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{{#Wiki_filter: | {{#Wiki_filter:May 12, 2021 | ||
==SUBJECT:== | |||
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2021001 AND 05000529/2021001 AND 05000530/2021001 | |||
==Dear Mrs. Lacal:== | |||
On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On April 7, 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. | |||
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 or severity 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 Palo Verde Nuclear Generating Station. | |||
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Palo Verde Nuclear Generating 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, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects | |||
Docket Nos. 05000528 and 05000529 and 05000530 License Nos. NPF-41, NPF-51 and NPF-74 | |||
===Enclosure:=== | |||
As stated | |||
==Inspection Report== | |||
Docket Numbers: | |||
05000528, 05000529 and 05000530 | |||
License Numbers: | |||
NPF-41, NPF-51 and NPF-74 | |||
Report Numbers: | |||
05000528/2021001, 05000529/2021001 and 05000530/2021001 | |||
Enterprise Identifier: I-2021-001-0090 | |||
Licensee: | |||
Arizona Public Service Company | |||
Facility: | |||
Palo Verde Nuclear Generating Station | |||
Location: | |||
Tonopah, AZ | |||
Inspection Dates: | |||
January 1, 2021 to March 31, 2021 | |||
Inspectors: | |||
C. Peabody, Senior Resident Inspector | |||
E. Lantz, Resident Inspector | |||
N. Cuevas, Resident Inspector | |||
R. Alexander, Senior Emergency Preparedness Inspector | |||
N. Greene, Senior Health Physicist | |||
G. Hansen, Senior Emergency Preparedness Inspector | |||
A. Siwy, Senior Resident Inspector | |||
S. Hedger, Emergency Preparedness Inspector | |||
D. Reinert, Reactor Inspector | |||
B. Baca, Health Physicist | |||
D. Antonangeli, Health Physicist | |||
Approved By: | |||
John L. Dixon, Jr., Chief | |||
Reactor Projects Branch D | |||
Division of Reactor Projects | |||
=SUMMARY= | |||
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palo Verde Nuclear Generating 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=== | |||
Failure to Correctly Classify a Condition Adverse to Quality Associated with Turbine Driven Auxiliary Feed Water Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000528, 05000529, 05000530/2021001-01 Open/Closed | |||
[H.6] - Design Margins 71111.06 The inspectors identified a Green non-cited violation of 10 CFR 50, Appendix B, Criterion V, for the licensees failure to disposition a condition adverse to quality associated with safety-related cables in accordance with the licensees condition reporting procedure. This has led to repeated water intrusion into Class 1E electrical conduits, which could degrade cabling and affect the reliability of the turbine driven auxiliary feedwater (AFW) pump. | |||
===Additional Tracking Items=== | |||
Type Issue Number Title Report Section Status URI 05000528, 05000529, 05000530/2021001-02 10 CFR Part 37 Requirements URI 71124.08 Open | |||
=PLANT STATUS= | |||
Unit 1 operated at or near full power for the duration of the inspection period. | |||
Unit 2 entered the inspection period at full power. Between February 22 through 25, 2021, the unit had a short-term planned down power to 40 percent for condenser leakage repairs. Shortly after returning to full power on February 26, 2021, the unit tripped due to inadvertent manipulation of generator output breaker protective relay controls by personnel performing maintenance evolutions in the Palo Verde switchyard. Unit 2 was restarted on February 28, 2021 and remained at or near full power for the remainder of the inspection period. | |||
Unit 3 operated at or near full power for the duration 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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) (3 Samples)=== | |||
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains: | |||
: (1) Unit 1, high pressure safety injection B, on January 21, 2021 | |||
: (2) Unit 2, Class 1E 125Vdc batteries B and D during startup transformer NANX02 outage, on February 10, 2021 | |||
: (3) Unit 3, essential spray pond system B during planned maintenance on diesel generator A, on March 2, 2021 | |||
==71111.05 - Fire Protection== | |||
===Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 3, main turbine operating deck and main turbine bearings, Fire Zones TB9 and TB10, on February 10, 2021 | |||
: (2) Unit 1, Class 1E 4kV switchgear A, Fire Zone 5A, on March 11, 2021 | |||
: (3) Unit 2, Class 1E 4kV switchgear A, Fire Zone 5A, on March 11, 2021 | |||
: (4) Unit 3, high pressure safety injection pump A, Fire Zone 31A, on March 12, 2021 | |||
==71111.06 - Flood Protection Measures== | |||
===Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)=== | |||
The inspectors evaluated internal flooding mitigation protections in the: | |||
: (1) Unit 1, turbine driven auxiliary feedwater pump room, on January 2, 2021 | |||
===Cable Degradation (IP Section 03.02) (1 Sample)=== | |||
The inspectors evaluated cable submergence protection in: | |||
: (1) Unit 3, diesel generator B fuel vault, on March 24, 2021 | |||
==71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance== | |||
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample) | |||
: (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 reactor startup, on February 28, 2021. | |||
===Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)=== | |||
: (1) The inspectors observed and evaluated operator requalification simulator training activities, on March 17, 2021. | |||
==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) Unit 1, safety injection system performance monitoring criteria exceeded due to safety injection tank vent valves SIA-608 and SIB-633 failing to close, on February 13, 2021 | |||
: (2) Unit 2, condition monitoring and maintenance plan for radwaste level transmitter failure, on February 13, 2021 | |||
==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) Unit 1, repair of main steam isolation valve B thermal relief valve manifold assembly, on February 4, 2021 | |||
: (2) Unit 3, revised weekly risk assessment for extended diesel generator A outage from previous week displacing planned maintenance on high pressure safety injection pump A, on March 8, 2021 | |||
: (3) Unit 3, weekly risk assessment diesel generator, spray pond, essential cooling water, and essential chilled water planned maintenance, on March 28, 2021 | |||
==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) Unit 1, missed valve position indication test following maintenance for containment power access purge isolation valve, on February 17, 2021 | |||
: (2) Unit 1, main steam support structure door 1-CA01 locking mechanism malfunctioning, on March 11, 2021 | |||
: (3) Unit 3, diesel generator B sump pump failed to start, on March 12, 2021 | |||
: (4) Unit 1, 2, and 3, charging line containment isolation valve CH-560 limit switches may not provide reliable position indications during loss of cooling accident (LOCA) event submergence, on March 12, 2021 | |||
: (5) Unit 2, charging pump A missed vibration data gathering during surveillance testing, on March 30, 2021 | |||
==71111.19 - Post-Maintenance Testing== | |||
===Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)=== | |||
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality: | |||
: (1) Unit 1, inspect and adjust Class 1E 480V Circuit Breaker 1EPHBM3607, on March 25, 2021 | |||
: (2) Unit 3, inspect and adjust Class 1E 480V Circuit Breaker 3EPHBM3810, on March 25, 2021 | |||
: (3) Unit 3, A diesel generator post-maintenance testing on replaced air start valves, on March 31, 2021 | |||
==71111.20 - Refueling and Other Outage Activities== | |||
===Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)=== | |||
: (1) The inspectors evaluated Unit 2 forced outage activities following reactor trip from February 26 to 28, 2021. | |||
==71111.22 - Surveillance Testing== | |||
The inspectors evaluated the following surveillance tests: | |||
===Surveillance Tests (other) (IP Section 03.01)=== | |||
{{IP sample|IP=IP 71111.22|count=2}} | |||
: (1) Unit 3, control element assembly operability check surveillance test risk informed documented evaluation for a one-time extension of frequency from every nine months to annually under the surveillance frequency control program, on January 12, 2021 | |||
: (2) Unit 1, observed engineered safety features actuation system train B relay testing (main steam isolation signal, recirculation actuation signal, containment isolation actuation signal), on March 15, 2021 | |||
===Inservice Testing (IP Section 03.01) (1 Sample)=== | |||
: (1) Unit 1, observed safety injection train B emergency core cooling system throttle valve inservice testing, on March 23, 2021 | |||
==71114.01 - Exercise Evaluation== | |||
Inspection Review (IP Section 02.01-02.11) (1 Partial) | |||
(1) | |||
(Partial) | |||
The inspectors evaluated the biennial emergency plan exercise which was conducted on March 9, 2021. However, as of the end of the 1st Quarter 2021, the licensee had not completed its critique process for the exercise. As such, the inspectors were unable to complete the full evaluation of the exercise and the critique process. The inspectors will complete the inspection early in the 2nd Quarter, and the results of the inspection will be documented in that report. | |||
==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 recently submitted Emergency Action Level and Emergency Plan changes. | |||
* PVNGS Emergency Plan Revisions 67 and 68 | |||
This evaluation does not constitute NRC approval. | |||
==71114.08 - Exercise Evaluation Scenario Review== | |||
===Inspection Review (IP Section 02.01 - 02.04) (1 Sample)=== | |||
: (1) The inspectors reviewed the licensee's preliminary exercise scenario which was submitted to the NRC on December 18, 2020 (ADAMS Accession No. | |||
ML20353A421), for the exercise scheduled to occur on March 9, 2021. The inspectors discussed the preliminary scenario with Ms. C. Shields, Manager, Emergency Preparedness, and other members of the emergency preparedness staff on February 3, 2021. The inspectors' review does not constitute NRC approval of the scenario. | |||
==RADIATION SAFETY== | |||
==71124.05 - Radiation Monitoring Instrumentation== | |||
===Calibration and Testing Program (IP Section 03.02) (15 Samples)=== | |||
The inspectors evaluated the calibration and testing of the following radiation detection instruments: | |||
