IR 05000483/2019002

Integrated Inspection Report 05000483/2019002

ML19221B450
Person / Time
Site:	Callaway
Issue date:	08/09/2019
From:	O'Keefe N NRC/RGN-IV/DNMS/NMSB-B
To:	Diya F Ameren Missouri
References
IR 2019002
Download: ML19221B450 (51)

Text

August 9, 2019 Mr. Fadi Diya Senior Vice President and Chief Nuclear Officer Ameren Missouri Callaway Plant 8315 County Road 459 Steedman, MO 65077 SUBJECT: CALLAWAY UNIT 1

- INTEGRATED INSPECTION REPORT 05000483/2019002

Dear Mr. Diya:

On June 30, 2019 , the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Callaway Plant. On July 2, 2019 , the NRC inspectors discussed the results of this inspection with Mr. T. Herrmann, Site Vice President, and other members of your staff.

The results of this inspection are documented in the enclosed report. The NRC inspectors did not identify any finding or violation of more than minor significance

. 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/ Neil F. O'Keefe, Chief Reactor Projects Branch B Docket No.: 05000483 License No

.: NP F-30 Enclosure:

Inspection Report 05000483/2019002 With Attachments:

Documents Reviewed Request for Information Occupational Radiation Safety Inspection Request for Information Public Radiation Safety Inspection

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensee's performance by conducting a n integrated inspection at the Callaway Plant in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRC's program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information

. List of Findings and Violations No findings or violations of more than minor significance were identified.

Additional Tracking Items None.

3

PLANT STATUS

Callaway began the inspection period at approximately 20 percent power with a planned shutdown in progress for the refueling outage.

On April 1, 2019, the licensee shut down the reactor and commenced the planned refueling outage.

On April 17 , with the reactor defueled and in no Mode, safety

-related bus NB01 lost power and was automatically reenergized by the associated emergency diesel generator due to a loss of the 365 kV switchyard bus (NRC Event 54005). On May 11 , with the reactor in Mode 4, the licensee identified an auxiliary building door that had been blocked open through reactor Mode ascension (NRC Event 54061). On May 16 , the licensee commenced a reactor startup. Later that day, an automatic reactor trip occurred due to high flux in the source range (NRC Even t 54069) when operators failed to block this trip when conditions called for them to do so. On May 17 , the licensee commenced a reactor startup. On May 18 , the licensee tripped the main turbine due to high vibrations and the reactor remained critical, by design, due to the low power level at the time of the turbine trip. The licensee restored the main turbine to service and connected the main generator to the electric grid on May 19. The licensee reached full power on May 22 and remained at this power level through the end 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)

The inspectors evaluated summer readiness of offsite and alternate alternating current (AC) power systems on June 5, 2019. The inspectors also reviewed the prioritization of efforts to restore offsite power to support Callaway, including a tour of the Ameren Transmission facility in St. Louis, for a design basis loss of offsite power event.

71111.04 - Equipment Alignment

===Partial Walkdown Sample (IP Section 03.01)

(4 Sample s) The inspectors evaluated system configurations during partial walkdowns of the following systems/trains:

(1) Essential service water trains A and B on April 22, 2019

(2) Emergency diesel generator train A on April 28, 2019

(3) Residual heat removal system train B on May 8, 2019

(4) Main turbine and electro

-hydraulic control systems on June 4, 2019

71111.05Q - Fire Protection

Quarterly Inspection (IP Section 03.01)

(5 Sample s) The inspectors evaluated fire protection program implementation in the following selected areas:

(1) Switchyard including switchyard control building, fire area S

-15 on April 22, 2019

(2) Spent fuel pool, bridge, and laydown area, fire area FB

-1 on May 10, 2019

(3) Control building 2016' elevation, fire areas C

-13, C-15, C-17, and C-35 on May 29, 2019

(4) Spent fuel pool heat exchanger rooms and cask wash down area, fire area FB-1 on June 4, 2019

(5) Emergency diesel generator train A and essential switchgear train B, fire areas D-1 and C-10 on June 20, 2019

71111.06 - Flood Protection Measures

Inspection Activities

- Internal Flooding (IP Section 02.02a.)===

The inspectors evaluated internal flooding mitigation protections in the:

(1) Control building 1974' elevation, room 3101, on May 8, 2019

71111.07A - Heat Sink Performance

Annual Review (IP Section 02.01)

The inspectors evaluated readiness and performance of:

(1) Component cooling water heat exchanger EEG01A on April 4, 2019 71111.08P

- Inservice Inspection Activities (PWR)

PWR Inservice Inspection Activities Sample (IP Section 03.01) (1 Sample) The inspectors verified that the reactor coolant system boundary, steam generator tubes, reactor vessel internals, risk

-significant piping system boundaries, and containment boundary are appropriately monitored for degradation and that repairs and replacements were appropriately fabricated, examined and accepted by reviewing the following activities from April 8 through April 12, 2019: 03.01.a - Nondestructive Examination and Welding Activities

(1) NDE activity type:

Magnetic Particle Testing (MT)a) Pipe to flange weld (FW

-01), Job #17002729, Task 180, Report 5010-19-0001, ASME Class 3 b) Pipe to crossover tee weld (FW

-17), Job # 17002729, Task 500, Report 5010 0008, ASME Class c) Pipe to elbow weld (FW

-21), Job # 17002729, Task 500, Report 5010 0009, ASME Class 3 d) Pipe to crossover tee weld (FW

-10), Job # 17002729, Task 500, Report 5010-19-0012, ASME Class

(2) NDE activity type:

Ultrasonic Testing (UT)a) RPV replacement stud 2, Report 19-000245, ASME Class1

(3) NDE activity type:

Visual Testing (VT)a) Fuel transfer system tube and flange, Job #17512708, Task 510, Report 5040-19-002, ASME Class IWE (VT

-1) 03.01.b - Pressurized

-Water Reactor Vessel Upper Head Penetration Examination Activities

(1) Penetration numbers 1 through 78, Job #13503632; no indications identified 03.01.c - Pressurized

-Water Reactor Boric Acid Corrosion Control Activities

(1) Condition Report 201800861-002, boric acid screen and evaluation

(2) Condition Report 201801218-001, boric acid screen and evaluation

(3) Condition Report 201801218-002, boric acid screen and evaluation 03.01.d - No steam generator tube inspections were performed this inspection period 03.01.e - The inspector s reviewed 10 condition reports associated with inservice inspection related topics and determined that the licensee was entering issues into the corrective action program and taking appropriate actions to resolve

71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance

Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01)

The inspectors observed and evaluated licensed operator performance in the control room during:

(1) Reduced reactor coolant system inventory, including infrequently performed test or evolution (IPTE) briefs, on May 5, 2019

(2) Vacuum fill of the reactor coolant system on May 6, 2019 Licensed Operator Requalification Training/Examinations (IP Section 03.02)

(1 Sample) The inspectors observed and evaluated licensed operator training in the simulator for:

(1) Reactor start

-up on May 6, 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) Essential service water including butterfly valves on April 8, 2019 Quality Control (IP Section 02.02)

(1 Sample) The inspectors evaluated maintenance and quality control activities associated with the following equipment performance activities:

(1) Residual heat removal train A including hand

-switches on June 21, 2019

71111.13 - Maintenance Risk Assessments and Emergent Work Control

===Risk Assessment and Management Sample (IP Section 03.01)

(4 Sample s) The inspectors evaluated the risk assessments for the following planned and emergent work activities:

(1) Planned elevated risk during polar crane maintenance and operation on April 4, 2019

(2) Planned elevated risk for the train A work window on April 8, 2019

(3) Planned elevated risk during switchyard maintenance on April 2, 2019

(4) Planned elevated risk for reactor power ascension and recovery of a digital turbi ne hydraulics controller on May 20, 2019

71111.15 - Operability Determinations and Functionality Assessments

Operability Determination or Functionality Assessment (IP Section 02.02)

(6 Sample s) The inspectors evaluated the following operability determinations and functionality assessments:

(1) Drop ped control rod H

-8, Condition Report 201901077, on April 12, 2019

(2) Turbine-driven auxiliary feedwater pump internal inspection results, Condition Report 201902635, on April 17, 2019

(3) Reactor coolant motor

-operated valve BBHV0016 stem nut wear, Condition Report 201902462, on April 18, 2019

(4) Switchyard breaker MDV45 failure to close, Condition Report 201902658, on April 18, 2019

(5) Essential service water failure analysis for valves EFHV0065 and EFHV0066, Condition Report 201806521, on May 9, 2019

(6) Control room air conditioning unit SGK04A degraded cooling capacity, Condition Report 201904050, on May 31, 2019

71111.18 - Plant Modifications

Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02)===

The inspectors evaluated the following permanent modification:

(1) Main turbine generator governor controls, MP 08

-0027, on April 4, 2019

71111.19 - Post-Maintenance Testi

===ng Post Maintenance Test Sample (IP Section 03.01)

(7 Sample s) The inspectors evaluated the following post maintenance tests:

(1) Polar crane and load cell after equipment outage on April 6, 2019

(2) Ultimate heat sink cooling tower fans train B after equipment outage on April 12, 2019

(3) Essential service water modification MP 17-0006 on April 16, 2019

(4) 36 kV circuit breaker MDV55 after modification on April 22, 2019

(5) Main feedwater regulating valves AEFCV0510 and AEFCV0530 after equipment outage on May 5, 2019

(6) 125 Vdc battery NK11 after replacement on May 13, 2019

(7) Load shedding and emergency load sequencing train A after equipment outage on May 19, 2019

71111.20 - Refueling and Other Outage Activities

Refueling/Other Outage Sample (IP Section 03.01)===

(1) The inspectors evaluated refueling outage RF23 from April 1 through May 22, 2019

71111.22 - Surveillance Testing

===The inspectors evaluated the following surveillance tests:

Inservice Testing (IP Section 03.01)

(2 Sample s)

(1) Pressurizer power operated relief valve inservice test in Mode 4 on April 3, 2019

(2) Component cooling water cross tie valves inservice testing on June 2, 2019 Reactor Coolant System (RCS) Leakage Detection Testing (IP Section 03.01)===

(1) RCS water inventory balance surveillance post

-reactor startup from Refueling Outage RF23 on June 19, 2019 Surveillance Tests (other) (IP Section 03.01)

(3 Sample s)

(1) Engineered safety features actuation systems train A on April 5, 2019

(2) Class 1E electrical equipment air conditioning system actuation and flow test on date May 11, 2019

(3) Turbine-driven auxiliary feedwater pump test in Mode 3 on May 15, 2019

71114.04 - Emergency Action Level and Emergency Plan Changes

===Inspection Review (IP Section 02.01

-02.03)===

(1) The inspectors evaluated Procedure EIP-ZZ-00101, Addendum 2, "Emergency Action Level Technical Basis Document," Revision 16, on May 1, 2019 This evaluation does not constitute NRC approval.

