the radwaste building ventilation: radwaste building ventilation gas grab sample analysis M5: RWBV, dated August 10, 2023; and work order 54018927-01, dated August 10, 2023, respectively (4)off gas post-treatment exhaust gaseous isotopic sample collection and analysis: work order 54026583-01, dated August 10, 2023
Dose Calculations (IP Section 03.03) (2 Samples)
The inspectors evaluated the following dose calculations:
- (1) liquid discharge permits and associated dose assessments: 2020182, 2021003,
2021070, 2022174, 2023007 (2)gaseous discharge permits and associated dose assessments: 2021029 and 2022005 Abnormal Discharges (IP Section 03.04)
The inspectors evaluated the following abnormal discharges:
- (1) On November 30, 2020, a total of 342 gallons liquid radwaste effluent was discharged prior to the automatic isolation detector isolating the release. The liquid radwaste tank was resampled, analyzed using a different detector system, and the volume released was determined to not exceed an administrative or technical specification limits for public dose for the discharge (condition report CR-GGN-2020-11892).
- (2) On January 3, 2021, a total of 22,790 gallons from the floor drain storage tank B (FDST-B) was discharged without an approved discharge permit. The FDST-B was sampled, and the volume was determined to not exceed an administrative or technical specification limits for public dose for the discharge (condition report CR-GGN-2021-00869).
- (3) For the first quarter 2022, the average tritium concentration in Outfall 007 was 29,796 picoCuries per liter (pCi/L). This value was less than the reportable level (30,000 pCi/L non-drinking water) as specified in the Grand Gulf Nuclear Station Offsite Dose Calculation Manual, table 6.12.1-2. The licensee identified a turbine building steam leak was ascending to the building roof, dripping onto the roof, and making its way to the storm drains which ran to Outfall 007. The steam leak was repaired in February 2022, and tritium concentrations at Outfall 007 have remained near baseline levels since March 2022 (condition report CR-GGN-2022-00608).
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 a 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.
No issues were identified.
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification The inspectors verified licensee performance indicators submittals listed below:
MS06: Emergency AC Power Systems (IP Section 02.05)===
- (1) July 1, 2022, through June 30, 2023
MS07: High Pressure Injection Systems (IP Section 02.06) (1 Sample)
- (1) July 1, 2022, through June 30, 2023
MS08: Heat Removal Systems (IP Section 02.07) (1 Sample)
- (1) July 1, 2022, through June 30, 2023
71153 - Follow Up of Events and Notices of Enforcement Discretion Event Report (IP section 03.02)
The inspectors evaluated the following licensee event reports (LERs):
- (1) LER 05000416/2023-001-00, Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification (ADAMS Accession No. ML23215A204). The circumstances surrounding this LER and a non-cited violation is documented in the Inspection Results section of this report. This LER is Closed.
INSPECTION RESULTS
Inadequate Maintenance Procedures for Division 2 Drywell Purge Compressor Isolation Valve Cornerstone Significance Cross-Cutting Aspect Report Section Barrier Integrity Green NCV 05000416/2023003-01 Open/Closed None 71153 The inspectors are documenting a self-revealed, Green finding and associated non-cited violation of Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, for the failure to provide information appropriate to the circumstances in station procedures. Specifically, work order 00487808 did not contain instructions or drawings to describe or illustrate the proper installation of the motor-operated actuator in relation to the disc and stem for valve E61F003B, drywell purge isolation valve, resulting in the valve having to be declared inoperable. Additionally, the work order did not have an adequate post maintenance test, in that, the post maintenance test performed did not detect that the valve was incorrectly assembled.
Description:
On October 26, 2017, while performing surveillance Procedure 06-OP-1E61-M-0001, Post LOCA Drywell Vacuum Breaker Operability, revision 104, for the division 2 drywell vacuum breaker, the equipment operator did not observe any movement of the stem for valve 1E61F003B upon initiation of a close or open signal. The control room indications showed the valve was opened and closed, but stem movement was not observed locally.
Upon inspection, the splined coupler of valve 1E61F003B was found slipping down the valve stem causing disengagement between the valve stem and the drive sleeve. Thus, the actuator was moving and indicating opened/closed, but the valve did not move with the actuator. The licensee documented this in the corrective action program as condition report CR-GGN-2017-10756.