: (1) Eberline AMS 4, SN #112914, 08/05/2020 | |||
: (2) Econoair Plus L-12P Personal Air Sampler, SN #1741, 12/11/2020 | |||
: (3) Ludlum Model 3 Count Rate Meter, SN #231550, 07/08/2020 | |||
: (4) GM Probe, SN #13478, 12/04/2020 | |||
: (5) AMP-100, SM #5014035, 09/17/2020 | |||
: (6) RO-20 Meter, SN #1411, 09/09/2020 | |||
: (7) RO-7 Meter, SN #679, 10/24/2020 | |||
: (8) Neutron Detector, SN #110762, 10/30/2020 | |||
: (9) Air Sampler - Charcoal, SN #16456, 12/04/2020 | |||
: (10) Small Article Monitor (SAM) 12, SN #6700, 10/28/2020 | |||
: (11) Small Article Monitor (SAM) 12, SN #6710, 11/18/2020 | |||
: (12) ThermoFisher Scientific Personal Contamination Monitor (PM-12), SN #12018, 09/03/2020 | |||
: (13) ThermoFisher Scientific Personal Contamination Monitor (PM-12), SN #1213, 11/17/2020 | |||
: (14) ThermoFisher Scientific iPCM 12, SN #112021, 11/20/2020 | |||
: (15) ThermoFisher Scientific iPCM 12, SN #12019, 08/14/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples) | |||
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation: | |||
: (1) RU-200, Radioactive Liquid Effluent Monitor | |||
: (2) RU-144, Plant Vent Radiation Monitor High | |||
: (3) RU-14, Radwaste Effluent Radiation Monitor | |||
==71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &== | |||
Transportation | |||
===Waste Characterization and Classification (IP Section 03.03) (3 Samples)=== | |||
The inspectors evaluated the licensees characterization and classification for the following radioactive waste streams: | |||
: (1) Unit 1 Resin Stream for 2020 | |||
: (2) Unit 2 Resin Stream for 2020 | |||
: (3) Unit 2 Dry Active Waste stream for 2020 | |||
===Shipping Records (IP Section 03.05) (5 Samples)=== | |||
The inspectors evaluated the following non-excepted radioactive material shipments through a record review: | |||
(1)19-RW-018, LSA - II, Dewatered Resin (2)19-RW-023, LSA - I, Concentrates (3)20-RW-012, LSA - II, Dewatered Resin (4)20-RW-031, LSA - II, Dewatered Resin (5)20-RW-034, LSA - II, Dewatered Resin | |||
==OTHER ACTIVITIES - BASELINE== | |||
===71151 - Performance Indicator Verification | |||
The inspectors verified licensee performance indicators submittals listed below: | |||
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01)=== | |||
{{IP sample|IP=IP 71151|count=3}} | |||
: (1) Unit 1, January 1, 2020 through December 31, 2020 | |||
: (2) Unit 2, January 1, 2020 through December 31, 2020 | |||
: (3) Unit 3, January 1, 2020 through December 31, 2020 | |||
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (3 Samples) | |||
: (1) Unit 1, January 1, 2020 through December 31, 2020 | |||
: (2) Unit 2, January 1, 2020 through December 31, 2020 | |||
: (3) Unit 3, January 1, 2020 through December 31, 2020 | |||
===IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (3 Samples)=== | |||
: (1) Unit 1, January 1, 2020 through December 31, 2020 | |||
: (2) Unit 2, January 1, 2020 through December 31, 2020 | |||
: (3) Unit 3, January 1, 2020 through December 31, 2020 | |||
===MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04) (3 Samples)=== | |||
: (1) Unit 1, January 1, 2020 through December 31, 2020 | |||
: (2) Unit 2, January 1, 2020 through December 31, 2020 | |||
: (3) Unit 3, January 1, 2020 through December 31, 2020 | |||
===EP01: Drill/Exercise Performance (IP Section 03.12) (1 Sample)=== | |||
: (1) January 1, 2020 through December 31, 2020 | |||
===EP02: ERO Drill Participation (IP Section 03.13) (1 Sample)=== | |||
: (1) January 1, 2020 through December 31, 2020 | |||
===EP03: Alert & Notification System Reliability (IP Section 03.14) (1 Sample)=== | |||
: (1) January 1, 2020 through December 31, 2020 | |||
===71153 - Followup of Events and Notices of Enforcement Discretion | |||
Event Followup (IP Section 03.01)=== | |||
{{IP sample|IP=IP 71153|count=1}} | |||
: (1) The inspectors evaluated Unit 2 automatic reactor trip and licensees response on February 26, | |||
==INSPECTION RESULTS== | |||
Failure to Correctly Classify a Condition Adverse to Quality Associated with Turbine Driven Auxiliary Feed Water Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems | |||
Green NCV 05000528, 05000529, 05000530/2021001-01 Open/Closed | |||
[H.6] - Design Margins 71111.06 The inspectors identified a Green non-cited violation of 10 CFR 50, Appendix B, Criterion V, for the licensees failure to disposition a condition adverse to quality associated with safety-related cables in accordance with the licensees condition reporting procedure. This has led to repeated water intrusion into Class 1E electrical conduits, which could degrade cabling and affect the reliability of the turbine driven auxiliary feedwater (AFW) pump. | |||
=====Description:===== | |||
On August 22, 2019, indication of water intrusion was found on a junction box and two electrical conduits that penetrate down through the 100 foot train A auxiliary feed pump room. The licensee identified deposits from previous water intrusion and corrosion on the bottom of the junction box around the junction box cover. The union on conduit 1EZCAEARK63, which transitions between an unlabeled junction box and another junction box 1EZCAEAKKJ17 (J17), also had signs of water leaking out of the fittings indicating that water had entered the conduit at some point in the past. The licensee screened this issue as not a condition adverse to quality, entered it into the Performance Monitoring Program, and assigned a corrective maintenance work order to correct the condition per condition report CR 19-10684. | |||
Per step 4.5.2 of licensee procedure, 01DP-0AP12, Condition Reporting Process, Revision 34 the screening committee classifies condition reports as either a significant condition adverse to quality, condition adverse to quality, or not a condition adverse to quality. This same procedure defines a condition adverse to quality as an all-inclusive term used in reference to failures, malfunctions, deficiencies, defective items, and non-conformances in items, activities, software and services that fall within the current licensing basis. | |||
On January 1, 2021, the licensee observed water dripping from electrical conduit junction box J17 and after further evaluation determined that the source of water leakage was from main steam safety valves condensation overflow above which was spilling onto junction box 1EZC2EAKKJ04 (J04) at the 120 foot level. Per evaluation 21-00021-004, water flowed from junction box J04 down through the internal side of two electrical conduit penetrations into junction box J17 leaking into the AFW pump room. The main steam safety valve condensation is handled by a temporary drip catch which diverts the flow away from the junction box, however, in August 2019 and January 2021, that temporary drip catch had a clogged collection standpipe resulting in overflow onto junction box J04. | |||
The inspectors concluded that the disposition on August 22, 2019, as not a condition adverse to quality was incorrect because safety-related power cables in this conduit provide electrical power to the turbine governor and valves associated with train A AFW pump, which is described in the current licensing basis. Therefore, continued water intrusion as observed on January 1, 2021, could degrade the electrical cabling and affect the reliability of the auxiliary feedwater system components. | |||
The inspectors visually examined junction box J04 and it was apparent that water had been pooling on the roof of the junction box challenging the front side cover seal. Until the licensee corrects the configuration to prevent pooling on the top of the junction box, it will likely continue to leak into the cable conduit when wetted. | |||
Corrective Actions: Per evaluation report 21-00013, junction boxes J17 and J04 will be inspected for drain holes if not already installed or inspected for drain hole-clogging if already installed. | |||
Corrective Action References: Condition Reports 21-00013 and 21-03848 | |||
=====Performance Assessment:===== | |||
Performance Deficiency: The licensee failed to correctly classify a condition adverse to quality in accordance with step 4.5.2 of licensee procedure, 01DP-0AP12, Condition Reporting Process. Specifically, during the screening committee review of Condition Report 19-10684, the licensee classified water intrusion into safety-related junction boxes and electrical conduits related to Class 1E electrical cabling and turbine driven AFW pump train A as a condition not adverse to quality. | |||
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the performance deficiency resulted in repeated water intrusion into junction boxes and conduits which could degrade cabling and affect the reliability of the turbine driven AFW pump. | |||
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions. finding was determined to be of very low safety significance (Green) because it | |||
: (1) was not a design deficiency, | |||
: (2) did not represent a loss of system and/or function, | |||
: (3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time, | |||
: (4) did not represent a loss of the probabilistic risk assessment (PRA) function of two separate technical specification systems for greater than 24 hours, | |||
: (5) did not represent a loss of a PRA system and/or function for greater than 24 hours, and | |||
: (6) did not result in the loss of a high safety-significant, nontechnical specification train. | |||
Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Specifically, when water intrusion into safety-related junction boxes and electrical conduits was found on August 22, 2019, the licensee failed to maintain safety-related equipment and incorrectly screened this issue as not a condition adverse to quality. | |||
=====Enforcement:===== | |||
Violation: 10 CFR 50 Appendix B, Criterion V, requires, in part, that activities affecting quality shall be accomplished in accordance with instructions, procedures or drawings. Procedure 01DP-0AP12, Condition Reporting Process, Revision 34, step 4.5.2, requires that the licensee screening committee assigns the condition report an appropriate quality classification. | |||
Contrary to the above, on August 22, 2019, the licensee failed to accomplish an activity affecting quality in accordance with instructions, procedures, or drawings. Specifically, during condition report screening, an activity that affects quality, the licensee failed to assign the correct level of classification to junction box water intrusion, which could affect the reliability of the turbine driven AFW pump, as a condition adverse to quality, in accordance with procedure 01DP-0AP12. | |||