71114.06 - Drill Evaluation

Select Emergency Preparedness Drills and/or Training for Observation (IP Section 03.01)

(1) Team 4 full participation emergency response organization drill on June 6,

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. The inspectors verified the following sealed sources are accounted for and are intact:

(1) 0029GZ

(2) 3217GN

(3)81-616

(4) 0819GG/4660

(5) E-083/S-13

(6) CNP-148

(7) MRC-4108 High Radiation Area and Very High Radiation Area Controls (IP Section 02.05)===

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:

Radiation work packages

(1) R23HDDESTUD, Revision 0

- install stud tensioner hoists, deten 0sion reactor vessel studs, remove reactor vessel studs, clean stud holes, lubricate stud holes, install stud hole plugs, and install guides studs/pins

(2) R23HDSTUD18, Revision 0

- Refuel 23 activities to remove reactor vessel stuck stud 18, including thread repairs, and inspect its stud hole; includes cutting, boring, QC/Engineering inspections, and associated cavity work (except cavity decontamination)

(3) R23STD18DECON, Revision 0

- RF23 upper cavity gross rinse, vacuum of seal ring, upper cavity decontamination, and reactor vessel flange cleaning to support removal of stuck reactor vessel stud 18, includes all Radiation Protection coverage and surveys

(4) R23ENGHRA, Revision 0

- R23 engineering activities inside high radiation areas in all radiologically controlled areas including the reactor building

(5) 16003707510, Revision 0

- RT new nipolet to valve weld on Valve EMV0161 Electronic alarming dosimeter alarms

(1) The licensee did not have an occurrence of a dosimeter alarm during the inspection period. The inspectors reviewed corrective action documents, radiation work permits and ALARA plans, as well as, interviewed workers to ensure the licensee was evaluating and controlling occupational worker exposures appropriately.

Labeling of containers

(1) Framatome core offloading/reloading and stuck stud removal equipment boxes

(2) Westinghouse fuel assembly inspection equipment boxes

(3) Pipefitters equipment boxes for the radiologically controlled area use

(4) Radioactive material (radioactive source) storage containers

(5) Radioactive material trash bags in the reactor containment building and auxiliary building Radiation Worker Performance and Radiation Protection Technician Proficiency (IP Section 02.06) (1 Sample) 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. The inspectors reviewed the following:

Radiological surveys

(1) General containment

(2) Reactor cavity

(3) Reactor h ead

(4) Inside bioshield

(5) Incore t unnel Risk significant radiological work activities

(1) Reactor head lift

(2) Refuel activities

(3) Reactor head stud replacement

- stuck stud 2 and 18

(4) Cavity decontamination

(5) Radiography Air sample survey records

(1) Reactor containment building entries: 29-MAR-19-200005,7,8; and 31-Mar-19-200004, 5, 8

(2) Reactor containment building outage dailies

08-APR-19-200008,9,10; 09-APR-19-200012,13,14; and 10

-APR-19-200004,5,6

(3) Reactor cavity: 08-APR-19-200023, 24; 08-APR-19-200025, 26; 09-APR-19-200003,5; 09

-APR-19-200006,8; and 10

-APR-19-200023, 24

(4) Reactor head stand O

-ring cutout: 10-APR-19-200007,18

(5) Breach of Valve BGHV8149B: 10-APR-19-200029, 34 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.

Radiological work package for areas with airborne radioactivity

(1) There were no radiation work permits with airborne radioactivity available for review during this inspection.

The inspectors reviewed radiation work permits with the highest potential for airborne radioactivity and the results for air samples taken during the inspection period.

71124.02 - Occupational ALARA Planning and Controls

Implementation of ALARA and Radiological Work Controls (IP Section 02.03)

The inspectors reviewed ALARA practices and radiological work controls by reviewing the following activities:

(1) RWP 16003707510, EMV0161 radiography

(2) RWP R23HDSTUD18, remove stuck stud 18

(3) RWP R23STD18DECON, RF23 Cavity Decontamination Radiation Worker Performance (IP Section 02.04)

(1 Sample) The inspectors evaluated radiation worker and radiation protection technician performance during general work in containment, decontamination of the vessel flange in preparation for the removal of stuck stud 2, and during the radiography of EMV0161 in the auxiliary building.

71124.05 - Radiation Monitoring

Instrumentation Calibration and Testing Program (IP Section 02.02)

The inspectors evaluated the calibration and testing program implementation.

The inspectors reviewed the following:

Alarm Setpoint and Calibration Method Check of Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

(1) TM-4010-HP

(2) PM-4046-HP Failure to Meet Calibration or Source Check Acceptance Criteria

(1) CRM-4190-HP Walk Downs and Observations (IP Section 02.01)

(1 Sample) The inspectors evaluated radiation monitoring instrumentation during plant walkdowns.

The inspectors reviewed the following:

Portable Survey Instruments

(1) CRM-4025-HP

(2) CRM-4087-HP

(3) CRM-4134-HP

(4) CRM-4023-HP

(5) CRM-4089-HP

(6) ION-4174-HP

(7) GMI-4178-HP Source Check Demonstration

(1) ION-4172-HP

(2) CRM-4115-HP

(3) GMI-4178-HP Area Radiation Monitors and Continuous Air Monitors

(1) 0-EG-RE-09

(2) 0-GT-RE-33

(3) 0-SD-RE-24

(4) 0-SD-RE-38

(5) CAM-4019-HP

(6) CAM-4020-HP Personnel Contamination Monitors, Portal Monitors and Small Article Monitors

(1) TM-4010-HP

(2) PCM-4054-HP

(3) PM-4046-HP

71124.06 - Radioactive Gaseous and Liquid Effluent Treatment

Calibration and Testing Program (Process & Effluent Monitors) (IP Section 02.02)

The inspectors reviewed the following gaseous and liquid effluent monitor instrument calibrations and tests:

(1) GH-RE-10 radwaste building unit vent functional test, June 13, 2019

(2) GT-RE-21A plant unit vent calibration, January 29, 2019

(3) GT-RE-21B plant unit vent calibration, August 23, 2018

(4) HB-RE-18 liquid radwaste discharge monitor calibration, August 21, 2018 Dose Calculations (IP Section 02.05)

(1 Sample) The inspectors reviewed the following liquid and gaseous discharge permits to evaluate public dose calculations:

(1) Batch liquid radioactive release permit numbers

RP09-2019-L0037;0 RP09-2018-L0007;1 RP09-2017-L0028;1

(2) Batch airborne radioactive release permits

RP11A-2019-G0013;1 RP13-2018-G0002;56 RP13-2017-G0006;52 The inspectors reviewed the following annual radiological effluent release reports:

(1) 2017 Annual Radiological Effluent Release Report

(2) 2018 Annual Radiological Effluent Release Report The inspectors also reviewed the following abnormal gaseous or liquid tank discharges:

(1) None were available for review during this inspection Instrumentation and Equipment (IP Section 02.04)

(1 Sample) The inspectors reviewed the following radioactive effluent discharge system surveillance test results:

(1) Auxiliary/fuel building emergency exhaust filter adsorber Unit B, in-place leak test

(2) Control room pressurization filter adsorber Unit B, in-place leak test

(3) Control room filter adsorber Unit A, in-place leak test Sampling and Analysis (IP Section 02.03)

(1 Sample) The inspectors reviewed the following radioactive effluent sampling and analysis activities:

(1) None were available for review during this inspection The inspectors reviewed the following effluent discharge:

(1) June 11, 2019 , discharge monitor tank A discharge Walk Downs and Observations (IP Section 02.01)

(1 Sample) The inspectors walked down the following gaseous and liquid radioactive effluent monitoring and filtered ventilation systems to assess the material condition and verify proper alignment according to plant design:

(1) Liquid radwaste treatment system

(2) Gaseous radwaste treatment system

71124.07 - Radiological Environmental Monitoring Program

Groundwater Protection Initiative (GPI) Implementation (IP Section 02.02)

The inspectors evaluated the licensee's voluntary groundwater protection initiative through review of licensee documented leaks and spills since the last inspection, groundwater sampling results, and any changes to the licensee's groundwater sampling, ground water protection initiative, and spill and leak program and procedures.

The inspectors reviewed and observed selected onsite groundwater locations as delineated in the licensee's program to ensure timely identification of inadvertent releases into the groundwater.

The licensee had no entries of spills or leaks into their 10 CFR 50.75(g) records since the last inspection.

The licensee is continuing to monitor tritium through monitoring wells MW

-31, MW-34, MW-36, MW-39, M W-47, MW-58, and MW

-59. In 2017, the licensee identified a peak concentration in monitoring well MW

-31 of 1,688 picoCuries per liter (pCi/l) in January which decreased by the end of the year to 278 pCi/l. In 2018, monitoring well MW

-58 peaked at 911 pCi/l in January and decreased to 516 pCi/l by October.

The licensee reported their sampling results in each respective annual radiological environmental operating report.

The licensee is continuing to monitor the tritium levels and the continued decrease through natural attenuation.

Site Inspection (IP Section 02.01)

(1 Sample) The inspectors evaluated the radiological environmental monitoring program implementation:

Walkdowns, Calibrations, and Maintenance Record Review

(1) Air sampling stations: A1, A7, A8, A9, A10, and A11

(2) Thermoluminescent dosimeter (TLD) locations: 03, 05, 06, 21, 22a, 44, 45, 46, 47, and 61

(3) Air sampler pump calibrations: LAS

-4179, LAS-4182, and LAS

-4201

(4) Meteorological tower instrument calibrations Environmental Sample Collections and Preparation Observation

(1) Vegetation samples from three sample locations: V9, V11, and V16

(2) Surface water grab samples from S01 and S02 locations Licensee Actions in Response to Missed Sample, Inoperable Sampler, Lost TLD or Anomalous Measurement

(1) Licensee instituted compensatory sampling for selected surface water sampling locations (S01 and S02) due to flooding conditions

(2) Licensee replaced older air sampling pumps with new F&J pumps

(3) Licensee converted air sample stations from a straight line sample port to an overhanging goose neck configuration

(4) Missed environmental samples were evaluated for nominal equipment failures, aged equipment issues, power source issues, and sample reliability.

The licensee made repairs, replaced equipment, and adjusted sampling locations to fulfill the environmental sampling program requirements.

