IR 05000266/2019002

Integrated Inspection Report 05000266/2019002 and 05000301/2019002

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

uly 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: DPR-24 and DPR-27 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 Enclosure

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: 71152.

List of Findings and Violations Human Performance Error Causes Unplanned Pressurizer Pressure Drop Cornerstone Significance Cross-Cutting Report Aspect Section Initiating Events Green [H.12] - Avoid 71111.20 NCV 05000266/2019002-01 Complacency Open 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.

71111.01 - Adverse Weather Protection Summer Readiness Sample (IP Section 03.01)

(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)

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) 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)

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) 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)

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)

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)

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)

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)

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) 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) 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)

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,

71124.01 - Radiological Hazard Assessment and Exposure Controls Contamination and Radioactive Material Control (IP Section 02.03)

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

• Steam Generator Eddy Current Testing 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)

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)

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

• HEPA ventilation for RTD tent 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) 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)

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) 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 Report Aspect Section Initiating Events Green [H.12] - Avoid 71111.20 NCV 05000266/2019002-01 Complacency Open 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 Type Designation Description or Title Revision or

Procedure Date

71111.01 Corrective Action 2314350 NRC Items Identified during Switchyard Walkdown 05/14/2019

Documents

Resulting from

Inspection

Miscellaneous PBNP-MISO- Nuclear Plant Operating Agreement for Point Beach Nuclear 7

NUC-001 Plant

Procedures NP 2.1.5 Electrical Communications, Switchyard Access and Work 32

Planning

NP 5.2.19 NERC Standard NUC-001 Nuclear Plant Interface 2

Coordination Agreement Control

71111.04 Drawings 110E018, Sheet 3 Auxiliary Coolant System 45

110E018, Sheet 5 CCW Minimum Flow Recirculation Cross Connect Details 00

M-201, Sheet 1 P&ID Main & Reheat Steam System 62

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 20

CL 13E Part 1 Auxiliary Feedwater Valve Lineup Turbine-Driven Unit 1 52

CL 5A Chemical and Volume Control System Unit 1 31

71111.04S Drawings 110E018, Sheet 1 P&ID Auxiliary Coolant System 71

110E018, Sheet 2 P&ID Auxiliary Coolant System 22

110E018, Sheet 3 P&ID Auxiliary Coolant System 45

110E029, Sheet 1 P&ID Auxiliary Coolant System 57

110E029, Sheet 2 P&ID Auxiliary Coolant System 17

110E029, Sheet 3 P&ID Auxiliary Coolant System 46

110E029, Sheet 4 P&ID Auxiliary Coolant System 00

Procedures 1-CL-CC-001 Component Cooling Unit 1 20

2-CL-CC-001 Component Cooling Unit 2 19

71111.05Q Corrective Action 2300129 Material Missing From Structural I Beams 1/31/2019

Documents

Resulting from

Inspection

Fire Plans PFP-0-CB Control Building Elevation 8', 26', 44' and 66' 1

Inspection Type Designation Description or Title Revision or

Procedure Date

PFP-0-PAB-26 Auxiliary Building 26' 0

PFP-0-PAB-8 Primary Auxiliary Building Elevations 8' and Below 0

PFP-0-PAB-8 Pre-Fire Plan Primary Auxiliary Building Elevations 8' and 0

Below

71111.08P Corrective Action AR 2309189 Anomaly During U1R38 SG Tube Plug Installation 04/05/2019

Documents AR 2309427 Debris Found on Unit 1 Reactor Pressure Vessel Closure 04/08/2019

Head

AR 2309430 Boric Acid Streaking from CETNA 37 on Unit 1 RPV Head 04/08/2019

AR 2309467 Boric Acid Streaking from CETNA 35 on Unit 1 RPV Head 04/08/2019

AR 2309598 Recordable Indication on RTD Bypass Piping Support RC- 04/09/2019

2501R-14-102R

Corrective Action AR 2307462 Weld Data Sheets in Incorrect Record 03/26/2019

Documents AR 2309226 Incorrect Revision of Code Case N-729 Referenced in NDE 04/05/2019

