IR 05000266/2019002
| ML19214A097 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 07/30/2019 |
| From: | Eric Duncan Reactor Projects Region 3 Branch 4 |
| To: | Craven R Point Beach |
| References | |
| IR 2019002 | |
| Download: ML19214A097 (30) | |
Text
July 30, 2019
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2INTEGRATED INSPECTION REPORT 05000266/2019002 AND 05000301/2019002
Dear Mr. Craven:
On June 30, 2019, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Point Beach Nuclear Plant, Units 1 and 2. On July 22, 2019, 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. The inspectors documented a licensee-identified violation which was determined to be of very low safety significance in this report. The NRC is treating this violation as non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.
If you contest a violation or the significance or severity of a 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 III; the Director, Office of Enforcement; and the NRC Resident Inspector at Point Beach.
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 III; and the NRC Resident Inspector at Point Beach. 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 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Eric R. Duncan, Chief Branch 4 Division of Reactor Projects
Docket Nos. 05000266 and 05000301 License Nos. DPR-24 and DPR-27
Enclosure:
As stated
Inspection Report
Docket Numbers:
05000266 and 05000301
License Numbers:
Report Numbers:
05000266/2019002 and 05000301/2019002
Enterprise Identifier: I-2019-002-0060
Licensee:
NextEra Energy Point Beach, LLC
Facility:
Point Beach Nuclear Plant
Location:
Two Rivers, WI
Inspection Dates:
April 1, 2019 to June 30, 2019
Inspectors:
K. Barclay, Resident Inspector
M. Domke, Reactor Inspector
G. Edwards, Health Physicist
T. Hartman, Senior Resident Inspector
D. Kimble, Senior Resident Inspector
D. Krause, Senior Resident Inspector
V. Myers, Senior Health Physicist
R. Ng, Project Engineer
Approved By:
Eric R. Duncan, Chief
Branch 4
Division of Reactor Projects
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees performance by conducting an integrated inspection at Point Beach in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. A Licensee-identified non-cited violation is documented in Report Section: 7115
List of Findings and Violations
Human Performance Error Causes Unplanned Pressurizer Pressure Drop Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events Green NCV 05000266/2019002-01 Open
[H.12] - Avoid Complacency 71111.20 A self-revealed finding of very low safety significance and an associated non-cited violation (NCV) of Technical Specification 5.4.1, Procedures, was identified when licensee personnel failed to adequately implement a procedure for the normal sequence of startup of the plant following a refueling outage. Specifically, the licensee exceeded the single step power limit of 3 percent when power was increased from 50.0 percent to 53.4 percent. The resulting temperature transient caused pressurizer pressure to drop below the Core Operating Limits Report (COLR) minimum pressure limit of 2205 pounds per square inch gauge (psig).
Additional Tracking Items
None.
PLANT STATUS
Unit 1 began the inspection period shutdown for a refueling outage. On April 18, 2019, Unit 1 was restarted. On April 19, 2019, Unit 1 was synchronized to the grid and on April 24, 2019, achieved full power. On May 16, 2019, Unit 1 was reduced in power to 43 percent to support main condenser water box cleaning. Unit 1 subsequently returned to full power on May 18, 2019, and remained at or near full power for the remainder of the inspection period.
Unit 2 began the inspection period at full power. On May 8, 2019, Unit 2 was reduced in power to 59 percent to support turbine stop valve testing. Following the completion of this testing, Unit 2 returned to full power on May 9, 2019. On May 28, 2019, Unit 2 was reduced in power to 60 percent to investigate elevated B steam generator feed pump vibrations. Following repairs, Unit 2 returned to full power on May 31, 2019, and remained at or near full power for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection Program - Operations Phase. The inspectors performed 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.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Summer Readiness Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated the summer readiness of offsite and alternate alternating current (AC) power systems
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 Train B Component Cooling Water (CCW) pump on April 9, 2019
- (2) Unit 1 Chemical and Volume Control System (CVCS) when credited as a shutdown inventory flowpath on April 11, 2019
- (3) Unit 1 Turbine-Driven Auxiliary Feedwater (TDAFW) pump following testing on May 11, 2019
71111.04S - Equipment Alignment
Complete Walkdown Sample (IP Section 03.02) (1 Sample)
- (1) The inspectors evaluated system configurations during a complete walkdown of the Unit 1 and Unit 2 CCW systems on May 1, 2019
71111.05Q - Fire Protection
Quarterly Inspection (IP Section 03.01) (5 Samples)
The inspectors evaluated fire protection program implementation in the following selected areas:
- (1) Fire Zones 225 and 228 on April 10, 2019
- (2) Fire Zones 306 and 307 on April 10, 2019
- (3) Fire Zones 142 and 151 on May 22-23, 2019
- (4) Fire Zones 156 and 156A on May 22-23, 2019
- (5) Fire Zone 166 on May 22-23, 2019
71111.08P - Inservice Inspection Activities (PWR) PWR Inservice Inspection Activities Sample (IP Section 03.01)
- (1) The inspectors verified that the Reactor Coolant System (RCS) boundary, steam generator tubes, reactor vessel internals, risk-significant piping system boundaries, and containment boundary were appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined, and accepted by reviewing the following activities from March 25, 2019 to April 9, 2019:
03.01.a - Nondestructive Examination and Welding Activities.
- Volumetric ultrasound examination of Reactor Coolant System (RCS)components RC-03-AS-1001-02, elbow-to-tee; RC-03-PS-1002-24, tee-to-pipe; RC-03-PS-1002-25, pipe-to-reducer, on 3-inch diameter piping located in the pressurizer upper cubicle of containment
- Volumetric ultrasound examination of RCS components RC-03-PS-1001-08, pipe-to-elbow; RC-03-PS-1001-09, elbow-to-pipe; on 3-inch diameter piping located in the head laydown area of containment
- Surface liquid dye penetrant examination of Residual Heat Removal (RHR)piping welded attachment AC-601R-6-H4-IWA
- Pressure boundary field welds W-2 and W-3 for Safety Injection (SI) system check valve 1SI-845E replacement for seat leakage per Work Order (WO)
===40479783
- Pressure boundary field welds W-1 and W-3 for Auxiliary Feedwater (AF)system gate valve 1AF-00195A for body-to-bonnet leakage per WO 40459909
03.01.b - Pressurized Water Reactor Vessel Upper Head Penetration Examination Activities.