All missed and anomalous results were reported in the annual radiological environmental operating report. Sampling Program for the Potential of Licensed Material Entering Groundwater

(1) The inspectors reviewed data from and observed the following sampled groundwater wells: U1MW-31, U1MW-937D, U1MW

-939R, U1MW-940, U1MW-941, and U1MW-GW

71124.08 - Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation

Radioactive Material Storage (IP Section 02.01)

The inspectors evaluated radioactive material storage in the follow areas:

(1) Low Level Drum Storage Area (55-gallon drums)

(2) Radwaste north yard

(3) Radwaste south yard The inspectors performed a container check (e.g., swelling, leakage and deformation) on the following containers:

(1) 9563, sludge oil solidified waste

(2) 9673, solidified waste

(3) 9677, solidified waste

(4) 9687, solidified waste

(5) 9709, SLW sludge solidified waste

(6) 9710, oily waste

(7) 16145, SGBD resin Radioactive Waste System Walkdown (IP Section 02.02)

(1 Sample) The inspectors evaluated the following radioactive waste processing systems [and processes] during plant walkdowns:

Liquid or Solid Radioactive Waste Processing Systems

(1) Self-engaging dewatering system Radioactive Waste Resin and/or Sludge Discharges Processes

(1) Resin handling system for spent resin and charcoal Shipment Preparation (IP Section 02.04)

(1 Sample) The inspectors evaluated [and observed] the following radioactive material shipment preparation processes:

(1)19-021, UN2912, radioactive material, LSA-I, Class 7, resin, June 11, 2019 Shipping Records (IP Section 02.05)

(1 Sample) The inspectors evaluated the following non

-excepted package shipment records:

(1)17-010, UN3321, radioactive material, LSA-II, Class 7, drummed mechanical filters, June 22, 2017

(2)17-012, UN3321, radioactive material, LSA-II, Class 7, dewatered resin, July 12, 2017

(3)17-061, UN2912, radioactive material, LSA-I, Class 7, dry active waste CYC 21, November 17, 2017

(4)18-001, UN3321, radioactive material, LSA-II, Class 7, dewatered resin and charcoal , January 12, 2018

(5)18-010, UN2911, radioactive material, Excepted Package, Class 7 , instruments, April 12, 2018

(6)18-018, UN2911, radioactive material, Excepted Package, Class 7, instruments, September 20, 2018

(7)18-036, UN2912, radioactive material, LSA-I, Class 7, dry active waste , December 26, 2018

(8)19-005, UN3321, radioactive material, LSA-II, Class 7, resin and charcoal, March 19, 2019 Waste Characterization and Classification (IP Section 02.03)

(1 Sample) The inspectors evaluated the radioactive waste characterization and classification for the following waste streams:

(1) 14Aug17-200011GEL, FBG02A BTRS Resin 2017, August 1, 2017

(2) 17Aug17-200011FBGD, FBG02D BTRS Resin, August 17, 2017

(3) 09MAR200018 DAW1, DAW CYCLE 22, March 8, 2018

(4) 18APR18-200020 PV3/6, ALPS PV3/PV6 Resin, April 18, 2018

(5) 07May18-200011(PV1), ALPS PV

-1 C harcoa l 2019, May 1, 2018

(6) 16AUG18-200010(PV3), ALPS PV

-3 Resin, August 15, 2018

(7) 18Jan19-200021(PV2), ALPS PV

-2 Charcoal 2019, January 15, 2019

==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 Sample)

(1) April 1, 2018 through March 31, 2019 MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04)

(1 Sample)

(1) April 1, 2018 through March 31, 2019 MS08: Heat Removal Systems (IP Section 02.07)

(1 Sample)

(1) April 1, 2018 through March 31, 2019 OR01: Occupational Exposure Control Effectiveness Sample (IP Section 02.15)

(1 Sample)

(1) October 1, 2018, through March 31, 2019 PR01: Radiological Effluent Technical Specifications/Offsite Dose Calculation Manual Radiological Effluent Occurrences (RETS/ODCM) Radiological Effluent Occurrences Sample. (IP Section 02.16)

(1 Sample)

(1) October 1, 2018, through March 31, 2019

71152 - Problem Identification and Resolution Annual Follow

-up of Selected Issues (IP Section 02.03)

The inspectors reviewed the licensee's implementation of its corrective action program related to the following issues:

(1) Instrument air pressure control valves on June 22, 2019 Semiannual Trend Review (IP Section 02.02)

(1 Sample) The inspectors reviewed the licensee's corrective action program for potential adverse trends in troubleshooting equipment issues when the cause of a deficiency is n o t immediately clear and for a trend in safety

-related door issues on June 3, 2019. 71153 - Followup of Events and Notices of Enforcement Discretion Event Followup (IP Section 03.01)

(1 Sample)

(1) The inspectors evaluated essential service water valve EHV0066 valve coupling failure and the licensee's response on April 12, 2019 Personnel Performance (IP Section 03.03)

(2 Sample s)

(1) The inspectors evaluated an automatic reactor trip and the licensee's performance on May 17, 2019

(2) The inspectors evaluated a manual turbine trip and the licensee's performance on May 18, 2019

INSPECTION RESULTS

Observation

Semi-Annual Trend Review 71152 The inspectors reviewed the licensee's corrective action program, performance indicators, system health reports, and other documentation to identify trends that might indicate the existence of a more significant safety issue for troubleshooting equipment issues when the cause of a deficiency is not immediately clear and for a trend in safety

-related door issues.

The following troubleshooting examples were reviewed by the inspectors for 2019 where the licensee was unable to positively identify the cause or correct the apparent condition:

Condition Report 201900105: The P

-9 bistable light was found unexpectedly not lit during a routine control room walkdown. The licensee decided to make an unplanned entry into the reactor trip instrumentation technical specification based on the indication. The licensee determined there were no activities in progress that affected the indication, verified that that the P

-9 bistable was in the correct state, and a lamp test confirmed the light bulb was functioning. The P-9 bistable light then spontaneously relit and the licensee exited Technical Specification 3.3.1. The licensee concluded that that the observed condition appeared to be an indication problem only but was unable to find a clear cause.

The licensee later inspected and re-lamped indicator lights for this issue.

Condition Report 201901077: Control rod H

-8 dropped while operating control rod bank D. Extensive troubleshooting by the licensee could not determine a conclusive reason for the control rod drop. After performing an undetermined cause risk assessment per Procedure MDP-ZZ-TR001, "Planning and Execution of Formal Troubleshooting Activities," the licensee recovered the rod. The licensee discussed the condition with the vendor, reviewed industry operating experience, and later performed inspections of the control rod drive mechanism during the refueling outage. After eliminating other possible causes, the licensee concluded that the probable cause was crud in the latching mechanism.

Condition Report 201903494: When the trai n B motor-driven auxiliary feedwater pump suction check valve failed its breakaway torque checks, the licensee decided to make an unplanned entry into the auxiliary feedwater system technical specification. The licensee conducted an inspection of the valve's internals which did not identify an obvious cause for the increased torque required to operate the check valve. The licensee later concluded the valve packing was the cause of the increased resistance. The licensee returned the check valve to service following an adjustment of the valve packing and a successful performance of the torque check. Although a clear cause was not identified, the licensee took steps to eliminate other possible causes and took corrective action to improve operating torque.

The inspectors noted that the for these three examples, the licensee conservatively declared the equipment inoperable and initiated timely actions to identify the cause of the condition. When the condition self

-cleared or the cause could not be positively identified, the licensee ensured that they ruled out the known possible cause s and took appropriate corrective actions to try to address the problem. The inspectors verified that all issues were addressed within the scope of the corrective action program and that the completed and planned corrective actions were appropriate to correct the identified causes. The inspectors did not identify any trends or concerns that might be indicative of a more significant safety issue for troubleshooting equipment issues when the cause of a deficiency is not immediately clear.

The inspectors also reviewed an apparent trend in problems with doors that were important to safety. After the NRC identified Green n on-cited violation 05000483/2018002-02 (ADAMS ML18221A398), an auxiliary building door that was blocked open during Mode ascension (NRC Event 54061), and damaged door seals identified by the NRC which were documented in Condition Report 201903536, the licensee wrote Condition Report 201904398 to evaluate 34 condition reports generated in 2019 for an adverse trend in door issues. The licensee recognized gaps in their staff's understanding of functions performed by doors, identifying degraded conditions (including during use), and timely resolution of the issues identified. The inspectors noted that condition reports were being appropriately generated for individual deficiencies but that programmatic issues remain to be addressed. The inspectors noted that many of the condition reports are the result of a concerted effort to identify door issues at a low threshold. The inspectors concluded that the licensee appropriately identified this trend in safety-related door issues and was acting to address the causes.

Overall, the inspectors concluded that the licensee demonstrated a low threshold for issue identification and documentation in the corrective action program. The licensee applied a risk-based approach to ensure corrective actions are completed commensurate with a n issue's safety significance. The inspectors did not identify any additional trends or concerns that might be indicative of a more significant issue with safety

-related doors.

EXIT MEETINGS AND DEBRIEFS

The inspectors verified no proprietary information was retained or documented in this report.

On July 2, 2019, the inspector s presented the integrated inspection results to Mr. T. Herrmann, Site Vice President, and other members of the licensee staff.

On April 12, 2019

, the inspector s presented the occupational radiation safety inspection results to Mr. T. Herrmann, Site Vice President and other members of the licensee staff.

On April 12, 2019

, the inspector s presented the inservice inspection results to Mr. T. Herrmann, Site Vice President and other members of the licensee staff.

On June 14, 2019

, the inspector s presented the public radiation safety inspection results to Mr. B. Cox, Assistant Site Vice President and other members of the licensee staff.

DOCUMENTS REVIEWED

Inspection Procedure Type Designation

Description or Title

Revision or Date 71111.01 Corrective Action Documents Condition Reports

201104350, 201900304, 201903907, 201903907

71111.01 Miscellaneous

ULDBD-GF-001 Miscellaneous Building HVAC

71111.01 Procedures

EDP-ZZ-01129 Callaway Plant Risk Assessment

71111.01 Procedures

ODP-ZZ-0016E Operations Technician Watchstation Practices and Rounds 45 71111.01 Procedures

PDP-ZZ-00027 Summer Readiness Program

71111.04 Corrective Action Documents Condition Reports

201702402, 201806793, 201807138

71111.04 Procedures

OTN-EJ-00001 Residual Heat Removal System

71111.05Q Miscellaneous

MP 16-0024 SGK05 Supplemental Fan System

71111.05Q Miscellaneous

Various Fire Pre-plan Manual

71111.05Q Procedures

APA-ZZ-00703 Fire Protection Operability Criteria and Surveillance Requirements

71111.05Q Procedures

APA-ZZ-00750 Hazard Barrier Program

71111.06 Miscellaneous

PM0900506 Walkdown of the RWST FDN and Valve House

71111.06 Miscellaneous

PM1009292 Clean Debris from UHS Cooling Tower Fan Deck Drains 71111.06 Procedures

ESP-ZZ-01013 Maintenance Rule Structures Inspection

71111.07A Corrective Action Documents Condition Reports

201902062, 201902231, 201902396, 201902456, 201902921 71111.07A Work Orders

16506165, 17513066

71111.08P Corrective Action Documents Condition Report

s 201800861 , 201801218 , 201804786 , 201804794 , 201804816 , 201901976 71111.08P Corrective Action Documents Resulting from Condition Report s 201902288

Inspection Procedure Type Designation

Description or Title

Revision or Date Inspection

71111.08P Engineering Evaluations

Condition Report

s 201800861-002 , 201801218-001 , 201801218-002 71111.08P Miscellaneous

Callaway Nuclear Plant Containment Exterior Concrete and Tendon Inspection Program

71111.08P Miscellaneous

Callaway Nuclear Plant Containment Pressure Boundary ISI Program, ASME Section XI, Subsection IWE 4 71111.08P Miscellaneous

Fourth Interval Inservice Inspection Program Plan, Fourth Interval Inservice Inspection Program Plan

71111.08P Miscellaneous

Fourth Interval Inservice Inspection Program Plan

71111.08P Miscellaneous

Fourth Interval Inservice Inspection Program Plan Appendix A, Code Cases and Requests for Relief/Alternative Applied to the Fourth Interval

71111.08P Miscellaneous

Fourth Interval Inservice Inspection Program Plan Appendix A, Code Cases and Requests for Relief/Alternative Applied to the Fourth Interval