Resulting from Procedure

Inspection

Engineering 17-198B-E Safety Injection Pump Inboard Seal Leakoff Area and Pump 04/17/2018

Evaluations Skid Below

18-021-E 1P-2A CHG Pump Discharge Header Drain First Off 03/27/2018

Isolation/8/PAB/U1

LTR-CECO-19- Evaluation of Roll Expanded Mechanical Tube Plug 04/08/2019

29 Extending from the Tubesheet in Tube R13C49 in SGA Cold

Leg at Point Beach Unit 1

Miscellaneous NPM 2007-0145 Documentation of Point Beach Nuclear Plants Position on 04/24/2007

the Use of Liquid Penetrant and Magnetic Particle Materials

Contained in Aerosol Containers and Stored Under Ambient

Conditions

NSAL-12-1 Nuclear Safety Advisory Letter for Steam Channel Head Revision 1

Degradation

NSD-TB-94-03- Westinghouse Technical Bulletin for Steam Generator 05/02/1994

R0 Secondary Side Erosion-Corrosion

SG-CDMP-19-3 Point Beach U1R38 Steam Generator Degradation Revision 1

Assessment

NDE Reports 2019U1PT-001 Liquid Penetrant Examination of Component AC-601R-6-H4- 04/02/2019

IWA

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures FP-PE-B31- ASME-Welding Procedure Specification Revision 6

P1P1-GTSM-001

FP-PE-B31- ASME-Welding Procedure Specification Revision 5

P8P8-GTSM-037

MRS-GEN-1217 Rolled Mechanical Plug Installation Using the Advanced Revision 5

Rolling Tool and the Universal Platform Control Box

NDE-173 PDI Generic Procedure for the Ultrasonic Examination of Revision 17

Austenitic Piping Welds

NDE-201 Radiographic Examination Revision 6

NDE-451 Visible Dye Penetrant Examination Temperature Revision 30

Applications 45°F to 125°F

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 2314216 Simulator Issue Negatively Affected LOC Evaluated 5/13/2019

Documents Scenario

Procedures OP 1B Reactor Startup 77

OP-AA-100-1000 Conduct of Operations 27

71111.12 Corrective Action 2263887 K-3B SA Compressor High Temp/Standby Compressor Start 05/11/2018

Documents 2264862 K-3B Service Air Compressor Discharge Temp High Alarm 05/17/2018

Received

291891 K-3B Service Air Compressor Improper Operation 11/21/2018

297959 K-3B Service Air Compressor Rapid Motor Vibration 01/15/2019

Increase

2308290 NI System Maintenance Rule Evaluation Inconsistencies 04/01/2019

Identified

2316963 U1 CW System Exceeds Maintenance Rule Performance 06/05/2019

Criteria

2317207 SA System Exceeds Maintenance Rule Performance Criteria 06/07/2019

Corrective Action 2308290 NI System Maintenance Rule Evaluation Inconsistencies 4/1/2019

Documents Identified

Resulting from

Inspection Type Designation Description or Title Revision or

Procedure Date

Inspection

Miscellaneous Service Air Reliability Event Report 04/01/2017-

04/29/2019

71111.13 Corrective Action 2319493 IT-90 Train B Test Moved PRA Risk Review Not Done In 06/27/2019

Documents Advance

Resulting from 2319494 DGB Door 107 Not Self Latching 06/27/2019

Inspection

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 04/11/2019

Checklist

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

71111.15 Calculations CN-CPS-07-8 Point Beach Reactor Coolant Flow Instrumentation Setpoint 3

and Uncertainty Calculation (1C-41)

Corrective Action 2308372 Steam Generator Snubber HS-9 Failed Functional Test 04/01/2019