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy. | |||
Unresolved Item (Open)10 CFR Part 37 Requirements URI URI 05000528, 05000529, 05000530/2021001-02 71124.08 | |||
=====Description:===== | |||
The inspectors, while conducting a public radiation safety baseline inspection, identified numerous issues of concern regarding the implementation of 10 CFR Part 37 requirements during their review of the controls for an aggregated Category 2 quantity of radioactive material. The inspection was conducted the week of January 11, 2021, using IP 71124.08, Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation. The inspectors informed the licensee of the issues of concern regarding the implementation of the 10 CFR Part 37 requirements, specifically associated with 10 CFR 37.49(a)(3)(ii), 37.51(a), and 37.51(b). | |||
10 CFR 37.49(a)(3)(ii) requires, in part, for Category 2 quantities of radioactive material, that the licensee shall establish and maintain weekly verification through physical checks, tamper indicating devices, use, or other means to ensure that the radioactive material is present. | |||
10 CFR 37.51 requires, in part, | |||
: (a) that the licensee shall implement a maintenance and testing program to ensure that intrusion alarms, associated communication systems, and other physical components of the systems used to secure or detect unauthorized access to radioactive material are maintained in operable condition and are capable of performing their intended function when needed; and | |||
: (b) that the licensee shall maintain records on the maintenance and testing activities for 3 years. | |||
These issues of concern relative to the control of Category 2 radioactive material required additional information and review to determine whether the licensee performance constituted violations of NRC requirements. Consequently, we are considering this matter as an Unresolved Item (URI). | |||
Planned Closure Actions: The inspectors plan to continue their review of documentation provided by the licensee as it is made available, as well as hold discussions to resolve these issues of concern. This review will be a comprehensive assessment of all associated violations and/or findings related to these potential issues identified. The results of the final determination of these 10 CFR Part 37 violations, if validated, will be documented in a standalone report due to the security-related aspects of the potential violations. | |||
Licensee Actions: The licensee placed this matter into their corrective action program for review and implementation of corrective actions. The licensee used the corrective action program to document their corrective actions already taken and planned, as well as communicated them to the inspectors. Thus far, the licensee has been very responsive to the potential violations. The licensee has already addressed perceived gaps the inspectors identified in the implementation of 10 CFR Part 37 requirements. | |||
Corrective Action References: CR-21-03309 | |||
==EXIT MEETINGS AND DEBRIEFS== | |||
The inspectors verified no proprietary information was retained or documented in this report. | |||
* On February 4, 2021, the inspectors presented the Radiation Safety inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff. | |||
* On March 11, 2021, the inspectors presented the EP Performance Indicator Verification and Emergency Plan Changes inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff. | |||
* On April 7, 2021, the inspectors presented the integrated inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff. | |||
* On April 22, 2021, the inspectors discussed the integrated inspection results to Mr. Matt Kura, Department Leader, Nuclear Regulatory Affairs, and other members of the licensee staff. | |||
* On April 28, 2021, the inspectors debriefed the 10 CFR Part 37 Requirements URI with Mr. Todd Horton, Senior Vice President, Site Operations. | |||
=DOCUMENTS REVIEWED= | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
71111.04 | |||
Drawings | |||
01-M-SIP-001 | |||
P& I Diagram Safety Injection & Shutdown Cooling System | |||
2 | |||
71111.04 | |||
Drawings | |||
01-M-SIP-002 | |||
P& I Diagram Safety Injection & Shutdown Cooling System | |||
044 | |||
71111.04 | |||
Drawings | |||
03-M-SPP-001 | |||
P& I Diagram Essential Spray Pond System | |||
071 | |||
71111.04 | |||
Drawings | |||
03-M-SPP-002 | |||
P& I Diagram Essential Spray Pond System | |||
019 | |||
71111.05 | |||
Miscellaneous | |||
PVGS Pre-Fire Strategies Manual | |||
71111.05 | |||
Miscellaneous | |||
USAR Section 9B | |||
Fire Hazards Analysis | |||
71111.06 | |||
Calculations | |||
13-MC-ZA-0807 | |||
MSSS 100 Elevation Flooding Evaluation | |||
71111.06 | |||
Calculations | |||
13-MC-ZA-0808 | |||
MSSS 81 Elevation Flooding Evaluation | |||
71111.06 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
21-00013, 21-00016, 21-00021, 20-03848, 20-16841, 19- | |||
10684 | |||
71111.11Q Miscellaneous | |||
NLR21S020201 | |||
Licensed Operator Training Simulator Scenario: LOCA / | |||
Loss of Class Instrument / Rapid Downpower | |||
2/24/2021 | |||
71111.12 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
20-15752, 20-15757, 20-15943, 20-15954, 20-16314 | |||
71111.12 | |||
Miscellaneous | |||
20-15752-003 | |||
MRFF Evaluation | |||
71111.12 | |||
Miscellaneous | |||
20-15752-004 | |||
Level 3 Evaluation Report | |||
71111.12 | |||
Miscellaneous | |||
20-15757-003 | |||
MRFF Evaluation | |||
71111.12 | |||
Miscellaneous | |||
20-15757-004 | |||
Level 3 Evaluation Report | |||
71111.12 | |||
Miscellaneous | |||
Level 3 | |||
Evaluation Report | |||
Maintenance Rule Expert Panel Meeting 633 | |||
2/04/2021 | |||
71111.12 | |||
Miscellaneous | |||
SI-2503 | |||
Maintenance Rule (a)(1) Issue Tracking Form | |||
71111.12 | |||
Procedures | |||
70DP-0MR01 | |||
Maintenance Rule | |||
71111.13 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
21-00853 | |||
71111.13 | |||
Miscellaneous | |||
U1 MSIV RICT Projection Details | |||
2/04/2021 | |||
71111.13 | |||
Miscellaneous | |||
U1 MSIV Risk Management and Readiness Plan | |||
2/03/2021 | |||
71111.13 | |||
Miscellaneous | |||
EOOS 4.1 | |||
Weekly Schedulers Evaluation for PV Unit 3 Mar 8-14 | |||
2/17/2021, | |||
03/8/2021 | |||
71111.13 | |||
Miscellaneous | |||
EOOS 4.1 | |||
Weekly Schedulers Evaluation for PV Unit 3 Mar 22-28 | |||
03/25/2021 | |||
71111.13 | |||
Miscellaneous | |||
Phoenix Risk | |||
Monitor | |||
WW 2112 Schedule Evaluation (3/22-28/2021) | |||
03/23/2021 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
71111.13 | |||
Miscellaneous | |||
Phoenix Risk | |||
Monitor | |||
WW 2110 Schedule Evaluation (3/8-14/2021) | |||
2/17/2021, | |||
03/8/2021 | |||
71111.13 | |||
Miscellaneous | |||
RICT-U1-2021-01 | |||
Risk Informed Completion Time Summary | |||
2/04/2021 | |||
71111.13 | |||
Miscellaneous | |||
Risk Challenge | |||
Meeting | |||
Risk Challenge Meeting for U1 MSIV-171 Repair | |||
2/03/2021 | |||
71111.13 | |||
Procedures | |||
2DP-0RS01 | |||
Online Integrated Risk | |||
71111.13 | |||
Procedures | |||
40DP-9RS01 | |||
Operations Department Online Nuclear Risk Determination | |||
in Modes 1 and 2 | |||
71111.13 | |||
Procedures | |||
40DP-9RS03 | |||
Risk Management Actions | |||
71111.13 | |||
Work Orders | |||
5310300 | |||
71111.15 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
21-01818, 21-02855, 21-02888 | |||
71111.15 | |||
Miscellaneous | |||
Updated Final Safety Analysis Report | |||
20B | |||
71111.15 | |||
Miscellaneous | |||
21-01818-002 | |||
Engineering Evaluation | |||
71111.15 | |||
Miscellaneous | |||
EEQ-N007-001 | |||
Namco EA180 Limit Switches | |||
71111.15 | |||
Procedures | |||
40DP-9OP26 | |||
Operations Condition Reporting Process and Operability | |||
71111.15 | |||
Procedures | |||
40DP-9ZZ17 | |||
Control of Doors, Hatches, and Floor Plugs | |||
71111.15 | |||
Procedures | |||
73ST-9XI15 | |||
CP (Power Access Purge) Valves - Inservice Test | |||
71111.15 | |||
Work Orders | |||
5159840 | |||
71111.19 | |||
Procedures | |||
2MT-9ZZ74 | |||
Molded Case Circuit Breaker Test | |||
71111.19 | |||
Work Orders | |||
5062359, 5202497 | |||
71111.22 | |||
Miscellaneous | |||
Plant Review | |||
Board | |||
STRIDE PRB Approval Meeting for CEA Operability Checks | |||
01/12/2021 | |||
71111.22 | |||
Procedures | |||
01DP-0RS01 | |||
Surveillance Frequency Control Program | |||
71111.22 | |||
Procedures | |||
01DP-0RS02 | |||
Surveillance Test Risk Informed Documented Evaluation | |||
(STRIDE) Process | |||
71111.22 | |||
Procedures | |||
70DP-0RA06 | |||
PRA Methodology for Evaluating Changes to Surveillance | |||
Test Intervals | |||
71111.22 | |||
Procedures | |||
PVN-N-0034 | |||
STRIDE for One-Time Change for DEA Operability Checks | |||
71114.01 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
19-03672, 19-03691, 19-05088, 19-08356, 19-13385, 19- | |||
13930, 19-17244, 20-01446, 20-01527, 20-03432, 20- | |||
03738, 20-04408, 20-04999, 20-14892, 20-15325, 20- | |||
15510, 20-16537, 20-16863 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
71114.01 | |||
Miscellaneous | |||
2-05627 | |||
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, | |||
and 3; Docket No. STN 50-528; 50-529; 50-530 and 72-44; | |||
License No. NPF-41; NPF-51; NPF-74; Response Providing | |||
Information Regarding Implementation Details for the Phase | |||
and 3 Mitigation Strategies | |||
01/11/2007 | |||
71114.01 | |||
Procedures | |||
16DP-0EP31 | |||
Emergency Preparedness Equipment Out of Service | |||
71114.01 | |||
Procedures | |||
40AO-9ZZ23 | |||
Loss of SFP Level or Cooling | |||
71114.01 | |||
Procedures | |||
40AO-9ZZ24 | |||
Deliberate Acts Against PVNGS | |||
71114.01 | |||
Procedures | |||
40MG-9ZZ05 | |||
Extensive Damage Mitigation Guidelines | |||
71114.01 | |||
Procedures | |||
40MG-9ZZ05-001 | |||
EDMG Command and Control | |||
71114.01 | |||
Procedures | |||
40MG-9ZZ05-002 | |||
Mitigating Guidelines Supplemental Strategies | |||
71114.01 | |||
Procedures | |||
40MG-9ZZ07 | |||
FLEX Support Guidelines | |||
71114.01 | |||
Procedures | |||
40MG-9ZZ07-001 | |||
FLEX Support Guidelines, Modes 1, 2, 3, or 4 | |||
71114.01 | |||
Procedures | |||
EP-0900 | |||
Emergency Response Organization (ERO) Position | |||
Checklists | |||
71114.01 | |||
Procedures | |||
EP-0901 | |||
Classifications | |||
71114.01 | |||
Procedures | |||