- Draft 71111.08P Miscellaneous

NDE Personnel Qualifications for D. Davis and W. Thomas 71111.08P Miscellaneous

Welding Personnel Qualifications for

A. Carroll,

M. Collier,

R. Holliday,

A. Langkop,

D. Leeper,

J. Parker,

N. Rosenquist,

B. Thomas,

A. Weisacosky, and C. Wood 71111.08P Miscellaneous

Relief Request I4R

-02 Relief from the Requirements of the ASME Code,Section XI, Table IWF

-2500-1 for 100 Percent Visual Examination of Class 1 Supports

71111.08P Miscellaneous

Relief Request I4R

-04 Request for Alternative Applicable to the Fourth 10

-Year Inspection Program Interval

71111.08P Miscellaneous

Specification

C-1003(Q) Inservice Inspection of the Containment Post

-Tensioning System and Exterior Concrete Shell

71111.08P NDE Reports

Job #13503632, Task 500 RPV Head Bare Metal Examination Summary, ASME Code Class 1

04/13/19 71111.08P NDE Reports

Report 5010-19-0001 Pipe to flange weld (FW

-01), Job # 17002729, Task 180, ASME Class 3

Inspection Procedure Type Designation

Description or Title

Revision or Date 71111.08P NDE Reports

Report 5010

-19-0008 Pipe to crossover tee weld (FW

-17), Job # 17002729, Task 500, ASME Class 3

71111.08P NDE Reports

Report 5010

-19-0009 Pipe to elbow weld (FW

-21), Job # 17002729, Task 500, ASME Class 3

71111.08P NDE Reports

Report 5010

-19-0012 Pipe to crossover tee weld (FW

-10), Job # 17002729, Task 500, ASME Class 3

71111.08P NDE Reports

Report 5040

-19-002 Fuel Transfer System Tube and Flange, Job # 17512708, Task 510, ASME Class IWE

71111.08P NDE Reports

Report: 19

-000245 Component: 2

-CH-STUD-02-R2, Component Description: RPV Stud #2 2nd Replacement, ASME Code Class 1

04/29/19 71111.08P Procedures

APA-ZZ-00661 Administration of Welding

71111.08P Procedures

APA-ZZ-00662 ASME Section XI Repair/Replacement Program

71111.08P Procedures

EDP-ZZ-01003 Inservice Inspection Program

71111.08P Procedures

EDP-ZZ-01004 Boric Acid Corrosion Control Program

71111.08P Procedures

ESP-ZZ-01012 Containment Post

-Tensioning System Inspection

71111.08P Procedures

ESP-ZZ-01016 ASME Section XI IWE Containment Pressure Boundary Inspection

71111.08P Procedures

LMT-08-PDI-UT-5 Straight Beam Ultrasonic Examination of Bolts and Studs 0 71111.08P Procedures

MDP-ZZ-LM001 Fluid Leak Management Program

71111.08P Procedures

MTW-ZZ-WP002 Welder Performance Qualification

71111.08P Procedures

MTW-ZZ-WP003 Control of Welding Filler Materials

71111.08P Procedures

MTW-ZZ-WP006 Qualification of Welding Procedures

71111.08P Procedures

QCP-ZZ-05040 Visual Examination to ASME VT

-1 23 71111.08P Procedures

QCP-ZZ-05041 Visual Examination to ASME VT

-2 30 71111.08P Procedures

QCP-ZZ-05042 Visual Examination to ASME VT

-3 21 71111.08P Procedures

QCP-ZZ-05048 Boric Acid Walkdown for RCS Pressure Boundary

71111.08P Procedures

QCP-ZZ-05049 RPV Head Bare Metal Examination

71111.08P Self-Assessments

Self-Assessment

201309684-08 Material Degradation Management Plan

09/4/2014 71111.08P Self-Assessments

Self-Assessment

201309684-31 ISI Program, dated 6/20/14

Inspection Procedure Type Designation

Description or Title

Revision or Date 71111.08P Work Orders

17002729/180 , 17002729/00 , 17002729/40 , 17992729/580

71111.12 Corrective Action Documents Condition Reports

201902794, 201901943, 201903344, 201903353, 201903360, 201903366, 201903372

71111.12 Procedures

OTG-ZZ-00002 Reactor Startup

- IPTE 61 71111.12 Procedures

OTG-ZZ-00003 Plant Startup Hot Zero Power to 30% Power

71111.12 Procedures

OTN-BB-00001 Reactor Coolant System

- IPTE 50 71111.13 Procedures

ODMI 19-0002 Tuning Parameter Adjustments on Digital Controls Post Mod Testing

OOA-ZZ-SSM01 Shutdown Safety Monitoring (SSM)

71111.15 Corrective Action Documents Condition Reports

201806521, 201902462, 201904050

71111.15 Procedures

EDP-ZZ-01114 Motor Operated Valve Program Guide

71111.15 Procedures

MTE-ZZ-QA006 Motor Operated Valve Analyst Guide

71111.15 Work Orders

19002798 71111.19 Corrective Action Documents Condition Reports

201805239, 201902591, 201902876, 201903026, 201903553 71111.19 Procedures

OTN-MD-00001 Switchyard Breakers and Disconnects

71111.19 Work Orders

18000062, 18000065, 19001674

71111.20 Corrective Action Documents Condition Reports

201903004 71111.20 Procedures

ITM-BB-L0053 BBLT0053A/B/BB Fill Vent and Calibration

71111.20 Procedures

OSP-BB-00007 RCS Heatup and Cooldown Limitations

71111.20 Procedures

OTA-RK-00018 Annunciator Response Procedure MCB Panel RK018

71111.22 Corrective Action Documents Condition Reports

201902874, 201902927, 201903657, 201903953, 201904075, 201904191

71111.22 Procedures

OSP-AL-P0002 Turbine Driven Aux Feedwater Pump Inservice Test

- Group B 80 71111.22 Procedures

OSP-BB-00009 RCS Inventory Balance

Inspection Procedure Type Designation

Description or Title

Revision or Date 71111.22 Procedures

OSP-BB-V002A PORV Inservice Test

71111.22 Work Orders

17001333, 17001334, 17003817, 17512419, 17512680, 17513093, 17514041, 17514487, 19507557, 19507663, 19507685, 19507835

71124.01 Corrective Action Documents Condition Reports 201900315, 201900883, 201900908, 201900930, 201901021, 201901659, 201901908, 2019

01995 71124.01 Miscellaneous

Air Sample Log

Various Air Sample Logs

01/16/2019

- 04/10/2019

71124.01 Miscellaneous

PM1002835 Non-Special Nuclear Material RAM Stored in the Spent Fuel Pool

71124.01 Miscellaneous

Source Leak Checks Various Source Leak Checks

01/18/2017

- 01/25/2019

71124.01 Procedures

APA-ZZ-01000 Callaway Energy Center Radiation Protection Program 046 71124.01 Procedures

APA-ZZ-01000 , Appendix A

Control of Radioactive Material 22 71124.01 Procedures

APA-ZZ-01004 Radiological Work Standards

71124.01 Procedures

HDP-ZZ-01200 Radiation Work Permits

71124.01 Procedures

HDP-ZZ-01500 Radiological Postings

71124.01 Procedures

HDP-ZZ-03000 Radiological Survey Program 47 71124.01 Procedures

HDP-ZZ-06000 Contamination Control and Alpha Monitoring Program

71124.01 Procedures

HSP-ZZ-00001 Radioactive Sealed Source Leak Check Surveillance

71124.01 Procedures

HTP-ZZ-01203 Radiological Area Access Control

71124.01 Procedures

HTP-ZZ-02005 Handling of Radioactive Material

71124.01 Procedures

HTP-ZZ-06001 High Radiation / Locked High Radiation / Very High Radiation Area Access

71124.01 Procedures

HTP-ZZ-06028 Radiological Controls for Pools that Contain or Store Spent Fuel

71124.01 Procedures

HTP-ZZ-06042 Industrial Radiography Using a Radioactive Source

71124.01 Radiation Surveys CA-M-20190401-10 RB2000I Mode 3 Survey

04/10/2019

71124.01 Radiation

CA-M-20190402-24 R23 RB Lower Cavity Blind Flange Removal

04/02/2019

Inspection Procedure Type Designation

Description or Title

Revision or Date Surveys 71124.01 Radiation Surveys CA-M-20190402-31 RB2023I Regen HX Post Shielding Survey

04/02/2019

71124.01 Radiation Surveys CA-M-20190404-31 RB2023I Scaffold Build to BG1E0126

04/04/2019

71124.01 Radiation Surveys CA-M-20190406-09 RBHead - Reactor Head Lift

04/06/2019

71124.01 Radiation Surveys CA-M-20190408-05 RB-2000-I G/A Five Days After CRUD Burst

04/08/2019

71124.01 Radiation Surveys CA-M-20190408-25 Reactor Vessel Head (On Stand)

04/06/2019

71124.01 Radiation Surveys CA-M-20190410-26 Gross Cavity Decon

04/10/2019

71124.01 Radiation Surveys CA-M-20190410-27 Rx Shield Plate Install Post Survey

04/10/2019

71124.01 Radiation Work Permits (RWPs)

R23ENGHRA RF23 Engineering Activities Inside High Radiation

Areas in all RCA Areas Including the Reactor Building.

71124.01 Radiation Work Permits (RWPs)

R23FUEL RF23 Offload Reactor, Perform FOSAR, Perform Reactor Reload, Core Mapping, Insert Shuffle, Pool Mapping, B5B Moves, and Miscellaneous Support Activities.

71124.01 Radiation Work Permits (RWPs)

R23HDDESSTUD

RF23 Install Stud Tensioner Hoists, Detension Reactor Vessel Studs, Remove Reactor Vessel Studs, Clean Stud Holes, Lubricate Stud Holes, Install Stud Hole Plugs, and Install Guides Studs/Pins. 0 71124.01 Radiation Work Permits (RWPs)

R23HDSTUD18

RF23 Activities to Remove Reactor Vessel Stuck Stud 18, Including Thread Repairs, and Inspect Its Stud Hole. Includes Cutting, Boring, QC/Engineering Inspections, and Associated Cavity Work (Except Cavity Decontamination).

71124.01 Radiation Work Permits (RWPs)

R23RCPCHANGE

RF23 Motor Change on A Reactor Coolant Pump and Associated Tasks.