Documents 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 05/21/2019

U1R38

Corrective Action 2311877 CR 02308372 Canceled Versus Processed 04/23/2019

Documents 2312945 Water Up to ISI-850A-O (Operator) in Tendon Gallery 05/01/2019

Resulting from

Inspection

Drawings 617F354, Sheet Schematic Diagram - Inputs, Reactor Protection System 3

4A1 Train "A," Unit 1

Miscellaneous 01257 Model 1154 Alphaline Pressure Transmitter 7

Operability 165 SSC Affected by Condition: 1&2 SI-00850A&B, RHR Pump 11/06/2005

Evaluations Suction from Sump B

Inspection Type Designation Description or Title Revision or

Procedure Date

2315095 1P-11A had Elevated Vibrations During IT-12 Train A 05/21/2019

Procedures MA-AA-203-1000 Maintenance Testing 13

RMP 9061-3 Anker Holth Snubber Removal, Functional Testing, and 17

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 04/17/2019

Span Adjustment

40665209 1P-11A CCW Pump - Coupling Alignment Verification 06/12/2019

71111.18 Calculations 2014-06279 Time Available to Respond to Rising Lake Level 0

Engineering EC - 281811 External Wave Run-up Flood Mitigation Strategy 0

Changes EC-293289 Basis for Changing Monitored Lake Level from the Highest 06/05/2019

of All Reporting Stations to the Mean of All Reporting

Stations

Miscellaneous 2316179 PBF-2124A - Maximum Converted Lake (Doc Dist) 05/30/2019

PBF-2124a Maximum Converted Lake Level Calculation 1

PBF-2124a Average Converted Lake Level Calculation 2

PCR 2316179 10 CFR 50.59 Screening Form: PBF-2124a, Maximum 06/05/2019

Converted Lake Level Calculation

Procedures AOP-13C Severe Weather Conditions 47

71111.19 Corrective Action 2304474 PMT Failed on HX-105A 03/05/2019

Documents 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 04/02/2019

Task

2315175 1P-011A IST PMT Not Performed After 1P-011B Re-Piping 05/21/2019

U1R38

Procedures IT 12A CC Pumps and Valves While Aligned for RHR Operation 26

(Cold Shutdown) Unit 1

Work Orders 2312548 K-2 Relay Found With Broken Center Post 04/29/2019

40543692 02 2P-010A/OPS PMT 01/17/2019

40582325 01 B52-DB50-011; Breaker Maintenance Per RMP-9303 and 03/05/2019

RMP-9369-1

Inspection Type Designation Description or Title Revision or

Procedure 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

WO 40104553-49 1P-011B - Operations PMT - RTS

71111.20 Corrective Action 2310563 Deficiencies Noted During CL 20/20A Walkdown 4/14/2019

Documents 2310581 CL-20 CTMT Walkdown Items Identified 4/15/2019

Corrective Action 2310884 NRC Observations During NOP/NOT & Key Way Walkdown 04/16/2019

Documents

Resulting from

Inspection

Drawings 500B728; Sheet Main Control Board Component Wiring 4

541F091; Sheet 1 P&ID Reactor Coolant System 56

541F091; Sheet 2 P&ID Reactor Coolant System 41

Engineering EC 292423 Point Beach Unit 1 Cycle 39 Core Reload Modifications 0

Changes

Miscellaneous PBNP Shutdown Safety Assessment and Fire Inspection 03/26 -

Checklist 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 04/12/2019

Fire Brigade

AF AF-4000-O Clearance Package 4/11/2019,

4/15/2019

Inspection Type Designation Description or Title Revision or

Procedure Date

OP-3C Accum Clearance Package 4/15/2019

Out

Procedures ARB 1C04 1C 2-8 Alarm Response Book; BA Flow Deviation or Potential 9

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 42

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

WO 40521042 1ICP 13.14 - Core Exit T/C Recorder Calibration 12/18/2017

WO 40573349 1ICP 2.8-1 NI Axial Offset Calibration 4/22/2019

71111.22 Corrective Action 2296665 South SW Header Flowmeter Calibration 01/04/2019

Documents 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 2310121 Procedure Use and Adherence Issue 04/11/2019

Documents 2310869 Rebaselining of P-32A and P-32C Improvements 04/16/2019

Resulting from

Inspection

Miscellaneous 2291226 10CFR50 Appendix J Program Routing Task - 2018-2019 04/14/2019