On October 27, 2017, the splined coupler was reinstalled via work order (WO) 00487808. The post maintenance testing included a current and switches only diagnostic test, which was the licensee standard for limit controlled soft seated butterfly valves at that time. This standard did not include the guidance of generic letter GL-96-05 to measure valve torque during testing.
1 of GL-96-05 stated the following:
Static diagnostic tests provide information on the thrust/torque output of the motor actuator and any changes to the motor actuator output as a result of aging effects. The thrust and torque required to operate a valve are highly dependent on the differential pressure and flow across the valve disk, which are not present during static testing. Therefore, dynamic tests can provide information on the thrust/torque requirements and any changes to those requirements as a result of aging effects. Efforts are underway within the nuclear industry to develop methods to obtain information from static tests that would allow prediction of valve dynamic performance. As discussed below, EPRI has developed an analytical methodology that, when combined with static test data, provides bounding information on the thrust/torque requirements to operate gate, globe, and butterfly valves under dynamic conditions.
On January 24, 2019, condition report CR-GGN-2019-00618 identified that the diagnostic testing on safety significant butterfly valves did not meet the requirements of GL-96-05 due to not measuring valve stem torque during testing. Licensee maintenance and work procedures were subsequently updated for all applicable butterfly valves to reflect that the diagnostic testing required measuring the valve stem torque. The inspectors noted that the licensee did not consider at the time whether maintenance and testing completed previously was adequate.
On June 6, 2023, the licensee performed diagnostic testing for motor operated valve E61F003B per WO 52982721 including dynamic testing with a strain gauge on the stem to measure valve torque.
On June 13, 2023, condition report CR-GGN-2023-13838 documented that while reviewing data from the motor operated diagnostic test on valve E61F003B, it was identified that the butterfly valves disc was traveling past the valve seat. The test data indicated that the valve was contacting the seat at 40 seconds of the full 60 second stroke time. After contacting the seat, the seating torque decreased (relaxed) and the valve continued to travel for 20 seconds past the seat. The valve E61F003B has a full travel of 90 degrees. With the actuator in the full-open position, the valve disk was 60 degrees open. Conversely, with the actuator in the full closed position, the valve disk was 30 degrees open. This valve has no torque switch in the circuit and is positioned seated using the limit switches. With this information, operations personnel declared valve E61F003B and the division 2 drywell purge subsystem inoperable and entered technical specification (TS) 3.6.3.3 and TS 3.6.5.6.
On June 16, 2023, the licensee repaired the value per WO 540006669. A subsequent post maintenance test, including the dynamic testing, verified proper operation and alignment of the valve actuator and valve stem. The licensee declared the division B drywell purge subsystem, drywell post-LOCA and drywell vacuum relief subsystem operable.
On August 3, 2023, the licensee reported the events associated with the misaligned valve to the NRC in Licensee Event Report 2023-001-00, "Valve Closure Test Failure Resulting in Condition Prohibited by Technical Specification," (ML23215A204).
The inspectors noted the valve E61F003B has two safety functions as described in the updated final safety analysis report (UFSAR). UFSAR, section 7.3.1.1.5.1.1 describes the valve function to automatically close on a LOCA to shut the pathway from the drywell to containment should the system be in operation for testing. Section 6.2.5.2.1 of the UFSAR describes the function of valve E61F003B to open on a LOCA signal to break vacuum in the drywell via the vacuum breakers in the pathway and prevent flow of the suppression pool over the weir wall on a small break LOCA. Section 9.4.7.3 of the UFSAR further describes the ability of the drywell purge isolation valve E61F003B, which is designed to be able to shut against LOCA forces in the drywell. As described in condition report CR-GGN-2023-13833, the E61F003B valve was neither able to be fully open nor fully close, preventing it from meeting its intended safety function to shut on a LOCA as described in UFSAR, section 7.3.1.1.5.1.1.
The inspectors agreed with the licensees determination that the licensee failed to provide sufficient information in work order 00487808, to ensure the correct alignment of the motor operated actuator to the valve stem for valve E61FF003B and that the limiting conditions for operation for technical specifications 3.6.3.3 and 3.6.5.6 were not met between October 27, 2017, and June 16, 2023.
Corrective Actions: The licensee repaired and performed satisfactory post maintenance testing on valve E61F003B per WO 540006669 on June 16, 2023.
Corrective Action References: This issue was entered into the licensees corrective action program as condition report CR-GGN-2023-13838.