- Bare Metal Visual (BMV) examination of reactor vessel head nozzles 40, 28, 20, 16 and 32 03.01.c - Pressurized Water Reactor Boric Acid Corrosion Control Activities.
- Boric acid leakage evaluation on SI system component 1P-15B SI pump 17-198B-E
- Boric acid leakage evaluation on charging system component 1P-2A charging pump discharge drain first off isolation, 18-021-E
- Boric acid leakage corrective action on SI system component 1SI-D-25, WR 94168630
03.01.d - Pressurized Water Reactor Steam Generator Tube Examination Activities.
- Steam Generators A and B tubes were subjected to eddy current examinations
- Steam Generators A and B were subjected to secondary side visual examinations
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) The inspectors observed and evaluated licensed operator performance in the main control room during a Unit 1 reactor startup following a refueling outage on April 18, 2019
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
- (1) The inspectors observed and evaluated a licensed operator simulator scenario on May 27, 2019
71111.12 - Maintenance Effectiveness
Routine Maintenance Effectiveness Inspection (IP Section 02.01) (1 Sample)
The inspectors evaluated the effectiveness of routine maintenance activities associated with the following equipment and/or safety significant functions:
- (1) K-3B Service Air Compressor
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the risk assessments for the following planned and emergent work activities:
- (1) Unit 1 elevated risk due to lowered reactor inventory for reactor pressure vessel head placement, on April 9, 2019
- (2) Elevated risk for G-05 Gas Turbine Generator maintenance and Service Water pump testing, on May 15, 2019
- (3) Elevated risk for DY-0A Red Inverter maintenance and Unit 1 Emergency Core Cooling System (ECCS) testing, on June 19-20, 2019
- (4) Elevated risk during Unit 1 Train B ECCS testing, on June 27, 2019
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 02.02) (5 Samples)
The inspectors evaluated the following operability determinations and functionality assessments:
- (1) Unit 1 Steam Generator (SG) Snubber HS-9 Failed Functional Test on April 2, 2019
- (2) Unit 1 Reactor Coolant Loop Flow Relay Found De-energized on April 26, 2019
- (3) Unit 1 Train A Containment Sump Recirculation Valve Operator Corrosion on May 21, 2019
- (4) Unit 1 Train A CCW Pump Elevated Vibrations on May 23, 2019
- (5) Unit 1 RCS Flow Transmitter Error on June 5, 2019
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1 Sample)
The inspectors evaluated the following temporary or permanent modifications:
- (1) EC 293289 - Flood Protection Lake Level Change on June 18, 2019
71111.19 - Post-Maintenance Testing
Post Maintenance Test Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated the following post maintenance tests:
(1)1P-11B, Unit 1 Train B CCW pump following replacement/upgrade on April 9, 2019 (2)1DY-02 Inverter following maintenance on April 30, 2019 (3)1P-2A Charging Pump following maintenance on May 21, 2019
- (4) K-3B Service Air Compressor following maintenance on May 23, 2019
71111.20 - Refueling and Other Outage Activities
Refueling/Other Outage Sample (IP Section 03.01) (1 Sample)
- (1) The inspectors evaluated Refueling Outage (RFO) U1R38 activities from March 22-April 17, 2019
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance tests:
Containment Isolation Valve Testing (IP Section 03.01) (1 Sample)
- (1) ORT 28, Demineralized Water Supply to Unit 1 Containment, on April 13, 2019
Inservice Testing (IP Section 03.01) (1 Sample)
- (1) IT 45, Unit 2 Safety Injection Valves Train B, on April 11, 2019
Surveillance Tests (other) (IP Section 03.01) (3 Samples)
- (1) IT 7C, P-32C Service Water Pump Quarterly Test, on March 5, 2019
- (2) ORT 6, Unit 1 Containment Spray Sequence Test, on April 11, 2019
- (3) IT 230, Unit 1 Leak Test of Class 1 Components Following a Refueling Shutdown, on April 16, 2019
71114.06 - Drill Evaluation
Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01) (1 Sample)
The inspectors evaluated the conduct of the following planned licensee Emergency Preparedness (EP) drill:
- (1) A full scale EP site drill conducted on May 21,
RADIATION SAFETY
71124.01 - Radiological Hazard Assessment and Exposure Controls
Contamination and Radioactive Material Control (IP Section 02.03) (1 Sample)
The inspectors evaluated licensee processes for monitoring and controlling contamination and radioactive material.
- (1) The inspectors verified the following sealed sources are accounted for and were intact:
- 1113-7
- 2602-9
- 9121
High Radiation Area and Very High Radiation Area Controls (IP Section 02.05) (1 Sample)
- (1) The inspectors evaluated risk-significant high radiation area and very high radiation area controls
Instructions to Workers (IP Section 02.02) (1 Sample)
The inspectors evaluated instructions to workers including radiation work permits used to access high radiation areas.
- (1) Radiation Work Packages
- 19-1064; Unit 1B Reactor Coolant Pump Impeller Change Out and Pump Bowl Inspection
- 19-1053; Unit 1 Narrow Range Resistance Temperature Detector Replacement
- 19-1057; Steam Generator Eddy Current Testing
Electronic Alarming Dosimeter Alarms
- AR 02309081; Unanticipated Rate Alarms Received During U-1 A Steam Generator Sludge
- AR 02308787; Unanticipated Dose Rate Alarm
- AR 02286293; Dosimeter Rate Alarm Received During Walk Down
Labeling of Containers
- Unit 1 Containment 8 Elevation Hot Trash Container
- Unit 1 Containment 66 Elevation Hot Trash Container
- Auxiliary Building Trash Containers (Various Locations)
Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample)
- (1) The inspectors evaluated radiation worker performance and radiation protection technician proficiency
Radiological Hazard Assessment (IP Section 02.01) (1 Sample)
The inspectors evaluated radiological hazards assessments and controls.
- (1) The inspectors reviewed the following:
Radiological Surveys
'B' Reactor Coolant Pump (RCP) Platform
- Resistance Temperature Detector (RTD) Tent
- Refuel Floor
- Spent Fuel Pool
- Reactor Cavity
Risk-Significant Radiological Work Activities
'B' RCP Internals Removal
- RTD Removal and Repair
Air Sample Survey Records
- 30-105
- 30-108
- 30-112
- 30-106
Radiological Hazards Control and Work Coverage (IP Section 02.04) (1 Sample)
The inspectors evaluated in-plant radiological conditions during facility walkdowns and observation of radiological work activities.