IST Program Inservice Testing Program Document 8

Document

SCR 2014-0011 Revisions to IT 07C Following Rebaselining of P032C, 01/17/2014

Service Water Pump

Procedures 1-PT-RCS-1 Reactor Coolant System Pressure Test - Inside/Outside 9

Containment Unit 1

IT 230 Leak Test of Class 1 Components Following a Refueling 38

Shutdown Unit 1

IT 45 Train B Safety Injection Valves Train B Unit 2 8

Inspection Type Designation Description or Title Revision or

Procedure Date

OI 58 Leak Testing of Containment Isolation Valves - Unit 1 and 2 28

General Instructions and Information

ORT 6 Containment Spray Sequence Test Unit 1 28

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

71114.06 Corrective Action 2315151 EP Drill - Accountability in NES 05/21/2019

Documents 2315188 EP Pre-Existing Accountability 05/21/2019

2315195 NA Identified Gaps - EP Pre-Exercise (TSC) 05/21/2019

Miscellaneous PBN EPR 192 Emergency Preparedness (EP) Drill Manual for the 2019 EP 05/21/2019

001D Pre-Exercise

71124.01 Corrective Action 02255246 Source Leak Check Documentation Gaps 03/21/2018

Documents 02270541 Neutron Correction Factor Not Auto Adding Correctly 06/29/2018

285855 Dosimeter - Rate Alarm Encountered During Snubber 10/15/2018

Inspection

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 04/05/2019

Sludge

Procedures RP-AA-100-1002 Radiation Worker Instruction and Responsibilities Revision 8

RP-AA-102-1000 Alpha Monitoring Revision 4

Radiation 30-105 Airborne Radioactivity Survey 04/03/2019

Surveys30-106 Airborne Radioactivity Survey 04/03/2019

30-108 Airborne Radioactivity Survey 04/03/2019

30-112 Airborne Radioactivity Survey 04/03/2019

PBPROD-M- Unit 1 Reactor Cavity - Upper Level - Initial Entry 03/22/2019

20190300-20

PBPROD-M- U-1 Reactor Upper Cavity - Post Decon on Floor 03/25/2019

20190325-30

PBPROD-M- 66' U-1 Containment Shiftly Routine 03/31/2019

20190331-39

PBPROD-M- 66' U-1 Containment Shiftly Routine 04/01/2019

20190401

Inspection Type Designation Description or Title Revision or

Procedure Date

PBPROD-M- U1 Daily Outage Routines Spent Fuel Pool 04/02/2019

20190402-40

PBPROD-M- Unit 1 Containment B Elevation 10 Foot Platform 04/02/2019

20190402-55

PBPROD-M- Unit 1 B Cold Leg RTD Manifold Removal 04/02/2019

20190403-21

PBPROD-M- BG C/L RTD Rebuild Tent 04/03/2019

20190403-25

PBPROD-M- Reactor Coolant Pump Lower, B Side U1 Post 04/04/2019

20190404-2 Shielding/Contamination Survey

PBPROD-M- Reactor Coolant Pump Lower, B Side U1 Job Coverage 04/04/2019

20190404-30

PBPROD-M- Reactor Coolant Pump Lower, B Side U1 Impeller Removal 04/04/2019

20190404-32

PBPROD-M- U1 Daily Outage Routines Spent Fuel Pool 04/04/2019

20190404-41

Radiation Work 19-1021 B RCP Maintenance Seal Replacement Revision 2

Permits (RWPs) 19-1053 Unit 1 Narrow Range RTD Replacement Revision 2

19-1056 FOSAR Activities Revision 1

19-1057 S/G Eddy Current Testing Revision 00

19-1064 Unit 1B RCP Impeller Change Out and Pump Bowl Revision 1

Inspection

71124.02 ALARA Plans R-003 Replace B Loop Hot Leg RTD Manifold and Refurbish B 03/29/2019

Cold Leg Manifold (Mechanical Cut-Out and Replace)