EP-0905 | |||
Protective Actions | |||
71114.04 | |||
Miscellaneous | |||
PVNGS Emergency Plan | |||
67, 68 | |||
71114.04 | |||
Miscellaneous | |||
Emergency Plan Evaluation - Medical Support During a | |||
Public Health Emergency | |||
2/17/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-001e | |||
Emergency Plan Revision 67 Effectiveness Evaluation Form | |||
05/05/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-002s | |||
Transitioning the Operations Advisor - STSC position to a | |||
pooled position Screening Evaluation Form | |||
03/17/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-003e | |||
Emergency Plan Revision 68 Effectiveness Evaluation Form | |||
2/16/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-003e, | |||
Revision 1 | |||
Emergency Plan Revision 68 Effectiveness Evaluation Form | |||
2/16/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-003s | |||
Emergency Plan Revision 67 Screening Evaluation Form | |||
05/01/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-004s | |||
Emergency Plan Revision 68 Screening Evaluation Form | |||
07/30/2020 | |||
71114.04 | |||
Miscellaneous | |||
20-005s | |||
Update to the Palo Verde Emergency Planning Zone (EPZ) | |||
population Screening Evaluation Form | |||
2/10/2020 | |||
71114.08 | |||
Miscellaneous | |||
1904 ERO Mini Drill - ERO Green Team (June 4, 2019); | |||
1905 ERO Mini Drill - ERO Blue Team (June 11, 2019); | |||
1906 ERO Mini Drill - ERO Red Team (June 18, 2019) | |||
10/29/2019 | |||
71114.08 | |||
Miscellaneous | |||
1907 ERO Mini Drill - ERO Red Team (September 10, | |||
10/23/2019 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
2019); 1909 ERO Mini Drill - ERO Green Team (September | |||
24, 2019) | |||
71114.08 | |||
Miscellaneous | |||
1910 ERO Mini Drill Report - ERO White Team (December | |||
10, 2019) | |||
01/2/2020 | |||
71114.08 | |||
Miscellaneous | |||
240-02859 | |||
CS/SW | |||
1901 Full-Scale Dress Rehearsal - ERO Gold Team | |||
(February 2019) | |||
06/13/2019 | |||
71114.08 | |||
Procedures | |||
EP-0905 | |||
Protective Actions | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 04908361 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 3 | |||
2/19/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 05091219 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 3 | |||
06/25/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 4904815 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 2 | |||
01/03/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 4906938 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 1 | |||
01/03/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 4925134 | |||
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit | |||
04/27/2018 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 4981791 | |||
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit | |||
2/12/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 4981791 | |||
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit | |||
2/12/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5005338 | |||
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit | |||
05/01/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5027206 | |||
RU-151 Radiation Monitor | |||
10/26/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5027531 | |||
RU-141 Radiation Monitor | |||
11/18/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5037715 | |||
RU-30 Radiation Monitor | |||
11/12/2019 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5074919 | |||
RU-157 Radiation Monitor | |||
2/27/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5081319 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 2 | |||
06/19/2020 | |||
71124.05 | |||
Calibration | |||
WO 5085209 | |||
RU-143 Plant Ventilation Monitor, Low Range - Unit 1 | |||
06/22/2020 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
Records | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5086713 | |||
RU-150 Radiation Monitor | |||
04/09/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5111166 | |||
RU-145 Fuel Building B Ventilation Exhaust Monitor, Low | |||
Range - Unit 3 | |||
07/15/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5111180 | |||
RU-146 Fuel Building B Ventilation Exhaust Monitor, High | |||
Range - Unit 3 | |||
10/16/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5145645 | |||
RU-15 Waste Gas Area Combined Ventilation Exhaust | |||
Monitor - Unit 1 | |||
09/22/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5151446 | |||
RU-1 Radiation Monitor | |||
11/07/2020 | |||
71124.05 | |||
Calibration | |||
Records | |||
WO 5151451 | |||
RU-148 Radiation Monitor | |||
11/12/2020 | |||
71124.05 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
19-00740, 19-01086, 19-02060, 19-02467, | |||
19-02886, 19-03691, 19-05830, 19-06030, | |||
19-06237, 19-08355, 19-08808, 19-12890, | |||
19-13509, 19-13899, 19-16388, 19-17175, | |||
19-17244, 19-18312, 20-00153, 20-00391, | |||
20-00576, 20-01188, 20-02588, 20-04408, | |||
20-04707, 20-04730, 20-07625, 20-08012, | |||
20-08563, 20-09920, 20-12560, 20-12803, | |||
20-13297, 20-15324, 20-15678, 20-16032 | |||
71124.05 | |||
Miscellaneous | |||
2018 Annual Radioactive Effluent Release Report | |||
04/16/2019 | |||
71124.05 | |||
Miscellaneous | |||
2019 Annual Radioactive Effluent Release Report | |||
04/17/2020 | |||
71124.05 | |||
Miscellaneous | |||
Offsite Dose Calculation Manual PVNGS Units 1, 2, and 3 | |||
71124.05 | |||
Miscellaneous | |||
Portal Monitors (PM) and Personal Contamination Monitors | |||
(PCM) Alarm Setpoints | |||
01/05/2021 | |||
71124.05 | |||
Miscellaneous | |||
Instrument Calibration Data Point Sheet | |||
10/18/2020 | |||
71124.05 | |||
Miscellaneous | |||
Unit 1 2019-2020 Inoperable Effluent Monitor Logs | |||
2/31/2020 | |||
71124.05 | |||
Miscellaneous | |||
Unit 2 2019-2020 Inoperable Effluent Monitor Logs | |||
2/31/2020 | |||
71124.05 | |||
Miscellaneous | |||
Unit 3 2019-2020 Inoperable Effluent Monitor Logs | |||
2/31/2020 | |||
71124.05 | |||
Miscellaneous | |||
Special Report 1- | |||
SR-2019-001-00 | |||
Palo Verde Nuclear Generating Station (PVNGS) Unit 1, | |||
Docket No. STN 50-528 /License No. NPF 51, Special | |||
Report 1-SR-2019-001-00: Non-functionality of a fuel | |||
04/26/2019 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
building ventilation system high range radioactive gaseous | |||
effluent monitor for more than 7 days | |||
71124.05 | |||
Procedures | |||
74DP-0CH02 | |||
Analytical Instrument Quality Control (QC) | |||
71124.05 | |||
Procedures | |||
74RM-9EF43 | |||
Actions For Non-Functional Radiation Monitors: Preplanned | |||
Alternate Sampling Program | |||
71124.05 | |||
Procedures | |||
74ST-9SQ10 | |||
Train "A" Radiation Monitoring Quarterly Functional Test | |||
Procedure | |||
71124.05 | |||
Procedures | |||
74ST-9SQ20 | |||
RU-1 Calibration Test | |||
71124.05 | |||
Procedures | |||
74ST-9SQ21 | |||
Radiation Monitoring Calibration Test for Baseline Process | |||
Monitors | |||
71124.05 | |||
Procedures | |||
74ST-9SQ22 | |||
Train "A" Radiation Monitoring Calibration Test for Baseline | |||
Area Monitors | |||
71124.05 | |||
Procedures | |||
74ST-9SQ23 | |||
Train "A" Radiation Monitoring Calibration Test for | |||
Containment New Scope Area Monitors | |||
71124.05 | |||
Procedures | |||
74ST-9SQ27 | |||
Radiation Monitoring Calibration Test for RU-144 | |||
71124.05 | |||
Procedures | |||
75RP-9EQ13 | |||
Canberra Whole Body Counting System Calibration | |||
71124.05 | |||
Procedures | |||
75RP-9EQ22 | |||
Calibration of Counter Scalers | |||
71124.05 | |||
Procedures | |||
75RP-9EQ56 | |||
Calibration of the RO-2 and RO-20A Ion Chambers | |||
71124.05 | |||
Procedures | |||
75RP-9ME20 | |||
Canberra APEX - In Vivo Whole Body Counting System | |||
Calibration | |||
71124.05 | |||
Self-Assessments IPA-RP2020S1 | |||
Integrated Performance Assessment Report: Radiation | |||
Protection - 1st Half 2020 (07/24/2020) | |||
09/02/2020 | |||
71124.05 | |||
Self-Assessments SR-20-0021 | |||
NAD Surveillance Report: 2020 Radiation Safety | |||
Performance Evaluation | |||
07/23/2020 | |||
71124.05 | |||
Work Orders | |||
5010217 | |||
74ST9SQ042 Effluent Monitor Monthly Source Checks Unit | |||
2: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
08/15/2019 | |||
71124.05 | |||
Work Orders | |||
5010218 | |||
74ST9SQ043 Effluent Monitor Monthly Source Checks Unit | |||
3: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
08/15/2019 | |||
71124.05 | |||
Work Orders | |||
5011137 | |||
74ST9SQ041 Effluent Monitor Monthly Source Checks Unit | |||
1: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
08/15/2019 | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
71124.05 | |||
Work Orders | |||
5030412 | |||
74ST9SQ042 Effluent Monitor Monthly Source Checks Unit | |||
2: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
10/17/2019 | |||
71124.05 | |||
Work Orders | |||
5030413 | |||
74ST9SQ043 Effluent Monitor Monthly Source Checks Unit | |||
3: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
10/21/2019 | |||
71124.05 | |||
Work Orders | |||
5031145 | |||
74ST9SQ041 Effluent Monitor Monthly Source Checks Unit | |||
1: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and | |||
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent | |||
Monitor | |||
10/17/2019 | |||
71124.08 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
19-02590, 19-07431, 19-11705, 19-18567, 20-02759, 20- | |||
2763, 20-14858 | |||
71124.08 | |||
Miscellaneous | |||
December 2020 Radwaste Inventory | |||
2/2/2020 | |||
71124.08 | |||
Miscellaneous | |||
Waste /Material Characteristic Summary for Part 61 Waste | |||
Stream Analysis - Unit 1 DAW - 2020 | |||
2/17/2020 | |||
71124.08 | |||
Miscellaneous | |||
Waste /Material Characteristic Summary for Part 61 Waste | |||
Stream Analysis - Unit 1 DAW - 2020 | |||
2/17/2020 | |||
71124.08 | |||
Miscellaneous | |||
Waste /Material Characteristic Summary for Part 61 Waste | |||
Stream Analysis - Unit 2 DAW -2020 | |||
05/12/2020 | |||
71124.08 | |||
Miscellaneous | |||
Waste /Material Characteristic Summary for Part 61 Waste | |||
Stream Analysis - Unit 1 Resin - 2020 | |||
05/14/2020 | |||
71124.08 | |||
Miscellaneous | |||
Waste /Material Characteristic Summary for Part 61 Waste | |||
Stream Analysis - Unit 2 Resin - 2020 | |||
2/09/2020 | |||
71124.08 | |||
Miscellaneous | |||
75ST-9ZZ02 | |||
Radioactive Source Leak Test Surveillance Sheet | |||
01/26/2020 | |||
71124.08 | |||