71124.01 Radiation Work Permits (RWPs)

R23STD18DECON

RF23 Upper Cavity Gross Rinse, Vacuum of Seal Ring, Upper Cavity Decontamination, and RV Flange

Inspection Procedure Type Designation

Description or Title

Revision or Date Cleaning to Support Removal of

Stuck RV Stud #18. Includes all RP Coverage and Surveys. 71124.01 Self-Assessments

AP18006 Nuclear Oversight Audit of Radiological and Non Radiological Environmental Monitoring Programs

06/13/2018

71124.02 Corrective Action Documents Condition Reports 2018-02443, 2018

-02930, 2018

-02953, 2018

-04531, 2018-04758, 2018

-04903, 2018

-05952, 2018

-06019, 2018-06973, 2019

-00904, 2019-00908, 2019

-00998, 2019-01277, 2019

-01355 71124.02 Miscellaneous

RF23 Plant ALARA Review Committee (PARC) Meeting 01/24/2019

71124.02 Miscellaneous

RT Examination of 1" SCH 80 Pipe Weld in Room 113 of Aux Building Shot Plan

04/09/2019

71124.02 Miscellaneous

Powering into the Future

- Callaway Refuel 23 Daily News Flyer

04/08/2019

- 04/11/2019

71124.02 Miscellaneous

Refuel 23 Outage Update & Shiftly SOM Turnover

04/08/2019

- 04/11/2019

71124.02 Miscellaneous

Callaway Radiation Protection Current Log

04/11/2019

71124.02 Miscellaneous

CA2943 Radiography Checklist

- Radioactive Source

04/09/2019

71124.02 Miscellaneous

Reactor Vessel Stuck Stud Removal Project

01/31/2019

71124.02 Procedures

APA-ZZ-01000 Callaway Energy Center Radiation Protection Program 45 71124.02 Procedures

APA-ZZ-01001 Callaway Plant ALARA Plant

71124.02 Procedures

APA-ZZ-01004 Radiological Work Standards

71124.02 Procedures

HDP-ZZ-01100 ALARA Planning and Review

71124.02 Procedures

HDP-ZZ-01200 Radiation Work Permits

71124.02 Procedures

HDP-ZZ-01500 Radiological Postings

71124.02 Procedures

HDP-ZZ-06000 Contamination Control and Alpha Monitoring Program

71124.02 Procedures

HTP-ZZ-01101 Administrative Controls for Radiation Shielding

71124.02 Procedures

HTP-ZZ-01104 Hot Spot Trending Program

71124.02 Procedures

HTP-ZZ-01203 Radiological Area Access Control

71124.02 Procedures

HTP-ZZ-06001 High Radiation/Locked High Radiation/Very High

Inspection Procedure Type Designation

Description or Title

Revision or Date Radiation Area Access

71124.02 Procedures

HTP-ZZ-06042 Industrial Radiography Using A Radioactive Source

71124.02 Radiation Surveys CA-M-20190402-14 SJ Sample & Boron

ometer / PASS Rooms

04/02/2019

71124.02 Radiation Surveys CA-M-20190402-17 Access Pit

04/02/2019

71124.02 Radiation Surveys CA-M-20190405-23 RB-2090 RF Stud Rack Survey Update 18501154.500

04/05/2019

71124.02 Radiation Surveys CA-M-20190405-31 RB2047 General Area

- Routine Survey

04/05/2019

71124.02 Radiation Surveys CA-M-20190405-33 RB2068 General Area Routine 04/05/2019

71124.02 Radiation Surveys CA-M-20190408-19 Safety Injection Pump Room A

04/08/2019

71124.02 Radiation Surveys CA-M-20190408-32 RB2026' General Area Routine

04/08/2019

71124.02 Radiation Surveys CA-M-20190408-5 RB-2000-I G/A Five Days After CRUD Burst

04/08/2019

71124.02 Radiation Surveys CA-M-20190410-26 Gross Cavity Decontamination

04/10/2019

71124.02 Radiation Surveys CA-M-20190410-27 Rx Shield Plate Install Post Survey

04/10/2019

71124.02 Radiation Work Permits (RWPs)

16003707510

EMV0161 Radiography

71124.02 Radiation Work Permits (RWPs)

18500671139

RF23 Scaffold to BGV0449

71124.02 Radiation Work Permits (RWPs)

R23HDDESTUD

Detension Reactor Vessel Studs

71124.02 Radiation Work Permits (RWPs)

R23HDRESTUD

Install Reactor Vessel Studs

71124.02 Radiation Work Permits (RWPs)

R23HDSTUD18

Remove Stuck Stud 18

71124.02 Radiation Work Permits (RWPs)

R23STD18DECON

RF23 Cavity Decontamination

Inspection Procedure Type Designation

Description or Title

Revision or Date 71124.02 Self-Assessments

201820044-064 NRC Pre Inspection Self

-Assessment: Rad Safety ALARA Planning and Occupational Dose Assessment

06/14/2018

71124.02 Self-Assessments

AP19001 Nuclear Oversight Audit of Radiation Protection

03/27/2019

71124.05 Calculations

HPCI-05-03 Evaluate Plant Radioactivity Mixture (Set Points)

2/22/2005 71124.05 Calculations

HPCI-1403 Use of PM-12 for Passive Monitoring

2/11/2018

71124.05 Calibration Records 16503276-500 SD-RE-024 Reactor Coolant Sample Room

3/16/2018 71124.05 Calibration Records 16513022-500 EG-RE-009 CCW HX A Inlet

5/7/2018 71124.05 Calibration Records 17504995-500 SD-RE-038 Spent Fuel Pool Area Rad High

10/22/2018

71124.05 Calibration Records 17506055-500 SD-RE-012 Aux Bldg. Corridor Basement Hi

6/11/2019 71124.05 Calibration Records 17506056-500 SD-RE-015 Aux Bldg. Corridor Basement Hi

6/11/2019 71124.05 Calibration Records 17508210-500 GT-RE-059 CTMT High Range (Electronics Calibration)

1/17/2019 71124.05 Calibration Records 17510146-500 GT-RE-033 CTMT Purge

2/8/2019 71124.05 Calibration Records 17512545-500 GT-RE-059 CTMT High Range (Isotopic Calibration)

4/10/2019 71124.05 Calibration Records CAM-4019-HP Calibration Certificate (PING

-1A) 6/28/2018 71124.05 Calibration Records CAM-4020-HP Calibration Certificate (PING

-1A) 2/27/2019 71124.05 Calibration Records CAM-4045-HP Calibration Certificate (Eberline AMS

-4) 12/10/2018

71124.05 Calibration Records CRM-4023-HP Calibration Certificate (Ludlum Model 2000)

3/5/2019 71124.05 Calibration Records CRM-4026-HP Calibration Certificate (Ludlum Model 2000)

8/21/2018 71124.05 Calibration Records CRM-4089-HP Calibration Certificate (Ludlum Model 177)

1/26/2019

Inspection Procedure Type Designation

Description or Title

Revision or Date 71124.05 Calibration Records CRM-4134-HP Calibration Certificate (Ludlum Model 177)

2/6/2019 71124.05 Calibration Records GPC-4003-HP Instrument Calibration / Verification (Tennelec)

11/4/2007 71124.05 Calibration Records GSS-4220-HP Instrument Calibration / Verification (Ortec

- Detector 2) 3/21/2019 71124.05 Calibration Records LAS-4198-HP Calibration Certificate (Radeco Model HD

-29A) 1/28/2019 71124.05 Calibration Records LSC-4004-HP Instrument Calibration / Verification (Perkin

-Elmer) 4/25/2018 71124.05 Calibration Records PCM-4054-HP Calibration Certificate (PCM

-12) 8/28/2018 71124.05 Calibration Records PM-4046-HP Calibration Certificate (PM

-12) 8/28/2018 71124.05 Calibration Records TM-4010-HP Calibration Certificate (SAM

-12) 3/31/2019 71124.05 Corrective Action Documents Condition Report

s 201703216, 201707720, 201800120, 201801122, 201805869, 201805975, 201900857, 201901599, 201902538, 201903111 71124.05 Miscellaneous

Area Radiation Monitor Calibration Data

6/11/2019 71124.05 Miscellaneous

Calibration of Xradin Ion Chamber A3, A4, & A6

3/23/2018 71124.05 Procedures

APA-ZZ-00014 Conduct of Operations

- Radiation Protection

71124.05 Procedures

HDP-ZZ-04000 Radiation Protection Instrumentation Program

71124.05 Procedures

HDP-ZZ-04700 Count Room and Whole Body Counter Quality Control Program 22 71124.05 Procedures

HSP-ZZ-00014 Rad Monitor Non

-Functionality

71124.05 Procedures

HTP-SD-06033 Control of Area Radiation Monitor Alarm Setpoints

71124.05 Procedures

HTP-ZZ-04101-DTI-M177-Cal Ludlum Model 177 Frisker Calibration

71124.05 Procedures

HTP-ZZ-04102-DTI-RO2-CAL Eberline RO

-2 Survey Meter Calibration

71124.05 Procedures

HTP-ZZ-04150 Operations of the GA Process Monitor System

71124.05 Procedures

HTP-ZZ-04167-DTI-Thermo-Radeye Thermo RadEye Neutron Survey Meter Calibration

Inspection Procedure Type Designation

Description or Title

Revision or Date NL-Cal 71124.05 Procedures

HTP-ZZ-04176-DTI-SAM12-Cal Thermo Fisher Model SAM-12 Small Articles Monitor Calibration

71124.05 Procedures

HTP-ZZ-04178-DTI-Telepole-Cal Rotem Telepole Survey Meter Calibration

71124.05 Procedures

HTP-ZZ-06020 Count Room Analytic and Quality Control Calculations and Methods

71124.05 Procedures

HTP-ZZ-07010 Alternate Method for Obtaining CHARMS Reading

71124.05 Procedures

ISL-GT-00R59 CTMT High Range Area Rad Monitor Loop Calibration

71124.05 Procedures

ITL-SD-00R00 Eberline Area Radiation Monitors

71124.05 Radiation Surveys CA-M-20190327-19 NS-1 Neutron Source

- Quarterly Routine

3/27/2019 71124.05 Self-Assessments

201807096-010/201900029

-036 Instrument Program and Pre

-NRC Inspection

3/28/2019 71124.05 Self-Assessments

AP19001 Nuclear Oversight Audit of Radiation Protection

3/27/2019 71124.06 Calculations

RP09-2017-L0028;1 Batch Liquid Radioactive Release Permit

07/28/2017

71124.06 Calculations

RP09-2018-L0007;1 Batch Liquid Radioactive Release Permit

2/01/2018

71124.06 Calculations

RP09-2019-L0037;0 Batch Liquid Radioactive Release Permit

06/11/2019

71124.06 Calculations

RP11A-2019-G0013;1 Batch Airborne Radioactive Release Permit

2/17/2019

71124.06 Calculations

RP13-2017-G0006;52 Continuous Airborne Radioactive Release Permit

2/07/2017

71124.06 Calculations

RP13-2018-G0002;56 Continuous Airborne Radioactive Release Permit

2/20/2018

71124.06 Calibration Records Job 12504965.500

RW Bldg Disch Line Process Rad Mon Loop Cal

08/21/2018

71124.06 Calibration Records Job 17502388.500

Ctmt Bld Air Exg

Plenum (Unit Vent) Rad Xmt

08/23/2018

Inspection Procedure Type Designation

Description or Title

Revision or Date 71124.06 Corrective Action Documents Condition Report

201703216, 201703232 , 201703516 , 201800052 , 201800125 , 201801122 , 201801301 , 201802268 , 201802267 , 201802407 , 201802547 , 201803062 , 201803391 , 201805008 , 201805070 , 201805144 , 201805978 , 201805987 , 201805989 , 201806167 , 201900239 , 201900348 , 201900353 , 201900438