- (1) Radiological work package for areas with airborne radioactivity
- 19-1064; Unit 1B RCP Impeller Change Out and Pump Bowl Inspection
- 19-1053; Unit 1 Narrow Range RTD Replacement
- 19-1057; Steam Generator Eddy Current Testing
71124.02 - Occupational ALARA Planning and Controls
Implementation of ALARA and Radiological Work Controls (IPSection 02.03) (1 Sample)
The inspectors reviewed as low as reasonably achievable practices and radiological work controls.
- (1) The inspectors reviewed the following activities:
- 19-1064; Unit 1B Reactor Coolant Pump Impeller Change Out and Pump Bowl Inspection
- 19-1053; Unit 1 Narrow Range Resistance Temperature Detector Replacement
- 19-1057; Steam Generator Eddy Current Testing
Radiation Worker Performance (IP Section 02.04) (1 Sample)
The inspectors evaluated radiation worker and radiation protection technician performance during:
(1)the observations of activities listed in Section 02.03
71124.03 - In-Plant Airborne Radioactivity Control and Mitigation
Engineering Controls (IP Section 02.01) (1 Sample)
The inspectors evaluated airborne controls and radioactive monitoring.
- (1) Installed Ventilation Systems
- Unit 1 Containment Purge
Temporary Ventilation Systems
- High Efficiency Particulate Air (HEPA) ventilation for steam generator work
Portable or Installed Monitoring Systems
- Continuous Air Monitors on the Refueling Floor
- Continuous Air Monitors in the Auxiliary Building
Use of Respiratory Protection Devices (IP Section 02.02) (1 Sample)
The inspectors evaluated the licensees use of respiratory protection devices by:
- (1) Evaluations for the Use of Respiratory Protection
- 19-1053; Unit 1 Narrow Range Resistance Temperature Detector Replacement
- 19-1064; Unit 1B Reactor Coolant Pump Impeller Change Out and Pump Bowl Inspection
Respiratory Protection Use During Work Activities
- 19-1053; Unit 1 Narrow Range Resistance Temperature Detector Replacement
- 19-1064; Unit 1B Reactor Coolant Pump Impeller Change Out and Pump Bowl Inspection
Medical Fitness for Use of Respiratory Protection Devices
- Three individuals wearing respirators for steam generator work
- Two individuals wearing respirators for RTD work
Observation of Donning, Doffing and Functional Test
- Three individuals wearing respirators for steam generator work
- Two individuals wearing respirators for RTD work
Respiratory Protection Device Evaluation
- Three OptimAir powered air purifying respirators
- Two OptimAir MM 2K respirators
71124.04 - Occupational Dose Assessment
External Dosimetry (IP Section 02.02) (1 Sample)
- (1) The inspectors evaluated the external dosimetry program implementation
Internal Dosimetry (IP Section 02.03) (1 Sample)
The inspectors evaluated the internal dosimetry program implementation.
- (1) Whole Body Counts
- Dose assessment completed on April 8, 2017
- Two dose assessments completed on October 29, 2017
- Dose assessment completed on May 14, 2018
In-Vitro Internal Monitoring
- None available
Dose Assessments Performed using Air Sampling and DAC-hr Monitoring
- None available
Source Term Categorization (IP Section 02.01) (1 Sample)
- (1) The inspectors evaluated the licensees characterization of the source term and use of scaling factors for the use of hard-to-detect radionuclide activity
Special Dosimetric Situations (IP Section 02.04) (1 Sample)
The inspectors evaluated the following special dosimetric situation:
- (1) Declared Pregnant Workers
- Declaration Date July 10, 2018
Effective Dose Equivalent for External Exposures
- None available
Shallow Dose Equivalent
- Dose assessment completed on October, 28, 2017
- Dose assessment completed on March 9, 2018
Neutron Dose Assessment
- None available
71124.06 - Radioactive Gaseous and Liquid Effluent Treatment
Instrumentation and Equipment (IP Section 02.04) (1 Sample)
The inspectors reviewed the following radioactive effluent discharge system surveillance test results:
- (1) The inspectors reviewed effluent instrumentation and equipment
OTHER ACTIVITIES - BASELINE
===71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
BI02: RCS Leak Rate Sample (IP Section 02.11)===
- (1) Unit 1 (April 1, 2018 - March 31, 2019)
- (2) Unit 2 (April 1, 2018 - March 31, 2019)
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (2 Samples)
- (1) Unit 1 (April 1, 2018 - March 31, 2019)
- (2) Unit 2 (April 1, 2018 - March 31, 2019)
71152 - Problem Identification and Resolution
Semiannual Trend Review (IP Section 02.02) (1 Sample)
- (1) The inspectors reviewed the licensees corrective action program, trend reports, major equipment problem lists, system health reports, self-assessments, and additional documents, to identify trends that might indicate the existence of a more significant safety issue.
INSPECTION RESULTS
Licensee-Identified Non-Cited Violation 71152 This violation of very low safety significance was identified by the licensee and has been entered into the licensee corrective action program and is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
Violation: Point Beach Nuclear Plant, Units 1 and 2, Renewed Facility Operating License Condition 4.F, required, in part, that the licensee implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), National Fire Protection Association Standard NFPA 805, as specified in the license amendment requests, and as approved in the Safety Evaluation Report (SER)dated September 8, 2016. National Fire Protection Association (NFPA) 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, Section 3.3.1.2, Control of Combustible Materials, required, in part, that procedures for the control of transient combustibles shall be developed and implemented.
Licensee procedure NP 1.9.9, Transient Combustible Control, was developed by the licensee to implement the requirements of NFPA 805 for the control of transient combustibles. Revision 36 of NP 1.9.9, Step 4.12.3.b, stated, Except as permitted by Step 4.12.3.f, up to 100 pounds of Class A combustible materials may be brought into and left unattended in an Ordinary Risk fire zone without a TCCP [transient combustible control permit].
Contrary to the above, on April 4, 2019, the licensee failed to implement the requirements of Revision 36 of NP 1.9.9, Step 4.12.3.b associated with the control of transient combustibles.