Performance Assessment:
Performance Deficiency: The failure to provide instructions or drawings to describe or to illustrate the proper installation of the motor-operated actuator in relation to the disc and stem for valve E61F003B as required by 10 CFR Part 50, appendix B, criterion V was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Procedure Quality attribute of the Barrier Integrity cornerstone and adversely affected the cornerstone objective to provide reasonable assurance that physical design barriers protect the public from radionuclide releases caused by accidents or events. Specifically, improper maintenance on valve E61F003B led to misalignment of the motor-operated valve actuator and valve disc and stem. This misalignment would prevent the valve from being able to shut on a LOCA as described in the UFSAR, section 7.3.1.1.5.1.1.
Significance: The inspectors assessed the significance of the finding using IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that the finding was of very low safety significance (Green) because the finding does not represent an actual open pathway in the physical integrity of reactor containment, a failure of the containment isolation system, a failure of containment pressure control equipment, a failure of containment heat removal components, or a failure of the plant's severe accident mitigation features nor does the finding involve an actual reduction in function of hydrogen igniters in the reactor containment.
Cross-Cutting Aspect: None
Enforcement:
Violation: Title 10 CFR Part 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires, in part that activities affecting quality be prescribed by documented procedures of a type appropriate to the circumstances and be accomplished in accordance with these procedures. The licensee established WO 00487808, "Drywell Purge E61F003B Inoperable, dated October 27, 2017, as the implementing procedure for repairing valve E61F003B, an activity affecting quality.
Technical Specification 3.6.3.3 limiting condition for operation requires two drywell purge subsystems to be operable during Modes 1 and 2.
Technical Specification 3.6.5.6 limiting condition for operation requires two drywell post-LOCA and two drywell vacuum relief subsystems to be operable during Modes 1, 2 and 3.
Contrary to the above, from October 27, 2017, through June 16, 2023, the licensee failed to have a procedure for repairing valve E61F003B. Specifically, WO 00478808 did not contain detailed instructions or drawings to confirm valve stem and disc orientation in relation to the motor-operated actuator. The misalignment of the stem and actuator resulted in the drywell purge subsystem, drywell post-LOCA and drywell vacuum relief subsystem being inoperable Because these systems were inoperable, the limiting conditions for operation for technical specifications 3.6.3.3 and 3.6.5.6 were not met between October 27, 2017, and June 16, 2023.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On August 17, 2023, the inspectors presented the radiation safety exit inspection results to Brad Kapellas, Site Vice President, and other members of the licensee staff.
- On August 18, 2023, the inspectors presented the technical debrief for the 71111.11 inspection results to Brad Kapellas, Site Vice President, and other members of the licensee staff.
- On August 22, 2023, the inspectors presented the formal exit for the 71111.11 inspection results to Brad Kapellas, Site Vice President, and other members of the licensee staff.
- On October 4, 2023, the inspectors presented the integrated inspection results to Brad Kapellas, Site Vice President, and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
CR-GGN-
2018-00087, 2019-04632, 2021-05734, 2022-00878, 2022-
10759, 2023-14032, 2023-15118, 2023-15297
Corrective Action
Documents
CR-GGN-
23-15564