71124.06 Miscellaneous

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report

71124.06 Miscellaneous

Callaway Energy Center

2018 Draft Annual Radioactive Effluent Release Report

71124.06 Miscellaneous

Job 15510527

FGG02A In-Place Bypass Leakage Test

03/10/2017

71124.06 Miscellaneous

Job 16509259

FGK02B In-Place Bypass Leakage Test

05/31/2018

71124.06 Miscellaneous

Job 17503239 FGE01 In-Place Bypass Leakage Test

07/16/2018

71124.06 Procedures

HSP-ZZ-00002 Radioactive Liquid Effluent Concentration

71124.06 Procedures

HSP-ZZ-00003 Dose Assessments from Liquid Effluents

71124.06 Procedures

HSP-ZZ-00004 Projected Dose from Liquid Waste

71124.06 Procedures

HTP-ZZ-02006 Liquid Radwaste Release Permit (Batch)

71124.06 Procedures

HTP-ZZ-02006 Liquid Radwaste Release Permit (Batch)

71124.06 Procedures

HTP-ZZ-02007 Gaseous Radwaste Release Permit (Gas Decay Tank) 48 71124.06 Procedures

HTP-ZZ-02008 Gaseous Radwaste Release Permit (Auxiliary/Fuel Building Ventilation)

71124.06 Procedures

HTP-ZZ-02009 Gaseous Radwaste Release Permit (Radwaste Building Ventilation)

71124.06 Procedures

HTP-ZZ-03006 Use of Airborne Sampling Cart

71124.06 Procedures

ISF-GH-0R10B RW Building Exhaust Discharge Radiation Detector

71124.06 Self-Assessments

Nuclear Oversight Audit of Radiological and Non

-Radiological Environmental Monitoring Programs, AP

18006 06/13/20 18 71124.06 Self-Assessments

Nuclear Oversight Audit of Radiation Protection AP19001 03/27/2019

71124.07 Calculations

HPCI 1092 Evaluation of the 2018 Annual Land Use Census

71124.07 Calculations

HPCI 18-01 Evaluation of the 2017 Annual Land Use Census 0 71124.07 Calculations

HPCI-1503 Calculation of Long

- Term Meteorological Dispersion

Inspection Procedure Type Designation

Description or Title

Revision or Date Parameters

71124.07 Calculations

HPCI-1506 Evaluation of Air Sampler Locations with Respect to the Recalculated Dispersion Parameters

71124.07 Calibration Records Job 18504263

RD01-Primary Meteorological Tower Loop A

10/24/2018

71124.07 Calibration Records Job 18504272

RD01-Primary Meteorological Tower Loop B

10/25/2018

71124.07 Calibration Records Job 18511186

RD01-Primary Meteorological Tower Loop A

03/29/2019

71124.07 Calibration Records Job 18511189

RD01-Primary Meteorological Tower Loop B

03/25/2019

71124.07 Calibration Records LAS-4179 Low volume Air Sampler Serial Number 10216

11/09/18 71124.07 Calibration Records LAS-4182 Low Volume Air Sampler Serial Number 8977

07/20/2018

71124.07 Calibration Records LAS-4201 Low Volume Air Sampler Seri

al Number 8975

01/31/2019

71124.07 Corrective Action Documents Condition Report

s 201700071, 201700835, 201701864, 201702166, 201702981, 201703331, 201703581, 201705266, 201705398, 201705399, 201705403, 201705417, 201706786, 201706793, 201706794, 201801634, 201801736, 201801950, 201802361, 201803357, 201900612, 201900937, 201901217, 201902100 71124.07 Corrective Action Documents Resulting from Inspection

Condition Report

s 201904252 71124.07 Miscellaneous

Environmental Dosimetry Company

- Annual Quality Assurance Status Report: January

- December 2017

03/07/2018

71124.07 Miscellaneous

Environmental Dosimetry Company

- Annual Quality Assurance Status Report: January

- December 2018

03/12/2019

71124.07 Miscellaneous

AP18006 Nuclear Oversight Audit of Radiological and Non Radiological Environmental Monitoring Programs

06/13/2018

Inspection Procedure Type Designation

Description or Title

Revision or Date 71124.07 Miscellaneous

AP19001 Nuclear Oversight Audit of Radiation Protection

03/27/2019

71124.07 Miscellaneous

APA-ZZ-01003 Off-Site Dose Calculation Manual

71124.07 Miscellaneous

AREOR Annual Radiological Environmental Operating Report: January 1- December 31, 2017

71124.07 Miscellaneous

AREOR Annual Radiological Environmental Operating Report: January 1- December 31, 2018

71124.07 Miscellaneous

NAQA-17-0038 Audit Report 17

-007 for the Audit of Environmental Dosimetry Company

09/01/2017

71124.07 Procedures

HDP-ZZ-07000 Radiological Environmental Monitoring Program and Groundwater Protection Initiative

71124.07 Procedures

HTP-ZZ-04123-DTI-F&J-DF1T-CAL F&J DF-1T Low Volume Air Sampler Calibration

71124.07 Procedures

HTP-ZZ-07001-DTI-Crop-Sampling Collection and Shipping of Environmental Crop Samples 7 71124.07 Procedures

HTP-ZZ-07001-DTI-Water-Sampling Collection and Shipping of Environmental Water Samples 11 71124.07 Procedures

HTP-ZZ-07101-DTI-REMP-SMPL-SCHED REMP Sample Locations and Analysis Schedule

71124.07 Procedures

HTP-ZZ-07103-RP-DTI-REMP-DATAEVAL Evaluation and Reporting of REMP Data

71124.07 Procedures

ISL-RD-RD01A Meteorological Monitoring Instruments

- Elevator A Loop Calibration

71124.07 Procedures

ISL-RD-RD01B Meteorological Monitoring Instruments

- Elevator B Loop Calibration

71124.07 Procedures

RP-DTI-ENVIRON-TLD LOCATIONS

Environmental TLD Locations

71124.07 Procedures

RP-DTI-ENVIRONMENTAL

-SPILLRESP Response to Spills or Leaks of Radioactive Material into Groundwater

71124.08 Corrective Action Documents Condition Report

01701008, 201702081 , 201704005 , 201706627 , 201804430 , 201804447 , 201806969 , 201900861 , 201900930 , 201901038 , 201902796 , 201904190

Inspection Procedure Type Designation

Description or Title

Revision or Date 71124.08 Miscellaneous

Callaway Final Safety Analysis Report (FSAR) - Chapter 11.4 06/01/2018

71124.08 Miscellaneous

2018 RAM and Radwaste Shipping Log

2018 71124.08 Miscellaneous

Callaway Energy Center 2018 Annual Radioactive Effluent Release Report

2018 71124.08 Miscellaneous

Callaway Energy Center 2017 Annual Radioactive Effluent Release Report

2017 71124.08 Miscellaneous

2017 RAM and Radwaste Shipping Log

2017 71124.08 Procedures

APA-ZZ-01011 Process Control Program

71124.08 Procedures

HTP-HC-09002 10 CFR 61 Sampling Program

71124.08 Procedures

HTP-ZZ-02005 Handling of Radioactive Material

71124.08 Procedures

HTP-ZZ-09003 Shipment of Radioactive Wastes

71124.08 Procedures

RDP-ZZ-00200 Radwaste Operational Guidelines

71124.08 Procedures

RTN-HC-01900 On-Site Storage Container Handling Procedure

71124.08 Procedures

RTS-HC-00310 Primary Resin Sluice To Bulk Waste Disposal Station

71124.08 Procedures

RTS-HC-00350 Primary Spent Resin Storage Tank Transfer To Bulk Waste Disposal Station

71124.08 Procedures

RTS-ZZ-CH040 Handling of Transport Cask Model 14

-215H 12 71124.08 Procedures

RTS-ZZ-CH050 Handling Procedure for CNS 8

-120A Transport Cask

71124.08 Radiation Surveys CA-M-20190409-24 RWY-4 & RWY-3 Radwaste Yard Plant (North & South) 04/09/2019

71124.08 Radiation Surveys CA-M-20190415-05 7228 Drywaste Compactor Area

- Quarterly Routine

04/14/2019

71124.08 Radiation Surveys CA-M-20190421-24 7225 Quarterly Routine Survey

- Low Level Drum Storage Area

04/21/2019

71124.08 Radiation Surveys CA-M-20190524-02 RSS-1 Characterization

- Resin Liner #PO661751

-16 05/24/2019

71124.08 Self-Assessments

EPRI Solid Radioactive Waste Program Assessment at Ameren Callaway Nuclear Power Plant

07/14/2017

71124.08 Self-Assessments

201900029-035 Simple Self

-Assessment: Shipping Program 05/02/2019

71124.08 Self-Assessments

AP19001 Ameren Nuclear Oversight Audit of Radiation Protection

03/27/2019

71124.08 Shipping 17-010 UN3321, RAM, LSA

-11, Class 7 (Drummed 06/22/2017

Inspection Procedure Type Designation

Description or Title

Revision or Date Records Mechanical Filters)

71124.08 Shipping Records17-012 UN3321, RAM, LSA

-II, Class 7 (Dewatered Resin)

07/12/2017

71124.08 Shipping Records17-061 UN2912, RAM, LSA

-I, Class 7 (Dry Active Waste Cycle 21) 11/17/2017

71124.08 Shipping Records18-001 UN3321, RAM, LSA

-II, Class 7 (Dewatered Resin and Charcoal) 01/12/2018 71124.08 Shipping Records18-010 UN2911, RAM, Excepted Package, Class 7 (Instruments)

04/12/2018

71124.08 Shipping Records18-018 UN2911, RAM, Excepted Package, Class 7 (Instruments)

09/20/2018

71124.08 Shipping Records18-036 UN2912, RAM, LSA-I, Class 7 (Dry Active Waste)

2/26/2018

71124.08 Shipping Records19-005 UN3321, RAM, LSA

-II, Class 7 (Resin and Charcoal)

03/19/2019

71124.08 Shipping Records19-021 UN2912, RAM, LSA

-I, Class 7 (Resin)

06/11/2019

71153 Corrective Action Documents Condition Reports

201901943, 201903787, 201903832

The following items are requested for the

Occupational

Radiation Safety Inspection

at Callaway Dates of Inspection: 04/08/2019

to 04/12/2019

Integrated Report 2019002 Inspection areas are listed in the attachments below.

Please provide the requested information on or before Monday, March 25, 2019

. Please submit this information using the same lettering system as below.

For example, all contacts and phone numbers for Inspection Procedure 71124.0

should be in a file/folder titled

"1-A," applicable organization charts in file/folder "

1-B," etc. The information should be provided in electronic format or a secure document management service. If information is placed on ims.certrec.com, please ensure the inspection exit date

entered is at least 30 days later than the onsite inspection dates, so the inspectors will have access to the information while writing the

report. In addition to the corrective action document lists provided for each inspection procedure listed below, please provide updated lists of corrective action documents at the entrance meeting. The dates for these lists should range from the end dates of the original lists to the day of the entrance meeting.

If more than one inspection procedure is to be conducted and the information requests appear to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which file the information can be found.

If you have any questions or comments, please contact

Natasha Greene at 817

-200-1154 or via

e-mail at Natasha.Greene@nrc.gov.

PAPERWORK REDUCTION ACT STATEMENT

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.

S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150

-0011.

1. Radiological Hazard Assessment and Exposure Controls (71124.01) and Performance Indicator Verification (71151)

Date of Last Inspection:

November 5, 2018

A. List of contacts and telephone numbers for the Radiation Protection Organization Staff

and Technicians, as well as the Licensing/Regulatory Affairs staff. Please include area code and prefix. If work cell numbers are appropriate, then please include them as well.