Specifically, the licensee brought in and left unattended in excess of 1000 pounds of Class A combustible materials in the primary auxiliary building truck bay, an Ordinary Risk fire zone, without a TCCP. This amount of material significantly exceeded the 100 pound limit of Class A combustible material specified in Step 4.12.13.b of NPP 1.9.9 and the Class A combustible material did not qualify for the Step 4.12.3.f exemption.
Significance: Green.
Corrective Action References: AR 2308895
Observation: Semi-Annual Trend Review 71152 The licensee documented a trend in procedure use and adherence errors on March 1, March 29, and April 10, 2019. A licensee Recovery Plan, issued on April 15, 2019, included actions for first-line supervisors to emphasize procedure use and adherence within their work groups; managers to perform observations of procedure use and adherence in the field; and operations, maintenance, chemistry, engineering, and radiation protection departments to perform information sharing to reinforce human performance and procedure use and adherence.
The inspectors reviewed a licensee Interim Effectiveness Review that was issued on May 13, 2019, and that assessed the effectiveness of the Recovery Plan. The licensee concluded that their recovery actions were effective based on a reduction in the number of identified procedure use and adherence errors documented in condition reports.
The inspectors observed that although some improvements in procedure use and adherence were noted, challenges with procedure use and adherence, which were also documented in the previous semi-annual trend inspection, continued to be identified in the first and second quarter of 2019. For example, procedure use, and adherence errors associated with the control of transient combustibles during the Unit 1 refueling outage were observed. In particular, the inspectors identified three condition reports that identified a failure to obtain a required transient combustible permit, one of which is documented in this report as a finding of very low safety significance with an associated non-cited violation.
The inspectors concluded that more time was required to determine whether the efforts to reduce procedure use and adherence errors were effective and sustainable.
Human Performance Error Causes Unplanned Pressurizer Pressure Drop Cornerstone Significance Cross-Cutting Aspect Report Section Initiating Events
Green NCV 05000266/2019002-01 Open
[H.12] - Avoid Complacency 71111.20 A self-revealed finding of very low safety significance and an associated non-cited violation (NCV) of Technical Specification 5.4.1, Procedures, was identified when licensee personnel failed to adequately implement a procedure for the normal sequence of startup of the plant following a refueling outage. Specifically, the licensee exceeded the single step power limit of 3 percent when power was increased from 50.0 percent to 53.4 percent. The resulting temperature transient caused pressurizer pressure to drop below the Core Operating Limits Report (COLR) minimum pressure limit of 2205 pounds per square inch gauge (psig).
Description:
On April 21, 2019, with Unit 1 at 49 percent following the U1R38 refueling outage, the licensee inadvertently commenced power ascension at a rate of 3 percent per minute instead of 3 percent per hour and stepped reactor power from 49 percent to 53.4 percent. A reactor operator communicated that the turbine ramp rate was being set for 3 percent per hour but misread an operator aid and inadvertently established a ramp rate of 3 percent per minute.
The reactor operator then requested a peer check for the ramp rate that had been established from a second reactor operator, who improperly concurred with the incorrect setting. The reactor operator informed the Unit 1 senior reactor operator (SRO) that the turbine ramp rate had been set and requested permission to commence the power ascension. The SRO gave permission to proceed and the power ascension was commenced. The reactor operator observed that the turbine setter display value had begun to increase, confirming that the ramp had commenced, and stated that the turbine was ramping up. About 2 minutes after the power ascension was initiated, the reactor operator noted that reactor coolant system (RCS) temperature was unexpectedly lowering and the second reactor operator communicated that RCS pressure was also unexpectedly lowering.
The second reactor operator subsequently suspended the power ascension by placing the turbine controls in hold.
The resulting temperature transient caused pressurizer pressure to drop below the Core Operating Limits Report (COLR) minimum pressure limit of 2205 psig required by Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits. The Technical Specification Action Condition (TSAC) required that when pressurizer pressure drops below the minimum pressure required by the COLR, that pressurizer pressure be restored to within the COLR limit of 2205 psig within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The licensee entered TSAC 3.4.1.a at 8:06 a.m.,
restored pressurizer pressure to within the COLR limit at 8:09 a.m., and subsequently exited the TSAC.
OP 1C, Startup To Power Operation Unit 1, Step 3.3.2, stated, in part, that the rate of core power change is not limited by the fuel up to the conditioned power level or the threshold power of 50 percent, whichever is greater. OP 1C also stated that to be conditioned above 50% power, the plant must have been operated in the current cycle at or above a given power level greater than 50 percent for at least 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> out of the last 7 days of power operation.
For the step change in power on April 21, the conditioned power level was not above 50 percent in the current cycle since the plant was restarting immediately following a refueling outage. Therefore, the threshold power level of 50 percent applied. OP 1C, Step 3.3.2, also stated, in part, that the following power limit increases shall not be exceeded: 4 percent over any 1-hour period; 7 percent over any 2-hour period; 10 percent over any 3-hour period; and no single step change in power of more than 3 percent of full power.
Corrective Actions: After identifying the issue, the licensee immediately halted the load ramp and reduced power to about 51 percent. The licensee contacted the fuel vendor, who validated that the step change in power did not adversely impact the fuel. Long-term corrective actions included revising the operator aid used to set the ramp rate and conducting a human performance investigation.
Corrective Action References: AR 2311530
Performance Assessment:
Performance Deficiency: The inspectors determined that the failure to adequately implement OP 1C, Startup To Power Operation Unit 1," Step 3.3.2, was contrary to TS 5.4.1, "Procedures, and was a performance deficiency.
Screening: The inspectors determined the performance deficiency was more than minor because it was associated with the Human Performance attribute of the Initiating Events cornerstone. The performance deficiency adversely affected the cornerstone objective of limiting the likelihood of events that upset plant stability and challenge critical safety functions during shutdown as well as power operations. Specifically, the licensee violated the step change limits for power ascension and violated the COLR limit for pressurizer pressure.
Significance: The inspectors assessed the significance of the finding using Appendix A, The Significance Determination Process (SDP) for Findings At-Power. The inspectors determined that the finding was of very low safety significance (i.e., Green) because they answered No to the Transient Initiators Question in Exhibit 1 - Initiating Events Screening Questions. Specifically, the finding did not cause a reactor trip, or the loss of mitigating equipment relied upon to transition the plant from the onset of the trip to a stable shutdown condition.