21-07860
10/20/2021
22-04984
04/28/2022
22-07050
07/07/2023
23-00448
01/19/2023
23-01415
03/03/2023
Corrective Action
Documents
CR-GGN-
23-01417
01/19/2023
23-15422
08/30/2023
23-154233
08/30/2023
23-15424
08/30/2023
23-15426
08/30/2023
Corrective Action
Documents
Resulting from
Inspection
CR-GGN-
23-15430
08/30/2023
Medical Records for six licensed operators
Narrative Logs for RO Rover watchstanding credit hours
(8-25-21 to 8-25-23)
Operator Physical Qualification Matrix
Week 2 RO Written Examination
08/02/2023
Week 2 SRO Written Examination
08/02/2023
Written Exam Sample Plan
JPM Overlaps 2023
JPM Overlaps 2021
Scenario Overlaps 2023
Scenario Overlaps 2021
LOR attendance Record for 2021-2023
Crew C Remediation Plan
Remediation Packages for 19 Licensed Operators
2-0073
Simulator Discrepancy Report
05/25/2022
Miscellaneous
DR 21-0080
Simulator Discrepancy Report
10/13/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
DR 22-0024
Simulator Discrepancy Report
03/02/2022
DR 22-0072
Simulator Discrepancy Report
05/24/2022
DR 22-0073
Simulator Discrepancy Report
05/25/2022
DR 22-0139
Simulator Discrepancy Report
08/16/2022
DR 23-0040
Simulator Discrepancy Report
2/22/2023
DR 23-0041
Simulator Discrepancy Report
2/22/2023
DR 23-0067
Simulator Discrepancy Report
04/11/2023
GJPM-OPS-
AAD01
GJPM-OPS-
AEM04
SRO Admin JPM - Par Determination
GJPM-OPS-
AEM13
GJPM-OPS-
B3313
GJPM-OPS-
C6103
GJPM-OPS-
C7108
JPM - RPS Motor Generator Startup w/ Fire in Room
GJPM-OPS-
E12015
GJPM-OPS-
E5104
GJPM-OPS-
EOP29
JPM - Obtaining Reactor Level Without Installed
Instrumentation
GSES-LOR-
AEX44
Crew E Simulator Examination Scenario
GSES-LOR-
AEX44
Simulator Examination Scenario
GSES-LOR-
AEX48R2
Simulator Examination Scenario
GSES-LOR-
AEX83
Simulator Exam Scenario
GSES-LOR-
Crew E Simulator Examination Scenario
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
AEX83
Report 14
08/22/2023
08/22/2023
TE-31
Simulator Exam Security Checklist Completed 8/29/23
Corrective Action Program
Operation Training Program Description
Conduct Of Simulator Training
Licensed Operator Requalification Annual and Biennial
Exam Development
Procedures
System Operating
Instruction 04-1-
01-E-E12-1
VII
Containment Spray Hard Card
161
Corrective Action
Documents
CR-GGN-
23-15984, 2023-15985
Corrective Action
Documents
CR-GGN-
22-09183, 2023-14205, 2023-15466
Work Orders
WO 2997899, 544047692
Corrective Action
Documents
CR-GGN-
23-14346
Procedures
06-IC-B21-Q-1009
Corrective Action
Documents
CR-GGN-
23-13838, 2023-14471, 2023-14711, 2023-14714, 2023-
14716
Work Orders
Corrective Action
Documents
CR-GGN-
2019-07435, 2020-02668, 2020-09965, 2021-06892, 2021-
08678, 2023-02096, 2023-13838, 2023-13926, 2023-14664,
23-15186
Work Orders
WO 567598, 575509, 586008, 587309, 587424, 5403720,
54006669, 54018564
Corrective Action
Documents
CR-GGN-
20-10264, 2020-10303, 2020-11892, 2021-00869, 2021-
03512, 2021-05078, 2021-06889, 2021-06890, 2021-06896,
21-07417, 2021-09022, 2022-00020, 2022-00024, 2022-
00608, 2022-03691, 2022-06270, 2022-07721, 2022-09141,
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22-11503, 2023-01009, 2023-02379, 2023-13977
CR-HQN-
21-01473
Corrective Action
Documents
Resulting from
Inspection
CR-GGN-
23-14990
List of Liquid Permits for 2020, 2021, 2022
List of Gaseous Permits for 2020, 2021, 2022
GNRO-
21/00015
20 Grand Gulf Nuclear Station Annual Radioactive
Effluent Release Report
04/28/2021
GNRO2021/00004
Grand Gulf Nuclear Station Unit 1, Spent Fuel Storage
Radioactive Effluent Release Report for 2020
2/24/2021
GNRO2022-
00007
Grand Gulf Nuclear Station Unit 1, Spent Fuel Storage
Radioactive Effluent Release Report for 2021
2/22/2022
GNRO2022-
00018
21 Grand Gulf Nuclear Station Annual Radioactive
Effluent Release Report
04/28/2022
GNRO2023-
00003
Grand Gulf Nuclear Station Unit 1, Spent Fuel Storage