Miscellaneous | |||
75ST-9ZZ02 | |||
Radioactive Source Leak Test Surveillance Sheet | |||
01/15/2019 | |||
71124.08 | |||
Procedures | |||
20DP-0SK77 | |||
Security Miscellaneous Testing | |||
71124.08 | |||
Procedures | |||
75RP-9RP09 | |||
Control of Vehicles, Equipment and Material | |||
71124.08 | |||
Procedures | |||
75RP-9RP15 | |||
Control and Storage of Radioactive Material and Radioactive | |||
Wastes | |||
71124.08 | |||
Procedures | |||
76DP-0AP12 | |||
Low Level Radioactive Material Storage Facility Overview | |||
Inspection | |||
Procedure | |||
Type | |||
Designation | |||
Description or Title | |||
Revision or | |||
Date | |||
71124.08 | |||
Procedures | |||
76DP-0RP02 | |||
Radioactive Waste Minimization Program Overview | |||
71124.08 | |||
Procedures | |||
76DP-0RP03 | |||
Radwaste Process Control Program | |||
71124.08 | |||
Procedures | |||
76DP-0RP05 | |||
Radwaste Control and Management Activities | |||
71124.08 | |||
Procedures | |||
76RP-0RW05 | |||
Packaging and Classification of Radioactive Waste | |||
71124.08 | |||
Procedures | |||
76RP-0RW06 | |||
Packaging of Radioactive Material | |||
71124.08 | |||
Procedures | |||
76RP-0RW07 | |||
Shipping Radioactive Materials | |||
71124.08 | |||
Procedures | |||
76RP-0RW08 | |||
High Integrity Container Receipt, Handling, Use, and | |||
Closure | |||
71124.08 | |||
Shipping Records 19-RW-018 | |||
Shipping paperwork package for the LSA-II dewatered resin | |||
shipment | |||
71124.08 | |||
Shipping Records 19-RW-023 | |||
Shipping paperwork package for the LSA-I concentrates | |||
shipment | |||
71124.08 | |||
Shipping Records 20-RW-012 | |||
Shipping paperwork package for the LSA-II dewatered resin | |||
shipment | |||
71124.08 | |||
Shipping Records 20-RW-031 | |||
Shipping paperwork package for the LSA-II dewatered resin | |||
shipment | |||
71124.08 | |||
Shipping Records 20-RW-034 | |||
Shipping paperwork package for the LSA-II dewatered resin | |||
shipment | |||
71151 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
20-01508, 20-01734, 20-07606, 20-08679 | |||
71151 | |||
Miscellaneous | |||
NRC Performance Indicator Data; Emergency Preparedness | |||
- Drill/Exercise Performance; 1st Quarter 2020 - 4th | |||
Quarter 2020 | |||
01/01/2020 - | |||
2/31/2020 | |||
71151 | |||
Miscellaneous | |||
NRC Performance Indicator Data; Emergency Preparedness | |||
- ERO Readiness 1st Quarter 2020 - 4th Quarter 2020 | |||
01/01/2020 - | |||
2/31/2020 | |||
71151 | |||
Miscellaneous | |||
NRC Performance Indicator Data; Emergency Preparedness | |||
- Alert and Notification System Reliability; 1st Quarter 2020 | |||
- 4th Quarter 2020 | |||
01/01/2020 - | |||
2/31/2020 | |||
71153 | |||
Corrective Action | |||
Documents | |||
Condition Reports | |||
21-02209 | |||
}} | }} | ||
Latest revision as of 09:01, 29 November 2024
| ML21131A223 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 05/12/2021 |
| From: | John Dixon NRC/RGN-IV/DRP |
| To: | Lacal M Arizona Public Service Co |
| References | |
| IR 2021001 | |
| Download: ML21131A223 (24) | |
Text
May 12, 2021
SUBJECT:
PALO VERDE NUCLEAR GENERATING STATION - INTEGRATED INSPECTION REPORT 05000528/2021001 AND 05000529/2021001 AND 05000530/2021001
Dear Mrs. Lacal:
On March 31, 2021, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Palo Verde Nuclear Generating Station. On April 7, 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.
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 or severity 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 Palo Verde Nuclear Generating Station.
If you disagree with a cross-cutting aspect assignment in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region IV; and the NRC Resident Inspector at Palo Verde Nuclear Generating 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, John L. Dixon, Jr., Chief Reactor Projects Branch D Division of Reactor Projects
Docket Nos. 05000528 and 05000529 and 05000530 License Nos. NPF-41, NPF-51 and NPF-74
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000528, 05000529 and 05000530
License Numbers:
Report Numbers:
05000528/2021001, 05000529/2021001 and 05000530/2021001
Enterprise Identifier: I-2021-001-0090
Licensee:
Arizona Public Service Company
Facility:
Palo Verde Nuclear Generating Station
Location:
Tonopah, AZ
Inspection Dates:
January 1, 2021 to March 31, 2021
Inspectors:
C. Peabody, Senior Resident Inspector
E. Lantz, Resident Inspector
N. Cuevas, Resident Inspector
R. Alexander, Senior Emergency Preparedness Inspector
N. Greene, Senior Health Physicist
G. Hansen, Senior Emergency Preparedness Inspector
A. Siwy, Senior Resident Inspector
S. Hedger, Emergency Preparedness Inspector
D. Reinert, Reactor Inspector
B. Baca, Health Physicist
D. Antonangeli, Health Physicist
Approved By:
John L. Dixon, Jr., Chief
Reactor Projects Branch D
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Palo Verde Nuclear Generating 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
Failure to Correctly Classify a Condition Adverse to Quality Associated with Turbine Driven Auxiliary Feed Water Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems Green NCV 05000528, 05000529,05000530/2021001-01 Open/Closed
[H.6] - Design Margins 71111.06 The inspectors identified a Green non-cited violation of 10 CFR 50, Appendix B, Criterion V, for the licensees failure to disposition a condition adverse to quality associated with safety-related cables in accordance with the licensees condition reporting procedure. This has led to repeated water intrusion into Class 1E electrical conduits, which could degrade cabling and affect the reliability of the turbine driven auxiliary feedwater (AFW) pump.
Additional Tracking Items
Type Issue Number Title Report Section Status URI 05000528, 05000529,05000530/2021001-02 10 CFR Part 37 Requirements URI 71124.08 Open
PLANT STATUS
Unit 1 operated at or near full power for the duration of the inspection period.
Unit 2 entered the inspection period at full power. Between February 22 through 25, 2021, the unit had a short-term planned down power to 40 percent for condenser leakage repairs. Shortly after returning to full power on February 26, 2021, the unit tripped due to inadvertent manipulation of generator output breaker protective relay controls by personnel performing maintenance evolutions in the Palo Verde switchyard. Unit 2 was restarted on February 28, 2021 and remained at or near full power for the remainder of the inspection period.
Unit 3 operated at or near full power for the duration 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 plant status activities described in IMC 2515, Appendix D, Plant Status, and conducted routine reviews using IP 71152, Problem Identification and Resolution. 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) (3 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:
- (1) Unit 1, high pressure safety injection B, on January 21, 2021
- (2) Unit 2, Class 1E 125Vdc batteries B and D during startup transformer NANX02 outage, on February 10, 2021
- (3) Unit 3, essential spray pond system B during planned maintenance on diesel generator A, on March 2, 2021
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (4 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) Unit 3, main turbine operating deck and main turbine bearings, Fire Zones TB9 and TB10, on February 10, 2021
- (2) Unit 1, Class 1E 4kV switchgear A, Fire Zone 5A, on March 11, 2021
- (3) Unit 2, Class 1E 4kV switchgear A, Fire Zone 5A, on March 11, 2021
- (4) Unit 3, high pressure safety injection pump A, Fire Zone 31A, on March 12, 2021
71111.06 - Flood Protection Measures
Inspection Activities - Internal Flooding (IP Section 03.01) (1 Sample)
The inspectors evaluated internal flooding mitigation protections in the:
- (1) Unit 1, turbine driven auxiliary feedwater pump room, on January 2, 2021
Cable Degradation (IP Section 03.02) (1 Sample)
The inspectors evaluated cable submergence protection in:
- (1) Unit 3, diesel generator B fuel vault, on March 24, 2021
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1 Sample)
- (1) The inspectors observed and evaluated licensed operator performance in the control room during Unit 2 reactor startup, on February 28, 2021.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated operator requalification simulator training activities, on March 17, 2021.
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) Unit 1, safety injection system performance monitoring criteria exceeded due to safety injection tank vent valves SIA-608 and SIB-633 failing to close, on February 13, 2021
- (2) Unit 2, condition monitoring and maintenance plan for radwaste level transmitter failure, on February 13, 2021
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) Unit 1, repair of main steam isolation valve B thermal relief valve manifold assembly, on February 4, 2021
- (2) Unit 3, revised weekly risk assessment for extended diesel generator A outage from previous week displacing planned maintenance on high pressure safety injection pump A, on March 8, 2021
- (3) Unit 3, weekly risk assessment diesel generator, spray pond, essential cooling water, and essential chilled water planned maintenance, on March 28, 2021
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) Unit 1, missed valve position indication test following maintenance for containment power access purge isolation valve, on February 17, 2021
- (2) Unit 1, main steam support structure door 1-CA01 locking mechanism malfunctioning, on March 11, 2021
- (3) Unit 3, diesel generator B sump pump failed to start, on March 12, 2021
- (4) Unit 1, 2, and 3, charging line containment isolation valve CH-560 limit switches may not provide reliable position indications during loss of cooling accident (LOCA) event submergence, on March 12, 2021
- (5) Unit 2, charging pump A missed vibration data gathering during surveillance testing, on March 30, 2021
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (3 Samples)
The inspectors evaluated the following post-maintenance test activities to verify system operability and functionality:
- (1) Unit 1, inspect and adjust Class 1E 480V Circuit Breaker 1EPHBM3607, on March 25, 2021
- (2) Unit 3, inspect and adjust Class 1E 480V Circuit Breaker 3EPHBM3810, on March 25, 2021
- (3) Unit 3, A diesel generator post-maintenance testing on replaced air start valves, on March 31, 2021
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Unit 2 forced outage activities following reactor trip from February 26 to 28, 2021.