Cross-Cutting Aspect: H.12 - Avoid Complacency: Individuals recognize and plan for the possibility of mistakes, latent issues, and inherent risk, even while expecting successful outcomes. Individuals implement appropriate error reduction tools. Specifically, the operators failed to implement appropriate error reduction tools.
Enforcement:
Violation: Technical Specification 5.4.1.a, of Technical Specification 5.4, Procedures, required, in part, that written procedures shall be established, implemented, and maintained covering the normal sequence of startup, operation, and shutdown of components, systems, and the overall plant. Point Beach Nuclear Plant Operating Procedure OP 1C, Startup To Power Operation Unit 1, is the procedure used in the normal sequence of startup of the overall plant subject to the requirements of Technical Specification 5.4.1.a. OP 1C, Step 3.3.2, stated, in part, that the rate of core power change is not limited by the fuel up to the conditioned power level or the threshold power of 50 percent, whichever is greater. OP 1C, Step 3.3.2 also stated, in part, that no single step in power shall exceed 3 percent of full power.
Contrary to the above, on April 21, 2019, the licensee failed to implement a procedure for the normal sequence of startup of the overall plant as required by Technical Specification 5.4.1.a.
Specifically, with the reactor at the threshold power of 50 percent, which was the greater of the conditioned power level and the threshold power level, the licensee exceeded the single step power increase limit of 3 percent of full power specified in OP 1C, Step 3.3.2, when a step change in power from 50 percent to 53.4 percent occurred.
Enforcement Action: This violation is being treated as a non-cited violation, consistent with Section 2.3.2 of the Enforcement Policy.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
- On April 5, 2019, the inspectors presented the radiation protection inspection results to Mr. R. Craven, Site Director, and other members of the licensee staff.
- On April 9, 2019, the inspectors presented the Inservice Inspection Exit to Mr. B. Wojak, Site Engineering Director and other members of the licensee staff.
- On July 22, 2019, the inspectors presented the integrated inspection results to Mr. R. Craven and other members of the licensee staff.
DOCUMENTS REVIEWED
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
Resulting from
Inspection
2314350
NRC Items Identified during Switchyard Walkdown
05/14/2019
Miscellaneous
PBNP-MISO-
NUC-001
Nuclear Plant Operating Agreement for Point Beach Nuclear
Plant
Procedures
NP 2.1.5
Electrical Communications, Switchyard Access and Work
Planning
NP 5.2.19
NERC Standard NUC-001 Nuclear Plant Interface
Coordination Agreement Control
Drawings
110E018, Sheet 3 Auxiliary Coolant System
110E018, Sheet 5 CCW Minimum Flow Recirculation Cross Connect Details
M-201, Sheet 1
P&ID Main & Reheat Steam System
M-217, Sheet 1
P&ID Auxiliary Feedwater System
104
Miscellaneous
Shutdown Safety Assessment and Fire Inspection Checklist
04/11/2019
Procedures
1-CL-CC-001
Component Cooling Unit 1
CL 13E Part 1
Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1
CL 5A
Chemical and Volume Control System Unit 1
Drawings
110E018, Sheet 1 P&ID Auxiliary Coolant System
110E018, Sheet 2 P&ID Auxiliary Coolant System
110E018, Sheet 3 P&ID Auxiliary Coolant System
110E029, Sheet 1 P&ID Auxiliary Coolant System
110E029, Sheet 2 P&ID Auxiliary Coolant System
110E029, Sheet 3 P&ID Auxiliary Coolant System
110E029, Sheet 4 P&ID Auxiliary Coolant System
Procedures
1-CL-CC-001
Component Cooling Unit 1
2-CL-CC-001
Component Cooling Unit 2
71111.05Q Corrective Action
Documents
Resulting from
Inspection
2300129
Material Missing From Structural I Beams
1/31/2019
Fire Plans
Control Building Elevation 8', 26', 44' and 66'
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PFP-0-PAB-26
Auxiliary Building 26'
PFP-0-PAB-8
Primary Auxiliary Building Elevations 8' and Below
PFP-0-PAB-8
Pre-Fire Plan Primary Auxiliary Building Elevations 8' and
Below
Corrective Action
Documents
Anomaly During U1R38 SG Tube Plug Installation
04/05/2019
Debris Found on Unit 1 Reactor Pressure Vessel Closure
Head
04/08/2019
Boric Acid Streaking from CETNA 37 on Unit 1 RPV Head
04/08/2019
Boric Acid Streaking from CETNA 35 on Unit 1 RPV Head
04/08/2019
Recordable Indication on RTD Bypass Piping Support RC-
2501R-14-102R
04/09/2019
Corrective Action
Documents
Resulting from
Inspection
Weld Data Sheets in Incorrect Record
03/26/2019
Incorrect Revision of Code Case N-729 Referenced in NDE
Procedure
04/05/2019
Engineering
Evaluations
Safety Injection Pump Inboard Seal Leakoff Area and Pump
Skid Below
04/17/2018
18-021-E
1P-2A CHG Pump Discharge Header Drain First Off
Isolation/8/PAB/U1
03/27/2018
LTR-CECO-19-
29
Evaluation of Roll Expanded Mechanical Tube Plug
Extending from the Tubesheet in Tube R13C49 in SGA Cold
Leg at Point Beach Unit 1
04/08/2019
Miscellaneous
NPM 2007-0145
Documentation of Point Beach Nuclear Plants Position on
the Use of Liquid Penetrant and Magnetic Particle Materials
Contained in Aerosol Containers and Stored Under Ambient
Conditions
04/24/2007
NSAL-12-1
Nuclear Safety Advisory Letter for Steam Channel Head
Degradation
Revision 1
NSD-TB-94-03-
R0