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 02308213 Narrow Range RTD Replacement Work is Tracking Above 03/31/2019

Documents Estimate

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 RP-AA-104-1000 ALARA Implementing Procedure Revision 15

71124.03 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 Type Designation Description or Title Revision or

Procedure Date

Corrective Action 02290219 HPIP 3.58.1 Air Sampling Process Instruction Review 11/09/2018

Documents

Miscellaneous HP-100-101718 Review of Steam Generator Channel Head Ventilation 10/18/2018

Practices

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

71124.04 Calculations High Level Contamination Report and Associated Dose 10/28/2017

Calculations for RWP 17-1027

High Level Contamination Report and Associated Dose 10/28/2017

Calculations for RWP 17-1016

Whole Body Count Evaluation for Radiation Protection 04/08/2017

Individual

Whole Body Count Evaluation for Radiation Protection 10/29/2017

Individual

Whole Body Count Evaluation for BHI Individual 10/29/2017

Whole Body Count Evaluation for Maintenance Individual 05/14/2018

Corrective Action 02253282 WBC Procedural Guidance Not Updated Following 03/08/2018

Documents Evaluation

255763 Error in DACDOS Calculation 03/23/2018

Procedures NP 4.2.15 Fetal Protection Policy Implementation Revision 7

71124.06 Calculations Calibration Factor Steam Line Monitors 06/21/1983

2013-0018 Radiological Effluent Initiating Condition Values For Revision 03

Emergency Action Level RS1 and RG1

99-0106 Dose Rate Calculations for Steam Line Monitors Calibration Revision 0

Factor

Miscellaneous Permanent Procedure and Procedure Revision Review and 04/21/1993

Approval for HPCAL 3.7, Steam Line Radiation Monitor

Calibration Procedure

Permanent Procedure and Procedure Revision Review and 08/20/1990

Approval for HPCAL 3.7, Steam Line Radiation Monitor

Calibration Procedure

349-17-1 Certificate of Gamma Standard Source for Cs-137 Source 08/01/1989

Inspection Type Designation Description or Title Revision or

Procedure Date

Number 349-17-1

65089-10 Certificate of Radioactivity Calibration for Kr-85 Source 10/01/1981

Number 65089-10

SDD-RASCAL- Unified RASCAL Interface Technical Design Description Revision 02

20140110

SRS-RASCAL- Requirements Specification Unified RASCAL Interface Revision 02

20140110

Procedures HPCAL 3.17 SPING Calibration Procedure Revision 0

Work Orders 4035767401 1RE-231 Calibration 03/18/2016

4046900301 RM-SPRING-23 Calibration 02/13/2017

4046911302 RM-SPING23 Pre-Calibration 02/13/2017

4047338801 1RE-231 Calibration 10/15/2017

71152 Corrective Action 2286174 Thermal Loading from Design-Basis Accident Exceeds 10/16/2018

Documents Platform [Capacity]

297419 Unit 2 Manway Platforms Thermal Loading Results 01/10/2019

2303987 Management Escalation: Procedure Use and Adherence 03/01/2019

Gap

2307731 MOV Diagnostic of 1SI-860C 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 2314702 OP 3A, Power Operations to Hot Standby Step Performance 05/16/2019

Documents

Resulting from

Inspection

Fire Plans PFP-0-PAB 26 Pre-Fire Plan Unit 1 & Unit 2 Auxiliary Building 26 0

PFP-1-TB 8 Pre-Fire Plan Unit 1 Turbine Hall Building Elevation 8' 0

Inspection Type Designation Description or Title Revision or

Procedure Date

Procedures 1RESP 6.1 Core Power Distribution and Nuclear Power Range 04/20/2019

Calibration Unit 1

NP 1.9.9 Transient Combustible Control 36

OP 3A Unit 1 Power Operation to Hot Standby Unit 1 17

Self-Assessments 2304521-01 Negative Trend in Fleet Engineering Program 05/14/2019

Implementation

2304925 PBN L1A on HU Recovery Effectiveness (RWA 02304925- 03/28/2019

01)

27