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Surveillance Tests (other) (IP Section 03.01)
- (1) Unit 3, control element assembly operability check surveillance test risk informed documented evaluation for a one-time extension of frequency from every nine months to annually under the surveillance frequency control program, on January 12, 2021
- (2) Unit 1, observed engineered safety features actuation system train B relay testing (main steam isolation signal, recirculation actuation signal, containment isolation actuation signal), on March 15, 2021
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) Unit 1, observed safety injection train B emergency core cooling system throttle valve inservice testing, on March 23, 2021
71114.01 - Exercise Evaluation
Inspection Review (IP Section 02.01-02.11) (1 Partial)
(1)
(Partial)
The inspectors evaluated the biennial emergency plan exercise which was conducted on March 9, 2021. However, as of the end of the 1st Quarter 2021, the licensee had not completed its critique process for the exercise. As such, the inspectors were unable to complete the full evaluation of the exercise and the critique process. The inspectors will complete the inspection early in the 2nd Quarter, and the results of the inspection will be documented in that report.
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 recently submitted Emergency Action Level and Emergency Plan changes.
- PVNGS Emergency Plan Revisions 67 and 68
This evaluation does not constitute NRC approval.
71114.08 - Exercise Evaluation Scenario Review
Inspection Review (IP Section 02.01 - 02.04) (1 Sample)
- (1) The inspectors reviewed the licensee's preliminary exercise scenario which was submitted to the NRC on December 18, 2020 (ADAMS Accession No.
ML20353A421), for the exercise scheduled to occur on March 9, 2021. The inspectors discussed the preliminary scenario with Ms. C. Shields, Manager, Emergency Preparedness, and other members of the emergency preparedness staff on February 3, 2021. The inspectors' review does not constitute NRC approval of the scenario.
RADIATION SAFETY
71124.05 - Radiation Monitoring Instrumentation
Calibration and Testing Program (IP Section 03.02) (15 Samples)
The inspectors evaluated the calibration and testing of the following radiation detection instruments:
- (1) Eberline AMS 4, SN #112914, 08/05/2020
- (2) Econoair Plus L-12P Personal Air Sampler, SN #1741, 12/11/2020
- (3) Ludlum Model 3 Count Rate Meter, SN #231550, 07/08/2020
- (4) GM Probe, SN #13478, 12/04/2020
- (5) AMP-100, SM #5014035, 09/17/2020
- (6) RO-20 Meter, SN #1411, 09/09/2020
- (7) RO-7 Meter, SN #679, 10/24/2020
- (8) Neutron Detector, SN #110762, 10/30/2020
- (9) Air Sampler - Charcoal, SN #16456, 12/04/2020
- (10) Small Article Monitor (SAM) 12, SN #6700, 10/28/2020
- (11) Small Article Monitor (SAM) 12, SN #6710, 11/18/2020
- (12) ThermoFisher Scientific Personal Contamination Monitor (PM-12), SN #12018, 09/03/2020
- (13) ThermoFisher Scientific Personal Contamination Monitor (PM-12), SN #1213, 11/17/2020
- (14) ThermoFisher Scientific iPCM 12, SN #112021, 11/20/2020
- (15) ThermoFisher Scientific iPCM 12, SN #12019, 08/14/2020 Effluent Monitoring Calibration and Testing Program Sample (IP Sample 03.03) (3 Samples)
The inspectors evaluated the calibration and maintenance of the following radioactive effluent monitoring and measurement instrumentation:
- (1) RU-200, Radioactive Liquid Effluent Monitor
- (2) RU-144, Plant Vent Radiation Monitor High
- (3) RU-14, Radwaste Effluent Radiation Monitor
71124.08 - Radioactive Solid Waste Processing & Radioactive Material Handling, Storage, &
Transportation
Waste Characterization and Classification (IP Section 03.03) (3 Samples)
The inspectors evaluated the licensees characterization and classification for the following radioactive waste streams:
- (1) Unit 1 Resin Stream for 2020
- (2) Unit 2 Resin Stream for 2020
- (3) Unit 2 Dry Active Waste stream for 2020
Shipping Records (IP Section 03.05) (5 Samples)
The inspectors evaluated the following non-excepted radioactive material shipments through a record review:
(1)19-RW-018, LSA - II, Dewatered Resin (2)19-RW-023, LSA - I, Concentrates (3)20-RW-012, LSA - II, Dewatered Resin (4)20-RW-031, LSA - II, Dewatered Resin (5)20-RW-034, LSA - II, Dewatered Resin
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE01: Unplanned Scrams per 7000 Critical Hours Sample (IP Section 03.01)===
- (1) Unit 1, January 1, 2020 through December 31, 2020
- (2) Unit 2, January 1, 2020 through December 31, 2020
- (3) Unit 3, January 1, 2020 through December 31, 2020
IE03: Unplanned Power Changes per 7000 Critical Hours Sample (IP Section 03.02) (3 Samples)
- (1) Unit 1, January 1, 2020 through December 31, 2020
- (2) Unit 2, January 1, 2020 through December 31, 2020
- (3) Unit 3, January 1, 2020 through December 31, 2020
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 03.03) (3 Samples)
- (1) Unit 1, January 1, 2020 through December 31, 2020
- (2) Unit 2, January 1, 2020 through December 31, 2020
- (3) Unit 3, January 1, 2020 through December 31, 2020
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 03.04) (3 Samples)
- (1) Unit 1, January 1, 2020 through December 31, 2020
- (2) Unit 2, January 1, 2020 through December 31, 2020
- (3) Unit 3, January 1, 2020 through December 31, 2020
EP01: Drill/Exercise Performance (IP Section 03.12) (1 Sample)
- (1) January 1, 2020 through December 31, 2020
EP02: ERO Drill Participation (IP Section 03.13) (1 Sample)
- (1) January 1, 2020 through December 31, 2020
EP03: Alert & Notification System Reliability (IP Section 03.14) (1 Sample)
- (1) January 1, 2020 through December 31, 2020
===71153 - Followup of Events and Notices of Enforcement Discretion
Event Followup (IP Section 03.01)===
- (1) The inspectors evaluated Unit 2 automatic reactor trip and licensees response on February 26,
INSPECTION RESULTS
Failure to Correctly Classify a Condition Adverse to Quality Associated with Turbine Driven Auxiliary Feed Water Pump Cornerstone Significance Cross-Cutting Aspect Report Section Mitigating Systems
Green NCV 05000528, 05000529,05000530/2021001-01 Open/Closed
[H.6] - Design Margins 71111.06 The inspectors identified a Green non-cited violation of 10 CFR 50, Appendix B, Criterion V, for the licensees failure to disposition a condition adverse to quality associated with safety-related cables in accordance with the licensees condition reporting procedure. This has led to repeated water intrusion into Class 1E electrical conduits, which could degrade cabling and affect the reliability of the turbine driven auxiliary feedwater (AFW) pump.
Description:
On August 22, 2019, indication of water intrusion was found on a junction box and two electrical conduits that penetrate down through the 100 foot train A auxiliary feed pump room. The licensee identified deposits from previous water intrusion and corrosion on the bottom of the junction box around the junction box cover. The union on conduit 1EZCAEARK63, which transitions between an unlabeled junction box and another junction box 1EZCAEAKKJ17 (J17), also had signs of water leaking out of the fittings indicating that water had entered the conduit at some point in the past. The licensee screened this issue as not a condition adverse to quality, entered it into the Performance Monitoring Program, and assigned a corrective maintenance work order to correct the condition per condition report CR 19-10684.
Per step 4.5.2 of licensee procedure, 01DP-0AP12, Condition Reporting Process, Revision 34 the screening committee classifies condition reports as either a significant condition adverse to quality, condition adverse to quality, or not a condition adverse to quality. This same procedure defines a condition adverse to quality as an all-inclusive term used in reference to failures, malfunctions, deficiencies, defective items, and non-conformances in items, activities, software and services that fall within the current licensing basis.
On January 1, 2021, the licensee observed water dripping from electrical conduit junction box J17 and after further evaluation determined that the source of water leakage was from main steam safety valves condensation overflow above which was spilling onto junction box 1EZC2EAKKJ04 (J04) at the 120 foot level. Per evaluation 21-00021-004, water flowed from junction box J04 down through the internal side of two electrical conduit penetrations into junction box J17 leaking into the AFW pump room. The main steam safety valve condensation is handled by a temporary drip catch which diverts the flow away from the junction box, however, in August 2019 and January 2021, that temporary drip catch had a clogged collection standpipe resulting in overflow onto junction box J04.
The inspectors concluded that the disposition on August 22, 2019, as not a condition adverse to quality was incorrect because safety-related power cables in this conduit provide electrical power to the turbine governor and valves associated with train A AFW pump, which is described in the current licensing basis. Therefore, continued water intrusion as observed on January 1, 2021, could degrade the electrical cabling and affect the reliability of the auxiliary feedwater system components.
The inspectors visually examined junction box J04 and it was apparent that water had been pooling on the roof of the junction box challenging the front side cover seal. Until the licensee corrects the configuration to prevent pooling on the top of the junction box, it will likely continue to leak into the cable conduit when wetted.
Corrective Actions: Per evaluation report 21-00013, junction boxes J17 and J04 will be inspected for drain holes if not already installed or inspected for drain hole-clogging if already installed.
Corrective Action References: Condition Reports 21-00013 and 21-03848
Performance Assessment:
Performance Deficiency: The licensee failed to correctly classify a condition adverse to quality in accordance with step 4.5.2 of licensee procedure, 01DP-0AP12, Condition Reporting Process. Specifically, during the screening committee review of Condition Report 19-10684, the licensee classified water intrusion into safety-related junction boxes and electrical conduits related to Class 1E electrical cabling and turbine driven AFW pump train A as a condition not adverse to quality.