Westinghouse Technical Bulletin for Steam Generator
Secondary Side Erosion-Corrosion
05/02/1994
SG-CDMP-19-3
Point Beach U1R38 Steam Generator Degradation
Assessment
Revision 1
NDE Reports
2019U1PT-001
Liquid Penetrant Examination of Component AC-601R-6-H4-
04/02/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
FP-PE-B31-
ASME-Welding Procedure Specification
Revision 6
FP-PE-B31-
ASME-Welding Procedure Specification
Revision 5
MRS-GEN-1217
Rolled Mechanical Plug Installation Using the Advanced
Rolling Tool and the Universal Platform Control Box
Revision 5
NDE-173
PDI Generic Procedure for the Ultrasonic Examination of
Austenitic Piping Welds
Revision 17
NDE-201
Radiographic Examination
Revision 6
NDE-451
Visible Dye Penetrant Examination Temperature
Applications 45°F to 125°F
Revision 30
Work Orders
WO 40459909 01
1AF-00195A/Replace Valve (Welding)
10/13/2017
WO 40479783 01
1SI-845E/Cut Out and Replace Valve
10/17/2017
WO 40514558 01
Perform NDE/UT of Pressurizer Spray Piping Welds
10/13/2017
WO 40514567 02
Perform NDE/RC-03-PS-1001-08
10/12/2017
WO 40573724 01
Reactor Pressure Vessel Closure Head
01/17/2019
71111.11Q Corrective Action
Documents
2314216
Simulator Issue Negatively Affected LOC Evaluated
Scenario
5/13/2019
Procedures
Reactor Startup
Conduct of Operations
Corrective Action
Documents
263887
K-3B SA Compressor High Temp/Standby Compressor Start
05/11/2018
264862
K-3B Service Air Compressor Discharge Temp High Alarm
Received
05/17/2018
291891
K-3B Service Air Compressor Improper Operation
11/21/2018
297959
K-3B Service Air Compressor Rapid Motor Vibration
Increase
01/15/2019
2308290
NI System Maintenance Rule Evaluation Inconsistencies
Identified
04/01/2019
2316963
U1 CW System Exceeds Maintenance Rule Performance
Criteria
06/05/2019
2317207
SA System Exceeds Maintenance Rule Performance Criteria
06/07/2019
Corrective Action
Documents
Resulting from
2308290
NI System Maintenance Rule Evaluation Inconsistencies
Identified
4/1/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Inspection
Miscellaneous
Service Air Reliability Event Report
04/01/2017-
04/29/2019
Corrective Action
Documents
Resulting from
Inspection
2319493
IT-90 Train B Test Moved PRA Risk Review Not Done In
Advance
06/27/2019
2319494
DGB Door 107 Not Self Latching
06/27/2019
Miscellaneous
Station Logs
05/15-
16/2019
Point Beach Station Unit 1 and 2 Daily Status Report
06/19/2019
Point Beach Station Unit 1 and 2 Daily Status Report
05/15/2019
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist
04/11/2019
Current Risk Summary Reports; PBN Unit 1 and 2
06/18-
21/2019
Current Risk Summary Report; PBN Unit 1 and 2
05/15/2019
Current Risk Summary Reports; PBN Unit 1 and 2
06/27-
28/2019
Point Beach Station Unit 1 and 2 Daily Status Report
06/28/2019
Calculations
CN-CPS-07-8
Point Beach Reactor Coolant Flow Instrumentation Setpoint
and Uncertainty Calculation (1C-41)
Corrective Action
Documents
2308372
Steam Generator Snubber HS-9 Failed Functional Test
04/01/2019
2312347
Relay 1RC-3A Found De-Energized During Visual Inspection 04/26/2019
2315175
1P-011A IST PMT Not Performed After 1P-011B Re-Piping
U1R38
05/21/2019
Corrective Action
Documents
Resulting from
Inspection
2311877
CR 02308372 Canceled Versus Processed
04/23/2019
2312945
Water Up to ISI-850A-O (Operator) in Tendon Gallery
05/01/2019
Drawings
617F354, Sheet
4A1
Schematic Diagram - Inputs, Reactor Protection System
Train "A," Unit 1
Miscellaneous
257
Model 1154 Alphaline Pressure Transmitter
Operability
Evaluations
165
SSC Affected by Condition: 1&2 SI-00850A&B, RHR Pump
Suction from Sump B
11/06/2005
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
2315095
1P-11A had Elevated Vibrations During IT-12 Train A
05/21/2019
Procedures
Maintenance Testing
RMP 9061-3
Anker Holth Snubber Removal, Functional Testing, and
Installation
Work Orders
40573498
1ICP 4.2-1 - RCS Flow Transmitter Outage Calibration
04/04/2019
40608261 37
1FT-414, 1FT-415, 1FT-416, RC Loop B Flow Transmitters
Span Adjustment
04/17/2019
40665209
1P-11A CCW Pump - Coupling Alignment Verification
06/12/2019
Calculations
2014-06279
Time Available to Respond to Rising Lake Level
Engineering
Changes
External Wave Run-up Flood Mitigation Strategy
Basis for Changing Monitored Lake Level from the Highest
of All Reporting Stations to the Mean of All Reporting
Stations
06/05/2019
Miscellaneous
2316179
PBF-2124A - Maximum Converted Lake (Doc Dist)
05/30/2019
PBF-2124a
Maximum Converted Lake Level Calculation
PBF-2124a
Average Converted Lake Level Calculation
PCR 2316179
CFR 50.59 Screening Form: PBF-2124a, Maximum
Converted Lake Level Calculation
06/05/2019
Procedures
Severe Weather Conditions
Corrective Action
Documents
2304474
PMT Failed on HX-105A
03/05/2019
2304487
Leakage on HX-105A
03/06/2019
2305348
PMT for WO 40543692, 2P-10A Coupling Lubrication
03/12/2019
2306539
Work Planning/Manage: PMT Guidance Inadequate
03/20/2019
2308538
1CV-296 1HX-2 Regen Hx To Aux Spray Valve Has No PMT
Task
04/02/2019
2315175
1P-011A IST PMT Not Performed After 1P-011B Re-Piping
U1R38
05/21/2019
Procedures
IT 12A
CC Pumps and Valves While Aligned for RHR Operation
(Cold Shutdown) Unit 1
Work Orders
2312548
K-2 Relay Found With Broken Center Post
04/29/2019
40543692 02
01/17/2019
40582325 01
B52-DB50-011; Breaker Maintenance Per RMP-9303 and