Radioactive Effluent Release Report 2022
2/16/ 2023
Miscellaneous
GNRO2023-
00013
22 Grand Gulf Nuclear Station Annual Radioactive
Effluent Release Report
04/27/2023
01-S-02-9
Offgas Vial Sampling
01-S-02-9
Operation and Calibration Instruction for Gas Flow
Proportional Counters
105
06-CH-1D17-M-
0003
Building Ventilation Gaseous Tritiums
110
06-CH-1D17-M-
0005
Building Ventilation Exhaust Gaseous Isotopic
114
06-CH-1D17-M-
0018
Gaseous Release Points Particulate Alpha Activity
110
06-CH-1D17-W-
0017
Gaseous Release Points, Iodines, Tritium and Particulates
108
06-CH-1N64-M-
0033
Offgas Post-Treatment Exhaust Gaseous Isotopic
107
Procedures
08-S-03-22
Installed Radiation Monitoring System Alarm Setpoint
115
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Determination and Control
08-S-04-14
Sample Preparation for Counting
08-S-04-218
Radiological Effluent Tracking and Dose Assessment Users
Guide
Entergy Audit
Report Number
WT-WTHQN-
21-00564
NUPIC Audit Report Number 25265 (CEXO2022-00020):
Teledyne Brown Engineering - Environmental Services;
Supplemental
03/08/2022
Entergy Audit
Report Number
WT-WTHQN-
21-00564
NUPIC Audit Report Number 25265 (CEXO2022-00020):
Teledyne Brown Engineering - Environmental Services
03/08/2022
LO-GLO-2021-
0093
Pre-NRC 71124.06 Inspection Radioactive Gaseous and
Liquid Effluent Treatment - Grand Gulf Nuclear Station
05/24/2023
Self-Assessments
QA-2/6-2021-
GGNS-1
Quality Assurance Audit Report: Combined Chemistry,
Effluents and Environmental Monitoring
09/20/2021
Corrective Action
Documents
CR-GGN-
20-10407, 2021-00046, 2021-01470, 2021-02616, 2021-
2653, 2021-04606, 2021-05174, 2021-05176, 2021-07512,
22-00110, 2022-00246, 2022-00365, 2022-00488, 2022-
00608, 2022-01090, 2022-03623, 2022-05542, 2023-00043,
23-01557, 2023-01972
Groundwater Data Summary Table, Entergy - Grand Gulf
Nuclear
06/21/2021
CFR 50.75(g)(1) Leak/Spill Record: Manhole 63, Catch
Basin 65, and Turbine Building Roof Drains and Storm Drain
System
01/06/2022
Groundwater Monitoring Plan
GGNS Offsite Dose Calculation Manual
Environmental Dosimetry Company 2020 Annual Quarterly
Assurance Status Report
03/22/2021
Environmental Dosimetry Company 2021 Annual Quarterly
Assurance Status Report
03/16/2022
Miscellaneous
Environmental Dosimetry Company 2022 Annual Quarterly
Assurance Status Report
03/24/2023
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
22 Bi-Annual Land Use Census
11/17/2022
GNRO 2020-
00013
20 Annual Radiological Environmental Operating Report
04/28/2021
GNRO 2021-
00014
21 Annual Radiological Environmental Operating Report
04/21/2022
GNRO 2021-
00015
20 Annual Radioactive Effluent Release Report
04/28/2021
GNRO 2022-
00008
22 Annual Radiological Environmental Operating Report
04/20/2023
GNRO 2022-
00018
21 Annual Radioactive Effluent Release Report
04/28/2022
GNRO 2023-
00013
22 Annual Radioactive Effluent Release Report
04/27/2023
06-IC-SC84-SA-
1003
Primary Tower Wind Speed/Win Direction, Air Temperature
(T/dT) and Relative Humidity
110
07-S-53-084-7
Backup Tower Wind Speed/Wind Direction, Air Temperature
Calibration
001
08-S-04-964
Met Data Processing
Monitoring of Nonradioactive Systems
Land Use Census
Radiological Environmental Monitoring Program
EN-CY-130-02
Radiological Environmental Monitoring Program (REMP) -
Grand Gulf Nuclear Station
Response to Contaminated Spills/Leaks
Procedures
Central Calibration Facility
Teledyne Brown Engineering Environmental Services, 1st
Quarter 2023 QA Report
05/01/2023
Self-Assessments
LO-GLO-2021-
00094
Pre-NRC Radiological Environmental Monitoring Program
(REMP) 71124.07 Self-Assessment
05/16/2023
53002124-01
SC84L600 Functional Test Met Alarms Per Work
Instructions
10/06/2022
53004666-01
06ICSC84-SA-1003 Met Tower Wind Speed, DIV N
10/07/2022
Work Orders
Replace Met Towers Wind Speed and Direction Sensors
09/15/2020