B. Applicable organization charts

including position or job titles. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, self

-assessments, LARs, and LERs written since the last inspection date , related to this inspection area

D. Procedure indexes for the radiation protection procedures

and other related disciplines.

E. Please provide procedures related to the following

areas noted below. Additional

procedures may be requested by number

after the inspector reviews the procedure indexes. 1. Radiation Protection Program

2. Radiation Protection Conduct of Operations, if not included in #1.

3. Personnel Dosimetry

4. Posting of Radiological Areas

5. High Radiation Area Controls

6. RCA Access Controls and Radiation Worker Instructions

7. Conduct of Radiological Surveys

8. Radioactive Source Inventory and Control

9. Fuel Pool Inventory Access and Control

F. Please provide a list of NRC Regulatory Guides and NUREGs that you are currently committed to relative to this program. Please

include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a summary list of corrective action documents (including corporate and sub-tiered systems) since the last inspection date.

1. Initiated by the radiation protection organization

2. Assigned to the radiation protection organization

NOTE: The se lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the significance level assigned to the condition, the status of the action (e.g., open, working, closed, etc.)

and the search criteria used. Please provide in document formats

which are "sortable" and "searchable" so that inspector

s can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. List of radiologically significant work activities scheduled to be conducted during the inspection period

. (If the inspection is scheduled during an outage, please also include a list of work activities greater than 1 rem, scheduled during the outage with the dose

estimate for the work activity.) Please include the radiological risk assigned to each activity.

I. Provide a summary of any changes to plant operation that have resulted or could result in a significant new radiological hazard. For each change, please provide the assessment conducted on the potential impact and any monitoring done to evaluate it.

J. List of active radiation work permits

and those specifically planned for the on

-site inspection week.

K. Please provide a list of air samples taken to verify engineering controls and a separate list for breathing air samples in airborne radiation areas or high contamination work areas. Please include the RWP the breathing air sampling supports.

L. Please provide the current radioactive source inventory, listing all radioactive sources

that are required to be leak tested. Indicate which sources are deemed 10 CFR Part 20, Appendix E, Category 1 or Category 2. Please indicate the radioisotope, initial and current activity (w/assay date), and storage location for each applicable source.

M. The last two leak test results for all required/applicable radioactive sources that have failed its leak test within the last two years. Provide any applicable condition reports.

N. A list of all

non-fuel items stored in the spent fuel pools, and if

available, their appropriate dose rates (Contact / @ 30cm)

O. A list of radiological controlled area entries greater than 100 millirem

, since the last inspection date. The list should include the date of entry, some form of worker identification, the radiation work permit used by the worker, dose accrued by the worker, and the electronic dosimeter dose alarm set

-point used during the entry (for Occupational Radiation Safety Performance Indicator verification in accordance with IP 71151).

P. A list describing VHRAs and TS HRAs (> 1 rem/hour) that are current and historical. Include their current status, locations, and control measures.

Q. Temporary effluent monitor locations and calibrations (AMS

-4) used to monitor normally closed doors or off

-normal release points (e.g., equipment hatch or turbine heater bay doors). Include any CRs associated with this monitoring or instrumentation.

2. Occupational ALARA Planning and Controls (71124.02)

Date of Last Inspection:

May 21, 2018

A. List of contacts

and telephone numbers for ALARA program personnel, as well as the Licensing/Regulatory Affairs staff. Please include area code and prefix. If work cell numbers are appropriate, then please include them as well.

B. Applicable organization charts

including position or job titles. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, self

-assessments, LARs, and LERs, written since the date of last inspection, focusing on ALARA

D. Procedure index for ALARA Program

procedures

and other related disciplines.

E. Please provide specific procedures related to the following areas noted below. Additional Specific Procedures may be requested by number

after the inspector reviews the procedure indexes.

1. ALARA Program

2. ALARA Planning

3. ALARA Reviews

4. ALARA Committee

5. Radiation Work Permit Preparation

F. Please provide a list of NRC Regulatory Guides and NUREGs that you are currently committed to relative to this program. Please include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a summary list of corrective action documents (including corporate and sub-tiered systems) written since the date of last inspection, related to the ALARA program, including exceeding RWP Dose Estimates.

NOTE: The se lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the significance level assigned to the condition, the status of the action (e.g., open, working, closed, etc.)

and the search criteria used. Please provide in document formats

which are "sortable" and "searchable" so that inspector

s can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. List of work activities (RWPs) greater than 1 rem, since date of last inspection , including the original dose estimate

s and actual doses accrued. (Excel format preferred)

. Please provide all revisions/changes, as well as any related RWPs that support the work activity.

I. List of active work activities (RWPs) that will be in use while we are onsite, including the dose and dose rate settings, and if available, the planned dose. Include planning documents and surveys. Include radiological risk assessments and proposed control measures.

J. Site dose totals for the past 3 years (based on dose of record). Also provide the current year-to-date (YTD) collective radiation exposure (CRE). In addition, please provide another document that separates the online and outage doses for the past 3 years.

K. Most recent assessment of your isotopic mix, including the hard

-to-detect radionuclides and alpha hazards. Include a list of new and historical exposure issues (radiological source term or high exposure areas/activities).

L. If available, provide a copy of the lessons learned from the most recently completed outage for each unit. Include a summary list of any associated corrective action documents and the current status of any corrective actions assigned.

M. Please provide the methods/reports that are in your process to meet the requirements of 10 CFR 20.1101(c) for periodic review of your RP program.

N. Current exposure trends (BRAC dose rates and/or source term information).

The following items are requested for the

Public Radiation Safety Inspection

at Callaway Dates of Inspection: 06/10/2019

to 06/14/2019

Integrated Report 2019002 Inspection areas are listed in the attachments below.

Please provide the requested information on or before Friday, May 24, 2019

. Please submit this information using th

e same lettering system as below. For example, all contacts and phone numbers for Inspection Procedure 71124.0

should be in a file/folder titled

"5-A," applicable organization charts in file/folder "

5-B," etc. The information should be provided in electronic format or a secure document management service. If information is placed on a secured document management system, please ensure the inspection exit date entered is at least 30 days later than the onsite inspection dates, so the inspectors will have access to the information while writing the report.

In addition to the corrective action document lists provided for each inspection procedure listed below, please provide updated lists of corrective action documents at the entrance meeting. The dates for

these lists should range from the end dates of the original lists to the day of the entrance meeting.

If more than one inspection procedure is to be conducted and the information requests appear to be redundant, there is no need to provide duplicate copies. Enter a note explaining in which file the information can be found.

If you have any questions or comments, please contact Natasha Greene at 817

-200-1154 or via

e-mail at Natasha.Greene@nrc.gov.

PAPERWORK REDUCTION ACT STATEMENT

This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.

S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3

150-0011.

5. Radiation Monitoring Instrumentation (71124.05)

Date of Last Inspection:

February 27, 2017

A. List of contacts and telephone numbers for the following areas

below. Please include area code and prefix. If work cell numbers are appropriate, then please include them as well. 1. Process monitor calibration

(Include Chemistry, Systems Engineering and I&C, as applicable)

2. Radiation protection instrument calibration

(Portable and Stationary)

3. Installed instrument calibrations

(Include Systems Engineering and I&C)

4. Count room and Laboratory instrument calibrations

(Include RP and Chemistry, as applicable)

5. EP contacts for Equipment Important to Emergency Response/Preparedness (EITER) 6. Licensing/Regulatory Affairs

B. Applicable organization charts, including position or job titles. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, self

-assessments, vendor or NUPIC audits for contractor support , LARs, and LERs, performed since the date of the last inspection

, related to:

1. Portable Radiation instruments: Area radiation monitors, portable continuous air monitors (AMS3/4), portable survey instruments (count rate, dose rate, occupational air sampling), electronic dosimeters, teledosimetry

2. Stationary Radiation Instruments: Portal monitors, small article monitors, personnel contamination monitors, or whole body counters

3. Installed Radiation Instruments: Area radiation monitors (RMS), process monitors (non-effluent), criticality monitors, accident monitors

4. Count Room instrumentation (Chemistry and RP, if separate RP Ops and Effluents): Gamma Spec, LSC, Gross Alpha, Gross Beta, including bench

-top counters

D. Procedure index

es for radiation protection procedures

and other related disciplines.

1. Calibration, use

, and operation of continuous air monitors, portable survey instruments, temporary area radiation monitors, electronic dosimeters, teledosimetry

2. Calibration use and operation of portal monitors, small article monitors, personnel contamination monitors, and whole body counters

3. Calibration of installed area radiation monitors, process monitors, criticality monitors, and accident monitors 4. Calibration use and operation of Count Room instrumentation (GS, LSC, GA, GB)

(include bench top counters here)

NOTE: Please ensure that RP, Chemistry, and I&C procedures are included, as appropriate.

E. Please provide specific procedures related to

the following areas

noted below. Additional

procedures may be requested by number

after the inspector reviews the

procedure index.

1. Calibration of portable ion chambers

2. Calibration of Friskers

3. Calibration of telescoping high range instruments

4. Calibration

of portable neutron instruments

5. Calibration of SAMs

6. Whole body counter calibration

7. Laboratory instrumentation quality control

8. Calibration of Containment/Drywell high range radiation monitor

F. Please provide a list of NRC Regulatory Guides and NUREGs that

you are currently committed to relative to this program. Please include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a summary list of corrective action documents (including corporate and sub-tiered systems) written since the date of the last inspection, related to the following programs: 1. Area radiation monitors, continuous air monitors, portable survey instruments, electronic dosimeters, and teledosimetr

y 2. Portal monitors, small article monitors, personnel contamination monitors, and whole body counters

3. Installed radiation monitors

, criticality monitors, accident range monitors

4. Count room radiation instruments

NOTE: The se lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the significance level assigned to the condition, the status of the action (e.g., open, working, closed, etc.)

and the search criteria used. Please provide in document formats which are "sortable" and "searchable" so that inspector

s can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. State the required calibration frequency and provide the most recent

calibration data for the whole body counter

s, at least one portable survey instrument, one area radiation monitor, one air sampler, one continuous air monitor, and one drywell/containment high

-range monitor.

I. Provide a list of any scheduled calibrations, while we are onsite, for the instrumentation noted in request above, in 5

-I. J. Provide the alarm set point values for the portal and personnel contamination monitors in operation. K. Radiation Monitoring System health report for the previous 12 months

L. Provide the following lists of instruments to include make, model, identifier (S/N or plant ID), and location:

1. Portable radiation instruments currently in use

(for EADs just make, model, and quantity).

2. Stationary radiation instruments currently in use.

3. Installed Radiation monitors

a. Area radiation monitors and

b. Process radiation monitors.

(Include their instrumentation designator, function and calibration procedure number and title.) Please indicate which, if any, detectors have been replaced within the past 2 years (since the last inspection).

c. Radiation instrumentation abandoned in place.

d. Radiation instrumentation covered

by the maintenance rule.

M. Provide a list of sources used routinely for source check of portable, stationary, and installed radiation monitoring instruments.

N. Provide the NIST traceability and calibration or verification of the primary sources for instrument calibration and the procedures used to achieve this.