RMP-9369-1
03/05/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
40611338
1DY-02, Maintain and Inspect Inverter
04/25/2019
40624975
1P-002A-Z/Replace Signal Conditioner Module
05/21/2019
40626242 02
1B52-13A; Setup and Stage Spare Breaker
05/02/2019
40664989 03
K-3B/Replace 1st and 2nd Stage Discharge Check Valves
06/27/2019
40664989 04
K-3B/OPS PMT
05/23/2019
1P-011B - Operations PMT - RTS
Corrective Action
Documents
2310563
Deficiencies Noted During CL 20/20A Walkdown
4/14/2019
2310581
CL-20 CTMT Walkdown Items Identified
4/15/2019
Corrective Action
Documents
Resulting from
Inspection
2310884
NRC Observations During NOP/NOT & Key Way Walkdown
04/16/2019
Drawings
500B728; Sheet
Main Control Board Component Wiring
541F091; Sheet 1 P&ID Reactor Coolant System
541F091; Sheet 2 P&ID Reactor Coolant System
Engineering
Changes
Point Beach Unit 1 Cycle 39 Core Reload Modifications
Miscellaneous
PBNP Shutdown Safety Assessment and Fire Inspection
Checklist
03/26 -
04/15/2019
Spent Fuel Pool Map After U1R38 Core Offload
4/30/2019
Spent Fuel Pool Map After U1R38 Outage
4/30/2019
Point Beach Component Move Sheet; U1R38 Core Reload
4/7-9/2019
Point Beach Component Move Sheet; U1R38 Core Offload
3/27-31/2019
Point Beach Component Move Sheet; U1R38 Insert Moves
3/31/2019
Point Beach Component Move Sheet; U1R38 Fuel Cleaning
3/31-
4/2/2019
Fatigue Management Work History from 03/23/2019 to
04/12/2019
04/12/2019
Outage Work Schedules for Operations, Maintenance, and
Fire Brigade
04/12/2019
AF AF-4000-O
Clearance Package
4/11/2019,
4/15/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OP-3C Accum
Out
Clearance Package
4/15/2019
Procedures
ARB 1C04 1C 2-8 Alarm Response Book; BA Flow Deviation or Potential
Dilution in Progress
CL 2A
Defueled to Mode 6 Checklist
04/07/2019
CL 2B
Mode 6 to Mode 5 Checklist
04/07/2019
CL 2C
Mode 5 to Mode 4 Checklist
04/10/2019
CL 2D
Mode 4 to Mode 3 Checklist
04/16/2019
CL 2E
Mode 3 to Mode 2 Checklist
04/18/2019
CL 2F
Mode 2 to Mode 1 Checklist
04/18/2019
OP 1C Unit 1
Startup to Power Operation
OP 3C Unit 1
Hot Standby to Cold Shutdown Unit 1
03/26/2019
Work Orders
40511562
1ICP 6.15 - Perform Steps 5.1 through 5.5.7
9/1/2017
1ICP 13.14 - Core Exit T/C Recorder Calibration
2/18/2017
1ICP 2.8-1 NI Axial Offset Calibration
4/22/2019
Corrective Action
Documents
296665
South SW Header Flowmeter Calibration
01/04/2019
2304475
P-32C SW Pump Performance Outside Acceptance Criteria
03/05/2019
2305377
Service Water South Header Flow Appears High
03/12/2019
2305380
Calibration of the SW South Header Flow Meter
03/12/2019
Corrective Action
Documents
Resulting from
Inspection
2310121
Procedure Use and Adherence Issue
04/11/2019
2310869
Rebaselining of P-32A and P-32C Improvements
04/16/2019
Miscellaneous
291226
10CFR50 Appendix J Program Routing Task - 2018-2019
04/14/2019
IST Program
Document
Inservice Testing Program Document
SCR 2014-0011
Revisions to IT 07C Following Rebaselining of P032C,
Service Water Pump
01/17/2014
Procedures
1-PT-RCS-1
Reactor Coolant System Pressure Test - Inside/Outside
Containment Unit 1
IT 230
Leak Test of Class 1 Components Following a Refueling
Shutdown Unit 1
IT 45 Train B
Safety Injection Valves Train B Unit 2
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
OI 58
Leak Testing of Containment Isolation Valves - Unit 1 and 2
General Instructions and Information
ORT 6
Containment Spray Sequence Test Unit 1
Work Orders
40573810 01
ORT 28, Cont DI H2O
04/13/2019
40610316 01
IT-07C, P-32C Service Water Pump Comprehensive Test
03/06/2019
Corrective Action
Documents
2315151
EP Drill - Accountability in NES
05/21/2019
2315188
EP Pre-Existing Accountability
05/21/2019
2315195
NA Identified Gaps - EP Pre-Exercise (TSC)
05/21/2019
Miscellaneous
PBN EPR 192
001D
Emergency Preparedness (EP) Drill Manual for the 2019 EP
Pre-Exercise
05/21/2019
Corrective Action
Documents
255246
Source Leak Check Documentation Gaps
03/21/2018
270541
Neutron Correction Factor Not Auto Adding Correctly
06/29/2018
285855
Dosimeter - Rate Alarm Encountered During Snubber
Inspection
10/15/2018
286293
Dosimeter Rate Alarm Received During Walk Down
10/17/2018
2308787
Unanticipated Dose Rate Alarm
04/03/2019
2309081
Unanticipated Rate Alarms Received During U-1 'A' S/G
Sludge
04/05/2019
Procedures
Radiation Worker Instruction and Responsibilities
Revision 8
Alpha Monitoring
Revision 4
Radiation
Surveys30-105
Airborne Radioactivity Survey
04/03/2019
30-106
Airborne Radioactivity Survey
04/03/2019
30-108
Airborne Radioactivity Survey
04/03/2019
30-112
Airborne Radioactivity Survey
04/03/2019
PBPROD-M-
20190300-20
Unit 1 Reactor Cavity - Upper Level - Initial Entry
03/22/2019
PBPROD-M-
20190325-30
U-1 Reactor Upper Cavity - Post Decon on Floor
03/25/2019
PBPROD-M-
20190331-39
66' U-1 Containment Shiftly Routine
03/31/2019
PBPROD-M-
20190401
66' U-1 Containment Shiftly Routine
04/01/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
PBPROD-M-
20190402-40
U1 Daily Outage Routines Spent Fuel Pool
04/02/2019
PBPROD-M-
20190402-55
Unit 1 Containment B Elevation 10 Foot Platform
04/02/2019
PBPROD-M-
20190403-21
Unit 1 B Cold Leg RTD Manifold Removal
04/02/2019
PBPROD-M-
20190403-25
BG C/L RTD Rebuild Tent
04/03/2019
PBPROD-M-
20190404-2
Reactor Coolant Pump Lower, B Side U1 Post
Shielding/Contamination Survey