Screening: The inspectors determined the performance deficiency was more than minor because if left uncorrected, it would have the potential to lead to a more significant safety concern. Specifically, the performance deficiency resulted in repeated water intrusion into junction boxes and conduits which could degrade cabling and affect the reliability of the turbine driven AFW pump.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors assessed the significance of the finding using IMC 0609, Appendix A, The Significance Determination Process (SDP) for Findings At-Power, Exhibit 2, Mitigating Systems Screening Questions. finding was determined to be of very low safety significance (Green) because it
- (1) was not a design deficiency,
- (2) did not represent a loss of system and/or function,
- (3) did not represent an actual loss of function of at least a single train for longer than its technical specification allowed outage time,
- (4) did not represent a loss of the probabilistic risk assessment (PRA) function of two separate technical specification systems for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />,
- (5) did not represent a loss of a PRA system and/or function for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and
- (6) did not result in the loss of a high safety-significant, nontechnical specification train.
Cross-Cutting Aspect: H.6 - Design Margins: The organization operates and maintains equipment within design margins. Margins are carefully guarded and changed only through a systematic and rigorous process. Specifically, when water intrusion into safety-related junction boxes and electrical conduits was found on August 22, 2019, the licensee failed to maintain safety-related equipment and incorrectly screened this issue as not a condition adverse to quality.
Enforcement:
Violation: 10 CFR 50 Appendix B, Criterion V, requires, in part, that activities affecting quality shall be accomplished in accordance with instructions, procedures or drawings. Procedure 01DP-0AP12, Condition Reporting Process, Revision 34, step 4.5.2, requires that the licensee screening committee assigns the condition report an appropriate quality classification.
Contrary to the above, on August 22, 2019, the licensee failed to accomplish an activity affecting quality in accordance with instructions, procedures, or drawings. Specifically, during condition report screening, an activity that affects quality, the licensee failed to assign the correct level of classification to junction box water intrusion, which could affect the reliability of the turbine driven AFW pump, as a condition adverse to quality, in accordance with procedure 01DP-0AP12.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Unresolved Item (Open)10 CFR Part 37 Requirements URI URI 05000528, 05000529,05000530/2021001-02 71124.08
Description:
The inspectors, while conducting a public radiation safety baseline inspection, identified numerous issues of concern regarding the implementation of 10 CFR Part 37 requirements during their review of the controls for an aggregated Category 2 quantity of radioactive material. The inspection was conducted the week of January 11, 2021, using IP 71124.08, Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation. The inspectors informed the licensee of the issues of concern regarding the implementation of the 10 CFR Part 37 requirements, specifically associated with 10 CFR 37.49(a)(3)(ii), 37.51(a), and 37.51(b).
10 CFR 37.49(a)(3)(ii) requires, in part, for Category 2 quantities of radioactive material, that the licensee shall establish and maintain weekly verification through physical checks, tamper indicating devices, use, or other means to ensure that the radioactive material is present.
10 CFR 37.51 requires, in part,
- (a) that the licensee shall implement a maintenance and testing program to ensure that intrusion alarms, associated communication systems, and other physical components of the systems used to secure or detect unauthorized access to radioactive material are maintained in operable condition and are capable of performing their intended function when needed; and
- (b) that the licensee shall maintain records on the maintenance and testing activities for 3 years.
These issues of concern relative to the control of Category 2 radioactive material required additional information and review to determine whether the licensee performance constituted violations of NRC requirements. Consequently, we are considering this matter as an Unresolved Item (URI).
Planned Closure Actions: The inspectors plan to continue their review of documentation provided by the licensee as it is made available, as well as hold discussions to resolve these issues of concern. This review will be a comprehensive assessment of all associated violations and/or findings related to these potential issues identified. The results of the final determination of these 10 CFR Part 37 violations, if validated, will be documented in a standalone report due to the security-related aspects of the potential violations.
Licensee Actions: The licensee placed this matter into their corrective action program for review and implementation of corrective actions. The licensee used the corrective action program to document their corrective actions already taken and planned, as well as communicated them to the inspectors. Thus far, the licensee has been very responsive to the potential violations. The licensee has already addressed perceived gaps the inspectors identified in the implementation of 10 CFR Part 37 requirements.
Corrective Action References: CR-21-03309
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On February 4, 2021, the inspectors presented the Radiation Safety inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff.
- On March 11, 2021, the inspectors presented the EP Performance Indicator Verification and Emergency Plan Changes inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff.
- On April 7, 2021, the inspectors presented the integrated inspection results to Mrs. Maria Lacal, Site Vice President/Chief Nuclear Officer and other members of the licensee staff.
- On April 22, 2021, the inspectors discussed the integrated inspection results to Mr. Matt Kura, Department Leader, Nuclear Regulatory Affairs, and other members of the licensee staff.
- On April 28, 2021, the inspectors debriefed the 10 CFR Part 37 Requirements URI with Mr. Todd Horton, Senior Vice President, Site Operations.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Drawings
01-M-SIP-001
P& I Diagram Safety Injection & Shutdown Cooling System
2
Drawings
01-M-SIP-002
P& I Diagram Safety Injection & Shutdown Cooling System
044
Drawings
03-M-SPP-001
P& I Diagram Essential Spray Pond System
071
Drawings
03-M-SPP-002
P& I Diagram Essential Spray Pond System
019
Miscellaneous
PVGS Pre-Fire Strategies Manual
Miscellaneous
USAR Section 9B
Fire Hazards Analysis
Calculations
13-MC-ZA-0807
MSSS 100 Elevation Flooding Evaluation
Calculations
13-MC-ZA-0808
MSSS 81 Elevation Flooding Evaluation
Corrective Action
Documents
Condition Reports
21-00013, 21-00016, 21-00021, 20-03848, 20-16841, 19-
10684
71111.11Q Miscellaneous
NLR21S020201
Licensed Operator Training Simulator Scenario: LOCA /
Loss of Class Instrument / Rapid Downpower
2/24/2021
Corrective Action
Documents
Condition Reports
20-15752, 20-15757, 20-15943, 20-15954, 20-16314
Miscellaneous
20-15752-003
MRFF Evaluation
Miscellaneous
20-15752-004
Level 3 Evaluation Report
Miscellaneous
20-15757-003
MRFF Evaluation
Miscellaneous
20-15757-004
Level 3 Evaluation Report
Miscellaneous
Level 3
Evaluation Report
Maintenance Rule Expert Panel Meeting 633
2/04/2021
Miscellaneous
SI-2503
Maintenance Rule (a)(1) Issue Tracking Form
Procedures
Maintenance Rule
Corrective Action
Documents
Condition Reports
21-00853
Miscellaneous
U1 MSIV RICT Projection Details
2/04/2021
Miscellaneous
U1 MSIV Risk Management and Readiness Plan
2/03/2021
Miscellaneous
EOOS 4.1
Weekly Schedulers Evaluation for PV Unit 3 Mar 8-14
2/17/2021,
03/8/2021
Miscellaneous
EOOS 4.1
Weekly Schedulers Evaluation for PV Unit 3 Mar 22-28
03/25/2021
Miscellaneous
Phoenix Risk
Monitor
WW 2112 Schedule Evaluation (3/22-28/2021)
03/23/2021
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
Phoenix Risk
Monitor
WW 2110 Schedule Evaluation (3/8-14/2021)
2/17/2021,
03/8/2021
Miscellaneous
RICT-U1-2021-01
Risk Informed Completion Time Summary
2/04/2021
Miscellaneous
Risk Challenge
Meeting
Risk Challenge Meeting for U1 MSIV-171 Repair
2/03/2021
Procedures
Online Integrated Risk
Procedures
Operations Department Online Nuclear Risk Determination
in Modes 1 and 2
Procedures
Risk Management Actions
Work Orders
5310300
Corrective Action
Documents
Condition Reports
21-01818, 21-02855, 21-02888
Miscellaneous
Updated Final Safety Analysis Report
20B
Miscellaneous
21-01818-002
Engineering Evaluation
Miscellaneous
EEQ-N007-001
Namco EA180 Limit Switches
Procedures
Operations Condition Reporting Process and Operability
Procedures
Control of Doors, Hatches, and Floor Plugs
Procedures
CP (Power Access Purge) Valves - Inservice Test
Work Orders
5159840
Procedures
Molded Case Circuit Breaker Test
Work Orders
5062359, 5202497
Miscellaneous
Plant Review
Board
STRIDE PRB Approval Meeting for CEA Operability Checks
01/12/2021
Procedures
Surveillance Frequency Control Program
Procedures
Surveillance Test Risk Informed Documented Evaluation
(STRIDE) Process
Procedures
PRA Methodology for Evaluating Changes to Surveillance
Test Intervals
Procedures
PVN-N-0034
STRIDE for One-Time Change for DEA Operability Checks
Corrective Action
Documents
Condition Reports
19-03672, 19-03691, 19-05088, 19-08356, 19-13385, 19-
13930, 19-17244, 20-01446, 20-01527, 20-03432, 20-
03738, 20-04408, 20-04999, 20-14892, 20-15325, 20-
15510, 20-16537, 20-16863
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Miscellaneous