6. Radioactive Gaseous and Liquid Effluent Treatment (71124.06)

Date of Last Inspection:

February 27, 2017

A. List of contacts and telephone numbers for the following areas. Please include area code and prefix. If work cell numbers are appropriate, then please include them as well.

1. Radiological effluent control

(liquid & gaseous) and reporting

(RP, Chemistry, RW, Ops, etc.)

2. Effluent Monitor calibration (liquid and gaseous) and maintenance

(RP, Chemistry, I&C, Maintenance, Systems Engineering, EP, etc.)

3. Engineered safety feature air cleaning systems

for effluent release

(Systems Engineering, I&C, Maintenance, etc.)

4. Licensing/Regulatory Affairs

B. Applicable organization charts including position or job titles

for the above individuals and also for their supportive Management. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, self

-assessments, vendor or NUPIC audits of contractor support, and LERs written since the date of the last inspection , related to:

1. Radioactive effluents

and effluent radiation monitors

2. Engineered Safety Feature Air cleaning systems

D. Procedure indexes for the following areas

and related disciplines.

1. Radioactive effluents

and effluent radiation monitors (to include the flow monitors)

2. Engineered Safety Feature Air cleaning systems

(both TS and no

n-TS systems for effluents)

E. Please provide specific procedures related to the following areas

noted below. Additional

procedures may be requested by number

after the inspector reviews the procedure indexes.

1. Sampling and analysis of radioactive effluen

ts 2. Effluent monitor setpoint determination

3. Generating radioactive effluent release permits

4. Effluent Monitor Calibrations (Include associated flow monitors)

5. Laboratory instrumentation quality control

6. In-place testing of HEPA filters and charcoal adsorbers

for TS effluent exhaust systems and other effluent air

-cleaning systems, but not breathing air systems

F. Please provide a list of NRC Regulatory Guides and NUREGs that you are currently committed to relative to this program. Please include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a summary list of corrective action documents (including corporate and sub-tiered systems) written since the date of the last inspection

, associated with:

1. Radioactive effluents

2. Effluent radiation monitors

(include associated effluent flow monitors)

3. Engineered Safety Feature Air cleaning systems

(effluents, not breathing air)

NOTE: The se lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the significance level assigned to the condition, the status of the action (e.g., open, working, closed, etc.)

and the search criteria used. Please provide in document formats which are "sortable" and "searchable" so that inspector

s can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. Annual Radioactive Effluent Release Reports for the latest two calendar years

I. Current revision of the Offsite Dose Calculation Manual

(or other name, but include all parts for effluents) and any changes made since the last inspection.

J. The inter-laboratory comparison results for laboratory quality control performance of effluent sample analysis

for the latest two calendar years

K. Effluent sampling schedule for the week of the inspection

L. Provide the last three annual trends of vent/stack effluent flow rates, by chart or table.

M. Operations department

(or other responsible dept.) log records for effluent monitors removed from service or out of service

or a list of the same and compensatory actions taken during the out of service condition.

N. List ing or log of liquid and gaseous release permits since the date of the last inspection

O. A list of the technical specification

-required air cleaning systems with the two most recent surveillance test dates of in

-place filter testing (of HEPA filters and charcoal adsorbers) and laboratory testing (of charcoal efficiency) and the work order numbers associated with the surveillances

(and their system number/name).

P. System Health Report for radiation monitoring instrumentation. Also, please provide a specific list of all effluent radiation monitors that were considered inoperable for 7 days or more since the date of the last inspection

. If applicable, please provide the relative Special Report and condition report(s).

If not covered by maintenance rule, please provide rationale.

Q. A list of significant changes made to the

gaseous and

liquid effluent process monitoring

system since

the date of the last inspection

. If applicable, please provide the corresponding UFSAR section in which this change was documented.

R. A list of any occurrence in which a non

-radioactive system was contaminated by a radioactive system

since the date of the

last inspection

. Please include any relevant condition report(s).

S. Current Part 61 analyses for hard to detect radionuclides

T. Latest Land Use Census (coordinate with 71124.07)

U. Effluent based procedures for EALs or EOPs.

7. Radiological Environmental Monitoring Program (71124.07)

Date of Last Inspection:

February 27, 2017

A. List of contacts and telephone numbers for the following areas. Please include area code and prefix. If work cell numbers are appropriate, then please include them as we

ll. 1. Radiological environmental monitoring

(RP, Chemistry, I&C, etc.)

2. Meteorological monitoring

(RP, Chemistry, EP, I&C, System Engineering, etc.)

3. Maintenance and calibration of the above equipment

4. Licensing/Regulatory Affairs

B. Applicable organization charts including position or job titles. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, self

-assessments, vendor or NUPIC audits of contractor support, and LERs written since the date of the last inspection , related to:

1. Radiological environmental monitoring program (including contractor environmental laboratory audits, if used to perform environmental program functions) 2. Environmental TLD processing facility

3. Meteorological monitoring program

D. Procedure index for the following areas

and other related disciplines.

1. Radiological environmental monitoring program

2. Meteorological monitoring program

3. Maintenance and calibration of related instrumentation, including the meteorological tower

E. Please provide specific procedures related to the following areas

noted below. Additional

procedures may be requested by number

after the inspector reviews the procedure indexes. 1. Sampling, collection and preparation of environmental samples

2. Sample analysis (if performed onsite) 3. Laboratory instrumentation quality control

4. Meteorological Tower sensor calibrations

F. Please provide a list of NRC Regulatory Guides and NUREGs that you are currently committed to relative to this program. Please include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a

summary list of corrective action documents (including corporate and sub-tiered systems) written since the date of the last inspection , related to the following programs: 1. Radiological environmental monitoring

(include TLDs and air sample pumps or their infrastructure)

2. Meteorological monitoring

(include Met Tower sensors and support equipment)

These lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the

significance level assigned to the condition, the status of the action (e.g., open, working, closed, etc.) and the search criteria used. Please provide in document formats which are "sortable" and "searchable" so that inspectors can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. Copies of the two

most recent calibration packages for the meteorological tower instruments

I. Copies of the Annual Radiological Environmental Operating Report

s and Land Use Census for the latest two calendar years, and current revision of the Offsite Dose Calculation Manual. Please include any supportive

documentation for the changes made to the ODCM since the last inspection.

J. Copy of the environmental laboratory

's inter-laboratory comparison program results for the latest two calendar years

, if not included in the Annual Radiological Environmental Operating Report K. Data from the environmental laboratory documenting the analytical detection sensitivities for the various environmental sample media (i

.e., air, water, soil, vegetation, and milk)

L. Quality Assurance audits (e.g.

, NUPIC) for contracted

services

M. Current NEI Groundwater Protection Initiative (GPI) Plan and status. Provide the most recent monitoring results for each monitoring well per the GPI. Provide a separate list of any missed samples, as applicable.

N. Technical requirements manual or licensee controlled specifications which list the meteorological instruments

' calibration requirements

O. If applicable, per NEI 07

-07, provide any reports that document any spills/leaks to groundwater since the date of the last inspection. Please indicate what external communications were made regarding each spill/leak.

P. Provide any new entries into 10 CFR 50.75(g) files since

the date of the last inspection.

Q. Please identify your three highest X/Q (chi/Q) and/or D/Q sectors, as currently used in the selection of your required REMP sampling locations. If these are different values from your most recent meteorological assessment, please provide that assessment and indicate the three highest X/Q and/or D/Q sectors per your latest assessment. Also indicate your noted predominant

and least prevalent

wind direction/sector, as used in your REMP analysis.

R. Provide the height of the highest effluent release point. Please indicate if the height accounts for plant grade elevation. Please also provide the most probable

atmospheric release height, if different

from the highest effluent release point.

S. Please provide a schedule of any planned REMP sampling activities while we, the NRC, are scheduled to be onsite performing this inspection.

8. Radioactive Solid Waste Processing, and Radioactive Material Handling, Storage, and Transportation (71124.08)

Date of Last Inspection:

February 27, 2017

A. List of contacts and telephone numbers for the following areas. Please include area code and prefix. If work cell numbers are appropriate, then please include them as well.

1. Solid Radioactive waste processing

(RP, Chemistry, Ops, Maintenance, I&C, Engineering, etc.)

2. Transportation of radioactive material/waste

(RP, Maintenance, Ops, Security, Chemistry, etc.)

3. personnel involved in solid radwaste processing, transferring, and transportation of radioactive waste/materials)

4. Licensing/Regulatory Affairs

B. Applicable organization charts including position or job titles. Please include as appropriate for your site, Site Management, RP, Chemistry, Maintenance (I&C), Engineering, and Emergency Protection. (Recent pictures are appreciated.)

C. Copies of audits, department self

-assessments, and LERs written since the date of the last inspection, related to:

1. Solid radioactive waste management

2. Radioactive material/waste transportation program

D. Procedure index for the following areas

and other related disciplines.

1. Solid radioactive waste management

2. Radioactive material/waste transportation

E. Please provide specific procedures related to the following areas

noted below. Additional

procedures may be requested by number

after the inspector reviews the procedure indexes.

1. Process control program

and any changes made since the last inspection

2. Solid and liquid radioactive waste processing

3. Waste stream sampling and analysis

4. Waste characterization and classification

5. Radioactive material/waste packaging & shipping F. Please provide a list of NRC Regulatory Guides and NUREGs that you are currently committed to relative to this program. Please include the revision and/or date for the commitment and where this may be located in your current licensing basis documents.

G. Please provide a

summary list of corrective action documents (including corporate and sub-tiered systems) written since the date of the last inspection, related to:

1. Solid radioactive waste

2. Transportation of radioactive material/waste

NOTE: These lists should include a description of the condition that provides sufficient detail that the inspectors can ascertain the regulatory impact, the significance level

assigned to the condition, the status of the action (e.g., open, working, closed, etc.) and the search criteria used. Please provide in document formats which are "sortable" and "searchable" so that inspectors can quickly and efficiently determine appropriate sampling and perform word searches, as needed. (Excel spreadsheets are the preferred format.) If codes are used, please provide a legend for each column where a code is used.

H. Copies of training lesson plans for 49

CFR 172 , Subpart H, for radwaste processing, packaging, and shipping

I. Provide a summary list or log of radioactive material and radioactive waste shipments for the two most recent calendar years, in addition to the current calendar year.

J. Please provide at least two different radioactive waste stream sample analys

is results and resulting scaling factors for the latest two calendar years.

K. A listing of all onsite radwaste storage facilities. Please include a summary or list of the items stored in each facility

with the most recent dose rates/surveys.

L. A list of any significant (e.g., DAW, resins, Type B or greater) radioactive shipments that will be completed during our onsite inspection period. If available, please provide the applicable shipping manifests/waste characterizations and most recent surveys for each shipment. M. A list of significant changes made to the liquid or solid radwaste processing systems

since the date of the last inspection

. If applicable, please provide the corresponding UFSAR section in which this change was documented.

Provide any supportive documentation for the changes made or have it

readily available for review.

N. List of radioactive waste processing systems or equipment abandoned in place since the last inspection.

O. Please provide a schedule of radioactive material or waste processing or shipment activities during the inspection

week. Please indicate the current storage location of the stored RAM or waste prepared for shipment, as well as any supportive surveys of its measured dose rates. If available, please indicate its current stated waste class.