04/04/2019
PBPROD-M-
20190404-30
Reactor Coolant Pump Lower, B Side U1 Job Coverage
04/04/2019
PBPROD-M-
20190404-32
Reactor Coolant Pump Lower, B Side U1 Impeller Removal
04/04/2019
PBPROD-M-
20190404-41
U1 Daily Outage Routines Spent Fuel Pool
04/04/2019
Radiation Work
Permits (RWPs)
19-1021
B RCP Maintenance Seal Replacement
Revision 2
19-1053
Unit 1 Narrow Range RTD Replacement
Revision 2
19-1056
FOSAR Activities
Revision 1
19-1057
Revision 00
19-1064
Unit 1B RCP Impeller Change Out and Pump Bowl
Inspection
Revision 1
ALARA Plans
R-003
Replace B Loop Hot Leg RTD Manifold and Refurbish B
Cold Leg Manifold (Mechanical Cut-Out and Replace)
03/29/2019
R-023
B RCP Rotating Element Change-Out
04/01/2019
R005
B RCP Seal, Motor Replacement and Maintenance
03/07/2019
R011
Steam Generator Eddy Current
03/06/2019
Corrective Action
Documents
2308213
Narrow Range RTD Replacement Work is Tracking Above
Estimate
03/31/2019
2308215
Additional Dose Needed for Added Scope on RV Head Work
03/31/2019
2309059
Dose Estimate Adjustment Needed on FOSAR Work
04/04/2019
Procedures
ALARA Implementing Procedure
Revision 15
ALARA Plans
Respirator Assessment for Radiation Work Permit 19-1064
04/01/2019
Respirator Assessment for Radiation Work Permit 19-1053
03/29/2019
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Corrective Action
Documents
290219
HPIP 3.58.1 Air Sampling Process Instruction Review
11/09/2018
Miscellaneous
HP-100-101718
Review of Steam Generator Channel Head Ventilation
Practices
10/18/2018
Procedures
NISP-RP-008
Use and Control of HEPA Filtration and Vacuum Equipment Revision 1
NP 4.2.32
Respiratory Protection Program
Revision 18
Self-Assessments 02256550-02
Shared Ownership Gaps - Respiratory Protection Program
05/03/2018
AR 02294511-04
2018 Annual Respiratory Protection Program Assessment
01/11/2019
Calculations
High Level Contamination Report and Associated Dose
Calculations for RWP 17-1027
10/28/2017
High Level Contamination Report and Associated Dose
Calculations for RWP 17-1016
10/28/2017
Whole Body Count Evaluation for Radiation Protection
Individual
04/08/2017
Whole Body Count Evaluation for Radiation Protection
Individual
10/29/2017
Whole Body Count Evaluation for BHI Individual
10/29/2017
Whole Body Count Evaluation for Maintenance Individual
05/14/2018
Corrective Action
Documents
253282
WBC Procedural Guidance Not Updated Following
Evaluation
03/08/2018
255763
Error in DACDOS Calculation
03/23/2018
Procedures
NP 4.2.15
Fetal Protection Policy Implementation
Revision 7
Calculations
Calibration Factor Steam Line Monitors
06/21/1983
2013-0018
Radiological Effluent Initiating Condition Values For
Emergency Action Level RS1 and RG1
Revision 03
99-0106
Dose Rate Calculations for Steam Line Monitors Calibration
Factor
Revision 0
Miscellaneous
Permanent Procedure and Procedure Revision Review and
Approval for HPCAL 3.7, Steam Line Radiation Monitor
Calibration Procedure
04/21/1993
Permanent Procedure and Procedure Revision Review and
Approval for HPCAL 3.7, Steam Line Radiation Monitor
Calibration Procedure
08/20/1990
349-17-1
Certificate of Gamma Standard Source for Cs-137 Source
08/01/1989
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Number 349-17-1
65089-10
Certificate of Radioactivity Calibration for Kr-85 Source
Number 65089-10
10/01/1981
SDD-RASCAL-
20140110
Unified RASCAL Interface Technical Design Description
Revision 02
SRS-RASCAL-
20140110
Requirements Specification Unified RASCAL Interface
Revision 02
Procedures
HPCAL 3.17
SPING Calibration Procedure
Revision 0
Work Orders
4035767401
1RE-231 Calibration
03/18/2016
4046900301
RM-SPRING-23 Calibration
2/13/2017
4046911302
RM-SPING23 Pre-Calibration
2/13/2017
4047338801
1RE-231 Calibration
10/15/2017
Corrective Action
Documents
286174
Thermal Loading from Design-Basis Accident Exceeds
Platform [Capacity]
10/16/2018
297419
Unit 2 Manway Platforms Thermal Loading Results
01/10/2019
2303987
Management Escalation: Procedure Use and Adherence
Gap
03/01/2019
2307731
03/28/2019
2307741
Maintenance Department Clock Reset
03/28/2019
2308008
Cognitive Trend: Procedure Use and Adherence
03/29/2019
2308185
Trend AR - BHI Human Performance Behaviors
03/31/2019
2308252
Combustible Liquid Quantity Exceeds TCCP Limit
03/31/2019
2308260
Compressed Flammable Gas Cylinders Exceed Limit
03/31/2019
2308895
Untreated Wood in PAB Truck Bay
04/04/2019
2309962
Escalation: Procedure Use and Adherence
04/10/2019
2311488
Data Entry Error During Generation of NIS Currents
04/20/2019
2311530
Unit 1 Enters LCO 3.4.1 PZR Pressure Less than 2205
04/21/2019
Corrective Action
Documents
Resulting from
Inspection
2314702
OP 3A, Power Operations to Hot Standby Step Performance
05/16/2019
Fire Plans
PFP-0-PAB 26
Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 26
PFP-1-TB 8
Pre-Fire Plan Unit 1 Turbine Hall Building Elevation 8'
Inspection
Procedure
Type
Designation
Description or Title
Revision or
Date
Procedures
1RESP 6.1
Core Power Distribution and Nuclear Power Range
Calibration Unit 1
04/20/2019
NP 1.9.9
Transient Combustible Control
OP 3A Unit 1
Power Operation to Hot Standby Unit 1
Self-Assessments 2304521-01
Negative Trend in Fleet Engineering Program
Implementation
05/14/2019
2304925
PBN L1A on HU Recovery Effectiveness (RWA 02304925-
01)
03/28/2019