2-05627
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2,
and 3; Docket No. STN 50-528; 50-529; 50-530 and 72-44;
License No. NPF-41; NPF-51; NPF-74; Response Providing
Information Regarding Implementation Details for the Phase
and 3 Mitigation Strategies
01/11/2007
Procedures
Emergency Preparedness Equipment Out of Service
Procedures
Loss of SFP Level or Cooling
Procedures
Deliberate Acts Against PVNGS
Procedures
Extensive Damage Mitigation Guidelines
Procedures
EDMG Command and Control
Procedures
Mitigating Guidelines Supplemental Strategies
Procedures
FLEX Support Guidelines
Procedures
FLEX Support Guidelines, Modes 1, 2, 3, or 4
Procedures
Emergency Response Organization (ERO) Position
Checklists
Procedures
Classifications
Procedures
Protective Actions
Miscellaneous
67, 68
Miscellaneous
Emergency Plan Evaluation - Medical Support During a
Public Health Emergency
2/17/2020
Miscellaneous
20-001e
Emergency Plan Revision 67 Effectiveness Evaluation Form
05/05/2020
Miscellaneous20-002s
Transitioning the Operations Advisor - STSC position to a
pooled position Screening Evaluation Form
03/17/2020
Miscellaneous
20-003e
Emergency Plan Revision 68 Effectiveness Evaluation Form
2/16/2020
Miscellaneous
20-003e,
Revision 1
Emergency Plan Revision 68 Effectiveness Evaluation Form
2/16/2020
Miscellaneous20-003s
Emergency Plan Revision 67 Screening Evaluation Form
05/01/2020
Miscellaneous20-004s
Emergency Plan Revision 68 Screening Evaluation Form
07/30/2020
Miscellaneous20-005s
Update to the Palo Verde Emergency Planning Zone (EPZ)
population Screening Evaluation Form
2/10/2020
Miscellaneous
1904 ERO Mini Drill - ERO Green Team (June 4, 2019);
1905 ERO Mini Drill - ERO Blue Team (June 11, 2019);
1906 ERO Mini Drill - ERO Red Team (June 18, 2019)
10/29/2019
Miscellaneous
1907 ERO Mini Drill - ERO Red Team (September 10,
10/23/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2019); 1909 ERO Mini Drill - ERO Green Team (September
24, 2019)
Miscellaneous
1910 ERO Mini Drill Report - ERO White Team (December
10, 2019)
01/2/2020
Miscellaneous
240-02859
CS/SW
1901 Full-Scale Dress Rehearsal - ERO Gold Team
(February 2019)
06/13/2019
Procedures
Protective Actions
Calibration
Records
RU-143 Plant Ventilation Monitor, Low Range - Unit 3
2/19/2019
Calibration
Records
RU-143 Plant Ventilation Monitor, Low Range - Unit 3
06/25/2020
Calibration
Records
RU-143 Plant Ventilation Monitor, Low Range - Unit 2
01/03/2019
Calibration
Records
RU-143 Plant Ventilation Monitor, Low Range - Unit 1
01/03/2019
Calibration
Records
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit
04/27/2018
Calibration
Records
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit
2/12/2019
Calibration
Records
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit
2/12/2019
Calibration
Records
RU-14 Radwaste Building Ventilation Exhaust Monitor - Unit
05/01/2020
Calibration
Records
RU-151 Radiation Monitor
10/26/2019
Calibration
Records
RU-141 Radiation Monitor
11/18/2019
Calibration
Records
RU-30 Radiation Monitor
11/12/2019
Calibration
Records
RU-157 Radiation Monitor
2/27/2020
Calibration
Records
RU-143 Plant Ventilation Monitor, Low Range - Unit 2
06/19/2020
Calibration
RU-143 Plant Ventilation Monitor, Low Range - Unit 1
06/22/2020
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Records
Calibration
Records
RU-150 Radiation Monitor
04/09/2020
Calibration
Records
RU-145 Fuel Building B Ventilation Exhaust Monitor, Low
Range - Unit 3
07/15/2020
Calibration
Records
RU-146 Fuel Building B Ventilation Exhaust Monitor, High
Range - Unit 3
10/16/2020
Calibration
Records
RU-15 Waste Gas Area Combined Ventilation Exhaust
Monitor - Unit 1
09/22/2020
Calibration
Records
RU-1 Radiation Monitor
11/07/2020
Calibration
Records
RU-148 Radiation Monitor
11/12/2020
Corrective Action
Documents
Condition Reports
19-00740, 19-01086, 19-02060, 19-02467,
19-02886, 19-03691, 19-05830, 19-06030,
19-06237, 19-08355, 19-08808, 19-12890,
19-13509, 19-13899, 19-16388, 19-17175,
19-17244, 19-18312, 20-00153, 20-00391,
20-00576, 20-01188, 20-02588, 20-04408,
20-04707, 20-04730, 20-07625, 20-08012,
20-08563, 20-09920, 20-12560, 20-12803,
20-13297, 20-15324, 20-15678, 20-16032
Miscellaneous
2018 Annual Radioactive Effluent Release Report
04/16/2019
Miscellaneous
2019 Annual Radioactive Effluent Release Report
04/17/2020
Miscellaneous
Offsite Dose Calculation Manual PVNGS Units 1, 2, and 3
Miscellaneous
Portal Monitors (PM) and Personal Contamination Monitors
(PCM) Alarm Setpoints
01/05/2021
Miscellaneous
Instrument Calibration Data Point Sheet
10/18/2020
Miscellaneous
Unit 1 2019-2020 Inoperable Effluent Monitor Logs
2/31/2020
Miscellaneous
Unit 2 2019-2020 Inoperable Effluent Monitor Logs
2/31/2020
Miscellaneous
Unit 3 2019-2020 Inoperable Effluent Monitor Logs
2/31/2020
Miscellaneous
Special Report 1-
SR-2019-001-00
Palo Verde Nuclear Generating Station (PVNGS) Unit 1,
Docket No. STN 50-528 /License No. NPF 51, Special
Report 1-SR-2019-001-00: Non-functionality of a fuel
04/26/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
building ventilation system high range radioactive gaseous
effluent monitor for more than 7 days
Procedures
Analytical Instrument Quality Control (QC)
Procedures
Actions For Non-Functional Radiation Monitors: Preplanned
Alternate Sampling Program
Procedures
Train "A" Radiation Monitoring Quarterly Functional Test
Procedure
Procedures
RU-1 Calibration Test
Procedures
Radiation Monitoring Calibration Test for Baseline Process
Monitors
Procedures
Train "A" Radiation Monitoring Calibration Test for Baseline
Area Monitors
Procedures
Train "A" Radiation Monitoring Calibration Test for
Containment New Scope Area Monitors
Procedures
Radiation Monitoring Calibration Test for RU-144
Procedures
Canberra Whole Body Counting System Calibration
Procedures
Calibration of Counter Scalers
Procedures
Calibration of the RO-2 and RO-20A Ion Chambers
Procedures
Canberra APEX - In Vivo Whole Body Counting System
Calibration
Self-Assessments IPA-RP2020S1
Integrated Performance Assessment Report: Radiation
Protection - 1st Half 2020 (07/24/2020)
09/02/2020
Self-Assessments SR-20-0021
NAD Surveillance Report: 2020 Radiation Safety
Performance Evaluation
07/23/2020
Work Orders
5010217
74ST9SQ042 Effluent Monitor Monthly Source Checks Unit
2: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
08/15/2019
Work Orders
5010218
74ST9SQ043 Effluent Monitor Monthly Source Checks Unit
3: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
08/15/2019
Work Orders
5011137
74ST9SQ041 Effluent Monitor Monthly Source Checks Unit
1: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
08/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
Work Orders
5030412
74ST9SQ042 Effluent Monitor Monthly Source Checks Unit
2: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
10/17/2019
Work Orders
5030413
74ST9SQ043 Effluent Monitor Monthly Source Checks Unit
3: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
10/21/2019
Work Orders
5031145
74ST9SQ041 Effluent Monitor Monthly Source Checks Unit
1: RU-143/RU-144 Plant Vent Gaseous Effluent Monitor and
RU-145/RU-146 Fuel Building Ventilation Gaseous Effluent
Monitor
10/17/2019
Corrective Action
Documents
Condition Reports
19-02590, 19-07431, 19-11705, 19-18567, 20-02759, 20-
2763, 20-14858
Miscellaneous
December 2020 Radwaste Inventory
2/2/2020
Miscellaneous
Waste /Material Characteristic Summary for Part 61 Waste
Stream Analysis - Unit 1 DAW - 2020
2/17/2020
Miscellaneous
Waste /Material Characteristic Summary for Part 61 Waste
Stream Analysis - Unit 1 DAW - 2020
2/17/2020
Miscellaneous
Waste /Material Characteristic Summary for Part 61 Waste
Stream Analysis - Unit 2 DAW -2020
05/12/2020
Miscellaneous
Waste /Material Characteristic Summary for Part 61 Waste
Stream Analysis - Unit 1 Resin - 2020
05/14/2020
Miscellaneous
Waste /Material Characteristic Summary for Part 61 Waste
Stream Analysis - Unit 2 Resin - 2020
2/09/2020
Miscellaneous
Radioactive Source Leak Test Surveillance Sheet
01/26/2020
Miscellaneous
Radioactive Source Leak Test Surveillance Sheet
01/15/2019
Procedures
Security Miscellaneous Testing
Procedures
Control of Vehicles, Equipment and Material
Procedures
Control and Storage of Radioactive Material and Radioactive
Wastes
Procedures
Low Level Radioactive Material Storage Facility Overview
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
Radioactive Waste Minimization Program Overview
Procedures
Radwaste Process Control Program
Procedures
Radwaste Control and Management Activities
Procedures
Packaging and Classification of Radioactive Waste
Procedures
Packaging of Radioactive Material
Procedures
Shipping Radioactive Materials
Procedures
High Integrity Container Receipt, Handling, Use, and
Closure
Shipping Records 19-RW-018
Shipping paperwork package for the LSA-II dewatered resin
shipment
Shipping Records 19-RW-023
Shipping paperwork package for the LSA-I concentrates
shipment
Shipping Records 20-RW-012
Shipping paperwork package for the LSA-II dewatered resin
shipment
Shipping Records 20-RW-031
Shipping paperwork package for the LSA-II dewatered resin
shipment
Shipping Records 20-RW-034
Shipping paperwork package for the LSA-II dewatered resin
shipment
71151
Corrective Action
Documents
Condition Reports
20-01508, 20-01734, 20-07606, 20-08679
71151
Miscellaneous
NRC Performance Indicator Data; Emergency Preparedness
- Drill/Exercise Performance; 1st Quarter 2020 - 4th
Quarter 2020
01/01/2020 -
2/31/2020
71151
Miscellaneous
NRC Performance Indicator Data; Emergency Preparedness
- ERO Readiness 1st Quarter 2020 - 4th Quarter 2020
01/01/2020 -
2/31/2020
71151
Miscellaneous
NRC Performance Indicator Data; Emergency Preparedness
- Alert and Notification System Reliability; 1st Quarter 2020
- 4th Quarter 2020
01/01/2020 -
2/31/2020
Corrective Action
Documents
Condition Reports
21-02209